Letter Sequence Approval |
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MONTHYEARML0612805272006-05-25025 May 2006 License Amendments, Issuance of Amendments Containment Area High-Range Radiation Monitors Project stage: Approval ML0633801122006-12-28028 December 2006 Meeting Summary, Status of Unit 1 Power Uprate (TAC MC8312 and MD3048) (TS-418) Project stage: Meeting 2006-12-28
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Similar Documents at Salem |
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Category:Letter
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[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
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ML13072A1052013-03-28028 March 2013 Issuance of Amendments Revision to Technical Specification 6.8.4.i, Steam Generator Program, and Technical Specifications 6.9.1.10, Steam Generator Tube Inspection Report, for a Permanent Alternate ML12335A2212012-12-10010 December 2012 and Salem Nuclear Generating Station, Units 1 and 2 - Issuance of Amendments Approval of Change to Implementation Milestone 6 of Cyber Security Plan ML1120203592011-08-25025 August 2011 Issuance of Amendments Technical Specification Requirements for Snubbers ML1118615602011-07-28028 July 2011 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, License Amendment, Issuance of Amendments Approval of Cyber Security Plan 2023-08-14
[Table view] Category:Safety Evaluation
MONTHYEARML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location ML23139A1472023-06-0505 June 2023 Relief Request Associated with Fourth Interval In-service Inspection Limited Examinations of Weld Coverage ML23096A1842023-05-0909 May 2023 Issuance of Amendment No. 328 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report ML23081A4662023-05-0202 May 2023 Issuance of Amendment Nos. 346 and 327 Revise Technical Specifications to Extend Allowable Outage Time for Inoperable Emergency Diesel Generator ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership ML23044A1052023-03-13013 March 2023 Issuance of Amendment Nos. 345 and 326 Relocate Technical Specifications Requirements for Reactor Head Vents to Technical Requirements Manual ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report ML23019A3482023-02-0202 February 2023 Issuance of Relief Request No. SC-I5R-221 for the Alternative Repair for Service Water System Piping ML22130A7912022-05-24024 May 2022 Issuance of Relief Request No. S1-I4R-210 Fourth Inservice Inspection Interval Limited Examinations ML22061A0302022-04-0404 April 2022 Issuance of Amendment Nos. 343 and 324 Revise Technical Specifications Surveillance Requirements for Auxiliary Feedwater ML22012A4352022-02-14014 February 2022 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendments Nos. 230, 342, and 323 Delete Definition in 10 CFR 20 and Figures of Site and Surrounding Areas ML21277A2482021-11-16016 November 2021 Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version) ML21295A2292021-11-15015 November 2021 Issuance of Amendment Nos. 340 and 321 Revise Technical Specifications to Adopt TSTF 569, Revision of Response Time Testing Definitions ML21230A0182021-10-0808 October 2021 Issuance of Amendment No. 339 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report ML21202A0782021-09-0303 September 2021 Issuance of Amendment Nos. 338 and 320 Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21195A0622021-08-0303 August 2021 Issuance of Amendment No. 319 One-Time Request to Revise Technical Specification Action for Rod Position Indicators ML21110A0522021-07-19019 July 2021 Issuance of Amendment Nos. 337 and 318, Revise Technical Specifications to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML21145A1892021-06-10010 June 2021 Authorization and Safety Evaluation for Alternative Request No. SC-I4R-200 ML20338A0382021-02-23023 February 2021 Issuance of Amendment Nos. 336 and 317 Leak-Before-Break for Accumulator, Residual Heat Removal, Safety Injection, and Pressurizer Surge Lines ML20224A2982020-08-20020 August 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20191A2032020-08-0606 August 2020 Issuance of Amendment Nos. 335 & 316-Revise Minimum Required Channels, Mode Applicability, & Actions for Source Range/Intermediate Range Neutron Flux Reactor Trip System Instrumentation ML20104A1862020-04-20020 April 2020 Issuance of Alternative Request SC-I4R-192 for Examination of ASME Code, Section XI, Steam Generator and Pressurizer Nozzle Inside Radius Sections ML20099E2332020-04-20020 April 2020 Issuance of Alternative Request S1-I4R-191 for the Fourth 10-Year Inservice Inspection Interval ML20091K7302020-04-13013 April 2020 Issuance of Relief Request SC-I4R-190 for the Fourth 10-Year Inservice Inspection Interval ML20034E6172020-02-27027 February 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 222, 333, and 314 Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer ML19352F2312020-02-18018 February 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2; Issuance of Amendment Nos. 221, 332, and 313 Revise Emergency Plan Staffing Requirements ML19330F1562020-01-14014 January 2020 Issuance of Amendment Nos. 331 and 312 Revise Technical Specifications to Adopt TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19275D6942019-11-18018 November 2019 Issuance of Amendment Nos. 330 and 311 Revise Technical Specifications to Adopt TSFT-547, Clarification of Rod Position Requirements ML19105B1712019-05-31031 May 2019 Issuance of Amendment Nos. 329 and 310 Revise Reactor Trip System and Engineered Safety Feature Actuation System Instrumentation, Main Steam Isolation Valves, and Add New TS ML19077A3362019-04-11011 April 2019 Issuance of Amendment Nos. 328 and 309 Revise Technical Specifications to Extend Refueling Water Storage Tank Allowed Outage Time ML19044A6272019-03-0606 March 2019 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 214, 327, and 308 Revise Technical Specifications to Adopt TSTF-529 ML19050A3702019-03-0606 March 2019 Alternative to Reactor Vessel Nozzle Welds Examinations Inspection Interval (EPID-L-2018-LLR-0110) ML19009A4772019-01-25025 January 2019 Issuance of Amendment Nos. 326 and 307 Revise Technical Specifications to Increase Vital Instrument Bus Inverter Allowed Outage Time ML18318A2662018-12-19019 December 2018 Issuance of Amendment Nos. 325 and 306 Revise TS Reactor Trip System Instrumentation and Engineered Safety Features Actuation System Instrumentation Test Times and Completion Times ML18142B1262018-05-29029 May 2018 Use of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Inservice Inspection Activities ML18040A7782018-04-18018 April 2018 Issuance of Amendment Nos. 323 and 304 Relocation of Reactor Coolant System Pressure Isolation Valve Tables ML18085B1982018-04-18018 April 2018 Issuance of Amendment Nos. 324 and 305 Revise Technical Specification Actions for Rod Position Indicators ML17355A5702018-02-16016 February 2018 Issuance of Amendment Nos. 322, 303, & 210, to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 (CAC Nos. MF9268/MF9269/MF9270; EPID L-2017-LLA-0173) ML17349A1082018-01-18018 January 2018 Issuance of Amendments Containment Fan Coil Unit Allowed Outage Time Extension (CAC Nos. MF9364 and MF9365; EPID L-2017-LLA-0212) ML17227A0162017-11-14014 November 2017 Issuance of Amendments Accident Monitoring Instrumentation ML17304A9432017-11-0101 November 2017 Use of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI, for Inservice Inspection Activities ML17219A1862017-08-17017 August 2017 Safety Evaluation of Relief Request SC-I4R-171 Regarding the Fourth 10-Year Interval of the Inservice Inspection Program ML17172A5872017-07-17017 July 2017 Safety Evaluation of Relief Request S1-I4R-160 Regarding the Fourth 10-Year Interval of the Inservice Inspection Program ML17165A2142017-06-28028 June 2017 Issuance of Amendment to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule App. to Section 5.5 Testing ML17132A0052017-05-19019 May 2017 Alternative Request to Adopt American Society of Mechanical Engineers Code Case OMN-20 (CAC Nos. MF8313 and MF8314) ML17093A8702017-05-16016 May 2017 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendments Revised PSEG Nulcear LLC Cyber Security Plan Milestone 8 Implementation Schedule ML17012A2922017-02-0606 February 2017 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Issuance of Amendments ML16351A1822017-01-19019 January 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16229A5192016-09-29029 September 2016 Issuance of Amendments Correct Non-Conservative Technical Specifications and Other Discrepancies ML16137A5792016-06-29029 June 2016 Issuance of Amendments Extension of Implementation Period for Salem, Unit No. 1, License Amendment No. 311, and Salem, Unit No. 2 License Amendment No. 292 2023-08-14
[Table view] |
Text
May 25, 2006 Mr. William Levis Senior Vice President & Chief Nuclear Officer PSEG Nuclear LLC - N09 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, ISSUANCE OF AMENDMENTS RE: CONTAINMENT AREA HIGH-RANGE RADIATION MONITORS (TAC NOS. MC8311 AND MC8312)
Dear Mr. Levis:
The Commission has issued the enclosed Amendment Nos. 272 and 253 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 August 31, 2005, as supplemented by letters dated December 8, 2005, and April 10, 2006. These amendments move the requirements for the containment area high-range radiation monitors from TS 3/4.3.3.1, Radiation Monitoring Instrumentation, to TS 3/4.3.3.7, Accident Monitoring Instrumentation, and correct a typographical error in TS Surveillance Requirement 4.2.2.
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, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311
Enclosures:
- 1. Amendment No. 272 to License No. DPR-70
- 2. Amendment No. 253 to License No. DPR-75
- 3. Safety Evaluation cc w/encls: See next page
May 25, 2006 Mr. William Levis Senior Vice President & Chief Nuclear Officer PSEG Nuclear LLC - N09 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, ISSUANCE OF AMENDMENTS RE: CONTAINMENT AREA HIGH-RANGE RADIATION MONITORS (TAC NOS. MC8311 AND MC8312)
Dear Mr. Levis:
The Commission has issued the enclosed Amendment Nos. 272 and 253 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 August 31, 2005, as supplemented by letters dated December 8, 2005, and April 10, 2006. These amendments move the requirements for the containment area high-range radiation monitors from TS 3/4.3.3.1, Radiation Monitoring Instrumentation, to TS 3/4.3.3.7, Accident Monitoring Instrumentation, and correct a typographical error in TS Surveillance Requirement 4.2.2.
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, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311
Enclosures:
- 1. Amendment No. 272 to License No. DPR-70
- 2. Amendment No. 253 to License No. DPR-75
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION RidsNrrDorlLpl1-2 RidsOgcRp RidsRgn1MailCenter PUBLIC RidsNrrPMSBailey RidsAcrsAcnwMailCenter LPL1-2 R/F RidsNrrLACRaynor RidsNrrDirsItsb RidsNrrDorl GHill, OIS SMazumdar RidsNrrDorlDpr Accession Number: ML061280527 OFFICE LPL1-2/PM LPL1-2/LA EEIB/BC OGC LPL1-2/BC NAME SBailey/em CRaynor AHowe HWedewer DRoberts DATE 5/24/06 5/12/06 05/12/06 5/24/06 5/24/06 Official Record Copy
Salem Nuclear Generating Station, Unit Nos. 1 and 2 cc:
Mr. Dennis Winchester Township Clerk Vice President - Nuclear Assessment Lower Alloways Creek Township PSEG Nuclear Municipal Building, P.O. Box 157 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Paul Bauldauf, P.E., Asst. Director Mr. Thomas P. Joyce Radiation Protection Programs Site Vice President - Salem NJ Department of Environmental PSEG Nuclear Protection and Energy P.O. Box 236 CN 415 Hancocks Bridge, NJ 08038 Trenton, NJ 08625-0415 Mr. George H. Gellrich Mr. Brian Beam Plant Support Manager Board of Public Utilities PSEG Nuclear 2 Gateway Center, Tenth Floor P.O. Box 236 Newark, NJ 07102 Hancocks Bridge, NJ 08038 Regional Administrator, Region I Mr. Carl J. Fricker U.S. Nuclear Regulatory Commission Plant Manager - Salem 475 Allendale Road PSEG Nuclear - N21 King of Prussia, PA 19406 P.O. Box 236 Hancocks Bridge, NJ 08038 Senior Resident Inspector Salem Nuclear Generating Station Mr. Darin Benyak U.S. Nuclear Regulatory Commission Director - Regulatory Assurance Drawer 0509 PSEG Nuclear - N21 Hancocks Bridge, NJ 08038 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. James Mallon Manager - Licensing 200 Exelon Way, KSA 3-E Kennett Square, PA 19348 Mr. Steven Mannon Manager - Regulatory Assurance P.O. Box 236 Hancocks Bridge, NJ 08038 Jeffrie J. Keenan, Esquire 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. 272 License No. DPR-70
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment filed by PSEG Nuclear LLC on behalf of itself and Exelon Generation Company, LLC (the licensees) dated August 31, 2005, as supplemented by letters dated December 8, 2005, and April 10, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's 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. 272, 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 I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 25, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 272 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Replace the following page of Facility Operating License No. DPR-70 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 4 4 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 2-6 3/4 2-6 3/4 3-36 3/4 3-36 3/4 3-38 3/4 3-38 3/4 3-55 3/4 3-55 3/4 3-56a 3/4 3-56a 3/4 3-57a 3/4 3-57a
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. 253 License No. DPR-75
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment filed by PSEG Nuclear LLC on behalf of itself and Exelon Generation Company, LLC (the licensees) dated August 31, 2005, as supplemented by letters dated December 8, 2005, and April 10, 2006, 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. 253, 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 I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 25, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 253 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Replace the following page of the Facility Operating License No. DPR-75 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 4 4 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 3-39 3/4 3-39 3/4 3-41 3/4 3-41 3/4 3-51a 3/4 3-51a 3/4 3-51c 3/4 3-51c 3/4 3-52a 3/4 3-52a
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 272 AND 253 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 August 31, 2005, as supplemented by letter dated December 8, 2005, PSEG Nuclear LLC (the licensee) proposed amendments to the Facility Operating Licenses for Salem Nuclear Generating Station, Unit Nos. 1 and 2 (Salem). The amendments would change the Technical Specifications (TSs) to move the requirements for the containment area high-range radiation monitors (R-44s) from TS 3/4.3.3.1, Radiation Monitoring Instrumentation, to TS 3/4.3.3.7, Accident Monitoring Instrumentation. The licensee also proposed an editorial change to correct a typographical error in TS Surveillance Requirement (SR) 4.2.2 related to the equation for the hot channel factor. By letter dated April 10, 2006, the licensee provided additional information that did not expand the scope of the application as originally noticed, and did not change the Nuclear Regulatory Commission (NRC or the Commission) staffs original proposed no significant hazards consideration determination as published in the Federal Register on January 17, 2006 (71 FR 2594).
2.0 REGULATORY EVALUATION
The NRCs regulatory requirements related to the content of the TSs are set forth in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Technical Specifications. This regulation requires that the TSs include items in the following five specific categories: (1) safety limits, limiting safety system settings and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and (5) administrative controls. Additionally, Criterion 2 of 10 CFR 50.36(c)(2)(ii) requires an LCO to be established for a process variable, design feature, or operating restriction that is an initial condition of a design-basis accident or transient analysis that either assumes the failure of, or presents a challenge to, the integrity of a fission product barrier. The NRC has issued guidance for acceptable structure and content of TSs in the form of the standard technical specifications (STSs) found in NUREG-1431, Standard Technical Specifications Westinghouse Plants, Revision 3. The NRC has provided additional guidance on accident monitoring instrumentation in Regulatory Guide (RG) 1.97,
Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident.
3.0 TECHNICAL EVALUATION
The current TS LCO 3.3.3.1 requires that the radiation monitoring instrumentation be Operable in accordance with TS Table 3.3-6, Radiation Monitoring Instrumentation. TS Table 3.3-6 requires, in part, that two channels of R-44 be Operable in Operational Modes (Modes) 1-4, as defined in TS Table 1.1, Operational Modes. SR 4.3.3.1 requires, in part, that these channels receive channel checks, source checks, channel calibrations, and channel functional tests in accordance with TS Table 4.3-3, Radiation Monitoring Instrumentation Surveillance Requirements. TS Table 4.3-3 requires a monthly source check for the R-44s. TS 1.31, Source Check, defines the surveillance as the qualitative assessment of channel response, when the channel sensor is exposed to a source of increased radioactivity.
The licensee has proposed to move the TS requirements for the R-44s from the radiation monitoring instrumentation requirements, TS 3/4.3.3.1, to the accident monitoring instrument requirements, TS 3/4.3.3.7. LCO 3.3.3.7 requires that the accident monitoring instrumentation be Operable in Modes 1-3. SR 4.3.3.7 requires that each channel be demonstrated Operable by performance of channel checks, channel calibrations, and channel functional tests as specified in TS Table 4.3-11, Surveillance Requirements for Accident Monitoring Instrumentation. Moving the requirements for the R-44 channels from TS 3.3.3.1 to TS 3.3.3.7 would result in the following changes to the requirements:
- Remove the requirement for the R-44 channels to Operable in Mode 4, and
- Remove the requirement for a source check of the R-44 channels.
TS Table 1.1 defines Mode 4, Hot Shutdown, as having the reactor shut down and reactor coolant system average temperature between 200 and 350 degrees Fahrenheit.
The licensee stated that the goal of the subject requirements is to ensure that sufficient information is available to monitor and assess plant conditions following an accident, in accordance with RG 1.97. The R-44 channels are designed to meet the criteria in RG 1.97 with respect to locations (widely separated) and range (between 1 and 10,000 Rad/hour). The TS Bases state that the purpose of the R-44 channels is to ensure that 1) the radiation levels are continuously monitored, and 2) the alarm is initiated when the setpoint is reached. The licensee did not propose any changes to the design of the R-44 channels or the alarm setpoint.
The licensee stated that removing the requirements for the source check will result in significant dose savings and remove the industrial safety hazards associated with the surveillance.
Performance of a source check requires containment entries at power, climbing, and potential heat stress. Furthermore, to perform the manual source check, the technicians are required to remove the instrument from its mounting. This has increased the wear on the instrument leads and resulted in equipment failure. The licensee also stated that the R-44 monitors are designed to automatically perform an electronic source check (ESC). The ESC increases the voltage across the ionization chamber, causing an increase in current that simulates an increase in radiation levels. The ESC automatically performs this equivalent check several times a day and generates an alarm that alerts the control room operators of any malfunction.
The licensee stated that the ESC is functionally equivalent to the source check and provides an additional level of assurance that the monitors are functional.
The licensee also discussed the change to the Operability of the R-44s. Following a postulated accident, they are used as part of the fission product barrier integrity determination in the Salem Event Classification Guide (ECG), which is applicable in Modes 1-4. The ECG uses multiple independent parameters, such as core exit thermocouples, containment pressure, and reactor vessel water level, and other parameters would be available in Mode 4 even if the R-44s were not operable. The output from the R-44s is also used in the emergency operating procedures (EOPs), which are applicable in Modes 1-3. The R-44s output is used directly as a measurement of containment radiation level, and indirectly as an input to the Sub-Cooling Margin Monitor (SCMM), where the R-44s switch the SCMM display to the adverse mode when high radiation is detected in containment. The SCMMs are required by TS 3.3.3.7 to be Operable in Modes 1-3. The licensee further stated that the SCMM can be used in Mode 4 to determine whether safety injection flow can be reduced following a postulated event (e.g., a loss-of-coolant accident (LOCA)) in Mode 4. However, not having the SCMM automatically switch to the adverse mode has minimal consequence because 1) Mode 4 is a transitional mode that is not maintained for a significant period of time, and 2) procedures exist to calculate the subcooling margin manually in the event that the SCMMs are unavailable, and contingencies exist in the procedure to account for adverse conditions in the containment.
The NRC staff reviewed the proposed changes against the Salem licensing bases, RG 1.97, and the STSs found in NUREG-1431, Revision 3. The proposed change would bring the Salem TSs into better alignment with the STSs. The STSs do not contain requirements for radiation monitoring instrumentation (similar to Salem TS 3.3.3.1) and do not contain a definition for source check (since this SR only applies to the radiation monitoring instrumentation). In the STSs, the requirements for the wide-range containment radiation monitors are contained in STS 3.3.3, Post Accident Monitoring. STS 3.3.3 specifies that the accident monitoring instrumentation be Operable in Modes 1-3 and be subjected to channel checks, channel calibrations, and channel functional tests.
The STS Bases state that the postulated accidents are assumed to occur in Modes 1-3. In lower modes (e.g., Mode 4), operating conditions are such that the probability of an event that would require accident monitoring instrumentation is low. Consistent with this, the Salem EOPs, which use the R-44s, are applicable in Modes 1-3. Further, the Salem SCMMs, which receive an input from the R-44s, are required to be Operable in Modes 1-3. Therefore, the proposed change provides a consistent set of requirements between the accident monitoring instruments and the applicable safety analyses. In the unlikely event of a LOCA in Mode 4, the Salem procedures to calculate the subcooling margin manually have contingencies for adverse conditions inside containment.
In response to the NRC staffs request, the licensee provided additional information on the operating history of the R-44s. The licensee has historically relied on the ESC for demonstrating operability of the R-44 monitors. The licensee stated that the experience at Salem has demonstrated that the ESC is a more effective method for ensuring equipment reliability, including the integrity of the detector, cabling, and electronics, than the source check.
The ESC performs the check several times a day and generates an alarm to alert the operators of a malfunction.
Based on above evaluation, the NRC staff concludes that the proposed change to move the requirements for the R-44 monitors from TS 3/4.3.3.1 to TS 3/4.3.3.7 is acceptable.
The typographical error in TS SR 4.2.2.2.c.2 is an incorrect minus sign in the equation for a peaking factor, Fxy, that was inadvertently introduced in Salem Unit No. 1, Amendment 201, issued on November 26, 1997. The NRC staff finds correction of the error 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. 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 and changes surveillance requirements. The NRC staff has determined that the amendments involve 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding (71 FR 2594). Accordingly, the amendments meet 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 amendments.
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: S. Mazumdar S. Bailey Date: May 25, 2006