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MONTHYEARML12251A1222012-09-0707 September 2012 Acceptance Review E-mail - Relief Request C-2 for the Reactor Pressure Vessel Leak-Off Flange, Third 10-Year Inservice Inspection Interval Project stage: Acceptance Review ML12345A1882012-12-10010 December 2012 Request for Additional Information E-mail - Relief Request C-2 for the Reactor Pressure Vessel Leak-Off Flange, Third 10-Year Inservice Inspection Interval Project stage: RAI ML13025A2612013-01-0909 January 2013 Enclosure to TXX-13003 Drawings for Response to RAI Question 2 Project stage: Response to RAI CP-201300002, Response to Request for Additional Information for Unit 1 Relief Request No. C-22013-01-0909 January 2013 Response to Request for Additional Information for Unit 1 Relief Request No. C-2 Project stage: Response to RAI ML13046A3852013-03-19019 March 2013 Relief Request C-2 for the Reactor Pressure Vessel Flange Leak-Off Piping, Third 10-Year Inservice Inspection Interval Project stage: Other CP-201301199, Relief Request No. C-3 for the Unit 2 Reactor Pressure Vessel leak-off Flange (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End Date: August 2, 20142013-10-31031 October 2013 Relief Request No. C-3 for the Unit 2 Reactor Pressure Vessel leak-off Flange (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End Date: August 2, 2014 Project stage: Request ML13350A6302013-12-16016 December 2013 NRR E-mail Capture - Acceptance Review for Relief Request C-3 for Comanche Peak Unit 2, - TAC No. MF2997 Project stage: Acceptance Review ML14007A0002014-01-0303 January 2014 NRR E-mail Capture - Request for Additional Information (RAI) - Relief Request (RR) C-3 - TAC No. MF2997 Project stage: RAI CP-201400070, Response to Request for Additional Information for Relief Request No. C-3 for Unit 2 Reactor Pressure Vessel Leak-off Flange (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End Date August 2, 2014)2014-01-23023 January 2014 Response to Request for Additional Information for Relief Request No. C-3 for Unit 2 Reactor Pressure Vessel Leak-off Flange (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End Date August 2, 2014) Project stage: Response to RAI ML14030A4662014-01-30030 January 2014 NRR E-mail Capture - Follow-up Request for Additional Information for Relief Request C-3 - TAC MF2997 Project stage: RAI CP-201400144, Clarification to Response to Request for Additional Information for Relief Request No. C-3 for Unit 2 Reactor Pressure Vessel Leak-Off Flange (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End.2014-02-11011 February 2014 Clarification to Response to Request for Additional Information for Relief Request No. C-3 for Unit 2 Reactor Pressure Vessel Leak-Off Flange (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End. Project stage: Supplement ML14084A2912014-04-0404 April 2014 Relief Request No. C-3 for Reactor Pressure Vessel Leak-Off Flange for the Second 10-Year Inservice Inspection Interval Project stage: Other CP-201500157, Relief Request No. 2C3-1 for the Reactor Pressure Vessel Leak-Off Flange (Third ISI Interval Start Date: August 3, 2014; Third ISI Interval End Date: August 2, 2023)2015-02-24024 February 2015 Relief Request No. 2C3-1 for the Reactor Pressure Vessel Leak-Off Flange (Third ISI Interval Start Date: August 3, 2014; Third ISI Interval End Date: August 2, 2023) Project stage: Request 2013-03-19
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Category:Letter type:CP
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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-202300159, (Cpnpp), 2022 Annual Radiological Effluent Release Report2023-04-27027 April 2023 (Cpnpp), 2022 Annual Radiological Effluent Release Report CP-202300160, (Cpnpp), 2022 Annual Radiological Environmental Operating Report2023-04-27027 April 2023 (Cpnpp), 2022 Annual Radiological Environmental Operating Report CP-202300165, License Renewal Application Revision 0 - Supplement 22023-04-24024 April 2023 License Renewal Application Revision 0 - Supplement 2 CP-202300096, License Amendment Request (LAR) 23-002 Application Regarding GDC-5 Shared Systems Requirements2023-04-20020 April 2023 License Amendment Request (LAR) 23-002 Application Regarding GDC-5 Shared Systems Requirements CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments CP-202300175, Submittal of 2022 Annual Environmental Operating Report (Non-Radiological)2023-04-20020 April 2023 Submittal of 2022 Annual Environmental Operating Report (Non-Radiological) CP-202300140, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. LAR 23-0012023-04-19019 April 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. LAR 23-001 2024-08-05
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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 Lum inant 2548975590 C 817 559 0403 F 254 897 6652 CP-201400144 Ref. # 10CFR50.55a(a)(3)(ii)
TXX-14020 February 11, 2014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NO. 50-446 CLARIFICATION TO RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST NO. C-3 FOR THE UNIT 2 REACTOR PRESSURE VESSEL LEAK-OFF FLANGE (SECOND ISI INTERVAL START DATE: AUGUST 3,2004; SECOND ISI INTERVAL END DATE: AUGUST 2,2014)(TAC NO. MF2997)
REFERENCES:
- 1. Letter logged TXX-13145 dated October 31, 2013, from Rafael Flores to the NRC submitting Relief Request No. C-3 for the Unit 2 Reactor Pressure Vessel Leak-Off Flange (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End Date:
August 2, 2014)
- 2. Letter logged TXX-14004 dated January 23, 2014, from Rafael Flores to the NRC responding to Requests for Additional Information for Unit 2 Relief Request C-3
- 3. Phone conversation dated January 28, 2014, between the NRC and Luminant Power discussing response to Requests for Additional Information for Unit 2 Relief Request C-3 (TAC No. MF2997)
- 4. Email dated January 30, 2014, from Balwant Singal of NRR to Tim Hope of Luminant Power providing Follow-up Requests for Additional Information for Unit 2 Relief Request C-3 (TAC No. MF2997)
Dear Sir or Madam:
Pursuant to 10 CFR 50.55a(a)(3)(ii), Luminant Generation Company LLC (Luminant Power) submitted Relief Request C-3 for Comanche Peak Nuclear Power Plant (CPNPP) Unit 2 for the second ten year inservice inspection interval via Reference 1. Per Reference 2, Lunminant Power provided the NRC with a response to a request for additional information (RAI) regarding the subject relief request. During a phone conversation between Luminant Power and the NRC, Reference 3, Luminant Power discussed clarifications to the response to RAIs. Per Reference 4, the NRC provided follow-up questions regarding the CPNPP Unit 2 relief request C-3. Luminant Power's clarifications and follow-up responses are provided in the attachment to this letter.
A member of the STARS Alliance YkLA"l Callaway
U. S. Nuclear Regulatory Commission TXX-14020 Page 2 of 2 02/11/2014 This communication contains no new commitments regarding CPNPP Unit 2.
Should you have any questions, please contact Mr. Jack Hicks at (254) 897-6725.
Sincerely, Luminant Generation Company LLC Rafael Flores By: A14. 242d r*W*. Madden Director, External Affairs
Attachment:
Comanche Peak Nuclear Power Plant Unit 2 Clarifications to the Response to Request for Information Regarding Relief C-3 for the Reactor Pressure Vessel Leak-Off Flange (Second 10-Year ISI Interval Start Date: August 3, 2004) c- Marc L. Dapas, Region IV Balwant K. Singal, NRR Resident Inspectors, Comanche Peak Jack Ballard, ANII, Comanche Peak Robert Free Environmental Monitoring & Emergency Response Manager Texas Department of State Health Services Mail Code 1986 P.O. Box 149347 Austin, TX 78714-9347
Attachment to TXX-14020 Page I of 2 COMANCHE PEAK NUCLEAR POWER PLANT UNIT 2 Clarifications to the Response to Request for Information Regarding Relief C-3 for the Reactor Pressure Vessel Leak-Off Flange (Second 10-Year ISI Interval Start Date: August 3, 2004)
NRC's Request 1 For Follow-Up Information:
- 1. Section 5 "Burden Caused by Compliance" and Section 6 "Proposed Alternative and Basis for Use" of Attachment 1 of RR C-3 stated, in part, Therefore, compliance with the IWC-5220 system leakage test requirements results in an unnecessary hardship without a sufficient compensating increase in the level of quality and safety.
In lieu of the requirements of IWC-5220, a VT-2 visual examination of the accessible areas will be performed each period on the piping subjected to the static pressure head when the reactor cavity is filled. This test will be part of the reactor coolant Class 2 leakage test.
The NRC staff notes that the ASME Code,Section XI, IWC-5220 "System Leakage Testing" includes two sub-articles, IWC-5221 "Pressure" and IWC-5222 "Boundaries." (a) Please clarify whether the proposed system leakage test was submitted as an alternative to address only the pressure requirement as specified in IWC-5221. (b) IWC-5222(a) and (b) require specific pressure boundaries for the system pressure tests. The NRC staff notes that the licensee's submittal did not address the requirements of IWC-5222(a) and (b). If IWC-5222(a) and IWC-5222 (b) are also the subject of this RR, please discuss the hardship caused by compliance with IWC-5222(a) and 1WC-5222(b), and provide corresponding alternatives.
Luminant Power's Response to Follow-Up Request 1:
Luminant Power did not seek relief from Subsubarticle IWC-5220, which includes Paragraphs IWC-5221 and IWC-5222. The relief request was for Paragraph IWC-5221, which requires that the system leakage test be performed with lines pressurized to the system pressure prior to performing a VT-2 visual examination.
To provide clarification that the relief was sought for Paragraph IWC-5221, Section 5 "Burden Caused by Compliance" and Section 6 "Proposed Alternative and Basis for Use" of Attachment 1 of RR C-3 are repeated below with corrections:
- 5. Burden Caused by Compliance:
Purposely failing or not installing the inner O-ring in order to perform a pressure test would require purchasing a new O-ring set and the time and radiation exposure associated with removing and reinstalling the RPV head to replace the O-rings would be an undue hardship.
Therefore, compliance with the IWC-5221 system leakage test requirements results in an unnecessary hardship without a sufficient compensating increase in the level of quality and safety.
- 6. Proposed Alternative and Basis for Use:
In lieu of the requirements of IWC-5221, a VT-2 visual examination of the accessible areas will be performed each period on the piping subjected to the static pressure head when the reactor cavity is filled. This test will be part of the reactor coolant Class 2 leakage test.
Attachment to TXX-14020 Page 2 of 2 COMANCHE PEAK NUCLEAR POWER PLANT UNIT 2 Clarifications to the Response to Request for Information Regarding Relief C-3 for the Reactor Pressure Vessel Leak-Off Flange (Second 10-Year ISI Interval Start Date: August 3, 2004)
If the inner O-ring should leak during the operating cycle it will be identified by an increase in temperature of the leak-off line above ambient temperature. This high temperature would actuate an alarm in the Control Room, which would be closely monitored by procedurally controlled operator actions allowing identification of any further compensatory actions required.
This leakage would be collected in the Reactor Coolant Drain Tank.
Additionally, the flange seal leak-off line is essentially a leakage collection/detection system and the line would only function as a Class 2 pressure boundary if the inner O-ring fails, thereby pressurizing the line. If any significant leakage does occur in the leak-off line piping itself during this time of pressurization then it would clearly exhibit boric acid accumulation and be discernable during the proposed VT-2 visual examination that will be performed unpressurized as proposed in this request. The elevation of the Reactor Vessel flange is 834' 1/2". The elevation for the water level when the cavity is flooded is 858" 6". Therefore, the minimum pressure at the opening of the flange leak-off line when the exam is performed is 24' 5 1/2" of static pressure head or 10.6 psi.
There has been no known evidence of corrosion, stress corrosion cracking, or fatigue in the subject flange leak-off piping at CPNPP.
NRC's request 2 for follow-up Information:
2, Please discuss leakage detection capabilities at the plant, and or any measure(s) taken, to monitor and identify leakage in an unlikely event of a through wall leak in the RPV flange seal leak-off line piping concurrent with leak or failure of the RPV flange inner seal during normal operation.
Luminant Power's Response to Follow-Up Request 2:
During normal operation, the inner O-ring isolation valve is open. Should the inner O-ring leak, a high temperature alarm actuates at 140'F in the control room, informing the operator of the leak. The operator monitors reactor vessel flange leak-off temperature in accordance with CPNPP alarm procedures (ALM-053A for Unit 1 and ALM-053B for Unit 2) and closes the valve, isolating the leak. The procedure directs shutting the manual isolation valve and opening another valve, transferring RCS pressure boundary maintenance to the outer O-ring. Opening the valve then transfers leak detection to the outer O-ring. All drainage/leakage is piped to the reactor coolant drain tank. The procedure also addresses notifying chemistry department to increase monitoring of containment atmosphere to detect possible outer O-ring failure; perform an operations test to determine leakage rate as applicable; and initiating corrective action documents to identify the condition and correct the condition as applicable.