ML20092C123
| ML20092C123 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/05/1995 |
| From: | Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9509120260 | |
| Download: ML20092C123 (6) | |
Text
,
i IUA Tennessee Valley Authonty, Post Office Box 2000 Decatuf. A:abama 35609 September 5, 1995 U.S.
Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket No. 50-296 Tennessee Valley Authority
)
BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 3 - CORRECTIVE ACTION TRACKING DOCUMENT (CATD) RELATED COMMITMENTS TVA's letter to NRC dated January 18, 1995, notified NRC of TVA's intent to take an aggressive approach and complete the corrective actions for Unit 3 CATDs prior to Unit 3 return to service.
Exceptions were to be addressed on a case by case basis with a report to be submitted to the NRC within 90 days prior to restart.
At this time, the corrective actions for ten CATDs are not scheduled to be completed prior to Unit 3 return to service.
The associated CATDs have been closed and the remaining corrective actions for these CATDs are being tracked by the commitment management system.
The enclosure provides information about actions remaining to be completed including the bases for the acceptability of the completion schedule.
There are no commitments contained in this correspondence.
If you have any questions, please contact Pedro Salas at (205) 729-2636.
Sinc alas Manager of Site Licensing cc:
See page 2
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ENCLOSURE l
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (bFN)
UNIT 3 i
CORRECTIVE ACTION TRACKING DOCUMENT (CATD)
CORRECTIVE ACTIONS TO BE COMPLETED AFTER RESTART J
Activities Related to Unresolved Safety Issue (USI) A-46 1.
Evaluation of Seismic Spatial Interactions will be conducted following resolution of USI A-46 utilizing techniques developed by the Seismic Qualification Upgrade Group (SQUG).
(NCO860326222)
Related CATDs 22600-BFN Spatial Interaction 22600-BFN Lighting Fixture Supports 50132-BFN Support Welds Schedule for Completion March 19, 1996 Basis for Not Completina Actions Prior to Unit 3 Restart This action is tied to the overall resolution of USI A-46.
The implementation schedule for the resolution of USI A-46 for Units 2 and 3 is March 19, 1996, as described in the January 19, 1993, TVA letter to NRC, Generic Letter 87-02, Supplemental 120 Day Response, Request for Additional Information.
2.
Perform the seismic plant verification walkdown required by the Generic Implementation Procedure for resolution of USI A-46.
(NCO880208003)
Related CATD 22500-BFN Battery Racks Schedule for Completion March 19, 1996
)
Basis for Not Completina Actions Prior to Unit 3 Restart This act!.on is tied to the overall resolution of USI A-46.
The implementation schedule for the resolution of USI A-46 for Units 2 and 3 is March 19, 1996, as described in the January 19, 1993, TVA letter to NRC, Generic Letter 87-02, Supplemental 120 Day Response, Request for Additional Information.
3.
Safety related flexible conduits not attached to 10 CFR 50.49 equipment will be evaluated as part of the overall resolution of USI A-46.
(NCO890113026)
Related CATDs 19200-NPS Flex Conduit 19201-NPS Flex Conduit Schedule for Completion March 19, 1996 Basis for Not Completina Actions Prior to Unit 3 Restart Issues associated with flexible conduit attached to electrical equipment covered by 10 CFR 50.49 will be resolved prior to restart of Unit 3.
Seismic qualification of other flexible conduit is tied to the overall resolution of USI A-46.
The implementation schedule for the resolution of USI A-46 for Units 2 and 3 is March 19, 1996, as described in the January 19, 1993, TVA letter to NRC, Generic Letter 87-02, Supplemental 120 Day Response, Request for Additional Information.
Personnel Safety Issue Associated With Removal and Reinstallation of Main Steam Relief Valves 4.
Implement the actions associated with the latest approved corrective action plan for CATDs 90700-BFN-01 and 30801-BFN-01. (NCO930185047)
Related CATDs 30801-BFN Personnel Safety - Main Steam Relief Valves 90700-BFN Personnel Safety - Main Steam Relief Valves Schedule for Completion To Be Established E-2
l Basis for Not Completina Actions Prior to Unit 3 Restart These CATDs involve personnel safety issues associated with rigging required for removal and reinstallation of the Main Steam Relief Valves (MSRVs).
There are no nuclear safety issues associated with these CATDs.
The MSRVs can be safely moved using enhanced procedural guidance.
Implementation of the corrective action plan for the listed CATDs involves plant desir-changes which have not been fully developed.
Drawings for Security Lighting 5.
Summary of Actions to be Completed After Restart Implement the actions associated with the latest approved corrective action plan for CATD 31211-BFN-01.
(NCO930185063)
Related CATD 31211-BFN Security Lighting Drawings Schedule for Completion January 5, 1996 Basis for Not Completina Commitment Prior to Unit 3 Restart This CATD involves the adequacy of "as constructed" documentation for security lighting.
Security lighting is being modified as part of the current security upgrade project.
This action is tied to the completion of the current Security System upgrades.
The Security System upgrades are currently scheduled for completion by January 5, 1996 but are not constraints to Unit 3 start-up.
Personnel Safety Issues Associated with Removal and Installation of Main Steam Relief Valves 6.
Summary of Actions to be Completed After Restart Obtain resolution of issues associated with Control Room Emergency Ventilation System (NCO930185001)
Related CATD 20000-BFN Control Room Habitability E-3
Schedule for Completion February 29, 1996 i
Basis for Not Completina Actions Prior to Unit 3 Restart The referenced CATD involves leakage of potentially contaminated outside air from the control building HVAC supply ducts into the control bay pressurization envelope.
The issue of Control Room Emergency Ventilation System (CREVS) compliance with General Design Criteria (GDC) 19 is the subject of current discussions with the NRC staff.
Completion of this action is tied to overall resolution of the CREVS GDC 19 issues.
The resolution of these issues is j
still ongoing with final resolution currently expected by i
February 29, 1996.
Reactor Feed Pump Low Load By-Pass Lines Vibration 7.
Summary of Actions to be Completed After Restart Implement the actions associated with the latest approved corrective action plan (CAP) for CATD 30103-BFN-03.
The reactor feedwater (RFW) pump low load by-pass lines (minimum flow line) may have excessive pipe vibration.
However, this cannot be verified unless an inspection is performed during operation.
The inspection should include a clearance check and thermal movement verification to establish if additional hangers are necessary.
Related CATD 30103-BFN-03 4
Schedule for Comoletion January 3, 1996 Basis for Not Completina Actions Prior to Unit 3 Restart The inspection is required to be performed during operation.
E-4
U.S., Nuclear Regulatory Commission
,Page 2.
l September 5, 1995 l
{
Enclosure:
cc (Enclosure):
Mr. Mark S. Lesser, Acting Branch Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 l
Mr.
J.
F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North i
11555 Rockville Pike Rockville, Maryland 20852 l
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