|
|
| (5 intermediate revisions by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML120610634 | | | number = ML120610634 |
| | issue date = 03/01/2012 | | | issue date = 03/01/2012 |
| | title = Diablo Canyon Power Plant, Unit 1 and 2 - Email, Draft Request for Additional Information, License Amendment Request to Revise Technical Specification 3.7.1, Main Steam Safety Valves (TAC Nos. ME5713 and ME5714) | | | title = Email, Draft Request for Additional Information, License Amendment Request to Revise Technical Specification 3.7.1, Main Steam Safety Valves |
| | author name = Sebrosky J M | | | author name = Sebrosky J |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Soenen P R | | | addressee name = Soenen P |
| | addressee affiliation = Pacific Gas & Electric Co | | | addressee affiliation = Pacific Gas & Electric Co |
| | docket = 05000275, 05000323 | | | docket = 05000275, 05000323 |
| | license number = DPR-080, DPR-082 | | | license number = DPR-080, DPR-082 |
| | contact person = Sebrosky J M, NRR/DORL/LPL4, 415-1132 | | | contact person = Sebrosky J, NRR/DORL/LPL4, 415-1132 |
| | case reference number = TAC ME5713, TAC ME5714 | | | case reference number = TAC ME5713, TAC ME5714 |
| | document type = E-Mail, Request for Additional Information (RAI) | | | document type = E-Mail, Request for Additional Information (RAI) |
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:From: Sebrosky, Joseph Sent: Thursday, March 01, 2012 3:11 PM To: Soenen, Philippe R Cc: Gall, Jennifer; Gardocki, Stanley; Billerbeck, John; Wang, Alan; Burkhardt, Janet; Lent, Susan; Baldwin, Thomas (DCPP) | | {{#Wiki_filter:From: Sebrosky, Joseph Sent: Thursday, March 01, 2012 3:11 PM To: Soenen, Philippe R Cc: Gall, Jennifer; Gardocki, Stanley; Billerbeck, John; Wang, Alan; Burkhardt, Janet; Lent, Susan; Baldwin, Thomas (DCPP) |
|
| |
|
| ==Subject:== | | ==Subject:== |
| DCPP requested revision to TS 3.7.1, "Main Steam Safety Valves" draft request for additional information (Tac No. ME5713 and ME5714) Philippe, By letter dated February 17, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110480870), Pacific Gas and Electric Company (PG&E) submitted PG&E Letter DCL-11-018, "License Amendment Request 11-02, Revision to Technical Specification 3.7.1, 'Main Steam Safety Valves (MSSVs)." This request was later supplemented by letters dated April 21, 2011, and February 27, 2012. The staff has determined additional information is needed to complete our review. Below are draft requests for additional information regarding the license amendment request. Please let me know if you need a clarifying call before I issue them. Sincerely, Joe Sebrosky Project Manager (Diablo Canyon Power Plant) Nuclear Regulatory Commission Division of Operating Reactor Licensing joseph.sebrosky@nrc.gov 301-415-1132 | | DCPP requested revision to TS 3.7.1, "Main Steam Safety Valves" draft request for additional information (Tac No. ME5713 and ME5714) |
| >>>>>>>>Draft RAIs>>>>>>>>>>>>>>>>>>> The staff has reviewed PG&E's February 27, 2012, (ML12059A076) response and has the following questions related to the license amendment request.
| | : Philippe, By letter dated February 17, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110480870), Pacific Gas and Electric Company (PG&E) submitted PG&E Letter DCL-11-018, License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (MSSVs). This request was later supplemented by letters dated April 21, 2011, and February 27, 2012. The staff has determined additional information is needed to complete our review. Below are draft requests for additional information regarding the license amendment request. Please let me know if you need a clarifying call before I issue them. |
| 1. Can PG&E provide the Crosby test data referenced in EPRI Report NP-4306-SR that supports a 5 psi max accumulation behavior for main steam safeties? 2. Can PG&E provide the Westinghouse evaluation that determines that the DCPP Dresser valves will perform in a similar manner? 3. Can PG&E provide an overview of the maintenance and test program for their MSSVs including inservice test history? 4. Because the EPRI report identified that a safety valve's performance may vary based upon the physical plant piping configuration, the staff requests the licensee evaluate the individual plant configuration in which the safeties are installed for an effect on the valve's performance. | | Sincerely, Joe Sebrosky Project Manager (Diablo Canyon Power Plant) |
| }} | | Nuclear Regulatory Commission Division of Operating Reactor Licensing joseph.sebrosky@nrc.gov 301-415-1132 |
| | >>>>>>>>Draft RAIs>>>>>>>>>>>>>>>>>>> |
| | The staff has reviewed PG&Es February 27, 2012, (ML12059A076) response and has the following questions related to the license amendment request. |
| | : 1. Can PG&E provide the Crosby test data referenced in EPRI Report NP-4306-SR that supports a 5 psi max accumulation behavior for main steam safeties? |
| | : 2. Can PG&E provide the Westinghouse evaluation that determines that the DCPP Dresser valves will perform in a similar manner? |
| | : 3. Can PG&E provide an overview of the maintenance and test program for their MSSVs including inservice test history? |
| | : 4. Because the EPRI report identified that a safety valves performance may vary based upon the physical plant piping configuration, the staff requests the licensee evaluate the individual plant configuration in which the safeties are installed for an effect on the valves performance.}} |
Letter Sequence Draft RAI |
|---|
|
|
MONTHYEARDCL-11-018, License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs)2011-02-17017 February 2011
License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs)
Project stage: Request
ML1108706822011-03-28028 March 2011
Acceptance Review E-mail, License Amendment Request to Revise Technical Specification (TS) 3.7.1, Main Steam Safety Valves (Mssvs), to Remove a One-time Note from TS Table 3.7.1-1
Project stage: Acceptance Review
ML1203704962012-02-0606 February 2012
Email, Request for Additonal Information, License Amendment Request to Revise TS 3.7.1, Main Steam Safety Valves
Project stage: Other
DCL-12-024, Response to NRC Request for Additional Information Regarding PG&E Letter DCL-11-018. License Amendment Request 11-02. Revision to Technical Specification 3.7.1. 'Main Steam Safety Valves (Mssvs)'.2012-02-27027 February 2012
Response to NRC Request for Additional Information Regarding PG&E Letter DCL-11-018. License Amendment Request 11-02. Revision to Technical Specification 3.7.1. 'Main Steam Safety Valves (Mssvs)'.
Project stage: Response to RAI
ML1206106342012-03-0101 March 2012
Email, Draft Request for Additional Information, License Amendment Request to Revise Technical Specification 3.7.1, Main Steam Safety Valves
Project stage: Draft RAI
DCL-12-065, Response to NRC Request for Additional Information Regarding PG&E Letter DCL-11-01B, License Amendment Request 11-02, Revision to Technical Specification 3.7.1. Main Steam Safety Valves (Mssvs).2012-07-0202 July 2012
Response to NRC Request for Additional Information Regarding PG&E Letter DCL-11-01B, License Amendment Request 11-02, Revision to Technical Specification 3.7.1. Main Steam Safety Valves (Mssvs).
Project stage: Response to RAI
ML12240A3222012-09-0707 September 2012
Summary of Audit to Review Calculations That Support License Amendment Request Related to Main Steam Safety Valves
Project stage: Other
2012-02-06
[Table View] |
|
|---|
Category:E-Mail
MONTHYEARML23334A0912023-11-30030 November 2023
NRR E-mail Capture - Diablo Canyon 1 and 2 - Audit Questions for License Amendment Associated with TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML23335A1012023-11-0606 November 2023
OEDO-23-00350-NRR - Screen-in Email - 10 CFR 2.206 Petition from Mother'S for Peace and Change.Org Regarding Diablo Canyon
ML23306A0422023-11-0202 November 2023
NRR E-mail Capture - Acceptance Review Diablo Canyon Request to Adopt 10 CFR 50.69, risk-informed Categorization and Treatment of SSCs
ML23230A0702023-08-18018 August 2023
NRR E-mail Capture - Acceptance Review - Diablo Canyon Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b
ML23165A2702023-06-14014 June 2023
NRR E-mail Capture - Acceptance Review - Diablo Canyon Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule
ML23157A2392023-06-0505 June 2023
Limited Appearance Statement from Nina Babiarz in the Matter of the Diablo Canyon ISFSI License Renewal Application
ML23096A1792023-04-0606 April 2023
NRR E-mail Capture - Request for Additional Information Diablo Canyon Exemption Request Regarding Senior Reactor Operator License Application
ML23094A1032023-04-0404 April 2023
NRR E-mail Capture - Acceptance Review - Diablo Canyon Exemption Request Regarding Senior Reactor Operator License Application
ML23076A0932023-03-16016 March 2023
16-2023 Email - Estimate of Spent Nuclear Fuel in Tons
ML23067A0202023-03-0808 March 2023
NRR E-mail Capture - Diablo Canyon Nuclear Power Plant Evacuation Time Estimate Analysis Review
ML23046A1132023-02-13013 February 2023
Transmittal Email, Paul Bessette to Gibson, 2/13/23, Filing of Formal Opposition to PG&E Exemption Request
ML23046A1042023-02-13013 February 2023
Transmittal Email, Diane Curran to Gibson, 2/13/23, Filing of Formal Opposition to PG&E Exemption Request
ML23052A2042023-01-10010 January 2023
E-mail from Paul Bessette Dated 01/10/2023 Regarding Diablo Canyon
ML22326A1632022-11-21021 November 2022
Licensee Comment Email on Post-Shutdown Emergency Plan Amendment
ML22266A0012022-09-22022 September 2022
(External Sender) E-Mail Diablo Canyon Power Plant, Unit Nos. 1 and 2 - Total Amount of Spent Nuclear Fuel Stored in Tons
ML22241A1142022-08-29029 August 2022
NRR E-mail Capture - Acceptance Review - Diablo Canyon Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions
ML22194A8872022-07-11011 July 2022
September 2022 Emergency Preparedness Exercise Inspection - Request for Information Email
ML22187A2652022-07-0606 July 2022
NRR E-mail Capture - Request for Additional Information: Diablo Canyon Exemption Request for Part 73 force-on-force Training Due to COVID-19
ML22105A0702022-04-15015 April 2022
NRR E-mail Capture - Acceptance Review - Diablo Canyon Request to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections
ML22090A0832022-03-31031 March 2022
NRR E-mail Capture - Acceptance Review - Diablo Canyon Request for Approval of a Certified Fuel Handler Training and Retraining Program
ML22089A1672022-03-29029 March 2022
Email - Acknowledgement of NRC Receipt of Diablo Canyon ISFSI Renewal Application
ML22087A0412022-03-25025 March 2022
NRR E-mail Capture - Acceptance Review - Diablo Canyon Request for Approval of Alternative Security Measures for Early Warning System
ML22061A2192022-03-0202 March 2022
NRR E-mail Capture - Request for Additional Information - Diablo Canyon Proposed Changes to Emergency Plan for post-shutdown and Permanently Defueled Condition
ML21323A0652021-11-19019 November 2021
NRR E-mail Capture - Acceptance Review - Diablo Canyon Revision of Emergency Plan for post-shutdown Condition
ML21264A6722021-09-21021 September 2021
NRR E-mail Capture - Revised Schedule: Diablo Canyon Request to Revise Technical Specification to Reflect the Permanent Cessation of Reactor Operation
ML21215A3432021-08-0303 August 2021
NRR E-mail Capture - Request for Additional Information - Diablo Canyon Request to Revise Technical Specification 3.8.1, AC Sources - Operating to Support Diesel Fuel Oil Transfer System Component Planned Maintenance
ML21189A0462021-07-0707 July 2021
NRR E-mail Capture - Draft Request for Additional Information - Diablo Canyon Emergency Amendment Request to Revise Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System
ML21188A0382021-07-0707 July 2021
(External_Sender) DCPP Draft Emergency LAR - Asw
DCL-21-046, Email for Emergency LAR for TS 3.7.8, Auxiliary Saltwater (Asw) System2021-07-0707 July 2021
Email for Emergency LAR for TS 3.7.8, Auxiliary Saltwater (Asw) System
ML21189A0662021-07-0707 July 2021
NRR E-mail Capture - Additional Draft Request for Additional Information - Diablo Canyon Emergency Amendment Request to Revise Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System
ML21189A0442021-07-0707 July 2021
NRR E-mail Capture - Request for Additional Information - Diablo Canyon Emergency Amendment Request to Revise Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System
ML21124A0612021-05-0404 May 2021
NRR E-mail Capture - Acceptance Review - Diablo Canyon Request to Revise Technical Specification 3.8.1, AC Sources - Operating to Support Diesel Fuel Oil Transfer System Component Planned Maintenance
ML21104A3642021-04-14014 April 2021
NRR E-mail Capture - Request for Additional Information - Diablo Canyon Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition
ML21062A0642021-03-0202 March 2021
NRR E-mail Capture - Request for Additional Information for Diablo Canyon Generic Letter 2004-02 Submittal (L-2017-LRC-0000)
ML21054A3112021-02-23023 February 2021
NRR E-mail Capture - Acceptance Review: Diablo Canyon Request for One-Time Exemption from Select 10 CFR 55.59 Requirements
ML21012A4432021-01-12012 January 2021
NRR E-mail Capture - Acceptance Review - Diablo Canyon Request to Revise Technical Specification to Reflect the Permanent Cessation of Reactor Operation
ML20328A3002020-11-23023 November 2020
Email from Cgnp to the NRC - Comment Diablo Canyon Nuclear Power Plant, Units 1 and 2 - Dcdep Public Meeting - November 24, 2020
ML20329A0692020-11-23023 November 2020
NRR E-mail Capture - Request for Additional Information: Diablo Canyon COVID-19 Exemption Request to Extend force-on-force Exercise
ML20323A4532020-11-18018 November 2020
NRR E-mail Capture - Request for Additional Information: Diablo Canyon COVID-19 Exemption Request to Extend Firearms Requalification
ML20261H4232020-09-17017 September 2020
NRR E-mail Capture - Request for Additional Information: Diablo Canyon Unit 2 Fall 2019 Steam Generator Tube Inspection Report
ML20239A9492020-08-26026 August 2020
(External Sender) E-Mail Comment by D. Lochbaum Regarding Diablo Canyon Unit 1 AFW System Piping
ML20239A7282020-08-24024 August 2020
(External-Sender) E-mail Comments on No Significant Hazards Determination for Diablo Canyon LAR
ML20239A7752020-08-24024 August 2020
(External-Sender) E-mail Comments on No Significant Hazards Determination for Diablo Canyon LAR
ML20240A2302020-08-23023 August 2020
(External-Sender) E-mail Public Comment by D. Lochbaum Regarding Diablo Canyon Safety Issue
ML20234A2422020-08-20020 August 2020
NRR E-mail Capture - Diablo Canyon Additional Request for Additional Information: Exigent License Amendment Request for Application to Provide a New Technical Specification 3.7.5, Auxiliary Feedwater System, Condition G EPID: L-2020-LLA-017
ML20233A8592020-08-19019 August 2020
Mothers for Peace Public Comment on Exigent LAR to Modify TS 3.7.5, Auxiliary Feedwater System
ML20233A3222020-08-18018 August 2020
Comment (4) e-mail from D. Lochbaum Regarding Diablo Canyon Exigent LAR
ML20231A2372020-08-17017 August 2020
NRR E-mail Capture - Diablo Canyon Additional Request for Additional Information: Exigent License Amendment Request for Application to Provide a New Technical Specification 3.7.5, Auxiliary Feedwater System, Condition G EPID: L-2020-LLA-017
ML20232C6482020-08-17017 August 2020
Lochbaum Public Comment 1 on Exigent LAR to Modify TS 3.7.5, Auxiliary Feedwater System
ML20230A0732020-08-14014 August 2020
NRR E-mail Capture - Diablo Canyon Request for Additional Information: Exigent License Amendment Request for Application to Provide a New Technical Specification 3.7.5, Auxiliary Feedwater System, Condition G
2023-08-18
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24024A2072024-01-24024 January 2024
Inservice Inspection Request for Information
IR 05000275/20240152023-10-10010 October 2023
Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (050002752024015 and 050003232024015)
ML23249A2782023-09-0606 September 2023
Inservice Inspection Request for Information
ML23159A2382023-07-25025 July 2023
Request for Additional Information for the Technical Review of the Application for Renewal of the Diablo Canyon Independent Spent Fuel Storage Installation (Cac/Epid Nos. 001028/L-2022-RNW-0007)
ML23159A2372023-07-25025 July 2023
ISFSI Renewal RAI Transmittal Letter Enclosure
ML23096A1792023-04-0606 April 2023
NRR E-mail Capture - Request for Additional Information Diablo Canyon Exemption Request Regarding Senior Reactor Operator License Application
ML23047A0062023-02-21021 February 2023
Request for Additional Information Alternative Security Measures for Early Warning System (EPID: L-2022-LLA-0029) (Public Version)
ML23041A1862023-02-17017 February 2023
Request for Information Regarding Diablo Canyon Power Plant, Units 1 and 2 - December 8, 2022, Public Meeting
ML22258A1112022-09-14014 September 2022
2022 Diablo Canyon PIR Request for Information
ML22200A2572022-07-19019 July 2022
Notification of In-service Inspection (Inspection Report 05000323/2022004) and Request for Information
ML22187A2652022-07-0606 July 2022
NRR E-mail Capture - Request for Additional Information: Diablo Canyon Exemption Request for Part 73 force-on-force Training Due to COVID-19
ML22152A1502022-06-21021 June 2022
Request for Additional Information Regarding License Amendment Request for Technical Specifications and Revised License Conditions for the Permanently Defueled Condition
ML22122A1412022-05-0505 May 2022
.02 Doc Request
ML22068A2312022-03-17017 March 2022
Notification of NRC Design Bases Assurance Inspection (Team) 05000275/2022011 and 05000323/2022011 and Initial Request for Information
ML22061A2192022-03-0202 March 2022
NRR E-mail Capture - Request for Additional Information - Diablo Canyon Proposed Changes to Emergency Plan for post-shutdown and Permanently Defueled Condition
ML21363A1692021-12-29029 December 2021
Inservice Inspection Request for Information
ML22019A0412021-12-29029 December 2021
RFI
ML21215A3432021-08-0303 August 2021
NRR E-mail Capture - Request for Additional Information - Diablo Canyon Request to Revise Technical Specification 3.8.1, AC Sources - Operating to Support Diesel Fuel Oil Transfer System Component Planned Maintenance
ML21130A3642021-06-21021 June 2021
DC 2021401 Information Request
ML21104A3642021-04-14014 April 2021
NRR E-mail Capture - Request for Additional Information - Diablo Canyon Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition
ML21062A0642021-03-0202 March 2021
NRR E-mail Capture - Request for Additional Information for Diablo Canyon Generic Letter 2004-02 Submittal (L-2017-LRC-0000)
ML20329A0692020-11-23023 November 2020
NRR E-mail Capture - Request for Additional Information: Diablo Canyon COVID-19 Exemption Request to Extend force-on-force Exercise
ML20323A4532020-11-18018 November 2020
NRR E-mail Capture - Request for Additional Information: Diablo Canyon COVID-19 Exemption Request to Extend Firearms Requalification
ML20301A2212020-10-27027 October 2020
Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000275/2021010 and 05000323/2021010) and Request for Information
ML20261H4232020-09-17017 September 2020
NRR E-mail Capture - Request for Additional Information: Diablo Canyon Unit 2 Fall 2019 Steam Generator Tube Inspection Report
ML20231A2372020-08-17017 August 2020
NRR E-mail Capture - Diablo Canyon Additional Request for Additional Information: Exigent License Amendment Request for Application to Provide a New Technical Specification 3.7.5, Auxiliary Feedwater System, Condition G EPID: L-2020-LLA-017
ML20230A0732020-08-14014 August 2020
NRR E-mail Capture - Diablo Canyon Request for Additional Information: Exigent License Amendment Request for Application to Provide a New Technical Specification 3.7.5, Auxiliary Feedwater System, Condition G
ML20280A5432020-06-0303 June 2020
DC 2020 PIR Request for Information
ML20041E6012020-02-10010 February 2020
NRR E-mail Capture - Diablo Canyon Nuclear Power Plant, Units 1 and 2 - Request for Additional Information for Post -Shutdown Decommissioning Activities Report (PSDAR)
ML19262G7482019-08-0909 August 2019
Request for Information
ML19149A6012019-05-28028 May 2019
NRR E-mail Capture - Request for Additional Information (Supplemental) - License Amendment Request (LAR) to Revise Emergency Plan Response Organization Staffing and Augmentation
ML19123A2162019-05-0202 May 2019
NRR E-mail Capture - Diablo Canyon Nuclear Power Plant -Request for Exemption from Operator Written Examination and Operating Test - Request for Additional Information
ML19084A2572019-03-21021 March 2019
NRR E-mail Capture - Request for Additional Information - License Amendment Request (LAR) to Revise Emergency Plan Response Organization Staffing and Augmentation
ML19043A9452019-02-20020 February 2019
Notification of Inspection (NRC Inspection Report 05000275/2019002, 05000323/2019002 and Request for Information
ML17306A9382017-11-0202 November 2017
NRR E-mail Capture - Request for Additional Information - Request for Approval for Application of Full Weld Overlay REP-RHR-SWOL, Diablo Canyon Power Plant, Units 1 and 2
ML17152A3192017-06-0101 June 2017
NRR E-mail Capture - Request for Additional Information (RAI)- Relief Requests NDE-SLH U2, NDE-LSL U2, NDE-LHC U2, NDE-LHM U2, and NDE-ONV U2 (CAC Nos. MF9386 Through MF9390)
ML17102B6072017-04-12012 April 2017
NRR E-mail Capture - Request for Additional Information (RAI) - Revised Emergency Action Level Schemes Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6
ML16347A0032016-12-0909 December 2016
NRR E-mail Capture - Request for Additional Information (RAI) - Diablo Canyon Power Plant License Amendment Request for Adoption of NEI 94-01
ML16326A3562016-11-21021 November 2016
NRR E-mail Capture - Request for Additional Information - License Amendment Request to Adopt Nuclear Energy Institute (NEI) 94-01, Revision 2-A for Diablo Canyon Power Plant, Units 1 and 2 - CAC Nos. MF7731 and MF7732
ML16048A2322016-02-17017 February 2016
NRR E-mail Capture - Diablo Canyon 1 and 2 - Met Data Second Round of Requests for Additional Information for License Amendment Request 15-03 to Adopt the Alternative Source Term Per 10 CFR 50.67 (TAC Nos. MF6399 and MF640
ML16011A3652016-02-0202 February 2016
Requests for Additional Information for the Review of the Diablo Canyon Power Plant, Units 1 and 2, License Renewal Application - Set 39 (TAC Nos. ME2896 and ME2897)
ML16011A3172016-01-11011 January 2016
NRR E-mail Capture - Diablo Canyon 1 and 2 - Requests for Additional Information for License Amendment Request 15-03 to Adopt the Alternative Source Term Per 10 CFR 50.67
ML15358A0022015-12-23023 December 2015
Request for Additional Information Email (Follow-up Pra), Request to Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition)
ML15357A3822015-12-23023 December 2015
Request for Additional Information, Round 4 - Amendment Request to Replace Digital Process Protection System for Reactor Protection System and Engineered Safety Features Actuation System Functions
ML15295A3732015-11-0505 November 2015
Requests for Additional Information Related to the Diablo Canyon LRA Environmental Review
ML15287A1652015-10-23023 October 2015
Requests for Additional Information Related to the Diablo Canyon LRA Environmental Review - SAMA
ML15267A7742015-10-0101 October 2015
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1 Seismic Evaluations
ML15217A4812015-09-24024 September 2015
Requests for Additional Information for the Review of the Diablo Canyon Power Plant, Units 1 and 2, License Renewal Application Set-38 TAC Nos. ME2896 and ME2897
ML15238B7742015-08-27027 August 2015
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Reevaluations
ML15153A0332015-06-29029 June 2015
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Reevaluations
2024-01-24
[Table view] |
Text
From: Sebrosky, Joseph Sent: Thursday, March 01, 2012 3:11 PM To: Soenen, Philippe R Cc: Gall, Jennifer; Gardocki, Stanley; Billerbeck, John; Wang, Alan; Burkhardt, Janet; Lent, Susan; Baldwin, Thomas (DCPP)
Subject:
DCPP requested revision to TS 3.7.1, "Main Steam Safety Valves" draft request for additional information (Tac No. ME5713 and ME5714)
- Philippe, By letter dated February 17, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110480870), Pacific Gas and Electric Company (PG&E) submitted PG&E Letter DCL-11-018, License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (MSSVs). This request was later supplemented by letters dated April 21, 2011, and February 27, 2012. The staff has determined additional information is needed to complete our review. Below are draft requests for additional information regarding the license amendment request. Please let me know if you need a clarifying call before I issue them.
Sincerely, Joe Sebrosky Project Manager (Diablo Canyon Power Plant)
Nuclear Regulatory Commission Division of Operating Reactor Licensing joseph.sebrosky@nrc.gov 301-415-1132
>>>>>>>>Draft RAIs>>>>>>>>>>>>>>>>>>>
The staff has reviewed PG&Es February 27, 2012, (ML12059A076) response and has the following questions related to the license amendment request.
- 1. Can PG&E provide the Crosby test data referenced in EPRI Report NP-4306-SR that supports a 5 psi max accumulation behavior for main steam safeties?
- 2. Can PG&E provide the Westinghouse evaluation that determines that the DCPP Dresser valves will perform in a similar manner?
- 3. Can PG&E provide an overview of the maintenance and test program for their MSSVs including inservice test history?
- 4. Because the EPRI report identified that a safety valves performance may vary based upon the physical plant piping configuration, the staff requests the licensee evaluate the individual plant configuration in which the safeties are installed for an effect on the valves performance.
