tiEroHANOUI! FOR:

Ju 1 y l t. , 1 Q(jil

liRC/Hii-o4 - ll53

llarold R. Denton , [Jircct<•r Orfice of ~uct ea r Rcdc tor R~qul a tion

Bi!rrldrd J. S"njdet·, Program Director Till Progra~ urfice

FRG!1: Philip J . Grant, 1\cting Oi!puty Proqr;u,, llirt>ctor Ttl l Program Office

SU3JECT: llRC Till PROGRNI Offll.E ilEEKL Y STATUS REPORT FOR July 8 , 1984 - J uly 14, 19S4

Ddt.: f r cn t:tr luC'r.t and envlronro<'nt;~l monlt, ri ng systems indlcatPd no :d 1nt re l ec1se 1r1 PXC~JS~ ot rcgul.t t ory li r.ti t s. Has t -: prucessin9 ·11\d shipll)~nts continued on a r outine ba!>i!.. Pl ant paru~ters shO'•I'"'d no significant changes. Th~ r cilctor coolJnt SfSleM 1s depressuri zed and redctor coolant systc11 level is apprcxima t elj 321 ' 6".

Sit~: activi .. t es this period i nc luded: reactor bui !ding t:r. tri cs in support ol t c>chnicul specificat lon r·cquirenents ,1nd hedd lift preparations; auxiliary .Jnd f u~ l handi i ng I.Jui !ding dtcontilmindtion ; "A" spent tue l rcfut·bishraent; purif!cat i on lf(:rlincr.;l i lt:r r lutll'n cquipr.lt'nt installatior.; .1nd procedure .-eview. {For mot'\! t!L td i 1 s scr· ,1pprr-priatE: parilgrt~phs be: lvw.)

SlQ!lifi ccJn t ltP.r.Js CI)Vered in tht enclosure arc:

Hcdct or Buildt ny Activities Auxiliary and Fu~ l Handling Buildwg Act iviti es Wa s te ~-'~1nilgt'mcn t Pub 1 i c ll\'L t 1 ng s

Oil td • ur• .lc~ ~'Y sheets 1ncluded lu th1s rcpon ar e:

Liqu1 d Effluent Data En•1 i ronmenta 1 Oa ta ;{ad ioactivc llater tal/Radwaste Shipn~en t Oatil PlcJnt Status Uatu

ORIGlllAL SIGr:EO BY:

Philip J. Grilnt 8407240416 840716 PDR ADOCK 05~00320 R PDR Acting Ocpuly Progr~m Director

Till Prog ram Office

Enc 1 osure : As s t.l t ed

. ~ I OFFICIAL RECORD COPY

t. . .......... J. . . . .. .. . I .

. .... .. l ... _1 . . 1_

INTERIIAL OISTRIBUTIOU EOO OGC Office Directors Conmissioner's Technical Assistants iiRR Division Directors rmR AID's Regional Administrutors IE Division Directors TI\S EIS TN! Progr·am Office Staff (15) PHS EPA DOE Rl Division Directors Public Affairs, Rl Stat~ Liaison, ~I TI-IIPO HQ r/f TIH SITE t•/f CEiiTRAL FILE NRC PDR LOCAL PDR Tlll-2 ProJeCt

Section File

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IIIRCFORM316(10801NRCM0,40 OFFICIAL RECORD COPY

~!:CLOSURE

REACTOR BUILDING ACT IVITIES:

Reactor 'essel heao lift preparat1ons are ~cheduled to he completco curing the ~ee~ of J~ ty 15, 195~. it is ant1c1pated tnat the head i 1ft schedule wi ll be accelerateo i!S a result of :he early co~plet ;on of the head i Ht preparatory activities. read litt has been targeted ror early August. rOWe\er, penoing comp iet1 or of all rema ining supporting act1 vi ties, the head lift could be performed in late July.

One of the final pre-head l1ft activities will be the "parking" of.the cont rol rod drive lead screws. Pr1or to nead lift, the leao screws must be ra1sed (par~ed ) tc the tcp of the service structu~e above the reactor vessel heao. In the "parked" position, the botto~ ti ps of the 22 f t. long lead screws will clear tne reactor vessel head fla nge. The reactor vessel head and service structure will be lifted as a unit and transferred t o :he head storage stand on the 347 ft. elevation of the reactor building. Lead shi~loing blankets have been hung around the perimeter of the service structure to minimize the exoected radiation level increase when the lead screws are in the "parked" position.

Dose rates in restricted areas of t he reactor building are predicted to increase to several R/hr ouring tht head transfer. Fiberglass water shields, about 12 feet tall, have been installed around the head ~toraoe stand on the 347 ft. elevation as shielding. These, in conjunction with the lead shielding already installed on the service structure are expected to lower the radiation levels around the head on the storage stand to pre-head lift levels. New load tested rigging for the head lift ha~ been mounted on the reactor vessel head to replace rigging which has been in the reactor building.

The Internals Indexing Fi xture (IIF ) will be installed over the open reactor vessel soon after head lift. With the IIF in place, reactor coolant level will be raised and a lead shielded ~latform cover emplaced. It is expected that radiation levels wil l be reduced to prP-head lift levels.

The senior resident i nspector and a radiation specialist from the TMIPO will make a backshift entry to the reactor building on July 18, 1984 to independently determ1ne the aoequa cy of head lift preparatior.s. They will inspect welding and mecnanical prep~~a:ions and will independent ly measure radiation levels, obtain airoorne radioactivlty sampl es, and evaluate the suitability of the licensee's radiJtion surveys.

TM!PO 1s nearing cor.pletion of its review of the head lift safety evaluation report and technical specifi cation modificau ons to permit head lift. I~RC appro·val is required prior to head lift.

AUXIL!hRY AIIO FUEL HAIIDLirlG BUILDWG ACTIVITIES:

Installation of shielding around lines associated with the makeup and purification demineralizer elution system continued this week. TMI Program Office staff will require review and approval of the licensee's safety evaluation report (SEP) and . operating procedures prior to implementation.

Work cont inued on the "A" spent fuel pocl refurbishment in the fuel handling building. Decontamination efforts in the auxiliary building included low pressure water spray in the makeup pump. cubicles and the reactor coolant bleed tank room.

2

n'ASTE r.:;..•,AGEI·i£1,T tei!VIi!ES:

The sub~ergeo der.in~rali:er system (SDS, begcn process1ng about 40,000 oallons of ~·aste 1:ater directly from t he reactor bui ldin9 suno (batch 98) or. July i2, 1984. The su~p ~cter conta~ ns approxim~tel y 10 uCitcc of Cs-137.

SDS processed batch 97 from the "A" monitor :an~ on July 6-7, 1984. Thi:.. batch consisted of the reprocess i n~ of batch 96, which was terminated when high Sr-'0 concentratl ons were detected in the SDS effluent. Batch 97 processed a total water volume of 7,773 gallons.

SDS will continue processing decontamina tion water from the lower tank farm in the "A" fuel pool. The water has been generated as a result of the ongoing decontamination of the two 25,000 gallon tanks in the lower tank farm.

EPICOR II processed batch 216 from the "B" monitor tank on July 7-8, 1984. Total volume processed was 7,786 gallons.

PUBLIC MEETI~GS:

1. On July 12, 1984, Phil Grant met with Mayor Robert Reid of Middletown tc discuss head lift activities.

2. On July 12, :9~4. the Advisory Panel for the Decontamination of Three Mile Island Unit 2 held a meeting in Harrisburg, Pennsylvania . Or. W. Kirk, Director TMl Field Station, U.S. Environmental Protection Agency (EPA) reported on the results of the interagency TMl-2 radiological monitoring progr~m review. The radiolog ical monitoring programs conducted by the NRC, the Commonwealth of Pennsylvania and the licensee will remain essentially unchanged. The EPA monitoring program will incorpordte new sample methodology in a number of sampling programs. The changes will in many cases incr~ase the theoretical detection limits of the sampling. The Advisory Panel was asked by Or. Kirk to review the proposed changes and provide comments to EP~. by the middle of August 1984.

J. Devine, T~II-2 Recovery Technical Planning Director, GPUilC , provided a discus$ion on the licensee's continuing efforts to define the endpoint in the cleanup effort. The licensee's goal at TM l -2 is to eliminate any radiati on release carability and place the facility in a fully stable and secure condition so that a decision can be made as to the disposition of the facility. According to Mr. Devine, options under consideration are refurbishment, dismantling and interim safe storage.

E. Kintner, Executive Vice President, GPUNC, provided an update on TNI-2 cleanup funding levels. Anticipated funding fo r calendar year 1985 is $120 mi llion. Mr. Kintner expressed optimism that the Sl billion required for the cleanup is "within striking distance."

E. Kearney, Senior Vice President of the Edision Electric Institute (EEl) sunmarized EEl's efforts to date to secure voluntary contribution for the cleanup effort from its members which are investor owned utility companies. Hr . Kearney stated that recent actions on the part of EEl will make $25 million a year available to GPUNC for cleanup of TMI-2 beginning in 1985.

At the conclusion of the meeting, the Panel received comments and statements from members of the public.

APPEI:OIX 1

llQUlD EFFLUENT DATA

GPU Nuclear

Based on sampling and monitoring, liquid effluents from the TMI site released to the Susquehanna River were determined to be within regulatory limits and in accordance with NRC r~quirem~nts arid the City of lancaster Agreement.

During the period July 6 thr~~gh July 12, 1984, the effluents contained no detectable radioactivity at the discharge point. Individual effluent sources originating within Unit 2 contained minute amounts of radioactivity. Calculations indicate that less than 1.9 E-7 (0.00000019) of a curie of Cs-137 and less than 3.4 E-7 (0.00000036) of a curie of gross beta activity was discharged.

Environmental Protection Aaency

Lancaster Water Samples: 7 samples

Period Covered: June 24 - 30' 1984

Results: Ga11111a Scan Negative

TI1,I Water Samples: 7 samples

Period Covered: June 23 - 30, 1984

Results: Gammo Scan llegative

Ell\'IROia·lEI.lAL DATI.

ihe l~i<C c.peroted continuous outdoor air sampler at the THI site did not detect any reactor related radioacti\ity. The air sampler analysis results are listtd below.

Sample Period Volume

July 5- July 11, 1984 219.3 m3

1-131 (uCi/cc)

<1 .6 E-13

Cs-137 (ufi/cc)

<-1.6 E-13

APPEr:OI> 3

RAOIO~CT!VE MATERIALS/ RAOWASTE SHIPMENT ~~TA

On July 11, 1984, a combined Unit 1 and 2 shi p~ent of radioactively contarninat~:d launory was sent to Interstate • clear Service, Royersford, Pennsylvania.

On July 12, 1984, a Unit 1 sample was sent to Teledyne Isotopes, Westwood, r.ew Jersey.

APPEr;OIX t.

PLt.riT STATUS

Core Cooling Mode: Heat transfer fror the re ~ ctor coolant system (RCS ) to reactor buildi ng a"'bient

Available Core Cooling/ Makeup Sources: Standby pressure control (SPC) system Reactor coola~t bleed tan~ (RCBT) water transfer system Mini oecay heat removal (MOHR ) system

Major Parameters as of 5:00AM, July 13, 1984 (approximate values):

Reactor Coolant System:

Loop Temperatures:

Cold Leg (1) (2)

Pressure: Open to reactor building atmosphere

Reactor Core:

Average Jncore Thermocouples•: Maximum Jncore Thermocouple•: Decay Heat:

Reactor Building: Temperature: Pressure:

98°F 145"F 16.5 kilowatts

Airborne Radionuclide Concentrations:

Tritium: 1.5 E-9 uCi/cc H3 (sample 7/9/84) Particulates: 5.8 E-9 uCi/cc (sample 7/6/84)

predominately Cs-137

. .

~uncertainties exist as to the exact location and accuracy of these readings. •*Since the RCS is drained down below these temperature detectors, they no

longer are indicative of RCS temperatures.