ML041100734
| ML041100734 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/01/2002 |
| From: | Simril B, John Thomas Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2003-0358 | |
| Download: ML041100734 (10) | |
Text
Ji ram mepon FER100 03/01/02 Workorder 02-000550-000 Wtatus: I Fntry Date: 01/18/2002 15:24' PlannerISupv JOHN THOMAS Requested By: BRENDA F. SIMRIL 843-8515 SUPERVISOR PER Level Rev Level 00 Identified By LINE ORGANIZATION Self Revealing Y Problem Description As part of the extent of condition for PER 00-007928-000, the following Issue has been identified.
While verifying specified Appendix R manual actions and timelines associated with mitigation of spurious operation of valves 1.2-FCV-63-072 & -073, it has been determined that all technical issues were not considered. Specifically, manual actions specified for closure of valve 1.2-FCV-63-001 did not alert the operator to the potential for requiring local manual operation of the valve. Additionally, emergency lights have not been provided for local operation. Follow up walkdowns have been performed and accessibility of 1,2-FCV-63-1 has been confirmed.
PR Process Equip Y Potential Oper Issue Y Potential Reportable Y Potential Degrad/Noncon(91-18) Y ASME N Systems Affected N/A Systems Affected Systems Affected Systems Affected UnitsAffected 1&2 Recommendation Process PER No action, Justify If ProcessPER Level D If Utilize ACP, No Immed Action Taken Performed walkdowns of 1,2-FCV-63-1, -2 to determine accessability for manual -operation.
Provided guidance to operations to revise AOP-N.01 to respond to spurious operation of 1,2 FCV-063-072, -73 by manually closing 1,2-FCV-74-3, -21 as appropriate.
Sequoyah Nuclear Plant Page z
PER Report PER100 03101/02 Specified appropriate equipment to ensure manual actions can be completed within required time frame.
Contacted operations to re-evaluate minimum operator staffing requirements for responding to an Appendix R fire.
Revised AOP-N.01 to allow manual closure of FCV-63-1 for areas where RHR valves are inaccessable.
Recommended Resp Org ENG/MECH Coordinated With John Thomas Init Sup-First Last John Thomas Init Sup Phone 8224 Init Department ENGIMECH Init Sup Review Date 01/1812002 LEVEL D INFORMATION Lvl D Causing Org LvA D Causing Crew Human Perf Proc Code Apparent Cause LvI D Process/Proced Hardware Disposition Technical Justify Init Supv-First Last Init Supv Phone nit Sup Review Date C~OPSE Functional Eval (FE) Y FE Due Date 01/2212002 Affect Operability If Yes,Units/Actions Offsite OP Review Y Op Review BFN N Op Review BLN N Op Review SQN N Op Review WBN Y Reportable Y If Yes, List Basis It was determined that sufficient fighting did not exist to provide for local, manual operation of FCV-63-1 on Unit 1 or Unit 2. This condition was reported in accordance with License Condition 2.H for Unit 1 and 2 operating license to the Region II Director.
PER Report PER100 03101/02 Ops SROISTA-Fst Last Toney Whitten Cps SROISTA Rev Date 01/18/2002 FE Functional Maint N Potential Degrad/Noncon(91-18) Y FE/Eval Due Date Initial Evaluation A review of the condition identified revealed that this condition is in non-compliance with SQN's current licensing basis for maintaining Appendix R lighting and Is therefore, reportable.
91-18 Degrad Nonconf Y Functional/Eval Basis Actions associated with FOR 3.7.14.a taken to provide alternate lighting.
AOP-N.01 revised via the 50.59 process, therefore.
functional evaluation not required per SPP3.1.
Immed/Comp Measures Y List Action/Measures Notified NRC of condition within required 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Revised procedure AOP-N.01 to manually/locally close 1,2-FCV-74-3 and -21 to mitigate the spurious opening of 1.2-FCV-63-72, -73 and subsequent draining of RWST Into containment Provided tooling to assist operator In manually dosing isolation valves.
Issued standing order to require use of hand held lighting when manually dosing 1,2-FCV-3, and -21 to mitigate an Appendix R fire.
Engineer John Thomas Date 02/11/2002 Supervisor John Thomas Date 02/11/2002 OPS SRO/STA-Fst Last OPS SROISTA Rev Date MRC Process PER Level C Interim Action Req'd N If YES, Specify RCA Required N Site Qual Conc/Ver N
Sequoyah Nuclear Plant Page 4
PER Report PER100 03/01/02
- signed Resp Org ENG/MECH N Develop Due Date 02/20/2002 RC Directions RC CAP Review N RC-First Last John Hamilton RC Review Date 01/2212002 Resp Org A Develop Due Date 02/20/2002 ection ENG/MECH OC-First Last Brenda Simril OC Phone 8515 eactivity Mgt Issue N IB-LER N ER No.
ontrol of NonConfor N Yes, Scope
.ardware Disposition
'isposition RIMIEDMS iffsite Generic Rev Y
- eneric Rev BFN
- eneric Rev BLN
- eneric Rev Corp
'eneric Rev SON
- eneric Rev WBN Y
'rocess/Procedures A
CAUSE DATA
%pparent Cause Engineering failed to identify design requirements for qualified lighting to perform manual actions to mitigate a fire in accordance with Appendix R.
toot Cause ausing Org ENGIELECT
'ausing Crew
-uman Perf Proc Code UP Perf Second Code
'rev/Similar Event N/A Specify Search Basis
-xtent of Condition PER HUMAN PERF PER CANRC ITEMS I Action Item Issue design change documentation to rewire the control circuit for FCV-63-72 and -73 such that spurious operation of the valves from an Appendix R fire will not occur.
PER Repon FER10aj 03101/02 I Action Type CORRECTIVE ACTION
'Assigned Org ENGIELECT I CA Due Date 03/30/2002 1 AO Concur-Fst Last I AO POC Fst Last RON GLADNEY I CA Performed 1 Date Completed 2 Action Item Verify implementation of DCN for Unit 1 2 Action Type CORRECTIVE ACTION 2 Assigned Org ENG/MECH 2 CA Due Date 05/30/2003 2 AO Concur-Fst Last JOHN THOMAS 2 AO POC-Fst Last BRENDA SIMRIL 2 CA Performed 2 Date Completed 3 Action Item Verify implementation of DCN for unit 2 3 Action Type CORRECTIVE ACTION 3 Assigned Org ENG/MECH 3 CA Due Date 05/30/2002 3 AO Concur-Fst Last JOHN THOMAS 3 AO POC Fst Last BRENDA SIMRIL 3 CA Performed 3 Date Completed CLOSURE COMMENTS FROM CA CAP CONCUR PER Completion Date 05130/2003 Prep-First Last John Thomas Preparer Date 02120/2002 Telephone No 8224 (C) Supv-First Last John Thomas (C) Supv Ext 8224 (C) Supv Date 02/20/2002 (B) DptMgr-Frst Last (B) DptMgr Date MRC Reqd N MRC Concurrence Reason for N MRC-First Last MRC Date (A) SiteSr-Fst Last (A) SiteSr Date (A) PItMgr-Fst Lst (A) PltMgr Date
Sequoyan Nuclear Plant Page 6
PER Report PER100 03/01/02
- eact Eng-Fst Lst
.eact Eng Date
- ite Qual Conc Reqd. N
- ite Qual Concur teason for N
- ite Qual First Last
- ite Qual Date VERIFICATION Tinal Rev Level ags Rem-First Last
- ags Date tO Verify Comp ZO Verify Date kNIIANII Required N kNi/ANII Concurrence Reason for N MNI/ANII-First Last
%NI/ANII Date site Qual Concur Reason for N Mite Qual First Last Mite Qual Date
- O Supv Clos-Fst Lst
_losure Date EXTENSIONS
^
REVISIONS GENERIC REVIEWS BFN Resp Org BFN Due Date BFN Gen Rev Results BFN Review-Fst Lst BFN Review Date BLN Resp Org BLN Due Date BLN Gen Rev Results BLN Review-Fst Lst BLN Review Date CORP Resp Org CORP Due Date CORP Gen Rev Result
PER Report PER100 03/01/02 CORP Review-Fst Lst CORP Review Date SQN Resp Org SON Due Date SON Gen Rev Results SON Review-Fst Lst SON Review Date WBN Resp Org ENG/MECH WBN Due Date 02/13/2002 WBN Gen Rev Results Copy to CR Allen 02/13/02 for Information only review.
WBN Review-Fst Lst TERESA WILSON WBN Review Date 02113/2002 OPERABILITY REVIEWS BFN Notified-Fst Lst BFN Notified Date BFN Op Rev Results BFN Review-Fst Lst BFN Review Date SON Notified-Fst Lst SON Notified Date SON Op Rev Results SON Review-Fst Lst SON Review Date' WBN Notified-Fst Lst DUNCAN BENNETT WBN Notified Date 0112512002 WBN Op Rev Results A review of WBN AO1-30.2 did not Identify any local manual actions taken at the valve for 1-FCV-63-1.
Therefor this PER Is not applicable to WBN.
WBN Review-Fst ist DUNCAN BENNETT WBN Review Date 01/25/2002 TRENDS Program Code FP Program Code Program Code INPO Code FP1 INPO Code NRC Code NRC Code Category PROCESS Short Term Code Impact 4.0 Behavior Code
Sequoyah Nuclear Plant Page 8
- ° PER Report PER100 03/01/02 rg I Prog Code EMS ther AUSE CODES Total records selected:
I
- '^END OF REPORT
TVAN
-I SQN Fire Hazards Analysis Calculation l SQN-26-D0541 I
EPM-ABB-MIPFHA APPENDIX A.1
.6 1
Fire Area Valve with Spurious Possibility Required Manual Action FAA-098 1-FCV-063-073 Locally Close I-FCV-74-21 FAA-099 1-FCV-063-072 1-FCV-063-073 Locally Close I-FCV-74-3 and MCR Close 1-FCV-74-21 and then.
pull fuses/open breaker for valve i
FAA-100 F
1-CV-063-072 I-FCV-063:073 Locally Close 1-FCV-74-3, MCR Close 1-FCV-74-21 and then pull fuses/open breaker for valve FAA-102 2-FCV-063-072 2-FCV-74-3 Close from the MCR and then pull fus'es/open breaker for valve FAA-103 2-FCV-063-072-2-FCV-74-3 Close'from the MCR and then
..pull fuses/open breaker for valve FAA-107 2-FCV-063-072 2-FCV-063-073 Locally Close 2-FCV-74-3 and -21 FAA-108 FCV-063-072 Locally Close 2-FCV-74-3 In each of the fire areas listed above, in addition to the specifically identified actions, in order to prevent further spurious valve actuations, the breakers should be opened at the MCC for the following valves:
' FCV-063-072
-FCV-072-020 FCV-063-073 FCV-072-023 For fires in FMA-94, -95, -107, or -108 (Rxt MOY Board Roomns) breakers for the MQVs may be inaccessible. Therefore, the Rx MQV Boards may be de-energized from the 480V Shutdown Boards.
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TVAN SQN Fire Hazards Analysis Calculation SQN-26-D054/
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I lEPM-ABB-ll%1PFiA]
APPENDIX A.1 Appendix A.1.(e)
Spurious Opening of RCS Sump Suction Valves 63-72 & 63-73 in AB INOTE:
The compliance strategies and manual actions specified in this Appendix are required until implementation of DCNs D-21152 (Ul) and D-1 153 (U2)
For each of the Fire Areas Listed in the Table below there is a potential spurious opening of the Containment Sump Valves 1,2-FCV-63-072 or -073. For each of these fire areas the valves which could spuriously open and the mitigating action are listed. Additionally, for each of these areas the following generic local manual operator actions within 25 minutes are required:
Fire Area Valve with Spurious Possibility Required Manual Action FAA-001 I-FCV-063-072 1-FCV-063-073 Locally Close l-FCV-63-1 OR 2-FCV-063-072 2-FCV-063-073 1-FCV-74-3 and -21 Locally Close 2-FCV-63-1 OR 2-FCV-74-3 and -21 FAA-013 l-FCV-063-072 I-FCV-063-073 Locally Close l-FCV-74-3 and -21 FAA-026 2-FCV-063-072 2-FCV-063-073 Locally Close 2-FCV-74-3 and -21 FAA-029 Al-A6 I-FCV-063-072 I-FCV-063-073 Locally Close I-FCV-74-3 and -21 2-FCV-063-073 Locally Close 2-FCV-74-21 FAA-029 A13-2-FCV-063-072 Locally Close 2-FCV-74-3 A15 FAA-044 2-FCV-063-072 2-FCV-063-073 Locally Close 2-FCV-74-3 and -21 FAA-054 -
I-FCV-063-072 1-FCV-063-073 Locally Close l-FCV-74-3 and -21 A2-A5 I Q-S &
2-FCV-063-073 Locally Close 2-FCV-74-21 A5-A8 / Q-R FAA-054 -
2-FCV-063-072 2-FCV-063-073 Locally Close 2-FCV-74-3 and -21 AlI-A14 /Q-S FAA-067 I-FCV-063-072 I-FCV-063-073 Locally Close l-FCV-74-3 and -21 2-FCV-063-073 Locally Close 2-FCV-74-21 FAA-070 I-FCV-063-073 Locally Close l-FCV-74-21 2-FCV-063-073 Locally Close 2-FCV-74-21 FAA-074 1-FCV-063-073 1-FCV-74-21 Close from the MCR and then pull fuses/open breaker for valve FAA-081 2-FCV-063-072 2-FCV-063-073 Locally Close 2-FCV-74-3 and -21 FAA-085 2-FCV-063-072 2-FCV-063-073 Locally Close 2-FCV-74-3 and MCR Close 2-FCV-74-21 and then pull fuses/open breaker for valve FAA-094 l-FCV-063-072 I-FCV-063-073 Locally Close l-FCV-74-3 FAA-095 I-FCV-063-073 Locally Close I-FCV-74-21 2-FCV-063-073 Locally Close 2-FCV-74-21 Page A.l.(i)