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Category:E-Mail
MONTHYEARML24025A0172024-01-22022 January 2024 NRC Request for Concurrence with Endangered Species Act Determinations for Comanche Peak License Renewal, Issuance of Draft Supplemental Environmental Impact Statement, and Opportunity for Public Comment ML24019A0742024-01-19019 January 2024 NRR E-mail Capture - Comanche Peak - Draft Request for Additional Information - License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24008A2492023-12-18018 December 2023 Texas Shpo Response for Comanche Peak Deis Review and Comment ML23311A2202023-11-20020 November 2023 NRC to Fws, NRC Request for Concurrence with Endangered Species Act Determinations for Comanche Peak License Renewal, Issuance of Draft Supplemental Environmental Impact Statement, and Opportunity for Public Comment (Consultation Code: 2023 ML23255A2882023-09-12012 September 2023 NRR E-mail Capture - Comanche Peak - Acceptance of Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule ML23256A1492023-09-11011 September 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 4 ML23226A0072023-08-11011 August 2023 NRR E-mail Capture - Comanche Peak 1 and 2 Audit Plan - License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML23188A0442023-07-0707 July 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 3 ML23181A0722023-06-29029 June 2023 NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML23181A0202023-06-29029 June 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 2 ML23172A0152023-06-20020 June 2023 NRR E-mail Capture - Re Comanche Peak - Acceptance of License Amendment Request Regarding General Design Criterion 5 of Appendix a to 10 CFR Part 50 and Regulatory Guide 1.81 ML23167A0222023-06-14014 June 2023 Email: Request for Additional Information (RAI) Letter for the Review of the Comanche Peak Initial License Renewal Application, Set 1 ML23145A2332023-05-25025 May 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Confirmation of Information - Set 2 ML23143A1382023-05-23023 May 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Confirmation of Information - Set 1 ML23139A0802023-05-18018 May 2023 NRR E-mail Capture - Comanche Peak Draft Supplemental Information Request - License Amendment Request Regarding General Design Criterion 5 of Appendix a to 10 CFR Part 50 and Regulatory Guide 1.81 ML23138A1522023-05-18018 May 2023 Lr Docs - (External_Sender) Comanche Peak Nuclear Power Plants ML23135A9132023-05-15015 May 2023 NRR E-mail Capture - Comanche Peak - Draft Supplemental Information Request - License Amendment Request to 10 CFR 50.69 ML23131A2932023-05-11011 May 2023 Lr Docs - License Renewal for Comanche Peak Nuclear Power Plant, Units 1 and 2 ML23128A1612023-05-0808 May 2023 NRR E-mail Capture - Comanche Peak Nuclear Power Plant, Units 1 and 2, Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit No. 1 - Acceptance of Requested Licensing ML23110A7122023-04-20020 April 2023 NRR E-mail Capture - Comanche Peak - Verbal Authorization of Proposed Alternative RV-1 (L-2023-LLR-0019) ML23103A4682023-04-11011 April 2023 NRR E-mail Capture - Comanche Peak Request for Additional Information - License Amendment Request to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model ML23086B9852023-03-27027 March 2023 NRR E-mail Capture - Comanche Peak Draft Request for Additional Information - Request to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model ML23061A1612023-03-0202 March 2023 E-mail from David Griggs Regarding Submission to NRC Electronic Information Exchange on 03/01/2023 for Citizens for Fair Utility Regulation in Comanche Peak Proceeding ML23032A3842023-02-0101 February 2023 LRA On-Site Audit Needs List ML23214A0192023-01-30030 January 2023 (External_Sender) Request to Broaden Extended Deadline to the General Public (with Attachments) - C3 ML23214A0202023-01-29029 January 2023 (External_Sender) Requesting a Deadline Extension on NRC-2002-0183, Comanche Peak License Renewal - C2 ML23214A0182023-01-26026 January 2023 (External Sender) NRC-2022-0183-0003 (with Attachment) - C6 ML23214A0162023-01-24024 January 2023 (External Sender) EPA Scoping Comment Letter for the Comanche Peak Nuclear Power Plant License Renewal (with Attachment) - C8 ML23214A0142023-01-23023 January 2023 (External Sender) Docket NRC-2022-0183 Comanche Peak Nuclear Power Plant Renewal (with Attachment) - C1 ML23214A0172023-01-17017 January 2023 (External Sender) NRC License Extension? No! ML23214A0132023-01-17017 January 2023 (External Sender) Docket Id NRC-2022-0183, Request for Extension of License for Comanche Peak, Comment for Environmental Scoping - C9 ML23214A0122023-01-13013 January 2023 (External Sender) Correction to Comment Submitted 01-13-23 - C11 ML22362A0992022-12-28028 December 2022 NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request to Apply Westinghouse Fsloca Evaluation Model ML22362A0972022-12-28028 December 2022 NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request to Adopt WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications, ML22325A2742022-11-21021 November 2022 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps ML22318A3102022-11-10010 November 2022 NRR E-mail Capture - Comanche Peak - Draft Request for Additional Information - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps ML22237A2842022-08-25025 August 2022 CPNPP 2022 EP Program Inspection RFI Hjs 08252022 ML22230B1092022-08-17017 August 2022 NRR E-mail Capture - Comanche Peak Unit 2 - Request for Additional Information - 2RE19 Inspection Summary Report for Steam Generator Tubing ML22229A0792022-08-17017 August 2022 NRR E-mail Capture - Comanche Peak - Acceptance of Requested Licensing Action - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps ML22220A1942022-08-0808 August 2022 NRR E-mail Capture - Comanche Peak Unit 2 - Draft Request for Additional Information - 2RE19 Inspection Summary Report for Steam Generator Tubing ML22133A0472022-05-13013 May 2022 July 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22083A0262022-03-23023 March 2022 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Request to Adopt TSTF 505 Revision 2 ML22031A2122022-01-31031 January 2022 NRR E-mail Capture - Comanche Peak - Acceptance of Requested Licensing Action - Proposed Alternative to Extend the Snubber Inservice Program Third Interval ML21300A1342021-10-27027 October 2021 NRR E-mail Capture - Comanche Peak Units 1 and 2 - License Amendment Request to Adopt TSTF-505 - Audit Plan Update and Audit Questions (L-2021-LLA-0085) ML21286A7912021-10-13013 October 2021 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Request to Adopt TSTF-577 Revision 1 ML21272A2002021-09-29029 September 2021 NRR E-mail Capture - Comanche Peak Unit 2 - Upcoming Steam Generator Tube Inservice Inspection (L-2021-NFO-0013) ML21270A1632021-09-27027 September 2021 NRR E-mail Capture - Comanche Peak - Acceptance of Quality Assurance Program Change Request Regarding Internal Audit Frequency ML21253A2242021-09-0909 September 2021 Request for Information Occupational Radiation Safety Inspection (71124.01, 71124.02, and 71151) from 10/18-22/2021 ML21252A0062021-08-26026 August 2021 NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections 2024-01-22
[Table view] Category:Letter
MONTHYEARCP-202400030, License Renewal Application Revision 0 - Supplement 3, Revision 12024-01-31031 January 2024 License Renewal Application Revision 0 - Supplement 3, Revision 1 IR 05000445/20230042024-01-29029 January 2024 Integrated Inspection Report 05000445/2023004 and 05000446/2023004 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) ML24024A2102024-01-29029 January 2024 Summary of Regulatory Audit Regarding a License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24025A0052024-01-25025 January 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report ML24023A0242024-01-24024 January 2024 Correction to Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident Methodology ML24018A1072024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000445/2024012 and 05000446/2024012) and Request for Information ML23159A2082023-12-20020 December 2023 Request for Withholding Information from Public Disclosure ML23319A3872023-12-20020 December 2023 Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology ML23348A2392023-12-19019 December 2023 Nonacceptance of License Amendment Request to Relocate Technical Specification 3.9.3, Nuclear Instrumentation, to the Technical Requirements Manual 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 ML23333A0872023-12-13013 December 2023 Transmittal of Dam Safety Inspection Report - Public 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 ML23313A0732023-12-0606 December 2023 Issuance of Amendment Nos. 184 and 184 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Rev. 1, Improved Roac and CAOC Fq Surveillance Technical Specifications ML23291A4382023-11-30030 November 2023 Notice of Availability of the Draft Plant-Specific Supplement 60, to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Comanche Peak Nuclear Power Plant, Unit Numbers 1 and 2, License Renewal Applica ML23325A0182023-11-30030 November 2023 Schedule Revision for the License Renewal Application Review IR 05000445/20234022023-11-30030 November 2023 NRC Security Inspection Report 05000445/2023402 and 05000446/2023402 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 ML23308A0032023-11-17017 November 2023 Letter to R. Nelson, Executive Director; Achp; Re., Comanche Peak Draft Environmental Impact Statement ML23308A0022023-11-17017 November 2023 Letter to M. Wolfe, Executive Director; Shpo; Re., Comanche Peak Draft Environmental Impact Statement ML23317A3002023-11-13013 November 2023 Letter to R. Sylestine, Chairman, Alabama-Coushatta Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2972023-11-13013 November 2023 Letter to R. Martin, President, Tonkawa Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2872023-11-13013 November 2023 Letter to J. Garza, Chairman, Kickapoo Traditional Tribe of Texas Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2832023-11-13013 November 2023 Letter to D. Dotson, President, Delaware Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2852023-11-13013 November 2023 Letter to E. Martinez, President, Mescalero Apache Tribe Regarding Comanche Peak Draft Environmental Impact Statement ML23306A0302023-11-13013 November 2023 Letter to J. Cernek, Chairman; Coushatta Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2902023-11-13013 November 2023 Letter to M. Pierite, Chairman, Tunica Biloxi Tribe of Louisiana Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2982023-11-13013 November 2023 Letter to R. Morrow, Town King, Thlopthlocco Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2842023-11-13013 November 2023 Letter to D. Kaskaske, Chairman, Kickapoo Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2822023-11-13013 November 2023 Letter to D. Cooper, Chairman, Apache Tribe of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2962023-11-13013 November 2023 Letter to M. Woommavovah, Chairman, Comanche Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2812023-11-13013 November 2023 Letter to C. Hoskin, Principal Chief, Cherokee Nation; Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2862023-11-13013 November 2023 Letter to J. Bunch, Chief, United Keetoowah Band of Cherokee Indians Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3032023-11-13013 November 2023 Letter to W. Yargee, Chief, Alabama-Quassarte Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2882023-11-13013 November 2023 Letter to L. Johnson, Chief, Seminole Nation of Oklahoma Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3012023-11-13013 November 2023 Letter to S. Yahola, Mekko, Kialegee Tribal Town Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2792023-11-13013 November 2023 Letter to B. Gonzalez, Chairman, Caddo Nation Regarding Comanche Peak Draft Environmental Impact Statement ML23317A3022023-11-13013 November 2023 Letter to T. Parton, President, Wichita and Affiliated Tribes Regarding Comanche Peak Draft Environmental Impact Statement ML23317A2892023-11-13013 November 2023 Letter to L. Spottedbird, Chairman, Kiowa Indian Tribe Regarding Comanche Peak Draft Environmental Impact Statement ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23360A6312023-10-26026 October 2023 FEMA, Submittal of Radiological Emergency Preparedness Final Report for the Comanche Peak Nuclear Power Plant Medical Services Drill Evaluated on August 23, 2023 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 ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23263A0242023-09-21021 September 2023 Revision of Schedule for the Environmental Review of the Comanche Peak Nuclear Power Plant Units 1 and 2 License Renewal Application 2024-01-31
[Table view] |
Text
C:\WINDOWS\TEMP\GW}O000 .TMP Page 1 Mail Envelope Properties (3CB43A9B.ACB : 8: 39627)
Subject:
Draft RAI Response for LAR 01-008 Creation Date: 4/10/02 9:14AM From: <rsloughl @txu.com>
Created By: rsloughl@txu.com Recipients nrc.gov owf4_po.OWFN_DO DHJ (David Jaffe) txu.com DennisBuschbaum/CPSES/Texas Utilities C Post Office Route owf4_po.OWFNDO nrc.gov txu.com Files Size Date & Time MESSAGE 436 04/10/02 09:14AM TXX02073.pdf 69572 Mime.822 97494 Options Expiration Date: None Priority: Standard Reply Requested: No Return Notification: None Concealed
Subject:
No Security: Standard Attachment 10
iDavid Jaffe - Draft RAI Response for LAR 01-008 DRPage 1 From: <rsloughl@txu.com>
To: <dhj@nrc.gov>
Date: 4/10/02 9:14AM
Subject:
Draft RAI Response for LAR 01-008 Mr. Jaffe, Attached is a draft of the letter responding to the RAI and revised TS Bases pages. The letter is dated April 12, however I expect the letter will be signed today, in which case the date will be changed. When the letter is signed and mailed, I will e-mail you the final copy containing a signature.
If you or Keith have any further questions, please call me.
Thanks, Rob Slough (See attached file: TXX02073.pdf)
CC: <Den nisBuschbaum/CPSES/TexasUtilities@txu.com>, <rsloughl@txu.com>
Ref: 10CFR50.90 CPSES-200201164 Log # TXX-02073 File # 00236 April 12, 2002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION TO LICENSE AMENDMENT REQUEST (LAR) 01-008: REVISION TO TECHNICAL SPECIFICATION (TS) 3.3.2. ESFAS INSTRUMENTATION AND 3.3.6, CONTAINMENT VENTILATION ISOLATION INSTRUMENTATION (TAC NO. 2810)
REF: TXU Electric Letter logged TXX-01092, from C. L. Terry to the NRC dated August 24, 2001 Gentlemen:
Pursuant to 10CFR50.90, TXU Generation Company LP (TXU Energy) requested, via Reference, an amendment to the CPSES Unit I Operating License (NPF-87) and CPSES Unit 2 Operating License (NPF-89) by incorporating a change to the CPSES Units 1 and 2 Technical Specifications (TS) 3.3.2 and 3.3.6.
The proposed change will revise TS 3.3.2 entitled "ESFAS Instrumentation" and TS 3.3.6 entitled "Containment Ventilation Isolation Instrumentation". The proposed change will revise the CPSES Units 1 and 2 Technical Specifications to change the surveillance frequency for Westinghouse type AR relays, used as Solid State Protection System slave relays or auxiliary relays, from quarterly to refueling outage frequency. Surveillance Requirements (SR) 3.3.2.6 and 3.3.6.5 would be revised to change the frequency from "92 days" to "92 days OR 18 months for Westinghouse type AR relays."
The purpose of this letter is to respond to the NRC Staff Requests for Additional Information (RAIs).
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway Comanche Peak
- South Texas Project Wolf Creek
TXX-02073 Page 2 of 2 This communication contains no new licensing basis commitments regarding CPSES Units 1 and 2.
Should you have any questions, please contact Mr. Robert A. Slough at (254) 897 5727.
I state under penalty of perjury that the foregoing is true and correct.
Executed on April 9, 2002.
Sincerely C. L. Terry By:
David R. Moore Plant Manager RAS Attachment c- E. W. Merschoff, Region IV W. D. Johnson, Region IV D. H. Jaffe, NRR J. N. Donohew, NRR Resident Inspectors, CPSES Mr. Arthur C. Tate Bureau of Radiation Control Texas Department of Public Health 1100 West 4 9 th Street Austin, Texas 78704
Attachment I to TXX-02073 Page 1 of 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST 01-008 The following are questions on the application dated August 24, 2001, (CPSES 200101191), for Comanche Peak Steam Electric Station (CPSES), that proposed changes to Technical Specifications (TS) 3.3.2 and 3.3.6 to change the surveillance frequency for Westinghouse type AR relays, used as Solid State Protection System slave relays or auxiliary relays, from quarterly to refueling outage frequency.
Ouestion 1:
The licensee's submittal states, "The report can also be applied to ARD relays (DC coils) which are not used as slave relays, but are used in interposing relay applications." It should be noted that the Westinghouse Owner's Group Topical report (WCAP-13877) does not cover AR relays with DC coils. Therefore, if AR relays with DC coils are to be included in the extension request, please provide the basis for extending the applicability of the topical report to these relays. Such basis should be similar to the analysis for the AC relays.
TXU Energy Response:
Due to the expenditure of resources required in order demonstrate the applicability of the topical report to AR relays with DC coils, TXU Energy elects to revise our request to exclude AR relays with DC coils. Therefore, TXU Energy requests that the NRC withdraw the ARD relay from consideration in the proposed amendment request.
TXU Energy's proposed amendment request will continue to apply to Westinghouse Type AR relays with AC coils used in both SSPS slave relay and interposing relay applications, but will not include any DC relay applications at this time. This revised scope has been reflected in markups of the original proposed text for Technical Specifications Bases for Surveillance Requirements (SR) 3.3.2.6 and 3.3.6.5. These markups are provided in Attachment 2. The revised TS Bases pages which incorporate the marked-up information are provided in Attachment 3.
ATTACHMENT 2 to TXX-02073 MARKUP OF TECHNICAL SPECIFICATION BASES PAGES (For Information Only)
Pages B 3.3-115 B 3.3-168 to TXX-02073 ESFAS Instrumentation Page 1 of 2 B 3.3.2 BASES SURVEILLANCE SR 3.3.2.5 REQUIREMENTS (continued) SR 3.3.2.5 is the performance of a COT.
A COT is performed on each required channel to ensure the entire channel will perform the intended Function. Setpoints must be found within the Allowable Values specified in Table 3.3.2-1.
The difference between the current "as found" values and the previous test "as left" values must be consistent with the drift allowance used in the setpoint calculation. The setpoint shall be left set consistent with the assumptions of the current unit specific setpoint calculation.
The Frequency of 92 days is justified in Reference 6.
SR 3.3.2.6 SR 3.3.2.6 is the performance of a SLAVE RELAY TEST. The SLAVE RELAY TEST is the energizing of the slave relays. Contact operation is verified in one of two ways. Actuation equipment that may be operated in the design mitigation mode is either allowed to function, or is placed in a condition where the relay contact operation can be verified without operation of the equipment. Actuation equipment that may not be operated in the design mitigation mode is prevented from operation by the SLAVE RELAY TEST circuit. For this latter case, contact operation is verified by a continuity check of the circuit containing contacts operated by the slave relay. This test is 16 performed every 92 days. The Frequency is adequate, based on Industry operating experience, considering instrument reliability and operating history data.
For ESFAS slave relays and auxiliary relays which are Westinghouse 16 type AR relays, the SLAVE RELAY TEST is performed every 18 months. The Frequency is based on the slave relay reliability assessment presented in Reference 10. This reliability assessment is relay specific and applies only to Westinghouse type AR relays with AC coils. Note that, for normally energized applications, the relays may require periodic replacement in accordance with the guidance given in Reference 10.
SR 3.3.2.7 SR 3.3.2.7 is the performance of a TADOT every 31 days. This test is a check of the Loss of Offsite Power Function.
The SR is modified by a Note that excludes verification of setpoints for relays. Relay setpoints require elaborate bench calibration and are (continued)
COMANCHE PEAK - UNITS 1 AND 2 B 3.3-115 Amendmen.... ' 6-4Revision 16 to TXX-02073 Containment Ventilation Isolation Instrumentation Page 2 of 2 B 3.3.6 BASES SURVEILLANCE SR 3.3.6.5 (continued) 16 REQUIREMENTS (eontited) For ESFAS slave relays and auxiliary relays which are Westinghouse type AR relays, the SLAVE RELAY TEST is performed every 18 months. The Frequency is based on the slave relay reliability assessment presented in Reference 3. This reliability assessment is relay specific and applies only to Westinghouse type AR relays with AC coils. Note that, for normally energized applications, the relays may require periodic replacement in accordance with the guidance given in Reference 3.
SR 3.3.6.6 Not Used.
SR 3.3.6.7 A CHANNEL CALIBRATION is performed every 18 months, or approximately at every refueling. CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy.
The Frequency is based on operating experience and is consistent with the typical industry refueling cycle.
REFERENCES 1. 10 CFR 100.11.
- 2. NUREG-1366, July 22, 1993.
- 3. WCAP-13877-P-A, Revision 2, August 2000. 116 COMANCHE PEAK - UNITS 1 AND 2 B 3.3-168 Armend~ment, No*. 6G4Revision 16
ATTACHMENT 3 to TXX-02073 RETYPED TECHNICAL SPECIFICATION BASES PAGES (For Information Only)
Pages B 3.3-115 B 3.3-168 to TXX-02073 ESFAS Instrumentation Page 1 of 2 B 3.3.2 BASES SURVEILLANCE SR 3.3.2.5 REQUIREMENTS (continued) SR 3.3.2.5 is the performance of a COT.
A COT is performed on each required channel to ensure the entire channel will perform the intended Function. Setpoints must be found within the Allowable Values specified in Table 3.3.2-1.
The difference between the current "as found" values and the previous test "as left" values must be consistent with the drift allowance used in the setpoint calculation. The setpoint shall be left set consistent with the assumptions of the current unit specific setpoint calculation.
The Frequency of 92 days is justified in Reference 6.
SR 3.3.2.6 SR 3.3.2.6 is the performance of a SLAVE RELAY TEST. The SLAVE RELAY TEST is the energizing of the slave relays. Contact operation is verified in one of two ways. Actuation equipment that may be operated in the design mitigation mode is either allowed to function, or is placed in a condition where the relay contact operation can be verified without operation of the equipment. Actuation equipment that may not be operated in the design mitigation mode is prevented from operation by the SLAVE RELAY TEST circuit. For this latter case, contact operation is verified by a continuity check of the circuit containing contacts operated by the slave relay. This test is 16 performed every 92 days. The Frequency is adequate, based on industry operating experience, considering instrument reliability and operating history data.
For ESFAS slave relays and auxiliary relays which are Westinghouse 16 type AR relays, the SLAVE RELAY TEST is performed every 18 months. The Frequency is based on the slave relay reliability assessment presented in Reference 10. This reliability assessment is relay specific and applies only to Westinghouse type AR relays with AC coils. Note that, for normally energized applications, the relays may require periodic replacement in accordance with the guidance given in Reference 10.
SR 3.3.2.7 SR 3.3.2.7 is the performance of a TADOT every 31 days. This test is a check of the Loss of Offsite Power Function.
The SR is modified by a Note that excludes verification of setpoints for relays. Relay setpoints require elaborate bench calibration and are (continued)
COMANCHE PEAK - UNITS 1 AND 2 B 3.3-115 Revision 16 to TXX-02073 Containment Ventilation Isolation Instrumentation Page 2 of 2 B 3.3.6 BASES SURVEILLANCE SR 3.3.6.5 (continued) 16 REQUIREMENTS For ESFAS slave relays and auxiliary relays which are Westinghouse type AR relays, the SLAVE RELAY TEST is performed every 18 months. The Frequency is based on the slave relay reliability assessment presented in Reference 3. This reliability assessment is relay specific and applies only to Westinghouse type AR relays with AC coils. Note that, for normally energized applications, the relays may require periodic replacement in accordance with the guidance given in Reference 3.
SR 3.3.6.6 Not Used.
SR 3.3.6.7 A CHANNEL CALIBRATION is performed every 18 months, or approximately at every refueling. CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy.
The Frequency is based on operating experience and is consistent with the typical industry refueling cycle.
REFERENCES 1. 10 CFR 100.11.
- 2. NUREG-1 366, July 22, 1993.
- 3. WCAP-13877-P-A, Revision 2, August 2000. 116 COMANCHE PEAK - UNITS 1 AND 2 B 3.3-168 Revision 16