ML053420242
| ML053420242 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/11/2006 |
| From: | Stewart Bailey Plant Licensing Branch III-2 |
| To: | Levis W Public Service Enterprise Group |
| Bailey S N | |
| References | |
| TAC MC6041, TAC MC6042 | |
| Download: ML053420242 (11) | |
Text
January 11, 2006 Mr. William Levis Senior Vice President & Chief Nuclear Officer PSEG Nuclear LLC - X04 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, ISSUANCE OF AMENDMENTS RE: DELETION OF REACTOR COOLANT SYSTEM VOLUME (TAC NOS. MC6041 AND MC6042)
Dear Mr. Levis:
The Commission has issued the enclosed Amendment Nos. 269 and 250 to Facility Operating License Nos. DPR-70 and DPR-75 for the Salem Nuclear Generating Station, Unit Nos. 1 and 2, respectively. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated February 15, 2005. These amendments delete the total water and steam volume of the reactor coolant system from TS 5.4.2.
A copy of our Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Stewart N. Bailey, Sr. Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311
Enclosures:
- 1. Amendment No.269 to License No. DPR-70
- 2. Amendment No. 250 to License No. DPR-75
- 3. Safety Evaluation cc w/encls: See next page
January 11, 2006 Mr. William Levis Senior Vice President & Chief Nuclear Officer PSEG Nuclear LLC - X04 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, ISSUANCE OF AMENDMENTS RE: DELETION OF REACTOR COOLANT SYSTEM VOLUME (TAC NOS. MC6041 AND MC6042)
Dear Mr. Levis:
The Commission has issued the enclosed Amendment Nos. 269 and 250 to Facility Operating License Nos. DPR-70 and DPR-75 for the Salem Nuclear Generating Station, Unit Nos. 1 and 2, respectively. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated February 15, 2005. These amendments delete the total water and steam volume of the reactor coolant system from TS 5.4.2.
A copy of our Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Stewart N. Bailey, Sr. Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311
Enclosures:
- 1. Amendment No. 269 to License No. DPR-70
- 2. Amendment No. 250 to License No. DPR-75
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION PUBLIC CHolden MGray, RGN-I KDesai LPL1-2 Reading DRoberts TBoyce GHill(4)
ACRS SBailey CRaynor OGC Accession Number: ML053420242
- by memo OFFICE NRR/LPL1-2/PE NRR/LPL1-2/PM NRR/LPL1-2/LA NRR/SRXB/BC OGC NRR/LPL1-2/BC NAME TValentine: CM SBailey CRaynor (CHowe for)
JNakoski JLongo DRoberts DATE 1/09/2006 1/9/2006 12/29/05 6/3/2005*
1/9/06 1/10/06 OFFICIAL RECORD COPY
Salem Nuclear Generating Station, Unit Nos. 1 and 2 cc:
Mr. Michael Gallagher Vice President - Eng/Tech Support 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. Thomas P. Joyce Site Vice President - Salem PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Darin Benyak Director - Regulatory Assurance PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. George H. Gellrich Plant Support Manager PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038 Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Lower Alloways Creek Township c/o Mary O. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Dr. Jill Lipoti, 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 Mr. Carl J. Fricker Plant Manager PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038
PSEG NUCLEAR, LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 269 License No. DPR-70 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by PSEG Nuclear LLC (PSEG) on behalf of PSEG and Exelon Generation Company, LLC (the licensees) dated February 15, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR), Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 269, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Darrell J. Roberts, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 11, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 269 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Replace the following page of the Appendix A, Technical Specifications, with the attached revised page as indicated. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page Insert Page XVII XVII 5-5 5-5
PSEG NUCLEAR, LLC EXELON GENERATION COMPANY, LLC DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 250 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by PSEG Nuclear LLC (PSEG) on behalf of PSEG and Exelon Generation Company, LLC (the licensees) dated February 15, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR), Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 250, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Darrell J. Roberts, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 11, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 250 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Replace the following page of the Appendix A, Technical Specifications, with the attached revised page as indicated. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Page Insert Page XVII XVII 5-4 5-4
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 269 AND 250 TO FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 PSEG NUCLEAR, LLC EXELON GENERATION COMPANY, LLC SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311
1.0 INTRODUCTION
By letter dated February 15, 2005, PSEG Nuclear, LLC (the licensee) submitted a request for changes to the Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2, Technical Specifications (TSs). The proposed TS change will delete reactor coolant system (RCS) volume (total water and steam volume of the RCS) from TS 5.4.2. The application may be found in the Nuclear Regulatory Commissions (NRC or the Commission) Agencywide Documents Access and Management System (ADAMS) using Accession No. ML050560048.
2.0 REGULATORY EVALUATION
The Commissions requirements related to TS contents are set forth in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, which ensures that the TS specified limiting conditions for operations are consistent with assumed values of the initial conditions in the licensees safety analyses. 10 CFR 50.36(c)(4) governs the contents of TS Section 5.0, Design Features. It states, design features to be included are those features of the facility such as materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety and are not covered in categories described in paragraph (c)(1), (2), and (3) of this section.
3.0 TECHNICAL EVALUATION
Salem TS 5.4.2 lists the approximate total combined RCS volume at a nominal reactor coolant loop average temperature (Tavg) of 573 degrees F. This RCS volume is the RCS hardware volume, not the RCS coolant liquid volume. The updated final safety analysis report (UFSAR),
however, includes values for total RCS volume and RCS component and piping volumes that are more detailed and complete than the approximate RCS volume listed in the current TS 5.4.2. These more detailed values are used as design inputs to the UFSAR Chapter 15 accident analyses, and UFSAR Table 5.1-1 includes both values of the RCS volume (RCS hardware and RCS coolant liquid volume). Therefore, TS 5.4.2 is redundant to the UFSAR.
The original Salem TS were developed prior to the guidance provided in NUREG-1431, Revision 3, Standard Technical Specifications - Westinghouse Plants. NUREG-1431 does not include RCS volume in TS Section 4, Design Features, as this information does not meet the criteria of 10 CFR 50.36(c)(4) for inclusion in the TS.
The proposed TS change to delete RCS volume from TS 5.4.2 would not affect the methods for plant operations or actions to be taken in the event of an accident. Additionally, the licensee is required to evaluate any changes to the RCS volume information contained in the UFSAR in accordance with 10 CFR 50.59 to determine whether prior NRC approval is required.
Therefore, the NRC staff finds this TS change acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the New Jersey State official was notified of the proposed issuance of the amendments. As stated in a letter dated April 20, 2005, the State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (70 FR 15940; March 29, 2005). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: K. Desai Date: January 11, 2006