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October 4, 2004 LICENSEE: PSEG Nuclear, LLC (PSEG)
FACILITY: Salem Nuclear Generating Station, Units 1 and 2
SUBJECT:
SUMMARY
OF SEPTEMBER 9, 2004, PUBLIC MEETING WITH PSEG ON FULL SCOPE ALTERNATIVE SOURCE TERM AMENDMENT APPLICATION On September 9, 2004, members of the NRC staff met with representatives of PSEG, the licensee for the Salem Nuclear Power Station, Unit Nos. 1 and 2 (Salem). The meeting was held at the request of the licensee to allow them to present an overview of their April 26, 2004, amendment request to use an Alternate Source Term (AST).
Steve Mannon of PSEG opened the meeting with a brief explanation of why PSEG is pursuing use of AST for Salem. He stated that two principle reasons are that it will allow them to relax some assumptions regarding auxiliary building ventilation and that it will allow them resume use of their positive displacement pumps for reactor coolant charging.
Jay Arias of PSEG then gave an overview of the technical specification (TS) changes that are being requested. A full discussion of these TS changes can be found in the licensees April 26, 2004, amendment submittal.
Gopal Patel of NUCORE, a consultant for PSEG, provided details about the accident analysis that went in to the AST amendment request. The licensee considered five design basis accidents: Loss of coolant accident (LOCA), steam generator tube rupture (SGTR), main steam line break (MSLB), locked rotor, and control rod ejection.
In the description of their LOCA analysis, the licensee talked about the assumptions they made on original conditions before such a postulated accident. Among these assumptions are a 15%
uprate from current licensed power and an initial power of 105% to allow for instrument error.
The licensee went on to state that their revised analysis of the consequences of a LOCA is based on a 75% spray coverage area as opposed to the 60% coverage area used in the current analysis. When questioned about how they came up with the revised value, the licensee stated that the 60% value was provided to them by the architect engineer as a conservative value. A detailed engineering analysis showed that the actual coverage area is 80.2%; however, the licensee decided to use 75% to allow extra margin.
The licensee stated that they diverged from the guidance of Regulatory Guide (RG) 1.183 in that they assumed that when flashing occurred 10% of the elemental iodine in the sump would become airborne as opposed to 10% of the total iodine in the sump becoming airborne. The licensee maintained that, as long as the sump pH remains above 7.0, the iodine that is bound to other elements in compound form will not become airborne.
The licensee went on to discuss their analysis of post-LOCA atmospheric dispersion of radionuclides. They talked about their assumptions regarding control room air inleakage.
In their presentation on SGTR, the licensee stated that they followed the guidance of RG 1.183 with the exception of how they dealt with the behavior of the steam plume. In dealing with the plume they followed other regulatory guidance.
The licensee was asked why they provided engineering assessments of the decay tank rupture and instrument line break accidents in their amendment request. The licensee stated that these were provided for information and did not involve any design basis change under review.
The licensees final technical presentation was given by Barry Barkley and dealt with sump pH.
The licensee stated that a known phenomenon that can lower sump pH post-LOCA is radiolysis of electrical cables to form hydrochloric acid. The licensee evaluated the amount of such material that could be subject to radiolysis and determined that the sump pH would remain above 7.0.
The licensee then provided an summary of their accident analyses. The most limiting accident in terms of offsite dose is the LOCA. A summary of calculated doses for all five accidents is presented in the licensees handout.
The staff requested the licensee to submit their accident analysis calculations for review. The licensee agreed to submit these analyses on the docket.
A list of those in attendance at the meeting is provided as Enclosure 1. The licensees handout is provided as Enclosure 2.
Please direct any inquiries to Geroge F. Wunder at 301-415-1494, or gfw@nrc.gov.
Sincerely,
/RA/
George F. Wunder, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311
Enclosures:
- 1. List of Attendees
- 2. PSEGs Presentation Slides w/encls: See next page
In their presentation on SGTR, the licensee stated that they followed the guidance of RG 1.183 with the exception of how they dealt with the behavior of the steam plume. In dealing with the plume they followed other regulatory guidance.
The licensee was asked why they provided engineering assessments of the decay tank rupture and instrument line break accidents in their amendment request. The licensee stated that these were provided for information and did not involve any design basis change under review.
The licensees final technical presentation was given by Barry Barkley and dealt with sump pH.
The licensee stated that a known phenomenon that can lower sump pH post-LOCA is radiolysis of electrical cables to form hydrochloric acid. The licensee evaluated the amount of such material that could be subject to radiolysis and determined that the sump pH would remain above 7.0.
The licensee then provided an summary of their accident analyses. The most limiting accident in terms of offsite dose is the LOCA. A summary of calculated doses for all five accidents is presented in the licensees handout.
The staff requested the licensee to submit their accident analysis calculations for review. The licensee agreed to submit these analyses on the docket.
A list of those in attendance at the meeting is provided as Enclosure 1. The licensees handout is provided as Enclosure 2.
Please direct any inquiries to Geroge F. Wunder at 301-415-1494, or gfw@nrc.gov.
Sincerely,
/RA/
George F. Wunder, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311
Enclosures:
- 1. List of Attendees
- 2. PSEGs Presentation Slides w/encls: See next page DISTRIBUTION:
PUBLIC GMiller GMatakas, RI JLee PD1-2 R/F CRaynor JJolicoeur, EDO, RI KParczewski TMarsh/JLyons AMcMurtray OGC RRodriguez CHolden DCollins ACRS NRay Accession Number: ML042670035 Meeting Announcement: ML042320628 Attachment Nos. 2 and 3: ML Package Number: ML042710335 OFFICE PDI-2/PE PD1-2/PM PD1-2/SC(A)
NAME GMiller GWunder DCollins DATE 9/28/04 9/28/04 9/30/04
OFFICIAL RECORD COPY
Salem Nuclear Generating Station, Unit Nos. 1 and 2 cc:
Mr. Michael H. Brothers Dr. Jill Lipoti, Asst. Director Vice President - Site Operations Radiation Protection Programs PSEG Nuclear - X15 NJ Department of Environmental P.O. Box 236 Protection and Energy Hancocks Bridge, NJ 08038 CN 415 Trenton, NJ 08625-0415 Mr. John T. Carlin Vice President - Nuclear Assessments Brian Beam PSEG Nuclear - N10 Board of Public Utilities P.O. Box 236 2 Gateway Center, Tenth Floor Hancocks Bridge, NJ 08038 Newark, NJ 07102 Mr. David F. Garchow Regional Administrator, Region I Vice President - Eng/Tech Support U.S. Nuclear Regulatory Commission PSEG Nuclear - N28 475 Allendale Road P.O. Box 236 King of Prussia, PA 19406 Hancocks Bridge, NJ 08038 Senior Resident Inspector Mr. Steven Mannon Salem Nuclear Generating Station Acting Manager - Licensing U.S. Nuclear Regulatory Commission PSEG Nuclear - N21 Drawer 0509 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Carl J. Fricker Jeffrie J. Keenan, Esquire Plant Manager PSEG Nuclear - N21 PSEG Nuclear - N21 P.O. Box 236 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Ms. R. A. Kankus Joint Owner Affairs PECO Energy Company Nuclear Group Headquarters KSA1-E 200 Exelon Way Kennett Square, PA 19348 Lower Alloways Creek Township c/o Mary O. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038
List of Attendees NRC Meeting with PSEG Nuclear, LLC Full Scope Alternative Source Term Amendment Request Thursday, September, 9, 2004 10:00 A.M. - 5:00 P.M.
Room: O-7-B-4 Name Organization S. Mannon PSEG J. Arias PSEG J. Grant PSEG G. Patel NUCORE B. Barkley PSEG D. Zannoni State of New Jersey D. Collins* NRR R. Rodriguez NRR K. Parczewski NRR J. Lee NRR L. Brown NRR G. Miller NRR G. Wunder NRR NRR Office of Nuclear Reactor Regulation
- Attended part of morning session Enclosure 1
