ML19332D112
| ML19332D112 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/27/1989 |
| From: | Cutter A CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS-89-312, TAC-73271, NUDOCS 8911300029 | |
| Download: ML19332D112 (3) | |
Text
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m coronna Power a usht company
- P.O. Box 1651 + Raleigh. N C. 27602 Mh -
- NOV 2 71989--
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SERIAL: NLS 89-312
' A. B CUTTER P
. Vice President 10CFR50, Appendix'J Nuclear Services Department United States Nuclear Regulatory Commission k<,
- ATTENTION:' Document Control Desk Washington, DC.20555 y
. BRUNSWICK' STEAM ELECTRIC PLANT, UNIT NO. 2.
E DOCKET NO~ 50-324/ LICENSE NO.: DPR 62 t
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- RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION y,
ILRT TESTING-FREQUENCY i
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NRC TAC NO. 73271 Gentlemen:-
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1This letter provides responses to two questions concerning CP6L's May 23,.
1989, 10 CFR:50, Appendix J exemption request regarding Type A testing
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frequencyrfor, Brunswick-2. These-questions were provided, via telecopy, by lthe.-NRC Project: Manager for the Brunswick Plant on November 8,1989.
Ouestfon't 4
Are the inboard'feedwater check valves the only valves that.had a
. history'of repeated. failures?
Response
In addition to the two inboard'feedwater check. valves, ten valves have.
1 experienced repetitive LLRT failures. Attachment 1 provides a list of these
'l
. valves. This list was compiled as a result of an engineering evaluation
~~ completed in April 1988..A valve was considered to have experienced r.epetitive LLRT failures if it failed the' LLRT performed during the 1988
' Brunswick-2 outage and either or both of the LLRTs performed'during the Brunswick 2 1986 and 1984 refueling outages. Carolina Power & Light Company believesfthat the Local Leak Rate Testing Program is' effective in identifying and correcting valve problems. The LLRT results demonstrate the Company's
. aggressive approach to maintaining a high degree of containn.ent integrity.
Ouestion 2 i
i Has the Company officially committed to replace these valves (i.e. the inboard feedwater check valves)? If so, on what schedule?
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Response
The Company is committed lto a resolution of the problems with the 2-B21-F010A and B inboard feedwater check valves.
Indications are that the problems experienced by the 2 B21-F010A and B valves may have multiple contributors.
In addition to' valve design, -one of the possible contributors may be the h
location of the valve with respect to system piping' geometry. A solution tn E
this type'of problem would be relocation of the existing valve positions to a
-I location providing-a straight piping run on the downstream side of the valve.
'l Engineering investigations including flow modeling are-necessary in order to quantify this as a root cause.
If the piping re-configuration is pursued, NRC L
- approval of the design may be requested since it could represent an alternative method for compliance'with 10 CFR 50, Appendix A, General Design Criteria 55 in accordance with the guidance provided in Standard Review Plan
. 6.2.4.
The Company plans to complete the required modifications during the next Brunswick-2 refueling outage and the 1992 Brunswick 1 refueling outage if this option is pursued.
Another option being considered is to replace-the existing inboard feedwater check valves with new check valves with no piping configuration changes.
If this option is pursued the Company plans to complete the replacement during' t
the next Brunswick-2 refueling outage and the upcoming 1990 Brunswick-1 refueling outage. The Brunswick-1 replacement schedule is contingent on the ability to obtain replacement valves and to complete engineering design in sufficient time to support the current outage schedule.
If procurement and i
engineering cannot be' completed, the Brunswick-1 valve replacement will be i
accomplished during the 1992 refueling outage. The Company is in the process of determining which is the preferable option to pursue.
l Please refer any questions regarding this submittal to Mr. M. R. Oates at (919).546 6063.
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Yours very truly,-
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(gy A. B. Cutter ABC/ MAT Enclosure cc:
Mr. S. D. Ebneter Mr. W. H. Ruland Mr. E. G. Tourigny 4
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.-: ATI'ACHMENT I J" '#
VALVES WHICH HAVE EXPERIENCED REPETATIVE LLRT FAILURES y g:
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1989 LLRT
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Valve Number.'
Description Result
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2 B21-F028D Main Steam Isolation Valve Failed-
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~2 E51 F007
.RCIC Steam Supply Inboard Replacing 'this 6
' Isolation Valve
-outage 2-E51-F040 RCIC-Turbine Exhaust No longer in Check Valve program 2-E52-F062 RCIC Turbine Exhaust Failed Vacuum Breaker 2 B32-F032B Feedwater Injection Failed
[
Isolation Valve 2-B21-F019 JCIV'on a'line which is Replacing this I
used for draining various outage leakage points to the condenser.
2 C41 F007 SLC Injection Check Valve Passed ik 12-CAC-V9' Inboard Drywell Purge Passed
. Exhaust Valve
-1
=r~ CAC-V16' Suppression. Pool Vacuum.
Passed Breaker Isolation Valves 2-CAC-Vl?
Suppression Pool Vacuum Passed Breaker Isolation Valves-Those valves which have failed their 1989 LLRT are being repaired prior to startup of Brunswick-2, t
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