ML19344E784

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Slide Presentation Entitled, NRC Staff Review of Sequoyah (TVA) for Full Power Operation - Commission Briefing, 800821
ML19344E784
Person / Time
Site: Sequoyah  
Issue date: 08/21/1980
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19344E785 List:
References
NUDOCS 8009110336
Download: ML19344E784 (23)


Text

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a 0-l NRC STAFF REVIEW QE SEQUOYAH

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(IV.A)

SR FULLPOWEROPERATIdN

' COMMISSION BRIEFING - AUGUST 21', 1980 1

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t OUTLINE e

PURPOSE OF MEETING LICENSEE'S ACTIONS SINCE FUFP LICENSE ISSUANCE o

RESULTS OF LOW o0WER TESTING PROGRA!i e

NRC OL REVIEW NON-TMI ITEMS

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TMI ITEMS l

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e RECOMMENDATIONS

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LICENSEE ACTIONS SINCE LP ISSUANCE FEBRUARY 29, 1980 e

NRC FL APPROVAL e

INITIAL CRITICALITY JULY 5, 1980 JULY 10, 1980 e

NRC LP TESTING APPROVAL JULY 12, 1980 e

LOW POWER TESTING INITIATED e

LP COMPLETED

- JULY 18, 1980 HOT STANDBY e

CURRENT STATUS OF PLANT

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e PLANT READY TO START POWER ASCENSION

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LOW POWER TESTS CONDUCTED 1

1.

NATURAL CIRCULATION (N. C.) TEST 2.

N. C. WITH SIMULATED LOSS OF 0FFSITE POWER 3.

N. C.WITH LOSS OF PRESSURIZER HEATERS 4.

EFFECT OF STEAM GENERATOR SECONDARY SIDE ISOLATION ON N. C.

5.

N. C. AT REDUCED PRESSURE 6.

C00LDOWN CAPABILITY OF THE CHARGING AND LETDOWN SYSTEM 7.

SIMULATED LOSS OF ALL AC 8.

ESTABLISH N. C. FROM STAGNANT CONDITION 9i.

FORCED CIRCULATION C00LDOWN 9s.

BORON MIXING AND C00LDOWN

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RESULTS OF LOW POWER TESTING PROGRN4 e

TESTS CONDUCTED SAFELY j

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MEANINGFUL INFORMATION ON PLANT RESPONSE TO A VARIET.Y OF ABNORMAL CONDITIONS I

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PLAtlT RESPONDED AS PREDICTED AND TESTS C0tlFIRMED NATURAL CIRCULATION HEAT REMOVAL CAPACITY e

PROVIDED BASE LINE DATA FOR SPECIFIC PLANT CHARACTERISTICS i

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e ALL OPERATING CREWS RECEIVED SUPPLEMENTAL TRAINING DURING THE PROGRAM FOR NATURAL CIRCULATION i

SUMMARY

LOW POWER TEST PROGRAM CONDUCTED AT SEQUOYAH SATISFIED ALL HRC REQUIREMENTS I

NRC REVIEW

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e NON-TMI ITEMS INCLUDING FIRE PROTECTION ENVIRONMENTAL QUALIFICATION PRESSURIZER RELIEF LINE WELD REPAIR e

TMI ITEMS INCLUDING HYDROGEN CONTROL DATED ITEMS EMERGENCY PREPAREDNESS 4

t FIRE PROTECTION e

FIRE PROTECTION PROGRAM MEETS GDC-3 AND BRANCH TECHNICAL POSITION APCSB 9-5-1 e

IMPLEMENTATION OF REQUIRED 'TEMS TO BE COMPLETED BY NOVEMBER 1, 1980

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EQUIPMENT QUALIFICATIONS-e TVA RESPONSE TO NUREG-0558 RECEIVED JUNE 16, 1980 e

44 TYPES OF DEFICIENCIES e

INITIAL RESULTS INDICATED 44 TYPES OF DEFICIENCIES INCLUDES VALVES, MOTORS, MOTOR CONTROL CENTERS e

STATUS ALL "'JT ONE TYPE OF ITEM ACCEPTABLE TO STAFF ON BASIS OF SHORT TERM OPERATIONS ONE REIMINING TYPE OF ITEM WILL BE RESOLVED PRIOR TO EXCEEDING 5% POWER e

TVA WILL COMPLETE REVIEW BY NOVEMBER ', 1980 TVA WILL FOLLOW TECHNICAL SPECIFICATIONS OF DEFICIENCIES e

FOUND e

DEFICIENCIES WILL BE CORRECTED PROMPTLY l

e STAFF WILL COMPLETE SER BY FEBRUARY 1, 1981 PER COMMISSION MAY 23 ORDER 1

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EQUIPMENT QUALIFICATIONS STATUS 44 TYPES OF DEFICIENCICS e

6 REPLACED TRANSMITTERS SWITCHES SOLEN 01D VALVES e

1 RELOCATED TO LESS SEVERE ENVIRONMENT (TRANSDUCER) e 11 NOW QUALIFIED CABLES VALVES e

20 ACCEPTABLE BASED ON ANALYSIS OF QUALIFICATION DOCUMENTATION EXPECTED BY NOVEMBER 1, 1980 VALVES, TRANSMITTERS, SWITCHES, AIR HANDLING UNITS, FANS, RElli BOARDS'.

e 5 CONDITIONALLY QUALIFIED (MORE DOCUMENTATION EXPECTED BY NOVEMBER 1, 1980)

VALVES, MOTORS, FANS e

1 TO BE RESOLVED BEFORE EXCEEDING 5 PERCENT POWER 1

(LICENSE CONDITION) - TRANSMITTERS

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HYDROGEN CONTROL e

UNDER CERTAIN ASSLN.PTIONS SEQUOYAH CONTAllt?JiT CAPABILITY NOT SUFFICIENT TO ACC0m0DATE LARGE HYDROGEN RELEASE / BURN; E.s., TMI-2 e

IN SHORT TEM, PERMIT FULL POWER OPEPATION MITHOUT ADDITIONAL POST-ACCIDENT HYDROGEN CONTROL FEATUPIS REQUIRED ACTION PLAN APPROACH ACRS APPROVAL DEGPADED COPI RULEFAKING LESSONS LEARNED IMPLE?BiTATED e

TVA PROPOSED DISTRIBUTED IGiiITER SYSTEM LICENSEE SAFETY INFDPIATION WITHIti 90 DAYS STAFF EVALUATION COMPLETE BY DEC9tBEP. 1980 SYSTEM OFFER CONSIDE?ABLE PROMISE l

SYSTEM HILL BE INSTALLED; OPERATION NOT AUTHORIZED AT THIS TIFE

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e REQUIRING ADDITIONAL SArtiY FARGIN THROUGH NEE STRINGBIT TECHNICAL SPECIFICATIONS IN INTERIM

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NUREG-0694 - DATED REOUIREMENTS TVA COMMITTED TO COMPLETE ALL 15 ITEMS BY JANUARY 1, 1981 HOWEVER, 5 WILL BE DEFERRED AS FOLLOWS:

HEfi ER03 ID.

II.B.1 RSC VENTS 1/81 1/82 II.B.3 POST-ACCIDENT SAMPLING 1/81 1/82 II.F.1(c)

HYDR 0 GEN MONITORING 1/81 1/82 II.F.i(E)

NOBLE GAS EFFLUENT MONITORING 1/81' 1/82 II.F.2 REACTOR VESSEL WATER LEVEL 1/81 1/82

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EMERGENCY PREPAREDNESS TVA'S REVISED EMERGENCY PLAN IS IN COMPLIANCE WITH e

NUREG-0654 AND MEETS 10 CFR 50, APPENDIX E FEMA FINDINGS STATE THAT STATE AND LOCAL PLANS ARE e

ADEQUATE BASED ON OUR EVALUATION AND FEMA FINDINGS PROGRtJ1 e

MEETS THE REQUIREMENTS FOR A FULL POWER LICENSE

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  1. 1.<vkl ESCALATIDI TD 3(A POWEPo 7 IRYS
1. SU-8,5 NUOfAR #91DERATLTE ItSTRUE!TATIG! CALIBPATIM #9 TEIML PGER WASl!B9T
2. AUIU% TIC EACIDR C0mu.
3. AUTU% TIC STEAM EEPATOR LBEL 01tiju.
4. SU-LO PUNT EASUEENTS - BAS $LINE #9 CPEPATI0t'AL DATA 5.

CfLIBPATION OF STEAM #9 EE! MATER FLW I?STPi!E!TATIM AT PGER

6. SU-9.1 LOAD SWING lESTS
7. S0-1.1 LOSS OF 0FFSITE PGER
8. SU-1.2 SHUTIDil FROM OUTSIIE U.'TPOL RDW
9. SU-8.1 POER COEFFICITT A'O INTEGPAL %ER IEECT.YJSlEE!T
10. SU-8.2 RCCA PSEUD 0 EJECTIel #9 RCG /EE B#iK POSITIm EASlEENT
11. STARTlP AIUlETtS13 0F EACTOR #01HSIE CONTROL SYSTRS l

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ESCALATI0h TO 50% POER; 3 IRYS

1. SU-8.1 POER CEFFICIENT #9 INEGP!L POER IEECT EASWEIE!TS
2. SU-8,5 NUCLAR #8 TETEPATLIE I!STRIB!TATION CALIBRATIM #D TEPWL P0kER.TJEUEENT
3. SU-8.3 STATIC PCCS IRP #D PCG BElal B#!K POSITIm EASLTEfiS
4. SU-1.0 P1AT EASUEENTS - BASEUtE #0 0FSATITAL DATA 5.

CALIBR4 tim 0F STENI #D EENATER R.W IBSTP&E!TATIm AT POER S.'

SU-9.5 RD GROLP DRP #9 PLRIT TRIP

7. FAINTEFAE OUTAE - 14 MYs a 0%

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ESCALATIm TO 7.i% POElb 7 IRYS

1. SLF8.1 POER CEEICIENT AND INTEGPAL P0h8 IEECT EASLEH15
2. SLF8,5 NIHEAR #9 TEPPEIMTLE ItsIRfETATIm CALIBPATIm #D lETAL POER fBSIEET l
3. SlF8.4 INCOE-EXCDFE IEECTOR CALIBPATIm
4. SlF9.11.0AD SWING lESTS
5. SlF9.3 LAPE LOAD PEDUCTIm TESTS
6. II CALIBPATION OF STEAUO EEll!ATER FLOR ItGTPJJETATIO'!
7. SU-1.0 PL41T WJSLEBUS - BASELINE #9 OPEPATIO9L DATA
8. SLF10.2 STEA'i SEPATOR t0lSTUE CAPROER fBSLEST O

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ESCAIATI0l 10 90lC POER; 2 DAYS

1. St}-8.1 POWER CHFIGENT #iD INEGPAL POER EASUE?9fl3 IEECT
2. SU-8,5 NUCIE/2 #0 it:TEPATURE I!ETRE6510t! CALISPATION #0 WRML POER NASt>TEENT
3. SU-LO PUNT EASU ENTS - BKELINE MD O'EPATIO5'AL DATA I4. SU-10.2 STEA9 E!EFATOR P0ISTUR WOER PEWB9IT l

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ESCALATle! TO 103 POER; 35 IRYS

1. 50-8,5 NUQFEAR & TEPPEPATUE IBSTRtelTATIRJ CALBPATION #9 lER%L PQER fEASUEtEE
2. SU-10.1 PSSS ACEPT#lE TEST
3. St}-10.2 STEAM EEPATOR FDISTUE CAPRSER PEASUEtE!T 4.

CALIBNATIQ1 (F STEAM #0 EENATER R.m INSTPJ.fEITATI21

5. SU-9.1 LGAD SWItE TESTS
6. SU-9.3 LAKE LOAD FEDLLTIQ! TESTS
7. St}-9.4 PME TRIP FPCM103 POER
8. S0-1.0 PLNE tFEUEtB'1S BASELIFE #9 CPEPATIDL DATA 9.

FEACTOR PL#E SYSlBS SETP01.1TS ERIFICATIT!

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FIRE PROTECTION 7 TYPES OF DEFICIENCIES ITEMS 1, 2 & 3 - RELATED TO ERCW - LOSS OF ERCW BY FIRE DOES NOT AFFECT HEALTH OF PUBLIC (AERCH CAN BRING PLANTS TO COLD SHUTDOWN)

ITEM 4

- FIRE DAMPERS WILL BE INSTALLED BEFORE

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NOVEMBER 1, 1980 ITEM 5

- FLAME RETARDANT MATERIAL SUFFICIENT AT THIS. TIME

- 10 CABLES CAN BE INSTALLED BEFORE NEED TO C0AT

- ONGOING EFFORT ITEM 6

- P.ETAL BARRIER PL4TE NEED NOT BE COVERED WITH PYR0 CRATE ITEM 7

- ADDITIONAL SPRINKLER HEADS AND RELOCATION MUSTBECOMPLETEDBYNOVEMBER1,i980

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E PSI WORKING PESSLNE HAS MIXING'F#6 2PRESSLRETRMtSDU NE TERN 0cxxsuS (INcuo!Ns EATED SLMCE) h,QSMetERS g, STEM, AIR MIXMS POSSIRE INSTRMTED,WR Smp FIRST TEST SERIES M THRu 96 TEST EDURTION 9/15 Tmu 9/19 e

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TVA PHAS?.11 P!0GM RR EstED EFFECTIETSS.

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