ML20141J746

Summary of 970212 Plant Restart Panel Sixth Meeting W/Listed Attendees on Facility Site to Review Restart Items & Provide mid-week Debrief of Findings.Engineering Work Done in Response to GL 96-06 Appeared to Be Good

ML20141J746
Person / Time
Site:	Crystal River
Issue date:	02/24/1997
From:	Jaudon J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
GL-96-06, GL-96-6, NUDOCS 9708210183
Download: ML20141J746 (24)

Text

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NUCLEAR RE UNTY COMMISSION (g/%g

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February 24, 1997 MEMORANDUM T0: File FROM: -

Jo s . Jaudon Di ec 6Lu or Di ision of Reacto afety

SUBJECT:

MINUTES FOR THE CRYSTAL RIVER RESTART PANEL SIXTH HEETING HELD FEBRUARY 12, 1997

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The Crystal River Restart Panel met at the facility site on February 12, 1997.

The following panel members and others were present:

Panel Members: Johns P. Jaudon. Ril, Chairman Frederick J. Hebdon. NRR, Vice Chairman  :

Stephen J. Cahill, Senior Resident Inspector Laksminaras Raghaven, Project Manager Others: Robert P, Schin Reactor Inspector Rll BillyR.Crowley,ReactorInspector,Rijl McKenzie Thomas, Reactor Inspector, RII:

Larry S. Mellen, Reactor Inspector, RII' Paul J. Fillion, Reactor Inspector, Ril The inspection team, which was onsite to review restart items, provided a mid-week debrief of their findings. Salient

>oints made in this debrief included that work packages and welding found in tie field were good. Also it was noted that engineering work done in response to Generic Letter 96-06 appeared to be good.

It was also noted that there was a problem being developed that indicated that the temperature controls and design for some buildings and areas did not appear to match the specific temperature requirements for some instruments to pursue this located issue. in the buildings and areas. The inspectors will continue

.The panel reviewed the Restart Task Checklist and the Issues Checklist. Some items were characterized as "Not Applicable" [NA): others had responsibility assigned: for many other items for which there was activity, the panel characterized the status as "On going" (0) on these. All three restart list are attached for information.

' My present for the discussion of inspection status

'SeeFootnote1.

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File 2 The panel noted that the licensee was still developing plans for how to address some design issues.

It was concluded that when the licensee made these determinations, it would be a>propriate to hold a meeting with the licensee in Headquarters so that a > road spectrum of NRC management-could be brief-d on the proposed resolution of the various technical issues. It was also suggested that the frequency of panel meetings was too often for the

. point in recovery at which the plant was now: therefore, the frequency of-meetings should be adjusted accordingly. The next meting was tentatively set for the week of March 21 onsite.

The Chairman noted that the schedule for the conduct of Haintenance Team inspections in Region 11 was under review, and it had been necessary to move

--- another utility into the May time slot originally scheduled for Crystal River.

The inspection of Crystal River would be re scheduled.

The panel also discussed various issues expected to be raised at the public meeting scheduled with the licensee the same day as the panel meeting. The record of the public meeting will be docketed by separate correspondence.

Docket: 50 302 Attachments: A. Restart Open Item, Check List B. C stal River Issues Checklist C.

C stal River Restart Task Checklist J

Attachment A CRYSTAL RIVER 3 ISSUES CHECKLIST R ITEMS (TO BE INSPECTED BY THE NRC BEFORE RESTART)

Status as of February 24, 1997 The Crystal River Restart Panel met on November 13, 1996, and developed sev,en 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 zssos DasCRzrTzos ARma mac rosas rR/smR ucumBas Comee urs mRe STATUS STATUS LICBBBER*5 RESTART LIST OF DBEIGIS-RET.ATED ISSUES (D.I.a)(per 10/28/96 Itr from FPC)

CR3 D.I. 1 SPI pump recircislation to the =*up M 1 RI D-1 See lat! 96-01-02, IFI R 96-17-02, IR 96-17 CR3 D.I. 2 API system modifications to improve sRtoca marstas 1 RI D-2 see oRI 96-01-02, I.sa R 96-06, IR 96-17 CR3 D.I. 3 LPI pump M asica time 1 faa=haaf D-3 See tRI 96-201-01, IR R assR 96-17 C23 D.I. 4 Reactor inaildtag spray pump la NPSE 1 tenahm a D-4 See CRI 96-201-02, IR R 96-17 C13 D.I. S Emergency f== hater system upgrades and diesel generator load 1 Schia D-5 1apact See CRI 96-12-01s EEJ R 96-12-c2. In 96-17 CR3 S.I. 6 Emergency diesel generator leading 1 Fillica D-6 See EEI 96-12-02, IR R 96-17 C13 D.2. 7 Failure modes and effects of loss of DC power 1 Fillion D-7 See URI 92-12-01, LER R 96-07, IR 94-17

! C13 D,2. O c===eic lettar 96-06 IThermal overpressure protection for 1 f===ha=# D-0 See IR 96-12 Cantatament piping. penetrations. and cooleral R crawley l

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2230s DasCEIFTICAg 1E21 NRC LEAD 1R/834 LICENSEE rYmw!O NRC STATUS STATUS IMIFRCTOR FOIJ4tdDP SYSTEtt UEI 95-02-02 Cor. trol room habitability envelope leakage. Excessive 1 Schia leakage paths through doors, dampers, and drains due to See TIA 95003: FPC TS R design errors and lack of surveillances/ preventive Oaange Request No. 208 maintenance of 4/28/96; IEas 96 04, 94-20, 95-01, $$-

04-01,95-09s irs 95-02, 95-09, 95-11, 95-16,95-21s FPC ltrs.

of 5/26/95 and 10/23/95 URI 96-01-02 Discrepancies 1.n the high pressure injection design basis 1 RI D-9 analysis See CR3 D.I. Is R CR3 D.I. 2 URI M 01 ~Discrepanetes in the EIED and the FSAR regarding the;._ 1-. . .

prevention of post-14CA boron precipitatica' ' 3"

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A-URI 96-05-02 Design concerns with mala steam line hangars used in seismic 1 1mnahan, and other dynamic load applications Raghavan See VIO 96-05-01: R Coordinate with L.

Eachawan URI 96-06-03 son-safety related transfer switch used la ES status 1 Fillion D-21 R indicatino lioht circuitry

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URI 96-12-01'.

' Emergency Faadwater.Iow WPSM to both pumps <hae co postulated:

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m , g. ..g' y ,u m., ...g-...y ..w sin.gle failure? _ K ' ~ .Schin 4,- IR 96-19. :D.17?c ;Sao CR3 D.ls-Sit....,., ;R, C3 AV g7 ,

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.43.f-04 h-05/ .06 F URI 96-17-03 Failure to M*et required Technical Specification 4 Fillion See MFA DL601 (CL 96 surweillance testing on safety related circuitry ICL 96-011 015 A

URI 96-201-01 Long tere plant cooldown following a small break LOCA 1 Crowley/ D-3 See CR3 D.I. 3; see IR assuming a single f ailure in the decay beat drop line NRA 96-11. NRR taking R 3 responsibility for this item.

CRI 96-201-02 WPSM for building spray pump has very little margin, and some 1 Lenahan D-4 See CR3 D.I. 4 R calculatica factors were - --rvative URI 96-201-03 Operating curves 16, 17, and 18 in CP-1833 are not validated 4 by licensee Hopper 0-1 R URI 96-201-04 Nonaafety-related positioners on safety-related valves 1 Tha=== R-7, D-10 See IR 96-08 R

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Service water system haar loads.did not consider maximum L~ ., . ..

li ~v Crowleyf SIR 96-19 See 281;96 7 1) 04[

' trgnst heatt(OP-103B.' Curve ~153i L W . ~ .O 1,7 ,

[R;(CT l URI 96-201-87 EDG act protected against water spray from f ailure of fire i 1 Fillion protectica deluoe system in EDC room R l

LER 95-13-01 Design deficiency may cause makeup tank wortaming resulting 1 nellem la f ailure to meet

• W im R requirn._.;s LER 95-13 00 closed in p IR 96-06 8 ,

Failure to verify RB penetrations closed per TS g RI O-2 EEI 94-19-81 Four emaaples of failure to follow refueling procedure FP-203 3 Hopper **

EEI 96-10-02 Failure to assure root cause analysis and corrective actions 5 teopper **

taken to preclude repetition were adat ate af ter refuel k facident 8mo PR issuedt ,

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ISSUE DE3CRIPTION AREA NRC LEAD IR/SEE LICMESEE CoseGarT3 NRC STATUS STATUS EEI 96-12-02 EDO loading CSQs due to inadequate IS CFR if. 59 evaluations; 4 Schin/ R-2, D-6 D- Enforcement conference R three examples tone modification & two proc C re changest Fillion 14, D-15, 1/24/96. See CR3 D.I.

OP-5 5s CR1 D.I. 6 EEI 96-12-G3 Inadequate corrective actions for le CFR 50.59 evaluation 5 Schia errors: two enamoles Enforcement conference R 1/2e/96 EEI 96-12-04 Use of imverified calculaticas to support modifications. 4 Schin OP-6 Enforcement conference R NRC inspect licensee's extent of ron11 tion reviews.

1/24/96 EEI 94-19-81 nree inadequate procedures for containment penetration 4 RI surveillances Enforcement conference a 1/24/96 EEI 96-19-02 Inadequate corrective actions for h d*quate containment 1 RI Enforcement conference A penetration surveillances 1/24/96 EEI 96-19-03 EFW NPSM USQ due to inadequate 20 CFR 58.59 safety evaluation 1 for a modification Schia Enforcement conference a 1/24/96 EEI 96-19-04 Failure to update applicable design doc-* = to incorporate 1 Thomas EFW design information (EFP-2 assumed operating when EFP-1 Enforcement conference R r

trips at Saos RCs pressurel 1/24/96 EEI 96 49-05 Failure to include applicable design information la the 1 Thomas design input requirements for an Efw modification (EFP-2 Enforcement conference R continuing to operate af ter EFP-1 trips at 5008 RCS pressure 1/24/96 and arvtraulic requiremental EEI 96-19-06 EFw USQ due to removing the automatic open signal from ASV- 1 Thomas 2 04, reducing the reliability of EFP-2 Enforcement conference R 1/24/96 EEI 96-19-07 Inadequate 50.59 evaluation for post-I4CA boron precipitation 1 Crowlef Enforcement conference a control 1/24/96. Verify procedures and documentation adequate prior to restart .

EEI 94-19-06 Error la design calculations for SW systen heat 1cada 1 Crowley Enforcement conterance R 1/24/96 i

i EA 95-16 Use of non-conservative trip setpoints for safety-related 6, 1 Mellen l iwas EEI 95- equipment (SLIII) . See IR 95-16, IR 95-21 A

' Additional examples identified in IR 95-e2-04) 16.

EA 95-126 Nine instances where operators violated procedures for PETF Schia Nov I.A luas 6. 3 See IR 96-04 R pressure / level (SLIII).

EEI 95-22-018 I

EA 95-126. het of unauthorized tests of SEJT without 10 CFR 59.59 6, 3 Schin mov I.R twas evaluation (SLIIII- Additional examples (four tests) See IR 96 04 R EEI 95-22-023 identified in 1/1s/96 letter titled EA 95-126 and EA 96-1453.

(See 12I 96 04-04)

EA 95-126, Failvre to take adequate corrective actions for operator 6 5 Schin R NOW I.C.1 concerns regarding OP-1033, Curve e, for as/T pressure / level twas EEI $5- limits (SLIII)22-013 EA 95-126, Corrective actions for an inadequate Chrwe 8 (two STI's and a 6, 5 RI O-1 NOW I.C.2 revised Curve SA & SRI were also incorrect iSLIII) R twas EEI .4-l 22-01)

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ISSUE DasCRIPTIcur Anah auc Lama Ia/saR LIr = == CosasENTs mac STATUS STATUS EA 95-126, Dssiga controls failed to ensure adequate safety margia for 6, 1 RI OP-6 MOW I.D.1 MPI pumps fos certaia 1JXA scenarios (SLIII) R imas EEZ 95-22-04)

EA 95-126, Swapover of ECCS pumpa' suction from BMST tat five feet) to WOW 3.D.2 reactor building sump was iaad=Tiate (SLIIII 6, 1 RI. Mellen R Iwas EEI 95-22-04)

EA 95-126 EOPs allowed single LPI pump to supply two alPI pumps, with 6, 1 RI MOV II.A luas lasufficienL NPSM for LPI pump (SLIII) R EEI 95-22-04)

E4 95-126, Failure to take adequate corrective actions for tach 6, 5 RI MOV II.R twas volumes / level /suctica pelat (SLIV) R EKI 95 22-83)

RA 95-126 Failure to ensure fire water storage tank contained adequate 6, 1 RI Wow II.C twam volume of water ($ LIV 3 R ESI 9S-22-039 VIO 93-16-07 I= d=73=re 50P and AP procedures 6, 3 Mcpper 03 See IR 96-44 IFI 96- E e4-03, la 96-ce VIO 95-16-03 Inadequate procedure for operatics of the makeup pump 1A 6, 1 cooling water RI R

VIO 95-21-03 Failure to isolate the class 1E from the non-class 15 6, 1 Thomas /

electrical circuitry for the as purge and mial-purge valves RI R

TIO 96-01-01 T==aar te corrective action for MPI flow indication problem 6, 5 RI R TIO 96-01-06 Failure to correctly translate design basis of SW system into procedures, drawings, and lastructions 6, 1 RI R' VIO 96-04-02 Failure to take prompt corrective action la revising 6, 5 Mopper procachare VP-540 Plant Safety Verification (for STAS), VP- R See contained outdated and incorrect information.

TIO 96-05-01 Failure to create a PR and OCR for damaged main steam line 6, 5 ' = =haa, hangars Baghavan See URI 96-05-02: a Coordtaate with L.

Raghavan TIO 96-05-05 Failure to follow procedures for updating design basis documenta 6, 4 Crowley OP-8 R VIO 96-05-87 Imadequate receiving inspections for battery chargers twendor 6, 4 Schia testst R VIO 96-85-08 Failure to follow purchasing proce& ares for inverters 6, 4 Schia R VIO 96-06-82 No procedure for desimerallaad water flush performed by

' 6, 3 RI cmerators en borte acid additten lines R VIO 96-06-04 No evaluation om man-FSAR wital battery charger configuration 6, 4 RI R VIO 96-06-07 PR mot initiated to resolve CREVS test failure 6, 5 Immahan R

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T---- nascRIFrIon ARaa ame I. man la/ sat I.Icumsas ctnesmerrs ame STATUS STATUS VIO 96-04-01 Corrective action mot takaa on make-up system audit findings 6, 5 RI

& ==e===ive vibratica on speat fuel pool pump cooling fan motor R

VIO 96-09-03 Failure to perform a 18 CFR 50.59 safety evaluation for s. 5, 3 Thomas ehang-= to procedures described La the FSAR for controlling R dissolved hydrogen concer.tration la the RCS l v10 96-09-04 Failure to update operattag curves to reflect 1981 power uprate 6, 4 Thomas R

VIO 96-09-05 Failure to incorporate design change of 8EJV-64 into operations procedures 6, 4 Thomas / Licensee )

Crowley R Denied vio VIO 96-09-04 Three -= ==rles of design control errors terrr=== 6, 4 M. Miller 0P- 9 calculation imputs and Is! " * -yt R VIO 94-09-07 heimely corrective actione for the EFIC system concerns and probleme 6, 5 Thomas A

VIO 96-11-04 Reactor building sump mot constructed in accordance with 6, 1 E' approved construction drawings R VIO 96-15-62 Failure of reactor coolaat pump oil collection system to 6, 1 u. Miller retain oil leaking from reactor coolant pump R VIO 96-28-81 Failure to adhere to reactor coolar.t system cooldomen limits 3 RI VIO 96-20-82 Failure to follow procedure AI-400C for review and 1 RI develeg=-e of Malatenance Procedure PM-191, Nata turbine / Generator. F h eter Turbine layup IFT 95-15-01 Design requiremento for altregen overpressure toervice wateri I L. Mullea Meed to review R licensee's calculation 6 conclusion. See IR 95-21 IFI 95-15-82 Design requir====em for dynamic 10CR effects 1 See IR 95-21 and TIA R 96 011 '

IFI 95-15-03 Design requirements for reactor coolant pump cooler failure 1 See IR 95-21 and TIA R 95-014 IFI 95-15-04 Code requirement for thermal relief valves on decay beat 1 removal heat enchangers See IR 95-21 and TIA R 96-014 IFI 95-14-05 Relief valves removed from heat ==ch= agers 1 See IR 95-21 and TIA R 96-014 IFT 96-03-15 Evaluate the licensee's revised TS Sases and related le CFR 59.59 analysis for MPI flow indicators 2 RI R

IFI 96-11-62 Potential for RPI/LPI recirculation resulting in make-up tank overflow 1 RI See s1.L3 D.I. 1 R IFI 96-11-94 M P ey of 10 CFR 58 Appendia R fire study and A'es - ar. ion 1 v. Miller R IFZ 96-201-11 Design basis for decay heat / core flood / reactor coolant piping temperature I ranahan Identified la IPAP , A report as IF-96-201-01 IFI 96-201-12 Conduit siting criteria - j - iag ratio not considered 1 Fillion Identified la IPAP R report as IF-96-201-02

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ISSUE DaauuPT10H AAEA 3IRC Z.IAD IR/SER LICENSEE CCBSEEIFTS NRC STATUS STATUS samma 255Uma LTOP Qarrent TS does not address LTOP prevention or mitigation. 2 R. system branch will on the basis of CL 88-11 the licensee submitted informatica R to demonstrate that LTOP in S&W plants have less them 1 in send letter to 100 reactor years probability of occurrence and as a result licensee that they per GL 38-11 moe-appendia G met h logy can be used for FT have to submit TS.

curves. Such a PT curve wai.1d provide for hip,er LTOP enable pressure and temperature and would provide operational flexibility, staff denied the request la 1995 ami regmated a1997 revised response. The licensee espects to respond late Apper.lix A Appendia B design basis issues review by FPC consultant. 3ERC review opea Appendix R issues to assure that there are no W. Miller / D-11 R restart or coerability issues imbedded in them. Fillion/

una operator NEC review operator workarounds list to assure that there are uorkarounds RI M-2 See VIO $6 09-07 no restart or coerability issues contataed in then R 50.54f Letter NRC review licensee *s 50.54f letter response (due 2/3/97) on desicyn bases WRR R

License verify license conditions are met conditions R1 A

RC Loop  != a survey inspection, the staff noted that certata branch 2 mRR pgP i ng pipes off the primary coolant loop were not analrzed as code R class 1 pipe si.... no fatigue analysist as required by the Analyses code. seed mRR technical branch s opinion on this Sources Plants), Resident's OIL, PM's OIL for issues include: IFS, SIMS, NUREG 1435 (Status of Safety Issues at Licensed Power NOTE:

Open allegations, OI investigations, and emerging / draft issues are listed separately.

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4 CRYSTAL RIVER 3 ISSUES CHECKLIST j N ITEMS (INSPECTION PRIOR TO RESTART IS NOT NEEDED)

I Status as of February 24, 1991

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i 155K DE50LIPTION 1 AAEA MllC LEAD IR/SER LIEM5EE STATUS CaelENTS NRC STATUS LICEN5EE*5 RESTART LIST W DESIQi-RELATED 1554K5 (D.I.s)(per 18/28/96 Itr from FPC) 1' '

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t!EFR*5 CTWR RESTART ITEMS CT5G Tdes Adequacy of 075G tde stress-retteved rolled Jotats is questtened. libCG

7 analysts of a Davis-8 esse pulled OT5G taae. current test data. and limited See licensee Precursor N (G) i field empertence conflict with test data from 1972 maitch *<paltfeed a Card PC %-5077 of j stress-retteved rolled fatat 11/6/96. (No TIA)

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$ Lft! W D-04 Meassing of percent t%ll indications with an wupalifled i 7 procedure See IR %-M. Generic N (G)

) issue being addressed by Iful (no TIA) ist! 50-05 Eocy current sample expansim based cn degraded Ede percentages 7 See LR 96-06. m (5)

O 96-06-13 Justification for removal of Therno-Lag protection from the source range 1 tastnmentation M (5) 15t! %87 03 Incorrect laformation provided by contractors 7 **

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O 96-201-06 Preferred offstte electrical peer source with plant shut ocws (500 ke 1 switoryard) is not spaltfted. mote- t>tti this assue as resolved. m (5) licensee ss act ustag 500 cv switctward as an etertrical ener satrce tRI 96-201-09 Testing to galtfy relays beyond manufacturers' rattags tes inadequate 1 N (5)

LIR 93-02-82 Switchyard cable fatture caused degraded voltage of Class IE electrical LER 93-02-03 7 buses and actuation of EDG LER 93-02-01 closed in IR N (I) 4 5 09 e

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ISSUE DESCRIPTION AREA 8AC LEAD IR/5ER LICENSEE STATUS C0m OTS NRC STATUS LER 94- 5 01. Def tetency in lAianding of techntcal rewirements leads to LfR 94-06-03. 2 nonconservative RP5 setpoint and potential violatton of T5 LER 94-06 00 closed in IR N (D)

LER 94-E04 tfR 94- E 05 W 16- See EA % 16.

LER E 09-00 attatmal release osing sulfur stontde delivery causes actuatta of tonte 7 cas avstter resultino in rantrol rnra carroenry ==ntilation actuation See IR 95-11. N (I)

LER 95-13-01 Inadequate procedure causes 6 cooling imater th to ade@ ptsp 1 resulttre la operatton outside the design basis LER 95-10-00 closed in IR N (I)

W 16. See also W I 95-11-02. V!O %-16-03 LER W 17-00 SW th to control room cesters controlled by air cperated salves =Alch 1 could fati noen See IR E16. V10 %-01 N (D) 06 LER E 18-00 Inadequate 15 note alloned delayed entry into 15 LCD LER W 18-01 2 See NCV E 18-05. N (I) tER %-1p LER 95-19-00 Leat tastr.nentattras for SW th to RBCUs incapable ei acasuring 90 gpm 1 See IR W IS. N (I)

LER E 23-81. Inconsistent destgm assimptions cause butiding spray fh rates to be ifR 95-23-02 outsto= desem basis I t[R 95-23-00 closed in IR N (I)

%-04 LER 95-25-00 Inadequate tsolation of safety /non-safety related circuits LfR %-25-01 1 See V10 95-21-03. N (D)

LER E 28-00 8W5T vectam breder has inadewate reiter capacity tfR %-28-01 1 See IR 95-21. N (I)

LER %-01-01 UIC control circuits aisrouted: Appendta R concern 1 LER %-01-00 closed in IR N (1)

%-04: See also NCV 96-01-03 LER E 02-00 Ittatpurge valve has safety /non-safety related circutts withmet isolatics: 1 See 110 95-21-03. N (I)

LER W O3-00 EC5 coolotne rate exceded dstag cood ifR %-03-01 3 See W I 95-21-04. N (1)

LER WO4-00 CDE control d+i fomd damaged & leding 1 See E l W C2-02. IR W N (D) 21 LER E 05-01 SW th to RSCDs could enceed destgn 1 LER WO5-00 closed in IR N (D)

W O4 See also VIO %

01 01 LER %E00. WI instriment m- could result in WI pimp rmout tfR %-E01 1 See IR 95-20. It % 04 N (0)

CR3 0 f 2 LER W O7-00 WI line SSLOCA/ LOOP / loss of dc bus could have igadewate WI fb ifR W 67-01 fastriswntation 1 See IR E 01. CR3 0.I 2. N (D)

LER W OS-00 Ambt;peus T5 note results la mt perforting RC5 leak swwet11ance prior to 2 Mnde 2 m (5)

LER W O9-00 Failure to reattacta instrsment tacing to setsste supports after 1 unetsf w ati m leads to creratton outsede deseos basts See $ 1 E 03-06. IR W N (I) 05 LER E 13-00 Los basss ficne in SW system cooled components causes operation outside destyi I See VIO W16-03. N (D)

LER 5 11-00 Personnel error causes testing deftesency resulttag ta condttton 1

,_ prohibsted by tanrowed TS IGt % 01 iss W ) See !fA #L601 (GL WO3). N (D) i

- 4 10 8

ISSUE DESCRIPTION AREA NRC tEAD IR/5ER LICENSEE STATUS COMMCVS NRC STATUS LER % 12-00. Operation outside design basis caused by battery chargers having 4 LER W 12-01, taeJequate test results accepted la error See VIO 5 05-07 N (D) tfR E 17-02 LER W 13-40 4erator error resulted la the inadvertent actuatta of DCP-1A 3 See NCV E 03-02. N (1)

LER % 15-00 Personnel errors cause ca>'., separation / Isolation concerns resulting ta 1 aperattan outssde the e.stgn basis (tomte gas annitors) See IR E 04. N (1)

LER 5 16-00 CREV5 filter testing <Id not meet 15 specs 2 RI N (5)

LER 96-19-00 Ilm-safety related switch used la safety related wiring for E5 status 1 lights See (Ri %503. N (D)

LER %20-00 Unrevlemed safety questions cacerning EDG overloading caused by 4 taterpretstion of regulatory reestrements R-2. 0-6. D-14 See eel %12-02. N (D) 0-15 OP-5 LER 5 23-00 Personnel error leads to atssed save.11ances resulting in violattan of 2 See V10 E 15-01.

Tecntcal Spectfications (atssed remote shutdann panel EFW pimp pressure N (D) instriment channel chect)

LER W 24-00 Plant modification causes manalyzed condittm regarding emergency 1 fee &ater See LRI %12-01. N (D)

LER 525-00 Personnel error causes testing deficiency resulting la ccmdttson . 1 tbsted by Technscal Spectfications (12 contacts la ES logic tere not See PfA R 601 (GL 5 01). N (D) tag testea) -

t10 94-25-01 Fatture to properly control the Control Comples inabitability Envelope

! door blocted open for metatenance wwti 6. 7 See URI 95-02-02. N (D)

VIO 94-27-02 Failure to ade tie 10 CFR 50.73 reports to the sfic withta the required ttee 6. 2 (P-4 See IR 95-02. sR E 08. N (1) v!O 94-27-03 Fallwe to ade me reestred 10 CFR 50.72 report to the NRC withta the required tlar 6. 2 OP-4 See IR E 08. N (1)

VIO 96-01-05 Iwo examples of fattwe to secate FSAR as required by 10 CFR 50.71(e) 6. 4 N (5)

VIO 96-02-01 Fallwe to metatata 8.2 footcandles la the protected area 6. F See IR %-07 N (5)

VIO 96-02-34 Failure to metatata seconcery alara station operable and taasequate crapensatory measures 6. 2 N (5) v!0 5 03-11 Fatture to follow radiation sort perutt reestrements 6. 7 E (5)

V10 96-03-12 Fallwe to report the transpcrt of a radtoactively cmtaatnated individual offstte 6. 2 N (5)

V10 E 03-13 (> escorted visstor persoscel within the protected aree 6. 7 N (5)

1. 10 96-05-04 Licensee approvad eddy current acceptance criteria different from TS regnroments 6. 2 N (5)

VID E 06-06 Failure to timely nottfy the Isic of a condition cutside the Appendia R tscenstag dest e basis 6. 2 N (5)~

V10 96-07-01 Fallwe to protect safegueras informaiton 6. 7 N (5)

' s 11 8

ISSUE C5CRIPTION AflEA NRC (EAD IR/5ER LICENSEE STATUS COMMENTS fiRC STATUS VIO %-07-02 Failure to couplete screening elements for Fitness for Duty Personnel 6. 7 N (5)

VID E 09-01 Fatire to follow a maintenance procedse resulting in the inadvertent initiation of the control rama suergenry wentItation system 6. 7 N (5)

V10 E 09-02 thescorted visttor personnel witata the protected area 6. 7 N (5)

VIO % 11-01 Inadequate nort instructions to prevent the inadvertent start of tre A EDG 6. 7 N (5)

V!0 96-11-03 Persmnet performing eart on the reactor building sump without logging onto a clearance as required by approved nat 6. 7 N (5)

VIO % I5-01 Failure to perform a rewired T5 survetilance for the remote shutdcut panel 6. 2 N (5)

If! 94-18-09 Review periodic vertfication plans - POW (CL 89-10 stem) 2 See IR 95-11. IR 95-21: N (I)

See GL 89-!0 IFI 95-02-05 Resonance noise in victatty of MN-25 7 N (St IFI 95-08-03 Emergency Operating Proced w e sedate program 3 See IR 5 16. VIO 93-16-07 N (5)

Ifl 5 11-01 SCBA requirements for personnel Artag a teate gas release 2 N (5)

IFI % 21-02 Modtfication to the staney feed.ater pump rectrculation line I N (5)

IFI %-03-16 Review of 8t4R %82-09-01. WI flow indicators. tratallation package and 1 f mettonal testing results N (5)

If! E04-03. Effect of setpotat calculations on EDP revisions 1 See V10 93-16-07 N (D)

If! 5 05-06 Large breat loss of coolant analysts generte concerns 1 N (5) f IFI % 08-02 IhTh N kIh hh k kh ihf $k h Reactor building cavity cooltag piping thermal reitef protection 1 See 0.1. 8. GL 96-06 N (0)

ITI 96-15-03 Acttms taken to resolve post-accident recreticality Concerns de to I loraltred teron dilution NRR reviewirg. generic B&W N (G) issue MTI.PtAmT ACTimf5 MPA M 105; 5etssic qualtftcattom of ewtpment ttcensee's criterta and proceares 2 GL 87-M approved. Some issues are pending and =euld be resolved thru audit Expected ccupletion N (5)

(sdie4eled for Mar 97). Licensee 5 field walkd:wn results are currently December.

in staff rewten W A #111 (IP D : IPE and IPEEE - These are in staff rewtew. Net a restart tree.

• 4A 118 (IPfE O 2 N (5)

W A #X6 E; NRCS Movement of heavy loads over spent fuel cool l %-02 2

- tirensee response in staff review This wadd not be a restart issue N (5) 9 I

'2

ISSUE DESutIPTION AREA MtC LEAD IR/ SEA LICINSEE STATUS COMENTS NRC STATUS MPA R208; Thermolag - Licensee plans to use Mecattss GL 92-08; BU 92- 2 See IR %-01; la %-06 N (S)

(an alternate matertal). some reanalysts of APPDOII R. and some 01 enesotion. Fire barrier tests of stecattss including Aspacity tests are in staff review This also may not be restart issue PPAf L201: Reactor vessel struttural integrity. RAI to Itcensee on 7/22/%. Only a 2 N (S) fa. S 01 Rev 1. data base issue, set a restart stem.

Sep 1 MPA A604; Boraflex degradation. Licensee response is just in. Staff review to GL %-04 2 N ($)

commence. Ints may have to be aosressed prior to restart because of sensttsvtty to spent fuel pool issues MPA POf testing & surveillance. This item ts closed with the exception of IFI 2 CL 8970 94-18-09 on pertodic vertfication. which is to be foliched to after a new See Ifl 94 15-03 N (1) cenerte communication as issued t!Cfh5F AMDOMENT/ ret!EF Rf0 TEST 5 R G 1.97 RG 1.97 instrumentation - Subcool monitors etc - category change. License 2 Instruments amendment may be approved by Decemeer N ($)

Slometrics & Blanetric exemption to allow taking security badges offstte - Staff review 2

• m etty is espected to be complete soon N 45)

Core ficod Relief request RE: Core flood nozzle - Staff needs more info. Mt will saozzle 2 N (5) teco R11 tafonned CT5G Tdes OT5G tube testing - Licensee prwosed a revised DT5G tree acceptance 2 See VIO %-05-04 N ($)

criteria I

l l ma issrs Pressartzer Durtag Refuel 9 a ste-surface (N was discovered. The IICensee l

Nozzle flaw 2 better inspection during 810 and found the fW to be acceptable. performed The new N (S) inspection results to reduced flaw stre and conse@ently acceptance criteria ( dich is based on ratto of flaw to thickness) changes Staff review in progress Crittcality The licensee did not carry a previously a; proved exempttcn from part 70 2 ttanitor (70.24?) requirements to Part 50 Itcense. Need legal interpretation of N (S) l the status cf the escuDtfcn Sources for issues include: IFS. SlHS. NUREG 1435 (Status of Safety Issues at Licensed Power Plants). Resident's Oll.

PM's OIL NOTE: Open allegations. OI innstigations, and emerging / draft issues are listed separately.

LIST OF ACRONYMS USED -

AP Abnormal Operating Procedure BWST Borated Water Storage Tank 13

)

. . ___,m__ . _ . _ _ _ _ _ _

C' Closed

.CCHE  :. Control Complex Habitability Envelope' CFR ' Code of Federal Regulations.

CR3 0.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 E0P' Emergency Operating' Procedure FSAR- Final Safety Analysis Report GL .

NRC Generic Letter ILRT' Integrated Leak Rate. Test (of the Reactor Building)

IFI' ..NRC Inspector Followup Item

.LER; Licensee Event Report LOCA . Loss of... Coolant ' Accident LPI Low Pressure Injection

'LTOP Low Temperature Overpressure Protection EMPA: NRC Multi-Plant Action MUV Makeup Valve-

.N (D) Not an NRC Restart Item (because the issue is duplicated by a restart item)

.N (G) 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

-NPSH. ' Net Positive Suction Head

OCR . Operability Condition Report OP l Operating Procedure

PR LProblem Report R. 'NRC Restart Item RB.  !. Reactor Building RCS  : Reactor Coolant System RMG Radiation Monitor SFP l Spent Fuel Pool ,

tTIA1 NRC Task' Interface Agreement' (between NRC offices)-

TS . Technical Specifications URI- ,LNRC. Unresolved Item JUS 0- ".Unreviewed. Safety Question

.VIO f NRC Vi01ation

. 0FFICIAL RECORD COPY DOCUMENT NAME: 5:\DRS\EB\CRISSUE1.350:

l . .

3 -i '14

$tatus as of 2/19/97 CRYSTAL RIVER RESTART ISSUES CHECKLIST i ISSUE MC 03S0 RESP. REFERENCE STATUS REF APP A ASSESSMENT OF ROOT CAUSE-IDENTIFICATION AND CORRECTION I 5$$dVi%nrNihWi6iAIisl6}@ WillW8 IpfniEff Mdi;Q)$" $$

farefcleaHFinndefstobdEMMWA >

RsnW M WMPso Md!^4u WaM

[88 ire ${T ${jsi d$ 6 fjs?E $difl8S % j?iM{$$ihfE N cofring!shutdownicisarlb RN 9CP E @J  % w QWi N?

fUnceistdod!MFMM6%@@65ds D%b 64b[M M 3 hi% " MUM n## [d F  ?!

IMdffds0seE6fl5E$$Tl0Eifilsdf$ 650iTc@

[W"M@ @$6iff 'E d$ @1S5M$3 problems 0cleanliiuhderstobd W N a SWW 10"Y"T@

Effectiveness of root cause C.1.1 d. Panel 0 analysis program Thoroughness of corrective C.1.3 a.

action plan Panel 0 l Completeness of corrective C.I.3 b.

action plan Panel 0 Control of corrective action C.1.3 c. Panel 0 item tracking Effective corrective actions for C.1.3 d. Panel 0 the condition requiring shutdown implemented Effective corrective actions for C.1.3 e. Panel 0 other significant problems implemented Plan Control of long-term corrective C. 1 . 3 f.- Panel actions Effectiveness of corrective C.I.3 g. Panel 0 action verification orocess Effectiveness of QA Program C.1.4 a. Panel 0 Effectiveness of' industry C.1.4 b. Panel-experience review program-Effectiveness of Licensee's C.1.4 c. RII 0 independent review groups Effectiveness of deficiency C.1.4 d. Panel reporting system 0 ATTACHMENT B

ISSUE HC 0350 RESP. REFERENCE STATUS REF APP A Staff willingness to raise C.1.4 e. Panel concerns 0  !

Effectiveness of comitment C.1.4 9 Panel 0 tracking program I External Audit (i.e. INP0) C.1.4 h.

capability ASSESSMENT OF LICENSEE MANAGEMENT EFFECTIVENESS Goals / expectations communicated C.2.1 a. RII to staff Demonstrated expectation of C.2.1 b. RII adherence to procedures Management involvement in self- C.2.1 c. RII &

assessment and independent self. i0 NRR assessment capability Effectiveness of management C.2.1 d. RII review committees 0 Management's demonstrated C.2.1 e. RII 0 awareness of day-to-day operational concerns Management's ability to identify C.2.1 f. RII & 0 and prioritize significant NRR issues Management's ability to C.2.1 g. RII & 0 coordinate resolution of NRR significant issues Management's ability to C.2.1 h. RII implement effective corrective 0 actions Impact of any Management C,2.2 a. RII &

reorganization 0 NRR TENEUi/siie$NEditliiisfyR'WP [6I$21$$ $$s x !$i95{05 oi y s ; h &N?

irssolbt'ibinofj@]p;ssic6riderris&

mn y 3 x We& ?IRt96s09w$ [6h60' dom L, q ggy wu g; y gg Adequate engineering support as C.2.2 c. Panel demonstrated by timely resolution of issues ATTACHMENT B

4 t

ISSUE MC 0350 RESP. REFERENCE STATUS REF APP A Adequate plant administrative C.2.2 d. RII 3rocedures - 0 Engineering / Licensing Effective information exchange C.2.2 e. RII 0 with other utilities ASSESSMENT OF PLANT AND CORPORATE STAFF EFFECTIVENESS Demonstrated commitment to C.3.1 a. RII &

achieving improved performance NRR

~ ' ' -

Demonstrated safety C.3.1 b. Panel consciousness Understanding of management's C.3.1 c. Panel expectations and goals Understanding of plant issues C 3.1 d. Panel and corrective actions 4

Qualifications and training of C.3.1 e. RII staff Attentiveness to duty C.3.1 9 RII Level of attention to detail C.3.1 h. RII &

NRR .

Staff overtime usage C.3.1 j. RII Procedure usage / adherence C.3.1 k. RII Awareness of plant security C.3.1 1. RII Licensed operator staffing msets C.3.3 a. RII requirements and licensee goals Level of formality in control C.3.3 b. RII room Effectiveness of control room C.3.3 c. RII simulator training Control room / plant operator C.3.3 d. RII awareness of equipment status Adequacy of plant operating C 3.3 e. RII procedures Procedure usage / adherence C.3.3 f. RII Log keeping practices C.3.3 g. RII ATTACHMENT B

ISSUE HC 0350 RESP. REFERENCE STATUS REF APP A ASSESSMENT OF PHYSICAL READINESS OF PLANT Operability of technical C.4 a. RII specification systems Operability of required C.4 b. RII secondary and support systems Results of pre-startup testing C.4 c. RII J

~

Adequacy of system lineups C.4 d. RII Adequacy of Surveillance C.4 e.

tests / test program RII '

Significant hardware issues C.4 f. RII resolved (i.e. damaged equipment. equi modifications) pment ageing.

Effectiveness of the plant C 4 h. RII maintenance program Maintenance backlog managed and C.4 1. RII impact on operation assessed Adequacy of plant housekeeping C.4 j. RII and equipment storage ASSESSMENT OF COMPLIANCE WITH REGULATCRY REQUIREMENTS Applicable license amendments C.5 a. NRR have been issued Applicable exemptions have been C.5 b. NRR granted Applicable reliefs have been C.5 c. NRR granted Significant enforcement issues C.5 f. RII &

have been resolved NRR Allegations have been C.5 g.

appropriately addressed RII 101CW2?2061 ftT55sfh bppropriatel fa'ddresssd]FElb;ejsd Cl5jj NRif] NAIFEB 19 % 97]

COORDINATION WITH INTERESTED AGENCIES AND PARTIES ATTACHMENT B

ISSUE MC 0350 RESP. REFERENCE STATUS REF APP A Federal emergency Management C.6 a. RII &

_ Agency NRR Appropriate Sate and local C.6 e. RII officials Appropriate public interest C.6 f. RII &

groups NRR Local news media C.6 g. RII 4

ATTACHMENT B k

~

$tatut 41 Of* 2/12/97 CRYSTAL RIVER RESTART TASK CHECKLIST TASK HC 0350 RESP. REFERENCE STATUS

~

REF APP A

!Ihsue7preliininarprnotsiiidit' ion? ~ 8925is! . !R lif -

<'+

lCi Congressional Notification B.2 g.

[E$ti$klisfi$Rhstaf6

, m . Pans [yl lBMai[g[

,,g lRiI3NRRs fil/Nk< [ s'

>m m._ . . .. ..

.m .

tSOEsitr3

_ . . ~ . . ..

TAssessFava11h _ble( _informationt 1 Bi3f bi s 4 %nelu ,Me i 10s

~ '

!DhiilS$dassI56hEIfi$ChicklYsti $3 ff! ' ' siIONRR? if/1'3755$ @

Develop Restart Action Plan B.3 g. RII. NRR 0 Regional Administrator Approves B.3 h. RII Restart Action Plan NRR Associate Director Approves B.3 1. NRR Restart Action Plan Implement Restart Action Plan B.3 j. RII EV5TUhtsif@fyg[olfBPAP, Bi4j][6] EI; P

Inspection 2/J12/9J C Ilikense$peNotMsWooEcau$et '

tanalysista'ndide'velopsicorrectisek 'BMIME " '

'1

iicEnssel iactionfplan

~

' ~i~~ s

('% *m t x ,

NRC evaluates licensee's root B.4.1 c. Panel 0 cause determination and corrective action plan Review licensee generated B.4.3 a. Panel restart issues 0 Independent NRC identification B.4.3 b. Panel of restart items (consider 0 external sources)

NRC/ Licensee agreement on B.4.3 c. Panel restart issues Evaluate Licensee's restart B.4.3 d. RII issues implementation process Evaluate Licensee's B.4.3 e. RII implementation of verification 0 process Evaluate Licensee's restart B.4.5 a. RII readiness self-assessment ATTACHMENT C

TASK MC 0350 RESP. REFERENCE STATUS REF APP A NRC evaluation of applicable B.4.5 b. Panel items from ISSUES section below complete Restart issues closed B.4.5 c. Panel Conduct NRC restart readiness B.4.5 d. RII team inspection ,

Issue augmented restart coverage B.4.5 e. RII inspection plan

'~' -

Comments from other parties B.4.5 f. Panel considered Re-review of Generic Restart B.4.5 h. NRR Checklist complete Prepare restart authorization B.5 a. RII &

document and basis for restart NRR NRC Restart Panel approves 8.5 b. PANEL Restart Authorization No restart objections from other B,5 c NRR. RII applicable HQ offices l PANEL No restart objections from B.5 d RII &

applicable Federal Agencies NRR Regional Administrator concurs B.5 e. RII in Restart Authorization NRR Associate Director concurs B.5 f. NRR in Restart Authorization ED0 concurs in Restart B.5 g. NRR Authorization when required Conduct ACRS briefing when B.5 h. NRR requested Conduct Commission briefing when B.5 1. RII L requested NRR Commission concurs in Restart B.5 j.

Authorization when required Regional Administrator B.5 k. RII authorizes restart ATTACHMENT C

/- ,

TASX- MC 0350 RESP. REFERENCE STATUS REF APP A Notify Commission of restart B.6 a. NRR authorization (if Commission did '

not concur in Restart Authorization)

Notify EDO of restart . B.6 b. NRR authorization (if ED0 did not concur in Restart Authorization)

Notify Congressional Affairs of B.6 c. NRR restart authorization-

... . Notify ACRS of restart B.6 d. NRR authorization (a briefing may be substituted) l- Notify Applicable Federal B.6 e.

agencies of-restart authorization Notify Public Affairs of restart B.6 f. RII authorization Notify State and Local officials B.6 g. RII of restart authorization Notify citizens or groups that B.6 h. RII expressed interest during the restart approval process ATTACHMENT C t