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MONTHYEARML12348A1082012-12-18018 December 2012 Notice of 1/15/2013 Preapplication Meeting with Pacific Gas and Electric Company to Discuss License Amendment Request to Revise Diesel Generator Surveillance Requirements for Diablo Canyon, Units 1 and 2 Project stage: Meeting ML13018A1342013-01-15015 January 2013 Pacific Gas and Electric Handouts from January 15, 2013 Meeting Regarding Pending License Amendment Request Related to Diesel Generator Technical Specifications Project stage: Meeting ML13018A1242013-02-0606 February 2013 Summary of Preapplication Meeting with Pacific Gas and Electric Company to Discuss License Amendment Request to Revise Diesel Generator Surveillance Requirements for Diablo Canyon, Units 1 and 2 Project stage: Meeting ML13043A2802013-02-12012 February 2013 NRC Feedback Related to 1/15/13 Preapplication Meeting with Pacific Gas and Electric Company to Discuss License Amendment Request to Revise Diesel Generator Surveillance Requirements for Diablo Canyon, Units 1 and 2 Project stage: Meeting 2013-01-15
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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
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Lent, Susan From: Sebrosky, Joseph Sent: Tuesday, February 12, 20139:34 AM To: 'Soenen, Philippe R'; 'Schrader, Kenneth' Cc: Polickoski, James; Waig, Gerald; Matharu, Gurcharan; Lent, Susan
Subject:
NRC staff feedback on proposed Pacific Gas and Electric license amendment request related to Diesel Generator Technical Specifications for Diablo Canyon Philippe Soenen Regulatory Services - Diablo Canyon Power Plant In a January 15, 2013, public meeting and as documented in a February 6, 2013, meeting summary (Agencywide Documents Access and Management System Accession No. ML13018A124) the NRC staff took an action to provide feedback on Pacific Gas and Electric's (PG&E) proposal related to a forthcoming license amendment request to change some Diesel Generator (DG) Technical Specification Surveillance Requirements (SRs). The purpose of this email is to provide feedback in accordance with the action from the January 15, 2013, meeting. Specifically, the NRC staff indicated that it would provide the following feedback:
Whether or not the DG frequency bands in SRs 3.8. 1.2 and 3.8. 1.7 should also be changed. PG&E had stated that it would be proposing a change in the DG frequency bands for SRs 3.8.1.11 and 3.8. 1. 19 from 61.2 Hz to 60.8 Hz because of a concern related to the rating of the DGs during these SRs that require the DG to be fully loaded. From PG&E's perspective, the DG frequency bands for SRs 3.8. 1.2 and 3.8. 1. 7 do not need to change because the DG is not fully loaded during these surveilfances. The NRC staff indicated that it would consider PG&E's position, but the staff did express a concern that if approved, the DG SR frequency bands would be different for different SRs and this proposed change may not be consistent with the analysis or design basis.
The staff has considered your position as stated in the meeting and provides the following for your consideration prior to the submittal of your license amendment request. Please note that this information is for consideration only. If the license amendment is submitted, it will be reviewed in accordance with established processes and if it is found that additional information is needed formal requests for additional information will be issued.
BACKGROUND The purpose of the Emergency DGs is usually described in FSAR Section 8.3 (I.e. to supply a highly reliable, self-contained source of power in the event of a complete loss of off-site power). The DGs are designed to provide sufficient power for the electrical loads required for a safe shutdown of the plant. This includes the loads required to mitigate the effects of a design basis LOCA with a complete loss of off-site power plus a single failure in the on-site power system. For a dual unit site, this includes the loads required to mitigate the effects of a design basis LOCA on one unit with a complete loss of off-site power plus a single failure in the on site power system, concurrent with a safe shutdown on the other unit.
The Standard Technical Specifications (NUREGs 1430-1434) define "operable/operability" as follows:
A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety functions, and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related supporl function(s).
In order to be considered operable, structures, systems and components (SSC) must be capable of performing the safety functions specified by its design, within the required range of design physical conditions, initiation 1
times. and mission times. In addition, TS operability considerations require that SSCs meet all surveillance requirements (as specified in Surveillance Requirement (SR>>. A SSC that does not meet a SR must be declared inoperable. For operability determination purposes, the mission time is the duration of SSC operation that is credited in the design basis for the SSC to perform its specified safety function.
CONCLUSION The NRC's Electrical Engineering Branch staff considers that all SRs in TS 3.8.1 associated with DGs demonstrate its operational readiness to perform its intended design functions as delineated in the FSAR Section 8.3. The staff notes that the proposed change modifies frequency requirements only for SRs 3.8.1.11 and 3.8.1.19. The staff believes that the frequency requirements in SR 3.8.1.2 and SR 3.8.1.7 (along with voltage requirements) specified for slow and fast starts (irrespective of automatic or manual control) also need to be changed to demonstrate the EDGs' capability to support its required design functions.
Therefore, all frequency and voltage requirements should envelope the accident performance requirements when performing SRs required to demonstrate operational readiness of EDGs.
Please let me know if you have any questions.
Sincerely, Joe Sebrosky Project Manager Nuclear Regulatory Commission Division of Operating Reactor Licensing joseph.sebrosky@nrc.gov 301-415-1132 Joe Sebrosky Project Manager (Diablo Canyon Power Plant)
Nuclear Regulatory Commission Division of Operating Reactor Licensing joseph.sebrosky@nrc.gov 301-415-1132 2