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MONTHYEARML0809903882008-04-18018 April 2008 Request for Additional Information Related to Technical Specification 3.7.5 C, Completion Time Extension Project stage: RAI ML0811602062008-04-29029 April 2008 Request for Additional Information, Technical Specification s 3.7.5.C Completion Time Extension Project stage: RAI ML0825503752008-09-19019 September 2008 Withdrawal of an Amendment Request (Tac Nos. MD7672 and MD7673) Project stage: Withdrawal ML0822701582008-10-0606 October 2008 Summary of Meeting with FPL Energy Point Beach LLC, on the Auxiliary Feedwater Technical Specification Completion Time Extension Amendment Request Project stage: Meeting 2008-04-18
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Category:Letter
MONTHYEARML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update ML23221A0522023-08-0909 August 2023 Confirmation of Initial License Examination, March 2024 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval ML23171B1062023-06-21021 June 2023 Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2 ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 ML23114A1222023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications 2024-02-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 ML23136A2802023-05-0505 May 2023 SLRA Second Annual Update RAI Set 1 ML23122A0132023-05-0101 May 2023 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI - License Amendment Request Regarding Risk-Informed Approach to Address GSI-191 ML23033A0292023-01-31031 January 2023 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI (Volume 2) - License Amendment Request Regarding TSTS-505 ML23003A8022023-01-0303 January 2023 Notification of NRC Baseline Inspection and Request for Information ML22354A1612022-12-20020 December 2022 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI - License Amendment Request Regarding TSTS-505 ML22311A5582022-11-22022 November 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Cep ML22266A0872022-09-23023 September 2022 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML22172A1192022-06-27027 June 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Adopt TSTF-505 Provide Risk Informed Extended Complete Times - RITSTF Initiative 4B ML22130A5712022-05-12012 May 2022 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML22041B0752022-02-10010 February 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000266/2022002 ML21362A6812021-12-17017 December 2021 SLRA Safety RAIs Set 14 Final ML21362A6822021-12-17017 December 2021 SLRA Safety RAIs Set 14 Final Email ML21362A6712021-12-15015 December 2021 SLRA Safety RAIs Set 13 Final Email ML21362A6702021-12-15015 December 2021 SLRA Safety RAIs Set 13 Final ML21287A0852021-10-14014 October 2021 SLRA Safety RAI Set 11 Final Email ML21286A6032021-10-0505 October 2021 SLRA Safety RAIs Set 10 Final Email ML21286A6042021-10-0505 October 2021 SLRA Safety RAIs Set 10 Final ML21287A0862021-09-29029 September 2021 SLRA Safety RAI Set 11 Final ML21273A0222021-09-29029 September 2021 SLRA Safety RAI Set 9 Final ML21253A1672021-09-10010 September 2021 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information Inspection Report 05000266/2022010 05000301/2022010 ML21242A2282021-08-27027 August 2021 SLRA Draft Safety RAI Set 9 ML21242A2292021-08-27027 August 2021 SLRA Draft Safety RAI Set 9 Email ML21242A2472021-08-26026 August 2021 SLRA Safety RAIs Set 8 Final ML21242A2232021-08-23023 August 2021 SLRA Draft Safety RAI Set 8 Email ML21242A2222021-08-23023 August 2021 SLRA Draft Safety RAI Set 8 ML21242A2192021-08-20020 August 2021 SLRA Safety RAI Set 7 Final Email ML21242A2202021-08-20020 August 2021 SLRA Safety RAI Set 7 Final ML21242A2132021-08-13013 August 2021 SLRA Safety RAIs Set 7 Draft Email ML21242A2142021-08-13013 August 2021 SLRA Safety RAIs Set 7 Draft ML21242A2032021-08-12012 August 2021 Srla Safety RAIs Set 5 Final ML21242A2382021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final Email ML21242A2392021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final ML21242A2042021-08-12012 August 2021 SLRA Safety RAIs Set 5 Final Email ML21242A0152021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final ML21242A0122021-08-0909 August 2021 SLRA Draft Safety RAIs Set 6 ML21242A1992021-08-0505 August 2021 Srla Draft Safety RAIs Set 5 ML21242A2002021-08-0505 August 2021 SLRA Draft Safety RAIs Set 5 Email ML21285A1212021-08-0505 August 2021 SLRA Public Meeting Discussion Questions August 5 2021 ML21238A2332021-08-0404 August 2021 SLRA Safety RAI Set 4 Final ML21238A2322021-08-0404 August 2021 SLRA Safety RAI Set 4 Final Email ML21237A0062021-08-0202 August 2021 SLRA Draft Safety RAIs Set 4 ML21214A0842021-07-27027 July 2021 SLRA Safety RAIs Set 3 Final ML21208A1892021-07-27027 July 2021 SLRA Safety RAIs Set 2 Final ML21172A2382021-07-21021 July 2021 (Pbn) Subsequent License Renewal Application (SLRA) Draft Requests for Additional Information (Rais) Safety - Set 2 ML21214A0722021-07-20020 July 2021 Subsequent License Renewal Application Draft Safety RAIs Set 3 ML21161A1192021-06-10010 June 2021 RAIs Set 1 Final Aging Management of Irradiated Concrete and Steel Reactor Vessel Supports Final ML21134A0582021-05-14014 May 2021 Final Request for Additional Information and Requests for Confirmation of Information - Point Beach SLRA Environmental Review (EPID No. L-2020-SLE-0002) - Email 2024-01-30
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Text
April 18, 2008 Mr. James McCarthy Site Vice President FPLE Point Beach 6610 Nuclear Road Two Rivers, WI 54241-9516
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO TECHNICAL SPECIFICATION 3.7.5 C COMPLETION TIME EXTENSION FOR POINT BEACH, UNITS 1 AND 2 (MD7672 AND MD7673)
Dear Mr. McCarthy:
The purpose of this letter is two-fold, (1) to request additional information so that the staff can complete its review and (2) to request your assistance relating to planning of your future licensing requests submitted to the Nuclear Regulatory Commission (NRC).
FPL Energy Point Beach, LLC (FPLE-PB), submitted a license amendment request dated December 31, 2007, to revise Point Beach Nuclear Plant, Units 1 and 2, Technical Specification (TS) for the completion time (CT) of TS 3.7.5.C. This revision would allow two separate one-time extensions of the CT for TS 3.7.5.C from seven days to 16 days; one extension for each of the train-specific motor-driven auxiliary feedwater pumps.
FPLE-PB requested a completion date by August 1, 2008. This requested completion date allows approximately 7 months for us to complete our review. The NRC has established performance goals for licensing actions to complete 96 percent in less than 1 year and 100 percent in less than 2 years. Consistent with these performance goals, we will endeavor to complete our review of your December 31, 2007, license amendment request as expeditiously as possible. However, based on the technical issues that need to be resolved, we may not complete our review by August 1, 2008.
We request your assistance to ensure that your licensing requests are well planned, taking into consideration your needs as well as the NRCs performance goals.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on April 3, 2008, it was agreed that you would provide a response within 30 days of receipt of the request for additional information (RAI). The enclosed RAI is only from the balance of plant branch. Additional RAIs are being developed in the fire protection and risk assessment areas and will be transmitted to you at a later date.
J. McCarthy The NRC staff considers that timely responses to RAIs will help ensure sufficient time is available for staff review. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1424.
Sincerely,
/RA/
Jack Cushing, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosure:
Request for Additional Information cc w/encl: See next page
J. McCarthy The NRC staff considers that timely responses to RAIs will help ensure sufficient time is available for staff review. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1424.
Sincerely,
/RA/
Jack Cushing, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-266 and 50-301
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC LPL3-1 R/F RidsNrrDorlLpl3-1 RidsNRRPMJCushing RidsNrrLATHarris RidsAcrsAcnw&mMailCenter RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDss DHarrison, NRR SGardocki, NRR ADAMS Accession Number: ML080990388 OFFICE LPL3-1/PM LPL3-1/LA DRA/APLA/BC LPL3-1/BC NAME JCushing THarris DHarrision LJames DATE 04/ 17 /08 04/ 17 /08 03/27/08 04/ 18 /08 OFFICIAL RECORD COPY
Point Beach Nuclear Plant, Units 1 and 2 cc:
Licensing Manager Mr. R. S. Kundalkar FPL Energy Point Beach, LLC Vice President 6610 Nuclear Road Nuclear Technical Services Two Rivers, WI 54241 FPL Energy, LLC P. O. Box 14000 Mr. Ken Duveneck Juno Beach, FL 33408-0420 Town Chairman Town of Two Creeks J. Kitsembel 13017 State Highway 42 Electric Division Mishicot, WI 54228 Public Service Commission of Wisconsin P. O. Box 7854 Resident Inspector's Office Madison, WI 53707-7854 U.S. Nuclear Regulatory Commission 6612 Nuclear Road Mr. M. S. Ross Two Rivers, WI 54241 Managing Attorney FPL Energy, LLC Chairman P. O. Box 14000 Public Service Commission of Wisconsin Juno Beach, FL 33408-0420 P.O. Box 7854 Madison, WI 53707-7854 Mr. J. A. Stall Senior Vice President and Chief Nuclear Officer FPL Group P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. Antonio Fernandez Senior Attorney FPL Energy, LLC P. O. Box 14000 Juno Beach, FL 33408-0420 Mr. Mano Nazar Senior Vice President and Nuclear Chief Operating Officer FPL Energy, LLC P. O. Box 14000 Juno Beach, FL 33408-0420
REQUEST FOR ADDITIONAL INFORMATION (RAI)
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 TECHNICAL SPECIFICATION 3.7.5 C COMPLETION TIME EXTENSION DOCKET NOS. 50-266 AND 50-301 In reviewing the FPLE Point Beach, LLC=s submittal dated December 31, 2007, the Nuclear Regulatory Commission staff has determined that the following information is needed in order to complete its review:
Balance of Plant RAIs
RAI 1
On page 1 of Enclosure 1, List of Regulatory Commitments, and on page 11 of Enclosure 2, as part of Tier 2 - Avoidance of Risk Significant Plant Configurations - the licensee states no other work that impacts risk will be planned to take place concurrently. As a result, the licensee takes credit for zero-maintenance term in probabilistic risk assessment.
Verify that the licensee can operate the two plants for both 16 day periods, without having to perform any surveillances or maintenance that would impact risk.
RAI 2
On page 23 of Enclosure 2, the licensee states that there were seven fire areas where a fire concurrent with a motor driven auxiliary feedwater (MDAFW) pump being unavailable because of the extended replacement activities could result in no auxiliary feedwater (AFW) pump being available to provide decay heat removal.
Explain the basis for the above statement that no AFW would be available if there was a fire in any of these areas.
RAI 3
On page 1 of Enclosure 1, List of Regulatory Commitments, and on page 12 of Enclosure 2, as part of Tier 2 - Avoidance of Risk Significant Plant Configurations - the licensee states that redundant operable AFW trains and supporting systems will be protected from inadvertent challenges. This design modification may involve interfaces with electrical busses/logics that supply power/start signals to the other operable AFW trains, which would present inadvertent challenges to these protected trains. Regulatory Guide 1.174 directs the licensee to perform a safety margin assessment. Potential interfaces include:
a) Both the MDAFW pumps and turbine driven auxiliary feedwater (TDAFW) pumps start on a trip or shutdown of both main feedwater pumps or closure of both feedwater regulating valves in one unit. These signals are processed through AMSAC at power levels above 40 percent.
b) The Updated Final Safety Analysis Report (UFSAR) shows safe shutdown loads for 125v DC comes from two busses, D-03 and D-04.
The steam supply and AFW discharge valves for the TDAFW pumps are powered from vital 125V DC.
c) This change will result in an increase in the emergency diesel generator loading, that the licensee states has been factored in the station electrical analysis, and has been deemed acceptable. Though the design considers the impact on the bus and diesel, the implementation of this modification from the 480v AC bus to the 4160v AC bus may affect sequencing and logic of risk important equipment.
- 1) Describe the interfaces this modification may have with other risk important equipment during the modification and testing that may affect operability of the other AFW pumps if an inadvertent action occurred.
- 2) Identify actions that will be used to fulfill licensing commitment to protect redundant operable trains from these inadvertent challenges.
- 3) Identify how the safety margins were affected and methodology used to determine the new margins were acceptable.
RAI 4
The UFSAR states that the AFW system components are tested and inspected in accordance with technical specification surveillance criteria and frequencies. Testing verifies motor-driven pump operability, turbine-driven pump operability including a cold start, and operability of all required motor operated valves (MOV). Control circuits, starting logic, and indicators are verified operable by their respective functional test. New pumps and flow control valves will change flow rates, or may require changes to flow orifices to limit flow to ruptured generator with a MOV open.
Verify that all required post modification testing can be performed with the units at the proposed power level and would not present an inadvertent challenge to other protected trains.
RAI 5
In the event of a loss of the TDAFW pump during an accident involving a steam generator tube rupture (SGTR) main feedwater line break in containment, or faulted steam generator (main steam line break (MSLB)), there may only be AFW to the faulted generator. In the UFSAR design basis, AFW is to be capable of isolating steam and feedwater to the faulted steam generator following a SGTR or a MSLB.
On page 18 of Enclosure 2, the licensee states If one of the unit-specific TDAFW pumps fails, then the remaining unit-specific TDAFW pump system is capable of providing 200 gallons per minute (gpm) per steam generator to a single unit, and the remaining in-service MDAFW pump system is capable of providing the credited 200 gpm to a single steam generator on the other unit. However, the methodology does not appear to address if the faulted generator or tube rupture occurs on the only steam generator supplied by the MDAFW pump, assuming the TDAFW pumps fails.
In addition, on page 20 of Enclosure 2, Section 3.2.1.3 - Isolation of Ruptured or Faulted Steam Generator - the deterministic evaluation analysis does not address the ability to isolate feed to a steam generator if the faulted generator or tube rupture occurs on the only steam generator supplied by the MDAFW pump, assuming failure of the TDAFW pump.
Provide an analysis of the response of the plant to meet design criteria to isolate flow to a ruptured or faulted steam generator during this maintenance activity.
Further on page 3 of Enclosure 2, the licensee states that during this modification, the cross connect capability for the MDAFW pumps to feed the other steam generator will not be available.
Explain how the unavailability of the cross tie valves affects the ability to meet: the current design basis, functions credited in risk assessment, and fulfill the defense in depth for accident analysis.
RAI 6
On page 19 of Enclosure 2, the licensee states that upon a SGTR the required flow rate will be 270 gpm to provide a rapid cooldown to meet design basis requirement. The SGTR and MSLB events require a rapid cool down in addition to meeting the demands of decay heat removal.
However, the licensee reports that the margin available with a single MDAFW pump is minimal.
Based upon the steam generator level, reactor coolant system temperature and pressurizer level that accompany the loss of normal feed and loss of all AC power to the station auxiliaries analyses, additional pumping capacity would be required to mitigate the SGTR or MSLB events.
The existing MDAFW pump can only deliver 200 gpm and the proposed new pump only delivers 240 gpm, which is still less than the 270 gpm required for SGTR and MSLB.
The licensee states that the purpose for this design change and approval for an extended technical specification completion time (CT) was to modify the AFW pump system to alleviate the portions of the existing operable but nonconforming or degraded conditions; however, this modification does not meet the design flow requirements for SGTR and MSLB. Explain why the modification was not designed to alleviate this condition, and how will the licensee address this continuing degraded condition.