ML20112C912
| ML20112C912 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/28/1996 |
| From: | Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9606030187 | |
| Download: ML20112C912 (3) | |
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l St:tian Support Depirtment
-Mik 10 CFR 50.55a I
PECO NUCLEAR nwa c-,
Nuclear Group Headquarters i
A UNir or PECO ENf Rcy 965 Chestertscok Boulevard Wayne, PA 19087-5691 1
i j-May 28,1996 i
Docket Nos. 50-277 50-278 1
License Nos. DPR-44 i
DPR-56 i
i l
U. S. Nuclear Regulatory Commission i
Attn: Document Contri Desk j
Washington, DC 2055b L
Subject Peach Bottom Atomic Power Station, Units 2 and 3 j
Submittal of Revision 1 to Relief Request No. GVRR 1, Second Ten Year Interval of the Inservice Testing (IST) Program
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Reference:
Letter from G.A. Hunger, Jr. (PECO Energy Company) to U. S. Nuclear Regulatory Commission, dated February 15,1996 i
D.ar Sir.-
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Attached for your review and approval is Relief Request No GVRR-1, Revision 1 for the Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 Second Ten Year interval inservice Testing y
L (IST) Program. PECO Energy Company (PECO Energy) requests that this Relief Request be approved by July 19,1996 in order to avoid performing Local Leak Rate Testing currently scheduled to begin in August,1996.
In the Referenced letter coni.iaing Ucense Change Request No. 95-11, PECO Energy Company i
requested changes to the PBAPS, Units 2 and 3 Technical Specifications which would permit the implementation of 10 CFR 50, Appendix J, Option B at PBAPS, Units 2 and 3. This License Change Request contained the justification for changing to a performance-based frequency for leak rate j
testing of Containment Isolation Valves. Using the same justification, PECO Energy requests relief from the testing requirements contained in ASME Section XI,1980 Edition through Winter 1981 Addendum, 2d=d=adhn lWV 3420. This specifies that Containment isolation Valve testing is performed overy 2 years. As an attemative, PECO Energy requests that Category A Containment isolation Valves be tested in accordance ASME/ ANSI OMa-1988, Part 10, " inservice Testing of Valves in Ught-Water Reactor Power Plants," Paragraph 4.2.2, " Valve Seat Leakage Rate Test." This altemative wlN allow PBAPS, Units 2 and 3 to test Category A Containment isolation Valves in accordance with 10 CFR 50, Appendix J, Option B. Additionally, in accordance with 10 CFR 50.55a(b)(2)(vil), leakage rates for Category A Containment Isolation Valves that do not provide a reactor ccolant system pressure isolation function will be analyzed in accordance with paragraph 4.2.2.3(e) of Part 10 and corrective actions will be made in accordance with paragraph 4.2.2.3(f) of Part 10.
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9606030187 960528 PDR ADOCK 05000277 p
PoR
May 28,1996 l
i Page 2 u.
If you have any questions, please contact us.
Very truly yours, 1
1 Yb 1
G. A. Hunger, Jr.
I Director - Uceiwing Enclosure cc:
T. T. Martin, Adrninistrator, Region I, USNRC W. L Schmidt, USNRC Senior Resident inspector, PBAPS
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RELIEF REQUEST GVRR-1, REVISION 1 i
Valves:
Containment isolation Valves (CIVs)
Category:
A Test Requirement: Leak rate test in accordance with ASME Section XI,1980 Edition through Winter 1981 Addenda, Subsubsection IWV-3420.
Basis for Relief:
By rulemaking effective September 8,1992 (Federal Register Vol.
57, 34666), the NRC approved, by incorporation by reference, the 1989 Edition of the ASME Code,Section XI. This edition of the ASME Code requires valve testing to be performed in accordance with the requirements of ASME/ ANSI OMa-1988, Part 10. OM-10 revised the requirements of valve leak rate testing including allowance for testing of CIVs in accordance with 10 CFR 50, Appendix J.
Alternate Testing:
Category A valve leakage testing shall be performed in accordance with ASME/ ANSI OMa-1988, Part 10, " Inservice Testing of Valves in Light-Water Reactor Power Plants," Paragraph 4.2.2, " Valve j
Seat Leakage Rate Test." Additionally, analysis of leakage rates i
shall be in accordance with paragraph 4.2.2.3(e) of Part 10 and corrective actions for these valves will be made in accordance with paragraph 4.2.2.3(f) of Part 10.
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