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| * South Texas Project -Wolf Creek U. S. Nuclear Regulatory Commission TXX-12014 Page 2 of 2 Sincerely, Luminant Generation Company LLC Rafael Flores By: &A7,..L, Director, Oversight | | * South Texas Project -Wolf Creek U. S. Nuclear Regulatory Commission TXX-12014 Page 2 of 2 Sincerely, Luminant Generation Company LLC Rafael Flores By: &A7,..L, Director, Oversight |
| & Regulatory Affairs Attachment Response to Request for Additional Information for Relief Request A-1 c -E. E. Collins, Region IV B. K. Singal, NRR Resident Inspectors, Comanche Peak Jack Ballard, ANII, Comanche Peak Luis Ponce Environmental | | & Regulatory Affairs Attachment Response to Request for Additional Information for Relief Request A-1 c -E. E. Collins, Region IV B. K. Singal, NRR Resident Inspectors, Comanche Peak Jack Ballard, ANII, Comanche Peak Luis Ponce Environmental |
| & Consumer Safety Section Texas Department of State Health Services 1100 West 49th Street Austin, Texas 78756-3189 Attachment to TXX-12014 Page 1 of 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST NUMBER A-1 FOR THE UNIT 1 THIRD 10 YEAR ISI INTERVAL (THIRD INTERVAL START DATE: AUGUST 13, 2010) (TAC NO. ME6827)The following questions were provided to Luminant Power in the email dated January 25, 2012, from Balwant Singal of the NRC to Timothy Hope of Luminant Power (reference | | & Consumer Safety Section Texas Department of State Health Services 1100 West 49th Street Austin, Texas 78756-3189 Attachment to TXX-12014 Page 1 of 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST NUMBER A-1 FOR THE UNIT 1 THIRD 10 YEAR ISI INTERVAL (THIRD INTERVAL START DATE: AUGUST 13, 2010) (TAC NO. ME6827)The following questions were provided to Luminant Power in the email dated January 25, 2012, from Balwant Singal of the NRC to Timothy Hope of Luminant Power (reference |
| : 2) requesting additional information regarding Relief Request Nos. A-i: NRC Question 1: The Luminant Generation Company LLC (Luminant, the licensee) used Electric Power Research Institute (EPRI) Topical Report (TR) 1018427 to address those supporting requirements significant to the PRA for risk-informed inservice inspections (RI-ISI). | | : 2) requesting additional information regarding Relief Request Nos. A-i: NRC Question 1: The Luminant Generation Company LLC (Luminant, the licensee) used Electric Power Research Institute (EPRI) Topical Report (TR) 1018427 to address those supporting requirements significant to the PRA for risk-informed inservice inspections (RI-ISI). |
| The NRC has endorsed TR 1021467 through a NRC safety evaluation (ADAMS Accession No. ML11262A206) for determining the technical adequacy of the PRA for RI-ISI. Please review your analysis and address any outstanding supporting requirements for this application by using guidance found in the safety evaluation that references EPRI TR 1021467.Luminant Power's Response to Question 1: Electric Power Research Institute (EPRI) Topical Report (TR) 1021467.was issued around the time of this submittal. | | The NRC has endorsed TR 1021467 through a NRC safety evaluation (ADAMS Accession No. ML11262A206) for determining the technical adequacy of the PRA for RI-ISI. Please review your analysis and address any outstanding supporting requirements for this application by using guidance found in the safety evaluation that references EPRI TR 1021467.Luminant Power's Response to Question 1: Electric Power Research Institute (EPRI) Topical Report (TR) 1021467.was issued around the time of this submittal. |
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MONTHYEARCP-201100356, Relief Request A-1 for Unit 1 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Class 1 and 2 Piping Welds (Third Interval....)2011-08-0202 August 2011 Relief Request A-1 for Unit 1 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Class 1 and 2 Piping Welds (Third Interval....) Project stage: Request ML1125003292011-09-0707 September 2011 Acceptance Review Email, Relief Request A-1 for Approval of Risk-Informed Alternative to ASME Code, Section XI for Class 1 and 2 Piping Welds, Third 10-Year Inservice Inspection Interval Project stage: Acceptance Review ML1202505432012-01-25025 January 2012 Email, Request for Additional Information Relief Request A-1 Project stage: RAI ML1202703642012-01-27027 January 2012 Correction to Email, Request for Additional Information, Relief Request A-1, Risk-Informed Alternative to Code Exam Requirements for Class 1 and 2 Piping Welds, Second 10-Year Inservice Inspection Interval Project stage: RAI CP-201200097, Response to Request for Additional Information for Relief Request No. A-12012-02-21021 February 2012 Response to Request for Additional Information for Relief Request No. A-1 Project stage: Response to RAI CP-201200157, Response to Request for Additional Information for Relief Request No. A-12012-03-0808 March 2012 Response to Request for Additional Information for Relief Request No. A-1 Project stage: Response to RAI CP-201200488, Response to Request for Additional Information for Relief Request No. A-I2012-06-0606 June 2012 Response to Request for Additional Information for Relief Request No. A-I Project stage: Response to RAI ML12194A2502012-08-14014 August 2012 Relief Request A-1 for Approval of Risk-Informed Alternative to ASME Code, Section XI for Class 1 and 2 Piping Welds, Third 10-Year Inservice Inspection Interval Project stage: Other 2012-01-27
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Category:Letter type:CP
MONTHYEARCP-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-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-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) - 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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-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 Lu i a tRafael.Flores@Luminant.com Glen Rose, TX 76043 Luminant 2548975550 C 817 559 0403 F 254 897 6652 CP-201200097 Ref. # 10CFR50.55a Log # TXX-12014 February 21, 2012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NO. 50-445 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST NO. A-1 (TAC NO. ME6827)
REFERENCES:
- 1. Letter logged TXX-11038 dated August 2, 2011 from Rafael Flores to the NRC submitting Relief Request No. A-1 for the Unit 1 Third Interval Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Class I and 2 Piping Welds (Third Interval Start Date: August 13, 2010).2. Email dated January 25, 2012 from Balwant Singal of the NRC to Timothy Hope of Luminant Power requesting additional information regarding Relief Request No. A-1 -TAC ME6827.
Dear Sir or Madam:
Per reference 1, Luminant Generation Company LLC (Luminant Power) previously submitted a request for relief for application of an alternative to the American Society of Mechanical Engineers (ASME)Boiler and Pressure Vessel Code Section XI examination requirements for Class 1 and 2 piping welds.Per reference 2, the NRC provided a request for additional information regarding the subject relief request.Luminant Power has provided the information requested per reference 2 in the attachment to this letter.This communication contains no new commitment regarding Comanche Peak Unit 1.Should you have any questions, please contact Mr. Jack Hicks at (254) 897-6725.A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak -Diablo Canyon
- South Texas Project -Wolf Creek U. S. Nuclear Regulatory Commission TXX-12014 Page 2 of 2 Sincerely, Luminant Generation Company LLC Rafael Flores By: &A7,..L, Director, Oversight
& Regulatory Affairs Attachment Response to Request for Additional Information for Relief Request A-1 c -E. E. Collins, Region IV B. K. Singal, NRR Resident Inspectors, Comanche Peak Jack Ballard, ANII, Comanche Peak Luis Ponce Environmental
& Consumer Safety Section Texas Department of State Health Services 1100 West 49th Street Austin, Texas 78756-3189 Attachment to TXX-12014 Page 1 of 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST NUMBER A-1 FOR THE UNIT 1 THIRD 10 YEAR ISI INTERVAL (THIRD INTERVAL START DATE: AUGUST 13, 2010) (TAC NO. ME6827)The following questions were provided to Luminant Power in the email dated January 25, 2012, from Balwant Singal of the NRC to Timothy Hope of Luminant Power (reference
- 2) requesting additional information regarding Relief Request Nos. A-i: NRC Question 1: The Luminant Generation Company LLC (Luminant, the licensee) used Electric Power Research Institute (EPRI) Topical Report (TR) 1018427 to address those supporting requirements significant to the PRA for risk-informed inservice inspections (RI-ISI).
The NRC has endorsed TR 1021467 through a NRC safety evaluation (ADAMS Accession No. ML11262A206) for determining the technical adequacy of the PRA for RI-ISI. Please review your analysis and address any outstanding supporting requirements for this application by using guidance found in the safety evaluation that references EPRI TR 1021467.Luminant Power's Response to Question 1: Electric Power Research Institute (EPRI) Topical Report (TR) 1021467.was issued around the time of this submittal.
An earlier document, TR 1018427 was used in preparation of the submittal to address supporting requirements.
A comparison was performed of these two documents with.regards to Capability Category guidance (EPRI Traditional RI-ISI -Table 2.1 and 2.2 of each document).
The only difference that was identified between the two documents was the removal of Internal Flooding (IF), supporting requirements from the later EPRI document -TR 1021467.The NRC staff has reviewed EPRI TR 1021467 and concludes that the TR, as modified by the conditions and limitations and applicant/licensee action items summarized in Section 4.0 of this Safety Evaluation (SE), provides reasonable assurance that the PRA has sufficient quality to support the development of 'an, RI-ISI program. These conditions and limitations can be placed into two groupings, the first was a .revised justification for a lower capability category (CCI or "not-met" assignment) and the second was an increase in two SR's capability categories (CCII from CCI). A review of the NRC Safety Evaluation Report (SE for TR 1021467 dated 9-30-11 ML11262A206) attachment 1, table I identified SR AS-A9 and SC-B2 as those whose category had changed (increased).
The CPNPP PRA model self assessment of these supporting requirements indicates that they met or exceed capability category II; no gap identified.
The revised justification discussed in the SE and table 1 for the remainder of the SRs did not impact the capability category of those SRs.Therefore, there are no additional outstanding supporting requirements for this application in the reference EPRI TR 1021467 as modified by the NRC's safety evaluation.
Attachment to TXX-12014 Page 2 of 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR RELIEF REQUEST NUMBER A-1 FOR THE UNIT 1 THIRD 10 YEAR ISI INTERVAL (THIRD INTERVAL START DATE: AUGUST 13, 2010) (TAC NO. ME6827)NRC Question 2: The licensee noted that two supporting requirements (SY-A22 and DA-C15) of the American Society of Mechanical Engineers (ASME) standard (ASME RA-Sb-2005) as provided by PRA technical adequacy guidance in EPRI TR 1018427 are related to the use of hardware fault recovery.
DA-C15 and SY-A22 are not related in this standard.
In ASME RA-Sb-2005, DA-C15 pertains to data on recovery of plant-specific initiating events while SY-A22 addresses repair of hardware faults. Please provide additional justification that disposition DA-C15 for this application.
Luminant Power's Response to Question 2: We agree that the two supporting requirements (SR) are not related. The gap identified in the submittal relates to SY-A22 and should not have been tied to SR DA-C15. The ASME standard ties SR DA-C14 to SY-A22 and the table in the submittal should have reflected that relationship.
Both of these SRs, SY-A22 and DA-C14, relate to modeling of repair of hardware faults and its justification.
The CPNPP assessment identified these SRs as "not-met".
Recovery of failures other than offsite power is not generally accepted or supported by data. Further it identified that CPNPP had not collected and analyzed plant specific data associated with the recovery of hardware faults. 'The sensitivity study provided inthe submittal for SY- .A22 (Appendix 1, table item #1) anddits~conclusion provide the justification for use of the PRA model for this.application; (with respect to SRs SY-A22 and.DA-C14)_and no additional information is required.DA-C15 supporting requirement should have read:as found to be met; no, gap identified (spans all'three capability categories).
The basis for meeting the SR is that plant specific recovery data was used, in developing.
the probability of -the mean time to repair (MTTR). factor applied to the.CCW, CH, ahd,SW,,'.
i SSIE models. The. MTTR was;calculated based on~repair time, information for components in the three system initiator trees based on a review of maintenance rule-data.
This recovery was used to account for -.!* the probability that a failed component in one train could be repaired before a component in the other:.train of the samesystem failed. ..