ML031780101
| ML031780101 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/26/2003 |
| From: | Robert Fretz Office of Nuclear Reactor Regulation |
| To: | Richard Anderson Public Service Enterprise Group |
| Fretz R, NRR/DLPM, 415-1324 | |
| References | |
| TAC MB7541, TAC MB7542 | |
| Download: ML031780101 (12) | |
Text
June 26, 2003 Mr. Roy A. Anderson 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: ADMINISTRATIVE AND EDITORIAL CHANGES TO TECHNICAL SPECIFICATIONS (TAC NOS. MB7541 AND MB7542)
Dear Mr. Anderson:
The Commission has issued the enclosed Amendment Nos. 258 and 239 to Facility Operating License Nos. DPR-70 and DPR-75 for the Salem Nuclear Generating Station, Unit Nos. 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated January 29, 2003.
The amendment for Salem, Unit No. 1, effects administrative corrections to TS Section 3/4.7.6.
Additionally, the proposed amendment for Salem, Unit No. 2, makes administrative changes to TSs 3/4.2.2, 3/4.7.6, and Table 3.3-6.
A copy of our Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice.
Sincerely,
/RA/
Robert J. Fretz, 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. Amendment No. 258 to License No. DPR-70
- 2. Amendment No. 239 to License No. DPR-75
- 3. Safety Evaluation cc w/encls: See next page
ML031780101, TS(s): ML, Package: ML OFFICE PDI-2/PM PDI-2/LA SRXB/SC OGC PDI-2/SC NAME RFretz CRaynor JUhle RWeisman REnnis for JClifford DATE 05/19/03 5/22/03 5/28/03 6/19/2003 6/26/03
PSEG Nuclear LLC Salem Nuclear Generating Station, Unit Nos. 1 and 2 cc:
Mr. Timothy J. OConnor Vice President - Operations PSEG Nuclear - X15 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. John T. Carlin Vice President - Engineering PSEG Nuclear - N10 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. David F. Garchow Vice President - Projects and Licensing PSEG Nuclear - N28 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Gabor Salamon Manager - Nuclear Safety and Licensing PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 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 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 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
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. 258 License No. DPR-70 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by PSEG Nuclear, LLC and Exelon Generation Company, LLC (the licensees), dated January 29, 2003, 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. 258, 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 of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA by REnnis for/
James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 26, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 258 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages as indicated. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages 3/4 7-18 3/4 7-18 3/4 7-19 3/4 7-19
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. 239 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by PSEG Nuclear, LLC and Exelon Generation Company, LLC (the licensees), dated January 29, 2003, 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. 239, 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 of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA by REnnis for/
James W. Clifford, Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 26, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 239 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages as indicated. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages 3/4 2-5 3/4 2-5 3/4 3-39 3/4 3-39 3/4 7-15 3/4 7-15 3/4 7-16 3/4 7-16
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 258 AND 239 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 January 29, 2003, 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 amendment request for Salem, Unit No. 1, proposes administrative corrections to TS Section 3/4.7.6. Additionally, the proposed amendment for Salem, Unit No. 2, would implement administrative changes to TSs 3/4.2.2, 3/4.7.6, and Table 3.3-6.
2.0 REGULATORY EVALUATION
Section 182a of the Atomic Energy Act of 1954, as amended (the Act) requires applicants for nuclear power plant operating licenses to include TSs as a part of the license. The TSs ensure the operational capability of structures, systems and components that are required to protect the health and safety of the public. The U.S. Nuclear Regulatory Commissions (NRC or the Commission) regulatory requirements that are related to the content of the TSs are contained in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36. Section 50.36 of 10 CFR requires that the TSs include items in the following specific categories: (1) safety limits, limiting safety system settings, and limiting control settings (50.36(c)(1)); (2) limiting conditions for operation (LCOs) (50.36(c)(2)); (3) surveillance requirements (SRs) (50.36(c)(3)); (4) design features (50.36(c)(4)); and (5) administrative controls (50.36(c)(5)).
Pursuant to 10 CFR 50.90, a licensee may apply for an amendment to its license, including the TSs incorporated into the license. In determining the acceptability of the proposed changes, the NRC staff interprets the requirements of the current version of 10 CFR 50.36. Within this general framework, licensees may revise their current TSs provided that a plant-specific review supports a finding of continued adequate safety because: (1) the change is editorial, administrative, or produces clarification (i.e., no requirements are materially altered); (2) the change is more restrictive than the licensees current requirement; or (3) the change is less restrictive than the licensees current requirement, but continues to afford adequate assurance of safety when judged against current regulatory standards.
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3.0 TECHNICAL EVALUATION
The staff has reviewed the licensees regulatory and technical analyses in support of its proposed license amendment which are described in Sections 2, 3 and 4 of the PSEGs January 29, 2003, submittal. The detailed evaluation below will support the conclusion 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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
3.1 Salem, Unit No. 1, TS 3/4.7.6 The licensee has proposed to change a reference in Action Statements d (Modes 1, 2, 3, and 4) and e (Modes 5 and 6) of LCO 3.7.6.1. This change would correct a reference, in both statements d and e, from Action 24 of Table 3.3-6 to Action 25. Action Statements d and e apply to situations where one or both of the series isolation dampers on a normal Control Area Air Conditioning System (CAACS) is inoperable. In these situations, both radiation monitors in the affected intake are considered inoperable. Currently, the reference in LCO 3.7.6.1 refers to Action 24 which applies to operation with one intake radiation monitor inoperable. For operation with both intake radiation monitors inoperable, Action 25 is appropriate.
This error was caused by changes to Table 3.3-6 effected by Amendment 225. Prior to this amendment, Action 24 dealt with single and dual intake radiation monitor inoperability. After implementation the single Action was divided into separate Actions 24 (single) and 25 (both).
The two Action Statements of LCO 3.7.6.1 were not updated to reflect this. The proposed changes to Action Statements d (Modes 1, 2, 3, and 4) and e (Modes 5 and 6) are administrative in nature, and are, therefore, acceptable.
3.2 Salem, Unit No. 2, TS 3/4.7.6 The licensee has proposed to change a reference in Action Statements d (Modes 1, 2, 3, and 4) and e (Modes 5 and 6) of LCO 3.7.6.1. This change would correct a reference, in both statements d and e, from Action 27 of Table 3.3-6 to Action 28. Action Statements d and e apply to situations with one or both of the series isolation dampers on a normal CAACS inoperable. In these situations, both radiation monitors in the affected intake are considered inoperable. Currently, the reference in LCO 3.7.6.1 refers to Action 27 which applies to operation with one intake radiation monitor inoperable. For operation with both intake radiation monitors inoperable, Action 28 is appropriate.
This error was caused by changes to Table 3.3-6 effected by Amendment 206. Prior to this amendment, Action 27 dealt with single and dual intake radiation monitor inoperability. After implementation the single Action was divided into separate Actions 27 (single) and 28 (both).
The two Action Statements of LCO 3.7.6.1 were not updated to reflect this. The proposed changes to Action Statements d (Modes 1, 2, 3, and 4) and e (Modes 5 and 6) are administrative in nature, and are, therefore, acceptable.
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3.3 Salem, Unit No. 2, TS 3/4.2.2 The licensee has proposed a change to the conditions of applicability of the limitation FQ(z) FQ RTP/0.5, with FQ(z) being the Heat Flux Hot Channel Factor. The applicability would change from P > 0.5" to P 0.5" where P = Thermal Power/ Rated Thermal Power. The current applicability provides for double coverage of greater than 50% Rated Thermal Power (RTP), and no coverage of less than, and including, 50% RTP. This error was introduced in the retyping of pages for the implementation of Amendment 197. The proposed change is editorial in nature, correcting a typographical error, and is, therefore, acceptable.
3.4 Salem, Unit No. 2, TS Table 3.3-6 The proposed change would insert a minimum channels operable value of 1 for Table 3.3-6 2. a. 2) b), RCS Leakage Detection. Currently, the value is omitted from this table. The licensee stated that this omission was likely introduced during the retyping of pages for the implementation of Amendment 173. The proposed change is editorial in nature, correcting a typographical omission, and is, therefore, acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New Jersey State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
Pursuant to 10 CFR 51.21, 51.32, and 51.35, an environmental assessment and a finding of no significant impact has been prepared and published in the Federal Register on April 25, 2003 (68 FR 20412). Accordingly, based on the environmental assessment, the staff has determined that the issuance of the amendments will not have a significant effect on the quality of the human environment.
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 Contributors: R. Fretz Date: June 26, 2003