Letter Sequence Response to RAI |
---|
|
|
|
Similar Documents at Salem |
---|
Category:Letter type:LR
MONTHYEARLR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023 Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023 Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 LR-N23-0003, Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-2112023-02-0101 February 2023 Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-211 LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0095, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 20222022-12-20020 December 2022 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2022 LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0092, Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG2022-12-0909 December 2022 Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments LR-N22-0084, Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095)2022-11-17017 November 2022 Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095) LR-N22-0090, Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem2022-11-10010 November 2022 Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem LR-N22-0065, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations2022-09-27027 September 2022 Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations LR-N22-0074, Emergency Plan Evacuation Time Estimate2022-09-15015 September 2022 Emergency Plan Evacuation Time Estimate LR-N22-0066, License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM)2022-08-31031 August 2022 License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM) LR-N22-0063, Spent Fuel Cask Registration2022-08-10010 August 2022 Spent Fuel Cask Registration LR-N22-0068, In-Service Inspection Activities - 90-Day Report2022-08-10010 August 2022 In-Service Inspection Activities - 90-Day Report LR-N22-0012, License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature2022-08-0707 August 2022 License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature LR-N22-0062, Spent Fuel Cask Registration2022-07-21021 July 2022 Spent Fuel Cask Registration LR-N22-0006, License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days2022-06-29029 June 2022 License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days LR-N22-0051, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report2022-06-22022 June 2022 License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report LR-N22-0044, Emergency Plan Document Revisions Implemented November, 20212022-05-19019 May 2022 Emergency Plan Document Revisions Implemented November, 2021 LR-N22-0043, Core Operating Limits Report - Cycle 292022-05-0909 May 2022 Core Operating Limits Report - Cycle 29 LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr)2022-04-28028 April 2022 2021 Annual Radioactive Effluent Release Report (Rerr) LR-N22-0040, 2021 Annual Radiological Environmental Operating Report2022-04-28028 April 2022 2021 Annual Radiological Environmental Operating Report LR-N22-0039, Emergency Plan Document Revisions Implemented March 24, 20222022-04-21021 April 2022 Emergency Plan Document Revisions Implemented March 24, 2022 LR-N21-0052, Request for Relief from ASME Code Defect Removal for Service Water Buried Piping2022-04-0707 April 2022 Request for Relief from ASME Code Defect Removal for Service Water Buried Piping LR-N22-0023, Guarantees of Payment of Deferred Premiums2022-03-21021 March 2022 Guarantees of Payment of Deferred Premiums LR-N22-0022, Response to Request for Additional Information Relief Request S1-14R-210, Alternative Examination of Welds2022-03-21021 March 2022 Response to Request for Additional Information Relief Request S1-14R-210, Alternative Examination of Welds LR-N22-0017, Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data2022-02-25025 February 2022 Submittal of 2021 Annual Report of Fitness for Duty (FFD) Performance Data LR-N22-0016, Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility2022-02-24024 February 2022 Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility LR-N22-0013, In-Service Inspection Activities - 90-Day Report2022-02-10010 February 2022 In-Service Inspection Activities - 90-Day Report LR-N22-0007, Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs2022-01-0505 January 2022 Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs LR-N21-0061, Annual Report of Specific Activity Analysis - TS 6.9.1.5c2021-12-0909 December 2021 Annual Report of Specific Activity Analysis - TS 6.9.1.5c LR-N21-0083, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion2021-11-24024 November 2021 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion LR-N21-0078, Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-11-18018 November 2021 Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0066, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations2021-11-10010 November 2021 Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations 2023-09-08
[Table view] |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG NuclearLLC AUG 18 2010 10 CFR 50.90 LR-N10-0315 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Salem Generating Station -Unit 2 Facility Operating License No. DPR 75 NRC Docket No. 50-311
Subject:
Response to Request for Additional Information - License Amendment Request: One-Time On-Line Safety-Related Battery Replacement
References:
(1) Letter from PSEG to NRC, "License Amendment Request: One-Time On-Line Safety-Related Battery Replacement," dated March 29, 2010 (2) Letter from PSEG to NRC, "Response to Request for Additional Information - License Amendment Request: One-Time On-Line Safety-Related Battery Replacement," dated June 25, 2010 In Reference 1, PSEG Nuclear LLC (PSEG) submitted a license amendment request (S10-03) for the Salem Generating Station - Unit 2. This license amendment request proposed changes to Technical Specification (TS) Surveillance Requirements (SR) to allow a one-time replacement of the Salem Unit 2 2C 125VDC battery while at power. Specifically, SR 4.8.2.3.2 f and g would be revised, on a one time basis, to permit battery testing in a non-shutdown condition. The proposed one-time change is necessary to support the on-line replacement of the existing 2C battery with a new battery tested in accordance with the SR 4.8.2.3.2 f and g.
In Reference 2 PSEG provided the response to an NRC Request for Additional Information (RAI) on the license amendment request. Subsequently, the NRC has provided PSEG an additional RAI. The NRC RAI and the PSEG response are provided in Attachment I to this letter.
PSEG has reviewed the information supporting a finding of no significant hazards consideration that was provided in Reference 1. The additional information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. No new regulatory commitments are established by this submittal.
Should you have any questions regarding this submittal, please contact Mr. Jeff Keenan at (856) 339-5429.
A-()C 95-2168 REV. 7/99
Document Control Desk 2 LR-N10-0315 I declare under penalty of perjury that the foregoing is true and correct.
Executed on /Z O/O (16ate)
XarlA. Fricker Sitd Vice President - Salem Attachments (1)
CC M. Dapas, Regional Administrator (Acting) - NRC Region I R. Ennis, Project Manager - USNRC NRC Senior Resident Inspector - Salem P. Mulligan, Manager IV, NJBNE Commitment Coordinator - Salem PSEG Corporate Commitment Manager
LR-N10-0315 Attachment 1 REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT ONE-TIME ON-LINE BATTERY REPLACEMENT SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 DOCKET NO. 50-311 By letter dated March 29, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100970064), PSEG Nuclear LLC (the licensee) submitted an amendment request for Salem Nuclear Generating Station (Salem), Unit No. 2. The proposed amendment would revise the Technical Specifications (TSs) to allow a one-time replacement of the 2C 125-volt direct current (VDC) battery while Salem Unit 2 is at power.
The Nuclear Regulatory Commission staff has reviewed the information the licensee provided that supports the proposed amendment and has made a Request For Additional Information (RAI) in order to complete its review.
NRC Question In Section 4.8 of Attachment 1 to the application dated March 29, 2010, and on page 8 of to the letter dated June 25, 2010, PSEG described the testing that will be performed for both the temporary and new replacement (permanent) battery. As proposed, the preoperational testing for the batteries, following installation in the switchgear room (temporary battery) and 2C battery room (permanent battery), will include: (1) check of the battery connection resistance (cell connections, inter-rack connections and connections to the 125 VDC bus); and (2) check of battery cell parameters (intra-cell voltage, electrolyte specific gravity, electrolyte level, electrolyte temperature) and overall battery voltage on float charge. The licensee stated that testing for both batteries will be performed in accordance with IEEE-450-2002.
NRC Regulatory Guide (RG) 1.129, Revision 2, dated February 2007, endorses (with certain clarifying regulatory positions) IEEE-450-2002. Regulatory Position C.1 in RG 1.129 states that:
Subsection 2, "References," which stipulates that this standard should be used in conjunction with other IEEE standards, should be supplemented as follows:
"This recommended practice shall be used in conjunction with the following publications:
- IEEE Std 484, 'IEEE Recommended Practice for Installation Design and Installation of Vented Lead-Acid Batteries for Stationary Applications,' as endorsed by Regulatory Guide 1.128
- IEEE Std 485-1997, 'IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications'"
In RG 1.32, Revision 3, "Criteria for Power Systems for Nuclear Power Plants," dated March 2004, the NRC staff endorsed, with certain exceptions, IEEE-308-2001, as providing a method acceptable to the staff for use in complying with the NRC's regulations for the design, operation,
LR-N1 0-0315 Attachment 1 and testing of electric power systems in nuclear power plants. Section 6.3, "Preoperational system test" of IEEE-308-2001 states that:
The preoperational system tests shall be performed with all components installed.
These tests shall demonstrate that the equipment operates within design limits and that the system is operational and can meet its performance specification. These tests shall be performed after the preoperational equipment tests and shall demonstrate that a) All required coincident Class 1E and non-Class 1E loads can operate acceptably on the preferred power supply.
b) The loss of the preferred power supply can be detected.
c) Each standby power supply can be started and can accept its design load within the time specified in the design basis while maintaining acceptable voltage regulation.
d) The redundant Class 1 E sources and their associated load groups are each independent of all other sources.
e) Transfer between preferred and standby power supplies can be accomplished.
f) The batteries of the direct current power supply can meet the design requirements of their connected load without the charger(s) in operation.
g) Each battery charger has sufficient capacity to meet the largest combined demands of the various continuous steady-state loads plus the charging capacity to restore the battery from the design minimum charge state to the fully charged state within the time stated in the design basis.
Consistent with IEEE-308-2001, the NRC staff position is that the preoperational tests for the temporary and permanent batteries (after they are installed in the switchgear room and 2C battery room, respectively), need to provide assurance that the batteries would be capable of supplying power to support all required loads for as long as would be required following a loss of alternating current power consistent with the Salem design basis. A battery service test, consistent with SR 4.8.2.3.2.f, on each battery would satisfy the staff's concerns. Please clarify how the proposed testing of the temporary and permanent batteries (after they are installed in the switchgear room and 2C battery room, respectively), provides assurance that the batteries will be demonstrated operable (i.e., battery capacity is adequate to supply all loads for the design duty cycle).
PSEG Response In accordance with IEEE 308-2001, Section 6.3, the temporary 2C battery and the new 2C replacement battery will be tested to verify the batteries can meet the design requirements of their connected load without the charger(s) in operation. The test, as described below, will be performed after final installation with all components installed.
This testing requirement will be fulfilled by performing an additional test on both the temporary 2C battery and the new replacement 2C battery prior to placing the batteries in service. A service test, in accordance with PSEG Procedure SC.MD-ST.125-0006, will be performed on the temporary 2C battery and the new 2C replacement battery after they are installed in the switchgear room and 2C battery room, respectively. This is a test of the battery's ability to satisfy the battery duty cycle.
The test meets the requirements of IEEE 450-2002 for "Service Test" and PSEG TS SR 4.8.2.3.2.f.