NRC Generic Letter 1981-04
| ML031210168 | |
| Person / Time | |
|---|---|
| Issue date: | 02/26/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-0313, Rev 1, USI A-42 GL-81-004, NUDOCS 8103170225 | |
| Download: ML031210168 (3) | |
- I REQ I
AUNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555 February 26, 1981 ALL BWR LICENSEES
(EXCEPT HUMBOLDT BAY AND LACROSSE)
RE: IMPLEMENTATION OF NUREG-0313, REV. 1, TECHNICAL REPORT ON MATERIAL
SELECTION AND PROCESSING GUIDELINES FOR BWR COOLANT PRESSURE BOUNDARY
PIPING (GENERIC TASK A-42)
Enclosed for your action is the final NUREG-0313, Rev. 1, Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping,' dated July 1980, which incorporates the public comments on the wFor Commento edition of the same subject report published in October
1979. This final report constitutes the staff's resolution of the NRC's Generic Technical Activity A-42, Pipe Cracks in Boiling Water Reactors,"
which was an mUnresolved Safety Issue' pursuant to Section 210 of the Energy Reorganization Act of 1974.
This report, NUREG-0313, Rev. 1, identifies NRC requirements resulting from the recent publication, NUREG-0531, "Investigation and Evaluation of Stress-Corrosion Cracking in Piping of Light Water Reactor Plants,*
by the NRC Pipe Crack Study Group (PCSG). The Study Group was specifically chartered to reexamine our previous conclusions and recommendations on this subject In view of cracks recently discovered in large diameter pipes, to evaluate the significance of safe end cracking at Duane Arnold relative to similar material and design aspects at other facilities, and to examine detection capabilities.
NIUREG-0313, Rev. 1 sets forth the NRC staff's revised acceptable methods to reduce the intergranular stress corrosion cracking susceptibility of BWR ASME Code Class 1, 2, and 3 pressure boundary piping and safe ends.
For plants that cannot fully comply with the material selection, testing and processing guidelines of this report, varying degrees of augmented inservice inspection and leak detection requirments are presented.
We request that you review all of the ASME Code Class 1 and 2 pressure boundary piping, safe ends, and fitting material, including weld metal, at your facility to determine if it meets the material selection, testing, and processing guidelines set forth in the enclosed report. You should identify to us ayw materials that do not meet these guidelines and propose appropriate changes to your Technical Specifications to incorporate the augmented inservice inspection requirements specified in Section IV of the enclosed report. In the case of 'service sensitive" lines you should also provide your plans and schedule for the replacement, to the extent practicable, of nonconforming materials with those that conform to the staff's guidelines.
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-2- In addition, we request that if it is needed, you propose appropriate changes to your Technical Specifications to bring them into conformance with the enclosed report and the affected portion of the model Technical Specifications denoted with an asterisk in the margin of the text.
You should respond to this letter by July 1, 1981. In your response, you should propose a schedule to accomplish the above requested actions or a description, schedule and justification for alternative actions to accomplish the objectives of this program.
This request for information was approved by GAO under a blanket clearance number R0072 which expires November 30, 1983. Comments on burden and dupli- cation may be directed to the UbS. General Accounting Office, Regulatory Reports Review, Room 5106, 441 G Street, N.W., Washington, D.C. 20548.
The response to this request should reference this letter by title and number.
Sincerely, UarI 1 sen Divison Licensing Enclosures:
1. NUREG-0313, Rev. 1
2. Model Technical Specifications cc: Service Lists, w/o Enclosure 1
-A
I-AS
I- 6 4 t~e,,enCIf 'Ct yd, BOILING WATER REACTOR LICENSEES
Docket No. 50-293 Pilgrim Unit 1
- ( lDocket No. 50-245 Millstone Unit 1 Docket No. 50-325 Docket No. 50-263 Brunswick Unit 1 Monticello Docket No. 50-324 Docket No. 50-133 Brunswick Unit 2 Humboldt Bay Docket No. 50-10 Docket No. 50-277 Dresden 1 Peach Bottom Unit 2 Docket No. 50-237 Docket No. 50-278 Dresden 2 Peach Bottom Unit 3 Docket No. 50-249 Docket No. 50-333 Dresden 3 FitzPatrick Docket No. 50-254 Docket No. 50-259 Quad-Cities Unit 1 Browns Ferry Unit 1 Docket No. 50-265 Docket No. 50-260
Quad-Cities Unit 2 Browns Ferry Unit 2 Docket No. 50-155 Docket No. 50-296 Big Rock Point Browns Ferry Unit 3 Docket No. 50-409 Docket No. 50-271 Lacrosse ro c) Vermont Yankee Docket No. 50-321 Edwin I. Hatch Unit 1 Docket No. 50-366 Edwin I. Hatch Unit 2 Docket No. 50-331 Duane Arrnold Docket No. 50-219 Oyster Creek Docket No. 50-220
Nine Mile Point Unit 1 Docket No. 50-298 Cooper Station e