JPN-98-008, Forwards Rev 1 to Fitzpatick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy. Changes Continue to Meet Requirements of 10CFR50,App G & Do Not Affect Conclusion of Rept

Forwards Rev 1 to Fitzpatick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy. Changes Continue to Meet Requirements of 10CFR50,App G & Do Not Affect Conclusion of Rept

ML20216C218
Person / Time
Site:	FitzPatrick
Issue date:	03/09/1998
From:	James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20216C222	List: B110073, Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy JPN-98-008, Forwards Rev 1 to Fitzpatick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy. Changes Continue to Meet Requirements of 10CFR50,App G & Do Not Affect Conclusion of Rept
References
JPN-98-008, JPN-98-8, NUDOCS 9803130334
Download: ML20216C218 (8)

Text

123 Man Street M Whrte Plans. New York 10301 914 681.6840 914 287.3309 (FAX)

N OE or Vice sdent and g ,4jgg Chief Nuclear Offcer March 9,1998 JPN-98-008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, D.C. 20555

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 REVISED REACTOR PRESSURE VESSEL MATERIAL SURVEILLANCE PROGRAM

SUMMARY

REPORT AND IMPLEMENTATION SCHEDULE I

REFERENCES:

1. NYPA Letter, R. J. Deasy to NRC, " Reactor Pressure Vessel 3 Material Surveillance Program Summary Report and Implementation Schedule," (JPN-97-035), dated November 10,1997

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Dear Sir:

The letter provides a copy of the revised FitzPatrick Reactor Pressure Vessel (RPV) Material Testing and Analysis Report. The changes do not affect the conclusion or technical basis of the report and the requirements of 10 CFR 50 Appendix G continue to be satisfied. A i schedule and technical justification for the next capsule withdrawal is submitted for NRC 4 review and approval. In addition, the Authority is providing the results of the ongoing Owner's Group RPV integrity program relative to FitzPatrick. The Authority committed to provide this information in Reference 1.

ki Attachment 1 describes the Authority's resolution to the Reference 1 Commitments.

Attachment 2 is the revised FitzPatrick RPV Surveillance Materials Testing and Analysis report. Attachment 3 is a summary of the commitments made in this letter.

9803130334 980309 PDR ADOCK0500g3

.W lilEpElit,E!HRH

e If you have, any questions, please contact Ms. C. Faison.

Very Truly Yours, J. K ubel Chief Nuclear Officer and Senior Vice President cc: Regional Administrator

' U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Office of the Resident inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, New York 13093 Mr. J. Williams, Project Manager Project Directorate 1-1 Division of Reactor Projects I/II U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555 1

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i Attachment 1 to JPN-98-008 RESOLUTION OF COMMITMENT NUMBERS JPN-97-035-001 AND JPN-97-035-002 I

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New York Power Authority .

JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 l

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introduction and Background The Authority committed (JPN-97-035, Reference 1) to provide the NRC with a copy of the test result report, revised to reflect the resolution of comments and concerns within 120 days. Included in this response is a description of the Quality Assurance (QA) finding regarding specimen test procedures, and its resolution. A schedule and technical justification for the next capsule withdrawal is also submitted at this time for NRC review and approval. In addition, the Authority is providing the results of the ongoing Owner's Group Reactor Pressure Vessel (RPV) integrity program relative to FitzPatrick.

Resolution of QA Concerns The Authority had a concern regarding how the capsule testing was performed based on the results of an audit conducted on the General Electric (GE) Company by the Authority's OA Department in November 1997. The subject of the audit was reactor vessel surveillance specimen testing for FitzPatrick. As a result of this audit, one finding was identified concerning the availability and use of procedures for conducting charpy impact tests. Specifically, the finding stated the following:

l "The test engineer responsible for the testing of NYPA's (JAF) surveillance capsules charpy specimen stated that testing was performed without a procedure."  !

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~ The Authority performed an audit in February 1998 to address this finding. During this audit, the GE personnel that actually performed the FitzPatrick specimen ti ing were interviewed. The Authority was informed during these interviews that the 1993 version of I the charpy test procedure, valid at the time of testing, was available in a file cabinet in the hot lab test room where the tests were performed. However, the GE personnel did not refer to this procedure during testing. The Authority determined during this audit that the ,

GE personnel performing the testing were familiar with the requirements of the 1993 I

- charpy test procedure and followed these requirements to perform the various tasks necessary to conduct the tests. Each engineer has the requisite education and experience required to qualify them to perform these tests.

At the time the FitzPatrick tests were performed, a draft revision to the charpy test procedure existed. This draft test procedure included a newly purchased 300 ft-Ib charpy test machine in the list of applicable apparatus. This machine was used to test the FitzPatrick surveillance capsule specimens. However, at the time of the test, the 1993 test procedure had neither been amended nor revised to include this test machine in the list of applicable apparatos. Other than the omission of the new test machir.e, there was no substantive difference between the two procedures. The draft revi:, ion to the procedure was approved in October 1997. This version of the charpy test procedure contains the requirements that GE followed during the conduct of the FitzPatrick surveillance capsule charpy specimen test.

L Based on the above, the Authority is satisfied that the t'.ssts were performed properly and I

in accordance with the newly revised charpy test procedure. The test results are therefore valid for use in GE Report No. GE-NE-B1100732-01 Revision 1, " Plant FitzPatrick RPV Surveillance Material Testing and Analysis of 120' Capsule at 13.4 EFPY" (Reference 2).

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, . i Editorial Comments The following two changes were made to GE Report No. GE-NE-B1100732-01 (Reference

3) and are incorporated in Revision 1 (Reference 2) to this report:

1. Page 12, Table 3-3 l l

Weld 1-233 charpy energy values of 74ft-lb,63ft-lb, and 82ft-lb have been corrected and replaced with charpy energy values of 60ft-Ib,64ft-lb, and 56ft-lb.  ;

respectively. The original values were incorrectly taken from a previous report. l Since this weld continued not to be the limiting weld / plate, this correction does not  !

change the results of the original GE report.

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2. Page 17, Section 4.1.1, Third Paragraph, Third Sentence

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I Delete:

"The calculated fluence results for the Fe, Ni, and Cu wires differed by less than I 10%, thus, an average fluence value was used." i i

Replace with:

I "The calculated fluence result from the iron flux wire was used. The Ni and Cu flux I wires confirmed the fluence result from the iron specimen, with all three results differing by less than 10%." I This change has no effect on the results of the original GE report. l Based on the above, the editorial comments and QA concerns did not alter the overall conclusion of the report. The revised report continues to demonstrate that the i requirements of 10 CFR 50, Appendix G are satisfied.

Schedule and Technical Justification for Next Capsule Removal Based on ASTM E185-82 (Reference 4), the third capsule does not need to be withdrawn until end of license (i.e.,2014). The curves contained in the GE report are valid for up to 32 Effective Full Power Years (EFPY) of operation which corresponds to at least the end of license. Vessel fluence is expected to be less than 32 EFPY at that time. The third capsule will be withdrawn at approximately 30 EFPY, This will support operation beyond 32 EFPY, should the operating license be extended. In accordance with 10 CFR 50, Appendix H, Section Ill.B.3, the Authority requests NRC approval of this proposed withdrawal schedule.

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Status of ongoing BWR Owner's Group RPV Integrity Program Relative to FitzPatrick

A revised report, "BWR Vessel and Internals Project Update of Bounding Assessment of l BWR/2-6 Reactor Pressure Vessel Integrity issues (BWRVIP-46)," EPRI, Palo Alto, Ca.,

! December 1997, (EPRI TR-109727) was submitted by EPRI to the NRC. This revised report included data not previously reported and concluded that there is no effect on the Pressure-Temperature (P-T) curves due to chemistry variability for the BWR vessels.

References 1 NYPA Letter, R. J. Deasy to NRC, " Reactor Pressure Vessel Material Surveillance Program Summary Report and implementation Schedule," (JPN-97-035), dated November 10,1997

2. General Electric Company Final Report, " Plant FitzPatrick RPV Surveillance Materials Testing and Analysis of 120 Capsule at 13.4 EFPY," GE-NE-B1100732-01, Revision 1, Class ll, dated February 1998

3. General Electric Company Final Report, " Plant FitzPatrick RPV Surveillance Materials Testing and Analysis of 120 Capsule at 13.4 EFPY," GE-NE-B1100732-01, Class ll, dated October 1997

4. American Society for Testing and Materials, Standard Practice Regarding Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, ASTM E185-82, approved July 1,1982 3

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Attachment 2 to JPN-98-008 GENERAL ELECTRIC REPORT NO. GE-NE-B1100732-01, REVISION 1 FITZPATRICK REACTOR PRESSURE VESSEL SURVEILLANCE MATERIALS TESTING AND ANALYSIS REPORT OF 120 DEGREE CAPSULE AT 13.4 EFPY New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59

se Attachment 3 to JPN 98-008 Summary of Commitments Commitment Number Description Due Date JPN 98-008-01 Withdraw the third capsule. Approximately 30 EFPY t

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