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ACCESSION, NBR: 7910250)33 DOC ~ DATE: 79/10/22'OTARIZED j NOFACIL:50 335 St, Lucia Planti Unit li Flor ida Power L Light Co.

AUTH~ NAMg AUTHOR AFFILIATIONUHRIgiR ~ ED Florida Power 8 Light Co ~

R E C I P y hf AME!, R E C I P I E N T A F F ILIAT I0 NEISENHUT'iD.G. Division of Operating Reactors

DOCKET05000335

SUBJECTS )or wards response to NRC 790913 .l tr ry fol 1owup actionsr esul ting f rom NRC review of TMI '.Requir ements. r e emer gencyoperations ctr unsufficiently defined to designatededicated primary L alternate locations.

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FLORIDA POWER 5 LIGHTCOMPANY

October 22, 1979L-79-292

Office of Nuclear Reactor RegulationAttention: MT. Darrell G. Eisenhut, -Acting Director

Division of Operating ReactorsU. S. Nuclear Regulatory CommissionWashington, D. C. 20555

Dear Mr. Eisenhut:

Re: .St. Lucie Unit 1

Docket No. 50-335NUREG-0578

We have r'eviewed your letter of September 13, 1979 regarding the followupactions resulting from NRC staff review of the TMI-2 event, and our responsefor St. Lucie Unit 1 is attached. While we are attempting to meet thestaff's proposed schedule, this will not be possible in every instance.We believe that the commitments made in our response represent a realisticand reasonable schedule.

Very tr y ours,

obert E. UhrigVice PresidentAdvanced Systems 8 Technology

REU/MAS/cph

Attachment

cc: Mr. James P. O'Rei lly, Region IIHarold F. Reis, Esquire v

$0 ~Pp )pQ,

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PEOPLE... SERVING PEOPLE

ATTACHMENT

2.1.1 EMERGENCY POWER SOURCES

2.1.2

The pressurizer heaters are fed from the 480 volt pressurizer heaterbusses 1A3 and 1B3 with one-half of the backup heaters and one-halfof the proportional heaters on each bus. Following diesel start andload sequencing, the two pressurizer heater busses can be manuallyloaded onto the 4.16 KV emergency diesel busses lA3 and 1B3respectively via the closure of class 1E circuit breakers. Power tothe two power operated relief valves (PORV) is supplied from the 125VDC lA and 1B battery busses. The blocking valves (2) are poweredfrom 480 VAC vital busses 1A5 and 1B5 respectively.and areautomatically reloaded onto the 1A5 and 1B5 busses as part of thediesel loading automatic sequenci ng. Pressurizer level i nstrumentsLT-1110X and LT-1110Y are powered from vital busses 1A6 and 1B6 (viapower panels PP-101 and PP-102) which upon loss of power are alsoautomatically sequenced onto the diesel generators. In view of theabove, St- Lucie Unit 1 is considered to be in compliance with theintent of Recommendation 2. 1. 1.

RELIEF AND SAFETY VALVE TESTING

A program for testing power operated relief valves and safety valvesused for pr'imary system pressure control under design basis operatingconditions is being developed by the C-E Owners Group. This programincludes definition of test conditions and qualification requirementsfor all specified valves in operating reactors designed by CombustionEngineering (C-E). The results of this program will be madeavailable to the generic efforts being undertaken by the industry(through for example the Electric Power Research Institute, EPRI, andthe Nuclear Safety Analysis Center, NSAC) no later than January 1,1980. These results will also be available for discussions with theNRC Staff to establish generic resolutions no later than Ja'nuary 1,1980. St. Lucie Unit 1 will comply with the schedule for completionof the test program which is agreed to during these genericresol utions meet i ngs.

2.1.3.a DIRECT INDICATION OF VALVE POSITION

St. Lucie Unit 1 will comply with the intent of recommendation2.1.3.a. We currently intend, pending final design review, toinstal„l acoustic-type (accelerometer) flow monitors on eachpressurizer code safety and power operated relief valve and arecurrently evaluating vendor proposals. The final design will besubmitted for implementation review by January 1,,1980. Should othermethods'or indication become available, consideration will be givento such designs.

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2.1.3.b INSTRUMENTATION FOR INADE UATE CORE COOLING

St. Lucie Unit 1 is proceeding with the purchase of a SubcoolingMeter for installation in the control room. The meter willcontinuously display the margin to saturation in units of eithertemperature or pressure through the use of a selector switch. Avendor has been selected and advised of our decision in order toexpedite delivery in parallel with the processing of documentsrequired for the purchase of the equipment.

The procedures to be used by an operator to recognize inadequate corecooling will be developed based on analyses being performed asrequired by Item 2.1.9, Transient 8 Accident Analysis, Analysis ofInadequate Core Cooling. The guidelines for the procedures are beingdeveloped by the C-E Owners Group and will be available fordiscussions with the NRC Staff to establish generic resolutions nolater than January 1, 1980.

Both the need for and feasibility of reactor vessel water levelinstruments are being evaluated by the C-E Owners Group. Thefunctional requirements and a conceptual design for a reactor'essellevel measurement device are being developed as part of thiseffort. A survey of currently available technology and assessment ofthe feasibility of various alternatives will be included in theoverall evaluation. If requi red as a result of the genericresolutions di scussions with the NRC Staff, the functionalrequi rements and conceptual design will be submitted for proposalreview by the NRC Staff prior to implementation. The installationschedule for such a device, should it be deemed necessary, will beestablished during the Proposal Review.

2.1.4 DIVERSE CONTAINMENT ISOLATION

The original plant design provides for containment isolation on thereceipt of either a high containment pressure signal or a highcontainment radiation signal. Additionally,'he design has beenchanged to add the Safety Injection Actuation Signal (SIAS) as aninput'to the containment isolation circuitry (CIAS). Receipt of SIASwill now automatically initiate containment isolation. Neither SIASnor CIAS can be reset while an initiating signal is present, andresetting of either SIAS or CIAS will not result in the reopening ofany valves. Therefore St. Lucie Unit 1 complies with the intent ofrecommendation 2.1.4.

2.1.5.a DEDICATED PENETRATIONS FOR EXTERNAL HYDROGEN RECOMBINERS

St. Lucie Unit 1 is equipped with 2 hydrogen recombiners locatedwithin the containment. This recommendation is therefore nota ppl icab 1 e.

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2.1.5.c HYDROGEN RECOMBINER OPERATING PROCEDURES

A detailed review of the existing bases and procedures for reccmbineruse at St. Lucie Unit 1 has been conducted in response to NUREG-0578and other NRC documents. Our review has concluded that no changesare necessary at this time, and that St. Lucie Unit 1 complies withthe intent of this item.

2. 1.6. a SYSTEMS INTEGRITY FOR'HI GH RADIOACTIVITY

FP&L is currently developing a program which will identify leaks insystems outside containment that could possibly contain highlyradioactive fluids during a serious transient or accident. Theprogram will identify applicable systems, develop procedures, andestablish inspection frequenci es and acceptance criteria. Ourpreliminary evaluations i ndicate that applying thi s program togaseous systems will be considerably more difficult than to theliquid systems, however, our intent is to complete the short termleakage reduction program during the unit's 1980 refueling outage.

2.1. 6.b PLANT SHIELDING REVIEW

2.1.7.a

Ebasco is reviewing the St. Lucie Unit 1 plant design to identifylocations where additonal shielding may be required in'order toconduct post-accident operations. This revi ew is schedul ed forcompletion prior to January 1, 1980.'ose calculations affectingpersonnel access and sensitive equipment will be completed by July 1,1980. Any additional shielding which may be required as a result ofthese reviews will be installed on a schedule which will be submittedfollowing the completion of the reviews.

AUTO INITIATON OF AUXILIARY FEED

A Plant Change/Modification (PCM) has been engineered which providesfor automatic starting of all three auxiliary feedwater pumpsinstalled at St. Lucie Unit 1. This PCM provides for safety-gradesystem which allows use of the steam generator low level trip toinitiate the pump start. Initial investigations into equipmentprocurement i ndicate that delivery schedules for qualified componentsmay severely, delay implementation of the PCM. Additionally, the PCM,which was generated as a result of commitments made in response to IEBulletin 79-06b, does not incorporate the automatic opening of theAFW pump flow control valves. Engineering efforts to resolve thismatter are in progress, but may prove extensive due to potentialrequirements for complex circuitry and/or new safety analysesrelative to postulated accidents such as main steam line break andthe reactivity restart analyses. It is anticipated that suchanalyses would be performed on a generic basis through the C-E Owners'Group. We expect that the complete safety-grade system could beinstalled and operational prior to returning to power operationfollowing the scheduled 1981 refueling outage. The concept of adedicated operator such as is currently in effect at St. Luci e Unit 1

is considered to be an adequate interim measure.

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2.1.7.b AUXILIARY FEED FLOW INDICATION

The St. Lucie Unit 1 design incorporates safety-grade auxiliaryfeedwater flow indication in the control room which currently meetsthe intent of this recommendation.

2-1.8.a POST ACCIDENT SAMPLING

In conjunction with Section 2. 1.6.b above, a design revi ew is inprogress to identify areas where the post-accident samplingcapability can be improved. This review is scheduled for completionby January 1, 1980. Additionally, plant procedures are undergoi ng adetailed review in order to accompli sh the same end including theminimization of personnel exposure. Procedure revisions arescheduled for completion by July 1, 1980. If plant modifications arerequired, a description of arly such modifications and a schedule forimplementation will be submitted to the NRC.

If the radiological spectral analysis cannot be performed in a promptmanner with existing equi pment, design modifications, equipmentprocurement, or contractural arrangement will be undertaken toaccompli sh a spectral analysis. The two hour time restriction isconsidered to be neither practical nor critically essential. Itshould be noted that we anticipate complex and potentiallyinsurmountable difficulties in complying with the requirementsregarding chlorine and boron analyses. Our'nvestigations indicatethat a highly-radioactive chloride and boron analysis'ould not beperformed on-site. A contractural arrangement is being investigatedalong with on-line boron-monitoring capabilities. Following theresolution of these specific requirements, an implementation schedule-will be submitted to the NRC.

2.1.8.b HIGH RANGE RADIATION MONITORS

Florida Power 8 Light is proceeding to design, procure and installnoble gas monitors in plant effluent lines and high range containmentradiation monitors. We anticipate that installation of this systemcan be accomplished during or prior to the unit's schedul-ed 1981refueling outage.

2.1.8.c IMPROVED IN-PLANT IODINE INSTRUMENTATION

2.1.9

„In view of the lead time involved in obtaining the equipmentnecessary to comply with this requirement, as well as the time neededto engineer and install the modification, we estimate that we will beunable to meet implementation schedule date of January 1, 1980. FPSLwill, however, make every effort to acccmplish the installation ofthis system at the earliest date practical.

TRANSIENT AND ACCIDENT ANALYSIS

The response to Transient and Accident Analysis requirements is beingdeveloped by the C-E Owners Group in conjunction with genericresolution meetings with the NRC Bulletins and Orders Task Force.

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These responses will be submitted on the schedule agreed to by thattask force and the C-E Owners Group and will be referenced forspecific application to St. Lucie Unit 1.

CONTAINMENT PRESSURE MONITOR

A system for the monitoring of St. Lucie Unit 1 containment pressureis currently in the design stage. Installation of the completesystem is scheduled for completion prior to returning to poweroperation following the unit's scheduled 1981 refueling outage.

CONTAINMENT WATER LEVEL MONITOR

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A system for the monitoring of St. Lucie Unit 1 containment waterlevel is currently in the design stage.. Installation of the completesystem is scheduled for completion prior to returning to poweroperation following the unit's scheduled 1981 refueling outage.

CONTAINMENT HYDROGEN MONITOR

A system for the monitoring of St. Luci e Unit 1 containment hydrogenconcentration is currently in the design stage. Installation of thecomplete system is scheduled for completion prior to returnin'g topower operation following the unit's scheduled-= 1981 refueling outage.

RCS VENTING

2.2.1.a

The functional requirements and conceptual design of a system forremote venting of the RCS are being developed by both the C-E OwnersGroup and our Architect-Engineer (Ebasco, Inc.). These requirementsand a conceptual design will be available for discussions with theNRC Staff to establish generic resolutions no later than January 1,1980. A decision concerning installation of an RCS venting system inSt. Lucie Unit 1 will be made following completion of the genericresolution meetings.

SHIFT SUPERVISOR RESPONSIBILITIES

Plant procedures and practices in this area are undergoing review toensure that reactor operations command and control'esponsibilitiesand authority are properly defined. Procedure revisions or otherchanges required as a result of this revieii will be incorporated byJanuary 1,'980. An operational policy directive specifying theduties, responsibilities, authority and lines of command covering thecontrol room operators, the shift technical advisor and the shiftsupervisor will be issued by FPEL's corporate management by January1, 1980.

2.2.1.b SHIFT TECHNICAL ADVISOR

FPEL will establish technical advisors, either on call or on eachshift; during'eriods when St. Lucie Unit 1 is operating in Modes 1

through 4 as defined in the Technical Specifications. '

minimum of 2qualified individuals would be on call at all times and would be

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capable of responding within 45 minutes. Each individual on callwill be supplied with two-way radios to enable communications withthe plant. Coverage will commence on January 1, 1980. The technicaladvisor's primary function will be one of assessment and diagnosis

'uringaccidents or abnormal transients. He may be assigned othercollateral duties that will not interfere with his primaryfunction. Training of technical advisors is scheduled to becompleted by January 1, 1981, but this schedule may be impacted bythe availability of simulator training time. At such time that theman-machine interface is improved as a result of such activities asimproved control room design and/or operator qualification, FPEL mayelect'to designate a qualified member of the operating shift toperform the accident/transient function. Operational experienceevaluation and assessment may be performed by the technical advisoror other functional organizations either onsite or at FP8L's GeneralOffice.

SHIFT TURNOVER PROCEDURES

An existing plant procedure e is being revised to incorporate a shiftturnover checklist for shift supervisors. This revised procedurewill become effective no later than January 1, 1980. The need toextend this checklist concept to other operations, technical, and/ormaintenance personnel is being evaluated.

2.2.2a CONTROL ROOM ACCESS

An existing plant procedure is being revised to limit control roomaccess consistent with the recommendations of NUREG-0578. Therevised procedure will become effective no later than January 1,1980.

2.2.2.b ONSITE TECHNICAL SUPPORT CENTER

2.2.2.c

St. Lucie Unit 1 has designated the training classroan area (formerlythe Unit 2 control room located adjacent to the Unit 1 control room)as the onsite Technical Support Center. Control room communicationsand as-built drawings for Unit 1 will be available in the TechnicalSupport Center by January 1,, 1980. Specific instrumentation,additional communication, and data requirements are undergoingevaluation with the intent to begi n installation of selectedequi pment by January;1, 1980. An overall scope and implementationschedule will also be submitted at this time.

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ONSITE OPERATIONAL SUPPORT CENTER

St. Lucie Unit 1 has designated the first floor maintenance area ofthe service building as the on-site Operational Support Center.Communications equipment to and from the control room presentlyexists in this area- The Emergency Plan will be revised to reflectthe existence of this center and to establish the methods and linesof communication and management by January 1, 1980.

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Encl. 8 NEAR TERM EMERGENCY PREPAREDNESS IMPROVEMENTS

Florida Power 5 Light is in general agreement with the requiredimprovements contained in Enclosure 8 to your September 13, 1979letter.'e believe we can implement these improvements consistentwith the NRC schedule with the exceptions noted in Section 2. 1.8 inaddition to three other areas of concern as discussed in thefollowing paragraphs.

Each of our sites has, in the past, routinely conducted site testexercises in conjunction with local, State, and Federal officials onan annual basis. The 1980 tests are scheduled to be conducted duringAugust/September. As the improvements to the emergency plan are notscheduled for completion until June, 1980, we believe the presenttest exercise schedule is reasonable and can commit to meeting thisrequirement by October 1, 1980.

Regarding the upgrading of the emergency plans, we agree in principlewith the recommendation to upgrade to Regulatory Guide 1.101.However we cannot at this time ccmmit to the action level criteria ascontained and described in that document and in NUREG-0610, DRAFT

EMERGENCY ACTION LEVEL GUIDELINES FOR NUCLEAR POWER. We requirea stlona time to review the draft criteria. e elieve we canforward our position on this item to the NRC by January 1, 1980.

With respect to the Emergency Operations Center, we believe thatspecific requirements are not sufficiently defined to enable FP8L todesignate dedicated primary and alternate locations at this time.Considering the level of construction underway on Unit 2 we believethat more than adequate space would be available if required. Oncethe criteria are firm, we will provide the NRC with primary andalternate locations and a schedule for implementation of upgo'dingrequi rements.

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STATE OP PLORXDA ))

COUNTY OP DADE )ss.

E. A. AQomat , being first Quly sworn, deposes anQ says=

That he is Executive Vic . Pgc.Light Company, the Licensee herein'

of .Florida Power 5

That he has executeQ the foregoing document; that the state-ments made in this saiQ document are true and correct'o thebest of his knowledge, information, and belief:, and that he isauthorized to execute the document on behalf of said Licensee

H. A. Adomat

Subscribed anQ sworn to before me this

day of

Coun y of Dade,1

-~'O'L"/>'thRr p~ ~pyy ~ rLORlOA Sl ps'

MAYH><

Ply commission expires:

Ej /fE'/

NOTAR P .BLXC, in and or thState of Florida

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