ML20199F492
| ML20199F492 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf, Arkansas Nuclear, River Bend, Waterford  |
| Issue date: | 11/19/1997 |
| From: | Wigginton D NRC (Affiliation Not Assigned) |
| To: | Hagan J ENTERGY OPERATIONS, INC. |
| Shared Package | |
| ML20199F499 | List: |
| References | |
| TAC-M95814, TAC-M95815, TAC-M95816, TAC-M95829, TAC-M95830, TAC-M95832, TAC-M95874, TAC-M95875, TAC-M95876, TAC-M960100, TAC-M960101, TAC-M960102, TAC-M960103, TAC-M960104, TAC-M96099, NUDOCS 9711240235 | |
| Download: ML20199F492 (8) | |
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November 19, 1997 Mr. Joseph J. Hagan Vice President, Operations GGNS Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150
SUBJECT:
USE OF ASME CODE CASES N-509, N-524, AND N-546 FOR ARKANSAS NUCLEAR ONE, UNITS 1 AND 2, GRAND GULF NUCLEAR STATION, UNIT 1 RIVER BEND STATION, AND WATERFORD 3 STEAM ELECTRIC STATION (TAC N05.'M96099 7 M96100, M96101, M96102, M96103, M96104, M95814, M95815, M95816, M95829,M95830,M95832,M95874,M95875,ANDM95876)
Dear Mr. Hagan:
By the letters dated June 20, 1996 (3 letters), and January 14, May 12, and July 29, 1997 (GNR0-96/00069 to 72, GNR0-97/00003, 00042, and 00072), you requested relief from the requirements of Section XI, " Rules for Inservice Ins)ection of Nuclear Power Plant Components," of the American Society of Mec1anical Engineers Boiler and Pressure Vessel Code (ASME Code) for the current or new 10-year inservice inspection (ISI) interval in accordance with Paragraph 50.55a(a)(3)(1) of 10 CFR Part 50 for the following plants:
l Arkansas Nuclear One, Units 1 and 2, Grand Gulf Nuclear Station, Unit 1, River Bend Station, and Waterford 3 Steam Electric Station. The current and new 10-year ISI interval for each plant is listed in the enclosed Safety Evaluation, j
i In the letters of June 20, 1996, you requested approval of the use of ASME Code Cases N-s08-1, N-509, N-524, and N-546 for the above Entergy plants.
The letters of January 14, May 12, and July 29, 1997, provided additional information needed by the staff on these code cases.
In the letters of October 7,1996 (for Grand Gulf), and July 30, 1997 (for Arkansas Nuclear One, River Bend, and Waterford 3), we approved the use of Code Case N-508-1 for the four Entergy plants.
This letter concerns the use of the remaining code cases for the four Entergy plants. The remaining code cases are the following: N-509, " Alternative Rules for the Selection and Examination of Class 1, 2, and 3 Integrally Welded Attachments"; N-524. " Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping,Section XI, Division 1"; and N-546,
" Alternative Requirements for Qualification of VT-2 Examination Personnel,
/
Section XI, Division 1."
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b 9711240235 971119 i
PDR ADOCK 05000313 G
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Joseph J. Hagan-As required by the regulations, the ISI for ASME Code Class 1, 2, and 3 components at nuclear power plants shall be performed in accordance with Section XI of the ASME Code and applicable addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(1). Or, as stated in 10 CFR 50.55a(a)(3), alternatives to the requirements of paragraph (g) may be used, when authorized by the Commission, if (i) the proposed alternatives would )rovide an acceptable level of quality and safety or (ii) compliance with t1e specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
In the enclosed Safety Evaluation, the staff concludes that your proposed alternative to use ASME Code Cases N-509 and N-524 in lieu of ASME Section XI Code requirements, for either the current or new 10-year ISI interval as described in the Safety Evaluation, is authorized by law, pursuant to 10 CFR 5J.55a(a)(3)(i). This is based on tha determination by the Commission, as stated in the Safety Evaluation, that the use of the two code cases will provide an acceptable level of quality and safety at the four Entergy plants.
For Code Case N-546, at the request of the staff, in the letter of July 29, 1997, you modified your proposed alternative use of the code case at the four Entergy plants, to include the following:
(1) development of procedural guidelines for obtaining consistent, quality VT-2 visual examinations in accordance with ASME Section XI, IWA-2210, (2) documentation and maintainance of records to verify the qualification of persons selected to perform VT-2 visual examinations in accordance with IWA-liOO(k), (3) independent review and evaluation of leakage by persons other than those that performed the VT-2 visual examinations in accordance with IWA-1400(n), (4) VT-2 inspections requiring the oversight of an authorized inspector in accore: ice with IWA-1400(f), (5) VT-2 results evaluated in accordanc wiin IWB/IWC/IWD-300.
and (6) corrective measures in accordance with IWA-3 0.
In the enclosed Safety Evaluation, thn staft concludes that your proposed alternative to use ASME Code Case N-546, as modified above, in lieu of ASME Section XI Code requirements, for either the current or new 10-year ISI interval as described in the Safety Evaluation, is authorized by law, pursuant to 10 CFR 50.55a(a)(3)(1). This is based on the determination by the Commission, as stated in the Safety Evaluation, that the use of code case N-546 will provide an acceptable level of quality and safety at the four Entergy plants.
The use of Code Cases N-509, N-524, and N-546 are authorized for the current or next ISI 10-year interval, as described in the attached Safety Evaluation, until such time as the code case is published in a future revision of Regulatory Guide 1.147. At that time, if you intend to continue to implement
-Joseph J. Hagan these code cases, you should follow all provisions in the above code cases, with the limitations, if any, prescribed in Regulatory Guide 1.147.
Sincerely, David L. Wi ginton, Acting Director Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos:-50-313, 50-368. 50-416, 50-458, and 50-382
Enclosure:
Safety Evaluation cc w/ encl:
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