ML083390757
| ML083390757 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf, Arkansas Nuclear, River Bend, Waterford  |
| Issue date: | 01/28/2009 |
| From: | Kalyanam N Plant Licensing Branch IV |
| To: | Entergy Operations |
| Kalyanam N, NRR/DORL/LPL4, 415-1480 | |
| References | |
| TAC MD8826, TAC MD8827, TAC MD8828, TAC MD8829 | |
| Download: ML083390757 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 28, 2009 Vice President, Operations Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 1, GRAND GULF NUCLEAR STATION, UNIT 1, RIVER BEND STATION, UNIT 1, AND WATERFORD STEAM ELECTRIC STATION, UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION RE: RELIEF REQUEST CEP-ISI-011 FOR THIRD 120-MONTH INSERVICE TESTING INTERVAL (TAC NOS. MD8826, MD8827, MD8828, AND MD8829)
Dear Sir or Madam:
By letter dated May 20, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081620369), Entergy Operations, Inc. (Entergy, the licensee),
submitted an application for a request to utilize, pursuant to paragraph 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations (10 CFR), the alternative requirements in American Society of Mechanical Engineers Boiler and Pressure Vessel Code (Code), Code Case N-747 in lieu of the requirements of Table IWB-2500-1, Examination Category B-A, Item Number B1.40.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the application and determined that additional information is required in order to complete the review. The enclosed request for additional information was discussed with Mr. W. Brice of your staff. Mr. Brice agreed to provide a response within 30 days of the receipt of this letter.
If you have any questions, please contact me at (301) 415-1480.
Sincerely, I
)~.
lL.~~...
N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-313, 50-416, 50-458, and 50-382
Enclosure:
Request for Additional Information cc: w/encl: Distribution via ListServ
REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST FOR ALTERNATIVE CEP-ISI-011 FOR ARKANSAS NUCLEAR ONE, UNIT 1 GRAND GULF NUCLEAR STATION, UNIT 1 RIVER BEND STATION, AND WATERFORD STEAM ELECTRIC STATION, UNIT 3 ENTERGY OPERATIONS, INC.
By letter dated May 20, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081620369), Entergy Operations, Inc. (Entergy, the licensee),
submitted an application for a request to utilize, pursuant to paragraph 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations (10 CFR), the alternative requirements in American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Code Case N-747 in lieu of the requirements of Table IWB-2500-1, Examination Category B-A, Item Number B1.40.
The U.S. Nuclear Regulatory Commission (NRC) staff requests that the licensee provide additional analyses to support the elimination of the ASME Code, Section XI-required volumetric examination for the reactor vessel head-to-f1ange weld. This alternative, as established in Code Case N-747, may be rejected for endorsement by the staff in Regulatory Guide 1.147 for the reasons outlined below:
Alternatives to current inservice inspection (lSI) requirements that use a probabilistic risk assessment as a basis must initially be submitted as a risk-informed lSI program pursuant to 10 CFR 50.55a(a)(3)(i) (Le., on a plant-specific basis and not on a generic basis).
The NRC staff requests that Entergy provide a more quantitative technical basis for the alternative proposed in Code Case N-747. First, no supporting neutron fluence assessment or documentation to establish a conservative neutron fluence estimate for these welds and a conservative reference temperature nil ductility (RTNDT) value for the welds is provided. Thus, there is no data to support a conclusion that the fracture toughness is low. Second, the methods in ASME Code Appendix G to Section XI apply only to pressure-temperature limit methods and not to lSI inspection requirements.
The additional supporting analyses for the alternative proposed in CEP-ISI-011 must address the two technical issues outlined above, specifically:
(1)
Provide a determination (or conservative estimation) of the neutron fluence at the flange location and explain how a sufficiently high plant-specific fracture toughness is assured at the location of interest (Le., show that the toughness of the limiting Waterford 3 material at the plant-specific boltup temperature is consistent with assumptions made in the technical basis).
(2)
Explain how the results of the Appendix G-related analysis directly support the requested lSI program relief.
Enclosure
January 28, 2009 Vice President, Operations Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 1, GRAND GULF NUCLEAR STATION, UNIT 1, RIVER BEND STATION, UNIT 1, AND WATERFORD STEAM ELECTRIC STATION, UI\\IIT 3 - REQUEST FOR ADDITIONAL II\\lFORMATION RE: RELIEF REQUEST CEP-ISI-011 FOR THIRD 120-MONTH INSERVICE TESTING INTERVAL (TAC NOS. MD8826, MD8827, MD8828, AND MD8829)
Dear Sir or Madam:
By letter dated May 20, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML081620369), Entergy Operations, Inc. (Entergy, the licensee),
submitted an application for a request to utilize, pursuant to paragraph 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations (10 CFR), the alternative requirements in American Society of Mechanical Engineers Boiler and Pressure Vessel Code (Code), Code Case N-747 in lieu of the requirements of Table IWB-2500-1, Examination Category B-A, Item Number B1.40.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the application and determined that additional information is required in order to complete the review. The enclosed request for additional information was discussed with Mr. W. Brice of your staff. Mr. Brice agreed to provide a response within 30 days of the receipt of this letter.
If you have any questions, please contact me at (301) 415-1480.
Sincerely, IRA!
N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of I\\luclear Reactor Regulation Docket Nos. 50-313, 50-416, 50-458, and 50-382
Enclosure:
Request for Additional Information cc: w/encl: Distribution via ListServ DISTRIBUTION:
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