ML19332F176
| ML19332F176 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 12/05/1989 |
| From: | Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-REGGD-01.168, RTR-REGGD-1.168 NYN-89160, NUDOCS 8912130498 | |
| Download: ML19332F176 (2) | |
Text
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Me'w Hampshire Ted C. l ? ' : dent and Senior Vice Presi Chief Operating Officer NYN-89160 i
December 5, 1989 i
i United States Nuclear Regulatory Commission i
Washington, DC '20555
' Attention:
Document Control Desk I
i
References:
a) Facility Operating License NPF-67 Docket No. 50 443 b) NHY Letter NYN-89140, dated November 6, 1989, 'NHY Power Ascension Test Program. FSAR Chapter 14 Revisions' T. C. Feigenbaum to USNRC i
Subject-Elimination of Main Steam Isolation Valve Closure Test (ST-47)
]
Gentlemen:
New Hampshire Yankee's (NHY) letter dated November 6, 1989, (Reference (b))
delineated revisions to the Power Ascension Test Program as described in Chapter 14 of the Final Safety Analysis Report (FSAR). This letter provides further
. clarifying information regarding the proposed elimination of the Main Steam Isolation Vkive Closure Test (ST-47).
)
The justification provided in Reference (b) for the elimination of ST-47 j;
(restated for clarification purposes) is as follows:
1 (1) FSAR Chapter 15 contains analyses which envelope the
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inadvertent closure of the main steam isolation valves (e.g. Turbine Trip FSAR Sec. 15.2.3)
(2) A unit trip from 1001 power test (ST-38) will be performed.
1 which will demonstrate the effects of a secondary system i
ST-38 does not envelope the Main Steam Isolation Valve Closure Test (ST-47) which NHY has proposed to eliminate.
The performance of ST-38 results in a milder transient than the closure of MSIVs at 100 percent power, in that the main J
steam safety valves are not expected to lift during ST-38, I
given the availability of the Steam Dump System.
(3) Stroke testing of the main steam isolation valves has been performed during hot standby conditions.
(4) The performance of type / qualification tests on similar main steam isolation valves demonstrate that the valves are capable of closing under design flow conditions within the required
- time, 8b n
8912130498 891205 L
PDR ADOCK 05000443 PNV
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p New Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300
- Seabrook, NH 03874 + Telephone (603) 474 9521
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4' United States Nuclear Regulatory Commission December 5, 1989 Attention: Document Control Desk Page 2 Additionally, NHY notes that the FSAR's for several plants which have had their initial test programs evaluated pursuant to USNRC Regulatory Guide 1.68 Revision 2 have taken exception to Appendix A.
Section 5.m.m., which requires a main steam isolation valve closure test at 100 percent power, to demonstrate that the dynamic response of the plant is in accordance with design.
The FSARs for Vogtle, Wolf Creek, and Commanche Peak indicate that a main steam isolation valve closure test will not be performed and that their unit trip from 100 percent power tests would yield similar results, short of opening the main steam p
safety valves.
As indicated in Reference (b) and above, NHY will perform a unit trip from 100 percent power test (ST-38) and has proposed that this test satisfy RG 1.68 Revision 2, Appendix A. Section 5.m.m.
If you have any further questions on this matter please contact Mr. Terry L. Harpster, Director of Licensing Services at extension 2765.
Very truly yours, f)W ds N"
Ted C. Feigenbaum cc Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr. Victor Herses, Project Manager i
Project Directorate I-5 United States Nuclear Regulatory Commission Division of Reactor Projects Washington, DC 20553 Mr. Antone C. Cerne i
NRC Senior Resident Inspector i
P.O. Box 1149 Seabrook, NH 03874 l