ML20036B302
| ML20036B302 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/13/1993 |
| From: | Fenech R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9305190037 | |
| Download: ML20036B302 (6) | |
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A Tewssee vaky Aeonty Post offee som 20T SaddrDrmy.Tenrvssee 37377237J t
Robert A. Fenech vee P escem Seamah % clear Piant May 13, 1993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk i
Washington, D.C. 20555 Gentlemen:
f In the Matter of
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Docket Nos. 50-327 i
Tennessee Valley Authority
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50-328 4
SEQUOYAH NUCLEAR PIANT (SQN) - FIRE PROTECTION IMPROVEMENT PIAN PER7.0DIC STATUS REPORT A working meeting between TVA and NRC was held at SQN on August 19, 1991, to discuss the self-identified problems in SQN's fire protection program and the improvement plan efforts initiated by TVA. As a result of this meeting, TVA agreed to submit periodic status reports to inform NRC on f
the progress of efforts made in conjunction with the improvement plan.
i The most recent status report identifying progress achieved and areas b
needing further action is included in Enclosure 1.
Changes to the improvement plan are identified in Enclosure 2.
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If you have any questions concerning this submittal, please telephone
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j C. H. Whittemore at (615) 843-7210.
Sincerely, kk-W.
Robert A. Fenech l
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Enclosures cc:
See page 2 l
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t 9305190037 930513 PDR. ADOCK 05000327 l
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U.S. Nuclear Regulatory Commission Page 2 May 13, 1993 Enclosures cc (Enclosures):
Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 I
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EVCLOSURE 1 FIRE PROTECTION IMPROVEMENT PLAN - STATUS FOR PERIOD ENDING APRIL 1, 1993 Ehase I - Phase I is Complete P
Phase II - Phase II is Complete Ihase III - Targeted Completion Date October 1. 1993 l
3-1 Perform an independent fire protection assessment to assess that the f
actions taken in Phase II are properly implemented and effective.
Status:
This item is complete as documented in the Nuclear Quality i
Assurance-Biennial / Triennial Fire Protection Audit - SQA92209 and via memorandum dated January 22, 1993, from T. A. Flippo, i
Site Quality Manager, to R. S. Egli, Fire Protection Manager.
The results of the assessment were positive in that the issues reviewed were found to be properly implemented and effective.
I 3-2 Issue a revised Fire Hazards Analysis (FHA).
Status: This item is approximately 5 percent complete. Data gathered in relation to the walkdowns (Item 3-5) will be used as a I
basis for the combustible loading calculations. Upon completion of the calculation, the FHA will be updated. This i
is expected to be accomplished by September 24, 1993.
I 3-3 Perform a life-cycle analysis on high-pressure fire protection (HPFP) i components and provide replacement recommendations.
Status: This item has been rescheduled to be completed in Phase IV (refer to Item 4-5) and will be accomplished in conjunction with Item 4-4.
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3-4 The Fire Protection Manager is to review previous commitment items for effectiveness and completeness to ensure that the improvement program j
has been adequately addressed and implements proposed corrective actions.
This item will be accomplished in conjunction with the independent assessment described in Item 3-1.
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Status: This item was completed by the Fire Protection Manager on March 8, 1993. Completed items were found to be adequately implemented and effective.
E 3-5 Perform a plant-walkdown procedure to update the FHA.
i Status: This item is complete.
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3-6 Evaluate the necessity of field verification of the FRA and establish methods, as appropriate, before issuance of the FHA.
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i Status: The walkdown completed in Item 3-5 will be used to update and verify the FHA. The means to keep the FHA current will be f
incorporated into the revised FRA for completion of Item 3-2.
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This item was previously rescheduled to Phase IV (refer to Item 4-4).
3-7 3-8 Complete an evaluation of the mechanical and electrical fire-barrier penetration seals in accordance with the guidelines in Information Notice No. 88-04.
a Status: Plant walkdowns of penetration seals to gather information for evaluation are 75 percent complete. This includes an additional scope of work (approximately 5,000 penetration seals) that has been identified and will require additional time to complete (this item was originally estimated to be completed in July 1993).
Evaluations based on walkdown information are currently 10 percent complete. This issue is estimated to be complete by September 1993.
3-9 Ensure that the SQN fire protection design and site-specific Loplementation instruction (for design) adequately reflect design j
criteria and general engineering specifications issued from corporate j
Nuclear Engineering.
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Status: This item is complete.
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3-10 Upgrade the preventive maintenance (PM) program for the fire protection hardware in System No. 39, "CO-2 Storage, Fire Protection and Purging
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System."
l Status: The reliability-centered maintenance study on System 39 has been completed. Recommendations concerning the upgrade of the
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System 39 FM program are scheduled to be complete by l
l October 1, 1993.
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Sate _lY - Targeted _Completi_onJatelecember_L 1994 i
4-1 Perform an independent fire protection assessment to assess that 4
actions taken in Phase III are properly implemented and effective.
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Status: This item has not been started, awaiting completion of l
Phase III.
j 4-2 This item was previously rescheduled and is now included as part of
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Phase III (refer to Item 3-8).
l 4-3 Issue the remaining updated design documentation to support final compilation into the SQN Fire Protection Report and establish a process to maintain documentation current.
l Status: Current design control processes are considered adequate to I
maintain the documentation current. Preliminary work has begun on this item.
This item is on schedule for completion
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by December 1, 1994.
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. j Issue a design package for PCN 607.
4-4 Status: The design for this item is approximately 15 percent complete.
Initial flow calculations have been performed,
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piping routes have been determined, pump and tank j
specifications have been written, and initial layouts for the buildings have been completed. Work is continuing on this item. However, as a result of recent events, the overall j
schedule and funding levels for this effort have been evaluated, and the completion date for the design change
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package associated with this change has been extended to fiscal year 1994.
4-5 Perform a life-cycle analysis on HPFP components and provide i
replacement recommendations.
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Status: This item will be dispositioned in conjunction with the j
upgrade to the fire protection system within the scope of
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Project Control No. (PCN) 607 (refer to Item 4-4).
In the new i
design of the system, consideration will be given to
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components that may be near their design-life limit.
It.is not anticipated that any components will require replacement.
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ENCLOSURE 2 l
CHANGES TO THE FIRE PROTECTION IMPROVEMENT PLAN I
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Phase IV
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l 4-5 Perform a life-cycle analysis on high-pressure fire protection components and provide replacement recommendations.
Status: This item will be accomplished in conjunction with the upgrade to the fire protection system within the scope of PCN 607.
In the new design of the system, co:isideration will be given to 4
I components that may be near their design life limit.
It is
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l not anticipated that any components will require replacement.
!i This item was originally scheduled to be completed in Phase III as Item 3-3.
However, after closer examination, it 1
has been determined that the item can be accomplished easier j
j and with less repetitive analysis if it is performed in l
conjunction with the PCN 607 activity (Item 4-4).
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