ML041100732

Per Report, Work Order No. 02-000550-000

ML041100732
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: ML041100732 (8)

Text

r Sequoyah Nuclear Plant Page 1 PER Report PER100 03/01/02

,Workorder: 02-000550-000 Status: I Entry Date: 01/18/2002 15:24 Planner/Supv: JOHN THOMAS Requested By: BRENDA F. SIMRIL 843-8515 a 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.

Pit 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 Units Affected 1&2 Recommendation Process PER No action, Justify If Process,PER 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.

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r Sequoyah Nuclear Plant Page 2 PER Report PER100 03/01/02 f 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 ENG/MECH Init Sup Review Date 01/18/2002

• 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 Init Sup Review Date OPS Functional Eval (FE) Y FE Due Date 01/22/2002 Affect Operability If Yes,Units/Actions Offsite OP Review Y Op Review BFN N Op Review BLN N Op Review SON N Op Review WBN Y Reportable Y If Yes, List Basis It was determined that sufficient lighting did not exist to provide for local, manual operation of FCV-63-1 on Unit I 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.

• Sequoyah Nuclear Plant Page 3 PER Report PER100 03/01/02 Ops SROISTA-Fst Last Toney Whitten Ops SRO/STA 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 closing isolation valves.

Issued standing order to require use of hand held lighting when manually closing 1,2-FCV-3, and -21 to mitigate an Appendix R fire.

Engineer John Thomas Date 02/1112002 Supervisor John Thomas Date 02/11/2002 OPS SRO/STA-Fst Last OPS SRO/STA Rev Date MRC Process PER Level C Interim Action Req'd N If YES, Specify RCA Required N Site Qual ConclVer N

Sequoyah Nuclear Plant Page 4 PER Report PER100 03/01 /02 Assigned Resp Org ENG/MECH CA Develop Due Date 02120/2002 MRC Directions MRC CAP Review N MRC-First Last John Hamilton MRC Review Date 01/2212002 be Resp Org CA Develop Due Date 0212012002 Section ENGJMECH ..

POC-First Last Brenda Simril POC Phone 8515 Reactivity Mgt Issue N ANB-LER N LER No.

Control of NonConfor N If Yes, Scope Hardware Disposition Disposition RIM/EDMS Offsite Generic Rev Y Generic Rev BFN Generic Rev BLN Generic Rev Corp Generic Rev SQN Generic Rev WBN Y Process/Procedures

'- CAUSEUDATA Apparent Cause Engineering failed to identify design requirements for qualified lighting to perform manual actions to mitigate a fire in accordance with Appendix R.

Root Cause Causing Org ENGIELECT Causing Crew Human Perf Proc Code HP Perf Second Code Prev/Similar Event N/A Specify Search Basis Extent of Condition PER HUMAN PERF PER CAIRC ITEMS 1 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.

Sequoyah Nuclear Plant Page 5 PER Report PER100 03/01/02 1 Action Type CORRECTIVE ACTION 1 Assigned Org ENG/ELECT 1 CA Due Date 0313012002 1 AO Concur-Fst Last 1 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 05/3012003 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 ENGIMECH 3 CA Due Date 05130/2002 3 AO Concur-Fst Last JOHN THOMAS 3 AO POC Fst Last BRENDA SIMRIL 3 CA Performed 3 Date Completed CLOSURE COMMENTS FROM CA CAPCONCUR~

PERCompletion Date 05/3012003 Prep-First Last John Thomas Preparer Date 02/2012002 Telephone No 8224 (C) Supv-First Last John Thomas (C) Supv Ext 8224 (C) Supv Date 02120/2002 (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) PItMgr Date

Sequoyah Nuclear Plant Page 6 PER Report PER100 03101/02 React Eng-Fst Lst React Eng Date Site Qual Conc Reqd N Site Qual Concur Reason for N Site Qual First Last Site Qual Date VERIFICATION Final Rev Level Tags Rem-First Last Tags Date RO Verify Comp RO Verify Date ANI/ANII Required N ANI/ANII Concurrence Reason for N ANI/ANII-First Last ANI/ANII Date Site Qual Concur Reason for N Site Qual First Last Site Qual Date RO Supv Clos-Fst Lst Closure 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

Sequoyah Nuclear Plant Page 7 PER Report PER100 03/01/02

CORP Review-Fst Lst CORP Review Date SON 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 02113102 for information only review.

WBN Review-Fst Lst TERESA WILSON WBN Review Date 02/1312002 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 BENNElT WBN Notified Date 01/2512002 WBN Op Rev Results A review of WBN AOI-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 Lst DUNCAN BENNElT WBN Review Date 0112512002 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

'Org I Prog Code GEMS Other CAUSE CODES Total records selected: 1

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