ML20046B494
| ML20046B494 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Limerick |
| Issue date: | 07/28/1993 |
| From: | Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, NUDOCS 9308040287 | |
| Download: ML20046B494 (3) | |
Text
.
50.54(f)
PHILADELPHIA ELECTRIC COMPANY NUCLEAR GROUP HEADQUARTERS 955-65 CHESTERBROOK BLVD.
WAYNE, PA 19087-5691 July 28, 1993 Docket Nos. 50-277 50-278-50-352 50-353 STATION SUPPORT DEPARTMENT License Nos. DPR-44 DPR-56 NPF-39 NPF-85 3
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Peach Bottom Atomic Power Station, Units 2 and 3 Limerick Generating Station, Units 1 and 2-Response to Request for Addition'al Information Concerning Generic Letter 92-01, Revision 1,
" Reactor Vessel Structural Integrity, ~ 10 CFR 50.54(f)"
REFERENCES:
- 1) Generic Letter 92-01, Revision 1, " Reactor Vessel 1
Structural Integrity, 50.54(f)," dated March 6,1992-2)
Letter from G. J. Beck (PEco) to U. S. Nuclear Regulatory Commission, dated July 10, 1992 3)
Letter from G. J. Beck (PEco) to D. S. Nuclear Regulatory Commission, dated November 16, 1992
Dear Sir:
Attached is our response to the subject " Request for Additional Information," contained in the letter from J. Shea (NRC) and F. Rinaldi (NRC) to G. Hunger (PECo), dated June 2, 1993.
Our original responses' to Generic Letter 92-01, Supplement 1 (Reference.1), were provided in the Reference 2 and 3 letters. Generic Letter 92-01 concerns licensee's compliance with requirements and commitments regarding reactor vessel integrity.
If you have any questions, please contact us.
Very truly yours, fu A.
Op 10f l
i G. A. Hunger, Jr., Director Licensing Section Tcc:
T. T. Martin, Administrator, Region I, USNRC t
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B. S. Norris, USNRC Senior Resident. Inspector, PBAPS N. S. Perry, USNRC Senior Resident Inspector, LGS 930B040287 930728' t
PDR ADOCK 05000277 P '
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COMMONWEALTH OF PENNSYLVANIA :
ss.
COUNTY OF CHESTER G. R. Rainey, being first duly sworn, deposes and says:
l That he is Vice President of Philadelphia Electric Company; the Applicant l
herein; that he has read the attached response to the " Request for Additional Information," contained in NRC letter dated June 2,1993, for Peach Bottom Atomic Power Station Facility Operating Licenses DPR-44 and DPR-56, and Limerick Generating Station Facility Operating Licenses NPF-39 and NPF-85 and kncws the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.
r V eP siden Subscribed and swo n to before me this-) day of 1993.
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Notary Public 3
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Erica A Sawi.vyaeuc 1
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. ATTACHMENT RESPONSE TO THE JUNE 2, 1993 REQUEST FOR ADDITIONAL 1 JORMATION CONCERNING GENERIC LETTER 92-01, REVISION 1,
" REACTOR VESSEL STRUCTURAL INTEGRITY, 50.54(f)"
RE0 VEST 1:
"1.
In the response to GL 92-01, the licensee referenced a General Electric (GE) report GE-NE-523-18-1191 to predict initial Charpy upper-shelf-energy (USE) of beltline materials from tests performed at a single temperature. The Report GE-NE-523-18-1191 was withdrawn by GE and a topical report, NED0-32205, title "BWR Owners' Group Topical Report on Upper Shelf Energy Equivalent Margin Analysis" regarding beltline materials with low USE, was submitted by General Electric Corporation on April 30, 1993. The licensee must either confirm that this topical report will be used as.its licensing bases or provide its plant specific approach to demonstrate that all' beltline materials that do not have measured USE will' meet requirements of Appendix G, 10 Part CFR 50."
RESPONSE
General Electric Topical Report, NED0-32205, titled "BWR Owners' Group Topical Report on Upper Shelf Energy Equivalent Margin Analyses,"
submitted by the Boiling Water Reactor Owners' Group (BWR0G) Chairperson to the NRC by letter dated April 30, 1993, will be used as the licensing bases for. upper-shelf energy concerns for Limerick Generating Station (LGS), Units 1 and 2, and Peach Bottom Atomic Power Station (PBAPS),
Units 2 and 3.
RE0 VEST 2:
"2.
The response indicates that data from the drop weight test and Charpy test for beltline materials is either absent or incomplete for initial RT,.y determination.. An alternative method. developed by General Electric (GE) was used 'in deriving the initial RT,, for. these materials.
In the GE method, the establishment of the slope for the transition zone of the Charpy curve is crucial in deriving the initial RT,,, from incomplete test data.
Provide all plate and weld Charpy test curves compiled by GE for establishing the 2*F per ft-lb slope for the transition zone of the Charpy curve. All test data must be from materials equivalent to (i.e.
same vendor, fabrication-time frame, fabrication process, material specification, etc.) the beltline materials of this reactor vessel."
RESPONSE
General Electric is preparing a report for the Boiling Water Reactor.
(BWR) Owners' Group which will provide justification for the 2*F per ft-lb slope in the ttansition zone of the Charpy curve. We anticipate that this report will be submitted'to the NRC in the Fall of 1993 by the BWROG. Upon review and acceptance of the document by Philadelphia Electric Company, this report will be our licensing bases for-
)
establishing the initial reference temperature of nil-ductility transition (RT,,) for LGS, Units 1. and 2, and PBAPS, Units 2 and 3.
A status of the review and acceptance of this document will be provided to the NRC by December 1, 1993.
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