ML20236Y353
| ML20236Y353 | |
| Person / Time | |
|---|---|
| Issue date: | 05/22/1998 |
| From: | Miraglia F NRC (Affiliation Not Assigned) |
| To: | Martin T Committee To Review Generic Requirements |
| Shared Package | |
| ML20236Y348 | List: |
| References | |
| TAC-MA1226, NUDOCS 9808120122 | |
| Download: ML20236Y353 (1) | |
Text
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MEMORANDUM TO: Thomas T. Martin, Chairman j
Committee to Review Generic Requirements l
FROM:
Frank J. Miraglia, Jr., Deputy Director Office of Nuclear Reacte ; 8egulation
SUBJECT:
WAIVER OF CRF.a REVIEW OF STAFF RESPONSE TO "BWR VESSEL AND INTERNALS PROJECT, INSTRUMENT PENETRATION INSPECTION AND FLAW EVALUATION GUIDELINES (BWRVIP-49)"
The Office of Nuclear Reactor Regulation (NRR) requests that the Committee to Review Generic l
Requirements (CRGR) waive review and endorse the subject proposed response to the Boiling Water Reactor Vessel and Internals Project (BWRVIP) regarding their March 13,1998, submittal "BWR Vessel and Internals Project, Instrument Penetration inspection and Flaw Evaluation Guidelines (BWRVIP-49)." The BWRVIP-49 report proposed guidelines for inspection and I
evaluation procedures to ensure the long term integrity of BWR instrument penetrations.
The NRC staff has reviewed this report and finds it provides adequate guidance which, if followed, should expedite NRC review, thereby minimizing the impact on industry and NRC resources. The use of this guidance by the various BWR licensees is purely voluntary, and does not involve an !rnposition of a new staff position nor any backfit. Therefore, we believe that review by the CRGR is not necessary.
If you agree that CRGR review is not necessary, please indicate by signature on the line below.
Otherwise, we will proceed with the preparation of an appropriate CRGR package.
Attachment:
As stated Approved: CRGR review is not necessary CONTACT: C. E. Carpenter, NRR 415-2169 Distribution:
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OFFICIAL RECORD COPY I
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9008120122 900720 PDR TOPRP EXIEPRI C
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UNITED STATES y
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. tamaa anni August 4, 1998 i
Carl Terry, BWRVIP Chairman Niagara Mohawk Power Company
- Post Office Box 63
- Lycoming, NY 13093
SUBJECT:
SAFETY EVALUATION OF "BWR VESSEL AND INTERNALS PROJECT, INSTRUMENT PENETRATION INSPECTION AND FLAW EVALUATION GUIDELINES (BWRVIP-49)"_ (TAC NO. MA1226)
Dear Mr. Terry,
The NRC staff has completed its review of the Electric Power Research Institute (EPRI) Report TR-108695, "BWR Vessel and Intemals Project, instrument Penetration inspection and Flaw Evaluation Guidelines (BWRVIP-49)," dated March 13,1998. The BWRVIP-49 report proposed
- guidelines for inspection and evaluation procedures to ensure the long term integrity of BWR instrument penetrations.
The NRC staff has reviewed the BWRVIP-49 report and finds, in the enclosed Safety Evaluation (SE), that the guidance of the BWRVIP-49 report is acceptable for inspection of the subject safety-related RPV intemal components, The staff has concluded that licensee implementation of the guidelines in BWRVIP-49 will provide an acceptable level of quality for examination of the safety-related components addressed in the BWRVIP-49 document. The staff requests that each BWR licensee that plans to implement the BWRVIP-49 report so inform the NRC.
Please contact C. E. (Gene) Carpenter, Jr., of my staff at (301) 415-2169 if you have any further questions regarding this subject.
Sin rely, M
Gus C. Lainas, Acting Director Division of Engineering Office of Nuclear Reactor Regulation i
Enclosure:
As stated cc: See next page i
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cc:
George Jones, Executive Chairman Dana Covill, Technical Chairman BWRVlP Assessment Task BWRVIP Assessment Task Pennsylvania Power & Light GPU Nuclear A6-1 1 Upper Pond Road Two North Ninth Street Parsippany, NJ 07054 Allentown, PA 18101 Joe Hagan, Executive Chairman Carl Larsen, Technical Chairman BWRVIP inspection Task BWRVIP inspection Task Entergy Yankee Atomic P. O. Box 756 580 Main Street Waterloo Road Bolton, MA 01740 Port Gibson, MS 39'.50 Paul Bemis, Executive Chairman Vaughn Wagoner, Technical Chairman BWRVIP Integration Task BWRVIP Integration Task Washington Public Power Supply System Carolina Power & Light Company 4
P. O. Box 968 One Hannover Square 9C1 North Power Plant Loop P.O. Box 1551 Richland, WA 99352-0968 Raleigh, NC 27612 Lewis Sumner, Executive Chairman John Wilson, Technical Chairman BWRVIP Mitigation Task BWRVIP Mitigation Task Southern Nuclear Operating Co.
Clinton Power Station, M/C T-31C 40 inverness Center Parkway P.O. Box 678 Birmingham, AL 35201 Clinton, IL 61727 John Blomgren, Executive Chairman Bruce McLeod, Technical Chairman BWRVIP Repair Task -
BWRVIP Repair Task Commonwealth Edison Co.
Southern Nuclear Operating Co.
.1400 Opus Place, Suite 600 Post Office Box 1295 Downers Grove, IL 60515-5701 40 inverness Center Parkway Birmingham, AL 35201 Bill Campbell, BWRVIP Vice Chairman Warren Bilanin, EPRI BWRVIP Carolina Power & Light Integration Manager P. O. Box 1551 Joe Gilman, EPRI BWRVIP Raleigh, NC 27612 Mitigation Manager Ken Wolfe, EPRI BWRVIP l
' Robert Carter, EPRI BWRVIP Repair Manager Assessment Manager-Electric Power Research Institute Greg Selby, EPRI BWRVIP P. O. Box 10412 Inspection Manager 3412 Hillview Ave.
EPRI NDE Center Palo Alto, CA 94303
~ P. O. Box 217097 1300 W. T. Harris Blvd.
Charlotte, NC 28221
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U.S. NUCLEAR REGULATORY COMMISSION I
OFFICE OF NUCLEAR REACTOR REGULATION DIVISION OF ENGINEERING 1
SAFETY EVALUATION OF EPRI TOPICAL REPORT TR-108695 j
- BWR VESSEL AND INTERNALS PROJECT.
INSTRUMENT PENETRATION INSPECTION AND FLAW EVALUATION GUIDELINES (BWRVIP-49)"
1.0 INTRODUCTION
1.1 Backaround By letter dated March 13,1998, the Boiling Water Reactor Vessel and intemals Project (BWRVIP) submitted the Electric Power Research Institute (EPRI) Topical Report TR-108695, "BWR Vessel and intemals Project, Instrument Penetration inspection and Flaw Evaluation Guidelines (Ref.1), for staff review and approval. The BWRVIP intended, in submitting the BWRVIP-49 report, to provide proper inspection and evaluation procedures to ensure the long term integrity of instrument penetrations.
Instrument penetrations, consisting of penetrations, nozzles, and safe ends / extensions in a variety of configurations and materials, are used to allow measurement of reactor water level and maintain the reactor pressure boundary. The materials used are stainless steel, Alloy 600, Alloy 182 or 82, and low alloy steel (nozzles). The size of the instrument lines is under NPS 4 (4-inch pipe size).
1.2 -
Purpose The staff reviewed the BWRVIP-49 report to determine whether its guidance would ensure the long term integr;ty of instrument penetrations.
1.3 Organization of this Report l
Because the BWRVIP-49 report is proprietary, this SE was written so as not to repeat information contained in the report. The staff does not discuss in any detail the provisions of the guidelines nor the parts of the guidelines it finds acceptable.
2.0
SUMMARY
OF TOPICAL REPORT The BWRVIP-49 report addresses the following topics:
Instrument Penetration Assessment: Penetration function and configuration, susceptibility factors, consequences of cracking.
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Inspection and Evaluation Guidelines: Inspection history, inspection guidelines, evaluation guidelines-3.0 STAFF EVALUATION The staff finds the BWRVIP-49 report and its guidance acceptable. The report addressed the degradation mechanisms of potential significance. It discussed the causes of crack initiation and growth, the susceptibility factors of environment, materials, and stress state, and the history of materials performance in this application. It discussed the consequences of failure, the monitoring used to detect failures, and measures prescribed to deal with the consequences.
Ref. 2 covered the safety cons 6quences of failures.
One of the mechanisms which can cause degradation of the instrument penetrations is fatigue.
During the initial design process, the influence of fatigue on the penetrations was considered. In a majority of instances, the penetrations were determined to be exempt from the requirements of a detailed ASME Code Section lil fatigue analysis. In those instances where a fatigue analysis was required, the fatigue usaDe factors were determined to be very low, in addition, operational experience indicates that no unanticipated mechanisms exist which may accelerate degradation due to fatigue. Therefore, no additional guidance has been provided in this area.
4.0 CONCLUSION
S AND RECOMMENDATION 1 The staff finds that the guidance presented should ensure the long term integrity of the instrument penetrations and thus provide an adequate level of quality and safety.
5.0 REFERENCES
1.
Electric Power Research Institute (EPRI) Topical Report TR 108695, 'BWR Vessel and intemals Project, Instrument Penetration inspection and Flaw Evaluation Guidelines, March 13,1998, 2.
Electric Power Research Institute (EPRI) Topical Report TR-105707, "BWR Vessel and intemals Project, " Safety Assessment of BWR Reactor Intemais," October 1995.
3.
NUREG-1557, Summary of Technical Information and Agreements from Nuclear
. Management and Resources Council Industry Reports Addressing License Renewal, October 1996.
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