ML20206K291

Responds to Generic Ltr 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Matls & Impact on Plant Operations. Submittal Dates for Tech Spec Amends & Results of Fracture Toughness Analyses for Plants Stated

ML20206K291
Person / Time
Site:	Peach Bottom, Limerick, 05000000
Issue date:	11/23/1988
From:	Gallagher J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
Shared Package
ML20206K294	List: ML20206K291 ML20206K302 ML20206K310
References
RTR-REGGD-01.099, RTR-REGGD-1.099 GL-88-11, NUDOCS 8811290350
Download: ML20206K291 (3)

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s PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHIL ADELPHI A, PA 19101 (ass) sai soon

oscen w oguonen November 23, 1988 Docket Nos. 50-277 50-278 50-352 50-353 License Nos. OPR-44 DPR-56 NPF-39 Construction Permit No. CPPR-107 Dr. Thomas Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission ATTH

Document Control Desk Washington 0.C.

20555

SUBJECT:

Peacii 8ottom Atomic Power Station Units 2 and 3 Limerick Generating Station Units 1 and 2 Response to Generic Letter 88-11. "NRC Position on Radiation Embrittlement of Reactor Vessel Materials and its Impact on Plant Operations"

REFERENCE:

Letter from J. W. Gallagher (PECo) to T. E. Murley (NRC) dated May 13, 1988 (Docket Nos. 50-277/50-278)

Dear Sir:

This letter is in response to Generic Letter 88-11, dated July 12, 1988. The Generic letter stated that the NRC will use the methodology in Revision 2 of Regulatory Guide 1.99 ("Radiation Embrittlement of Reactor Vessel Materials") to review submittals regarding pressure-temperature (P-T) limits and for analyses other than pressurized thermal shock (PTS) that require an estimate of the embrittlement of reactor vessel beltline materials. Accordingly, Generic Letter 88-11 requested that licensees use the methodology described in Revision 2 to Regulatory Guide 1.99 to predict the effect of neutron radiation on reactor vessel materials as required by paragraph V.A. of 10 CFR Part 50, Appendix G.

The use of the Revision 2 methodology, as compared to the i

previously used Revision 1 methodology, may result in a modification of the pressure.

temperature limits contained in the Technical Specifications in order to continue to satisfy the requirements of Section V of 10 CFR Part 50, Appendix G.

Therefore, the NRC requested in Generic Letter 88-11 that within 180 days of the effective date of Revision 2 Licensees submit the results of their technical analysis and a proposed schedule for whatever act!ons they propose to take.

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' Or. Thomas Hurley, Director November 23, 1988 Page 2 The following is our response to the Generic Letter and a schedule of followup actions:

Peach Bottom Atomic Power Station Unit 2 In the referenced letter, Philadelphia lilectric Company (PECo) forwarded the results of the analysis of the Peach Bottom Unit 2 reactor vessel specimens in accordance with the requirements of 10 CFR 50, Appendix H.

This analysis was performed utilizing Revision 2 to Regulatory Guide 1.99 methodology. The analysis concluded that the adjusted reference temperature (ART) for the limiting beltline material is below the 200gF limit established by 10 CFR 50, Appendix G.

Accordingly, we consider the requests in Generic Letter 88-11 to be satisfied, and the only remaining action necessary is the submittal of the application for amendment to revise the Peach Bottom Unit 2 Technical Specifications. As stated in the referenced letter, an application for amendment to revise the Peach Bottom Unit 2 Technical Specifications to reflect the modification to the pressure-temperature limits will be submitted by January 15, 1989.

Peach Bottom Atomic Power Station Unit 3 General Electric has provided PECo with the results of a fracture toughness analysis of the Peach Bottom Unit 3 reactor pressure vessel utilizing Revision 2 of Regulatory Guide 1.99 methodology (Enclosure 1, "Impact of Regulatory Guide 1.99, Revision 2 on Peach Bottom Atomic Power Station Unit 3").

The pressure-temperature curves currently used in the Peach Bottom Technical Specifications are based on an ART that is now, and through 16 EFPY will be, conservative compared to Revision 2 predicted 0

ART values. Additionally, the Revision 2 ART values at 32 EFPY are below 200 F as allowed by 10 CFR 50, Appendix G.

Accordingly, we consider the requests of this Generic Letter to be satisfied since the Peach Bottom Unit 3 Technical Specifications require the removal of the Unit 3 vassel specimen capsule (between 7 to 9 EFPY) prior to the 3 year time limit specified in the Generic Letter. An analysis will be performed on these specimens in conformance with the requirement. of 10 CFR 50, Appendix H, and submitted to the NRC within one year of the removal of the specimen from the vessel. Any subsequent revisions of the pressure-temperature curves will be based on the analyses of the Unit 3 vessel specimen capsule as required by the Peach Bottom Technical Specifications.

Limerick Generating Station Unit 1 General Electric has provided PEco with the results of a fracture toughness analysis for the Limerick Generating Station Unit I reactor pressure vessel utilizing Revision 2 of Regulatory Guide 1.99 (Enclosure 2. "Impa.ct of Regulatory Guide 1.99, Rcvision 2 on Limerick Generating Statit.i Unit 1").

The current pressure temperature curves are applicable up to 10 EFPY if the ART is calculated according to Revision 2 Therefore,thecurrentcurvesar2conservativeforseveralmoreyegrsof methods.

operation.

Additionally, the Revision 2 ART values at 32 EFPY are below 200 F as alloaed by 10 CFR 50, Appendix G.

The current pressure-temperature curves are identified in the Limerick Generating Station Unit 1 Technical Specifications as being valid for 32 EFPY.

Therefore, ar, amendment to the Technical Specifications will be submitted by December 29, 1989 to specify the revised time period (10 EFPY) for which these curves are valid thus constituting our final response to the requests of Generic Letter 88-11.

' Dr. Thomas Hurley, Director November 23, 1988 Page 3 i

i Limerick Generating Station Unit 2 General Electric will perform a fracture toughness analysis for the Limerick i

i Generating Station Unit 2 (a construction permit holdtr) reactor pressure vessel utilizing Revision 2 of Regulatory Guide 1.99.

This analysis will be submitted to the i

NRC by March 31, 1989. An application for amendment to revise the Limerick Unit 2 i

Technical Specifications will be submitted by December 29, 1989 to reflect any necessary c

changes in the pressure-temperature curves of Limerick Unit 2.

Summary Based on the above discussion, applications for amandments to revise the i

Technical Specifications and/or the results of our analyses utilizing the methodology in Regulatory Guide 1.99, Revision 2 in order to comply with the requests of Generic Letter l

i 88-11 will be submitted as follows:

r Submittal dates for Submittal of the i

Technical Specificat on Results of the l

Pi e r.t Amendments fracture toughness analysis Peach Bottom Un't 2 January 15, 1989 i

i Peach Bottom Unit 3 (As required by 10 CFR 50, i

Appendix 11) f Limerick Generating December 29, 1989 l

Station Unit I Limerick Generating December 29, 1989 April 28, 1989 i

e Station Unit 2 If you have any questions or require additional information, please do not l

l hesitat.e to contact us.

Very truly yours, i

l Attachment i

cc:

Addressee l

W. T. Russell, Administrator, Region I. USNRC T. P. Johnson, USNRC Senior Resident inspector - PB l

T. J. Kenny, USNRC Senior Resident inspector - LGS-1 R. A. Gramm, USNRC Senior Resident Inspector - LGS-2 R. E. Hartin, USNRC Project Manager, PB R. J. Clark, USNRC Project Manager, LGS T. E. Hagette, State of Maryland J. Urban, Delmarva Power J. T Boettger, Public Service Electric & Gas it. C. Schwemm Atlantic Electric i

.