ML18031A624
| ML18031A624 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 07/30/1986 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | Muller D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.C.6, TASK-TM IEB-79-08, IEB-79-8, NUDOCS 8608050094 | |
| Download: ML18031A624 (8) | |
Text
ACCESSION NBR FAC IL: 50-259 50-260 50-296 AUTH. NAI"fE CRI DLEY> R.
REC IP. NAf'fE f'fULLER,D. R:
REQULPINFORNATIGN DISTR IBUTI TEl'1 (R IDS) 8608050094 DOC. DATE: 86/07/30 NOTARIZED:
NG Browns Fev rg Nuc leav Power Stations Unit i. Tennessee Bl owns Fel 1 g Nuc1eav'ower Stations Unit 2i Tennessee Browns Fev'vie Nucleav'ower Station.
Unit 3i Tennessee AUTHOR AFFILIATION Tennessee Valley Authority RECIPIENT AFFILIATION BMR Pv object Div ectorate 2
DOCKET e 05000259 05000260 05000296
SUBJECT:
Fov wards revised v.esponses to IE Bulletin 79-08'tem 6 re safety-related valve positions i~ NUREQ-0737. Item I. C. 6 on cv itical sgsi stv uctures 5 component (CSSC) alignment. Revs v eflect util policy v e CSSC status contv ol.
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~y TENNESSEE VALLEYAUTHORITY CHATTANOOGA, TENNESSEE $7401 5N 157B Lookout Place JUL ~0 686 Director of Nuclear Reactor Regulation Attention:
Mr. D. R. Muller, Project Director BWR Project Directorate No.
2 Division of Boiling Water Reactor Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Muller:
In the Matter of the Tennessee Valley Authority Docket Nos
~
50-259 50-260 50-296 By letter from L. M. Mills to H. R. Denton dated April 13,
- 1982, TVA provided clarification of response to item No.
6 of IE Bulletin 79-08, and a revised response to NUREG-0737, item I.C.6 for the Browns Ferry Nuclear Plant.
Enclosed are revised responses to item 6 and the clarification previously provided.
These revisions are needed to properly reflect our policy regarding critical systems, structures and component (CSSC) status control.
The revisions reflect the use of a caution tag now being used in lieu of an "abnormal status" form used previously. It also reflects performance of a review of panel checklists each shift, in lieu of weekly as done previously.
Revisions to the responses are denoted by a vertical change bar in the right hand margin.
If you have any questions, please get in touch with M. J.
May through the BFN Project Manager.
Very truly yours, TENNESSEE V LLEY AUTHORITY Enclosure cc (Enclosure):
Mr. R. J. Clark U.S. Nuclear Regulatory Commission Browns Ferry Project Manager 7920 Norfolk Avenue
- Bethesda, Maryland 20814 R. Gridley, irector Nuclear Safety and Licensing U.S. Nuclear Regulatory Commission Region II ATTN:
Dr. J.
Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 8608050094 860730 PDR ADGCK 05000259
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8 PDR an Equal Opportunity Employer
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~l ENCLOSURE
~y ITEM 6 OP BULLETIN 79-08 (BROWNS FERRY NUCLEAR PLANT) 6.
Review all safety-related valve positions, positioning requirements, and positive controls to ensure that valves remain positioned (open or closed) in a manner to ensure the proper operat,ion of engineered safety features.
Also, review related procedures such as those for maintenance,
- testing, plant and system startup, and supervisory periodic (e.g., daily/shift checks) surveillance to ensure that such valves are returned to their correct positions following necessary manipulations and are maintained in their positions during all operational modes.
Revised Res onse to Item 6 Plant administrative procedures require that (a) all Critical Systems, Structures and Component (CSSC) alignment is verified before unit startup, (b) changes in the alignment of any CSSC that is required to be operational are documented and controlled using the plant equipment clearance procedure or other plant procedures, (c) shift employees being relieved communicate information on any abnormal plant conditions including temporary conditions.
Plant operating instructions require completion of a prestartup checklist before system startup to standby readiness.
This checklist is used to verify correct alignment of all safety systems.
Any time a component is changed from its normal position or condition, if required to be operational, and the system is rot being controlled using an approved plant procedure, a caution tag will be issued to fully describe the nature of the abnormal alignment.
When removed from service and operability is not required, the status of all safety-related systems (CSSC) will be maintained or a complete valve checklist will be verified and required surveillance checks run before returning to operable status.
In addi.tion, panel checklists are reviewed each shift to verify that flow paths exist for all safety systems.
A safety system status display panel is located in the main control room.
The purpose of this panel is to display a specific plant parameter selected by the unit operator.
Return of a system or system component to its normal mode or position following maintenance or testing is addressed in the response to question 8.
REVISED RESPONSE TO RE VEST FOR CLARIFICATION OF ITEM 6 OF BULLETIN 79-08 Item No.
6
- l. It is not clear from your response that safety-related valve positioning requirements were reviewed to ensure proper operation of engineered safety features.
Please supplement your response to provide a commitment to conduct this review and a schedule for completion.
2.
Please augment your response to indicate the extent to which position and locking device checks are performed for locked safety system valves.
3.
Your response did not clearly indicate that all accessible safety-related'alves had been inspected to verify proper position nor was a schedule for performing the position verification for all safety-related valves provided.
Please supplement your response to provide this information.
Revised Res onse to Item No.
6 Clarification 1.
Safety-related valve position requirements have been reviewed to ensure proper operation. of engineered safety features.
This review has been completed.
2.
CSSC valve position requirements are listed and documented in the operating instruction valve checklist for each individual system.
The complete system valve checklist is performed prior to sy'tem startup in order to initially align the system in a prestartup configuration.
Locked safety valves are included on the checklists during all operational modes when system operability is required.
If the position of any locked valve is to be changed and the system is not being controlled using an approved plant procedure, a caution tag will be issued to fully describe the nature of the abnormal alignment.
When the locked valve is returned to the normal position, the caution tag is removed.
The clearance procedure is periodically audited including physical walkdowns and verification of tags.
In addition, all accessible locked valves are checked annually to ensure proper position and locking device integrity.
3.
Accessible safety-related valves in the main flow path of CSSC equipment have been inspected to verify proper positioning.
This verification is performed by each shift by the unit operator.
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