ML20076M429
| ML20076M429 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/03/1994 |
| From: | Shell R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9411070274 | |
| Download: ML20076M429 (3) | |
Text
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i Tevessa vaney Autnmty. Posi omce sa 2000 soday Da sy Tevenee 37379 l
I November 3, 1994 i
U.S.
Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
l l
In the Matter of
)
Dr;ket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT (SQN) - FIRE PROTECTION IMPROVEMENT PLAN PERIODIC STATUS REPORT A working meeting between TVA and NRC was held at SQN on August 19, 1991, l
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 i
I meeting, TVA agreed to submit periodic status reports to inform NRC of the progress of efforts made in conjunction with the improvement plan.
i The most recent status report identifying progress achieved and areas needing further action is included in the enc 1csure.
The SON commitment date to complete the four phases of the Fire i
Protection Improvement Plan is December 1, 1995.
I If you have any questions concerning this submittal, please telephone l
Steve D.
Gilley at (615) 843-7427.
l Sincerely, 4
I R.
H.
Shell Manager SQN Site Licensing Enclosure cc: See page 2 i
l 070047 l
9411070274 941103 jn l
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a U.S. Nuclear Regulatory' Commission Page 2 November 3,.1994 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 Tgou 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
[~
- m e
o ENCLOSURE FIRE PROTECTION IMPROVEMENT PLAN - STATUS FOR PERIOD ENDING MAY 1, 1994 l
Phase I - Phase I is Complete Phase II - Phase II is Complete Phase III - Phase III is Comolete l
1 Phase IV - Tarceted Completion Date December 1, 1995 1
l 4-1 Perform an independent fire protection asse sment to assess that the actions taken in Phase III are properly implemented and effective.
t Status:
There is one item which involves the enhancement of site procedures to require the involvement of fire protection expertise in the design-review process, which was previously determined to need additional attention. A j
problem evaluation report (SQ940019) was written to provide the needed attention.
This item is complete.
]
4-2 This item was previously rescheduled and completed during Phase III i
(refer to Item 3-8).
4-3 Issue the remaining updated design docamentation to' support the final compilation into the Sequoyah Nuclear Plant (SQN) Fire Protection Report and establish a process to maintain';he documentation current.
Status:
The approach of re-baselining the fire protection commitments for SQN has begun.
Comments from Watts Bar j
Nuclear Plant have been reviewed for applicability to SQN.
Additionally, action plans for.the resolution of major issues such as fire dampers and Thermo-Lag have been developed. The impact on overall compliance was considered when developing these action plans for SQN.
The final resolution of these issues will be taken into account when performing the re-baselining effort and developing the Fire Protection Report.
The Fire Protection Report is expected to be submitted by December 1995.
4-4 Issue a design package for Project Control No. (PCN) 607.
Status:
The design for this item is approximately 65 percent complete, and vendors have been selected for the major components.
It is anticipated that the final design for this project will be complete by June 30, 1995, i
4-5 Perform a life-cycle analysis on high-pressure fire protection j
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.
This item should be considered an integral part of Item 4-4.