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| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 6 | | | page count = 6 |
| | project = CAC:MF6065, CAC:MF6066 | | | project = CAC:MF6066, CAC:MF6065 |
| | stage = RAI | | | stage = RAI |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Robert Braun President and Chief Nuclear Officer PSEG Nuclear LLC -N09 P.O. Box 236 Hancocks Bridge, NJ 08038 November 2, 2015 SUBJECT: SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST REGARDING REPLACEMENT OF SOURCE RANGE AND INTERMEDIATE RANGE NEUTRON MONITORING SYSTEMS (CAC NOS. MF6065 AND MF6066) Dear Mr. Braun: By letter dated April 3, 2015,1 PSEG Nuclear LLC (the licensee) submitted a license amendment request to revise Technical Specification 3/4.3.1, "Reactor Trip System Instrumentation," to support planned plant modifications to replace the existing source range and intermediate range nuclear instrumentation with the Thermo Scientific Neutron Flux Monitoring Systems. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the application and the June 2, 2015,2 supplemental information submitted by the licensee during the acceptance review. The supplemental information provided the basis for detailed review. During this detailed review, the NRC staff identified additional information that is needed to complete its review of the submittals. The specific questions are found in the enclosed request for additional information. The draft questions were sent by electronic transmission on October 6, 2015, to Mr. Paul Duke. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. On October 22, 2015, Mr. Brian Thomas of your staff indicated that the licensee will submit a response within 30 days of the date of this letter. 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15068A359. 2 ADAMS Accession No. ML 15153A 193. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Robert Braun President and Chief Nuclear Officer PSEG Nuclear LLC -N09 P.O. Box 236 Hancocks Bridge, NJ 08038 November 2, 2015 |
| R. Braun -2 -If you have any questions, please contact me at 301-415-4037 orThomas.Wengert@nrc.gov. Docket Nos. 50-272 and 50-311 Enclosure: Request for Additional Information cc w/enclosure: Distribution via Listserv Sincerely, Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION REGARDING PSEG NUCLEAR LLC SALEM NUCLEAR GENERATING STATION. UNITS 1AND2 DOCKET NOS. 50-272 AND 50-311 By letter dated April 3, 2015,1 PSEG Nuclear LLC (the licensee) submitted a license amendment request to revise Technical Specification (TS) 3/4.3.1, "Reactor Trip System Instrumentation," to support planned plant modifications to replace the existing source range (SR) and intermediate range (IR) nuclear instrumentation with the Thermo Scientific Neutron Flux Monitoring Systems. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the application and the June 2, 2015,2 supplemental information submitted by the licensee during the acceptance review. The supplemental information provided the basis for detailed review. The NRC staff identified additional information that is needed, as described below, to complete its review of the submittals. The requested information is applicable only to new or replacement items. Instrumentation and Controls Branch (EICB)-Reguest for Additional Information (RAl)-1 In its response to the NRC's request for supplemental information dated June 2, 2015, the licensee explained that the Nuclear Instrumentation System source, intermediate range detectors, and associated cables inside the containment were evaluated for applicability of Title 1 O of the Code of Federal Regulations Part 50.49 criteria and were exempted from the Salem Nuclear Generating Station equipment qualification program requirements. Since the equipment is located inside the containment, it should be qualified for normal and abnormal conditions inside the containment for its qualified life, so that the equipment can continue to meet its safety functions as required by General Design Criterion (GDC) 4. Please provide the qualification documentation that shows how the equipment meets the environmental conditions for its qualified life. If this information is not available, please specify when the information will be available for staff review. If a summary report is provided, it should explain the test requirements based on plant specifications and provide the test results. If the equipment inside the containment has been previously qualified and is not being changed or replaced in the subject amendment request, state that in the response. 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15093A291. 2 ADAMS Accession No. ML 15153A 193. Enclosure | | |
| -2 -EICB-RAl-2 Please provide the documentation to confirm that all new and replacement equipment will perform their safety functions during and after an earthquake, as required by GDC 4. The equipment must be qualified to the seismic response spectra based on the location of the equipment and any amplification caused by the test equipment elevation. State the basis (e.g., Institute of Electrical and Electronics Engineers standard) and a summary of the test results. EICB-RAl-3 With regard to the electromagnetic interference/radio frequency interference (EMl/RFI) susceptibility for the equipment in mild environment (the source range (SR) and intermediate range (IR) monitors), the licensee stated in its June 2, 2015, letter that the qualification and analysis were conducted in accordance with Electric Power Research Institute Topical Report-102323, Revision 2, "Guidelines for Electromagnetic Interference Testing in Power Plants." Please provide a summary of the qualification requirements and the tests performed to confirm that the equipment is not susceptible to EMl/RFI. The summary should include sufficient description for the NRC staff to determine the adequacy of the test program and its results. As an alternative, the licensee may provide the test requirements specifications and the test reports. EICB-RAl-4 With respect to the embedded software or embedded electronic components with software, the licensee's June 2, 2015, letter stated, in part: The power to the SDMM [shutdown margin monitor) assembly is via a fuse in the SDMM that provides the isolation between the SDMM and the power source associated with the Source Range (SR) Monitor. The circuit isolation between SDMM and SR is provided by two relays. The SDMM provides +/-12v to LEDs [light emitting diodes) for local indication of the status of the instrument power and does not interface with any other components. The SR signal processor provides a pulse signal to the SDMM through an isolation device in the SR channels .... Please confirm that the fuse supplying power to the SDMM is properly coordinated with the upstream power supply breaker or fuse. Also, describe the type of signals processed through the isolation device. Is the circuit isolation achieved by coil to contact or fiber optic isolation or some form of isolation? Further, describe the type of isolation device used for sending the SR pulse signal to the SDMM.
| | ==SUBJECT:== |
| -3 -EICB-RAl-5 In response to the accident analysis impact, the licensee referenced Section 15.2 of the Updated Final Safety Analysis Report (UFSAR) in its letter dated June 2, 2015, and provided the accident analysis table to go with this section. Item 15.2.4 in this table addresses uncontrolled boron dilution accident and reactor trip initiators. The reactor trip for this event is credited by an operator action based upon audible count rate. A note at the end of table states: *For the uncontrolled boron dilution event, UFSAR Section 15.2.4 notes that the operator has prompt and definite indication of any boron dilution from the audible count rate instrumentation. The Source Range and Intermediate Range upgrades do not affect the audible count rate instrumentation. The UFSAR also states that high count rate is alarmed in the reactor containment and the Control Room. The UFSAR does not provide for a High Count Rate alarm setpoint. Please clarify the source of audible count rate, since it is stated that the audible count rate is not affected by the SR and IR changes. What is the current setpoint for high count rate alarm? Also, provide the rationale for selecting the current setpoint (no calculation is required to be provided). Please confirm that the audible count rate and the high count rate alarm will continue to be provided after the implementation of the license amendment.
| | SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST REGARDING REPLACEMENT OF SOURCE RANGE AND INTERMEDIATE RANGE NEUTRON MONITORING SYSTEMS (CAC NOS. MF6065 AND MF6066) |
| R. Braun -2 -If you have any questions, please contact me at 301-415-4037 or Thomas.Wengert@nrc.gov. Docket Nos. 50-272 and 50-311 Enclosure: Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION: PUBLIC RidsACRS MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDeEicb Resource RidsNrrLALRonewicz Resource RidsNRRLIC109 Resource ADAMS A ccess1on N o.: ML 15287A141 OFFICE LPL 1-2/PM LPL 1-2/LA NAME TWengert LRonewicz DATE 10/23/15 10/15/15 Sincerely, IRA/ Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LPLl-2 R/F RidsNrrPMSalem Resource RidsNrrDorlLpl1-2 Resource GSingh, DE RidsRgn1 MailCenter Resource *b d 1y memoran um DE/EICB/BC* LPL 1-2/BC MWaters DBroaddus 9/18/15 10/30/15 LPL 1-2/PM TWengert 11/02/15 OFFICIAL RECORD COPY | | |
| | ==Dear Mr. Braun:== |
| | By letter dated April 3, 2015,1 PSEG Nuclear LLC (the licensee) submitted a license amendment request to revise Technical Specification 3/4.3.1, "Reactor Trip System Instrumentation," to support planned plant modifications to replace the existing source range and intermediate range nuclear instrumentation with the Thermo Scientific Neutron Flux Monitoring Systems. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the application and the June 2, 2015,2 supplemental information submitted by the licensee during the acceptance review. The supplemental information provided the basis for detailed review. During this detailed review, the NRC staff identified additional information that is needed to complete its review of the submittals. The specific questions are found in the enclosed request for additional information. The draft questions were sent by electronic transmission on October 6, 2015, to Mr. Paul Duke. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. On October 22, 2015, Mr. Brian Thomas of your staff indicated that the licensee will submit a response within 30 days of the date of this letter. 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15068A359. 2 ADAMS Accession No. ML 15153A 193. |
| | R. Braun If you have any questions, please contact me at 301-415-4037 orThomas.Wengert@nrc.gov. Docket Nos. 50-272 and 50-311 |
| | |
| | ==Enclosure:== |
| | Request for Additional Information cc w/enclosure: Distribution via Listserv Sincerely, Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION REGARDING PSEG NUCLEAR LLC SALEM NUCLEAR GENERATING STATION. UNITS 1AND2 DOCKET NOS. 50-272 AND 50-311 By letter dated April 3, 2015,1 PSEG Nuclear LLC (the licensee) submitted a license amendment request to revise Technical Specification (TS) 3/4.3.1, "Reactor Trip System Instrumentation," to support planned plant modifications to replace the existing source range (SR) and intermediate range (IR) nuclear instrumentation with the Thermo Scientific Neutron Flux Monitoring Systems. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the application and the June 2, 2015,2 supplemental information submitted by the licensee during the acceptance review. The supplemental information provided the basis for detailed review. The NRC staff identified additional information that is needed, as described below, to complete its review of the submittals. The requested information is applicable only to new or replacement items. Instrumentation and Controls Branch (EICB)-Reguest for Additional Information (RAl)-1 In its response to the NRC's request for supplemental information dated June 2, 2015, the licensee explained that the Nuclear Instrumentation System source, intermediate range detectors, and associated cables inside the containment were evaluated for applicability of Title 1 O of the Code of Federal Regulations Part 50.49 criteria and were exempted from the Salem Nuclear Generating Station equipment qualification program requirements. Since the equipment is located inside the containment, it should be qualified for normal and abnormal conditions inside the containment for its qualified life, so that the equipment can continue to meet its safety functions as required by General Design Criterion (GDC) 4. Please provide the qualification documentation that shows how the equipment meets the environmental conditions for its qualified life. If this information is not available, please specify when the information will be available for staff review. If a summary report is provided, it should explain the test requirements based on plant specifications and provide the test results. If the equipment inside the containment has been previously qualified and is not being changed or replaced in the subject amendment request, state that in the response. 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15093A291. 2 ADAMS Accession No. ML 15153A 193. Enclosure EICB-RAl-2 Please provide the documentation to confirm that all new and replacement equipment will perform their safety functions during and after an earthquake, as required by GDC 4. The equipment must be qualified to the seismic response spectra based on the location of the equipment and any amplification caused by the test equipment elevation. State the basis (e.g., Institute of Electrical and Electronics Engineers standard) and a summary of the test results. EICB-RAl-3 With regard to the electromagnetic interference/radio frequency interference (EMl/RFI) susceptibility for the equipment in mild environment (the source range (SR) and intermediate range (IR) monitors), the licensee stated in its June 2, 2015, letter that the qualification and analysis were conducted in accordance with Electric Power Research Institute Topical Report-102323, Revision 2, "Guidelines for Electromagnetic Interference Testing in Power Plants." Please provide a summary of the qualification requirements and the tests performed to confirm that the equipment is not susceptible to EMl/RFI. The summary should include sufficient description for the NRC staff to determine the adequacy of the test program and its results. As an alternative, the licensee may provide the test requirements specifications and the test reports. EICB-RAl-4 With respect to the embedded software or embedded electronic components with software, the licensee's June 2, 2015, letter stated, in part: The power to the SDMM [shutdown margin monitor) assembly is via a fuse in the SDMM that provides the isolation between the SDMM and the power source associated with the Source Range (SR) Monitor. The circuit isolation between SDMM and SR is provided by two relays. The SDMM provides +/-12v to LEDs [light emitting diodes) for local indication of the status of the instrument power and does not interface with any other components. The SR signal processor provides a pulse signal to the SDMM through an isolation device in the SR channels .... Please confirm that the fuse supplying power to the SDMM is properly coordinated with the upstream power supply breaker or fuse. Also, describe the type of signals processed through the isolation device. Is the circuit isolation achieved by coil to contact or fiber optic isolation or some form of isolation? Further, describe the type of isolation device used for sending the SR pulse signal to the SDMM. |
| | EICB-RAl-5 In response to the accident analysis impact, the licensee referenced Section 15.2 of the Updated Final Safety Analysis Report (UFSAR) in its letter dated June 2, 2015, and provided the accident analysis table to go with this section. Item 15.2.4 in this table addresses uncontrolled boron dilution accident and reactor trip initiators. The reactor trip for this event is credited by an operator action based upon audible count rate. A note at the end of table states: *For the uncontrolled boron dilution event, UFSAR Section 15.2.4 notes that the operator has prompt and definite indication of any boron dilution from the audible count rate instrumentation. The Source Range and Intermediate Range upgrades do not affect the audible count rate instrumentation. The UFSAR also states that high count rate is alarmed in the reactor containment and the Control Room. The UFSAR does not provide for a High Count Rate alarm setpoint. Please clarify the source of audible count rate, since it is stated that the audible count rate is not affected by the SR and IR changes. What is the current setpoint for high count rate alarm? Also, provide the rationale for selecting the current setpoint (no calculation is required to be provided). Please confirm that the audible count rate and the high count rate alarm will continue to be provided after the implementation of the license amendment. |
| | R. Braun If you have any questions, please contact me at 301-415-4037 or Thomas.Wengert@nrc.gov. Docket Nos. 50-272 and 50-311 |
| | |
| | ==Enclosure:== |
| | Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION: PUBLIC RidsACRS MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDeEicb Resource RidsNrrLALRonewicz Resource RidsNRRLIC109 Resource ADAMS A ccess1on N o.: ML 15287A141 OFFICE LPL 1-2/PM LPL 1-2/LA NAME TWengert LRonewicz DATE 10/23/15 10/15/15 Sincerely, IRA/ Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LPLl-2 R/F RidsNrrPMSalem Resource RidsNrrDorlLpl1-2 Resource GSingh, DE RidsRgn1 MailCenter Resource *b d 1y memoran um DE/EICB/BC* LPL 1-2/BC MWaters DBroaddus 9/18/15 10/30/15 LPL 1-2/PM TWengert 11/02/15 OFFICIAL RECORD COPY |
| }} | | }} |
Letter Sequence RAI |
|---|
CAC:MF6066, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) CAC:MF6065, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
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ML17199A1122017-07-18018 July 2017
Request for Additional Information - Salem Units 1 and 2 - Accident Monitoring Instrumentation License Amendment Request (CAC Nos. MF8859 & MF8860)
ML17192A1672017-07-11011 July 2017
Request for Additional Information - Salem Unit 1 - Steam Generator Tube Inspection Report
ML17115A4032017-05-0909 May 2017
Request for Additional Information Regarding Relief Request SC-14R-171 - Use of Code Cases N-695-1 and N-696-1
ML16321A4642016-11-21021 November 2016
and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request for Additional Information Regarding License Amendment Request to Remove Certain Training Requirements
ML16218A0052016-08-11011 August 2016
Request for Additional Information Concerning Request for an Extension to Enforcement Guidance Memorandum 12-001
ML16195A4492016-07-14014 July 2016
Request for Additional Information Regarding Chilled Water System Modifications
ML16188A4152016-07-0707 July 2016
Request for Additional Information Aging Management Program Plan for Reactor Vessel Internals
ML16124A5802016-05-0303 May 2016
and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Redacted - Request for Additional Information Review of Security Plan Revision 17 Changes
ML16013A1592016-02-17017 February 2016
Request for Additional Information Regarding Chilled Water System Modifications
ML15287A1412015-11-0202 November 2015
Request for Additional Information License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems
ML15287A1052015-11-0202 November 2015
Request for Additional Information License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors During Mode 6 (Refueling) (CAC Nos. MF5831 & MF5832)
ML15299A3832015-10-29029 October 2015
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request Regarding Chilled Water System Modification
ML15069A1812015-03-31031 March 2015
Request for Additional Information Aging Management Program Plan for Reactor Vessel Internals (TAC Nos. MF5149 and MF5150)
ML15075A2602015-03-24024 March 2015
Request for Additional Information Spring 2014 Steam Generator Tube Inspections
ML15055A3772015-03-10010 March 2015
and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Request for Additional Information Request to Update Appendix B to Renewed Facility Operating License DPR-70, DPR-75 and NPF-57
ML14197A6192014-07-24024 July 2014
and Salem Nuclear Generating Station, Units 1 and 2 - Request for Additional Information Regarding Cyber Security Plan Milestone 8 Implementation Schedule (Tac Nos. MF3384, MF3385 and MF3386)
ML14168A2422014-06-28028 June 2014
Request for Additional Information Regarding Flooding Hazard Reevaluation
ML14135A2912014-06-0202 June 2014
RAI Regarding Request for Relief SC-I4R-140 from American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section XI Requirements Regarding the Reactor Vessel Head Flange Seal Leak Detection
ML14086A6362014-04-30030 April 2014
Request for Additional Information Regarding Core Operating Limits Report
ML14066A2952014-03-0606 March 2014
Licensed Operator Positive Fitness-For-Duty-Test (FY14)
ML13330A5672013-11-22022 November 2013
Request for Additional Information: Salem Units 1 and 2 - Relief Request SC-14R-133 Repair of Service Water Piping (TAC MF1375 & 1376)
ML13304B4182013-11-0101 November 2013
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns
ML13304B9362013-10-29029 October 2013
Request for Additional Information: Salem Units 1 and 2 - Relief Request SC-14R-133 Repair of Service Water Piping (TAC MF1375 & 1376)
ML13270A4142013-10-17017 October 2013
Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation (TAC Nos. MF0913 and Mf
ML13249A0112013-09-0505 September 2013
Weko Seal Relief Request RAI
ML13196A3382013-07-15015 July 2013
2013 Decommissioning Fund Report RAI
ML13192A2322013-07-11011 July 2013
Draft Request for Additional Information Overall Integrated Plan in Response to Order EA-12-051, Reliable Spent Fuel Pool Instrumentation.
ML13186A1672013-07-11011 July 2013
Request for Additional Information Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
ML13179A3032013-06-28028 June 2013
RAIs for Salem Regarding Response to Order EA-12-051 (SFP Instrumentation)
ML13137A4882013-06-0505 June 2013
Request for Additional Information Relief Request SC-l4R-133
ML13149A0862013-06-0505 June 2013
Request for Additional Information Decommissioning Funding Status Report
ML13102A2752013-04-25025 April 2013
Request for Additional Information Change to PSEG Emergency Plan to Remove the Backup R45 Plant Vent Radiation Monitor Indications
2024-02-28
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Robert Braun President and Chief Nuclear Officer PSEG Nuclear LLC -N09 P.O. Box 236 Hancocks Bridge, NJ 08038 November 2, 2015
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT REQUEST REGARDING REPLACEMENT OF SOURCE RANGE AND INTERMEDIATE RANGE NEUTRON MONITORING SYSTEMS (CAC NOS. MF6065 AND MF6066)
Dear Mr. Braun:
By letter dated April 3, 2015,1 PSEG Nuclear LLC (the licensee) submitted a license amendment request to revise Technical Specification 3/4.3.1, "Reactor Trip System Instrumentation," to support planned plant modifications to replace the existing source range and intermediate range nuclear instrumentation with the Thermo Scientific Neutron Flux Monitoring Systems. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the application and the June 2, 2015,2 supplemental information submitted by the licensee during the acceptance review. The supplemental information provided the basis for detailed review. During this detailed review, the NRC staff identified additional information that is needed to complete its review of the submittals. The specific questions are found in the enclosed request for additional information. The draft questions were sent by electronic transmission on October 6, 2015, to Mr. Paul Duke. The draft questions were sent to ensure that they were understandable, the regulatory basis was clear, and to determine if the information was previously docketed. On October 22, 2015, Mr. Brian Thomas of your staff indicated that the licensee will submit a response within 30 days of the date of this letter. 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15068A359. 2 ADAMS Accession No. ML 15153A 193.
R. Braun If you have any questions, please contact me at 301-415-4037 orThomas.Wengert@nrc.gov. Docket Nos. 50-272 and 50-311
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv Sincerely, Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION REGARDING PSEG NUCLEAR LLC SALEM NUCLEAR GENERATING STATION. UNITS 1AND2 DOCKET NOS. 50-272 AND 50-311 By letter dated April 3, 2015,1 PSEG Nuclear LLC (the licensee) submitted a license amendment request to revise Technical Specification (TS) 3/4.3.1, "Reactor Trip System Instrumentation," to support planned plant modifications to replace the existing source range (SR) and intermediate range (IR) nuclear instrumentation with the Thermo Scientific Neutron Flux Monitoring Systems. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the application and the June 2, 2015,2 supplemental information submitted by the licensee during the acceptance review. The supplemental information provided the basis for detailed review. The NRC staff identified additional information that is needed, as described below, to complete its review of the submittals. The requested information is applicable only to new or replacement items. Instrumentation and Controls Branch (EICB)-Reguest for Additional Information (RAl)-1 In its response to the NRC's request for supplemental information dated June 2, 2015, the licensee explained that the Nuclear Instrumentation System source, intermediate range detectors, and associated cables inside the containment were evaluated for applicability of Title 1 O of the Code of Federal Regulations Part 50.49 criteria and were exempted from the Salem Nuclear Generating Station equipment qualification program requirements. Since the equipment is located inside the containment, it should be qualified for normal and abnormal conditions inside the containment for its qualified life, so that the equipment can continue to meet its safety functions as required by General Design Criterion (GDC) 4. Please provide the qualification documentation that shows how the equipment meets the environmental conditions for its qualified life. If this information is not available, please specify when the information will be available for staff review. If a summary report is provided, it should explain the test requirements based on plant specifications and provide the test results. If the equipment inside the containment has been previously qualified and is not being changed or replaced in the subject amendment request, state that in the response. 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15093A291. 2 ADAMS Accession No. ML 15153A 193. Enclosure EICB-RAl-2 Please provide the documentation to confirm that all new and replacement equipment will perform their safety functions during and after an earthquake, as required by GDC 4. The equipment must be qualified to the seismic response spectra based on the location of the equipment and any amplification caused by the test equipment elevation. State the basis (e.g., Institute of Electrical and Electronics Engineers standard) and a summary of the test results. EICB-RAl-3 With regard to the electromagnetic interference/radio frequency interference (EMl/RFI) susceptibility for the equipment in mild environment (the source range (SR) and intermediate range (IR) monitors), the licensee stated in its June 2, 2015, letter that the qualification and analysis were conducted in accordance with Electric Power Research Institute Topical Report-102323, Revision 2, "Guidelines for Electromagnetic Interference Testing in Power Plants." Please provide a summary of the qualification requirements and the tests performed to confirm that the equipment is not susceptible to EMl/RFI. The summary should include sufficient description for the NRC staff to determine the adequacy of the test program and its results. As an alternative, the licensee may provide the test requirements specifications and the test reports. EICB-RAl-4 With respect to the embedded software or embedded electronic components with software, the licensee's June 2, 2015, letter stated, in part: The power to the SDMM [shutdown margin monitor) assembly is via a fuse in the SDMM that provides the isolation between the SDMM and the power source associated with the Source Range (SR) Monitor. The circuit isolation between SDMM and SR is provided by two relays. The SDMM provides +/-12v to LEDs [light emitting diodes) for local indication of the status of the instrument power and does not interface with any other components. The SR signal processor provides a pulse signal to the SDMM through an isolation device in the SR channels .... Please confirm that the fuse supplying power to the SDMM is properly coordinated with the upstream power supply breaker or fuse. Also, describe the type of signals processed through the isolation device. Is the circuit isolation achieved by coil to contact or fiber optic isolation or some form of isolation? Further, describe the type of isolation device used for sending the SR pulse signal to the SDMM.
EICB-RAl-5 In response to the accident analysis impact, the licensee referenced Section 15.2 of the Updated Final Safety Analysis Report (UFSAR) in its letter dated June 2, 2015, and provided the accident analysis table to go with this section. Item 15.2.4 in this table addresses uncontrolled boron dilution accident and reactor trip initiators. The reactor trip for this event is credited by an operator action based upon audible count rate. A note at the end of table states: *For the uncontrolled boron dilution event, UFSAR Section 15.2.4 notes that the operator has prompt and definite indication of any boron dilution from the audible count rate instrumentation. The Source Range and Intermediate Range upgrades do not affect the audible count rate instrumentation. The UFSAR also states that high count rate is alarmed in the reactor containment and the Control Room. The UFSAR does not provide for a High Count Rate alarm setpoint. Please clarify the source of audible count rate, since it is stated that the audible count rate is not affected by the SR and IR changes. What is the current setpoint for high count rate alarm? Also, provide the rationale for selecting the current setpoint (no calculation is required to be provided). Please confirm that the audible count rate and the high count rate alarm will continue to be provided after the implementation of the license amendment.
R. Braun If you have any questions, please contact me at 301-415-4037 or Thomas.Wengert@nrc.gov. Docket Nos. 50-272 and 50-311
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION: PUBLIC RidsACRS MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDeEicb Resource RidsNrrLALRonewicz Resource RidsNRRLIC109 Resource ADAMS A ccess1on N o.: ML 15287A141 OFFICE LPL 1-2/PM LPL 1-2/LA NAME TWengert LRonewicz DATE 10/23/15 10/15/15 Sincerely, IRA/ Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation LPLl-2 R/F RidsNrrPMSalem Resource RidsNrrDorlLpl1-2 Resource GSingh, DE RidsRgn1 MailCenter Resource *b d 1y memoran um DE/EICB/BC* LPL 1-2/BC MWaters DBroaddus 9/18/15 10/30/15 LPL 1-2/PM TWengert 11/02/15 OFFICIAL RECORD COPY
