mr. james g. keppler

| 0,

Northern States Power Company~9

e J_ 414 Nicollet Mall D. E. GilbertsMinneapohs. Minnesota 55401 senior vice Presidentlelephone (612) 330-6071 Power Supply

January 22. 1981.

Mr. James G. KepplerDirector, Region IIIOffice of Inspection and Er.forcementU. S. Nuclear Regulatory Commission799 Roosevelt Road ,, g ) 4 % /

DGlen Ellyn, IL 60137 Ny.-n s' iDear Mr. Keppler:

Gk. #'?>' Y.'f; V~

pqG NPRAIRIE ISLAND NUCLEAR GENERATING PLAhT | II~

gjDocket Nos. 50-282 and 50-306

References: S

1. NSP Letter to Mr. J. G. Keppler, NRC Region III, October 31, 19 - / * |. #2. NRC Office of Inspection and Enforcement; IE Supplement No. 3 to

Bulletin No. 79-OlB, October 24, 19803. NSP Letter to Director of Nuclear Reactor Regulation on January 1, 1980

Lessons Learned Implementation, March 13, 1980

IE Supplement No. 3 to Bulletin No. 79-OlB required submit'.al of qualificationinformation for equipment resulting from TMI Action Plan requirements andequipment which is required to achieve cold shutdown.

Qualification Information for Installed TMI Action Plan Equipment

Safety grade subcooling margin monitors have been installed in Unit 1 and 2.

The temperature input is derived from multiple core exit thermocouples andthe pressure input is derived from Reactor Coolant System (RCS) wide rangepressure. Outstanding items concerning qualification of the temperature andpressure inputs have been previously addressed in Reference 1.

Until the inputs to the subcooling monitors have been upgraded, the P-250plant computer has been programmed to accept the best available temperatureand pressure inputs; see Reference 3. Qualification relating to componentsnot previously addressed is reported in Attachment A of this response.

Qualification information for future TMI Action Plan equipment will be sub-mitted by the pre-implementation or implementation review date as required DOjby Reference 2, Supplement 3 to Bulletin 79-OlB. #

# /Equipment Required to Achieve Cold Shutdown

The November 1, 1980 response to Bulletin 79-OlB has been reviewed to identifyadditional electrical equipment necessary to achieve and maintain a ColdShutdown condition.

I8204070472 810122 !PDR ADOCK 05000282 JAN 2 61981* PDR

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Mr. James G. Kepplero

January 22, 1981

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The residual heat removal system, while not necessary, would, if available,normally be used to cool the plant to cold shutdown. Additional electrical.

equipment normally used would be the nonsafeguarda RHR suction valves fromboth RCS hot 1 cgs and the nonsafeguards loop B RHR return valve. The environ-mental specification and qualification of these components is identified inAppendix A of this response. Outstanding items have been identified forspecific accident related environmental conditions. NSP intends to continueinvestigation of these outstanding items.

In the event that the residual heat removal system components identified for.cooldown are not available, the auxiliary feedwater system along with thesecondary side power-operated relief valves would be used to bring the plantto a safe cold shutdown condition. The safety injection pumps and residualheat removal pumps, taking suction from the refueling water storage tank orcontainment sump, would be used to maintain reactor coolant system inventory.Use of the steam generators as a forced cooling water heat exchanger at lowertemperatures is discussed in FSAR Section I.8.

Yours truly,

0D. E. GilbertsSenior Vice PresidentPower Supply

cc: Mr. G. CharnoffMr. C. D. FeierabendNRC Office of Inspection and Enforcement

Washington, D. C. 20555

Enclosures

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UNITED STATES NUCLEAR REGULATORY COMMISSION

NORT11ERN STATES POWER COMPANY -

PRAIRIE ISLAND NUCLEAR GENERATING PLANT

Docket No. 50-282 and 50-306

LETTER DATED JANUARY 22, 1981RESPONDING TO NRC REQUEST

FOR INFORMATION IN IE BULLETIN 79-01B

Northern States Power Company, a Minnesota corporation, by this letter datedJanuary 22, 1981, hereby submits information in response to NRC request forinformation concerning IE Bulletin no. 79-01B.

This request contains no restricted or other defense information.

NORTHERN STATES POWER COMPANY

By h, W-

L 0 MayptManager of Nuclear Support Services

On this MM day of & m m /98[,beforemeanotarypublicinand,

for said County, personallyvappearedfL 0 Mayer, Manager of Nuclear Support Services,and being first duly sworn acknowledged that he is authorized to execute thisdocument on behalf of Northern States Power Company, that he knows the contentsthereof and that to the best of his knowledge, information and belief, the statementsmade in it are true and that it is not interposed for delay,

O~aru

.::..:: :.: :.::::.:7...

ffe% BETTY J. DEAN o-

Notanv evotic . uiNNtsotA ::? RAMSEY COUNTY !{.: . :. ^^ ^, u Commism Empes Dec to 1987 |; , r

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'' MASTI ' LIST

nev. 61/9/81

"ASYSTE!!: INSTRUMENTATION & PROTECTION (R.C.)

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COMPONENTS

PLANTIDENTIFICATION INSIDE PRIM.\RY OUTSIDE PRIMARY?iU!IBER GENERIC NA?fE CONTAI:01ENT CONTAI:01ENT

I21146 Pressurizer Pressure X I

21147 Pressurizer Pressure X|

21148 Pressurizer Pressure X |

21150 Pressurizer Pressure X .

|21154 Pressurizer Pressure X

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21155 Pressurizer Pressure X .'|

21156 Pressurizer Pressure X :

deb |21157 Pressurizer Pressure X |

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24041 Pressurizer Level i X'

!24042 Pressurizer Level X i

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24043 Pressurizer Level X |

24046 Pressurizer Level X l

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24047 Pressurizer Level X

24048 Pressurizer Level X

*15197 RTD (Narrow) X

i*15199 RTD (Narrow) X

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i*15201 RTD (Narrow) X ,,

f*15203 RTD (Narrow) X



#m> *15211 RTD (Narrow) X


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'UU "ER LISTRev. 6*

.jfP' 1/9/81

SYSTEM: INSTRIBENTATION & PROTFNTO'I (R.C)*

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i COMPONENTS

PLANT LOCATION

IDENTIFICATION INSIDE PRIMARY OUISIDE PRII|' RYANUMBER GENERIC NA'IE CONTAINMENT CONTAINMENT



'*15232 RTD (Narrow) X



*15240 RTD (Narrow) X'

*15242 RTD (Narrow) X,


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*TNE Installe d Lessons Learned-Supplement 3

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Rev.'6,

SYSTD4 CX24PONDE EVAI11ATION VERKSIIEE.T

. UNIT: . Prairie Island 1 & 2

DOCKET: '50-282 & 60-306N W ,E OmmE

EQUIH4E!E DESCRIPTIONPARW1'ER j SPIIIFICATION QUALIFICATION SPlf. G.IALIF. 5 Elf 0D ITDIS

SYSTU4: Instrumentation & OPEFATIMPIR E ID 10.: Prot. Type

,,

See. Note 1 3 days 2 weeks 6 4 g Test NONE* ~

00tTONDE: TDIP. I Type~

RTD Deg. F 268 F 320 F 1 4 Test NONE,

WMJFICI'JRE: PRESSURE Type |

W/SSTFN (PSIA) 60.7 psia 80.7 psia 1 4 Test NONE i. - - _ _ . . __ . !

!DDEL IEEER: PJ21.T1VE 6 i

!DM11834B 100% 100% 5 4 es NONE*

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| |'o M ETION: CIID1ICAL II B0 /Na0ll 1.146% ll B0 DY3 3 3 3 Type*RCS Temp. Narrow SPIF3 pil 9.0-9. 5 wt 17% Na0li 2 4 Test NONE :

~ ~~~7ACCURTCY: SPIR. 5% .

7DDON: 2-3% PADIATION 3.6 x 10 Rad 5 x 10 Rad 3 4 Tes NONE_ . _ _ __I,

SE!WICE: RCS Unit 1 T Iie |^i

G V "'' 4 Test NONE jLOCATION: Containment |

12 years ;'

FI/DCO leNEL ELEV: 706' '-

GUE,-! NONE

_ _ __Yesk

Not Required!

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I.!UVE FI/JOD LEVEL: i

*DOCUM17EITION REFERRCES: IDTI.}:.

1) FSAR Chapter 5 Figure 5.2-7 1) Includes: 15197

2) FSAR Chapter 6 Section 6.4.3 15199152013) FSAR Chapter 7 Page 7.5-1215203

~4)- WCAP 9151, September 19775) FSAR Chapter 5 Tabic 5.4-4 15207

152096) -Engineering Evaluation1521115213 ..

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Rev. 6 -

SYSTEM CCEPONE2R EkeMTION VCPSSFELT 1/9/81

UNIT: Praire Island 1 & 2

DOCKET * 50-282 & 50-306.

AUIRIE2.T DESCRIPTICN'

PAPNET. ER SPECIFICATION QUALIFICATION SPT:C. QUALIF. MEnlOD ' ITDG

SYSTD4: Inst rumentat ion 6 OPERATIN3PIANT ID !O.: Prot. Type-

See Note 1 3 days 2' weeks | 6 4 Test NONET'

CCEIONE2R: IntP. Type| TestRTD Deg. F 268 F 320 F 1 4 NONE

li W FACIUPE: PPFSSUIE|

NONEl Type ,

e Rosemount (PSIA) ', 60.7 psia 80.7 psia 1 4 Test * i

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| . MODEL IGBER: IELATIVE |

f 176 KF 100% 100% 5 4 s NONE'

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EfE CISMI N 11 B0 /Na0li 1.146% 11 B0o ~ * 3 3 3 3 Type

.-w

* ACCURACY: SPFC. 5%-

- pH 9.0-9. 5 by wt. 17% Naoll 2 | 4 Test NONE !g RCS Temp. Narrow SPPvTi'

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DD ON: 2-3% RADIATION 3.6 r. 10 Rad 5 x 10 Rad 3 4 Test NONE

| SFJWICP.: RCS Unit 2 q |

1.'JATION: Containment I12 years ! 4 e NONE i

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FI!J FGIEL ELEV: 706'i SU"~ ~ ~ ~ ~'

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!A'rNE E"OOD LEVEL: Yes Not Required NONE

L__*DVJMRATION RWJ:NCPS: IUI"p:

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1) FSAR Chapter 5 Figure 5.2-7 ' 1) Includes: 15228, 15230, 15232, 152342) FSAR Chapter 6 Section 6.4.3 15238, 15240, 15242, 15244

3) FSAR Chapter 7 .5-12-

4) 'WCAP 9157, September 19775) FSAR Cahpter 5 Table 5.4-4

I 6) Engineering Evaluations

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MAF.ER LIST Rev. 61/9/81*

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SYSTEM: Residual lient Removal (Ril) ,

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COMPONENTS

IPLANT LOCATION

IDENTIFICATION INSIDE PRIMARY OUTSIDE PRIliARYNUMBER GENERIC NAME CONTAINMENT CONTAINMENT

11 Motor X

12 Moto r X

21 Mo to r X

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22 Moto r X

' CV-312 35 Limit Switches X

CV-31236 Limit Switches X

ar CV-31237 Limit Switches X

CV-31238 Limit Switches X

CV-31239 Lirit Switches X

CV-31240 Limi t Switches X j.

*32066 Valve Operator X







'*32231 Valve Operator X [l

*32232 Valve Operator X !+

|d[ *32233 Valve Operator X

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* Cold Shutdpwn Equipment - Supplement 3 ;

A.17.1._.

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Rev. 6 '

SYSTF14 CEMPONH7f EVALUATION HORKSHEET 1/9/81

UNIT: Prairie Island'1 & 2

DOCKET. : 50-282 & 50-306

DWIRISTr DESCRIPTIONPAIW2T. ER SPECIFICATION QUALIFICATION SPEC. QUALIF. ML'HIOD ITDIS

SYSIB4: Residual Heat OPERATIIC| Type

PI1NP ID 10.: Removal 1 .TDIE 69 Ilours 6 Test NOTE 2See Note 1

O'EPONCfr: TC4' ., peNONE' Valve Operator Deg. F 268 F 325 F 1 4 | Test

EMJFACIURE: PRESSURE !Type

(PSIA) 60.7 psia 74.7 psia 1 4 Test NONE I

Limitorque ._ _ _ __ yFCDEL NUMBER: RELATIVE I

Type g!!RilDIT'l100% 100% 5 6 Test NONE *

?" SMB-1 (%),

II B0 /Na3 2 3S0lC FUICTION: Q DiICAL ll B0 /Na011 3 3 Type3 3 ,,

SPPI6Y pil 9.0-9. 5 Naoli pil 7.85 2 4 i Test NONE |RilR Isolationl

|ACCUPIC': SPEC. NR Type

| NONE7 8DDON: NR RADIATION 3.6 x 10 Rad 2.04 x 10 Rad 3 4 Test_

SEINICE: 11, 12, 21, 22' Type#" Test NONE

|na ent i_ - . _ ,

IOCATION:

FIDOD LLVEL ELII/: 706 ' SUB-NONEI4EPSENCE Not Required

ASOVE FIDOD LEVEL: Yes -

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IN*_DO_CUMENritTION REFITCTSS:*

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1) FSAR Chapter 5 Figure 5.2-7 1) Valves Include: MV 32165MV 321932) FSAR Chapter 6 Paragraph 6.4.3MV 322313) FSAR Chapter 7 Page 7.5-12

. 4) WCAP 7410-L Dated December 1970 & MV 32232

WCAP 7744 Dated August 1971.5) FSAR Chapter 5 Table 5.4-4 2) Reference attached letter, this

6) FIRL F-C3271 Dated February 1972 response.

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Rev. 6 * ~

SYSTEM CIEPOtfr:fr LVAIEATION 1rCPESIIEET 1/9/81

UNIT: Prairie Island 1 & 2

D3CKLT: 50-282 & 50-306-1;UIIGH2C DOCUSETTATION REF* Ql1%IF OUTSTANDUC

-ITJUIR412TT DESCRII'rION |

PAPMunER SPECIFICATION QUALIFICATION SPIR. QUALIF. ML*DIOD l'11FS

SYSTF14: Residual Heat OPr3ATRX3TypePIRTT ID !O.: Removal TIME _ 69 Hours 6 Test NOTE 2

See Note 1 _

OJMPONI21r: 'IEMP . Type'

268 F 325 F 1 4 Test NONEValve Operator 939, pa _ . . . = _

MA!UFACIURE: PRESSURE TypeLimitorque (PSIA) 60.7 psia 74.7 psia 1 4 Test NONE

%._... i w oun-.. =

Type !PODEL ID*BER: P121sTIVE>

fSMB-1- 100% 100% 5 6 Test NONE,

* FUNCTION: L 'T31I N H B0 /Na0ll ll B0 /Na3 2 3S0/3 3 Type*3 3|pH9.0-9.5 Na0li pH 7.85 2 | 4 Test , NONE IRHR Isolation SPRAY

ACCURACY: SPEC. NR [ ].g.ypgDHON: NR PADIATION 7 83.6 x 10 Rad 2.04 x 10 Rad 3 4 Test NONE |

._[SWICE: RilR. Loop i

Type 'Suction tc,nyj

19. 210N: Containment 40 Years 4 Test NONE [-_ __ . . . -,

fin 01EVEL ELIN: 706r 3.g;;_ ,

IJ.POVE FIDDD LEVEL: No - NOTE 2J ._.1_ !

*IrmiEt7 RATION ic2im2CE3: INE:*

') FSAR Chapter 5' Figure 5.2-7 1) Valves Include: MV 32164

2) FSAR Chapter 6 Paragraph 6.4.3 FN 32192

3) FSAR Chapter 7 Page 7.5-12 MV 32230

4) .UCAP 7410-L Dated December'1970 & IN 32233WCAP 7744 Dated August 1971 2) Reference attached letter, this

5) .FSAR Chapter 5 Tabic 5.4-4 response.

6) FIRL F-C3271 Dated February.1972

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Rev. 6I

SYSTEM GNPONENT EVALUATION VERKSIIEET..

UNIT: Praire Island 1 & 2

DCOTT: 50-282.& 50-306" '

ECUIIMIITT DESCRIPTIONPAPNIUTER SPI:CIFICATION QUALIFICATION SPlc. QUALIF. ME1110D ITE26'

SYEN: Residual Heat CPEl&TII7iPIA!TP ID 10.: Removal Type

;6911 urs 6 I Test NOTE 2See Note 1 ,

| .g. eCOMPOTE 7F: TD1P .

| TestValve Operator Dog. F 268 F 325 F 1 4 NONE-

| TypefrcCFAC'IUFE: PluSSURE

Limitorque (PSIA) 60.7 psia 74.7 psia 1 4 Test NONE.

MODEL IE:BER: PJ2ATIVE'y Type.IUiIDI'iYy S MB-0 100% 100% 5 6 Test NONE 1g)

* FUNCTIOM: RSDL llT CIIiMICAL ll B0 /Na3 2 3S0/ll B0 /Na0ll3 3 3 3 Typele P B Return gppAy pil 9.0-9.5 Na0li pil 7.85 2 | 4 Test NONE !

ACCUPICY: SPEC. NR IType

DRDN: NR RADIATION 7 2.04 x 10 Rad 3 4 Test NONE83.6 x 10 Rad

SEIWICE: Unit 1 & 2 [--Loop Injection Line Agrn 'lype ,

' ICCATION: Containmen t 40 Years 4 Test NONE |

FIfyJ) Lt. VFL ELEN: 70F SUb- |~

; 7MEICE E $

ACOVE F1 COD IEVEL: Yes Not Required NONE_. _ _. ._J

*COCUMrNTATION REFEPJ1CIE: INE*.

1) FSAR Chapter 5 Figure 5.2-7 1) Valve Include: MV 32066

2) FSAR Chapter 6 Paragraph 6.4.3 MV 32169

~. 3) FSAR Chapter 7 Page 7.5-124) WCAP 7410-L Dated December 1970 & 2) Reference attached letter, this

WCAP 7744 Dated August 1971 response.

5). FSAR Chapter 5 Tabic 5.4-46) FIRL F-C3271 Dated February 1972

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Rev. 6-

1/9/81MASTER LIST

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SYSTEM: 480V MTSC AUX (EB);

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COMPONENTS

PLANT LOCATION

IDENTIFICATION INSIDE PRLMARY OUTSIDE PRIMARY

NUMBER GENERIC NAME CONTAINMENT CONTAINMENT

*1LAl Motor Control Center X

*lLA2 Motor Control Center X

*2LAl Motor Control Center X

*2LA2 Motor Control Center X

* Cold Shutdown Equipment - Supplement 3

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Rev. 6 *

I/9/01SYSTEM CCMPONDir LVALUATION HCPSSHEFJr

(IRT: Prairie Island 1&2

DOCKET: .50-282 & 50-306

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E2UIH4I2TP DESCRIPTIONPAPNEIER SPECIFICATION QUALIFICATION SPEC. CXJALIF. FEDIOD IID'S

SYSTD1:480V_ Misc Aux (EB.) OPERATR EPIIME ID:D.: TRE Continuous NOTE 2See Note 1COM00taff: TEM?. .'

Motor Control Center W. F - 210 F 1 NOTE 2, 3

!@llfFACTUTE: PPESSURE |

General Electric (PSIA) 15.2 psia 1 NOTE 2, 3> PDDEL !UGER: RELATIVE ,.

N !!GilDITY IF 7700 Line Control (g) !100% 1 NOTE '. 3

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"" #FUNCTION: OID11 CAL l

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480 Volt MCC' gppny Not Required Not Required NONE |ACCURACY: SPEC. NR

DEMON: NR PJ4DIATIO!! 20 mr/hr Not Required 2 3 NOTE 4

SERVICE: SafeguardsAGD73

ILUsTION: Aux Bldg |~

]E"JJOD LINEL ELEV: NR | SUli-

FSOVE FIf)OD IEVEL: NR Not Required NONE..

*P/X1MlfrATION le.meKTS: Wr"S:.

1) FSAR Appendix 1, para I.11.1 1) MCC's; ILA1, ILA2, 2LAl, 2LA2~

2) Design Review of Plant Sheilding and Environmental 2) Reference attached letter, this response.Qualification of Equipment for Spaces / Systems outside 3) Only when a llELB occurs.Containment which may be used in Post. Accident 4) Only when a LOCA occurs.Operations - Part I; July 1,1980.

3) Engineers Evaluation.

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mr. james g. keppler

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