ML20216D084
| ML20216D084 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/03/1997 |
| From: | Jaudon J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 9709090212 | |
| Download: ML20216D084 (27) | |
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UNITED STATES q'o,, NUCLEAR REGULATORY COMMISSION 8' I REGION 11 h ATLANTA FEDERAL CENTER L / '""E'eSZ"!BMS"O*'" September 3< 1997 MEMORANDUM-TO: File e::La *VT FROM: Joh P. Jaudon. O ector Division of Reacto Safety
SUBJECT:
MINUTES OF THE CRYSTAL RIVER 3 RESTART PANEL MEETING HELD AUGUST 20. 1997 This provides the' record of the meeting of the NRC Restart Panel for the Crystal River 3 facility which was held onsite. August 20, 1997. The panel members present for the meeting were: Johns P. Jaudon. Chairman Kerry D Landis Stephen J. Cahill L. Ragshaven Others present were: Son Ninh Robert P. Schin ! The panel reviewed the open inspection item list, a copy of which is attached. The Panel noted that the rate of closure of items is slower than expected and - discussed reasons for this. R. Schin reported that for the most part, closure packages =have not ben ready for closure. It was also reported that the recent inspections of the change review process (i.e.,10 CFR 50.59 changes) produced satisfactory results: these results indicated that the Licensee's processes to ' make changes had been adequately implemented. The recently completed
- inspection of the design process had produced results-characterized as good.
The Parcl also noted that Licensee's )rojected restart date remains mid-Dacember. The Panel concluded that t11s date was challenging but potentially ac.n.:. ble. _ The Par,al-also noted that the submittal and approval of licensing issues appec. rat to be the greatest known challenge. There are 31 licensing issues identified'at this time.- but only 12 have been docketed and started the review / process. The status of. licensing amendment submittals is attached for information. The Panel noted that the major inspection activities which were upcoming were
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the Sa ty System Functional Inspection (SSFI). The systems chosen as the targat' for that inspection were the high and low pressure injection systems. The le er for that inspection will be W. Holland, who replaced P. Kellog, who has bet.1 assigned to-the Clinton DET effort. The regional participants for DR ADO O 00 02 G PDR h hhh ' 1 i
iI pluul l File 2 the SSFI will be R. Schin. R. Moore, and N. Merrweather. NRR participants identified are R.- Landry-and K. Mortensen.
-The-Panel also noted that FSAR Revision 23 had been sent- to .he NRC in
-November 1996. The quality of the revision was considered )oor, but the license has taken actions to correct deficiencies in the su)mittal, and these revisions will be included in Revision 24. expected to be sent to the NRC in November 1997. Revision 24 is also expected to contain information reflecting the design changes made during the current outage Attachments: As stated Docket: 50-302 cc w/att: Panel Members L. Reyes, RA S. Collins. NRR B. Mallett ADRA-B.-Boger. NRR J. Johnson. RII C. Casto. DRS L. Plisco. DRP S. Ninh.-DRP R. Schin. DRS
Attachment A , CRYSTAL RIVER 3 ISSUES CHECKLIST R ITEMS (TO BE INSPECTED BY THE NRC BEFORE RESTART) Status as of August 21, 1997 The original Crystal River Restart Panel meeting on November 13, 1996 developed seven general areas under which the restart issues will be grouped. Those seven areas are:
- 1. Knowledge of design and-licensing bases and adequacy of design margin
- 2. Regulatory knowledge and perspective
- 3. Operator performance and knowledge
- 4. Marginally effective engineering organization
- 5. Management oversight; including quality assurance, self assessment, and corrective action
- 6. Corrective actions for NRC violations
- 7. Other Total Restart (R) Items: 152
#'Open 101 1
# Closed 51 Sources for issues include: IFS, SIMS, NUREG 1435 IStatus of Safety Issues at Licensed Power Plants), Resident
- s OIL, FM's OIL IUTE: Open allegations, OI investigations, and emerging / draft issues are not contained in this list.
NOTE: An Asterisk (*) in far right column denotes a change froma previously issued report. ISSUE DESCRIPTION AREA NRC LEAD IR/SER LICENSEE C000EENTS IIRC CLOSURE STATUS STATUS LICENSEE *S RESTART LIST OF DESIGN-RELATED ISSUES (D.I.s)(per 10/20/96 Itr fra FPC) CR3 D.I. 1 HPI pump recirculation to the makeup tank 1 RI Cahill D-1 LER 97-08. R See URI 96-01-02, IFI 96-17-02, IR 96-17 CR3 D.I. 2 HPI system modifications to improve SBLOCA margins 1 Schin/NRR D-2 See URI 9f-01-02, LER R 96-06, IR 96-17 TS Change Request 210 ATTACHMENT A
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.s DESCRIPTIDst ARSA MutC LEAD " IO/suut LICaness commmurrs sutC .
2SSUE cumma sTAms sTAns CR3 D.I. 3 LPI pump sik. ion time (NRR for boron precip review) 1~ RI Cooper / D-3 See URI 96-201-015 IR R.' NRR R-9 96-17 . Reactor building spray pump 1B NPSH 1 RI Sanches D-4 See URI 96-201-C2, IR R CRJ D.I. 4 96-17 Emergency feedwater system upgrades and diesel generator load 1 Schin D-5 Series See URI 96-12-01;' .I R CR3 D.I. 5 ' 96-12-02, IR 96-11 impact D-6 Series See EEI 96-12-02, IR " R CR3 D.I. 6 Emergency diesel generator loading 1 Fillion/ 96-17, LER 96-20, LER Schin 96-25 Failure modes and effects of loss of DC power 1 M. Miller D-7 See URI 96-12-01,' LER R CR3 D.I. 7 96-07. IR 96-17 ceneric tetter 96-06 (Thermal overpressure protection for 1 RI Cahill/ D-9 See IR 96-12,. LER 97- R CR3 D.I. 8 04 Cont ainment piping, penetrations, and coolers) Crowley LICENSEE
- s OTHER RESTART ITERES RMG 29/30 Seismic mounting of HR Rad Monitor 1 RI Bartley D-19 Inspected 7/20 R
- BWST NPSH NPSH concern with ECCS pumps when SFP pumps are running in 1 Thomas D-10 Review SP-630 test R BWS and Recire results following FJT event MJV-21 Section XI leakage testing 1 Schin R-21 PC 97-1954 R F2VE 1mWa* OP COtfTINUIlO0 C00FCERN, WITE IPAP m-_.- -ED INSPBCTICIE AND RII -- - ---- ADDITICBr5 OP-2 New CA system R Management - NRC inspect Problem Identifications focusing on CA audit s 5 RI Cahill/ IR 97-07 Oversight - and the orcblem retorting syst em . - Increased inspection of QA Thomas OP-3 inspected ist IR 97-07.
IPAP Problem Analysis and Evaluations focusing on root cause 1 VIO (97-07-01) needs evaluations. follow up. CA audits Recommended good - discussed irs Inspection various reports in
*97.
Marginally - NRC inspect Engineering Problem Identification and 4 Schin OP-4 $0.59 R Effective Resolutions with emphasis on li ensee evaluations for CP-6 Engineering significant issues and work backloos. Organization - Also inspect Quality of Engineersngs with emphasis on to - IPAP CFR 50.59 screening and safety evaluatione, accuraev of tee Recottnended FSAR, and manage-ent overaight. Inspect the licensee's FSAR Inspect ion keview Project and assess the identified FSAR errors. 2
4 Isses' DesemIPTroer Amma mute z.ano zo/sma r.2csmasas commerrs asse . ~ CIASUIts STATUS status 1ack of - NRC inspect Engineering Safety Focuss focusing on crecer - 1 Schin- D-13 R Ddequate identification of discrecancies with the plant's desion basis D-15 ,, Knowledge of in t he correct ive acticn eystem. .. D- 15 " the Design - Also inspect Engineering Proclee Identification and CP-7 Basis - IPAP Resolutions, focusing on rrograms fer identifying design basis OP-8 Recommended issues and capturing them 2n the corree-ive act sen crogram. D-23 Inspection - Also inspect Quality of Engineerings focusing on sens it ivit v/underst andi ng by the engineerino/licensina staf f of tne olant s desian basis. . .
- Also assess the design maroin, including the licensee's
=ertere of ennotrinn- reviews lack of - NRC inspect 50.59s, coarabilit y, report abili t y 2 Schin CP-4 R Regulatory OP-5 Knowledge and Compliance with Regulations -
IFAP Recommended inspection
- NRC inspect Safety Focus; focusing on communication within 3 RI Cahill 0-4 Will evaluate CPS R Operator Improvement Plan and Perforecace - operations, communicat ion with other site groups, and overtime success of recent IFAP changes in CPS Recommended erganiration Inspection _
INSPECTOR FOLI4tfDP SYSTutt URI 95-02-02 Control room habitability envelope leakage. Excessive 1 Schin/NRR R-12 See TIA 95003: FPC TS R leakage paths through doors, dampers, and drains due to - Change Request No. 206 design errors and lack of surveillances/ preventive of 6/28/96: IERs 96-04, 94-10, 95-01 95-maintenance 04-01. 95-09; irs 95-02 95-09, 95-11. 95-16, 95-21, 97-05, 91-07: FFC ltre. of 5/26/95 and 10/23/95. VIO 94-25-01
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n... .. . URIl96e01-021,
- Discrepancies in the high pressure injection design basis;. .r. 1 [ Schib !R 97-07? D+9(D+1). See CR3 D. Inly - RJC-:
. analysis
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Discrepancies M;the EDSD'and the FSAR:regarding;the
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Design concerns:with main steam line hangere used'.in seiselc r, 1' ': RIP > ;2R 97+01': D-514 see VIG M-99-01tg Rf CJ
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'URI $6-06t037 Non-safety related Ltransfer swit.ch used in ES status E " "1f: '
indicating light eircuitry'-" D
.beergencyS Feedwaterflew NPSR to bbth
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pumps Ne to postulated? I1l i Schin! ;IR 96 D-17q See'CR3 D;10 Ss; , Rf _C l UDI 9'6,12-01f. 7s EEI'M ' gg ' ' '
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tHtI 961bO3; : Failure to: conduct' required..Technicci-Specificationi . - % 4L E Millerj . . .IR.97-42.'e ells See IR 9h el^
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surveillance testing on safety related circuitry (GL M-CID 3
l e 125UE DESCRIFTICN aWTR NRC LEAD 20/8E1 LICENSEE CCsWEE3rTS SERC . C14SURE STATUS STATUS i URI 96-201-S1 Iong term plant cooldewn following a small break LOCA 1 RI Cooper / D-3 See CR3 D.I. J; See IR R ] assuming a single failure in the decay heat drop line NRR 96-11. NRR taking , ! responsit iltty for this it m. URI 96-201-02 NPSH for building spray pu g has very little margin, and some 1 RI Sanchez D-4 See CR3 D.I. 4 R calculat ion f actors were tyynconservat ive Operating curves 16, 17, and 18 in CP-103B are not validated 4 Hopper 0-1 R LPI 96-201-03 by licensee See IR 96-08 IR 97-01 R URI 96-201-04 Nonsafety-related positioners on safety-related valves 1 Thomas D-10 R-7 URI 96-201-05 Service water system heat loade did'no tconsider maximum 1 Crowley IR 96-19' O-1 See EB! 96-19-OF R, C . input heat (GP-1019, Curve 15}- EEG not protected against water spray from failure of fire 1 Fillion/ D-52 R LPI 96-201-07 protection deluge system in EDG roem M. Miller / W. Miller URI 97-Obo6, EPI system design,Ilicensing basis,' and TS concerns ~ 'l . Schin IR 97-05 See IR 97-06, EA 97- R, C 142 (01023! URI 97-01;08 Adequacy of proc (dures to take the plant from hot standby to . 2 Thomas. IR 97-02 R. C cold shutdown from curside the control room TAppendix R) Deletien of water quality requirements f rom the FSAR 2 Thomas /NRR OP-5-B R URI 97-02-02 50.59 saf ety evaluation does not address oper& tion of the 1 Thomas / OP-OSD See LER 97-10 R LTI 97-05-02 atmospheric dump valves f rom remote shutdown panel during an Raghavan OP-50 Appendix R fire event LER and VIO not supplemented by date stated in licensee 2 Thomas CP-32 Review commitment R UR.! 97-05-04 rerponse trackiry; system URI 97-07 03 Peactor building liner plate degradation 7 Blake M-12 See IR 97-08 R URI 97-07-04 Unanalyzed combustible burden in reactor bldg HVAC ductwork 7 Blake M-13 See IR 97-08 R
- LER 95-13-01 Design deficiency may cause makeup tank vortexing resulting l Mellen .IR'97-G5 D'-48 LER 95-13-00 closed in R, C in' failure to meet Appendix R requirements' IR 94-06 LER 96-18-00, Failure to verify RB penetrations closed per TS 1 RI Cooper 0-2 See EA 94-365 R LER 96-18-01 VIO B (C20111 3 RI Cahill 0-15 R LER 96-21-00 Delayed entry into t echnical specification required action involving an inoperable React or Protect ion Syst*m channel LER 96-22-00, Design error regarding hot shorts result s in operation 1 M. Miller D-11D R LER 96 22-01 outside Arpendix R design basis LER 97-05-00 Unanalyzed condition re small break LOCA & EFW 1 Schin/NRR CP-09A See D.I.2 R LER 97-09-00, Inadequate design resulted in RCP lubricating oil collection 1 W. Miller / D-57 See VIO 96-15-02 R LER 97-09-01 system being out side 10 CFR 50 requir*ments jaghavan D-06A R LER 97-13-00 Functional testing of EDG-1A room temperature may exceed 1 M. Miller 120*F 4
ISSUI DESCRIPTIOff AREA NRC LEAD 22/SER LICENSEE CODG3rTS FRC - CLOSURE STATt'$ STATUS See D.I 9, LER 97-12 R
- LER 97-14-00 RB penetrations do not meet code requirements - outside 4 RI Cahill CP-16 design basis ,
MUV-40, 41., 505 incapable of performing safety function post- 4 RI Sanchez D-67 R LER 97-15-00 1ACA R
- LER 97-16-00 RB Coatings not included in sump calculation 4 Blake D-71 LER 97-17-00 Inadequate electrical separation of the High Pressure Flow 7 RI R Indicators R
- LER 97-16-00 High Energy Line Bresk could result in loss of chilled water 1 Schin t o cent rol complex vent ilat ion system R
- LER 97-19-00 Elevated EDG supply air temps due to EDG radiator discharge 1 RI air recirculation effect Four examples of f ailure to follow refueling procedure FP-233 3 Hopper, 04 See EA 91-316 101014)' R, C EEI 96-10-01 EEI 96-10 02 'Fa11ure to assure root cau6e analysis and corrective. actions 5 Hopper. O-5 See EA 96-316102c141 R. C taken to preclude repetition were adequate after refuel incident (no PR issued)
EEI 96-12-02 EDG loading USQs due to inadequate 10 CR 50.59 evaluationsi
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4 Schin/ R2 D-6, D- See EA 96-365, 96-465, R. C three examples .- {one modification in two procedure changes) ' FAllion 14, D-15, 96-527, VIO A (01012i OP-S 01022, C1032). See-CR3 D.I. 52 CR3 D.I.'6 LFR 96-20 Inadequate corrective actions for 10 CFR 5c159 evaluation. Schln CP 14 See EA 96-365 et al, R, C EHI 96-12 03. S VIO C (030131 errors; two examples Use of tanverified calculations to support modifications. 4 Schin OP-6, D-14 See EA 96-365 et al, R. C EEI 94-12-04 NRC inspect licensee's extent of condition reviews, VIO B (0201 M Three' inadequate procedures .for containment' penetration, 4 RI' CP-15 See EA 96-365 et al., R, C EEI 96-19 01 surveillances ' VIO B (02013) RI. CP 16 See EA 94-365 et al, R, C EEI 96-19-02 Inadequate corrective actions for inadequate containment 1 VIO C (03013)
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penetration surveillances' EEI $6-19-03 EFW NPSFI USQ due 'to inadequate 10 Cm ED 59. safety evaluation - l'. Schin D See EA 96-365 et alf VIO A 1D10431, See IR R. C' for a modification - 97 04 EEI'96-19-04 Failure to update applicable design' docuteents to' incorporate 1 1 Thomas- D- 3 9 - See EA 96-165 et al, R. C
- EFW design information (EFP-2 assumed operating when EFP-1 VIO 3 102013)'
trips at 500# RCS pressuren Failure to include applicable design'information in the 1L Thomas' D-40 See EA 96-365 et al, R, C EEI 96-19-05 design input requirements for an EFW niadification (EFP-2 ' VIO 5 t020131 continuing to operate efter EFP-1 trips at 500# RCS pressure; and hydraulic requirements)' EEI 9449-06 EFw USQ due to removing the autenatic open signal.from AEVJ 1. Thomas R-4 See E4 96-365 et al, R. C 204, reducing the reliability of EFP-2 VIO A (010521 5 l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
2SSUI DESCRIPTIcst AREA NRC LEAD IO/SER LICENSEE COBeefTS WRC , CicSURE STATUS STATUS Inadequate 50.59 evaluation for post-loCA boren precipitation 1 Crowley- CP-17 See EA 96-365 et al, R, C . EEI 96-19-07-- ' VIO A 101062), Verify control' , procedures and documentation adequate prier to restart . ERI 96-19-08 Error in design calculations for SW system heat loads 1- Crowley . D-28 See FE 36-365 et al, R, C VIO B (C2013}- EEI 97-06-01 Inadequate safety evaluations for added operator actions for 1 See EA 97-162. VIO R, C design basis SBLOCA mitigation 01013 EE! 97-09-01 Unreviewed safety question involving added EDG protective 4 Schin D-12 See EA 97-330 R trips EA 95-16 Use of non-conservative trip setpoints for safety-related 6, 1 Mellen OP-13 See IR 95-16 IR 95- K VIO 01013, equipment (SLIII) . Additional examples identified in IR 95- 21, IR 97-01, IR 97-C2 01023, 01033, 16. LER 94-06 01043 (was IEI 95-02-04i Itice ir. stances where operators violated procedures for MUT 6, 3 .. Schin IR 97-07 R-13 See IR 96-04, LER 94- R, C EA 95-126, VIO I.Ac pressure / level (SLIII).
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09 - 101013) (was EEI 95-22-01) EA 95-126, Conduct of unauthorized tests of MtJT without 10 CFR $0.59 ' 6, 3 .- Schin IR 97 .CP-10 See IR 96 04 R. C VIO I.R evaluation-(SLIII); Additional examples (four tests) -(02013)-{was: identified in 1/18/96 letter titled EA 95-126 and EA 96-18$). EEI 95-22-02)' fSee URI 96-04-08) EA 95-126, Failure to take adequate corrective actions for operator- 6; 5 Schin IR 97-07 CP-11 ' R. C VIO I.C.1 concerns regarding OP-103B,' Curve 8, 'for MTI pressure / level... (03013) (was . limits (SLIIII ' ESI 95+22-03) Corrective actions for an inadegaate Curve 8 (two STI's and a 6, S RI Cooper / O-1 R EA 95-126 VIO I.C.2 revised Curve 8A & 8B) were also incorrect (SLIII) Schin (04013) iwas EEI 95-22-03) EA 95-126, Design controls failed to ensure adequate safety margin for 6, 1 RI Cooper / CP-6 R VIO I.D.1 ifPI pumps for certain LOCA scenarios (SLIII) Schin (05013) twas EEI 95-22-04) EA 95-126, Swapover of ECCS pumps' suction from BWST (at five feet} to , 6. 1- R1 Cooper /' .IR 97-07 .D-15 R C VIO I.D.2e reactor building sump.was. inadequate'(ELIIIli. Schin (36013) (was EHI 95-22-04) EA 55 d26, 'ECPs allowed single LFI pump.to supply two HPI pumps, with. ~ ' S i : l' . .RI Cooper /- IR.97-07 D-36 R.C UIO II.A . insuf ficient NPSif for' LPI pump (SL111) Schin . (07013) (was EEI 95-22 04) EA 95-126, Failure f.o take adequate corrective actions for tank 6, S RI Cooper CP-12 R VIO II.B volumes / level / suction point (SLIV) 100014) (was EE1 95-22 03) 6
IS3UE DESCRIPTICII- AREE 3E;C LERD IR/SER LIC WBER COBEWITS EEtC ' .. - CIASURE STATUS ST&TUS D-37' R *- EA 95-126, Failure to ensure fire water storage tank contained adequate 6, 1 RI Cooper VIO II.C volume of water (SLIV) . (09014) (was EE! 95-22 04P
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M EA 96-316) Pour examp;1es ofjfailure to(follow refueling procedute FPr203 : 3 .[ -Hopper [. . { 3t 97f' 0-4 q - s REC"
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EDG loading USQs due to inadequate 10 CFR 50.59 evaluations; 4 Schin/ D-6 See CR3 D.I. 5 CR3 R-EA 96-365 96-465, 96- three examples (one modification & two procedure changes) Fillion D-14 D.I. 6 527 VIO A D-15 See LER 96-24 and 96-(01012, CP-5 20 01022, and R-2 01032). (was EEI 96-12-02 EA 96-365 et EFid NPSH USQ due to inadequate 10 CFR 50.59. safety evaluation 1 Schin D-38 See LER 97-01 R al, VIO A for a modification (01042). (was EE! 96-19-031 EFW USO due to removing the automatic open signal from ASV- 1 Thomas R-4A See IR 97-07 R EA 96-365 et al, VIO A 204, reducing the reliability of EFP-2 (03052). (was EEI 96-19 061 EA 96 365 et Inadequate 50.59 evaluation for post-LOCA boron precipitation 1 RI Cooper OP-17 Verify procedures and R al, VIO A control documentation adequate prior to restart. (01C62). (was EEI 96-19-07) Use of unverified calculations to support modifications, 4 Schin D-14 R EA 96-365 et al, VIO B NRC inspect licensee's extent of condition reviews. CP-6 (02013). (was EEI 96-12-04) Three inadequate procedures for containment penetration 4 RI Cooper OP-15 R EA 96-365 et al, VIO B surveillances (02013). twas EEI 96-19-01) See IR 97-07 R EA 96-365 et Failure to update applicable design' documents to incorporate 1 Thomas D-39 al, VIO B EFW design information (EFP-2 assumed operating when EFP-1 (02013). trips at 500# RCS pressure) (was EEI 96-19-04) Failure to include applicable design information in the 1 Thomas D-40 See IR 97-07 R EA 96-365 et al, VIO B design input requirements for an EFW modification (EFP-2 (02013). continuing to operate af ter EFP-1 trips at 5000 RCS pressure (was EEI 96- and hydraulic requirements) 19-05) 7
t + ISSUE DESCRIPTIOgg masa IntC LEAD IR/SEE LICENSEE CassiBrTS 35tc - - CIASURE STATUS STATUS EA 96-365 et Error in design calculations for SW system heat Icada 1 Crowley/ D-20 R I al, VIO B Mellen , (02013). (eas EEI 96-19-08) EA 96-365 et Inadequate corrective actions for 10 CFR 50.59 evaluation 5 Schin CP-2 R al, VIO C errors; two examples CP-2A (03013). CP-14 (was EEI 96-12-03) EA 96-365 et Inadequate corrective actions for inadequate containment 1 BI Cooper CP-16 R al, VIO C penetration surveillances (03013), (was EEI 96-19 02) EA 97-094 Failure to eport an unanalyzed condition that significantly 2 Schin/ D-S See LER 97-001, IR 97- R
- VIO A2 (01023) compromised plant safety. Inadequate NPSH for EFW pump RI Cahill 04, IR 97-08 (was EEI 97-04-01)
EA 97-162, Inadequate safety evaluations for added operator actions for 1 Schin CP-5C R VIO 01013 design basis SBLOCA mitigation (was EEI 97-06-01)
.VIO.93-16A 07; 'Inadequete ROP arsi kP procchures) 6, 'liopper : IR 97J- 0-3 :. . See IR 96-04, IFI 96+'. R C 300? 04,03,'IR 96-CG,11FI:~
' CP-19 l.
95-08-03' VIO 95-16-03 Inadequate procedure for operation of the makeup pump 1A 6, 1 RI Cahill 0-8A See LER 96-10, LER 95- R cooling water 10 VIO 95-21-03 Failure to isolate the class IE from the non-class 1E 6, 1 Thomas / D-30 See LER 95-25, LER 96- R electrical circuitry for the RB purge and mini-purge valves RI 02, IR 97-01, IR 97-02, IR 97-05 VIO 96-01-01 Inadequate corrective action for HPI flow indication problem 6, 5 RI Cooper D-53 See LER 96-05 R VIO 96-01-06 Failure to correctly translate design basis of SW system into 6, 1 RI Sanchez D-54 See LER 95-17 R procedures, drawings, and instructions
- Faiiure to take'prcept corrective- actioni in revising ? 6,' 5f IR 97; O-9 j R,1 C ifIn 96i04-02: 4 '
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procedure VP-580/TPlantLSafety verification?(for STAst.,: 'Y7s;
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300;
~580 contained outdated and incorrect informationb
' Failure:to create alPR and OCR.foridamaged main-steam'line. '6, 57 RIi .IR 97-01 O-10. l , See TAI 96-OS-02s ' See ' R;: C VIO9655-d17 0 ' ' " '
Raghavan :!R 97-02 ; IR'97-02 hangars
'Failuretofollowprocedures[for'bpdating.designbasisi:! 6,: 4 ( Crowleyf -IR 97A01 CP-8,.D-55" R, C =-
'VIO 96'05 05L
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docuwnts '
' Inadequate'receivinglicapectionsfortatterychargers'.ivendorh (6[42 [IR'97 CP-20 ; R, - C :
VIO 96-05e07[ ' ' ' ' - '
' Echin $
tests) ' '
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R. C . VIC'96-05 08: Failure to fol1ow' purchasing proceddres for; inverters : 6,( 4 ? Schin; 'IR 97_-01< CP-21
- VIO 96.-06-02C JNoprochdurefor-deminerhlizedwaterf1bshperformedbyh ^- ' ^ ' ' - ~ -
- 6, [3 i Ri l- (IR 97-02? CPr22f R,- . C :.
eperators on borto aefd addition'Iines*
.VID 96-06-04;.J No evaluation' on non-TSAR . vital battery chargericonfiguration (:. . 6)f 4 f RI. Cooper $, 'IR 97-09:. R218 .' - R, C* a e
- 1 7
25573 DESCRIPTION REFE NRC LEAD IR/SEE LICENSEE CtssSNTS IMC - CLOSURE STATtrS STATUS VIO 96-06-07 : PR not ' initiated to resolve CREYS test f ailure 6 5 Lenahan/ IR 97-02 CP-13 R, C ] crowley VIO 96-08-01 Corrective action not taken on make-tp system audit findings 6, 5 RI Cahill CP-24 R t
& excessive vibration on spent fuel pool pump cooling fan motor ;
I V!O 96-09 03 Failure to perform a 10 CFR S3 59 safety evaluation for . 6, 3 Thones IR 97-02 CP-25 R, C- ! I
~
changes to procedures described in the FSAR for cocitrolling dissolved hydrcqen concentration in the RCS VIO 96-09-04' Failure to update operating curves to reflect 198f power - 6, 4 Thomas IR 97-02 CP-26 R. C cprate VIO 96-09-05 Failure to incorporate design change of MUV-64 into 6, 4 Thomas / CP-27 R operations procedures Crowley VIO 96-09-06 Three exampl(s of design control errors (erroneous 6, & RI Cooper CP-6 R calculation input s and ISI boundary) VIO 96-09-07 Untimely corrective actions f or the EPIC system concerns and 6, 5 Thomas CP-28 See IR 97-01 R problems VIO 96-11-04 Reactor building sump not construc~ ed in accordance with 6, 1 RI Cooper D-56 See IR 97-02 R approved const ruct ion drawings VIO 96-15-02 Failure of reactor coolant purp oil collection syste's to 6, 7 W. Miller D-57 See IR.97-02. LER 97- R retain oil leaking f rom reactor coolant pump 009, PC 97-3147 VIO 96-20-01 Failure to adhere to reactor coolant afstem cooldown limits 3 R1 Cooper CP-29 R VIO 96-20-02 Failure to follow procedure AI-4COC for review and 7 RI Cooper OP-30 R develepment of Maintenance Procedure PM-191, Main Turbine / Generator, Feedwat er Turbine Layup VIO 97-01-01 Inadequate clearance tagging requirements 3 RI Cahill 0-12 R VIO 97-01-02 Failure to follow procedures, resulting in inadvertent EDG 3 RI Cooper 0-1? More prcblems R start dipeussed in IR 97-ce See LER 97-02, IR 97- R
- VIO 97-01-04 Failure to perform TS surveillance for spent fuel pool level 3 RI Cooper M-9 09 VIO 97-01-07 Instrument loop uncertainty setpoint calculation assuarptions 4 Mellen D-26 See IR 97-02, LER 97- R not t ranslated into procedures 07 VIO 97-01-09 Inadequate corrective actions for cable ampacity 4 Fillion/ D-22 R M. Miller VIO 97-02-01 Failure to follow equipment status control procedural 3 RI Cahill C-13A R requirements VIO 97-02-03 Adequate procedures not in effect to take the plant from hot 1 Thomas CP-19A R standry to cold shutdown f rom outside the cont rol room VIO 97-02-04 Failure to conduct TS logic testing 1 M. Miller R-1A See GL 96-01, LER 97- R 03 VIO 97-05-01 Failure to follow equipment tagging control procedural 3 RI Cahill 0-12A See IR 97-07 VIO 96- R requirements 11-03 Incorrect information in annunciator response procedure for 3 Thomas 0-16 R VIO 97-05-03 inve rt ers 9
ICSUE DESCRIPTIOg masa 31tc 1.EAD IR/SER I.ICBESEE N grac - CLosT H STATUS STRT78 5 Thomas CF-2 R
- VIO 97-07-01 Failure to follow proced2re CP-111 for precursor card prMassing .
R = Yto 97-08-01 Inadeg2 ate procedure and corrective action fer NRC reporting 2.6 schin r*?> i r em***t s l IFI 95-15-01 Design re72iremente for nitregan overpressure { service water) 1 L. MrJ1*n 1R 97-G1 U-41 Weed to review R. C licensee's calc +slation a cenclusicr-. Sea IR 95 21 IFI 95-15-02 Desig's require *nts fcr dynamic LOCA ef fects per surge lina 1 RI Sa*rher D-59 Sea IR 95-21 and TIA R ef f ect s 96-C13 1FI 13-15-07 Design ret 41 resents for reactor coolant pmv cooler failure 1 Themas IR 97-05 D-59 See IR 95-21 and TIA R, C 9-014 RI Sanchez D-60 R *
"sa n *5-04 Code r*quirement for thermal relief valves on decay heat 1 s removal heat exchangers See IN 95-21 and TIA 96-014 - S*e IR 97-te
- FPC a+fi rrs r*11*f e IFI 95-15-05 Relief valves removed from heat enchangers 1 RI Sancher D-61 Se* IR 95-21 and TIA R 95-c 4 IFI 96-03-15 Evaluate the licensee's revised TS Bases and related 10 CFR 2 RI Cahill R-14 Saa LER 96-07 R 50.59 analysis for NFI finw indicaters IFI 96-17-02 Potential for HFI/LFI recirculatien resulting in wake-up tank 1 RI Cahill D-1 See CR3 D.I. 1, IJ7 R overflew 97-ece IFI 96-17-04 Ad*T2acy of 10 CFR 50 Arpendia R fire stwar and docuwntatien 1 N. Miller D-43 R IFI $4-201-11 Design be. sis for decay beat / core flood / reactor coolant, piping 1- Crewley - IR 97-C2 D-44 1Jencif1=d in IFAP R. C t **ca rat ure g.*;crt es IF-94-291 M1 IFI 96-201-12 Conduat sizing criteria - jaaning ratio not considered 1 F1111er./ D-45 13entafzef an IFAP R
- w. willer remrt as IF 94-201-02 IFI 96-201 Cable aepacities - aeveral cables exceed ratin.L includire 1. Fillion IR 97-91 D-22 Identifici in IFAP R. C Dit?-1 r* pert as !F *C-;ct-M IFI 96-201-14 EI77 pr*>tective trips not bypassed Nang e . .j +, s g mod
- of 1 N. Miller IR 97-39 D-12 Identified in IFAP 7, C operation report as IF-94-201-04 S=* IP 91-Ce IFI 96-201-15 Verification of motor starting data 1 Fillion/ D-46 Identified in IFAP R
- w. willar repe r* ** IF 96-2*1- M IFI 96-201-16 Coordination of Second level undervoltage relay (SIER) 1 Fillion/ IR 97-05 D-47 Identified in IFAP R, C Fetting vs. inv*rter Operat ien M. willer f* port 39 IF #6-701-06 IFI 96-201-17 Coordination of SIUR and fuse protection 1 Fillion/ D-31 Idantified in IFAP R M. willar r eport sa IF-95-201-07 IFI 97-02-05 Outstanding issues associated with the emergency diesel 1 RI Cocpar D-6-G As*oc. wit h room t==p R reanerat er pr. war uprat e modifica* ice rt**
IFI 97-08-03 Unacceptable variance in classifying scenarios among a 3 Salyers R rarr*=*nt at iva sgle of *=wr-reeev coordienters 12
ISSUE DESCRIPTICEF assa ENtC LEAD IR/SER LICISESEE CEBW WITS EERC - C1,D5URE ST11% STA7?S 10'37-c6 week.nesses in plant-epecific emerg.ney cperatirx; procetnes - J' scrper/ IR 97-07 ' c-14 Ins; met licensee's R. C for refilling the secondary side cf dry once-througt steam RI Cooper. ECPs - in FPC planned .
-senaretors tp7r
- MULTI-P!JUf7 ACTIONS MPA SL507: Pressure locking and thermal binding of safety-related gate 2 NRR D-49 S** LE2 9 7- 11. New PC R CL 95-07 valves. Ct2rrently in staf f review. An RAI is outstanding. 97-1517 ident ifies Expected cowpletion7 that EFIC valves egen/ clos
- was not taken into erm t r** rat im MFA #L601; Testing of saf ety-related logic circuits - 2 M. Miller R-1 Sea LER 94-25. TER 97 R CL 96-01 Licensee response in staff review. C3. IR $7-C2. 11/96 -
the licensee has 1dantified testing daf aciencies that mast be fixed prior to r*=t a rt (Vic 97-c2-04) MIA #L5034 Cireurferential' cracking of SG tube flaws. 2 Blake/MRR IR 9T-C8 R-17 See NRC letter 5/19/77 R. C
- CL75-01 Licens** respon?* in staff ravi*w.
OT1NR ISSUES a LTOP Current TS does not address LTOP prevent ion or mitigation. 2 NRJt/R I R-16 NRC ltr. 2/4/97 R On the basis of CL 88-11. the licensee submitted inf ormation revaested licens** to to demonstrate that LTCP in Bau plants have less than 1 in submit a TS A. . 100 reacter years probability of occurrence and as a result On 4/7/97 FPC par CL 88-11 non-appendix G methodology ca* be used for PT submatted an ex*=ption curves. Such a PT curve would provide for higher LTCP enable request to use Code preesure and teaperature and would provide operational case M514. Ex**ption flexibility. Staf f denied the req 2est in 1995 and retaested granted 7/97. TS a revised response. The licensee expects to respond late ammdment request 1997 reflecting the approved exemption sufmitted on July 18. Short term action to change Posv setteint / limit RCS P to 20Cs. Appendix R Appendix R design basis issoas review by FPC consultant. NRC 1 Ir. Miller / D-11 a review cy*n Appendix R issues to assure that there are no Fillien/ restart or operability issues imbedded in the's. M. Miller / wun Operator NRC review operator workarounds list to assure that there are 3 RI Cahill 0-7 S** VIO 94-09-07 R serkarounde no restart or crerability issues contain*d in them 50.54f Letter NPC' review licensee's 53.54f letter response (due 2/3/97) en MRR R-8 Tha.se 2 review R, C e-pr1 *+ e desiv bases License verify license conditions are met 2 RI Cahill R-15 See FPC ltr 5/20/97 R Cbnditiens Severa1 1icense conditions were not I m-e 11
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CRYSTAL RIVER 3 ISSUES c'HRCKLIST . N ITEMS (OPEN ITEMS FOR WHICH INSPECTION PRIOR TO RESTART IS NOT NEEDED) - Status as of August 21, 1997 Total Non-Restart (N) Items: 114
# Open 95
# Closed 19 853UE DESCRIPTICES AREA E LEAD IR/sER LICENSEE CTesSNT3 EURC Crosvar eraws srawS
.ZeEnsur s o ern misrant trENs OTSG Tubes Ade72acy of CTSG tube stress-relieved rolled joirrts is 7 See licensae Precursor N (G) questioned. BwoG analysis of a Davis-Besse pulled CTSG tube, Card PC 96-5077 of current test data, and limited field experience conflict with 11/6/96. (No TIA) test data from 1972 which
- qualified
- a stress-relieved rolled joint.
IWSFECTOR FOLLOtfUP sYSTEN CRI 95-21-04 Exceceive cooldoom rate' 3 IE 96-2C See CR3 D.I. 1,, .N LET 96-03 fS),C URI 94-03-04' Measuring 'of percent through-wall indications with an
~
7 IR 97-08 See IR 94-04. Genene N 4Q . ungaalified procedure issue being 443ressed C*- t,e Irelt . (no TIAt CRI 96-03-05 Edjy current saeple expansion based en degraded tube ~ 7' IR 97-C8 See IR 94-06. N tS?,C* parcentagas ' ' URI 96-06-10 Justification for removal of Thermo-Lag protection from the 1 N (5) source ranca inst rumeM ar ion URI 96+D7-03' Incorrect . information prerided by contractors . - 7 IR 97-03 ** N (N? , t-
^ '
URI 96-18-06 Failure to adhere to 10 CFR 50.54 (p) (1) - Phys. Security Plan See IR 94-18 N ($1 sutenit t ed dacreased pl an ef fe<-t ivenass URI 96-201-06 Preferred of fsite electrical power source with plant shut 1 N ($1 doem (500 kv switchyard) is not 72alified. Not e : Until this issue is resolvad, licensee is not using'500 FY switchyard as an elect rical y=,wer scr2ree . URI 96-201-09 Testing to qualify relays beyond manuf acturers' ratings was 1 N (U inad*7 ate 13 i
ISSUE DESCRIPTIOgr asva WRC LEAD I'R/SER 1,ICENSEE COBEEENTS NRC
- CLoSURN STATUS STRTUS LER 93-C2-02, Switchyard cable failure caused degraded voltage of Class IE 7 LER 93-02-01 closed in N (I) trR 93-02-03
- 1 **-t r i ca l tmsen and a-tuat ion of EDG IR 95-09. - !
LER 94-06-01, Deficiency in understanding of technical requirem-nts leads 2 LER 94-06-03 closed in N (D) LER 94-0=-03, to nonconservative RPS setpoint and potential violation of TS In 95-16. See EA 95-LER 94-C6-04, 16. LER 94-06-05, LER 94-06-06 LER 94-09-02 Unauthorized tests involving makeup tank level and pressure See EA 95-126. VIC N (D) IA LER 95-09-00 Minimal release during sul. fur dicxide delivary causes 7 Sac IR 95-11. N (;) actuation of toxic gas monitor resulting in control room emargency ventilation ad uation LER 95-10-01 Inadequate procedure causes low cooling water flow to makeup 1 12R 95-10-00 closed in N (I) pump resulting in operation outside the design basis IR 95-16. See also URI 95-11-02, VIO 95-16-03. LER 95-17-00 SW flow to control room coolers controlled by air operated 1 See IR 95-16 VIO 94 - N (D) valves which could fall cy+n C1-04. LER 95-18-00, Inadaquete TS note allowed delayed entry into TS LCO 2 See NCV 95-18-05. N (1) LER 95-18-01, LFR 95-19-02 LER 95-19-00 Leak instrumentation for SW flow to 33CUs incapable of 1 S*e IR 95-18. N (I) maasurin2 9 0 <1In LER 95 23-01, Inconsistent design assuwptions cause building spray flow 1 12R 95-23-C0 closed in N (I) LFR 95-23-02 rates to te out s i da dasirn basis TR 96-04. LER 95-25-00, Inadequate isolation of safety /non-safety related circuits 1 See VIO 95-21-C3. See N (D) LER 95-25-01, IR 9 7-C2. IR 97-05. LER 95-25-02 LER 95-25-C1 closed in IR 97-os. LER 95-29-00, BWST va uum breaker has inadeq2 ate relief capacity 1 See IR 95-21. N (I) LFR 95-24-01 LER 96-01-01, EFIC control circuits risrouted; Appendir R concern 1 LER 94-01-00 closad in M (1) LER 96-01-02 IR 96-C4s See also NCY 96 01-03. 12R 96-02-03 Minipurty* valve has safety /non-safety related circuits 1 IR 97-05 See VIO 95-21-03 M (*). witho.st isolation C LER 96-03-00, P.CS cooldown rate exceeded during cooldown 3 See URI 95-21-04. N (I) LFR 96-03-01 LER 96-04-00 CCHE control deepers found damaged & leaking 1 See URI 95-02-C2, IR N 'D} 95-21. LER 96-05-01, SW flow to RBCUs could exceed d? sign 1 LER 96-C-5-C0 closed in N (D) LER 96-05-02 IR 94-C4. See also VIO #6-01-01. LER $6-06 00, FrI instrument error could result in HPI pump runout i Mellen IR 97-06 See IR 95-20, IR 96- N (D), 12R ?6-06-01 04, Cit 3 O.I. 2. c 14
issue DESCRIPTION Amma setC 1ahD IQ/sEE LICESEE CQue st,3 Este
- CLOSURN STATUS STATUS LER 96-07-00, HP1 line SB14XMLOCT/ loss of de bus could have inadequate HFI 1 RI Cahill Sea IR 94-01, CR3 N (D)
LER 96-07-01 flow instrumentation D.I.2., . IFI 94-01-15 LER 96-08-00 Ambiquous TS note results in not performing RCS lealt 2 RI Cahill N (S) surveillanca prior to Mode 2 LER 96-09-00 Failure to reattach instrument tubing to seismic supports 1 See t:RI 96-03-06 IR ' N lIl af ter modificat ion 3eads to operat ion outside desian basis 94-05. LER 96-10-00 Low flow in SW system cooled componente causes operation 1 RI Cahill Sea VIO 95-16-03, VIO N (D) outside design basis closed by Bartley in
- 97-11, LER has add 1 itees to w rify before elesf rn.
LIR.96-11-00 Personnel error causes testing deficiency resulting in 1 See MFA #L601 (GL 96- N (D) condition prohibited by improved TS (CL 94-01 issuest 011. Operatiora cutside design basis caused bY battery chargers .
~
LER 94+22-00, 4. IR 97 01 See VIO 96-00 07. N (D), LER'96-12-01, ~having inade pate test results accepted in error '- C LER 96-12 02 LER 96-13-00 Operator error resultri in the inadverter:t actuation of DCP- 3 See MCV 96-03-02. N t!) 1A 12R 96-15-00 Personnel errors cause cable separation / isolation concerns 1 See IR 96-04. N (I) resulting in operation outside the design basis (tomic gas monit ors t 4 LER 96-16-00 CREVS filter testing did ret meet TS specs 2 RI N ($) LE18 96-19-00, Non-safety related swit.ch used in safety related wiring for 1 See t;RI 96-06-01, See N (DJ LER 96-19-CI ES status lights IR 97-04 LER 96-20-00 tDireviewed safety questions concerning EDG cverloading caused 4 R-2 D-4, D- See EEI 96-12-02. N (D! by interpretation of regulatory requirements 14 D-15. CP-5 IER 96-23-00 Personnel error leads to missed survaillances resulting in 2 See VIO 96-15-01. N (D) violation of Techr.ical Specifications (missed remote shutdown panel EFK pump pressure instrumant channel ebe -kl LER 96 .24-00 Plant modification causes unanalyzed condition regarding 1 See EA 96-365, VIO A N (Db LEP 94-24-01 emergency f eedwater _ LER 96-25-00 Personnel error caeras testing deficiency resultifry in 1 See bWA #L601 (GL 96- N'A condition prohibited by Technical Specifications (12 contacts 01). In Es losic were not beirn testedi LER 97-01-00 Inef fective change management results in wirecognized NPSH See EA 96-365, VIO A N (D) issue af fecting EFW availability (010421 See EA 97-094 VID A2
!O102M LER 97-S01-00 Maintenance activities in circulating water system result in See EA 97-012. VfD N IS)
(See EA 97- protect =d area breach A(4) (01043) 012) 12R 97-502-00 Security zone cut of service N (S) 15 \ .
ISSUE DESCRIFT20er amma gutc LEND ED/ Set LICEISEE CM 3HtC CIZISURE STA71.S STATUS LER 97-02-00 Out of calibration fuel storage pool water level transmitters See VIO 97-01-04 N (D) (See VIO 97- . 01-04) LER 97-02-01 LER 97-03-00, Fer1ponnel error causes test.ing deficiencies (GL 96-01) See VIO 97-02-04 N (.D) LER 97-03-01,
- IER 97-0 3-02, LER 97-03-03, LER 97-03-04.,
ti"R 97-03-05 LER 97-04-00, 'Ihermal relief valves inside the containment do not meet GL 96-06 W (D) LER 97-04-07 r*TJir* ment s for d*sion basis accident s S** D.f.8 LER 97-06-00 Surveillance testing results in reduction of EDG rating limit See D.I.6 N (D) due t o irrad*72 ate awane* LER 97-07-00, ' Building tenperature variations larger than assumed. See VIO 97-01-07 N (D) LER 97-07-01 resu1 ting in unknown inFt rument uncert aiet 1*s LER 97-08-00 Potential of NFI pump recirculation capability resulting in RI Cahill See CR3 D.I.1 N (D) possible MJT overflow or possible puay f ailure LER 97-10-00 WAC was not considered for manual operation of safe-shutdewn See URI 97-05-02 N (D) equip =nent in post-fire conditions resulting in non-coepliance of AFP W LER 97-11-00 Pressure locking of EFV-32/33 (GL 95-07) See MFAsL507 3 (D) CL 95-07
*#* 97-12-00 CI systeur containment penetrations not designed for CL 96-06 N (D) containment isotation S** D.f.8 VIO 94-25-01 Failure to tNrly cor. trol the Control Co plex Habitability 6, 7 See URI 95-02-02. N (D)
Envelope (de ;r blocked coen for maintenaw e worit) VIO 94-27-02 Failure to inake two 10 CFR 50,73 reports to the NRC withia ' 6, 2 ' IR 97 CP-4 See IR 95-02, IR 95* N (I), C t he ragst red t ime - 09. a
~
VIO 94-27-03'. Failure to make one recraired 10 CETt 50.72 twport to the NRCi '
.6, 2' IR 97-04 CP-4 See IR 95-08. N (fl.
within the' required time C VIO 96-01-05 Two exanples of failure to update FSAR as regaired by 10 CFR 6, 4 N (S) 50.71fel VIO 96-02-01 Failure to maintain 0.2 footeandles in the protected area 6, 7 See IR 96-07. N (S) VIO 96-02-04 Failure to maintain secondary alarm station operable and 6, 2 N (S) inadeeraate compensatery measures VIO 96-C3-11 Failure to follow radiation work permit revairements 6, 7 N (S) VIO 96 03-12 Failure to report the transport of a radioactively 6, 2 N (S) contaminated individual of f site VIO 96-03-13 Unescorted visitor personnel within the protected area 6, 7 N (S) VIO 96-05-04 Licensee approved eddy current acceptance criteria different 6, 2 J. Blake N (St f rom TS requirement s 16
. .. .. = . .
ISSUI DESCRIPTICN asma NRC LEAD ID/SER LICENSEE Ct20eNTS NRC
- CIASURE STATUS STATUS 1F2O 96-06-C6 Failure to timely nctify the NRC of a ccedition oa *'de the
'~
- 6. 2 11 97-G4 3 45).
Appendix R Licensing design basis C - VIO 96-07-01 Failure to protect safeguards information 6. 7 N (57 VIO 96-07-02 Failure to complete screening elements for Fitness for INty 6. 7 N (S) Personnel VIO 96-09-01 Failure to follow a maintenance procedure resulting in the 6 7 N (St inadvertent initiation of the control room emery *ney vent ilat ion system VIO 96-09-02 Unescorted visitor personnel within the protected area 6 7 N (S) VIO 96-11-01 Inadequate work instr actions to prevent the inadvertent start 6. 7 N (S) of t h* A EM VIO 96-11-03 Personnel performing work on the reactor building sun 6 7 RI Cahill See YIO 97-05-01 N IS) wi t bNt locrzing ont o a clearance, as required by arprovad WR VIO 96-15-01 Failure to perform a required TS surveillance for the remote 6, 2 See IER 94-23 N "Si shutown panel VIO 97-03-01 Failure to maintain control of badge / key card N (51 VIO 97-07-02 Inad*quate planning and controlling of hydrostatic testing 3 RI Cahill N (S) VIO 97-07-06 Inadequate corrective action for use of UPS unit in security 4 RI Sanchez N (S) cent ral alarm stat ion IFI 94-18-09 Review periodic verification plans - MOV (CL 89-10 item) 2 See IR 95-11. IR 953- N (I) 21: S** C' 9 9- 10 IFI 95-02-05 Resonance noise in vicinity of PL*V-25 7 N (Si IFI 95-08-03 Emergency Operating Procedur? update program 3 See IR 95-16. VIC 93- N (S) 14-07 IFI 95-11-01 SCBA requirements for personnel duri g a toxic gas release 2 N (S) IFI 95-21-02 McCitfication to the standby feedwater puq recirculation line 1 N (S) IFI 96-03-16 Reviest of MAR 96-02-09-01. MPI flow i dicators, installation 1 N (S) package and f urv-t iem41 t est ing result s IFI 96-04-0J Effect of setpoint calculations on EOP revisions 1 Sea VIO 93-16-07 N !D!
, IFI 96-05-06 Large break loss of coolant analysis generic concerns 1 N (S)
IFI 96-06-09 Deficiencies in Mecaties fire barrier program precedures and 4 IR 96-15 5 (S), derumentat icn ** IFI 96-08-02 Reactor building cavity cooling piping thermal relief 1 See D.I. 8. GL 94-06 N (D) prot act i on 17 l L_______ _ _ _ _ _ _ _ _ _ _ __ __ _
a ISSUE DeSOtIFTICII AREL m c LERD IR/SM LIC M S M e m an'WIS EBC M- STATUS STa&US IFI 96-15 03' Actions taken to resolve post-accident recriticality concerns 1 N2R reviewing, generit. 5 (C1 tSue to localized boron dilution B&W issue - IFI 96-18-06 Adequacy of licensee *s corrective actions for security audit 5 N (5) findings EE1.97-O bO7-Continued failure to pectect.Sofoguards'inferimetion
+
2; Strattce- See SA 97-141, YIO N' Af010138 VIO 5801 M3f' fSt.C IFailure to make an Emukrgency 9taone' Report within t.he time , See afL 97-094f VIO
^
ERI 97-04-01; N s f 0103M # Ft ,C -
^
reesivements of 10 CPR 73.71 EEI97-04-02h' Failure to h$nd. carry a ' suspected repertable issue.to the - , see Eh 97-094, VIO N shift senager for ressortability review C(010437 (S),C
. .c . . . .. . .. . .. .
EEZ 97-94-03' . Repeat failure to report outside ' design inesis conditions - see M $7-094, VIO - N Afstc139 ist .c - EEI 97-09-02' Failure to update the FSAR to include added EDG trips Schin See EA 97-330 N (S) Ea 97-008 Loss of control of a security badge &. subsequent failure to 2 Stratton See IR 97-03 N (S) immediately recort lors & remove badae from security computer En 97-012, Failure to have adequate security procedures reflecting 2 Stratton See IR 94-18 N (S! VIO A(1) security upgrades 01013 (was ESI 96-18-01) EA 97-012, Failure to respond to a protected area alarm 2 Stratton See IR 94-19 N (S) YIO A(2) 01023 (was EEI 96-18-02) EA 97-012 Failure to assess more than one protected area alarm 2 Stratton See IR 94-18 5 (S) VIO A(3) 01033 (was EET 96-18-03) EA 97-012, Failure to maintain protected area barrier at Circulating 2 Stratten See IR 96-18 LER 97- N ($1 VIO A(4) Water System 501, IR 97-01 01043 (was EET 96-18-04? EA 97-012. Inadequate arms repository 2 Stratton See IR 96-18 N (S) VIO A(5) 01053 twas EET 96-18-05) EA 97-012, Failure to report changes to Physical Security Flan per 10 2 Stratton See IR 96-18 5 (5) VIO B 03063 CFR 50.54 requirements (was EEI 96-18 - 0M EA 97-094, Failure to make an emergency phone report, within the time 7 RI Cahill. N (5) VIO B(01033) requiremants of 10 CFR'73.71 (was EEI 97-04-01) 18
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ICSUE DESCRIPTICK AREA NRC LEAD IR/FER LICENSEE CupOEENTS NRC CIASURE STATUS STATUS EA 97-094 Failure to hand carry a suspected reportable issue to the 2 RI Cahill N (S) VIO C(010431 shif t manager for reportability review - {was EEI 97-04-02) EA 97-094 Peg *at failure to report outside design basis conditions 1, 2 Schin See IR 97-08 N ($) VIO A1(01013) * (was EEI 97-04-03) EA 97-161, Continued f ailure to protect Safeguards information 2 Stratton See IR 97-C3 N IS) VIO A 01013
- VIO B 01023 twas EE! 97-03-01)
MULTI-FLANT ACTICNS MFA #B105; Seisaie qualification of equipment. Licensee's criteria and 2 FPC walkdown id*d N 15) CL 87-02 procedures approved. Some issues are y nding and would be appres. 100 outliers. resolved thru audit (scheduled for Mar 97). Licensee *s field S*af f had telephone walkdown results are currently in staff review. discussierts on 5/16. Phone sumnary documented in 1GiC ltr 5/27 FPC committed to characterize the outliers for safety significance by JULY. FPC also consuttad to resolve the outliers oa prvride JCD prior to rest art . MFA #9111 IFE and IFEEE - These are in staf f review. Not a restart 2 N (S) iIPE); item. MPAsB118 (IPEFEi MPA #X602; Movement of heavy loads over spent fuel pool 2 N (S) NRCB 96-02 - Licensee response in staff review. This would not be a rest a rt issue. MFA #L208: Thermolag - Licensee plans to use Mecatiss 2 See IR 96-C1; IR 96-06 N (S3 GL 92-08: BU ian alternate material), some reanalysis of Ar M I2 R. and 92-01 some exemption. Fire barrier tests of Mecaties including Anpacity tests are in staf f review. This also may not be rest a rt issue. MFAS L201: Reactor vessel stnictural integrity. RAI to licensee on 2 N (S) CL 92-01 Rev 7/22/96. Only a data base issue, not a restart item. 1, Supp 1 MFA WL604: Borafles de7radation. Licensee response is just in. Staff 2- WPC ltr. Closed t=y NEC to FPC M (S), GL P6-04 review to commence. This inay have to be ailressed prior to of . letter dated S/1/97 C restart Wause of sensitiirity to spent fuel poo.L issues. 5/1/97 MFA _ 2 MOV testing & surveillance. This item is closed with the 2 See IFI 94-18-09 N (I) CL 89-10 exception of IFI 94-18-09 on periodic verification, which is to be follow =d up af ter a new generic coarnunication is issued. LICENSE AMENDDtENT/ RELIEF REQUESTS 19
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ISSUE DESCPlFTION ABS & NRC LEAD ZR/SER LICBESEE C:sgGKf3 NRC CLOSURE STATUS STATUS R.G. 1.97 RG 1.97 instrumentation - Subcool sonitors ete - category 2 N (S) I Int re.t s change License amen +nent may be approved by M r. l l flametrics E. Bioretric exemption to allow taking security badges offsite *' 2. IULE/RI IK 9b11 Exemption issued NIS),C Security ' Staff. review is espected to be corplete soon. S/7/P7 Isplemented-7/24 Core Flood.' Relief request P3t Core flood twszle.- Staff needs scre inic. 2 Felief issued ce N Norele PM will ku p RIT infor M . $/5/77' f ?) , C - CTSG Tubes CTSG tube testing - Licensee proposed a revised CmBG tube 2 See VIO 96-CS-04 m (S: ecceptance eriteria. OTRrm ISSUES Pressuriner Durirup Pefuel S a sub-surface flaw was discovered. The 2- Pef HRA itr of: N Nozzle Flaw 11 cees *e performed better insp*ctious dur132 R1G and found the. 7/24/97 TAC tio. (31.C flaw to be acceptable. The new inspection results in reduced M904 ss
' tisw size and conse72ectly acceptance criteria (wesich is based on ratio of flaw to thickness) changes. Staff review in proyress.
Criticality The licensee dirt not carry a previously approved exevion 2 N (S) h itor from part 70 (7 .247) regsirements to Part 50 license. Need local interpretat ion of t he status of the exemet ion. Sources for issues include: IFS, SIMS, NUREG 1435 (Status of Safety Issues at Licensed Power Plants), Resident's OIL, PM's OIL LIST OF ACRONYMS USED AP Abnormal Operating Procedure BWST Borated Water Storage Tank C Closed CA Corrective Action CCHE Control Complex Habitability Envelope CFR Code of Federal Regulations CR3 D.I. Crystal River 3 Design Item CREVS Control Room Emergency Ventilation System EA NRC Escalated Enforcement Action EDBD Engineering Design Basis Document ECCS Emergency Core Cooling System EDG Emergency Diesel Generator EEI NRC Escalated Enforcement Item EFP Emergency Feedwater Pump EOP Emergency Operating Procedure 20 [ - _ . _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - - _
FSAR Final Safety Analysis Report ,' GL NRC Generic Letter IFI NRC Inspector Followup Item IFS Inspector Followup System . ILRT Integrated Leak Rate Test (of the Reactor Building) IR NRC Inspection Report JCO Justification for Continued Operation LER Licensee Event Report LOCA Loss of Coolant Accident LPI Low Pressure Injection LTOP Low Temperature Overpressure Protection MPA NRC Multi-Plant Action MUV Makeup Valve N (D) Not an NRC Restart Item (because the issue is duplicated by a restart item) W (Gi Not an NRC Restart Item (because it is a generic issue affecting multiple operating plants and is being addressed by NRR) N (I) Not an NRC Restart Item (because previous inspection of the issue is adequate for restart) N (S) Not an NRC Restart Item (because resolution of the issue is not needed for safe restart) NOV NRC Notice of Violation WPSH Net Positive Suction Head OCR Operability Condition Report OIL Open Item List OP Operating Procedure PM Plant Manager l PORV Power Operated Relief Valve
' PR Problem Report I QA Quality Assurance R NRC Restart Item RB Reactor Building RCS Reactor Coolant System RMG Radiation Monitor SDLOCA Small Break Loss of Coolant Accident SFP Spent Fuel Pool SIMS Safety Issues Management System TIA NRC Task Interface Agreement (between NRC offices)
TS Technical Specifications URI NRC Unresolved Item USQ Unreviewed Safety Question VIO NRC Violation OFFICIAL RECORD COPY DOCUMENT NAME: S:\DRS\ RESTART.CR3\ RESTART.897 21 l l
p , l CRYSTAL RIVER 3 - SCHEDULE AND STATUS OF LICENSING ACTIONS / ACTIVITIES Sept seer 3,1997 .' TAC No. Action Description Application RegJest Remarks /Open Items INo Target 1 98991 SBLOCA Mitigation of S8LOCA. A combination of ECCS, 06/14/97A 11/1/97 FPC items: D1, D2. The submittat includes: License EFW flow, and EDG toad management are required Amendment to address $8LOCA event. This amendment - RCS 1500 psi signet for Make w Sg pty addresses: EDG g grade, requalification and Valve (MUV-27) automatic closure (not an load management; EFW and HP! system USQ).This is in addition to the existing modifications; and TS and FSAR changes operator action. associated with the above.
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-" ^ nPI anstysis mith volves'in throttle' position in lieu of cavitatifg venturis.
Other Open items: EDG fan gerade.. Due 8/26/97.
- EDG toeding cale and testing regJirements the 9/15/97.
- Draf t E0Ps 3 and 8, and AP 770 due 8/4/97.
Letter to confirm mods and E0Ps do ret result in additionet Usos due 9/15/97 Proprietary and non-proprietary versions of the L8tOCA ana1ysis dJe 8/29/97. Determine need to perform 30-start test or stAssit 8CE/Cottee test results due 9/15/97 Propmee license conditions.for'ensitments c 6 and 7 of tfie sihmittal
;?ltesolveLER97-021regarding'lossof1A' Train bettery and 'S' Train wicantrotted NPI flow.
2 99128 License Delete license condition 2C(5) which regJires 06/26/97A 9/26/97 Issue linked with boron precipitation (Item 13). Amendment testing of flow indication in the ECCS for 8/4 teleconference identified need to request DM-45-Fi boron dilution. approval for current licensing basis (3 active methods) aruf resolution of item 13. 3 Appendix a Appendix R III.0 emenption for RCP tube oft 9/5/97 Request will be similar to Ano Exemption fitt line - welded connections. 4 95817 Thermotag Erhanced sprinklers in certain areas in lieu 06/21/96A (a) of theramt barrier w grade. 5 95817 Thermotag Emergency lightirg. Atlow use of AC and 06/21/964 7/25/97 FPC reevaluation of lighting emenption request (b) portable DC powered tighting in two areas. 6 99277 LTOPs License TSCRs 213- PORY setpoint and LTOP TS using P/T 07/18/97A' 10/18/97 Approved emenption f rom 10 CFR 50.60 acceptance Amendnent curves for 15 EFPY. criterie (Code Case N514) by letter dated 7/3/97 Shelty sent out on 8/1. Issued RAI on 8/12/97 and Telecon on 8/13. FPC response by 9/2.' 7 92902 !L m it=? *
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- N-- ?/ * " 06/04/03 7/24/97C Item closed. LER 97-014 (7/17/97) reported R8 M pressure sensing line penetrations local test not done. FPC to complete att tests by 11/30.
ATTACHMENT B
TAC No. Action Description Application Cequest Remarks /Open Items INo Target l 8 License Operator action (20 sts) to isolate letdown 9/5/97 11/25/97 LER 97-015 (7/11/97) Amenchent USQ (MUV 49) per E0P following loss of stbcooling Witt include two open items requiring instattation
- Letdown margin. of a new inboard isolation valve and co gtetion of line rupture an analysis to adfress EQ parameters. PC 97-5975 -
stesequentty identifled simiter candition vith outbeerd vetve Muw-49. 9 Potentist USQ EDG Protective Trips not bypessed during ESAS 09/15/97
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EEI 97-09-01. EA 97-330. See FPC' response to' Eft , and LOOP. (May modify design instead of a dated 8/11/97. Iicense amenchent). Add new EDG trips. 10 98262 OTSG License TSCRW 211- exclusion of specific set of ttbes 05/01/974 10/30/97 In staff review. (See also 3/27/97 suturittat) Amenchent in "8" steam generator from random selection RAI response provided 8/20/97 and inctoded new TS for inspection and sample expansion criteria page for reporting (revert to' existing reporting requirements). Open Item - FPC to provide ne=s TSCRM (not restart related) by 10/6/97 regarding IGA growth to atlow release cf TSCRW 211 11 96606 Reg. Guide TSCRM209-lT,,g PAM, EDG kW Meters (Other new 07/29/97A 11/4/97 - Scope of response has been increased to include kW 1.97 License Type A's). 9/27/96 sub. Requested to add the meters. See previous FPC sthmittal 9/27/ % . Amenchent stbcooling margin monitors and LPI flow Additional design details retwired. FPC to justify indication to the PAM instrument table. to i g tement by Refuet 11. (TSCRW 209-1) 12 % 314 SBLOCA issues LPI Mission Time (DNP) letter 05/13/97A in staff review 13 Boron IPAP issue. FSAR change relies on reactor 09/02/97 URI 96-201-01. Precipitation hotteg injection instead of active method for Potential preventing boron precipitation. See item 2 - FPC to develop contingency if not USQ. resotved. 14 M96943 Appendix R Description of Issues related to FPC Restart 09/25/97 Design item D11. Requested more specific definition Issues Issue D-11 to stoport staff closecut. cf issues. See mRC tetter 7/7/97. Inspection 8/4/97. 15 Appendix R Capability to achieve cold shutdown within 72 09/02/97 Issues hours (Atmospheric dtsp valve capebility) 4 ? ,_ , _ J = " e' 2 _ - '-- '::-- r a*--: '- 08/19/97A C FPC has determined this to be not an USQ. Item is 4eeves ::':t; !:t d :: : !!: ^e * *-- ::: closed. See .F.PC tetter deted S/19/97
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17 Appendix R Response to IN 92-18 regarding modification to 09/19/97 Issues valves needed for cold shutdown (safe shutdown analysis) 18 Appendix R Remote Shutdown Panet addition of fuses to 08/19/97A C 5, " 'M r r - J * ,, ^ :---
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Issues controt circuits FPC hos determined this to be not an'tNG. . See FPC Potential USQ letter dated 8/19/97. 2
TAC No. Action Description Application Retpuest Remarks /Open Itsus INo Target l' 19 94668 GL @ 01 Logic testing. First Sthmittal 4/18/96A. 08/33/97 Several LERs (96-011, WO25, 97-003) indicate Sunenery Report expected 09/5/97 problems with logic testing. asport;to be provided ~ ~ '
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se respaired by EL 96-01 20 Potential FSAR Rev. 23 includes several potential USQs. 07/10/974 Usos NRC tetter 12/20/96 identified 15 examples. Licensee provided response 21 Seismic quat. Severat cuttiers. Licensee to provide schedule 08/1/97A Inspection'to occur inloctober[1997 of equip. - and status for resolution of restart related A-46 Phase !! items. response. 22 License ECCS/EFW requirements / operable equipment 09/05/97 11/1/97 amendnent required for,LCCA in Mode 4. (TS) 23 - License Operator Actions in E0Ps and APs 09/30/97 Draf t E0Ps scheduled to be complete 8/29/97 amendnent Potential USQs
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24 License ADV design capacity: Reduction in ftow, tocat 08/2T/97 FPC hos detersrined this to' be not "an use.' Amendnent operator action for opening. Potential USQ 25 M95347 License Review response to request for information 06/17/97 FPC Item D-62. FPC' tetter 4/17/97 indicates a Submittat regarding RCS attached piping fatigue analysis 09/30/97 schediate for this effort _witt_ be developed by adequacy 9/30/97. 26 M96604 Licensing Review of evaluation to determine Jet 09/26/97 Reference IFt 95-15-02 and FPC tetter dated 6/5/97. Basis-Dynamic inpingement interaction between the Need to inforis Region of results Loads pressurizer surge line and SW piping. Initial response (pipe whip) received 6/5/97A. 27 M93454 Gt95-07 , u *: - Addit fonetTinformatian 08/11/97A AA!'dsted 6/13/96' addressed PORY stock vetve (RCV-regarding pressure locking for valves EFV-12, 11).; Additlenet volves identified in LER 97-011. EFV-32, EFV-33, 28 uso 2
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09/15/97 N/A Sp - r! M - FPC to' provide kaplanatici a-- ^ t i= _ _ G8/.4/874 GT4 0/974 "" ' -- Sf"/"' ri -9= 5" ? ? ' ?
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30 99333 64eense Srw ^ _ ^ r --! Amendnent ;- ' -- t M ? ? 6/ M ' ! ;- _ -- th
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M ' hrtc-- 30 Potentist USQ Modification to provide automatic toeding of 09/30/97 third Reactor Building Cooting Unit (AMF-1C) could result in two RBCus toeding to one EDG 3
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