ML032370119
| ML032370119 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/01/2003 |
| From: | Robert Fretz NRC/NRR/DLPM/LPD1 |
| To: | Richard Anderson Public Service Enterprise Group |
| Fretz R, NRR/DLPM, 415-1324 | |
| References | |
| TAC MB8445, TAC MB8446 | |
| Download: ML032370119 (13) | |
Text
October 1, 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: TABLE 3.3-1, REACTOR TRIP SYSTEM INSTRUMENTATION (TAC NOS. MB8445 AND MB8446)
Dear Mr. Anderson:
The Commission has issued the enclosed Amendment Nos. 259 and 240 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 April 10, 2003. The amendments revise TS Table 3.3-1, Reactor Trip System Instrumentation, to modify the Condition and Setpoint description of permissive interlock P-7.
A copy of our Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's 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. 259 to License No. DPR-70
- 2. Amendment No. 240 to License No. DPR-75
- 3. Safety Evaluation cc w/encls: See next page
October 1, 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: TABLE 3.3-1, REACTOR TRIP SYSTEM INSTRUMENTATION (TAC NOS. MB8445 AND MB8446)
Dear Mr. Anderson:
The Commission has issued the enclosed Amendment Nos. 259 and 240 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 April 10, 2003. The amendments revise TS Table 3.3-1, Reactor Trip System Instrumentation, to modify the Condition and Setpoint description of permissive interlock P-7.
A copy of our Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's 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. 259 to License No. DPR-70
- 2. Amendment No. 240 to License No. DPR-75
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION SRichards JClifford OGC GMeyer, RGN-I PUBLIC RFretz ACRS CRaynor GHill(4)
PDI-2 Reading TBoyce WBeckner ACCESSION NUMBER: ML032370119 TS(s): ML, Package: ML
- See previous concurrence OFFICE PDI-2/PM PDI-2/LA IROB/SC OGC PDI-2/SC NAME RFretz SLittle for CRaynor WBeckner for TBoyce RHoefling JClifford DATE 08/28/03 08/28/03 09/08/03 09/17/03 10/01/03
OFFICIAL RECORD COPY
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. 259 License No. DPR-70 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by PSEG Nuclear, LLC and Exelon Generation Company, LLC (the licensees) dated April 10, 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. 259, 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 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
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: October 1, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 259 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Replace the following page of 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 Insert 3/4 3-7 3/4 3-7
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. 240 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by PSEG Nuclear LLC and Exelon Generation Company, LLC (the licensees) dated April 10, 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. 240, 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 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
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: October 1, 2003
ATTACHMENT TO LICENSE AMENDMENT NO. 240 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Replace the following page of 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 Insert 3/4 3-7 3/4 3-7
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 259 AND 240 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 April 10, 2003, PSEG Nuclear, LLC (PSEG or the licensee) submitted a request for changes to the Salem Nuclear Generating Station, Unit Nos. 1 and 2 (Salem), Technical Specifications (TSs). The requested changes would revise Salem TS Table 3.3-1, Reactor Trip System Instrumentation, to modify the Condition and Setpoint description of permissive interlock P-7. The "Condition and Setpoint" description for permissive P-7 provided in Table 3.3-1 currently states:
With 2 of 4 Power Range Neutron Flux Channels 11% of RATED THERMAL POWER or 1 of 2 Turbine impulse chamber pressure channels a pressure equivalent to 11% of RATED THERMAL POWER.
The proposed change replaces "Turbine impulse chamber pressure" with "Turbine steam line inlet pressure," and supports a planned modification that converts the high pressure turbine (HPT) from an impulse to a reaction turbine.
2.0 REGULATORY EVALUATION
The U.S. Nuclear Regulatory Commission (NRC or the Commission) staff reviews proposed changes to TSs for compliance with Title 10 of the Code of Federal Regulations (10 CFR),
Section 50.36, and other regulatory requirements, including conformance with applicable general design criteria (GDC), to determine whether or not the proposed changes maintain adequate safety. Changes that result in relaxation (less restrictive condition) of current TS requirements require detailed justification.
Licensees may revise their TSs provided that a plant-specific review supports a finding of continued adequate safety because: (1) the change is editorial, administrative or provides 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 nonetheless still affords adequate assurance of safety when judged against current regulatory standards.
The applicable GDC for Salem is found in Updated Final Safety Analysis Report (UFSAR),
Section 3.1.2, Criterion 12, Instrumentation and Control Systems. UFSAR GDC 12, states that [i]nstrumentation and controls shall be provided as required to monitor and maintain variables within prescribed operating ranges. UFSAR GDC 12 is analogous to 10 CFR Part 50, Appendix A, GDC 13, Instrumentation and control.
3.0 TECHNICAL EVALUATION
The requirement for the P-7 interlock within the Reactor Trip System (RTS) design is that the P-7 signal be representative of overall turbine power. This is accomplished by measuring the turbine first stage pressure, since turbine first stage pressure exhibits a consistent and accurate relationship with overall turbine power. The term impulse refers to a particular type of turbine blade design. PSEG is planning to replace its existing HPT with reaction turbine blades.
Hence, the licensee proposed a TS change to replace the words "Turbine impulse chamber pressure" with "Turbine steam line inlet pressure." The proposed change results in a TS that states the basic P-7 requirement generically, without specifying a particular turbine blade design. This TS change allows flexibility for the planned turbine design enhancements. The NRC staff has determined that the proposed change in the description of the Salem turbines is editorial in nature, does not involve any physical or design change for the P-7 function, and will have no effect on the operation of the RTS. The NRC staff further concludes that the licensees proposed revision is acceptable since the proposed generic turbine blade design description retains the required P-7 safety function, and will, thus, maintain conformance with Salem UFSAR GDC 12.
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 August 27, 2003 (68 FR 51597). 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 Contributor: R. Fretz Date: October 1, 2003
PSEG Nuclear LLC Salem Nuclear Generating Station, Unit Nos. 1 and 2 cc:
Mr. A. Christopher Bakken, III Senior Vice President - Site Operations PSEG Nuclear - X15 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. John T. Carlin Vice President - Nuclear Assessments PSEG Nuclear - N10 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. David F. Garchow Vice President - Eng/Tech Support PSEG Nuclear - N28 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Gabor Salamon Manager - 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