ML072980783
| ML072980783 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/02/2007 |
| From: | Richard Ennis NRC/NRR/ADRO/DORL/LPLI-2 |
| To: | Levis W Public Service Enterprise Group |
| Ennis R, NRR/DORL, 415-1420 | |
| References | |
| S2-I2-RR-B01, S2-I2-RR-C01, TAC MD5977, TAC MD5978 | |
| Download: ML072980783 (6) | |
Text
November 2, 2007 Mr. William Levis President & Chief Nuclear Officer PSEG Nuclear LLC - N09 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUESTS S2-I2-RR-B01 AND S2-I2-RR-C01 (TAC NOS. MD5977 AND MD5978)
Dear Mr. Levis:
By letter dated June 27, 2007, PSEG Nuclear LLC (PSEG) requested relief from certain requirements specified in Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for the inservice inspection (ISI) of Class 1 and Class 2 components at Salem Nuclear Generating Station, Unit No. 2. PSEG stated that it had conducted examinations as part of the second ten-year ISI interval to the extent practical.
However, coverage for certain weld examinations was less than required by the ASME Code.
The Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The RAI questions were previously provided in draft form to PSEG via e-mail on October 4, 2007. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. A conference call between the NRC staff and the PSEG staff was held on October 25, 2007, to discuss the questions.
We request that the additional information be provided by December 14, 2007. The response timeframe was discussed with Mr. Jeff Keenan of your staff on October 25, 2007. If circumstances result in the need to revise your response date, or if you have any questions, please contact me at (301) 415-1420.
Sincerely,
/ra/
Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-311
Enclosure:
Request for Additional Information cc w/encl: See next page
ML072980783 OFFICE LPL1-2/PM LPL 1-2/LA LPL1-2/BC NAME REnnis ABaxter HChernoff DATE 10/30/07 10/30/2007 11/2/2007
Salem Nuclear Generating Station, Unit Nos. 1 and 2 cc:
Mr. Thomas Joyce Senior Vice President - Operations PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Dennis Winchester Vice President - Nuclear Assessment PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Robert Braun Site Vice President - Salem PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Carl Fricker Vice President - Operations Support PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. George Gellrich Plant Manager - Salem PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. James Mallon Manager - Licensing PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Steven Mannon Manager - Salem Regulatory Assurance PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Township Clerk Lower Alloways Creek Township Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Mr. Paul Bauldauf, P.E., Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 Mr. Brian Beam Board of Public Utilities 2 Gateway Center, Tenth Floor Newark, NJ 07102 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Salem Nuclear Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038
REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUESTS S2-I2-RR-B01 AND S2-I2-RR-C01 FOR SECOND TEN-YEAR INSERVICE INSPECTION INTERVAL SALEM NUCLEAR GENERATING STATION, UNIT NO 2 DOCKET NO. 50-311 By letter dated June 27, 2007 (Agencywide Documents Access and Management System Accession No. ML071900437), PSEG Nuclear LLC (PSEG or the licensee) requested relief from certain requirements specified in Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for the inservice inspection (ISI) of Class 1 and Class 2 components at Salem Nuclear Generating Station, Unit No. 2. PSEG stated that it had conducted examinations as part of the second ten-year ISI interval to the extent practical.
However, coverage for certain weld examinations was less than required by the ASME Code.
The Nuclear Regulatory Commission staff, with assistance from Pacific Northwest National Laboratory, is reviewing your submittal and has determined that additional information is needed to complete the review. The specific information requested is addressed below.
General In both Tables 1-1 and 2-1, notes to data in the column labeled ARelief Previously Granted indicate that several of the welds have previously been granted relief based on one of the following stated references:
(a) Evaluation of the Second Ten-Year Interval Inspection Program Plan and Associated Requests for Relief for Salem Generating Station, Unit 2 (TAC No. M83316), dated October 23, 1995 (b) Inservice Inspection - Long Term Plan, Final Relief Requests - First Interval, Salem Generating Station, Unit No. 2, Docket No. 50-311, dated September 28, 1992
- 1. It is unclear which of the stated references are applicable to which of the welds shown in these table columns. Clearly state which reference applies to each specific weld. Also, state why the final relief requests for the first interval in reference (b) above are relevant to the second ten-year interval.
- 2. Clearly state which welds are intended to be a part of current relief requests S2-I2-RR-B01 and S2-I2-RR-C01. Explain why additional relief is needed for those welds which have previously been evaluated for the second ten-year ISI interval (reference (a) above).
Enclosure Relief Request S2-I2-RR-B01
- 3. For reactor pressure vessel (RPV) welds 2-RPV-1443 A, C, and D; 2-RPV-1446 A through F; and, 2-RPV-3442 A through C, the sketches submitted by PSEG are not sufficient to demonstrate impracticality and do not support the written description of the limitations.
Please submit information in the form of drawings, sketches and/or descriptions to support the determination that the inspection of these welds are limited and impractical.
An example that supports the claim for impracticality is provided by the licensee for weld 2-PZR-CIRC DUH. The sketches provided show the portion of the weld and base material that could not be examined, and indicate the outside geometry which limits scanning. It would also be helpful to describe the size of the inspection tool for the RPV, relative to the space available for inspection.
Relief Request S2-I2-RR-C01
- 4. For weld 12-RH-2252-2, the actual nondestructive examination (NDE) data sheet indicates that there was no limitation for the subject surface examination. However, Table 2-1 indicates that only 71% of the subject ASME surface area could be examined. Please explain this discrepancy and re-state the actual surface coverage obtained.