ML071700760

Request for Additional Information Regarding Steam Generator Tube Inspections Conducted During 2006 Refueling Outage, Salem Nuclear Generating Station, Unit No. 2 TAC MD4807)

ML071700760
Person / Time
Site:	Salem
Issue date:	07/10/2007
From:	Richard Ennis NRC/NRR/ADRO/DORL/LPLI-2
To:	Levis W Public Service Enterprise Group
Ennis R, NRR/DORL, 415-1420
References
TAC MD4807
Download: ML071700760 (6)

Text

July 10, 2007 Mr. William Levis President & Chief Nuclear Officer PSEG Nuclear LLC - N09 Post Office Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING STEAM GENERATOR TUBE INSPECTIONS CONDUCTED DURING 2006 REFUELING OUTAGE, SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 (TAC NO. MD4807)

Dear Mr. Levis:

By letters dated November 6, 2006, and March 1, 2007, (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML063190294 and ML070720424 respectively), PSEG Nuclear LLC submitted reports to the Nuclear Regulatory Commission (NRC) describing the results of the steam generator (SG) tube inspections conducted during the fall 2006 refueling outage (refueling outage 2R15) at Salem Nuclear Generating Station, Unit No. 2. Additional information concerning the SG tube inspections performed during refueling outage 2R15 was summarized by the NRC staff in a letter dated May 10, 2007 (ADAMS Accession No. ML071310308).

The NRC staff is reviewing your submittals and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information. We request that the additional information be provided within 30 days of the date of this letter. The response timeframe was discussed with Mr. Enrique Villar of your staff on July 3, 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:

As stated cc w/encl: See next page

ML071310308).

The NRC staff is reviewing your submittals and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information. We request that the additional information be provided within 30 days of the date of this letter. The response timeframe was discussed with Mr. Enrique Villar of your staff on July 3, 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:

As stated cc w/encl: See next page DISTRIBUTION:

PUBLIC RidsAcrsAcnwMailCenter LPL1-2 Reading RidsRgn1MailCenter RidsNrrDorlLpl1-2 RidsNrrDorlDpr RidsNrrLASLittle AHiser, RidsNrrPMREnnis LMiller RidsOgcRp KKarwoski ADAMS Accession No.: ML071700760 *via memo dated 6/13/07 OFFICE LPL1-2/PM LPL1-1/LA CSGB/BC LPL1-2/BC NAME REnnis SLittle AHiser* HChernoff (JBurkhardt for)

DATE 7/9/07 7/9/07 6/13/07 7/10/07 Salem Nuclear Generating Station, Unit Nos. 1 and 2 cc:

Mr. Thomas Joyce P.O. Box 236 Senior Vice President - Operations Hancocks Bridge, NJ 08038 PSEG Nuclear P.O. Box 236 Township Clerk Hancocks Bridge, NJ 08038 Lower Alloways Creek Township Municipal Building, P.O. Box 157 Mr. Dennis Winchester Hancocks Bridge, NJ 08038 Vice President - Nuclear Assessment PSEG Nuclear Mr. Paul Bauldauf, P.E., Asst. Director P.O. Box 236 Radiation Protection Programs Hancocks Bridge, NJ 08038 NJ Department of Environmental Protection and Energy Mr. Robert Braun CN 415 Site Vice President - Salem Trenton, NJ 08625-0415 PSEG Nuclear P.O. Box 236 Mr. Brian Beam Hancocks Bridge, NJ 08038 Board of Public Utilities 2 Gateway Center, Tenth Floor Mr. Carl Fricker Newark, NJ 07102 Vice President - Operations Support PSEG Nuclear Regional Administrator, Region I P.O. Box 236 U.S. Nuclear Regulatory Commission Hancocks Bridge, NJ 08038 475 Allendale Road King of Prussia, PA 19406 Mr. George Gellrich Plant Manager - Salem Senior Resident Inspector PSEG Nuclear Salem Nuclear Generating Station P.O. Box 236 U.S. Nuclear Regulatory Commission Hancocks Bridge, NJ 08038 Drawer 0509 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

REQUEST FOR ADDITIONAL INFORMATION REGARDING STEAM GENERATOR TUBE INSPECTIONS CONDUCTED DURING THE FALL 2006 REFUELING OUTAGE SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 DOCKET NO. 50-311 By letters dated November 6, 2006, and March 1, 2007, (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML063190294 and ML070720424 respectively), PSEG Nuclear LLC submitted reports to the Nuclear Regulatory Commission (NRC) describing the results of the steam generator (SG) tube inspections conducted during the fall 2006 refueling outage (refueling outage 2R15) at Salem Nuclear Generating Station (Salem), Unit No. 2. Additional information concerning the SG tube inspections performed during refueling outage 2R15 was summarized by the NRC staff in a letter dated May 10, 2007 (ADAMS Accession No. ML071310308).

The NRC staff is reviewing your submittals and has determined that additional information is needed to complete its review. The specific information requested is addressed below.

1. Please discuss whether the growth rates for the indications due to anti-vibration bar wear and cold leg thinning (CLT) are consistent with historical experience. In addition, discuss whether these indications (particularly the CLT indications) satisfy the structural integrity performance criteria.

2. Page 8 of Attachment 1 to your submittal dated March 1, 2007, states that the total postulated accident leakage is estimated to be much less than the total allowable for all SGs (1 gpm [gallon per minute]), and any single SG (0.6 gpm). In your Salem Unit 2 amendment request dated April 6, 2006, related to Technical Specification Task Force (TSTF) traveler TSTF-449, it appears that the only limit cited for accident-induced leakage was 1 gpm for all SGs. Please clarify your accident-induced leakage criteria for all design-basis accidents that are assumed to have primary-to-secondary leakage.

3. The leakage for the WEXTEX region, the top of tubesheet transition region, and from tube plugs was assessed in the letter dated March 1, 2007. Please discuss whether any other indications detected during the outage would have leaked under postulated accident conditions. In addition, discuss the amount of leakage expected from these indications and provide the total accident-induced leakage from all sources.

4. Please provide an assessment of the severity of the single axial indications and the single circumferential indications detected at the tube support plate elevations.

Did these indications satisfy the structural integrity performance criteria?

Enclosure

5. Please discuss whether the inspection data acquired for the permeability variation indications was adequate to determine whether the area may have had a significant flaw. If not, please discuss how tube integrity was assessed at these locations (i.e., in-situ testing).