ML20141J694
| ML20141J694 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/10/1996 |
| From: | Jaudon J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 9708210089 | |
| Download: ML20141J694 (23) | |
Text
, .
4
- NUCLEAR RE T Y COMMISSION l * "IrN[A.
o $'t!EE "
< b y,,, December 10, 1996
' MEMORANDUM T0: F 7724 41
- FROM: oins P. Ja do . Deputy Director Division of Reactor Safety
SUBJECT:
' MINUTES OF THE CRYSTAL RIVER RESTART PANEL SECOND MEETING OECEMBER 3. 1996
! The Crystal River Restart Panel met at the Crystal River site December 3.
l 1996. The following personnel attended the meeting:
Panel Members Johns P. Jaucon, Region !!. Chairman Frederick J. Hebdon. NRR. Vice Chairman Charles Casto. Region 11 Ker D. Landis. Re Ste en J. Cahill. gion 1111 Region l
Lak hminaris Raghaven. NRR Others Todd Cooper. Resident inspector Billy Crowley. Region !!
Robert Schin. Region !!
The Panel reviewed the restart issues Matrix and characterized each item as either " RESTART" or "NON RESTART." The panel also updated the cross reference of issue items which appeared on the matrix as multiple entries (e.g., a single item that ap) eared as both a Violation and as a Licensee Event Report).
The panel decided t1at only one item for each specific case should be retained and characterized as "RESTAR1" where there were multiple entries for a single issue. The Panel also determined to re word the line items related to the IPAP major issues so that they more clearly expressed what inspections were required.
The anel also added the following items to the matrix:
e A review of open Appendix R issues to assure that there were no restart and/or operability issues imbedded in them.
- A review of operator work-arounds to assure that there were no restart or operability issues contamed in them, o A RESTART item "Either to conduct an ILRT or to request a license amendment to use Option B of Appendix J to 10 CFR Part 50."
e A RESTART item for review and issuance of Licensee Amendments for Unresolved Safety Questions (US0s). This item was characterized by the board as a tickler for specific amendment requests that are expected to resolve individual USQs. I i ma"188u P
Pa=ab PDR h!I\llE)(ElEjll!l
%gi Q
2 e A RESTART item to review the licensees response to the 50.54f letter concerning design bases sent to all licensees. This response is due in February.
e A RESTART item to review impleinentation of the license conditions.
A copy of the revised Issues Matrix is Attachment A.
The Panel also reviewed and u> dated the checklists for Tasks and Issues (marked as Attachments C and ) to the minutes of the initial Panel meeting.)
These revised checklists are included herein as Attachments B and C.
During the afternoon, the Panel met with Florida Power representatives at a public meting. This meeting, which will be documented by separate correspondence, was for the purpose of having licensee representatives present their restart matrix. This licensee matrix will be discussed at the next -
Panel meeting.
The tentative scheaule for future Panel meetings was established as follows:
Data Ilme Location December 18, 1996 10:00 am Region II January 10, 1997 7:30 am CR3 Site January 22, 1997 10:00 am Region II Docket No. 50-302 Attachments: A. Issues Matrix B. Crystal River Restart Task Checklist C. Crystal River Restart Issues Checklist cc w/atts: 5. D. Ebneter RII L. A. Reyes. RII E. W. Merschoff, RII F. J. Miraglia NRR S. A. Varga, NRR G. M. Tracy, OEDO R. P. Zimmerman, NRR J. A. Zwolinski. NRR
)
l l
l 2 e- A RESTART item to review the licensees response to the 50.54f letter concerr.ing design bases sent to all licensees. This response is due in February, o A RESTART item to review implementation of the license conditions.
L A copy of the revised Issues Matrix is Attachment A.
The Panel also reviewed and updated the checklists for Tasks and Issues i
(marked as Attachments C and D to the minutes of the initial Panel meeting.)
These revised checklists are included herein as Attachments B and C.
l -
During the afternoon, the Panel met with Florida Power representatives at a public meting. This meeting. which will'be documented by separate correspondence, was for the purpose of havir.g licensee representatives present their restart matrix. This licensee matrix will be discussed at the next
! Panel-meeting.
T The tentative schedule for future Panel meetings was established as follows:
Qit.g ligt location l- December 18. 1996 10:00 am Region II January 10, 1997 7:30 am -CR3 Site
- January 22, 1997 10
- 00 am kegion II Docket No. 50 302 l Attachments: A. Issues Matrix l B.- Crystal River Restart Task' Checklist Crystal River Restart Issues Checklist C.
cc w/atts: S. D. Ebneter. RII L. A. Reyes, RII i E. W. Herschoff RII
! F. J. Miraglia. NRR l S. A..Varga. NRR G. M. Tracy. OEDO R. P. Zimmerman NRR
! J. A. Zwolinski, NRR o
1 e i
.l
. __ _ .~ - - _ _ . . . - - - , . - _ _ ~ .. -. - . _ -
l k
- mme49
- UNITED STATES g NUCLEAR REGULATORY COMMISSION
( l """An!7/855MFJ"
% ,,,,,, December 10. 1996 MEMORANDUM TO: F ;
FROM: o ns P. Ja do . Deputy Director Division of Reactor Safety
SUBJECT:
MINUTES OF THE CRYSTAL RIVER RESTART PANEL SECOND MEETING DECEMBER 3. 1996 The Crystal River Restart Panel met at the Crystal River site Decernber 3..
-1996. The following personnel attended the meeting:
Panel Members Johns P. Jaudon. Region II. Chairman .
Frederick J. Hebdon. NRR, Vice Chairman Charles Casto. Regicn II Kerry D. Landis. Re Stephen J. Cahill. Region gion II II Lakshminaris Raghaven. NRR '
Others Todd Cooper. Resident Inspector Billy Crowley, Region II .-
Robert Schin. Region II The Panel reviewed the restart Issues Matrix and characterized each item as either " RESTART" or "NON-RESTART." The panel also updated the cross reference of issue items which appeared on the matrix as multiple entries (e.g., a single item that ap) eared as both a Violation and as a Licensee Event Report).
The panel decided t1at only one item for each specific casa should be retained and characterized as " RESTART" where there were multiple entries for a single issue. The Panel also determined to re word the line items related to the IPAP major issues so that they more clearly expressed what inspections were required. -
The Panel also added the following items to the matrix:
o A review of open Appendix R issues to assure that there were no restart and/or operability issues imbedded in them, i
e- A review of operator work-arounds to assure that there were no restart or operability issues contained la them, e- A RESTART item "Either to conduct an ILRT or to request a license amendment to use Option B of Appendix J to 10 CFR Part 50."
! e A RESTART item for review and issuance of Licensee Amendments for
, Unresolved Safety Questions (US0s). This item was characterized by the board as a tickler for specific amendment requests that are expected to resolve individual US0s.
Attachment A CRYSTAL. RIVER 3 ISSUES CHECKLIST Status as of December 10, 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 -
G. Corrective actions for NRC violations
- 7. Other ISKDE D58CRIPTI0er AREA NRC IR/SER ' LICENSEE CENSIMrts 3ERC
- 1. SAD sTATos status LICasSER*s RESTART LIST OF DESIGRE-RELATED ZssUES (D.I.al fper 10/28/94 Its from FPC)
,G3 D.I. 3 NPI pump recirculation to the makeup tank 1 D-1 See URI 96-01-02 R CR3 D.I. 2 NPI system andifications to improve carnta margins 1 D-2 See tat! 96-01-02, LER R 96-06 G3 D.I. 3 LPI pump missiosa time 1 D-3 See URI 96-201-01 R G3 D.I. 4 Reactor building spray pump 18 NPSM 1 D-4 See URI 96-201-02 R G3 D.I. 5 Emergency feedwater system upgrades and diesel generator load 1 D-5 See URI 95-12-01: EE! A impact 96-12-02 G3 D.I. 6 Emergency diesel generator loading 1 D-6 See EEI 96-12-02 R CR3 D.I. 7 Failure modes and effects of loss of DC power 1 D-7 See URI 96-12-01, LER R 96-07 Ot3 D. . O Cereric Letter 96-04 (Thermal overpressure protection for 1 D-0 R Cont ainment pipine, penetrations. and coolers) s
' ~
ATTAuviENT A
4 If US DESCRIPTION AREA IsEC IR/SSR LICENSEE N3 HRC LEAD STATUS STAIUS 4
LIcEssEE*s orEER EsSTaar ITass OTSG Tubes Adequacy of CTSG tube stress-relieved rolled joints is 7 See licensee Precursor N questioned. BMOG analysis of a Davis-Besse pulled OTSG tube, Card PC 96-5077 of current test dats, and limited field experience conflict with 11/6/96.
l '
test data from 1972 which *gualhied* a stress-relieved rolled joint.
GL 96-01 The licensee has identified testing deficiencies in safety- 2 R-1 See MPA SL601 (GL 96-01) N testing related logic circuits 1
PTVE masse OP n uars mus:ww CONCEEN, WITE IPAP r- -ED INSPECTION AND RIZ 82- -ED ADDITIONS Management - NRC inspect Problem Identifications focusing on OA sudits 5 OP-2, OP-3 R Cversight - and the problem reporting system. - Increased inspection of 5
IPAP Problem Analysis and Evaluation; focusing on root cause l Re W ad evaluations, j Inspection Marginally - NRC inspect Engineering Problem Identification and 4 OP-4 R 7
Effective Resolution; with suphasis on Itcensee evaluations for Engineering significant issues and work bacirloos.
, Organization - Also inspect Quality of Engineering; with emphasis on 10,
! - IPAP CFE 50.59 screening and safety evaluations, accuracy of the
- h aded FSAR, and management oversight.
1 Inspection t-Lack of - NRC inspect Engineering Safety Focuss focusin3 on proper 1 OP-7, OP-8, R Adequate identificat ion of discrepancies with the plant's design basis D-13. D-15.
Knowledge of W be corrective action system. D-16 the Design - Also inspect Engineering Problem Identification and Basis - IPAP Eesolutions focusing osa p roqremfor identitving design ba h A- 4=d issues and capturing them in the corsective action program, eInspection - Also Anspect Quality of Engineering; focusing on sensi t ivit y/underst anding by the engineerino/licensin<a st af f of t he plant 's desian basis, i - Also assess the desian margin, including the licensee *s a a ewt ene of condi c i nn
- reviews l nn.
Lack of - NRC inspect 50 59s, coerability, report abi li t y 2 OP-5, OP-s R Sensitivity i,-
for the Need I to Comply '
Cith Regulations -
IPAP '
i Eccommended Inspection
!' Operator - NRC inspect Safety Focuss focusing on emnication withart 3
- Performance - operations, cesumnicar ton wit h other site aroups, and
- PAP - overt ime
, Et M 5 DeCCLon
~ _uspee,w e=s muP Sysras a
. . 2 s
g ,_ _, e +
e 3
% , w-- , -mw -
e v e-%-r s . . - . - * - * -e
ISSUE DESCRIPTICIE AREA NBC
, IR/SER LICBISRE m==TS NRC LEAD STATUS STATUS URI 95-02-02 Control room Abitability envelope leakage. Excessive 1 leakage paths through doors, dampers, and drains due to See TIA 95003: FPC TS R Change Request No. 200 design errors and lack of surveillances/ preventive of S/28/96; LERs 96-04, maintenance 94-10, 95-01, 95-04-01, 95-09; irs 95-02, 95-09, 95-11, 95-16, 95-21; FPC ltra. of 5/26/95 and 10/23/95 lat! 95-P71-04 Excessive cooldown rate 3 N URI 96-01-02 Discrepancies in the high pressure injection design basis 1 D-9 See CR3 D.I. 1; analysis R CR) D.I. 2 EDT H-03-34 Measuring of percent through-wall indications with an 7 See IR 96-06; NRR to N unqualified procedure resolve generic issue
. (no T7%)
Lat! 96 ~ s-uS Eddy current sample expansion based on degraded tube 7 See IR 96-06 N percentages URI 96-04-01 Discrepancies in the EDBD and the FSAR regarding the 1 Verify procedures and R prevention of post-ICCA boron precipitation documentation adegaate prior to restart Ut! 96-05-02 Design concerns with main steam line hangars used in seismic 1 R and other dynamic load applications URJ 96-06-03 Non-safety related transfer switch used in ES status 1 R indicating light circuitry URI 96-06-10 Justification for removal of Thermo-Lag protection from the 1 N source rance instrumentation URI 96-07-03 Incorrect information provided by contractors 7 ** N g e
URI 96-12-01 Emergency Feedwater low NPSH to both pumps due to postulated 1 D-17 See CR3 D.I. 5; R single failure CR3 D.I. 7 URI 96-201-01 Kong term plant cooldown following a small break 14CA 1 D-3 See CR3 D.I. 3s See IR R assuming a single failure in the decay heat drop line 96-11. NRR taking responsibility for this item.
URI 96-201-02 NPSH for building spray pump has very little margin, and some 1 D-4 See CR) D.I. 4 R calculation factors were nonconservative UR3 96-201-03 Operating curves 16, 17, and 18 in OP-103B are not validated 4 0-1 R by licensee URI 94-201-04 F~mafety-related positioners ou safety-related valves R-7, D-10 I See IR 96-08 R URI 96-201-05 Service wa?.er system heat loads did not consider maximum 1 0-1 input heat 80P-103B, Curve 15) R URI 96-201-06 Preferred offsite electrical power source with plant shut N down (500 kw switchyard) is not qualified URI 96-201-07 EDG not protected against water spray from failure of fire !' R protection deluge system in EDG room l 4 ,
3 s
. - . . . . .~ m _. e __
.l-18053 : _- _ - - uuss AREA amC 12/SEE LICuissa N NBC LEAD STATUS STATUS tRI 96-201-09 Testing to spaalify relays beyond manufacturers' ratings was 1 N
t a =d- ri at e i
IAR 93-02-02, Switchyard cable failure caused degraded voltage of Class IE 7 LER 93-02-01 closed in N I22 93-02-03 electrical buses and actuation of EDG IR 95-09 l'i LER IAR 94-06-01, 94-06-03, Deficiency in understanding of technical requirements leads 2 LER 94-06-00 closed in N to - - =arvative RPS setpoint and potential violation of TS IR 95-16. See also VIO i' IAR 94-06-04, 95-02-04
- I2R 94-06-05 1
< I2R 95-09-00 Ninimal release during sulfur dioxide delivery causes 7 See IR 95-11 N i actuation of toxic gas monitor resulting in control room amargency ventilation actuation LER 95-10-01 Jandaarate procedure causes low cooling water flow to makeup 1 LER 95-10-00 closed in N i pump resulting in operation outside the design basis i IR 95-16. - See also tRI 95-11-02, VIO 95-16-03 q LER 95-13 Design deficiency may cause makeup tank vorteming resulting ' 1 LER 95-13-00 closed in R j in failure to meet appendia R requirements IR 96-06
, LER 95-17-00 su flow to control room coolers controlled by air operated 1 See IR 95-16, VIO 96 N valves which could fail open 06 1AR 95-18-00, Inadequate TS note allowed delayed entry into TS I40 2 See NCV 95-18-05 N IJR 95-1" -01, 1AR 95-18-02 I2R 95-19-00 Laak instrumentation for SW flow to RSCUs incapable of 1 See IR 95-18
- measuring 90 gpa i.
- j. IJR 95-23-01, Inconsistent design assumptions cause building spray flow 1 LER 95-23-00 closed in N Ian 95-23-02 : ates to be outside design basis g'
< IR 96-04 LaR 95-25-40 I=-d=7==te isolation of ' safety /non-safety related circuits 1 See VIO 95-21-03 N IAR 95-25 01 IAR 95-20-00, BUST vacuum breaker has laad=T e e rel.ied capacity. 1 See IR 95-21 N
- IAR 95-20-01 4
IAR 96-01-01 EFIC control circuits misrouteda Appendix R concern 1 122 96-01-00 closed in - N IR 96-04s See also NCV 96-01-03 LER 94-02-00 Nimipurge valve has safety /non-safety related circuits 1 See VIO 95-21-03 N s
without isolation t
, 1AR 96-03-00, RCS cooldown rate exceeded during cooldown 3 See URI 95-21-04 N l- tar 96 03-01 i
IAR 96-04-00 COdB control dampers found d -=g-d & leaking 1 See 121 95-02-02, IR 95 N
, 21 LER 96 05-01 SW flow to ABCDs could exceed design 1 LER 96-05-00 closed in N 5 IR 96-04. See also VIO 96-01-01 12 96-06-00, NPI lastrument error could result in HPI pump runout 1 See IR 95-20, IR 96-04, N
, 12R 94-06-01 D.I. 2 i,
- i
)
s
. 4-
+ ~
v r
- t- *
- 7 --~ w v g-' vv - Tv---t- re ' y' -%4 =$-i m m s -+-wr-n- + -P tmg d e en ,w we% re-e = e -~e-" sv-aw*wbmww-w--
- a- -+-+.- w-M= "W- 6-w- *e**--===-=$=c"mt'u% s me m-*PNY--m't ae--r=-+ 5-- m .-
. ISSUE DESCRIPTION AREA NRC
, 1R/SER LICENSEE COBSEENTS NRC LEAD STATUS STATUS LER 96-07-00, EPI line SSI4CR/IDOPfloss of de bus could have inadequate HPI 1 See IR 96-01, D.I. 1 N LER 96-07-01 flow instrumentation LER 96-08-00 Artiguous TS note results in not performing RCS leak 2 surveillance prior to Mode 2 N LER 96-09-00 Failure to reattach instrument tubing to seismic supports 1 See URI 96-03-06, IR 96- N siter modification leads to Pration outside design basis 05 LER 96-10-00 Low flow in SN system cooled components causes operation 1 outside design basis See VIO 95-16-03 N LER 96-11-00 Personnel error causes testing deficiency resulting in 1 condition prohibited try improved TS 8CL 96-01 tenuest See GL 96-01 N IER 96-12-00 Operation outside design basis caused by battery chargers 4 LER 96-12-01, having inadequate test results accepted in error See V10 PS-05-07 N LER 96-12-02 I2R 96-13-00 Operator error resulted in the inadvertent actuation of DCP- 3 1A See NCY 96-03-02 N LER 96-15-00 Personnel errors cause cable separation / isolation concerns 1 See IR 96-04 N resulting in operation outside the design basis (tomic gas i monitoral e
IER 96-16-00 CREVS filter testing did not meet TS specs 2 N LFR 96-14-00, Failure to verify RB penetrations closed per TS 1 0-2 R LER 96-18-01 LER 96-19-00 Non-safety related switch used in safety related wiring for ES status lights 1 See URI 96-06-03 N LER 96-20-00 Ektreviewed safety questions concerning EDG overloading caused 4 R-2, D-6, D- See EE! So-12-02 N g.
by interpretation of regulatory requirements 14, D-15, OP-5 LER 96-23-GO Personnel error leads to missed surveillances resulting in 2 violation of Technical Specifications laissed remote shutdown panel EFW pump pressure instrument channel check) 12R 96-24-00 Plant modification causes unanalyzed condition regarding 1 See URI 96-12-J1 emergency feedwater LER 96-25-00 Personnel error causes testing deficiency resulting in 1 See MPA SL601 (GL 96-01) condition prohibited by Technical Specifications 812 contacts in ES logic were not being teated)
EEI 96-10-01 Four exmaples of failure ta follow refueling procedure FP-203 3 ** R EEI 96-10-02 Failure to assure root cause analysis and corrective actions 5 ** R taken to preclude repetition were adequate arter refuel incident ino PR issued) o 5
9
I I
, IS M DESCRIPTIM AREA M IR/SER LICENSEE Ct3AMMTS NRC LEAD - STATUS ST&IUS EEI 96-12-02 EDG loading USQs due to inadequate 10 CFR 50.59 evaluationes - 4 R-2, D-6, D- Enforcement conference R three examples (one modification & two procedure changes) 14, D-15, to be scheduled. See OP-5 CR3 D.I. 5: CR3 D.I. 6 EEI 96-12-03 Inadequate corrective actions for le CFR 50.59 evaluation 5 Enforcescat conference 4
R errors: two examples to be scheduled EEI 96-12-04 Use of unverified calculations to support modifications. OP-6 NRC inspect licensee's extent of condition reviews.
4 Enforcement conference R to be scheduled EA 95-16 Use of non-conservative trip setpoints for safety-related 6, 1 See IR 95-16, IR 95-21 R (was EEI 95- equipment (SLIII). Additional examples identified in IR 95-c2-04) 16.
EA 95-126 Nine instances where cperators violated procedures for MUT 6, 3 See IR 96-04 R asov I.A (was pressure / level (SLIII).
EEI 95-22-01)
EA 95-126, Conduct of unauthorized tests of MITY without 10 CFR 50.59 6, 3 See IR 96-04 R BIOW I.B (was evaluation (SLIII). Additional examples (four tests)
EEI 95-22-02) identified in 1/18/96 letter titled EA 95-126 and EA 96-185).
(See ta! 96-04-08)
EA 95-126 Failure to take adequate corrective actions for operator 6, 5 R aIOV I.C.1 concerns regarding CP-103B, Curve 4, for MJr pressure / level (was EEI 95- limits (SLIII) 22 03) !
EA 95-126, Corrective actions for an inadequate Curve 8 8two STI's and a 6, 5 O-1 R aIOW I.C.2 revised Curve SA & SB) were also incorrect (SLIII)
(was EEI 95-22-23)
EA 95-126, Design controls failed to ensure adequate safety margin for 6, 1 OP-6 R NOW I.D.1 HPI pumps for certain 14CA scenarios (SLIII)
(was EEI 95-22-04)
EA 95-126, Swapover of ECCS pumps' suction from BWST lat five feet) to 6, 1 R aIDW I.D.2 reactor building sump was inadequate (SLIII)
(was EEI 95-22-04)
EA 95-126, EOPs allowed single LPI pump to supply two HPI pumps, with 6, 1 R aIOV II.A (was insufficient NPSM for LPI pump (SLIII)
EEI 95-22-04)
EA 95-126, Failure to take adequate corrective actions for tank 6, 5 R uoy II.B (was volumes / level / suction point (SLIV)
EEI 95-22-01)
EA 95-126 Failure to ensure firs water storage tank contained adequate 6, 1 R 3 BOW II.C (was volume of water (SLIV)
EEI 95 22-03)
VI) 93-16-07 Inadequate EOP and AP procedures 6, 3 See IR 96-04, IR 96-08 R t
VI3 94-25-41 Failure to properly control the Control Complex Habitability 6, 7 See 121 95-02-02 N Envelope (door blocked open for maintenance work)
- l s
t - , , - =s -va =-=--,a w v*,,W s -v- - % == m-r- *---i---w, - + - - - w +t------ -
S -s-w- *pe V- * '"+-T -"P
- 7 - v
4 ISSW M*"m MTIQEI AREA NRC IR/SER LZc M BE
- CINEEENTS NRC LEAD STATUS STkTUS VIO 94-27-02 Failure to make two 10 CFR 50.73 reports to the NRC within 6, 2 CP-4 See IR 95-02, IR 95-C8 N the required time VI3 94-27-03 Failure to make one required 10 CFR 50.72 report to the NRC 6, 2 OP-4 See IR 95-08 N within the required time VIO 95-16-03 Inadequate procedure for operation of the makeup pump 1A 6, I cooling water R VIS 95-21-03 Failure to isolate the class 1E from the non-class 1E 6, 1 R electrical circuitry for the RB purge and mini-purge valves
- VIS 96-01-01 Inadequate corrective action for HPI flow indication problem 6, 5 R l
VIS 96-01-05 Te:, emaaples of failure to update FSAR as required by 10 CFR 6, 4 N 56.71te) ,
t VID 96-01-06 Failure to correctly translate design basis of SW system into 6, 1 R procedures, drawings, and instructions VI3 96-02-01 Failure to maintain 0.2 footcandles in the protected area 6, 7 g See IR 96-07 N VIO 96-02-04 Failure to maintain secondary alarm station operable and 6, 2 N inadequate e v nsatory measures
- VI3 96-03-11 Failure to follow radiation work permit requirements 6, 7 N 4
VID 96-03-12 Failure to report the transport of a radioactively 6, 2 N contaminated individual offsite V13 96-03-13 Ubescorted visitor personnel within the prc,tected area 6, 1 N VIS 96-04-02 Failure to take prompt corrective action in revising 6, 5 R $
, procedure VP-690, Plant Safety verification Ifor STAS). VP-580 cortained outdated and incorrect information.
VIO 96-05-01 Failure to cr3 ate a PR and OCR 6, 5 R VI3 96-05-04 Licensee approved eddy current acceptance criteria different 6, 2 N from TS requirements VID 96-05-05 Ts11ure to follow precedures for updating design basis 6, 4 CP-8 R documenta VIO 96-05-07 Inadequate receiving inspections for battery chargers (vendor 6, 4 R testab V12 96-05-08 Failure to follow purchasing procedures for inverters 6, 4 R VIO 96-06-02 No procedure for demineralized water flush performed by 6, 3 R operators on boric acid addition lines VI3 96-06-04 No evaluation on non-FSAR vital battery charger configuration 6, 4 R V13 96-06-06 Failure to timely notify the NRC of a condition outside the 6, 2 N.
Appendiz R Licensing design basis VI3 96-06-07 PR not initiated to resolve CREV5 test failure 6, 5 R 7
.p. ., -- , . , y
Z880s DESQL*PTIon AREA Nec 20/85R LICENSEE CORAGENTS NRC LEAD Status STATUS VIO 96-07-01 Failure to protect safeguards information 6, 7 N VIO 96-07-02 Failure to complete screening elements for Fitness for Duty 6, 7 N Personnel VIO 96-0s-01 Corrective action not taken on make-up system audit findings 6, 5 R
& excessive vibration on speat fuel pool pump cooling fan mot or VIO 96-09-01 Failure to follow a maintenance procedure resulting in the 6, 7 N inadvertent initiation of the control room emergency went11ation system VIO 96-09-02 Unesourted visitor persaan*1 within the protected area 6, 7 N VIO 96-09-03 Failure to perform a 10 CFR 50.59 safety evaluation for 6, 3 R changes to procedures described in the FSAR for controlling dissolved hydrogen concentration in the RCS VIO 96-09-04 Failure to update operating curves to reflect 1981 power 6, 4 R uprate VIO 96-09-05 Failure to incorporate design change of MUV-64 into 6, 4 R operations procedures VIO 96-09-06 Three examples of design control errors (erroneous 6, 4 OP-8 R calculation inputs and ISI h=n.4ryl VIO 96-09-07 Untimely corrective actions for the EFIC system concerns and 6, 5 R problems VIO.96-11-01 *nadequate work instructions to prevent the inadvertent start 6, 7 1 N of the A EDG VIO 96-11-03 Personnel performing work on the reactor building sump 6, 7 N e without logging or.co a clearance, as required by approved WR VIO 96-11-04 Reactor building sump not constructed in accordance with 6, 1 R approved construction drawings VIO 95-15-01 Failure to perform a required TS surveillance for the remote 6, 2 shutdown panel VIO 96-15-02 Failure of reactor coolant pump oil collection system to 6, 7 A retain oil leaking f rom reactor coolant pump IFI 94-18-09 Review periodic verification plans - MOV (GL 39-10 item 3 2 See IR 95-11, IR 95-21s N See CL 89-10 IFI 95-02-05 Resonance noise in vicinity of MJV-25 7 N IFI 95-08-03 Emergency Operating Procedure update prograe 3 See IR 95-16 VIO 93 N 07 IF1 95-11-01 SCBA requir-ts for personnel during a toxic gas release 2 N IFI 95-15-01 ,Desig.s requirements for nitrogen overpressure (service water) 1 See IR 95-21 R E
8 L
. ISSBNg meneuryyeces . AREA NBC IR/SER LICBBSEE CENSEENTS NRC LEAD STATUS STATUS IFI 95-15-02 Design requir===ars for dynamic LOCA affects J See IR 95-21 and TIA 96- N 013 IFI 95-15-03 Design requirements for reactor coolant pump cooler failure 1 See IR 15-21 and TIA 95- N 014 IFE 95-15-c4 Code requir===ar for thermal relief valves on decay beat 1 See IR 95-21 and TIA 96- N renowal beat exchangers 014 IFI 95-15-05 Relief valves removed from heat eschaaners 1 See IR 95-21 and TIA 96- N 014 IFK 95-21-02 Modification to the standby feedwater pump recirculation line 1 N IFI 94-03-15 Evaluate the licensee's revised TE Sases and related 10 CFR 2 R 50.59 analysis IFI 96-03-16 Review of MAR 96-02-09-01, MPI flow indicators, installation 1 N package and functional testing results IFI 94-04-03 Effect of setpoint calculations on ECP revisions 1 See VIO 93-16-07 N IFI 96-05-06 Large break lots of coolant analysis generic concerne 1 N ,
IFI 96-06-09 Deficiencies in Mecaties fire barrier program procedures and 4 IR 96-15 N. C documentation IFI 96-08-02 Reactor building cavity cooling piping thermal relief 1 See D.I. O, CL 96-06 N proteetion IFI 96-15-01 Actions takaa to resolve post-accident recriticality concerne 1 NRR reviewing, generic skaa to localized boroa dilution But issue IFI 96-201-11 Design basis for decay heat / core flood / reactor coolant piping 1 Identified in IPAP R I' e temperature report as IF-96-201-01 IFI 96-201-12 Conduit sising criteria - jamming ratio not considered 1 Identified in IPAP R report as IF-96-201-02 IFI 96-201-13 Cable ampacities - several cables exceed rating, including 1 Identified in IFAP R DNP-1 report as IF-96-201-01 IFI 94-201-14 EDG protective tripe not bypassed during emergency mode of 1 D-12 Identified in IPAP R operation report as IF-9s 201-04 IFI 96-201-15 Verification of motor starting data 1 Identified in IPAP R report as IF-96-201-05 IFI 96-201-16 Cbordination of Sarand level ==d=rvoltage relay (SIUR) 1 Identified in IPAP R setting vs. Inverter operation report as IF-96-201-06 IFI 96-201-17 Coordination of SI4lt and fuse protection 1 Identified in IPAP R report as IF-96-201-07 MN.TI-PEANT ACTIM e
9
~,,e- w-, ..
. .w-- , , , _ , , t -y.
i a
4 ..
i
, ISous asetaxyyscu : , samm unc ' 1R/ San ' LIcalmas colemurs Nec LEAD STAf45 STA7438 i sen teless Selamic spaalification of espalpment. Licensee's criterna and 2 Expected completion N GL 47-02 proceshares approved. Some issues are pending and would be December.
resolved thru audit techechaled for Mar 97). Licensee *s field walk h results are turrently la staff review. i set Still IPE and IPSEE - These are la staff review. Not a restart- 2 N 4IPS)s item.
MPAsette (IPERE)
MFA SL547s Pressure locking and thermal binding of safety-related gate ' '2 R GL 95-07 wolves. Qarrantly la staff review. An RAI is outstanding.
Espected completico?
MFA St4els . '
Testing of safety-related logic circuits - 2 R-1 11/96 the licensee has R.
GL M-01 Licensee response in staff review. More details are identified testing respaired. his imeue respaires attention, deficiencies that must be fixed prior to restart 894 SX682s h of heavy loads over spent fuel pool 2' ~ N amCB M-82 - Licemene r==gma=== la staff review. This would not be a restart 1seue.
sea SL2tes Thessolag - Licensee plans to use Mecaties' 2 See IR 96-01s IR 96-06 N ,
GL 92-04 EU (an alternate material), some reanalysis of APPEND 12 R, and S2-81 some esemption. Fire barrier tests of Mecatise including Ampacity tests are la staff review. This also may not be restart issue.
sea SL543s Circumferential cracklag of SG tube flaws. 2 R GL95-01 Licensee reara=== in staff review.
MFAS L201: Desctor vessel structural latogrity. RAI to licensee ca 2 N GL 92-01 Row 7/22/96. Only a data base issue, not a restart item.
- 1. Supp 1
.g tok85404s Boraflez degradation. Licensee response is just in. Staff 2 N GL 96-04 review to _ . This may have to be addressed prior to restart because of eenottivity to spent fuel pool issues.
seh Mov testing & surveillance. This item is closed with the- 2 See IFI 94-18-09 N GL SF"It exception of IFI 94-10-@9 on periodic werification, adnich is to be followed up after a new generic communication is t eenamA, LEMMB am/BM 3Ag533T8 COE- Ozoercl comples habitability envelope - Including TIA 95-01 2 R amed to be addressed. Licensee submittal does not provide adesguete TS action.
ER.S. 1.97 RG 1.97 imetrumentation - Subcool monitors etc - category- 2 N Imatru===es change. Licemme - ^ ; may be approved by December.
Dienstrice & Biometric esemption to allow taking security badges offsite - 2 N Security Staf f reviser is expected to be complete ane.a.
Core Fleed ^ Relief request RE: Core flood mossle - Staff needs more info. 2 N HosMe FM will keep RI! informed.
I s
10 U-- , , ,,.g.e.-r .--
-w- .-mv .-.--e-.e .w-,, my-%+-me%++ -t-w--w= vs= m"T~-- *-CT--e
- F*9"M-***'N
TL'N * *"""Y * '" ' * ' ' " ' ^ '"*# * '"
l 1885E DasCRIPTZou AREA NaC IR/SEE LICENSEE
, CENSEENTS NRC tEAD STATUS STATUS MSG Tubes MSG tube testing - Licensee proposed a revised CTSG tube 2 See VIO 96-05-04 N acceptance criteria.
OT M ISSUBS Pressurizar Daring Refuel 9 a sub-surface flaw was discovered. The 2 N Nosale Flaw licensee performed better inspection during R10 and found the flaw to be acceptable. The new inspection results in reduced flaw size and consequently acceptance criteria (which is based on ratio of flew to thickneso) changes. May require inspection. Staff review in progress. .
RC toop In a survey inspection, the staff noted that certain branch 2 N Piping pipes off the primary coolant loop were not analyzed as Code Analyses Class 1 pipe (i.e., no fatigue ar.alysis) as required by the code. Need technical branch's opinion on this. This is not expected to be restart issue.
Criticality The licensee did not carry a previously approved exemption 2 N Monitor from part 70 (70.247) requirements to Part 50 license. Need -
legal interpretation of the status of the exemption.
L70P Current TS does not address LTOP prevention or mitigation. 2 N '
On the basis of GL 88-11, the liceasee submitted information to demonstrate that LTOP in B&M plants have less than 1 in 100 reactor years probability of occurrence and as a result per GL 38-11 non-appendiz G methodofogy can be used for PT curves. Such a PT curve would provide for higher LTOP enable pressure and temperature and would provide operational flexibility. Staff denied the request in 1995 and requested a revised response. The licensee expects to reersond late 1997.
Appendia R Appendia R design basis issues review by FPC consultant. MRC R I e review open Appendia R issues to assure that there are no restart or operability issues imbedded in them.
1 Operator NRC review operator workarounds list to assure that there are See VIO 96-09-07 R teorkarounds no restart or operability issues contained in then UEOs Licensee request and NRC review and issue license amendments R-2, R-4 R for all Unreviewed Safety Questions (USOs3 IIAT Conduct an ILRT or seek an h ad===r to utilize Method 8 of R Appendia J to 10 CFR 50 50.54f Imtter NRC review licensee's 53.54f letter response (due 2/9/97) on R design bases License verify license conditions are met conditions R Sources for issues include: IFS, SIMS, NUREG 1435 (Status of Safety Issues at Licensed Power Plonts), Resident's OIL, PM's OIL NOTE: Open allegations, OI investigations, and emerging / draft issues are. listed separately.
o 11
% . - - - . - , =
_ . . _ _ _ _ . . _ . _ . _ _ . _ _ _ . _ . . _ . _ . . _ . _ . _ _ _ . _ _ _ _ . .~. _
4 e .
"tstus as of 42/03/%.
CRYSTAL RIVER RESTART TASK CHECKLIST l TASK HC 0350' RESP. REFERENCE STATUS 1 REF APP A
- n. w s, n.w ,w,. ~n ... . m p y qg pilssue% w a :.ny;c ru s.~-. nary.notifid tionW rprelikw 18?2tbW,; fRIllin&O Ag*w M !CW: .
. . ~
Congressional Notification B.2 g.
,_m n n. . - .
lEstMhshM,,tarty5,a gJgg, S* i8i3?a - _
.-~ .
M@wWmMenn As?&ww,$ W. TRIINNRR! E11/1/96kg.h ICi~ !h, W mm i EfW !$0E11t M k M@WW ISsssisMsiiA61SM$niidf$rifee I$f3%iME *6 M M!%M@ E!YEIM DEve r., ww my . _w ck lop CasetSpecificMw.r1fstl ..,
!Bi3 v%fum.
t wd ---
iRIIMHRR; 611713/96 % %
b e ,n Develop' Restart Action Plan B.3 g. RII. NRR
- Regional Administrator Approves .B.3 h. RII Restart-Action Plan NRR Associate Director Approves B.3 1. NRR e
Restart Action Plan-i- Implement Restart Action Plan B.3 j. RII i' Evaluate findings of IPAP B.4.1 a. PANEL -
Inspection nmn, ., en , nung nmma ti censee,f performstroot,icausene fginO,L m y , 7y# 4 B 1 m? y~ssor &
[ana19siMand?de' $1censees.
L" v elopsicorrectivei MiB % ? -
W? &i fa~ction 41an & +3 W W @ W % MOWD # EP#AnM*d n ~ 4$@M WG NRC evaluates licensee's root B.4.1 c. PANEL
[ cause determination and-i corrective action plan
- Review licensee generated B.4.3 a, PANEL restart issues i Independent NRC identification B.4.3 b. PANEL of restart items (consider external sources)
NRC/ Licensee agreement on B.4.3 c. PANEL F
- restart issues i Evaluate Licensee's restart B.4.3 d. PANEL 4
issues implementation process t
Evaluate Licensee's .
B,4.3 e. RII implementation _of verification process Evaluate Licensee's restart B.4.5 a. PANEL 2
readiness self-assessment 3
5
- ATTACHMENT B
! 4
-- - , ;. . - - . - . a._... . . - . , , , - -- -
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 olan l
~~ Comments from other parties B.4.5 f. PANEL considered Re-review of Generic Restart B.4.5 h. PANEL Checklist complete Prepare restart authorization B.5 a.
document and basis for restart NRC Restart Panel approves B.5 b. PANEL Restart Authorization No restart objections from other B.5 c NRR. RII applicable H0 offices PANEL No restart objections from B,5 d RII applicable Federal Agencies Regional Administrator concurs B.5 e. RII in Restart Authorization NRR Associate Director concurs B.5 f. NRR in Restart Authorization EDO 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. NRR requested Commission concurs in Restart B.5 j. PANEL Authorization when required I
Regional Administrator B.5 k. RII authorizes restart l
ATTACHMENT B i l
l J
TASK 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 E00 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.
4 agencies of restart authorization i
Notify Public Affairs of restart B6f. RII authorization l Notify-. State and Local officials B.6 g. RII '
, of restart authorization Notify citizens or groups that B.6 h. RI'I
- expressed interest during the
! restart approval process i
1 ATTACHMENT B
$tatu1 41 Of l?/03/96 CRYSTAL RIVER RESTART ISSUES CHECKLIST ISSUE MC 0350 RESP. REFERENCE STATUS REF APP A ,
ASSESSMENT OF ROOT CAUSE IDENTIFICATION AND CORRECTION Tohd(6bns mduirincfshutdowns
!aretclearly understood' ICilillai lPANELi
c 1 F^
9/
l Rbotica dssslof!$ie) c6ridi tYons :
(recuiringishutdesn clearly"e Cdfl%
.i
!FANEli', #
~'
. W :
. X '%
iuncerstood F ' 41" 7t - '
N
' Root causesiofJoEherJsignificanE i
problemsVclearly1understoodi<
Ililfci' iP N'EL4
., M'%
Effectiveness of root cause C.1.1 d. PANEL analysis program Thoroughness of corrective C.1.3 a. PANEL action plan Completeness of corrective C.1.3 b. PANEL action plan Control of corrective action C.1.3 c. PANEL item tracking Effective corrective actions for C.1.3 d. PANEL the condition requiring shutdown implemented '
Effective corrective actions for C.1.3 e. PANEL other significant problems implemented Plan Control of long-term corrective C.1.3 f. PANEL actions Effectiveness of corrective C.1.3 g. PANEL action verification process Effectiveness of QA Program C.1.4 a. PANEL Effectiveness of industry C.1,4 b. PANEL experience review program Effectiveness of Licensee's C.1.4 c. ] PANEL independent review groups Effectiveness of deficiency C.1.4 d. PANEL reporting system ATTACHMENT C
~ 1 l
ISSUE- MC 0350 RESP. REFERENCE STATUS REF APP A >
Staff willingness to raise C.1.4 e. PANEL ConCPrns Effectiveness of conmitment C.I.4 g. PANEL tracking program External Audit (i.e. INP0) C.1.4 h. PANEL capability ASSESSMENT OF LICENSEE MANAGEMENT EFFECTIVENESS Goals / expectations communicated C.2.1 a.
_ to staff Demonstrated expectation of C.2.1 b.
, 3dherence to procedures Management involvement in self- C.2.) c.
assessment and independent self-assessment capability Effectiveness of 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
!$f$dYNN$$7 Aid 20indiyM 6fEIN$9 -
iRd5{d5% 5 WWMi@4&j!enip"lofeelconce$s*k fresol0t1oin2of rn5 [ME F*@kk'[ M My %*M id {ilR!96i095 I [Mg MF *?a*Mem JW $W J . Mi CM^ Am _M 3
Adequate engineering support as C.2.2 c. PANEL demonstrated by timely resolution of issues ATTACHMENT C
k O
ISSUE MC 0350 RESP. REFERENCE STATUS REF APP A Adequate plant administrative C.2.2 d. PANEL procedures -
Engineering / Licensing Effective information exchange C.2.2 e.
with other utilities ASSESSMENT OF PLANT AND CORPORATE STAFF EFFECTIVENESS Demonstrated commitment to C.3.1 a.
achieving improved performance
~~
Demonstrated safety C.3.1 b.
consciousness Understanding of management's C.3.1 c.
expectations and goals Understanding of plant issues C.3.1 d.
_and corrective actions Qualifications and training of C.3.1 e.
staff Attentiveness to duty C 3.1 g.
Level of attention to detail C.3.1 h.
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.
requirements and licensee goals Level of formality in control C.3.3 b.
room Effectiveness of control room C.3.3 c.
simulator training Control room / plant operator C.3.3 d.
awareness of equipment status Adequacy of plant operating C.3.3 e.
procedures Procedure usage / adherence C.3.3 f.
Log keeping practices C.3.3 9 ATTACHMENT C
r .
wq ISSUE MC 0350 I RESP. REFERENCE STATUS REF APP A ASSESSMENT OF PHYSICAL READINESS OF PLANT Operability of technital C.4 a.
Specification systems Operability of required C.4 b.
secondary and support systems Results of pre-startup testing C.4 c.
Adequacy of system lineups C.4 d.
Adequacy of Surveillance C.4 e.
tests / test program Significant hardware issues C.4 f.
resolved (i.e. damaged equipment, eq ipment ageing, modifications 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.
and equipmert storage ASSESSMENT 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 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.
Agency ATTACHMENT C
1 i
l ISSUE MC 03SO RESP. REFERENCE STATUS REF APP A Appropriate Sate and local C.6 e.
officials Appropriate public interest C.6 f.
groups Local news media C.6 g.
4
- e.
ATTACHMENT C
.