Letter Sequence Response to RAI |
---|
|
|
MONTHYEARML0603903012006-02-0909 February 2006 GSI Letter RAI Response to GL 2004-02 (TAC Nos. MC4676 and 4677) Project stage: RAI ML0817601002008-06-27027 June 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Approval of Extension Request Project stage: Other ML0835004652008-11-26026 November 2008 Comanche Peak - Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Cover Letter Project stage: Request ML0916604102009-05-11011 May 2009 E-mail Draft Request for Additional Information, Licensee'S Supplemental Responses Dated February 29 and November 26, 2008, to GL 2004-02 Project stage: Draft RAI ML0916604222009-05-11011 May 2009 Request for Additional Information Supplemental Responses to Generic Letter (GL) 2004-02 Dated 02/29/2008 and 11/26/2008 Project stage: RAI ML0918207102009-07-0202 July 2009 Revised Notice of Meeting with Representatives of Luminant Generation Co., LLC, Comanche Peak to Discuss Draft Request for Information for Generic Letter 2004-02 Response Project stage: Draft RAI ML0919604492009-07-0808 July 2009 Alion Meeting Presentations on RAI 9 - Pool Fill Transport, & RAI 6 - Fiber Erosion Testing Project stage: Request ML0919400842009-07-0909 July 2009 Luminant RAI 22 and 23 SBLOCA, Vortex, Air Ingestion, Void Fraction and Flashing Issues Project stage: Request ML0919402762009-07-0909 July 2009 NRC Opening Remarks Discuss the Draft Us Nuclear Regulatory Commission Request for Additional Information for Generic Letter GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressur Project stage: Draft RAI ML0919402772009-07-0909 July 2009 Luminant Holistic Overview: Presentation Will Cover Information Related to RAIs 1 - 5, 7, 12 - 14,16 - 19, 21, 25 - 36 and Overall Response to GL 2004-02 Project stage: Request ML0919400832009-07-0909 July 2009 Pci RAI 8, Test Protocol, Erosion Issue, RAI 15, Test Protocol, Latent Fiber Issue, Areva RAI 20, Test Flume, Fiberglass Larges Question Project stage: Request ML0919400852009-07-0909 July 2009 Luminant RAI 24 and 37, Secondary Line Breaks, Debris Load and Testing Project stage: Request ML0916707382009-07-15015 July 2009 Request for Additional Information Supplemental Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0920203432009-07-22022 July 2009 Revised Conference Call with Luminant Generation Company, LLC, to Discuss Draft Request for Additional Information Re Generic Letter 2004-02, Dated May 11, 2009 Project stage: Draft RAI ML0919705782009-07-31031 July 2009 Summary of Category 1 Meeting with Luminant Generation Company LLC, Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Meeting ML0926107912009-09-10010 September 2009 Comanche Peak Supplement Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Request CP-200901396, Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basic Accidents at Pressurized-water Reactors.2009-10-12012 October 2009 Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basic Accidents at Pressurized-water Reactors. Project stage: Supplement ML0930800032009-10-13013 October 2009 Comanche Peak - Supplement to Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML1009505642010-04-19019 April 2010 Generic Letter 2004-02 Supplemental Response Project stage: Other ML13045A4102013-02-15015 February 2013 2/28/13 Notice of Meeting Via Conference Call with Luminant to Discuss Generic Safety Issue 191, Assessment of Debris Accumulation on PWR (Pressurized-Water Reactor) Sump Performance, for Comanche Peak, Units 1 and 2 Project stage: Meeting ML13059A2022013-02-28028 February 2013 Email Licensee Slides for 2/28/13 Meeting Via Conference Call Project stage: Meeting ML13059A1812013-02-28028 February 2013 Licensee Slides for 2/28/13 Meeting Via Conference Call with Luminant Generation Company, LLC, Project stage: Meeting ML13067A0292013-03-15015 March 2013 2/28/13 - Summary of Meeting Via Conference Call with Luminant to Discuss Generic Safety Issue 191, Assessment of Debris Accumulation on PWR (Pressurized-Water Reactor) Sump Performance, for Comanche Peak, Units 1 and 2 Project stage: Meeting CP-201300670, Closure Options for Generic Safety Issue 191 (GSI-191), Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance2013-05-16016 May 2013 Closure Options for Generic Safety Issue 191 (GSI-191), Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance Project stage: Other ML13267A1972013-09-30030 September 2013 Request for Additional Information, Closure of Option 2a to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage; Related to Generic Safety Issue 191 Project stage: RAI CP-201301214, Response to Request for Additional Information Regarding Closure Options for Generic Safety Issue 1912013-10-31031 October 2013 Response to Request for Additional Information Regarding Closure Options for Generic Safety Issue 191 Project stage: Response to RAI 2009-07-31
[Table View] |
|
---|
Category:Letter type:CP
MONTHYEARCP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel2024-09-12012 September 2024 License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel CP-202400294, (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule CP-202400319, (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-13013 August 2024 (CPNPP) - Revision to CPNPP Letter to the NRC, Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality CP-202400315, (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-0505 August 2024 (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality CP-202400253, (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 52024-06-26026 June 2024 (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 5 CP-202400235, (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 02024-06-18018 June 2024 (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 0 CP-202400120, (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions2024-06-0303 June 2024 (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions CP-202400205, (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval2024-05-30030 May 2024 (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval CP-202400175, (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-05-16016 May 2024 (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator CP-202400100, (Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications2024-05-13013 May 2024 (Cpnpp), Unit 2, Two Recurring Reactor Scrams Associated with Main Feedwater System Modifications CP-202400097, Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning2024-05-0606 May 2024 Re Potential Loss of Safety Function Due to Inoperability of Both Trains of Uninterruptible Power Supply Heating, Ventilation & Air Conditioning CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters CP-202400107, (CPNPP) - 2023 Annual Radiological Environmental Operating Report2024-04-18018 April 2024 (CPNPP) - 2023 Annual Radiological Environmental Operating Report CP-202400099, (CPNPP) - Registration of Dry Spent Fuel Storage Canisters2024-04-0909 April 2024 (CPNPP) - Registration of Dry Spent Fuel Storage Canisters CP-202400092, (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-04-0101 April 2024 (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202400089, Property Damage Insurance2024-03-25025 March 2024 Property Damage Insurance CP-202400087, (CPNPP) - Notification of Deviation from Electric Power Research Institute (EPRI) MRP 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-Isolatable2024-03-21021 March 2024 (CPNPP) - Notification of Deviation from Electric Power Research Institute (EPRI) MRP 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-Isolatable CP-202400085, (CPNPP) - Revised Requested Compliance Date - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-0707 March 2024 (CPNPP) - Revised Requested Compliance Date - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CP-202400073, (CPNPP) - Response to RAI for License Amendment Request to Extend Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-03-0404 March 2024 (CPNPP) - Response to RAI for License Amendment Request to Extend Allowed Outage Time for an Inoperable Emergency Diesel Generator CP-202400072, (Cpnpp), Unit 1, Special Report 1-SR-24-001-00, Inoperable Post Accident Monitoring Instrumentation2024-02-29029 February 2024 (Cpnpp), Unit 1, Special Report 1-SR-24-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300470, (Cpnpp), Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-02-28028 February 2024 (Cpnpp), Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown CP-202300474, (Cpnpp), Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-02-28028 February 2024 (Cpnpp), Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions CP-202400063, (CPNPP) - Inservice Inspection (ISI) Owners Activity Reports (OAR-1 Forms) for Unit 1 Refueling Outage 23 (1RF23)2024-02-12012 February 2024 (CPNPP) - Inservice Inspection (ISI) Owners Activity Reports (OAR-1 Forms) for Unit 1 Refueling Outage 23 (1RF23) CP-202400030, License Renewal Application Revision 0 - Supplement 3, Revision 12024-01-31031 January 2024 License Renewal Application Revision 0 - Supplement 3, Revision 1 CP-202400034, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1)2024-01-29029 January 2024 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1) CP-202300575, (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 22023-12-13013 December 2023 (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 2 CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation2023-12-12012 December 2023 (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300494, License Renewal Application Revision 0, Supplement 32023-12-0606 December 2023 License Renewal Application Revision 0, Supplement 3 CP-202300349, License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation2023-11-20020 November 2023 License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation CP-202300416, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-10-12012 October 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202300432, Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 42023-10-0404 October 2023 Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 4 CP-202300442, (CPNPP) - Request to Use Later Code Edition for Inservice Inspection (ISI) Program2023-09-15015 September 2023 (CPNPP) - Request to Use Later Code Edition for Inservice Inspection (ISI) Program CP-202300391, (CPNPP) - Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2023-08-24024 August 2023 (CPNPP) - Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule CP-202300411, (Cpnpp), Inservice Inspection (ISI) Owner'S Activity Reports (OAR-1 Forms) for Unit 2 Refueling Outage 20 (2RF20)2023-08-17017 August 2023 (Cpnpp), Inservice Inspection (ISI) Owner'S Activity Reports (OAR-1 Forms) for Unit 2 Refueling Outage 20 (2RF20) CP-202300361, (CPNPP) - Unit 2 Refueling Outage 20 (2RF20) Steam Generator 180 Day Report2023-08-17017 August 2023 (CPNPP) - Unit 2 Refueling Outage 20 (2RF20) Steam Generator 180 Day Report CP-202300401, 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 0182023-08-15015 August 2023 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 018 CP-202300358, (Cpnpp), Transmittal of Electronic Licensing Basis Documents Including Certified FSAR Amendment 1122023-08-0101 August 2023 (Cpnpp), Transmittal of Electronic Licensing Basis Documents Including Certified FSAR Amendment 112 CP-202300322, Response to Requests for Additional Information Regarding Review of the License Renewal Application Sets 2 and 32023-07-27027 July 2023 Response to Requests for Additional Information Regarding Review of the License Renewal Application Sets 2 and 3 CP-202300348, (Cpnpp), Transmittal of Revised Emergency Plan (Revision 48)2023-07-18018 July 2023 (Cpnpp), Transmittal of Revised Emergency Plan (Revision 48) CP-202300285, Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 12023-07-12012 July 2023 Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 1 CP-202300262, Response to Request for Confirmation of Information Regarding Review of the License Renewal Application - Set 22023-06-20020 June 2023 Response to Request for Confirmation of Information Regarding Review of the License Renewal Application - Set 2 CP-202300263, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-06-15015 June 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202300248, Response to Request for Additional Information Regarding License Renewal Application - Set 12023-06-13013 June 2023 Response to Request for Additional Information Regarding License Renewal Application - Set 1 CP-202300209, Response to Request for Additional Information - License Renewal Application Environmental Review2023-06-0606 June 2023 Response to Request for Additional Information - License Renewal Application Environmental Review CP-202300207, Revision to Comanche Peak Nuclear Power Plant'S Response to Notice of Violation (NOV) 05000445/2021011-052023-05-25025 May 2023 Revision to Comanche Peak Nuclear Power Plant'S Response to Notice of Violation (NOV) 05000445/2021011-05 CP-202300182, Response to Requests for Confirmation of Information Regarding the Environmental Review of the License Renewal Application2023-05-0808 May 2023 Response to Requests for Confirmation of Information Regarding the Environmental Review of the License Renewal Application CP-202300201, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 0)2023-05-0404 May 2023 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 0) CP-202300160, (Cpnpp), 2022 Annual Radiological Environmental Operating Report2023-04-27027 April 2023 (Cpnpp), 2022 Annual Radiological Environmental Operating Report CP-202300159, (Cpnpp), 2022 Annual Radiological Effluent Release Report2023-04-27027 April 2023 (Cpnpp), 2022 Annual Radiological Effluent Release Report 2024-09-12
[Table view] |
Text
Rafael Flores Luminant Power Senior Vice President P 0 Box 1002
& Chief Nuclear Officer 6322 North FM 56 rafael.flores@Luminant.com Glen Rose, TX 76043 Luminant T 254 897 5590 C 817 559 0403 F 254 897 6652 REF: GL 2004-02 CP-201301214 TXX-13149 October 31, 2013 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT (CPNPP)
DOCKET NOS. 50-445 AND 50-446 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING CLOSURE OPTIONS FOR GENERIC SAFETY ISSUE 191 (TAC NOS. MC4676 AND MC4677)
REFERENCE:
- 1. Letter logged TXX-13091, dated May 16, 2013, from Rafael Flores of Luminant Power to Balwant Singal of the NRC, RE: Closure OPTIONS FOR GENERIC SAFETY ISSUE 191 (GSI-191), ASSESSMENT OF DEBRIS ACCUMULATION ON PRESSURIZED WATER REACTOR SUMP PERFORMANCE, (ML13149A101)
- 2. Letter dated September 30, 2013, from Balwant Singal of the NRC to Rafael Flores of Luminant Power, RE: Comanche Peak Nuclear Power Plant, Units I and 2 - Request for Additional Information Regarding Closure Options for Generic Safety Issue 191, ASSESSMENT OF DEBRIS ACCUMULATION ON PRESSURIZED-WATER REACTOR SUMP PERFORMANCE (ML13267A197)
Dear Sir or Madam:
In Reference 1, Luminant Generation Company LLC (Luminant Power) provided the U.S. Nuclear Regulatory Commission (NRC) staff with the intended path forward for the resolution of Generic Safety Issue (GSI)-191, "Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance,"
for Comanche Peak Nuclear Power Plant, Units 1 and 2 (CPNPP). Luminant Power identified that CPNPP will follow Option 2a (defined as deterministic approach with additional modeling refinements in SECY-12-0093).
A member of the STARS Alliance Callaway
- Diablo Canyon - Palo Verde
U. S. Nuctear Regulatory Commission TXX-13149 Page 2 of 2 10/31/2013 In Reference 2, the NRC staff requested the following additional information to complete the review of Luminant Power's path forward for the resolution of GSI-191 for CPNPP:
- 1. Please provide the Westinghouse recommended mitigative measures deemed necessary for CPNPP, and if not yet implemented, the schedule for implementing the Westinghouse recommendations.
- 2. Please provide the details of actions performed by EOPs FRC-0-1A, FRC-0.1B, FRC-0.2A, and FRC-0.2B to deal with inadequate core cooling.
The attachment to this letter provides the requested information.
This communication contains no new commitments regarding CPNPP Units 1 and 2.
Should you have any questions, please contact Mr. J. D. Seawright at (254) 897-0140.
I state under penalty of perjury that the foregoing is true and correct.
Executed on October 31, 2013.
Sincerely, Luminant Generation Company LLC Rafael Flores By:
Thomas P. McCool Vice President, Station Support Attachment c- Marc L. Dapas, Region IV Balwant K. Singal, NRR Resident Inspectors, Comanche Peak
Attachment to TXX-13149 Page 1 of 2 NRC Request No. 1.
Please provide the Westinghouse recommended mitigative measures deemed necessary for CPNPP, and if not yet implemented, the schedule for implementing the Westinghouse recommendations.
CPNPP Response:
Westinghouse and the PWR Owners Group recommended (Ref. Direct Work Requests DW-01-017 dated 02/20/2008 and DW-12-13 dated 03/20/2013) that the following changes be made to generic Emergency Operating Procedures.
- ES-1.3, Loss of Reactor or Secondary Coolant (CPNPP EOS-1.3A for Unit 1 and CPNPP EOS-1.3B for Unit 2)
Westinghouse recommended that the following be added to the PLANT-SPECIFIC INFORMATION section of the Step Description Table for Step 6 (Step 7 LP) of ES-1.3:
"Some plants may be susceptible to blockage in the fuel assemblies due to debris passing through the sump screen. Plants can assess the impact of debris on equipment required by the ECCS and NSSS to maintain the core in a coolable geometry following an accident using WCAP-16406-P, Rev. 1, "Evaluation of Downstream Sump Debris Effects in Support of GSI-191". Susceptible plants should evaluate the use of available temperature monitoring (core exit thermocouples or PAMS) to initiate backflow through the core via hot leg recirculation on a potentially more frequent basis to ensure adequate core cooling. An analysis may be needed to determine the frequency of switching to and from hot-leg injection to satisfy core blockage requirements while addressing boron precipitation concerns."
The corresponding step in the CPNPP procedures (step 14) determines if transfer to hot leg recirculation will be required. The plant staff is consulted for this determination. In accordance with the generic recommendation, this guidance was added to the Plant Staff Document for use by the Emergency Response Organization.
" FR.C.1 Response to Inadequate Core Cooling (CPNPP FRC-0-1A for Unit 1 and CPNPP FRC-0.1B for Unit 2) and FR.C.2 Response to Degrade Core Cooling (CPNPP FRC-0.2A for Unit 1 and CPNPP FRC-0.2B for Unit 2)
Westinghouse recommended that the following be added to the PLANT-SPECIFIC INFORMATION section of the Step Description Table for Step 2 (HP and LP) of FR-C. 1 and Step 2 (HP and LP) of FR-C.2:
"Some plants may be susceptible to blockage in the fuel assemblies due to debris passing through the sump screen. Plants can assess the impact of debris on equipment required by the ECCS and NSSS to maintain the core in a coolable geometry following an accident using WCAP-16406-P, Rev. 1, "Evaluation of Downstream Sump Debris Effects in Support of GSI-191". During the recovery, if SI flow is indicated and core cooling remains inadequate, SI flow may not be reaching the core due to blockage. It may be possible to restore adequate core cooling by initiating backflow through the core via hot leg recirculation."
These changes to CPNPP procedures have been implemented by incorporation into the bases for the corresponding step in CPNPP procedures (step 3) and by changes to the Plant Staff Document for use by the Emergency Response Organization.
Attachment to TXX-13149 Page 2 of 2 Westinghouse also recommended procedure changes for plants that use a Westinghouse-designed reactor vessel level indication system. These do not apply to the CPNPP Reactor Vessel Water Level Indication System (RVLIS) design which employs heated and unheated junction thermocouples as described in the CPNPP FSAR TMI RESPONSE TO NRC ACTION PLAN DEVELOPED AS A RESULT OF THE TMI-2 ACCIDENT,Section II.F.2 IDENTIFICATION OF AND RECOVERY FROM CONDITIONS LEADING TO INADEQUATE CORE COOLING.
NRC Request No. 2.
Please provide the details of actions performed by EOPs FRC-0-1A, FRC-0.1B, FRC-0.2A, and FRC-0.2B to deal with inadequate core cooling.
CPNPP Response:
CPNPP FRC-0-1A for Unit 1 and CPNPP FRC-0.1B for Unit 2 are titled Response to Inadequate Core Cooling. This procedure is entered from Critical Safety Function CORE COOLING Status Tree when Core Exit Temperature (CET) is greater than or equal to 1200 degrees F.
CPNPP FRC-0.2A for Unit 1 and CPNPP FRC-0.2B for Unit 2 are titled Response to Degrade Core Cooling. This procedure is entered from Critical Safety Function CORE COOLING Status Tree when RCS subcooling is inadequate, Reactor Vessel Water Level Indication System (RVLIS) indicates low level in the vessel and Core Exit Temperature (CET) is greater than or equal to 750 degrees F.
Both procedures are based on assuring emergency core cooling to the reactor vessel. None of the steps in the original generic or plant specific guidance dealt with core blockage. There are no actions to be taken for core blockage other than switchover from cold leg recirculation to hot leg recirculation and back. Therefore, the guidance added is to contact the Plant Staff for specific guidance.
The Shift Technical Advisors (STAs) and/or the Technical Support Center (TSC) engineers would monitor plant conditions and advise the control room operators regarding switchover from Cold Leg Recirculation to Hot Leg Recirculation and back.