ML20141J691
| ML20141J691 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/15/1996 |
| From: | Jaudon J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 9708210085 | |
| Download: ML20141J691 (27) | |
Text
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% ! No mbe 15 1 96 MEMORANDUM T0: File FROM: J s P. Ja do . Dupty Director 01 ision o Reactor Safety
SUBJECT:
MINUTES OF CRYSTAL RIVER RESTART PANEL FIRST MEETING.
NOVEMBER 13. 1996 In accordance with Memcrandum from Stewart D. Ebneter, dated November 1. 1996.
Subject:
CRYSTAL RIVER UNIT 3 RESTART PANEL AND ACTION PLAN. (Attachment A), a Restart Panel was assigned for the restart of Crystal River. The Crystal River Restart Panel met at the Region II office on November 13, 1996. The i
Jurpose of the meeting was to: (1) develop a Restart Plan (2) develop a Restart Task Checklist. (3) develop a Restart Issues Checklist, and (4) to l schedule future meetings.
l The following personnel attended the meeting:
Panel Members - Johns P. Jaudon. Region II Chairman Frederick J. Hebdon. NRR. Vice Chairman Charles Casto. Region II. DRS
!. Kerry O. Landis. Region II DRP
} Lakshminaras Raghaven. NRR Others -
Todd Cooper. Resident Inspector
- Todd Cooper. Resident Inspector. participatca by phone as a substitute for the Senior Resident Inspector.
The following summarizes the actions taken by the Panel:
- 1. The draft of a proposed NRC Restart Plan was presented by the Chairman and discussed in detail. After discussion and modifications the following Restart Plan was adopted:
- a. Develop a checklist (i.e. matrix) of all open issues at CR3: this matrix will have non-docketed supplements that show all open allegations and 01 investigations.
' b. Identify the tie points in the matrix (e.g., a LER that is also an unresolved item, which is also an Allegation). 3 N001P> I Il
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- c. Group the items by issue (e.g., examples of lack of knowledge of I the design basis),
- d. Have the licensee develop a package for each issue from the basic matrix of which the licensee has knowledge (e.g., LERs.
Violations, etc.).
- e. For each issue grouping developed in c. above, assign an inspector to review all the items in the group and to verify by insoection of a samole from the group that the licensee is closing the issues appropriately. If the sample verification indicates that the
~ licensee has addressed the issues inspected, close the grou If there are problems with the verification expand the sample.p.
Repeat as necessary until the group is all verified or can be closed based on the expanded sample,
- f. There are several enforcement items concerning engiheering performance in process. There items should be combined and arocessed rapidly rather than waiting for additional examples to 3e identified. if there are additional examples found later.
l these should be dispositioned in accordance with the Enforcement Policy. -
-9 For allegations, inspect and resolve the technical issues. For l late filed allegations, use the late filed process (i.e. assume l that the allegation is substantiated and determine if it would therefore affect the restart recommendation). Have the EICS staff brief the panel on the status of allegations and investigations.
- 2. In accordance with 1.c. above, the panel developed the following Basic Groups for the issues:
(1) Knowledge of design & . licensing bases and adequacy of design margin (2) Regulatory knowledge and perspective (3) Operator performance & knowledge (4) Marginally effective Engineering Organization (5) Management Oversight including 0A and self assessment (6) Corrective actions (7) Other
- 3. A draft issues matrix was provided to the panel. The issues matrix was subsequently characterized by areas above and will be reviewed by panel members prior to the next panel meeting to identify which items need to be closed before restart. The issues matrix is Attachment B.
i 3
, _ _4 . NRC Inspection Manual Chapter 0350 was reviewed and Case pecific Checklists prepared using Appendix A of MC 0350 as guidance. The checklists are included as Attachments C and D to the Restart Plan.
- 5. The list of all open allegations and 01 investigations was reviewed and discussed.
- 6. The following future meeting dates were agreed upon:
December 3.-1996 (7:30AM) -
Site December 18. 1996 - Region II January 8. 1997 - Site January 22.-1997 - Region II l Docket No.-50-302:
Attachments: A. Restart Panel Assignment Memorandum B. Specific Issues Matrix ;
C. Crystal River Restart Task-Checklist !
D. Crystal River Restart Issues Checklist Distribution- .
Docket File w/atts L. Mellen. DRP/RII w/atts !
S. Ebneter. RA/RII w/etts S. Cahill. DRP/RII w/atts '
C. Casto. DRS/RII w/atts B. Crowley. DRS/RII w/atts K. Landis. DRP/RII w/atts R. Schin. DRS/RII w/atts J. Johnson, DRP/RII w/atts M. Inomas. DRS/RII w/atts-F. Hebdon NRR w/atts L. Raghaven. NRR w/atts G. Tracy. EDO w/atts R. Zimmerman. NRR-S. Varga, NRR
- FOR PREVIOUS CONCERENCE SEE ATTACHED COPY rytter Rtt. net ett. net SIGNATURE NAME 8Crowley* JJaudon*
DATE 11 / / 96 11 / / 96 11 / / 96 11 / / 96 11 / / 96 11 / / 96 COPY 1 YES NO YE5 NO YE5 NO YES NO YES NO YES NO grr RIAL nr.Wed WPY LAX 1ftNL NM;. r atnicPl . mig
3 .
- 4. - NRC Inspection Manual Chapter 0350-was reviewed and Case 5pecific Checklists prepared using_ Appendix A of MC 0350 as guidance. The 1 checHists are included as Attachments C and D to the Restart Plan.
- 5. The list of all open allegations and 01 investigations was reviewed and discussed.
- 6. The following future meeting dates were agreed upon:
December 3. 1996 (7:30AM) - Site December 18. 1996 - Region-II
. January 8. 1997 - Site January 22. 1997 - Region II Docket No.-50-302 i Attachments: 1. Restart Panel Assignment Memorandum
- 2. Specific Issues Matrix
- 3. Crystal River Restart Task Checklist
- 4. - Crystal River Restart Issues Checklist Distribution:
Docket File w/atts L. Mellen._ DRP/RII w/atts S. - Ebneter. RA/RII w/atts - S. Cahill. DRP/RII w/atts C. Casto. DRS/RII w/atts B. Crowley, DRS/RII w/atts K. Landis. DRP/RII w/atts R. Schin. DRS/RII w/atts J.--Johnson. DRP/RII w/atts M. Thomas. DRS/RII w/atts F. Hebdon.-NRR w/atts L. Raghaven NRR w/atts G._Tracy._EDO w/atts R. Zimmerman. NRR-
-S. Varga. NRR
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l wrtre ef f @t attI l stGMAtunt
.{ h l wit 8Crowley M aucon /
l OAtt 11 /_/ < / 96~ 1M b / 96 11 / / 96 11 / / 96 11 / / 96 11 / / 96 l torvt 77h/ m (vts) m- vis e vts e vts - m- its - m wr tilA RWKO LUFY WCurt.Ni IvW., r;\LivoPl.M 6
4 J. Jaudon, et al 2
- 4. Maintain.an ongoing overview of licensee performance throughout the i corrective action process to include periooic meetings (at least i biweekly) among members of the panel.
- 5. with the licensee to Conduct periodic discuss progress toward meetings (at least satisfactory monthly) ion of the program.
complet
- Heetings with the licensee will. typically be open to the public.
. 6. Provide oversight of the NRC's followup activities. Review NRC inspection and assessment plans and findings, and licensee performance.
identify areas where NRC inspection and technical review are needed.
l' 7. Periodically provide assessment of licensee performance and corrective
- actions to NRC management with appropriate documentation (at least monthly).
. 8. Based on the satisfactory completion of the li' Jee's restart program.
provide a recommendation to the Regional AF ..strator and Director. NRR
); for approval to restart.
I Docket No. 50 302 .,
l
Attachment:
Crystal River Restart Action Plan cc: 1., A. Reyes, RII
! F. Miraglia NRR S. A. Varga. NRR G, M. Tracy. OEDO R. P. Zimmerman NRR J. A. Zwolinski, NRR E. W. Merschoff. Ril J
CRYSTAL RIVER RESTART ACTION PLAN The Crystal River Restart Panel Johns P. Jaudon. Region II. Chairman Frederick J. Hebdon. NRR. Vice Chairman Lakshminaras Raghaven. NRR Kerry D. Landis. RII Charles A. Casto. RII Stephen J. Cahill. RII 9
4
. De
CRYSTAL RIVER RESTART ACTION PLAN
- 1. Puroose To provide a plan in accordance with NRC Manual Chapter 0350. Staff Guidelines for Restart Approval, and assign responsibility for NRC activities related to restart of the Crystal River Nuclear Power Plant.
- 2. Backaround On September 2.1996. FPC shutdown CR3 for repairing a pipe leak in the turbine lube oil system. While in this condition. FPC discovered several potential unreviewed safety questions involving the emergency diesel generator (EDG) loadings and design adequacy of the emergency feedwater (EFW) system. FPC plan for addressing these and other issues are currently in development.
Since 1994, the staff has observed significant performance concerns at CR3 (e.g.. unauthorized makeup tank test. nonconservative trip setpoints, missed surveillances and failure to follow procedures). Poor operator
>erformance was hi e iakeup Tank (MUT)ghlighted
. The staffbyalso theperformed Septembera1994 unauthorized root cause test analysis of of th'-
these adverse trends and determined the probable root cause, i.e. lack of management comitment. In response, the FPC initiated a Management Corrective Action Program (MCAP).
FPC's NCAP has not been effective in reversing the declining performance trend. Since its implementation, the staff observed continued notable deficiencies in personnel performance in general, and more specifically in the area of engineering. The engineering issues include, among others.
the inaccurate design basis curve for the MUT service water system design, and persistent control room and Technical Support Center ventilation system issues, poor quality of engineering relating to the Steam Generator tube plugging criteria, inadequate assumptions in the emergency operating procedures, inadequate safety evaluations, and implemerAation of modifications which compromised design basis limits. In April 1996, the staff identified five areas of concern: (1) inadequate management oversight and involvement. (2) configuration management and design bnsis issues. (3) lack of sensitivity to comply with regulations.
(4) a marginall" effective engineering organization and (5) poor operator perforicance. In July 1996, an IPAP and SSFI also confirmed the staff's
(.oncernS.
- 3. Resoonsibilj,tig 3.1 The Crystal,$jyer Restart Panel will coordinate staff activities, monitor licensen Ectivities, and keep the Regional Administrator informed regarding restart of the unit. The Panel will conduct periodic meetings wth the licensee to discuss progress toward satisfactory completion of the corrective action program. The Panel
C. j 2
will provide oversight of NRC inspection activitkes and provide assessment of licensee performance and corrective actions to NRC management. The Panel Chairman will provide periodic briefings to the Regional Administrator. Based on the satisfactory completion of the licensee's restart program the Panel will provide a recommendation to the Regional Administrator and Director of NRR for restart approval.
1 3.2 The Reaional Administr.gtn_r will coordinate with the Deputy Executive !
Director for Nuclear Reactor Regulation. Regional Operations and Research, and with the Director of Nuclear Reactor Regulation (NRR) in im)lementing the Restart Action Plan. The Regional Administrator will (eep the Director of NRR informed of staff and licensee restart actions. ,
3.3 The Associate Director for Pro 1ects. NRR will assure that the Comission is kept informed of staff and licensee restart actions 4
through Comission papers. E00 highlights, or comunications with the EDO. Based on these interactions between the staff and the Comission the need for Comission briefings will be determined by the circumstances and the Comission's wishes.
- 4. Action Plan Contents '
]
, The Task Checklist for the restart process will be prepared for Crystal River from the generic MC 0350 checklist. The Issues Checklist will identify all issues which need to be resolved prior to unit restart. The checklists will be maintained current and revised as appropriate by the Restart Panel. Sumaries. of the licensee programs and issues being
- upgraded and the scope of planned major inspections shall also be maintained by the Restart Panel,
- 5. Records All documents relating to tNe restart )rocess will be included in the docket file and, to the extent permittec by 10 CFR 2.790 made public in accordance with NRC policy. Such records include:
a) Minutes of Restart Panel meetings b) Minutes of meetings with licensee c) Other government actions comunicated to the NRC d) Commission papers e) Documents approving restart f)
Inspection reports g) Safety evaluations em
-. m ,. . , - , - - -.,w.. -- -
9' Attachment B CRYSTAL RIVER 3 ISSUES CHECKLIST Statue as of movember 15. 1996 The Crystal River Restart Panel met on November 13, 1996, and 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 z$ sus - xrTzas amma mac za/sma 1.z-== Coseawr3 mac LEAD STATUS STATUS LINam'S REST &aT LIST OF DESICES-REIATED ISSIMS (D. ?.41 (per 10/28/96 Str from FPC) 0 3 D.I. 1 NP1 pump recirculation to the makeup tama 1 See LEI 96-01-02 e
CR3 D.I. 3 HPI system modificatione to improve m m margias 1 See tRI 96-01-02 G 3 D.I. 3 LPI pump mission time 1 See LEI 96-201-01 G3 D.I. 4 Reactor building spray pump ITs NPSM 1 See tRI 96-201-02 C13 D.I. 5 Emergency fa n arer system upgrades and diesel generator load 1 See 121 9642-01; EEI impact 96-12-02 G3 D.I. 6 Emergency diesel generator loading 1 See EEI 96-12-02 03 p.I. 'P Failure h a and ef fects of loss of DC power 1 See Ier.a 96-12-01 G 3 D.I. O Generic Letter 96-06 (Thermal overpressure protectica for 1 Containment pipincy. penetrations. and coolerug
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ISSWE mammT*TIQat Aaan m Za/am L1- m ac .
taAB STATUS STATUS I LIcunem's p mestaar ITues CTSG Tubes M=Taney of CTSG tube screme-relieved rolled jotata is T see lie ====e Precareer questioned. Bus 0G analysis of a Davis-memae pulled CTSG tube. Card PC 96-5417 of current test data, and limited itold emperience conflict with 11/6/96 I test data from 1972 which *gualif ted* a stress-re11ewed rolled jotar.
GL 96-81 The 11- has iwified testing def aciencies la safety- 2 see MPA sL6el 4GL 96-en testiacy related loote circuits FTVE ARSAS OF w-a amussuu FmNeu, WTTE IP&P m- - " ZMSPSCTIces ARID RZZ m;--
ADDITZoBIS 1 P _m _ , - 1meressed inspectima of Probles identifications focusing on 5 Oversight - CA sudit s and the or-*1em reportino system. - Increased IPAP anspeccion of Problem Analysts and Ewatuations focusing on
! W rone cause evalumetons.
Inspecciam - mermal Amapection of Problem Resolutions focusing of detect inn and enrrect ton of repee tt ive avent s .
"m '_ - laspect/ Assess licemame's trendiaq tndlearors. 5 Oversight - 3 aspect IPAP tm - ._ M areas, includang processes for 04 RII A&11tions audits. Der f ormance assesseent s. and root cause evaluat sons.
laciude licensee's root cause evaluatson of IPAP findanos.
- laspect Problem Resolutacas focusing on the Proble= Becert system process, including tradrino of assigned act ion i t ems ,
timely comol+t ton of act ions, ased accuracy of te st at us information.
Marginally - Is. creased inspection of Engineerlag Problem Identification 4 Effective and Resoluticas with ==ph==1s on Itcensee evaluat tons for -
Engineerang sientffcant issues and work baetinos.
Orgaalaatio- - Inczessed inspection of Quality of Engineerings with
- IPAP emphasis om 30 CT1r se M9 screentno and saf ety evaluat tons,
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accuracy of t:se FSAit, aand management overs iant .
!==partien - amoraal inspectaan of Engineerang Proceduses end Programes focusing on root cause t rainine and correce ive act ions enneernino eha in-servic prnorame.
seasglaally - In=p-et/ Assess 11conose a trending indicat ors . 4 Effective - 2 aspect IPAP recommended areas. Aacludang the licensee's Engineering FSAR review proiert.
Organisation -irspect process for engineering calculations.
- Eli A&titions lack of - Zacreased lampectica of Englaeering Safety Fccuss focuslag 3 u-viar e on orcoer identificat ten of discrepancies alth the olent's Smo= ledge of design basis in t he correct ive act ion syst em.
the Design - lacr*=**d inspection of Engineering Froblem Identification Basis - IPAP and Resolutions focusing on programe for ident i f yino desi<==
3 be s t s i ssues mad capt ur t ne t hem in t he cor rect i* act son Inspection orogram.
- lacreased taspection of Quality of Engiacerlags focusing ca senate twity/umoerstandine tw the enoineertan/I tcensino staf f of the plant *s desien basis.
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AaEh MC 23/SM LIC MSEE N Ehc
. tahD STa258 sTA2US Lack o* - T==p-ee th 11oemeen's treadine tridtrators. 1 Adewate - Imepect IPhP recomuneded areas.
Emowledge of f the Design Seels - n11 Addit tene tack of - 1eeressed taspection of Engineering safety Focuss with 2 i sensStivity emphasis on interotet at ton of tec rvles eM rewlat lens. t for the w - Zacreased 4- p-e*1em of Quality of Engineeringa f acusing on to Comply , senatetwtev6saderstandtne by the enoineerino/Itcenstne staf f with - of Mac regulations.
Segulations -
IPAP W
Inspecttem tm og - Inspect /Assese licemese's trendine indicators. 2 Sensitivity - Zampact YPAP r- - '- + areas; includtag 50 59 for the Weed evaluations. L2ks_ and responses to NBC violet ions.
to Comply etch Begnalatione - ,
aiI Aastti<==
Cperator - Increased inspection of Saf ety Focuss focusing om refuelinra 3 '
performance - act ivit t ee, e =icat ion wit hin coerat ices, c*wemunic at ion IPAP =s t h ot her sit e groues, and overt ime Secommended - hosmai Amapection of Problem identification and Resolutions
!aspection focusing om observation of refueline activit tee, tenle=W at ton of management emoect ct ions, and problem r cooi ut 6 cws
- seoreal inspectiam of Cuality of Opesations; with eephasis on implementar ton of manaeement evo*ct at t ons, sens t e t yt t y to ennoit t one t hat coul d not ec t s a l l y deg r ade ewi zment reliabit atv, and cwacat ions and coordanat ton terween coeret tone and ot her s it e depart ment e.
- anormal snspect soen of Programs aM Procedures e
Operator - Imepect/Ameess 11c====e's t rendine indicators. 3 Performance - Saar=et TP&P recommended areas.
RIE Addittoms - Imapect procese f er coer abilit y evaluat ions.
InsesCToa partremum sYsrat Ut! 95-42-82 Control room habitability emwelope 3eakage. Encessive a See TIA 95003; FPC TS leakage paths through doose, dampers, and draias 4.= to change sequest so. 2os design errors and imek of surweillances/ preventive of 8/28/96: Leas 96-04, maint=== ace 94-10, 95-01, 95-04-01,95-09s IBs 95-02, 95-09, !
95-11, 95-16 95-21s FPC 1trs. of 5/26/95 and sa/2ttes Ult! 95-821-64 Escessive cooldoesu sete 3 tRI 96-41-52 Discrepencies in the high pressure injection design basta 1 See CR3 0.1. Es amelysis ("R 3 D. I . 2 3
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- Laas STATUS STATOs i
um! 96 83-e4 ma-= - eing of percent through-eall *= die =tione with am 7 See IR 96-46a autA to '
essupaalified proceshare ' resolve generic issua !
(mo TIAS WI M-43-45 Seer current ===r1= espansion bemed om degraded tube 7 See IR 96-06 percentages tnt! 96-84-81 Diacrepancies in the EDAD and the FSAA regarding the i r prevent ion of post v rra boram precipitation '
W I 96-85,-42 Design - -as with mais steam line hangars used in seismic 1
. and other dynamic lead applicat icas (3t1 96-04-43 man-eafety related tramafer switch used in ES status 1 indicatincJ light circuitry ;
MI M-86-18 Justification for renowal of Thermo-Lag protection from the 1
=<=+rce ramme Amstrumentarian Iacorrect information provided by contractors 7 **
URI 96-81-43 tRI 96-12-81 Emergency Feedwater lou asPSit to both pumps skse to postulated 1 See CR3 D I. 5; ,
siante failure G 3 D.I. 7 tut! 96-201-01 Long team plaat cooldown following a small break LOCA 1 See CR3 D.I. 3s See In assuming a single failuse in the decay beat dacp time 96-11. NBA taking responsibility for thia item.
URI 96-281-82 sePsat for building spray Ind"P has very little margia, and some 1 See CR3 C.I. 4 calculat tom f actors were ma=commerwat twe URI 96-281-83 Opesating curves 16 17 and it in Op-tela are not walidated 4 ;
try licensee 421 96-201-04 ma==afety-related positiamers am safety-related walwes 1 See IR 96-08 e
EstI %-281-05 Service water system beat loads did act consider maximum 1 input har (OP-ta 35 Charwe 151 i
M1 96-281-06 Preferred of fsite electrical power source with plant shut I down (See kw swiretwardt is not oualified IELI 96-201-07 EDG mot protected against water spray from f ailure of fire 3 protectica deltase avstem in EDG room 532 96-201-89 1 Testing e.. u . t.o , apaalify relays beyond manufacturers' raciags was i
&ER 93-82-RJ. Switchyard cable failure caused degraded weltage of Class 3E 7 lea 91-e2-01 cla==d la Lra 93-42-83 elect s ical buses and act uat ion of FIsc In 95 09 LER 94-06-41 Deficiemey in understanding of technical retsuirements leade 2 lea 94-06 84 cleoed la 12R 94-06-03, to - ==rwattwe RPS setpoint and potential w&olattom of TS In 95-16. See also VIO LER 94-06-84 95-62-04 LES 94-46-05 LER 95-49-os se.aimal release chasing mulf ar diamide delivery causes 1 See IR 95-11 actuation of tonic gas monitor resulting la control room emee,- r wantilatiam actuation 4
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Asah Esc XR/sma LIC u ess * * ===*fs M LanB sr&2WW STATUS i
LER 95-19-81 T =*=Ti-ee procedure e- - leu cooling water flow to w oup 1 L5R 95-18-00 closed la pump resultlag ta operatica outside tl.a design basis IR 95-16. See also ERI .
95-11-02, VIO 95-14-03 !
LER 95-13-01 Design deficiency may cause makeup e==k worteming resulting 1 12R 95-13-04 closed in in f ailure to meet Appendia R requirements IR 96-06 12R 95-17-40 Su flow to control room coolers enarrolled by air operated 1 See IR 95-16. VIO 96 walves matich could fail opem 06 LER 95-13-03, landequate TS mote allowed delayed entry into TS 14D 2 See NCV 95-18-05
- LER th14-41 LER M-18-42 12R 95-19-84 1aak instrumentation for Su flow to RRCus incapable of 1 See IR 95-18 r measuring 90 gpm 5
LER 95-23-41. 1-=istent design assumptions cause tamilding spray flow 1 12R 95-23-04 closed in ,
12a M-23-02 rates to be outside design basts IR 94-04 s
LER M-25-DO, 'd~:-r's isolation of safety / mon-saf ety selated circuits 1 See VIO 95-21-03 12m M-25-81 12R 95-28-60 BMST wacuum breaker has inadequate relief capacity 1 See IR 95-21 LER 95-24-81 LER 96-01-31 ETIC control circuits miarcuted; Appendia R concera 1 LER 96 41-00 closed in IR 96-04 See also WCV 96-01-03 LER 96-82-04 Mialpurge valve has safety / mon-safety related circuits 1 See VIO 95-21-03 uit h e isolation !
12R 96-83-00, RCS cooldous rate exceeded during coold - 3 - See 121 95-21-04 128 M-83-81 LER 96-64 00 CCHE coatsel dampers found damaged & leakiag 1 See IRI 95-02-02, IS 95-
, 21 LER 96-05-01 SM flaw to RRCUs could asceed design 1 LER 96-05-00 closed in IB 96-04. See also VIO 96-01-01 LER 96-46-04 EP1 instrument error could result in MP3 pump runaut 1 See IR 95-20, IR 96-04 LER 96-06-01 LER 96-09-80, EP1 line N m W/ loss of de bus could have imadaquete HPI 1 See IR 96-01 ;
LER 96 C1-01 flow inst rumentat ion j LER 96-64-00 Ambigm TS mote results in mot perforniag RCS least 2 surveillamee prior to pkade 2 LER 96-09-04 Failure to teattach instrument tubing to seismic supports 1 See LR1 96-03-06, IR 96-after modification leads to operation outside desian basis 05 LER M-19-49 Low flow is SM system cooled Components ema*=*s operation 1 autside destas basis [
LER M-11-ee Per - 1 error causes testing deticiency resulting in 1 witica prohibited by imorcued TS 4GL 96-01 isseest LER 94-12 00, Operation outside design basis caused by battery chargers 4 See Um! 96-03-Os, la 96 12R 96-12-31 having i= =W-*e test results accepted in error 85 LER 96-12-E2 5
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Issut , aun mac Im/saR LIC u ess 'wma===Is unc LR&B STATUS STATUS 12R 96-12-84 Operatcr error resulted in the inadvertent actuation of DCP- 3 See BBCT 96-43-02 1A 12R 94-15-00 W1 errera cause cable separation /1 solation concerme 1 See IR 96-04 resultlag in operattom =*=ide the design besta Etealc gae maatt ors) ;
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LER 96-16-04 CREWS filter tasting did not meet TS specs 2 '
it LER 96-24-GO Failure to werify as penetrations closed per TS 1 LER 94-19-04 Non-eafety related switch used in safety related wiring for 1 See URI 96-06-03 Es meatus 11 tit 9 o IAR 96-24-40 Eksreviewed saf ety ny ==H n== concerning EDG overloading = ==d 4 See EE1 96-12-02 bw laterpretation of regulatory reautrements EEI 96-14-81 Four esamples of failure to follow refueling procedure FP-203 3 "
EEE 96-18-62 Failure to assure reoc cause analysis and corrective actions 5 **
taken to proclede repetition were adequate af ter sefuel facident amo PR issued)
EE1 96-12-82 EIXI loading USQs due to inadaquate le CFR 59.59 evaluations; 4 Enforcement conference three sameples tone modification & two procedure chaagest to be sch=%1ed. See CR3 D.I. 5: CR) D.I. 6 EEI 96-12-83 Te nd-tate corrective actions for 18 CFR 59.59 evaluation 5 Enforcement conference errors: t wo e= ==ples to be scheduled EEI $6-12-64 Use of answerified calculations to support modifications e Enforcement conference to be scheduled s
EA 95-16 Dee of non-conservat swe trip setpoints for saf ety-related 6 1 See IR 95-16 Ia 95-21 t=as EEE 95- epip-==e (SLIII). Addittamal examples identifaed in la 95-s2-849 16.
EA 95-126, mine imetances where operators wielated proceduses fos setJT 6, 3 See IR 96-04 how 3.A t=as pressure / level ISLIII).
Err 95-22-013 EA 95-126 Conduct of unauthorized testa of MUT witiv;ut le CFR 59.59 6, 1 See IR 96-04 Nov 2.5 t=as evaluation SSLIII). Addittoma! esamples (four tests 3 EE! 95-22-52) identified in 1/18/96 letter titled EA 95-126 and EA 96-105).
(see tut! 94-04-ost EA 95-126 Failure to take adequate corrective actions for operator 6, 5 mos I.c.1 concerns regardaag ce-Isle, cerve e, for set:T pressure /tewel t=ma EEI 95- limita ESLIII)22-939 EA 95-126 Corrective actions for am i==d*Taare Curve e itmo ST!*s and a 6. 5 mow I.c.2 rewtaed C W SA & sal were also incorrect (SLIIll
(=es EEI 95-22 439 6
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Issus Desca2PTzcar
- Anah aunc za/ssa LICEusas CxassEMTS anac LEAD STATUS STATUS IF1 96-201-14 EDG protective trips anot byp===ad during emergency mode of 1 Identified la IPAP coeration reoort as IF-96-201-04 IFI 96-201-15 verification of motor starting data 1 Identified la IPAP repc-t as IF-96-201 05 IFE 96-201-16 Coordination of Secnnd level undervoltage relay (SilJR) 1 Identified la IPAP set t ing vs . laverter operation report as IF-96-201-66 IF1 96-231-11 Coordinatice of SLEET and f use protection 1 Idearifled in IPAP report as IP-96-201-07 asDLTI-PLANT ACTTours MPA 88105; Seismic qualification of equipment. Licensce's critesia and 2 Expected completion GL 87-02 procedures approved. Some issues are pendrag and would be December.
resolved thren a. adit Escateduled for Mar 978. Licensee *s field walkdown results are currently la staf f review.
SsPA ES131 IPE and IPEEE - These are in staff review. unt a rest art 2 81PE)4 itee.
MPasB114 i!PEEE)
MPA SL5472 Pressas e locking and thermal binding of safety related gate 2 CL 95-07 walves. Carrently in staf f review. Am RAI is out st anding.
Espect ed eglet ina)
MFA 8L601; Testieg of safety-related logic circuits - 2 11/96 - the lic msee has OL 96-el Licensee res,onse in staff review. More details are identified testiaq re wired. v ais issue requires attent ion, deficiencies that must be fised prior to restart MPA 82682; Mowenent of heavy loads over spent fuel pool 2
' maCB 96-62 - Licensee re= r a- ia staff review. This would stot be a restaat issue _
sePA EL2ces Thermo!ag - Licensee plaas to use esecatiss 2 See In 96-014 In 96-06 GL 12-084 BU (en alternate mat eria tl. =- seanalysis of APPENDIN A. ar=3 92-81 = - emeoption. Fire bastier tests of Mecat tas includang Ampacity tests are in stait review. This also may not be rest art issue.
MPA 8L543; Circumferential cracking of SG tube flaws. 2 CL95-On Licensee rer= in st af f review.
sePAs L2st; meactor vessel structural integrity. RAI to licensee on 2 GL 92-81 Rev 7/22/96. Only a data h=== issue, not a restart item.
2 Sueo 1 MPA SL684; Borafles degradattom. Licensee response is just in. Staff 2 CL 96-G4 review to e-e. This may have to be a43ressed ps ser to rest art because of sensitivit y to spent fuel pool issues MOV testing & surweillance. This item is closed wis h t he 2 See IFI 94-le-09 MPA _ s GL 89-18 esception of IFI 94-18-09 on periodic werification. =tasch is to be followed up af ter a new generic --icatier. As isee3 10
ISSUE DESCRIPT1GB maan ymC IR/SEE LICEuSEE CIEGEmrFS 3RC LEAD STATUS STATUS LIeuana - ./RELIEP ==rnmeTS Cott Cbatrol comples habitability envelcpe - Imeluding TIA 95-83 2 meed to be addressed. Licensee subatttal does not provide adeounte TS action. stay be denied. I R.G. 1.91 BG 1.97 imets w arion - Subcool monitors etc - category 2 Imet rument s change, mot a big issese. License - _.; may be esproved by Decenter .
Biometrics.4 staaetric emesption to allow taking securit y hedges of fsite - 2 Security
- Staf f review is espected to be complete soon. mot a restart issue.
Core Flood Belief request RE: Core floo$ aorale - Staff needs more info. 2 Nozzle Pts will keep RII informed.
OTSG Tubes CTSG tube testing - 1.ica see proposed a revised CTSG tube 2 See VIO 96-05-0*
acccorance eriteria OTEER ISSUES Pressuriser During Bef uel 9 a sut>-surf ace fla usas discovered. The 2 mozzle Flaw itcensee performed better ir.spection during R10 and ine.nd the flaw to be acceptable. The new taspection results in reduced flaw sise and consequently acceptance criteria dwhsch is based on sat to of flaw to thickness) chaseges . May require inspectica. Staf f review in progress.
RC 1 mop In a survey laspectica, the staf f noted that certata branch 2 Piping pipes of f the prieary coolaat loop i exe not analysed as Code Analyses Class 1 pipe ti.e.. suo f atigue maalysist as seguared by to code. Need technical bramch's opiaaon on this. This is suk empected to be rest art issue.
- Criticality The licensee did not carry a prewicualy approwed esempt aon 2 peonitor from part le 470.2473 seguirements to Part 54 license. meed leoal interoretation of the status of the exemption.
LTOP Current TS does not address LTOP prevention or nitigat ion. 2 On t.he basis of CL 89-11 the licensee =h tted inf ormat ion to Wtrate that LTOP in &&w plaats have less than 1 in 100 reactor years probability of occurres;ce and as a result per CL SG-11 ace-appendia G eethodology can be used f os PT curves. Se cta a PT curve monsid provide for higher LTOP enable pressure and t emper ture and ensld provid.- oyesas i. al f lesibilit y. Staf f denied the respeest in 19% as=8 respaesa rse a revised response. The licensee espects to sespond late 1997 This issue should be resolved prior to restart .
Sources for issues include: IFS, SIMS, NUREG 1435 (Status of Safety Issues at Licensed Power Plants), Resident *s OIL. IH*s 01L NOTE: Open allegations, OI investigations, and emerging / draft issues are listed separately.
11 a
i CRYSTAL RIVER RESTART TASK CHECKLIST , !
y n,i .i v l TASK HC 0350 RESP. REFERENCE STATUS REF APF A '-
issue ^ preliniiAarPnotiificNond iB12T '
Rill b 'A, 11 b ;
Congressional Notification B.2 g.
gEstisblNOedidiP$neIb
,e/ '$dlai 3 R w'III!(NRR; E11/1/96k skW: ,
w 2es v ;v
- s A as; ;
$0E;1tntU F4 Assess available information B.3 b.
Brief Regional Administrator B.3 d. Ril I Brief NRR Executive Team B.3 e.
- beseloo CiselSidcifibfCEhElisE E3?f5 a lIIi:555Ri FiDi3/96Z WNEV Develoo Restart Action Plan B.3 g. RII. NRR Regional Administrator Approves B.3 h. RI!
Restart Action Plan NRR Associate Director Approves B.3 1. NRR .
Restart Action Plan -
Imolement Restart Action Plan B.3 j.
Evaluate findings of IPAP B.4.1 a.
Insoection Licensee performs root cause B.4.1 b. Licensee analysis and develops corrective action olan NRC evaluates-licensee's root B.4.1 c.
cause determination and . 1 corrective action plan Review licensee generated B.4.3 a. Panel restart issues Independent NRC identification B.4.3 b. Panel of restart items (consider external sources)
NRC/ Licensee agreement on B.4.3 c. Panel restart issues Evaluate Licensee's restart B.4.3 d.
i issues imolementation process Attachment C '
(_____-______-__________ _ _ _ _ _ _ _ _
TASK HC 0350 RESP. REFERENCE STATUS REF APP A Evaluate Licensee's B.4.3 e.
Implementation of verification process Evaluate Licensee's restart B.4.5 a. Ri!
readiness self assessment '
NRC evaluation of applicable B.4.5 b.
Items from ISSUES section below complete j
Restart issues closed B.4.5 c. i Conduct NRC restart readiness B.4.5 d. Ril !
team inspection Issue augmented restart coverage 9.4.5 e.
insoection plan Comments from other parties B.4.5 f.
considered Re review of Generic Restart B.4.5 h.
- Chicklist complete
- Prepare restart authorization B.5 a.
' document and basis for restart NRC Restart Panel approves 8.5 b, iRestart Authorization No restart objections from other B.5 c applicable H0 offices No restart objections from B.5 d applicable Federal Aaencies .
Regional Administrator concurs B.5 e. RII in Restart Authorization NRR Associate Director concurs B.5 f. NRR in Restalt Authorization E00 concurs in Restart B.5 g. NRR Authorization when required Conduct ACRS briefing when B.5 h. NRR reouested Conduct Commission briefing when B 5 1. NRR requested ATTACHMENT C i
i .
I j
TASK HC 0350 RESP. REFERENCE STATUS 1 REF APP A Comission concurs in Restart B.5j.
Authorization when reouired Regional Administrator B.5 k. Rll authorizes restart Notify Comission of restart B.6 a. hRR -
authorization (if Comission did not concur in Restart Authorization)
Notify EDO of restart B 6 b. NRR ;
authorization (if EDO 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)
Notify Applicable Federal' B.6 e. '
[
agencies of restart '
i authorization Notify Public Affairs of restart- B.6 f. RI!
- authorization
- Notify State and Local officials B.6 g. RI!
of restart authorization l Notify citizens or groups that B 6 h. RII expressed interest during the i
restart approval orocess
)
i ATTACHMENT C
r ,
St4tul #1 t' CRYSTAL RIVER RESTART ISSUES CHECKLIST .
ISSUE I HC 0350 RESP. REFERENCE STATUS REF APP A ASSESSMENT OF ROOT CAUSE IDENTIFICATION AND CORRECTION Conaitions requiring shutdown C.1.1 a.
are clearly understood Root causes of the conditions C.1.1 b.
rcouiring shutdown clearly unoerstood
~
Root causes of other significant C.1.1 c.
proolems clearly understood Effectiveness of root cause C.1.1 d.
analvsis program Thoroughness of corrective C.1.3 a.
action plan Comoleteness of corrective C.1.3 b.
action plan
- Control of corrective action C.1.3 c.
item tracking Effective corrective actions for C.1.3 d.
the condition requiring shutdown imolemented effective corrective actions for C.1.3 e.
otner significant problems imoiemented Plan Control' of long term corrective C.1.3 f.
actions Effectiveness of corrective C.l.3 g.
action verification process Effectiveness of 0A Program C.I.4 a.
Effectivenest of industry C.1.4 b.
exoerience review program Effectiveness-of Licensee's C.1.4 c.
indeoendent review groups Effectiveness of deficiency C.1.4 d.
reporting system ATTACHMENT D
_ . , _ _ __ . _ _ _ . _ . _ _ _ . . _ _ . . _ _ _ _ _ _ . _ . _ _ AttachmentIf
F .
i ISSUE MC 0350 RESP. REFERENCE STAT'JS REF APP A Staff willingness to raise C.1.4 e. !
concerns Effectiveness of PRA usage C.1.4 f.
Effectiveness of commitment C.1.4 g.
tracking program _
External Audit (i.e. INP0) C.1.4 h.
capability ;
Ouality of 10 CFR S0.72 and C.1.4 1. >
50.73 reports Operability ASSESSMENT OF LICENSEE MANAGEMENT EFFECTIVENESS Goals / expectations communicated C.2.1 a, to staff Demonstrated expectation of C.2.1 b.
adherence to procedures Management involvement in self- C.2.1 c.
assessment and independent self-assessment capability Effectiveness uf management C.2.1 d.
review committees Management's demonstrated C.2.1 e.
awareness of day-to day operational concerns Management's ability to identify , C.2,1 f.
and prioritize significant issues Management's ability to C.2.1 g, coordinate resolution of significant issues Management's ability to C.2.1 h.
implement effective corrective actions Impact of any Management C.2.2 a.
reorganization Effectiveness and timely C.2.2 b.
resolution of employee concerns ATTACHMENT D a
ISSUE HC 0350 RESP. REFERENCE STATUS REF APP A Adequate engineering support as C.2.2 c.
demonstrated by timely resolution of issues Adequate plant admin 4trative C.2.2 d. !
procedures Effective infoination exchange C.2.2 e.
with other utilities Participation in industry groups C.2.2 f.
Effectiveness of emergency C.2.2 9 response organization i
Coordination with off site C.2.2 h.
energency planning officials ASSESSHENT OF PLANT AND CORPORATE STAFF EFFECTIVENESS ,
' Demonstrated commitment to C.3.1 a.
achieving improved oerformance i '
Demonstrated safety C.3.1 b. .
l consciousness i
Understanding of management's C 3.1 c.
i expectations and coals i
Vaderstanding of plant issues C.3.1 d.
i and corrective actions Qualifications and training of C.3.1 e.
staff Staff's fitness for duty -
C.3.1 f.
Attentiveness to duty C.3.1 g.
Level of attention to detail C.3.1 h.
Off hcJr plant staffing C.3.1 1.
Staff overtime usage C 3.1 j.
Procedure usage / adherence C.3.1 k.
Awareness of plant security C.3.1 1.
Licensed operator staffing meets C.3.3 a.
recuirements anri licensee goals Level of formality in control C.3.3 b.
room ,
3 .
ATTACHMENT D
ISSUE HC 0350 RESP. REFERENCE STATUS REF APP A Effectiveness of control room C.3.3 c.
l simulator training l Control room / plant operator C.3.3 d.
awareness of eauipment status-4 Adequacy of plant operating C.3.3 e, procedures Procedure usage / adherence C.3.3 f.
Log keeping practices C.3.3 g.
ASSESSMENT OF PHYSICAL READINESS OF PLANT Operability of technical C.4 a.
specification systems Operability of required C.4 b.
secondary and support systems Results of pre startuo testing C.4 c.
Adequacy of system lineues C.4 d. .
Adequacy of Surveillance C4e, tests / test program Significant hardware issues C.4 f.
resolved (i.e. damaged equipment equi modifications) pment ageing, Effectiveness of the plant C.4 h.
maintenance program Maintenance backlog managed and C.4 1.
impact on operation assessed
. Adequacy of plant housekeeping C.4 j.
nd eautpment storage JSSESSMENT OF COMPLIANCE WITH REGULATORY REQUIREMENTS Applicable license amendments C 5 a.
have been issued Applicable exemptions have been C.5 b.
granted Applicable reliefs have been C.5 c.
granted ATTACHMENT D
r ,
\
ISSUE MC 0350 RESP. REFERENCE STATUS REF APP A Significant enforcement issues C.5 f.
have been resolved Allegations have been C.5 g.
appropriately addressed 10 CFR 2.206 petitions have been C.5 h appropriately addressed COORDINATION WITH INTERESTED AGENCIES AND PARTIES
'~
Federal emergency Management C.6 a.
Acency Appropriate Sate and local C.6 e.
officials Appropriate public interest C.6 f.
grouos .
Local news media C.6 g.
I ATTACHMENT D 1
,