Letter Sequence RAI |
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TAC:ME6360, Allow 7 Day Completion Time for a TURBINE-DRIVEN AFW Pump Inoperable, Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO (Approved, Closed) TAC:ME6361, Allow 7 Day Completion Time for a TURBINE-DRIVEN AFW Pump Inoperable, Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO (Approved, Closed) |
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MONTHYEARML1120300652011-07-21021 July 2011 Acceptance Review Email, Request to Revise Technical Specifications Related to Auxiliary Feedwater System to Adopt TSTF-245, Rev. 1, TSTF-340, Rev. 3, TSTF-412, Rev. 3, and TSTF-439, Rev. 2 Project stage: Acceptance Review ML1200504882012-01-0505 January 2012 Request for Additional Information, Round 2, Revise Technical Specifications Related to Auxiliary Feedwater System to Adopt TSTF-245, Rev. 1, TSTF 340, Rev. 3, TSTF-412, Rev. 3, and TSTF-439, Rev. 2 (TAC ME6360-ME6361) Project stage: RAI DCL-11-059, Response to NRC Request for Additional Information Regarding PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification 3.6.6, 'Containment Spray and Cooling Systems,' ...2012-02-0606 February 2012 Response to NRC Request for Additional Information Regarding PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification 3.6.6, 'Containment Spray and Cooling Systems,' ... Project stage: Response to RAI ML1213607062012-05-21021 May 2012 Memo to File, Summary of 5/11/12 Telephone Conference Issues Associated TSTF-412, Rev. 3 and Effect on Staff Review of Request to Revise Technical Specifications Related to Auxiliary Feedwater System (TAC ME6360-ME6361) Project stage: Approval DCL-12-057, Supplement to PG&E Letter DCL-12-017, Response to NRC Request for Additional Information: NRC Question 12012-05-31031 May 2012 Supplement to PG&E Letter DCL-12-017, Response to NRC Request for Additional Information: NRC Question 1 Project stage: Supplement DCL-12-076, Response to NRC Second Request for Additional Information Regarding PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' Ts..2012-08-0606 August 2012 Response to NRC Second Request for Additional Information Regarding PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' Ts.. Project stage: Request DCL-12-107, Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW) System,' TS 3.8.1, 'Ac.....2012-11-0101 November 2012 Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW) System,' TS 3.8.1, 'Ac..... Project stage: Supplement ML12352A0672013-01-31031 January 2013 Issuance of Amendment Nos. 215 and 217, Revise Technical Specifications Related to Auxilary Feedwater System to Adopt TSTF-245, Rev. 1, TSTF-340, Rev. 3, TSTF-412, Rev. 3, and TSTF-439, Rev. 2 Project stage: Approval 2012-02-06
[Table View] |
Request for Additional Information, Round 2, Revise Technical Specifications Related to Auxiliary Feedwater System to Adopt TSTF-245, Rev. 1, TSTF 340, Rev. 3, TSTF-412, Rev. 3, and TSTF-439, Rev. 2 (TAC ME6360-ME6361)ML120050488 |
Person / Time |
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Site: |
Diablo Canyon |
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Issue date: |
01/05/2012 |
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From: |
Steven Lynch Plant Licensing Branch IV |
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To: |
Soenen P Pacific Gas & Electric Co |
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Lynch, S T, NRR/DORL/LPL4, 301-415-1524 |
Shared Package |
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ML120050473 |
List: |
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References |
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TAC ME6360, TAC ME6361 |
Download: ML120050488 (3) |
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Category:Request for Additional Information (RAI)
MONTHYEARML24250A0532024-09-0606 September 2024 LRA - Requests for Additional Information - Set 1 ML24184C0422024-07-0202 July 2024 NRR E-mail Capture - Request for Additional Information Diablo Canyon 50.69 risk-informed Categorization ML24065A1312024-03-20020 March 2024 ISFSI Renewal RAI Transmittal Letter ML24065A1332024-03-20020 March 2024 Enclosure- Diablo Canyon ISFSI Renewal Request for Additional Information ML24024A2072024-01-24024 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 ML23159A2372023-07-25025 July 2023 ISFSI Renewal RAI Transmittal Letter Enclosure 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) ML23096A1792023-04-0606 April 2023 NRR E-mail Capture - 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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 2024-09-06
[Table view] |
Text
REQUEST FOR ADDITIONAL INFORMATION FOR DIABLO CANYON CHANGES TO AUXILIARY FEEDWATER TECHNICAL SPECIFICATION BASED UPON TSTF 245, 340, 412 AND 439 (TAC NOS. ME6360 AND ME6361)
SBPB- RAI -1 On page 8 of the application letter dated June 1, 2011, the licensee, PG&E, states, under the scenario with one steam supply for the turbine-driven auxiliary feedwater pump (TDAFWP) inoperable and one motor-driven auxiliary feedwater pump(MDAFWP) inoperable, a feed line or steam line rupture could challenge the capability of the auxiliary feedwater (AFW) system to provide feedwater. The staff is evaluating conditions of the plant during scenarios such as a feedwater line break (FWLB) or a main steamline break (MSLB) on steam generator (SG) 3 occurs when the MDAFWP 1-2 for SG1 and SG2 is inoperable and the steam supply from SG2 to the TDAFWP is inoperable. This scenario would leave only SG4 supplied by MDAFWP 1-3 available. In final safety analysis report (FSAR) Table 6.5-2, the licensee requires a minimum of 390 gpm auxiliary feedwater (AFW) flow to 2 of the 4 intact SGs to mitigate a main feed line break. Therefore, in such scenarios the licensee would not meet the design requirement as stipulated in their design basis to mitigate an accident. Hence, the request to continue operations for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with one steam supply inoperable coincident with an inoperable motor driven pump may result in such postulated scenario that is beyond the current analyzed design basis.
In its draft safety evaluation report (SER) for TSTF-412, dated April 14, 2006, the staff considered the possible credit for operators having the ability to remotely feed other SGs from the control room using the operable MDAFWP. Figure 1 in the letter dated June 1, 2011, does show a possible cross tie line between the discharge headers of MDAFWPs. However, in their application the licensee does not mention using the cross tie line to mitigate accidents when the plant is in a degraded condition.
The staff requests the licensee to justify their proposed TS that allows for continued operations for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in conditions that result in an unanalyzed condition. Note: the licensee can limit the proposed condition, where the inoperable steam supply could only exist on the SG that can be fed by the operable MDAFWP.
SBPB- RAI -2 Based upon the event that happened June 29, 2009, the Eagle control system has a failure mode in which a single failure affects the operability of both MDAFW pumps. The FSAR section 3.3.2.3.2.7, External Design Class I Piping and Valves, evaluated events related to AFW valves.
However, there is no discussion on the affects of the Eagle system Loop Calculation Processor (LCP) card failure. The licensees design basis for emergency core cooling system addresses shared active components and delineates that components must meet the criteria stated in FSAR 3.1.8.8 Criterion 44. Also, FSAR Section 7.2.2.2.9 describes the standards that the Eagle 21 system must meet.
The staff requests the licensee a) provide an evaluation of the Eagle LCP card failure modes, to include consequences of a latent failure, b) Determine how the Eagle system with its card failures satisfies the design requirements described in FSAR Section 7.2.2.2.9, c) determine if the LCP card failure is a limiting failure, d) Evaluate whether the FSAR should include a discussion on this failure mode. Typically, the discharge valve is mostly closed when starting centrifugal pumps. However, the proposed immediate action directs operators to demand LCV valves full open. e) Describe how this action affects the operation of the MDAFWPs. f) Will upgrading the Eagle 21 Process Protection System address this failure mode?
SBPB- RAI-3 The licensee is proposing a new condition B be added to TS 3.7.5 to accommodate inoperability of the automatic control of the level control valves (LCV) to the SGs from the MDAFWPs. This condition results in both MDAFWP trains being declared inoperable. Current TS follow staff guidance to initiate a plant shutdown when both trains of MDAFWP are inoperable.
The licensee is proposing an immediate action to place both LCVs in manual with a full open demand. The licensee only proposes an immediate action and does not propose a completion time to return the automatic control to operable status. Furthermore, does the immediate action to place both LCVs in manual operation create any other credited actions (and associated completion times) for the dedicated operator? In addition the licensee claims it does not have to analyze for additional equipment failures while in the proposed TS Action statement due to inoperable automatic control of the MDAFW LCV(s). The relaxation of meeting the single failure criterion was intended to be temporary. Since the proposed action statement does not stipulate a completion time to return the automatic control, the system could remain in the degraded condition indefinitely. Therefore, for indefinite operating conditions, the staff requires the licensee to evaluate for additional equipment failures while in this degraded condition.
The staff requests the licensee provide an evaluation of additional equipment failures while the control valves automatic ability is inoperable, or provide a completion time to restore the function and its basis.
SBPB-RAI-4 In Enclosure 2 of letter dated, June 1, 2011, the licensee provides example 4, showing how the individual completion times would be limited to less than the 10 day second limiting condition for operation (LCO) time limit. These action statements are based upon existing TS.
However, the licensee is also proposing changes to TS 3.7.5 in accordance with TSTF-412 and TSTF-340. The licensee does not provide an assessment the new action statements and completion times that will be allowed with the incorporation of these TSTFs.
The intent of the second action statement was to limit not meeting LCO 3.7.5 to less than 10 days. Since the limit of the previous completion times were 7 days and 3 days, then 10 days could not be exceeded without re-entry into first action statement or shutting down the plant.
With the incorporation of TSTF-412 and TSTF-340, there are two provisions under Condition A that allow a 7-day completion time. Together, there exist a possible scenario where the LCO could not be met for up to 14-days. For example, coming out of a refueling outage the licensee tests the steam-driven AFW pump and finds a faulty governor and enters an action statement with a 7 day completion time for an inoperable steam driven AFW pump. After 6 days, they retest the pump and the governor is operable. However, during the test one of the steam admission valves fails. The action statement for an inoperable steam supply allows the licensee 7 days to return it to operable status. If the licensee exits the initial 7 day completion time and starts a new 7 day completion time, the AFW system LCO could possibly not be met for greater than the 10 day limit that exists with the second action statement.
The staff requests the licensee to assess implementation of TSTF-439 under the new conditions being proposed within this amendment to justify whether the second completion time can be removed.
SBPB-RAI-5 In enclosure 2 of letter dated, June 1, 2011, the licensee states, The administrative controls will ensure that a single contiguous occurrence of failing to meet the LCO will not be extended beyond the additive Completion Times of the two Required Actions for restoration unless a risk evaluation is performed, and the risk impact is managed.
TS 3.7.5 and TS 3.8.1 include the statement, LCO 3.0.4b is not applicable. LCO 3.0.4b permits the licensee to perform a risk assessment addressing inoperable systems and components, and based upon the results allows the licensee an exception to the restriction on not changing modes. Based upon the risk importance of AFW and emergency diesel generator (EDG) systems, their respective TS prohibit the use of using a risk assessment to be exempt from the mode change restriction.
The staff requests the licensee justify why administrative controls should allow a risk evaluation for AFW and EDG systems to extend conditions where the system is not meeting the LCO beyond the first completion time.