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Category:Letter
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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 ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000272/20230052023-08-31031 August 2023 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005) ML23233A0762023-08-21021 August 2023 Requalification Program Inspection ML23192A8212023-08-14014 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 IR 05000272/20230022023-08-0909 August 2023 Integrated Inspection Report 05000272/2023002 and 05000311/2023002 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 IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 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 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 IR 05000272/20230012023-05-0303 May 2023 Integrated Inspection Report 05000272/2023001 and 05000311/2023001 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 IR 05000272/20233012023-05-0101 May 2023 Initial Operator Licensing Examination Report 05000272/2023301 and 05000311/2023301 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-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) 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 ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership 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 ML23086A0912023-03-24024 March 2023 NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, 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 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 IR 05000272/20230112023-03-0707 March 2023 Comprehensive Engineering Team Inspection Report 05000272/2023011 and 05000311/2023011 IR 05000272/20220062023-03-0101 March 2023 Annual Assessment Letter for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2022006 and 05000311/2022006) 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 ML23034A1532023-02-0909 February 2023 Operator Licensing Examination Approval ML23019A3482023-02-0202 February 2023 Issuance of Relief Request No. SC-I5R-221 for the Alternative Repair for Service Water System Piping 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 2024-02-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML22333A9022022-11-29029 November 2022 NRR E-mail Capture - Final Iolb RAI - Salem 1 and 2 LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG ML22318A1062022-11-14014 November 2022 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000272/2023011 and 05000311/2023011 ML22290A2202022-10-17017 October 2022 NRR E-mail Capture - Final RAI - Salem 1 and 2 LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG ML22055A0702022-02-22022 February 2022 NRR E-mail Capture - Final RAI - Salem 1-Relief Request Associated with Fourth Inservice Inspection (ISI) Interval Limited Examinations (L-2021-LLR-0085) ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21068A4142021-03-0909 March 2021 NRR E-mail Capture - Final RAI for Salem Unit 1 LAR to Revise and Relocate Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report ML21043A1442021-02-11011 February 2021 NRR E-mail Capture - Salem - Final RAI Alternative for Examination of ASME Section XI, Category B-B, Item Number B2.11and B2.12 (L-2020-LRR-0103) ML21021A2592021-01-21021 January 2021 NRR E-mail Capture - Final RAI - Salem 1 - Steam Generator Tube Inspection Report ML20281A5172020-10-13013 October 2020 Notification of Conduct of a Fire Protection Team Inspection ML18267A1712018-09-21021 September 2018 NRR E-mail Capture - Final RAI from PRA Branch: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0140) ML18264A0122018-09-20020 September 2018 NRR E-mail Capture - Final RAI from I&C Branch: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0140) ML18250A3132018-09-0606 September 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0140) ML18171A3212018-06-20020 June 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Adopt TSTF-411 and 418 (L-2017-LLA-0442) ML18094B0832018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to P. Duke RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for Salem and Hope Creek, and Peach Bottom ISFSIs Docket Nos. 72-48 and 72-29) ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML17212B1152017-07-31031 July 2017 Request for Additional Information - Salem Units 1 and 2 - Containment Fan Coil Unit Allowed Outage Time Amendment Request (CACs MF9364 and MF9365) 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 ML13063A7172013-03-11011 March 2013 Second Request for Additional Information Deletion of Condition for Inoperable Control Area Air Condition System/Control Room Emergency Air Conditioning System Isolation Dampers 2022-02-22
[Table view] |
Text
February 28, 2005 Mr. William Levis Senior Vice President & CNO PSEG Nuclear - X15 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, REQUEST FOR ADDITIONAL INFORMATION RE: REQUEST FOR APPROVAL OF FINAL SAFETY ANALYSIS REPORT CHANGE REGARDING THE CARBON DIOXIDE SUPPRESSION SYSTEM AT SALEM GENERATING STATION, UNIT NOS. 1 AND 2 (TAC NOS. MC3096 AND MC3097)
Dear Mr. Levis:
By letter dated April 15, 2004, PSEG Nuclear LLC (PSEG) requested Nuclear Regulatory Commission (NRC) approval of a change to the Salem Generating Station, Unit Nos. 1 and 2, Updated Final Safety Analysis Report discussion of the carbon dioxide suppression system.
Specifically, the change involves changing the design basis of the carbon dioxide suppression system in the switchgear rooms and lower penetration areas from a 50-percent carbon dioxide concentration with a 30-minute hold time to a 27.6-percent concentration with a hold time sufficient to suppress a fire and allow the PSEG Nuclear Fire Department to respond and take proper actions.
The NRC staff has reviewed and evaluated the information provided in the April 15, 2004, application and has determined that responses to the questions in the enclosure to this letter are needed in order for the staff to complete its review. These questions were discussed between NRC and PSEG staff in a teleconference on February 1, 2005. During that conversation, it was agreed that NRC technical reviewers will make a visit to the site in order to visually observe the physical characteristics of the plant that are in question. Depending on the results of that site visit, the NRC staff may have additional questions that will require a formal response from PSEG. NRC staff is coordinating with PSEG licensing staff to determine a mutually agreeable date for this site visit. If you have any questions I can be reached at (301) 415-1427.
Sincerely,
/RA/
Daniel Collins, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311
Enclosure:
Request for Additional Information cc w/encl: See next page
ML050400642
- memo ML050330153 OFFICE PDI-2/PM PDI-2/LA SPLB/SC PDI-2/SC NAME DCollins CRaynor SWeerakkody DRoberts DATE 2/24/05 2/24/05 2/3/05* 2/24/05 Salem Nuclear Generating Station, Unit Nos. 1 and 2 cc:
Mr. Thomas P. Joyce Dr. Jill Lipoti, Asst. Director Site Vice President - Salem Radiation Protection Programs PSEG Nuclear - X15 NJ Department of Environmental P.O. Box 236 Protection and Energy Hancocks Bridge, NJ 08038 CN 415 Trenton, NJ 08625-0415 Mr. Michael H. Brothers Vice President - Nuclear Assessments Brian Beam PSEG Nuclear - N10 Board of Public Utilities P.O. Box 236 2 Gateway Center, Tenth Floor Hancocks Bridge, NJ 08038 Newark, NJ 07102 Mr. Michael P. Gallagher Regional Administrator, Region I Vice President - Eng/Tech Support U.S. Nuclear Regulatory Commission PSEG Nuclear - N28 475 Allendale Road P.O. Box 236 King of Prussia, PA 19406 Hancocks Bridge, NJ 08038 Senior Resident Inspector Ms. Christina L. Perino Salem Nuclear Generating Station Director - Regulatory Assurance U.S. Nuclear Regulatory Commission PSEG Nuclear - N21 Drawer 0509 P.O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Mr. Carl J. Fricker Jeffrie J. Keenan, Esquire Plant Manager PSEG Nuclear - N21 PSEG Nuclear - N21 P.O. Box 236 P.O. Box 236 Hancocks Bridge, NJ 08038 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
REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED AMENDMENT REQUEST SALEM GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 The Nuclear Regulatory Commission (NRC) staff has reviewed and evaluated the information provided in the April 15, 2004, application submitted by PSEG Nuclear, LLC (PSEG), and has determined that responses to the following questions are needed in order for the staff to complete its review.
PSEG has exemptions for the 460V switchgear rooms (areas 1 and 2 FA-AB-84A), lower electrical penetration areas (areas 1 and 2 FA-EP-78C), and the 4160V switchgear rooms (areas 1 and 2 FA-AB-64A). These exemptions are in place because the redundant safe shutdown systems are not protected by complete, 1-hour fire barriers. In addition, the carbon dioxide (CO2) fire suppression system in the 4160V switchgear rooms is manually actuated.
- 1. The National Fire Protection Agency (NFPA)-12 states that a CO2 design concentration of 50% shall be maintained for not less than 20 minutes for deep-seated fires. Testing done by Sandia National Laboratories (SNL) in 1986 (NUREG/CR-3656) also used a design concentration of 50% and that concentration was maintained for 15 minutes for Institute of Electrical and Electronics Engineers (IEEE)-383 qualified cables. In those tests, smoldering continued in the cable trays after the soak time and in one case this led to the re-ignition of the fire after the reintroduction of oxygen (deep-seated fire).
SNL testing conducted in 1982 (NUREG/CR-2431) concluded that, ...both propagation and reignition of cable fires are frequently preceded by a deep-seated fire in excess of 1 minute duration. The report also states that the use of fire retardant materials (IEEE-383 cable qualifications) tends to increase the duration of deep-seated fires.
a) Provide the technical justification for the use of a CO2 system with a 27.6%
design concentration.
b) Please explain how the level of safety will be maintained for surface fires with a CO2 system that has a 27.6% design concentration.
c) Please explain how the level of safety will be maintained for deep-seated fires with a CO2 system that has a 27.6% design concentration.
- 2. According to the PSEG submittal, the CO2 system was originally designed to maintain a 50% concentration for 30 minutes. With the current state of the system, the CO2 concentrations are 27.6% 14 to 30 minutes after discharge, depending on the room.
- a. How much CO2 gas is leaking from each of the rooms under consideration and where is it leaking to?
- b. What effect will this leakage have on plant personnel?
Enclosure
- c. What effect will the discharge of the CO2 system have on the safe shutdown of the plant as well as the fire fighting actions should the fire not be extinguished with the lower CO2 concentration?
- 3. Describe the operator and fire brigade response to an alarm in the 4160-volt and 460-volt switchgear rooms and the lower electrical penetration areas.
- 4. The PSEG request states (page 5) that, Smoldering solids are extinguished by Fire Department action that typically includes application of water for rapid cooling and removal/reduction of debris. Fire suppression without reflash will be successful when rapid suppression of open flames occurs and CO2 concentration is maintained to prevent flaming combustion.
- a. Are all of the areas under consideration equipped with floor drains?
- b. If there are floor drains in these areas, what are the sizes and quantities in each area?
- c. If there are no floor drains in these areas, how will this impact the possible use of water by the fire brigade?
- d. Will water coming out of any of the rooms under consideration impact any safe shutdown systems?
- e. In previous instances of electrical/cable fires at other plants the fire brigades have been reluctant to use water. What assurances can you provide that water will be applied to fires not immediately extinguished by the CO2 system?
- 5. The PSEG submittal states (page 7) that, Because the Fire Department responds to the first alarm (including smoke detector alarms) in any of these rooms, the response of the Fire Department will typically begin prior to CO2 discharge.
- a. Does this mean that normally the fire department is expected to extinguish the fires instead of the suppression system?
- b. Is the first line of defense against a fire the CO2 suppression system or the fire department?
- 6. The PSEG submittal states (page 4) that On March 28, 2003, Engineering Evaluation S-C-FP-FEE-1748, CO2 System Operability in Switchgear Rooms and Lower Penetration Areas, was completed to assess the current conditions of the carbon dioxide system in the Switchgear Rooms and Lower Electrical Penetration Areas. This evaluation was never formally submitted to the NRC. Please formally submit this document to the NRC.