ML20059C048
| ML20059C048 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/26/1993 |
| From: | Fenech R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9310290219 | |
| Download: ML20059C048 (5) | |
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Rot; ort A ienech ww Fwmiumt sequoyvi thew << aant October 26, 1993 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
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Docket Nos. 50-327 Tennessee Valley Authority
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'50-328 SEQUOYAll NUCLEAR. PIANT (SQN) - FIRE - PROTECTION IMPROVEMENT PLAN. PERIODIC 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
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and the improvement plan efforts initiated by IVA. As a result of this meeting, IVA agreed to submit periodic status reports to inform.NRC on the progress of efforts made in conjunction with the improvement plan.
a The most recent status report identifying progress achieved and areas needing further action is. included in the enclosure.
If you have any questions concerning this submittal, please telephone C.11. Whittemore at (615) 843-7210.
Sincerely, hhf $, -h wA
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Robert A. Fenech Enclosure cc:
See page 2 290052 i
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9310290219 931026
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I U.S. Nuclear Regulatory Commission Page 2
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October 26, 1993 Enclosure i
cc (Enclosure):
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 h
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J ENCLOSURE FIRE PROTECTION IMPROVEMENT PLAN - STATUS FOR PERIOD ENDING OCTOBER'1, 1993 EhaSe I - Eh8DC 1 LB._Com21RLc Ehanell - thaSelLLBlomplRLc i
Phcac_LII _fhasellLis__ComplaLe 1
3-1 Perform an independent fire protection assessment to assess that the actions taken in Phase II are properly implemented and effective.
Status:
This item was previously reported as having been completed.
3-2 Issue a revised Fire Hazards Analysis (FHA).
Status: The FHA upgrade has been completed. The Sequoyah Nuclear Plant walkdowns have been performed, resulting in combustible loading calculations being generated. The calculations have been used as input to revise the Fire Hazard Analysis.
3-3 Perform a life-cycle analysis on high-pressure fire protection (HPFP)'
components and provide replacement recommendations.
Status:
This item has been evaluated and will be accomplished in conjunction with Item 4-4 during Phase IV (refer to Item 4-5).
3-4 The Fire Protection Manager is-to review previous commitment items for effectiveness and completeness to ensure that the improvement program has been adequately addressed.and implements proposed corrective actions.
This item was accomplished in conjunction with the i
independent assessment described in Item 3-1.
Status:
This item was previously reported as having been. completed.
3-5 Perform a plant-walkdown procedure to update the FRA.
Status: This item was previously reported as having been completed.
3-6 Evaluate the necessity of field verification of the FHA and establish methods, as appropriate, before issucnce of the FHA.
Status:
This item was completed in conjunction with the previou: item (Item 3-5).
The plant walkdown. described ~1n Item 3-5 was used
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to update the FRA.
This method will also be used to maintain the FHA current.
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3-7 Isnue a design package for Project Control No..(PCN) 607, " Revise the Fire-Protection System."
Status: This item was previously rescheduled to Phase IV (refer to Item 4-4).
3-8 Complete an evaluation of the mechanica1'and electrical fire-barrier penetration seals in accordance with the guidelines in'Information Notice No. 88-04.
Status:
Plant walkdowns of penetration seals to gather information for evaluation have been completed. The evaluations associated with the walkdowns and the resulting upgraded combustible loading calculations have also been completed.
3-9 Ensure that the SQN fire protection design and site-specific implementation instruction (for design) adequately reflect design criteria and general engineering specificaticas issued from corporate Nuclear Engineering.
Status:
This item was previously reported as having been completed.
3-10 Upgrade the preventive maintenance (FM) program for the fire protection hardware in System No. 39, "CO-2 Storage, Fire Protection and Purging System."
Status: The reliability-centered maintenance study on System 39 was previously reported as having been completed. The.
I recommendations resulting from the study have been incorporated into the PM program.
Ehase_1V_._ Targeted _ Completion Dale _Decemhgr 1. 1994 4-1 Perform an independent fire protection assessment to assess that actions taken in Phase III are properly implemented and effective.
Status:
This item will be initiated by the corporate Fire Protection Services group with a scheduled completion date of t
December 24, 1993.
4-2 This item was previously rescheduled and is now included as part of Phase III as Item 3-8.
4-3 1ssue the remaining updated design documentation to cupport final compilation into the SQN Fire Protection Report and establish a process to maintain documentation current.
t Status:
Current desig, control processes are considered adequate to maintain the documentation current.
Preliminary work has i
begun on this item. This item is scheduled for completion by December 1, 1994.
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- 4; 4-4 lasue a design package for PCN 607.
Status: The design for this item is approximately 15 percent complete.
Initial flow calculations have been performed, piping routes have been determined, pump and tank 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 schedule and funding levels for this effort have been evaluated, and the completion date for the design change package associated with this change has been extended to fiscal year 1994.
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, consideration will be given to components that may be near their design life limit.
It is not anticipated that any components will require replacement.
This item was originally scheduled to be completed in Phase III as Item 3-3.
However, after closer examination, it has been determined that the item can be accomplished easier and with less repetitive analysis if it is performed in conjunction with the PCN 607 activity (Item 4-4).
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