ML20205M688
| ML20205M688 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/12/1999 |
| From: | Gramm R NRC (Affiliation Not Assigned) |
| To: | Hutchinson C ENTERGY OPERATIONS, INC. |
| Shared Package | |
| ML20205M691 | List: |
| References | |
| TAC-MA1547, NUDOCS 9904160013 | |
| Download: ML20205M688 (3) | |
Text
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t Mr. C. Randy Hutchinson April 12, 1999 Vice President, Operations ANO Entergy Operations, Inc.
1448 S. R. 333 Russel8ville, AR 72801
SUBJECT:
EVALUATION OF SECOND 10-YEAR INSERVICE INSPECTION RELIEF -
. REQUEST 96-005 FOR ARKANSAS NUCLEAR ONE, UNIT 1 (TAC NO. MA1547)
Dear Mr. Hutchinson:
By [[letter::1CAN129703, Requests Relief for RCS Weld Exam,From Requirements of 10CFR50.55(a)(g).Relief Request for 2 Welds Whose Volumes Could Not Be Examined 100%,encl|letter dated December 3,1997]], Entergy Operations, Inc., submitted a request for relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code-required
. volumetric examination coverage of the steam generator E24B inlet nozzle-to-upper head weld and of the steam generator E24B to the reactor coolant pump P32A pipe-to-pipe circumferential weld due to the geometry and the interference by another component.
i The staff, with technical assistance from its contractor, the Idaho National Engineering and Environmental Laboratory (INEEL), has reviewed and evaluated the information in your request.
The staff did not adopt the evaluation and conclusion presented in the Technical Letter Report (TLR) prepared by INEEL in its entirety. Subsequent to the evaluation by the contractor, the staff obtained further clarification on the examination technique for the subject welds. The enclosed safety evaluation incorporates the TLR and discusses its findings. The staff found that the Code requirements are impractical to comply with due to the gaometric configuration of the steam generator E24B nozzle-to-upper head weld and the obstruction of the whip restraint to the pipe-to-pipe weld between the reactor coolant pump P32A and the steam generator j
E248. The staff has further determined that if the Code requirements were to be imposed on the licensee, the components must be redesigned, which would impose a significant burden on the licensee. Therefore, the staff is authorizing relief, pursuant to Title 10 of the _Qosie_qf Federal Reaulations. Section 50.55a(g)(6)(i). The relief granted is authorized by law, will not endanger life, property, or the common defense and security, and is otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Sincerely, -
OltIGINAL SIGNED BY:
Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning Division c' Licensing Project Management j
Offica of Nuclear Reactor Regulation Docket No. 50-313 DISTRIBUTION CNorsworthy (RCN) (SE only) g
Enclosure:
Safety Evaluation Docket File PPatnaik
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- SE incorporated with no substantial changes Ta receive e copy of this document, indicate in'the boa: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy l
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April 12, 1999 Mr. C. Randy Hutchinson Vice President, Operations ANO Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72801
SUBJECT:
EVALUATION OF SECOND 10-YEAR INSERVICE INSPECTION RELIEF REQUEST 96-005 FOR ARKANSAS NUCLEAR ONE, UNIT 1 (TAC NO. MA1547)
Dear Mr. Hutchinson:
By [[letter::1CAN129703, Requests Relief for RCS Weld Exam,From Requirements of 10CFR50.55(a)(g).Relief Request for 2 Welds Whose Volumes Could Not Be Examined 100%,encl|letter dated December 3,1997]], Entergy Operations, Inc., sA tted a request for relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code-required volumetric examination coverage of the steam generator E24B inlet nozzle-to-upper head weld and of the steam generator E24B to the reactor coolant pump P32A pipe-to-pipe circumferential weld due to the geometry and the interference by another component.
The staff, with technical assistance from its contractor, the Idaho National Engineering and Environmental Laboratory (INEEL), has reviewed and evaluated the information in your request.
The staff did not adopt the evaluation and conclusion presented in the Technical Letter Report (TLR) prepared by INEEL in its entirety. Subsequent to the evaluation by the contractor, the staff obtained further clarification on the examination technique for the subject welds. The enclosed safety evaluation incorporates the TLR and discusses its findings. The staff found that the Code requirements are impractical to comply with due to the geometric configuration of the steam generator E248 nozzle-to-upper head weld and the obstruction of the whip restraint to the pipe to-pipe weld between the reactor coolant pump P32A and the steam generator E248. The staff has further determined that if the Code requirements were to be imposed on the licensee, the components must be redesigned, which would impose a significant burden on the licensee. Therefore, the staff is authorizing relief, pursuant to Title 10 of the Code of Federal Reaulations. Section 50.55a(g)(6)(i). The relief granted is authorized by law, wili not endanger life, property, or the common defense and security, and is otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
Sincerely, k
Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-313
Enclosure:
Safety Evaluation cc w/ encl: See next page
l i
Mr. C. Randy Hutchinson Entergy Operations, Inc.
Arkansas Nuclear One, Unit 1 cc:
Executive Vice President Vice President, Operations Support
& Chief Operating Officer Entergy Operations, Inc.
Entergy Operations, Inc.
P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 Jackson, MS 39286-199 Wise, Carter, Child & Caraway Director, Division of Radiation P. O. Box 651 Control and Emergency Management Jackson, MS 39205 Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867
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Winston & Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Manager, Rockville Nuclear Licensing Framatone Technologies 1700 Rockville Pike, Suite 525 Rockville, MD 20852 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope County Courthouse Russellville, AR 72801 1
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