ML18031B305
| ML18031B305 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/01/1987 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| IEB-85-003, IEB-85-3, NUDOCS 8705050261 | |
| Download: ML18031B305 (7) | |
Text
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50- 260 50-296 AUTH. NhNF 0RIDLFY> R.
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DOCS,ET 5
05000259 05000260 05000296 BUBJECT:
Forwards supplemental v esponse
+o IE Bulletin 85-003>
"Notor-Operated Va) ve Common l>ode Failures Duv ivig P lan+
Transients Due to Impropev Switch Settings.
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TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 3740t 5N 157 Lookout Place MAY OI 1II7 U.S. Nuclear Regulatory Commission ATTN:
Document, Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of Tennessee Valley Authority Docket Nos.
50-259 50-260 50-296
'BROWNS FERRY NUCLEAR'PLANT (BFN) SUPPLEMENTAL RESPONSE TO IE BULLETIN 85-03 MOTOR-OPERATED VALVE COMMON MODE FAILURES DURING PLANT TRANSIENTS DUE TO IMPROPER SWITCH SETTINGS Interim and supplemental responses to IE Bulletin 85-03 were provided by TVA in letters dated May 13, 1986 and September 30, 1986, for BFN.
Enclosure 1
contains a revised response to the bulletin reflecting the completion of action item b and changes to the implementation schedule for action itaws c, d,
and f.
The extensions to the commitment schedule are necessary because of scheduling of environmental qualification modifications and other scheduled maintenance activities, required before restart which will affect motor-operated. valves.
Enclosure 2 provides an updated list of commitment milestones for the completion of the remaining items of the bulletin.
Please refer any questions or comments to G.
W. Morris, BFN Site Licensing, (205) 729-3583.
Very truly yours, TENNESSEE VALLEY AUTHORITY R.
idley, Di ector Nuc ear Safety and Licensing Enclosures cc:
See page 2
8705050261 870501 PDR ADOCK 05000259 8
PDR An Equal Opportunity Employer
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I P
U.S. Regulatory Commission cc (Enclosures):
Mr. G. G. Zech, Assistant Director Regional.Inspections Division of TVA Projects Office of Special Projects U.S. Nuclear Regulatory Commission Region,I1'01 Marietta St.,
NW, Suite 2900 Atlanta, Georgia
'30323 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant P.O.
Box 311
- Athens, Alabama 35611
ENCLOSURE 1
BROWNS FERRY NUCLEAR PLANT (BFN)
RESPONSE
TO IE BULLETIN 85-03 Item a Review and document the design basis for the operation of each valve.
This documentation should include the maximum differential pressure expected during both opening and closing the valve for both normal and abnormal events to the extent that these valve operations and events are included in the existing approved design basis, (i.e., the design basis documented in pertinent licensee submittals such as FSAR analyses and fully approved operating and emergency procedures, etc.).
When determining the maximum differential
- pressure, those single equipment failures and inadvertent equipment operations (such as inadvertent valve closures or openings) that are within the plant design basis should be assumed.
This item is complete.
Item b Using the results from item a above, establish the correct switch settings.
This shall include a program to review and revise, as necessary, the methods for selecting and setting all switches (i.e., torque, torque bypass, position limit, overload) for each valve operat'on (opening and closing).
This item is complete.
Res onse U date for Item c d
and f The revised schedule for completion of items c, d, and f for units 1, 2, and 3
is provided in enclosure 2.
Items 3 and 5 of the schedule are being extended from April 15,
- 1987, and September 3,
1987, respectively, to reference the startup milestone for each unit.
This is being done in order to schedule the items after completion of environmental qualification modifications and other maintenance activities affecting motor-operated valves.
Item 4 is extended from the previous commitment date of June 4, 1987, to coincide with the respective unit's startup in order to perform dynamic differential pressure testing using nuclear steam on five of the subject valves.
The BFN units will not be operating during a majority of the extended timeframe, and therefore, there is no adverse impact, on nuclear safety.
ENCLOSURE 2
BROWNS FERRY NUCLEAR PLANT (BFN)
REVISED COMMITMENT LISTING FOR IE BULLETIN 85-03 1.
Provide the remaining information for item a as requested in the bulletin by October 1, 1986.
(Complete) 2.
BFN will review and establish the correct valve switch settings by February 15, 1987.
(Complete) 3.
BFN will implement any required switch settings by the respective unit startup.
4.
BFN will perform differential pressure testing to verify the established switch settings are correct or provide justification of the acceptability of those which cannot be tested within 30 days of achieving rated pressure on nuclear steam for the respective unit.
5.
BFN will implement any required procedures and/or procedure revisions necessary to ensure the correct switch settings can be maintained throughout the life of the plant by unit 2 startup.
6.
Provide a written report in accordance with item f of the bulletin 60 days after completion of the program for each respective unit.