ML19296C458

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Slide Presentation Entitled, NRC Staff Review of TVA Sequoyah Nuclear Plant for Fuel Load & 50% Power Ol
ML19296C458
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 02/12/1980
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19296C454 List:
References
NUDOCS 8002260088
Download: ML19296C458 (50)
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Text

{{#Wiki_filter:' 3 NRC STAFF REVIEW OF TVA SEQUOYAH NUCLEAR PLANT FOR FUEL LOAD AND 5% POWER OPERATING LICENSE =

OUTLINE I Introduction ll Plant Description lll Sequoyah Compliance With NTOL List IV Staff Review of Pre-TMI Matters V Conclusions

1. INTRODUCTION OBJECTIVE OF COMMISSION MEETING SCOPE OF REVIEW: PRE-TMI ITEMS SCOPE OF REVIEW: TMI MATTERS

OBJECTIVE OF MEETING To Obtain Commission Approval of NRR Staff's Review of Sequoyah Nuclear Plant e To Load Fuel e To Operate Up to 5% Power e To Conduct Special Test Program, Operator Training and Zero Power Test Program

SCOPE OF REVIEW TMI ITEMS (Based on NRC Action Plan) (NUREG-0660) e Lessons Learned (NUREG-0578) e Bulletins Er Orders (NUREG-0645) e Emergency Preparedness . Special Test Program including Recommendations of e Presidential Commission e NRC Special Study Group

SCOPE OF REVIEW PRE-TMI ITEMS CBased on Existing Regulations) e SRP e Branch Technical Positions e Regulatory Guides & Standarcs e Unresolved Safety Issues

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O e EC N 4 A ILP MT OS I CL HL AO Y T O N UH QT I ESW l l I

9 T'il ACTI(fl PIR! 50L E0l!IIrfT!"S PART 1 - 5 01.ItOlllREffilTS fl0T PREVIOUSLY ISSUED WEN SE0lIN#1 SSER ETEENE ITEll APPL.lCABLE A"DSTATLE (1) 1.A.1.3 SHIFT lhfililllG (A) S $, W Ill CQlTROL IDOM Il th0UIRES IVA CoffilTMEllT (n) OmRTirt itsTRicTIQis FL ( (2) 1.A.3.1 Lictrisirlo EXAMillATIQlS fl PART lj SEC.13.2 - SUBSTAtlTIAL C0fuMICE O G

SEQUOYAH OPERATOR LICENSING HISTORY 1. JANUARY-MARCH 1979. INITIAL GROUP OF COLD WRITTEN AND OPERATING TESTS. COMPLETE RESULTS NOT DIS-CLOSED DUE TO TMI-2. 70% OVERALL TO PASS. 2. SEPTEMBER 1979. SECOND GROUP OF COLD EXAMINA-TIONS (5 REEXAMS) WITH TMI RELATED MATERIAL ON WRITTEN AND SIMULATOR EXAMS. PASSING GRADE 70% OVERALL,80% ON TMI-2 MATERIAL. 3. NRC REQUIRED TVA TO ADMINISTER TMI-2 RELATED EXAMINATIONS TO JAN-MAR '79 GROUP. PASSING GRADE WAS 90%. ALL PASSED. NRC REVIEWED EXAMS AND GRADING. 4. TOTAL NUMBER OF LICENSED OPERATORS 6 SENIOR OPERATORS 18 5. PRESENTLY THERE ARE 12 APPLICANTS UNDERGOING NRC EXAMINATIONS FOR LICENSES. PASSING GRADE IS 70% OVERALL AND 80% ON TMI-2 MATERIAL.

SEQUOYAH OPERATOR ACADEMIC HISTORY 1. ALL APPLICANTS HAVE HAD APPROXIMATELY 3000 HOURS OF CLASSROOM TRAINING PRIOR TO LICENSING. 2. ADDITIONALLY, ALL OPERATORS HAVE BEEN TRAINED AND HAVE PASSED EXAMINATION ON TMI-2 RELATED SUBJECTS, INCLUDES SIMULATOR WORK. 3. GREATER EMPHASIS HAS BEEN PLACED IN THE TRAINING PROGRAMS ON HEAT TRANSFER AND FLUID FLOW. 4. THE OPERATOR REQUALIFICATION PROGRAM WAS PLACED IN EFFECT iMMEDIATELY AFTER THE JAN-MARCH 1979 EXAMINATIONS. INCLUDES CLASSROOM AND SIMULATOR TRAINING.

PutTm HEN SE0lDYMI SSER EFEfENE IUl APPLICABLE R!D STATLS F (3) I.B,1,1 QWd!ZATI0ll NID IhtWHEllT FL IllTEROFFICE REVIEW TEN 4 ilAS IDEilT!FIED CRITERIA i 7 ITD4S TO BE RESOLVED PRIOR TO OL ISSuNICE (f0 I.B.1.2 SAFETY filGillEERING GROUP fl !!EEDS TVA emilTMEllT (5) I.C,5 LiCctlSEE DISSEf tlllATI0ft 0F COVERED BY litTEROFFICE REVIEW (ITEM 3 ABOVE), O'ERATillGEXPERIDICES fl 1 G G $e lL

ACTION PLAN ITEMS REVIEWED BY JOINT NRR/IE TEAM Shift Manning Organization and Management Criteria Safety Engineering Group Resident inspector Licensee Dissemination of Operating Experience Applicant /NRC Communications STATUS Review Team Visited TVA January 28-29 Final Staff Posit}on to be Presented in Supplemental SER Prior to Fuel Load

OUTSTANDING ITEMS RESULTING FROM INSPECTION OF TVA MANAGEMENT

1. Senior Personnel (SS and Above) Lack Current PWR Operating Experience.
2. Plant Organization Needs Clarification.
3. Training of Emergency Response Teams.

4 Onsite Safety Review Group.

5. Qualification of Shift Technical Advisors.
6. Westinghouse Technical Support for Special Test Program.
7. Clarification of Command Lines for Emergency Response Organization.

Put TmEE WEN SE010Y#1 SScR IEIEIENE IEM APPLICABLE

  1. 9 STAILS (6)

I.C.7 Wrima ItVIEW T PROCEWRES (A) EtERGEllCY PROCEDURES fP (n) im Para TESTS fl ItiPROGRESS; SECT.l.C.7 (C) Parn AsCeriSI0ra FP G 9 e 9

O 6 PROPOSED TESTS 1. NATURAL CIRCULATION (NC), NORMAL CONDITIONS. 2. NC WITH SIMULATED LOSS OF OFFSITE AC. 3. NC WITH LOSS OF PRESSURIZER HEATERS. 4. EFFECT OF STEAM GENERATOR ISOLATION ON NC. 5. NC AT REDUCED PRESSURE. 6. COOLDOWN CAPABILITY OF CHARGING / LETDOWN SYSTEM. 7. SIMULATED LOSS OF ALL AC. 8. ESTABLISHMENT OF NC FROM STAGNANT CONDITIONS. 9A FORCED CIRCULATION COOLDOWN. 9B BORON MIXING AND COOLDOWN IN NC.

d LOW POWER TEST PROGRAM CRITERIA TESTS SHOULD PROVIDE MEANINGFUL INFORMATION TESTS SHOULD PROVIDE SUPPLEMENTAL OPERATOR = TRAINING TESTS SHOULD NOT POSE UNDUE RISK TO PUBLIC RISK OF PLANT DAMAGE SHOULD BE LOW POST-TEST RADIATION LEVELS SHOULD NOT PRECLUDE = IMPLEMENTATION OF FUTURE Tiv11-2 REQUIREMENTS

STAFF EVALUATION CRITERION 1 - MEANINGFUL TECHNICAL DATA

  • INITIAL TESTS ARE STEPS TOWARD THESE SIGNIFICANT TESTS

. LOSS OF ALL AC POWER

  • BORON MIXING DURING NC

. ESTABLISHMENT OF NC FROM STAGNANT CONDITIONS

  • NO TWO-PHASE TESTING PROPOSED

+ STAFF CONCLUDES CRITERION 1 IS SATISFIED CRITERION 2 - SUPPLEMENTAL OPERATOR TRAINING-

  • TESTS WILL BE REPEATED SEVERAL TIMES-EACH CREW TRAINED

= TRAINING PROVIDED FOR OPERATIONS OUT-SIDE OF CONTROL ROOM

  • STAFF CONCLUDES CRITERlON 2lS SATISFIED

STAFF EVALUATION (CONT'D) CRITERION 3 - NO UNDUE RISK TO PUBLIC

  • SAFETY ANALYSIS NOT YET SUBMITTED BY TVA
  • STAFF REVIEW OF SPEC lAL PROCEDURES
  • SPECIAL PROCEDURES NOT SELF-SUFFICIENT
  • STAFF CONCLUDES " MASTER" OR " LEAD" DOCUMENT NEEDED
  • " MASTER" DOCUMENT SHOULD:
  • OUTLINE ENTIRE TEST PROGRAM INCLUDING SEQUENCE
  • SPECIFY APPLICABLE EMERGENCY PROCEDURES FOR EACH TEST
  • SPECIFY A RETURM TO NORMAL PLANT SAFETY SYSTEM SETTINGS BETWEEN TESTS
  • SPECIFY THE APPLICABLE ADMINISTRATIVE PROCEDURES

STAFF EVALU ATION (CONT'D.) CRITERlON 4 - LOW RISK TO PLANT = TVA HAS PROPOSED ONLY THOSE TESTS WHICH THEY FEEL SATISFIES CRITERION 4

  • STAFF CONCLUDES CRITERlON 4IS SATISFIED CRITERION 5 - LOW POST-TEST RADIATION LEVELS
  • TVA HAS SUBMITTED A STATEMENT SAYING THAT IMPLEMENTATION OF POSSIBLE FUTURE REQUIREMENTS WILL NOT BE PRECLUDED
  • STAFF CONCLUDES CRITERlON SIS SATISFIED

" Art F0tn ~~ ~ HEN SE010YNi SSCR IERISKE IU) NTLICMLE A"OSTATlG (7) 1.C.8 flRR Irl-Irelli IIEVIEW OF SELECTED EP IP (8) 1.G. TRAirlirlG Dualtic Lav Para TESTitlG IhFillEPLNI fl SECTI0fl I.G; CLOSED) flEEDS DOCUEllTAT10tl - CairoCT TRAltilf1G [p NID STAFF REVIEW O O G

~ PART 2 - flTOL REQUIRGEtHS - AwEADY ISStED WEN SE0lDYAll SSCR IEfEIFJ1E lEl APPLICABLE A"OSTAllS (1) 1.A.1.1 STA l.A.1.1 - STA m NTY fl SQ1E COf1Ef1TS 04 FltlCTI0tlS #1D RESPalSIBILITIES - SIA TRAltliflG COPLETE 1/1/81 FRQi INTEROFFICE REVIEW TE#i. WILL BE RESOLVED PRIOR TO OL iSSUNICE. (2) I.A.1.2 SniFr SUPv. Amitt. IbTIES fl I.A.1.2; QBSED (3) I.ll.l.ll llCBISEE OlSITE 0>ERATiflG EXPERIBlCE EVALDATlal CAPABILITY fl ITBi IS Opal. INTEROFFICE TE#1 BELIEVES LICalSEE'S PROGRAri IS ADEQUATE; ilGEVER, TVA IIAS NOT ESTABLISHED 01-SITE GROUP

  • 00 I.C.1 SHORT-TERfi ACCIDEllT hlALYSIS &

REANALYSIS FOR Ull UNDER REVIEW. RESULTS PROCEDURE REVISI0tl S1100LD BE EXTRAPOLATABLE FRQi NQl-Ull (A) SBLOCA R PIRITS. Ih0UIRDiEllTS VELL-DEFillED; SHOULD BE CQ1PLETE 15-80. B). E R ftED TVA DOCutEllTAT 1 Q1 GUIDELINE #1D l (C) OllER TRAtlSIEilTS =& ACCIDEtlTS SAf1E SCHEDULE AS OR (5) I.C.2 SillFT IhLIEF NID TuRt10VER PROCEDURL3 8. I.C.2 CQ1PLETE

Pu.e Tm 11 01 SE000Ytfl SSER IEEfSlE IUl /PPLICABlE A"D STATLS (6) I.C.3 SilIFT PERSG#lEL RESP 0flSIBILITIES FL SEE I.A.I.2; CQ fLETE (7) 1.C.fl CQlTROL Ib0f1 ACCESS FL I.C.ll; COPLETE (8) II.B.1 ItGRADED CME - PRIMARY SYSTEM blT - PROVIDE DESIG1 fp - IllSTALLATIG1 CQFLETE UU8} (9) II.B.2 DEGRADED CORE - SillELDIllG - PROVIDE DESIG1 FP - PL#1T W D CQfLETE VV81 (10) II.B.3 ItGRADED C@E - SAMPLIllG - IrlTERIll PROCEDURES; FillAL SNfLillG IP DESIGl - PuviT tbD CQfLETE VV81 f c'

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PAos TilREE WEN SE0tr##1 SSCR IERENE IUl /PPLirAIE A"OSTAILS (11) II.D.1 NID II.D 2 ftWEERD_Slfm_ht.VE IEST - CGfilT TO PERFORfWICE TESTS R. II.D.2; CarwTe - TEST PROGRNi COPETE 7/1/81 (12) II.D.5 [hLIEF MlD SAFEW VALVE POSITIQ1 R. II.D.5J F1EED DOCUMEllTATIOff Qi OUALIFICATIQ1 #1D CALIBRATlal (13) II.E.1.2 /Bl IfilTIATIQ1 N1D If1DICAT10fl II.E.1.2; ESSEllTIALLY COPETE; B!A f1EEDS - CUllROL GRADE NJTOSTART NID FLQ1 TO DOCLP1EllT COTIECTION OF FLG4 IllDICATORS TO IflDICATORS R VITAL BUSSES. - SAFETY GRADE 1/1/81 ( 11 0 II.E.3.1 EMERGEllCY POWER FOR Pza llEATERS IP (15) II.E'.fl.1 C0flTAlllMEllT PEllETRATI0fi - DESIG1 EXIElhAL ll2 RECQiBillERS R. NA - CGPLETE Ill!TALIATIOil 1/1/81 - REVIEW PROCEDURES, BASES FOR USE R-

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~., PAM,f00R 'IUl SE0llWNI SSCR IEEIENE 11EM APP _ICABLE N!0 STATLS (17) II.EA.2 CQUAllifUlT ISOLATI0tl IP C01PETE DIVERSE C0flTAlfNEllT ISOLATI0tl SIGIAL (17) II.F.1 ADDITIQlAL ACCIDEtR IhllTORiflG II.F.1 IllSTRttiEllTdTlDil (A) PROCEDJRES FOR QuMITIFY!flG IhEASES 11 Ti!ElilTERIMPROCEDURESFORM0tilTORIflG10DillE (B) C0flTAlt# Tilt PRESSURE lhllTOR 1/1/81 PROVIDED TO T.E STAFF, MlD WILL BE REVIEWED (C) C0flTAlfitDIT WATER l_EVEL IhllTOR PRIOR TO TIE ASCEtlT 10 ST, TESTitlG. (D) C0tlTAlflfalf II h~ tilt R 2 (E) CQlTAltlMEllT ll1-RAllGE PADIAT10tl lhil10R (F) IllGI IWlE lbBE GAS EFFtuErlT lbliT0i : (18) II.F.2 ICC IrlSmreiTS II!F.2 (A)' PROCEDIRES FOR EXISTillG 'IrlSTR. FL EFFECTS OF Ull tilDER REVIEW (B) SUBC00LillG METER Il COMPETE (C) AlALYSIS TO DEECT ICCJ VESSEL EVEL Il COMPETE lilDICATOR DESIGl (D) IllSTALL VESSEL EVEL lilDICATOR (IF 1/1/81 .,z REQUIRED) > j,, /

PAGEflVE WEN SE011W#1 SSER IEEIENE IE APPLICABLE N!D STALLS (19) !!.G BERGEllCY POWER FOR PRESSURIZER FL II.G; COfLETE EQUIPf1EllT (2m III.A.1.1 - lbGRADE l1ERGEllCY PREPARED-PilASED llI.A.1.1 I flESS (21) III.A.1.2 lbGRADE DERGEllCY SUPPORT (A) OlSITE EC - ESTABLISil FL !!EEDS lVA CONITMEtiT Gl SEVERAL Mill 0R ITEMS,

  1. 1D EVEllTUAL RESOLUTIQ10F STAFFillG lbGRADE EC Vl/81

! BED CQ H W OIT (B) ESTABLISil @C fl. 00ffLETE (C) ESTABLIsilEOC Il SEElll.A3;C01PLETE lbGRADEE0C 1/V81 (22) III.D.1.1 SOURCES OLIISIDE CQlTA;ffEIT IP h Il SEEII.F.1; CLOSED (23) III.D.3.3 Ift-PLuiT IIADIATlal IhllTORIll provide illSTmtEllTAT10fl TO DETEIN1flE Ill PLAllT AIRBORflE RAD 1010DiflE CalCEllTRATIG l e ... r-

m. PAar 3 - flRC kTials ~ ~ 9EN SEQUDY#1 SSER IEEFErlE ITEM APPL.ICABlE R!D STATlB (1) I.B.2.2 ftSIretlT IllSPECTOR fl_ I.B.2.2; CarwTe (2) II.B.7 CORAlt#EtR li4ERTitlG IP II.B.7; C0fdTE, FOR fl01 (3) II.B 8 ItGRADED CORE-IhlDiAKillG IP (10 III.A.3.1 lblE OF liff IN DERGEllCIES IV (5) III.A.3.3 CormilCATIGIS fl III.A.3.3; CG PLETE (6) III.B.1 tlRC APPROVAL OF (MERAtl. der,GEtlCY PREPAREDIESS fl SEElll.A.3 (7) III.D.2.fi 0FFSITElhSElEASllREMEllTS IP (til0 ESTABLISilIlD) 9 e

d l - IEW PEWIREfEllTS 3ASED Q1 PEPORT OF SIG PART l 'lEN SE0llT(#1 S7R IEEfB1T ITEM APP ICABlE ND STARE (D CGITROL Pom IhSlal lhVIEW R. IV-1; IhVIEW IllCQfifTE (2) ParR ASCalSial TEST SCIEFARI [1 - l#1TIL IV-2; IFWILLFOLLOW,USillGSEllIORIISIDEllT COP!ETIQ10F IllSPECTOR, AUGiEllTED AS flECESSN1Y BY 011ERS PROGRAM pgg jggy 9 6 e 9

S F R O E W I I E A I VM E I R. M F T F AE TR SP .V I

CHRONOLOGY OF PRE-TMI REVIEW ON SEQUOYAH Application Docketed 10/15/68 Construct Permit Received 5/27/70 DES issued by TVA 10/71 Submit FSAR 1/31/74 FES lssued by TVA 2/74 SER Published 3/79 Draft DES Permit issued 3/15/79 Final DES Permit issued 5/29/79 ACRS MEETINGS Subcommittee Meetings 3/12/79,10/79 Full Committee 4/06/79, 5/11/79, 12/7/79 ACRS Letter 12/11/79

e PRINCIPAL ELEMENTS OF AN OPERATING LICENSE Contains Findings in Accordance With 10 CFR 50.57 Relative to: e Construction e Operation e Public Health & Safety e Common Defense & Security e Technical & Financial Qualifications e Balancing Benefits Against Environmental & Other Costs License Authorizes e Possession, Use & Operation of Facility e Possession, Use & Storage of Special Nuclear (Byproduct & Source) Materials License Conditions e Maximum Power Level e Technical Specifications Special Restrictions e Special Test Program (<5% Power) e Environmental e Physical Security Plan

SEQUOYAH PRE-TMI 2 ISSUES

1. Bolted Connections
21. Inservice inspection of SG Tubes
2. Seismic Qualification of 18C Equipment
22. Cold Shutdown
3. Fire Protection
23. Desian of SG and Pressurizer Supports
4. Radiolo0 cal Emer0ency Plan
24. Environmental Qualification of g/ Equipment i
5. Plant Trip Test
25. Upper Head injection Tests
6. ATWS Interim Procedures
26. Containment Sump
7. Foundations
27. Bypassed Safety injection Si nal 0
8. Reactor Vessel Closure Head
28. Loss-of-Coolant Accident Analysis
9. Guide Thimble Tubes
29. Response Time Testin0
10. Grid Straps
30. Isolation Valve Interlocks
11. Control Spiders
31. Post-Accident Monitoring Separation Criteria
12. Rod Drop Transient
32. Environmental Qual. of Bal.-of-Plant Equipment
13. Operator Training
33. Diesel Generator & Remote Shutdown Testing
14. By-Pass Leakage
34. Boron Dilution
15. Secondary Water Chemistry
35. Long-Term Effects of Steam Line Break
16. Steam Generator Level Instrumentation
36. Seismic Desian of Structures & Components
17. Containment Overpressurization Due to MSLB
37. Inservice Testina After Commercial Operation
18. Non-Safety Systems
38. Reactor Vessel Overpressurization
10. Single Failure in RHR
39. Loose Parts Monitor
20. Pressure-Temperature Limits

PE-IPJ PATE5 FIVE OriSTANDING ISSUES FRCM 3-79 ER IHIRTEEN ADDITIONAL t%TTERS ARCSE FROM 3-79 TO DATE SEVDJTr.Ett CalFIPPATORY f%TTERS WERE CITED IN ER RXJR POSITIONS ESTABLISHED C31CERNING WORK TO BE DONE AFTER CL ISSUANCE IGTALCF39 PRE-lIllMATTERS

STATLS 5 CU13 TRITE!G ISSLES FiTF. SER 1. BOLTEDCCNNECTIG4S(SEC.3.9.2) INTERCFFICE Te#4 REVIEWING GSJERICALLY; C31CLUSICt1 AT PRESENT IS THAT t%TTER IS SETILED AT LEAST FOR LCW-POWER OPERATIQ1. 2. SEISMIC CUALIFICATIG1 (SEC. 7.2.2; 7.8.D CDNFIPPATORY WORK t1EEDED BY IVAJ LOW-POWER CPEPATIOJ ACCEPTABLE. 3. FIRE PROTECTIO 1 (SEC. 9.5) Cai)Lc.TE. 4. PADIOLOGICAL bERGSICY PLAN (SEC. 13.3) DISCUSSED IN IMI SECTIQ1. 5. ACCT uiCE CRITERIA FOR Ptn4T TRIP IEST (SEC.14.6) CLCSED. 4

i I i i l i illIPEI fEI ITEFS 1, ANS INTERIM PROCEDURES (SEC. 15.2) TOBERESOLVEDPRIORTOGOINGABOVE5%PGER. 2. R)UNDATICt4S (SEC. 2.6) 1 PESOLVED. 3. PEACTCR VESSEL CLOSURE HEAD (SEC 3.2) FLAW SIZE ACCEPTABLE BASED ON NJALYSIS; 13I NEEDe; RESOL'ED. 4. GoIDe THIrmte tunes (SEC 4.2) SURVEldR4CE f1EEDED TO CBSERVE WR Of WIDE WIfGLE TUEE WALLSJ RESOLVED. 5. GRInSTPas(SEC.4.2) PESOLVED BY PROCEDURAL CF#1GES. 6. CamOL SPIDERS (SEC. 4.2) PESOLVED. 7. Pen Ihop TPR1SIENT (SEC 4.2) PESOL'KD BY ROD INSERTION LIMITS ABOVE E PG'ER. l

!Erl ITE?S CGTINtED 8. OPERATORIRAINING(SEC.13.2) DISCUSSEDINIMISECTION. 9. BYPASS LEAKAGE (SEC.15.4.D ID. SECONDARY WATER CHCMISTRY (SEC. 5.3.D FESCLVED. 11. STEM C91ERATOR Levet INSTRtPo1TATIcti (SEC. 7.2) FEScLVED. 32. CCNTAlfPEIT Ove=oRESSURIZATION DUC TO ItSl3 (SEC.15.3.3) PEScLvED. 13. f!Cf1SAFEW SYSTEMS (SEC.15.3.3) TVA PsSecnSE To IE NOTICE 79-22 ACCEPTAstE.

SRh?{iEJJ! CQ! FIR'ATORf ISSLES 1. SInct= FAILURE In fHR SYSTEM (SEC. 5.3.2) RESOLVED BY CPERATOR ACTIQ 1 CR NEW AURb TO M011 TOR FOR LCH-FLOf CONDITIO4S. 2. P-T LIMITS coa HEATUP, QXEN1 (SEC. 5.2.3)

PESOLVED, 3.

ISI SG Tunes (SEC, 5.2.6) RESCLVED. 4, COLD SHUECW1 USING SAFETY 4ADE EQUIPMBE (SEC. 5,3.2)

PESOLVED, 5,

Nsre4 cc SG, PZR SuPmRTs (SEC. 3.9.1; 5.2)

FESCLVED, 6.

CanAlnma PESPO4SE TD Sl3: EWIRGEITAL QUALIFICATI0ls CF ECUIPMEIT (SECS.6.2.1;7.2.2;7.8.2) MCRE WORK TO BE DONE 01 CU/1.IFICATIQ4S; P.ESCLVED FOR s 5%. 7. lHI Pas-OP IEsTS (SEC. 6,3,4)

PESCLVED,

GIlFIFAT0hY ISStES CCffTIt!'E 8. COFAlfPBF S&P (SEC. 6.3.4) REscean; HCWEVER, FURTHER WORK CORINUEs at LEI # A-43 wRT CORE ELOCKAGE FRO 4 DESRIS SUCH AS INSULATIQ4. 9. BYPASSED SI SIGtAL (SEC. 6.3.5) PESCO/ED. 10. LCG (SEC.6.3.5;15.3.2) FESOLVED. 11. PEsponsE Tim Testing (SEC. 7.2.2) RESCLVED. 12. ISCLATICet VALVE INTE9 LOCKS MD PosITial INDICATIO4 (SEC. 7.3.2) PESOLVED. 13. Post-AcCImF MmITORING SEDARATION CRITaIA (SEC. 7.5.2) PESCesD. 14. EWIROFEFAL CUALIFICATIQ10F E@ EQUIPPE (SEC 7.8.2) PESOLVED. 15. DG mD PEMOTE SHUT 1w TESTmG (SEC.14.0) PESCUED. 16. Ecm4 DILurlaa (SEC.15.2)

MIFPATOR( ISSLES CmTINtED 17, Lam-Tem EP= CTS CF Sl3 (SEC.14,3,3) PESOLVED.

FOUR POST-CL PCSITICS 1. SEISMIC I)ESIG1 OF STRUCTURES #4D COPOE4TS (SEC. 2.5) STAFF AUDITS Of SE!SMIC MARGIN TO CONTINUE, PER ACES REGUEST. 2. IST Arma CcrtraICAL (>= NATION (SEC. 3.9.1) CODITION LICENSE TO ASSURE ACCEPTABLE ISI PROGRN4 FOR PUMPS NO VALVES. 3. REACTOR VESSEL OEPPCESSURIZATION (SEC. 5.2.2) LICENSE WILL EE CONDITIO4ED TO REQUIRE INSTALLATIO4 0F MORE ECUIPMENT BY END OF FIRST REFUELING. 4. EmSE Pears Mcr41TcR (SEC. 5.2.8) SYSTEM WILL BE INSTALLD PRIOR TO LOW-fCWER TEST PROGRNi.

s to O 2 O D JO 2 OO

SLMSR/ A. 5 01rSTmotm ISSUES ALL RESOLVED, AT LEAST FOR LCW-c0WER (15D ceERATlat. B. 13 NEW ITEus ALL RESOLVED, AT LEAST FOR LOW-PCWER OPEMTION. C. 17C01FIPPATORYISSUES ALL RESOL'ED, AT LEAST FOR LCW-POWER TERATICN. D. 4 PcST-OL % itsS WILL BE RESOLVED EITHER BY LICBISE CCNDITIG4S OR BY STAFF EFFORT.

UNRESOLVED SAFETY ISSUES OF THE SEQUdYAH NUCLEAR PLANT 1. A-1 WATER HAMMER 2. A-2 ASYMMETRIC BLOWDOWN LOADS ON PWR PRIMARY SYSTEMS 3. A-3 WESTINGHOUSE STEAM GENERATOR TUBE INTEGRITY 4. A-9 ATWS 5. A-11 REACTOR VESSEL MATERIALS TOUGHNESS 6. A-12 FRACTURE TOUGHNESS OF STEAM GENERATOR AND RFACTOR COOLANT PUMP SUPPORTS 7. A-17 SYSTEMS ;NTERACTIONS IN NUCLEAR POWER PLANTS 8. A-36 HEAVY LOADS NEAR SPENT FUEL 9. A-40 SEISMIC DESIGN CRITERIA 10. A-43 CONTAINMENT EMERGENCY SUMP RELIABILITY 11. A-44 STATION BLACKOUT

ASSIGMENT OF NRR PERSONNEL FOR THE SEQUOYAH STARTUP AND LOW POWER TEST PROGRAM Major Load initial Power Physics Start Special Complete Special Milestona Fuel Criticality Tests Tests Tests Weeks After OL 0 2 9 16 18 LPM ORPM QA (Startup) Tech Spec CPB (Physics) RSB/AB ICSB/PSB ASB CPB (Fuel) .}}

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