JPN-97-035, Informs That Util Has Program to Monitor Fracture Toughness Properties of Ferritic Matls in Beltline Region of Reactor Vessel,As Required by 10CFR50,App H.Rept on Plant Reactor Pressure Vessel Surveillance Matls Testing Encl
| ML20198R781 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/10/1997 |
| From: | Deasy R POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20198R785 | List: |
| References | |
| JPN-97-035, JPN-97-35, NUDOCS 9711130379 | |
| Download: ML20198R781 (5) | |
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. comvw n suaes November 10, 19'37 JPN 97 035 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station F1 137 Washington D.C. 20555
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50 333 REACTOR PRESSURE VESSEL MATERIAL SURVEILLANCE PROGRAM EUMMARY REP _QHLAND IMPLEMENIATLON SCHEDMlf
REFERENCES:
See below.
Dear Sir:
The Authority has a program to monitor the fracture toughness proporties of ferritic materials in the beltline region of the reactor vessel, as required by 10 CFR 50, Appendix H (Reference 1). Under this program, data was obtained from tests of an exposed material sample which was withdrawn from the reactor vessel during the Refuel 12/Lycle 13 (R12/C13) Refueling Outage (RFOI. Reference 1 also requires that a report of the results of these tests be submitted to the NRC within one year of withdrawal of a reactor vessel r,nmple. A report on the FitzPatrick Reactor Pressure Vessel Surveillance Materials Testing and Analysis is contained in Attachment 1. Thc results of this report show that the requirements of 10 CFR 50, Appendix G (Reference 2) are satisfied.
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I The Authority has accepted the attached report with the provision that it be revised and reissued to address several comments and concerns. The Authority's comments and concerns involve the analytical techniques and models used to calculate fluence. The net effect of thcse comments is that the report over estimates.* absolute" reactor vessel j
fluence. Because the operating pressure temperature limit curves are not based on i
- absolute" fluence, the Authority's comments and concerns will not significantly affect i
those curves Pressure temperature limit curves are based on " measured" fluence derived l
from surveillence capsult nea:.utements, j
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in addition, the Authority has a concern regarding how the capsule testing was performed.
The Authority's Quality Assurance Department recently conducted an audit of the General Electric Company. The subject of the audit was reactor vessel surveillance specimen l
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.
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Based on the information currently available, the resolution of these comments and concerns is not expected to significantly alter the overall conclusion of thu report. -The Authority expects that the revised repc.t will demonstrate that the requirements of 10 Cf R 50, Appendix G continue to be satisfied. The Authority will submit a copy of the revised l
test result report, reflectinq the resolution of these comments and concerns, within 120 days. A schedule and technical justification for the withdrawal of the next capsult will also be submitted at that time, t
Applicability of NEDO 32205 A, Revision 1 i
Based on the test results contained in the attached report, the Authority has determined that NEDO 32205 A, Revision 1, February 1994, "10 CFR 50 Appendix G Equivalent j
Margin Analysis for Low Upper Shelf Ene:gy in BWR/2 Through BWR/6 Vessels," is
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applicable to FitzPatrick.
Operating Limit Cu ves Operating limit curves have been established for the following three reactor conditions:
Pressure Test Non nuclear Heatup and Cooldown Core Critical Operation i
4 The curves in Attachment 1 are valid for up to 32 Effective r ull Power Years (EFPY) of operation. The FitzPatrick Technical Specifications (TS) will be revised to reflect the new conditions. The Authority will submit revised TS not later than June 1999. The current TS are still within requirements and can be used until that time.
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Status of ongoing BWR Owner's Group RPV Integrity Program Relative to FitzPatrick The Authority is a member of the BWR Vessel & Internals Project (BWRVIP) and is l
monitoring the activities of this industry group. As requested by the NRC staff, (Reference l
- 3) the Authority will provide the results of the ongoing Owners' Group Reactor Vessel Integrity programs relat ve to FitzPatrick.- The Authority will submit these results not later i
than April-10,1998.
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' is a summary of commitments made in this letter, if you have any questions, please contact Ms. C. Faison.
Very Truly Yours, A'
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Robert J. Dea Vice President Appraisal & Compliance Services Department cc:
Regional Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19400 Office of the Resident inspector U.S. Nuclear Regulatory Cornmission P.O. Box 136 Lycoming, New York 13093 Ms. K. Cotton, Acting Project Manager Project Directorate 11 Division of Reactor Projects I/ll U.S. Nuclear Regulatory Commission Mail Stop 14 D2 Washington, DC 20555 t
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0 References 1.
Code of Federal Regulations, Title 10, Part 50, Appendix H, " Reactor Vessel Material Surveillance Program Requirements," dated December 29,1995 2.
Code of Federcl Regulations, Title 10, Part 50, Apperidix G, " Fracture Toughness Requirements," dated December 29,1995 3.
NRC letter, K. R. Cotton to W. J. Cahill, Jr. regarding closcout for Power Authority of the State of New York (PASNY) response to Generic Letter 92-01, Revision 1, for the James A. FitrPatrick Nuclear Power Plant (TAC No. M92077), dated September 6,1990.
List of Attachments 1.
General Electric Report, Report No. GE-NE-81100732-01, " Plant FitrPatrick RPV Surveillance Materials Testing and Analysis of 120 Degree Capsule at 13.4 EFPY,"
dated September 1997.
2.
Summary of Commitments f-3 1* d i
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t to JPN 97 035 GENERAL ELECTRIC REPORT NO. GE NE 81100732 01 i
FITZPATRICK REACTOR PRESSURE VESSEL SURVEILLANCE MATERIALS TESTING AND ANALYSIS REPORT OF 120 DEGREE CAPSULE AT 13.4 EFPY i
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l New York Power Authority JAMES A, FITZPATRICK NUCLEAR POWER PLANT Docket No. 50 333 DPR 59
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