Letter Sequence RAI |
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EPID:L-2021-LLA-0156, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation (Approved, Closed) |
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MONTHYEARL-21-068, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation2021-08-29029 August 2021 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation Project stage: Request ML21266A2222021-09-23023 September 2021 NRR E-mail Capture - Beaver Valley Loss of Power Diesel Generator Start and Bus Separation Instrument Project stage: Other ML22021A0292021-11-24024 November 2021 Engine Systems Inc., Part 21 - Swing Check Valve Pn ESI50359 Fax Project stage: Request ML21347A8832021-12-16016 December 2021 Audit Plan for Loss of Power Diesel Generator Start and Bus Separation Project stage: Other ML22068A1822022-03-0909 March 2022 NRR E-mail Capture - Beaver Valley Power Station, Units 1 & 2 - Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5 Project stage: RAI ML22094A1152022-04-0404 April 2022 Response to a Request for Additional Information Regarding a Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation (EPID No. L-202 Project stage: Response to RAI ML22108A2922022-05-0202 May 2022 Summary of Regulatory Audit in Support of License Amendment Request to Revise TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation Project stage: Other ML22147A0392022-05-27027 May 2022 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley, Units 1 & 2 Amendment - Revise TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Separation Instrumentation Project stage: Other L-22-159, Supplement to a License Amendment Request Revising Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation2022-08-0202 August 2022 Supplement to a License Amendment Request Revising Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation Project stage: Supplement ML22222A0862022-09-0101 September 2022 Issuance of Amendment Nos. 317 and 208 Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation Project stage: Approval 2022-03-09
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Category:E-Mail
MONTHYEARML24204A0012024-07-17017 July 2024 NRR E-mail Capture - Request for Additional Information Vistraops Fleet Exemption for the Requirements in 10 CFR 50.71 Pertaining to the Submittal of Updated Final Safety Analysis Reports ML24144A1082024-05-22022 May 2024 Acceptance Review Adoption of TSTF-569, Revise Response Time Testing Definition (EPID L-2024-LLA-0059) - Email ML24061A1002024-03-29029 March 2024 Energy Harbor Fleet- Closing of Transaction Between Vistra Operations Company LLC and Energy Harbor Nuclear Corporation (Email) ML24080A3922024-03-20020 March 2024 NRR E-mail Capture - Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Power Station Unit No. 1, and Perry Nuclear Power Plant, Unit No. - Acceptance of Requested Licensing Action Exemption for Final Safety Analysis Report Update ML23129A3122023-05-0909 May 2023 NRR E-mail Capture - Beaver Valley Unit 2 - Verbal Authorization of Alternative Request, 2-TYP-4-RV-06 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 ML23125A1462023-05-0505 May 2023 NRR E-mail Capture - Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23125A1602023-05-0505 May 2023 NRR E-mail Capture - Correction to Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23122A0342023-05-0202 May 2023 NRR E-mail Capture - Beaver Valley - Request for Additional Information Regarding Unit 1 - 180 Day Steam Generator Tube Inspection Report ML23089A1252023-03-30030 March 2023 NRR E-mail Capture - Beaver Valley Upcoming Steam Generator Tube Inservice Inspection ML23079A1202023-03-20020 March 2023 NRR E-mail Capture - Acceptance Review for Beaver Valley 1 & 2 Exemption from Specific Provisions in 10 CFR 50 Appendix H ML23065A0782023-03-0303 March 2023 Final RAIs Regarding the Beaver Valley Emergency LAR (EPID L-2023-LLA-002) - Email ML22321A2392022-11-17017 November 2022 NRR E-mail Capture - (External_Sender) Beaver Valley Power Station, Units 1&2 - Clarification on LAR to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML22312A5912022-11-0808 November 2022 NRR E-mail Capture - Beaver Valley Power Station, Units 1&2 - Request for Additional Information LAR to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML22273A1132022-09-30030 September 2022 NRR E-mail Capture - Acceptance of Requested Licensing Action to Add Full Spectrum LOCA Methodology to COLR ML22277A5122022-09-19019 September 2022 NRR E-mail Capture - (External_Sender) Eh Response to Corrected SE Associated with Beaver Valley Amendments 315 and 205 Changes to the EPP ML22238A2812022-08-25025 August 2022 Request for Additional Information for Beaver Valley Unit 2 - 2R22 Steam Generator 180 Day Report ML22202A4642022-06-29029 June 2022 Emergency Plan Safety Evaluation ML22178A1322022-06-24024 June 2022 Request for Additional Information for Beaver Valley Unit 2 Steam Generator Inspection Report - Fall 2021 Refueling Outage ML22173A0402022-06-21021 June 2022 NRR E-mail Capture - Acceptance of Requested Licensing Action Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML22147A0392022-05-27027 May 2022 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley, Units 1 & 2 Amendment - Revise TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Separation Instrumentation ML22129A0122022-05-0606 May 2022 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley Power Station, Unit 2 Amendment - Correct TS 3.1.7 Change Made by TSTF-547 ML22123A0232022-05-0202 May 2022 NRR E-mail Capture - Acceptance of Requested Licensing Action for Beaver Valley Power Station, Units 1 and 2 - Adoption of TSTF-501, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML22153A5212022-04-15015 April 2022 Email Error in Energy Harbor Submittal and Associated SE for Beaver Valley 1 & 2 - Containment Isolation Valve Relief Request ML22101A0122022-04-0808 April 2022 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley Power Station, Units 1 and 2 Amendment - Revise Technical Specification 5.6.3, Core Operating Limits Report (COLR) ML22087A1302022-03-28028 March 2022 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Pennsylvania Regarding a Beaver Valley Power Station, Units 1 and 2 Amendment - Adopt TSTF-577 ML22080A2512022-03-18018 March 2022 NRR E-mail Capture - (External_Sender) ASME OM Code Case OMN-27, Alternative Requirements for Testing Category a Valves (Non- Piv/Civ) ML22068A1822022-03-0909 March 2022 NRR E-mail Capture - Beaver Valley Power Station, Units 1 & 2 - Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5 ML21344A0392021-12-0909 December 2021 NRR E-mail Capture - Beaver Valley TSTF-577-A Acceptance Review ML21321A3782021-11-16016 November 2021 NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSEL Unit 1 - Acceptance of License Amendment Request Adoption of TSTF-554 EPID-L-2021-LLA-0193 ML21286A7892021-10-0707 October 2021 NRR E-mail Capture - Beaver Valley Acceptance Review for LAR Regarding TS 3.1.7.2 to Correct a Logic Error (L-2021-LLA-0160) ML21266A2222021-09-23023 September 2021 NRR E-mail Capture - Beaver Valley Loss of Power Diesel Generator Start and Bus Separation Instrument ML21259A1642021-09-16016 September 2021 NRR E-mail Capture - Request for Additional Information Regarding the LAR for Core Operating Limits ML21225A0362021-08-12012 August 2021 NRR E-mail Capture - Beaver Valley Unit Nos. 1 and 2 - Acceptance Review Determination Emergency Plan Amendment Request ML21197A0242021-07-15015 July 2021 NRR E-mail Capture - Beaver Valley No. 1 and 2 - Supplemental Information Needed for Acceptance of Requested Licensing Action Emergency Plan Amendment Request ML21137A0082021-05-14014 May 2021 Acceptance of License Amendment Request: Beaver Valley COLR TS LAR ML21119A2152021-04-28028 April 2021 NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSE Unit 1 - Acceptance of Relief Request Proposed Alternative to Use ASME OM Code Case OMN-27 ML21102A1542021-04-0909 April 2021 Request for Additional Information (2nd Round) - Steam Generator Tube Sleeve LAR ML21082A4942021-03-23023 March 2021 Final RAIs for GL 04-02 Closure (Email) ML21068A3502021-03-0909 March 2021 Final Request for Additional Information for Reactor Coolant System (RCS) and Pressure and Tempature Limits Report(Ptlr) TS LAR ML21053A0252021-02-20020 February 2021 NRR E-mail Capture - Request for Additional Information (Rais) - LaSalle Request for Exemption from Pre-Access Drug and Alcohol Testing ML21032A2582021-02-0101 February 2021 Acceptance of License Amendment Request: Beaver Valley Steam Generator Inspection Deferral ML21015A5762021-01-14014 January 2021 Final RAIs for Steam Generator 180 Day Tube Inspection Report ML21014A1142021-01-12012 January 2021 Correction Letter Notification from Licensee ML21007A3732021-01-0707 January 2021 NRR E-mail Capture - (External_Sender) (External) Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, ML21004A1442020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff ML20329A4562020-11-24024 November 2020 Acceptance of License Amendment Request: Beaver Valley RCS and PTLR TS Changes ML20325A2312020-11-20020 November 2020 Request for Additional Information - Beaver Valley Request for Exemption - Part 73 Force-on-Force Exemption ML20324A0872020-11-19019 November 2020 Acceptance of Requested Licensing Action: Beaver Valley Unit 2 Capsule Pull ML20323A0452020-11-17017 November 2020 2.206 Petition 2024-07-17
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24204A0012024-07-17017 July 2024 NRR E-mail Capture - Request for Additional Information Vistraops Fleet Exemption for the Requirements in 10 CFR 50.71 Pertaining to the Submittal of Updated Final Safety Analysis Reports ML24044A1772024-02-14014 February 2024 RAI for 180 Days Steam Generator Report ML23143A0272023-05-23023 May 2023 Licensed Operator Positive Fitness-For-Duty Test ML23125A1602023-05-0505 May 2023 NRR E-mail Capture - Correction to Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23125A1462023-05-0505 May 2023 NRR E-mail Capture - Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23122A0342023-05-0202 May 2023 NRR E-mail Capture - Beaver Valley - Request for Additional Information Regarding Unit 1 - 180 Day Steam Generator Tube Inspection Report ML22312A5912022-11-0808 November 2022 NRR E-mail Capture - Beaver Valley Power Station, Units 1&2 - Request for Additional Information LAR to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML22278A0972022-10-0606 October 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Fire Protection Program Changes ML22178A1322022-06-24024 June 2022 Request for Additional Information for Beaver Valley Unit 2 Steam Generator Inspection Report - Fall 2021 Refueling Outage ML22068A1822022-03-0909 March 2022 NRR E-mail Capture - Beaver Valley Power Station, Units 1 & 2 - Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5 ML22013A7512022-01-13013 January 2022 Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000334/2022010 and 05000412/2022010 ML21292A0482021-10-19019 October 2021 Ti 2515/194 Inspection Documentation Request ML21259A1642021-09-16016 September 2021 NRR E-mail Capture - Request for Additional Information Regarding the LAR for Core Operating Limits ML21124A1322021-05-0404 May 2021 Notification of Conduct of a Fire Protection Team Inspection ML21102A1542021-04-0909 April 2021 Request for Additional Information (2nd Round) - Steam Generator Tube Sleeve LAR ML21082A4942021-03-23023 March 2021 Final RAIs for GL 04-02 Closure (Email) ML21068A3502021-03-0909 March 2021 Final Request for Additional Information for Reactor Coolant System (RCS) and Pressure and Tempature Limits Report(Ptlr) TS LAR ML21053A0252021-02-20020 February 2021 NRR E-mail Capture - Request for Additional Information (Rais) - LaSalle Request for Exemption from Pre-Access Drug and Alcohol Testing ML21015A5762021-01-14014 January 2021 Final RAIs for Steam Generator 180 Day Tube Inspection Report ML21007A3732021-01-0707 January 2021 NRR E-mail Capture - (External_Sender) (External) Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, ML21004A1442020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff ML20290B0082020-10-0808 October 2020 Draft Request for Additional Information - Steam Generator Letter ML20127H8672020-05-0606 May 2020 NRR E-mail Capture - Beaver Valley, Davis-Besse, and Perry - Request for Additional Information Regarding Request for Exemptions from Part 73 Security Requalification Requirements ML20072N0402020-03-12012 March 2020 Request for Additional Information - Control Envelope Habitability LAR ML19192A2222019-07-18018 July 2019 Request for Additional Information Regarding Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML19143A0732019-05-29029 May 2019 FENOC Fleet - Beaver Valley, Units 1 and 2; Davis-Besse, Unit 1, Perry, Unit 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action; Application for Order Consenting to License Transfer and Conforming Amendments ML18242A3642018-08-29029 August 2018 Request for Additional Information (Final) -Steam Generator Technical Specification LAR ML18102B0852018-04-12012 April 2018 NRR E-mail Capture - Follow-up Request for Additional Information (RAI) FENOC FLEET-- Exemption Request for a Physical Barrier Requirement for Beaver ML18043A0102018-02-0909 February 2018 NRR E-mail Capture - FENOC--MG0010-MG0011, MG-0012, MG0013-- Request for Additional Information (RAI) - Exemption Request Security Barrier in Physical Plans ML18024B3642018-01-24024 January 2018 NRR E-mail Capture - Beaver Valley 10 CFR 50.54(f) - NTTF 2.1 SPRA Review ML18019A0722018-01-18018 January 2018 NRR E-mail Capture - Beaver Valley Unit No. 1: Request for Additional Information - Modified Rtpts Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule ML17353A1582017-12-19019 December 2017 NRR E-mail Capture - Request for Additional Information: Beaver Valley Unit No. 1 - Proposed Alternative Request, 1-TYP-4-BA-01 ML17352B2612017-12-18018 December 2017 NRR E-mail Capture - Request for Additional Information: Beaver Valley Unit No. 1 - Proposed Alternative Request, 1-TYP-4-BA-01 ML17303B1582017-11-0707 November 2017 FENOC-Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, Perry Nuclear Power Plant Unit 1 - Generic Letter 2016-01, Request for Supplemental Information ML17256A2502017-09-13013 September 2017 NRR E-mail Capture - Beaver Valley Power Station Units 1&2: Request for Additional Information for Emergency Plan EAL Change to Adopt NEI 99-01, Rev. 6, ML17220A2342017-08-0808 August 2017 E-mail Regarding Request for Additional Information for NFPA 805 License Amendment Request ML17093A7622017-04-10010 April 2017 Request for Additional Information Regarding Emergency Action Level Scheme Change License Amendment Request ML17031A0362017-02-0303 February 2017 Request for Additional Information Regarding Relief Request Numbers PR6 and PR7 ML16333A0162016-12-0202 December 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML16147A2842016-06-14014 June 2016 Request for Additional Infomation Regarding Fall 2015 Refueling Steam Generator Tube Inspections ML16071A1222016-04-0707 April 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML16084A8442016-03-30030 March 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML16060A0122016-02-29029 February 2016 FENOC - Email RAI to Licensee Regarding LAR for Changes to TS 5.3.1 CAC Nos. MF7118, MF7119, and MF7120 ML15320A4132015-11-24024 November 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML15280A0742015-10-0909 October 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML15279A1252015-10-0505 October 2015 Licensed Operator Positive for Fitness-for-Duty-Test ML15181A2142015-07-14014 July 2015 Request for Additional Information Regarding License Amendment Request to Revise Steam Generator Technical Specifications to Reflect TSTF-510 and to Revise Alloy 800 Sleeve Technical Specifications (TAC Nos. MF6054 & MF6055) ML15125A4162015-05-11011 May 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 (TAC Nos. MF3301 & MF3302) ML15016A4392015-01-20020 January 2015 Draft Request for Additional Information ML15007A5582015-01-15015 January 2015 Request for Additional Information Steam Generator Inspection Reports 2024-07-17
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From: Ballard, Brent Sent: Wednesday, March 9, 2022 1:42 PM To: 'Lashley, Phil H' Cc: 'McCreary, Dave M'; Danna, James
Subject:
Beaver Valley Power Station, Units 1&2 - Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5 (EPID L-2021-LLA-0156)
Attachments: Final RAIs for TS 3.3.5 LAR_EPID L-2021-LLA-0156.docx Hi Phil, By letter L-21-068 dated August 29, 2021, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21242A125), Energy Harbor Nuclear Corp (the licensee) submitted a license amendment request (LAR) to Facility Operating License Nos. DPR-66 and NPF-73 for the Beaver Valley Power Station, Unit 1 and Unit 2. The proposed amendment would add notes to technical specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation, required actions C.1 and D.1, and revise Table 3.3.5-1, Loss of Power Diesel Generator Start and Bus Separation Instrumentation.
The NRC staff has reviewed the information provided by the licensee and has determined that additional information is required to be submitted to the NRC to complete the review of the LAR. The requests for additional information (RAIs) are attached to this email. Draft RAIs were provided to the licensee and a clarification call was held on March 9, 2022. Following the clarification call, no changes were made to the draft RAIs. This email and attachment will be made publicly available in ADAMS and a response is due in 30 days (by April 8, 2022) as per agreement at the clarification call.
If you have any questions regarding this matter, please contact me at 301-415-0680 or by email.
Thank you, Brent Brent Ballard Project Manager Plant Licensing Branch 1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 301-415-0680
Hearing Identifier: NRR_DRMA Email Number: 1550 Mail Envelope Properties (BY5PR09MB4627BB411C0400023760F047E00A9)
Subject:
Beaver Valley Power Station, Units 1&2 - Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5 (EPID L-2021-LLA-0156)
Sent Date: 3/9/2022 1:41:59 PM Received Date: 3/9/2022 1:41:00 PM From: Ballard, Brent Created By: Brent.Ballard@nrc.gov Recipients:
"'McCreary, Dave M'" <dmccreary@energyharbor.com>
Tracking Status: None "Danna, James" <James.Danna@nrc.gov>
Tracking Status: None
"'Lashley, Phil H'" <phlashley@energyharbor.com>
Tracking Status: None Post Office: BY5PR09MB4627.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 1553 3/9/2022 1:41:00 PM Final RAIs for TS 3.3.5 LAR_EPID L-2021-LLA-0156.docx 43381 Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION BEAVER VALLEY POWER STATION- UNITS 1 & 2 LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 3.3.5, LOSS OF POWER (LOP) DIESEL GENERATOR (DG) START AND BUS SEPARATION DOCKET NUMBERS 50-334 AND 50-412 EPID No. L-2021-LLA-0156 By letter dated August 29, 2021, (Agency wide Document Access Management System (ADAMS) Accession No. ML21242A125), Energy Harbor Nuclear Corporation (the licensee),
requested an amendment to Facility Operating License Nos. DPR-66 and NPF-73 for the Beaver Valley Power Station (Beaver Valley), Unit Nos. 1 and 2. The proposed amendment would revise the Technical Specification (TS) 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation. In response to the audit plan issued by the Nuclear Regulatory Commission (NRC) on December 15, 2021 (ADAMS Accession No. ML21347A883), the licensee posted calculations relating to the license amendment request (LAR) on a secure web portal on January 4, 2022.
The NRC staff has reviewed the information provided by the licensee on the secure web portal and has determined that following additional information is required to be submitted to the NRC to complete the review of the LAR.
Regulatory Basis Title 10 of the Code of Federal Regulations (CFR) section 50.36, Technical Specifications, requires, in part, that the TS shall be included by applicants for a license authorizing operation of a production or utilization facility. 10 CFR 50.36(c) requires that TS include items in five specific categories related to station operation. These categories are (1) Safety limits, limiting safety system settings, and limiting control settings, (2) Limiting conditions for operation (LCOs)
(3) Surveillance requirements, (4) Design features, and (5) Administrative controls. 10 CFR 50.36(c)(2) requires that LCOs be established.
The licensing basis for LOP DG Start and Bus Separation Instrumentation is captured in the Beaver Valley Updated Final Safety Analysis for both Unit 1 and 2, and the corresponding Technical Specifications.
RAI EEB-1 The NRC staff reviewed the calculations provided by the licensee during the audit and has determined that the following information is needed to support the safety evaluation of the LAR:
a) Summary/Excerpts from Calculation No. 8700-E-345, Rev. 1 for BVPS-1, i.e.,
Background/Objective thru Recommendations [Pages 1 thru 15 of the calculation]
b) Summary/Excerpts from Calculation No. 10080-E-346, Rev. 1 for BVPS-2, i.e.,
Background/Objective thru Recommendations [Pages 1 thru 16 of the calculation]
c) Summary/Excerpts from Calculation No. 8700-E-271, Rev. 3, Addendum 4 for BVPS-1, i.e., Background/Objective thru Conclusions [Pages 6 thru 13 of the calculation]
d) Summary/Excerpts from Calculation No. 10080-E-271, Rev. 1, Addendum 6 for BVPS-2, i.e., Background/Objective thru Conclusions [Pages 5 thru 12 of the calculation]
e) Summary/Excerpts from Calculation No. 10080-E-271, Rev. 1, Addendum 7 for BVPS-2, i.e., Background/Objective thru Conclusions [Pages 4 and 5 of the calculation]
RAI EEB - 2 In the following calculations requested in RAI EEB-1 above, certain overcurrent relay replacements and settings changes have been proposed/recommended:
- Calculation No. 8700-E-345, Rev. 1 for BVPS-1
- Calculation No. 10080-E-346, Rev. 1 for BVPS-2 Please clarify whether the overcurrent relay replacements and settings changes, as proposed /
recommended in the above calculations, have already been implemented. If not, please provide status and timeline for implementation.
RAI EEB - 3 In Calculation No. 8700-E-271, Rev. 3, Addendum 4, for Unit 1 (requested in RAI EEB-1), the following Conclusions are made:
When the SSSTs are unloaded, the secondary-side voltages shall be regulated to within 128.5+/- 1.5 volts.
For accident conditions, the degraded voltage relay time delay shall be greater than 2.5 seconds. This provides adequate time for bus voltages to recover following fast bus transfers and is longer than the voltage transients associated with block starting safety-injection equipment. To minimize the potential for inadvertent relay actuation and to preserve operating margin, the time delay should be as long as permissible. (Refer to Calculation 8700-E-345.)
The dropout voltage of the loss of voltage relays for the safety-related 4160-volt buses shall be less than 80.1 percent of the nominal bus voltage. This ensures that the relays do not drop out when starting large motors, such as the reactor coolant pump motors.
To minimize the potential for inadvertent relay actuation and to preserve operating margin, the dropout setting should be as low as permissible. (Refer to calculation 8700-E-345.) To be within the bounds of the analysis, SSST taps should be raised such that secondary-side voltages are at least 127 volts before starting the A reactor coolant pump. Also, the reset voltages for the loss of voltage relays shall not exceed 90 percent of the nominal bus voltage.
Similarly, in the Calculation No. 10080-E-271, Rev. 1, Addendum 6, for Unit 2 (requested in RAI EEB-1), the following Acceptance Criteria is stated:
Voltage Regulation Band for the SSSTs The SSST voltage regulation scheme is being modified such that the transformer taps are maintained in elevated positions when the transformers are unloaded. This ensures the degraded voltage relays reset following fast bus transfers - without crediting the load tap changers. This addendum establishes an acceptable voltage regulation band for the SSSTs. The minimum voltage is selected such that the degraded voltage relays reset following fast bus transfers. For the degraded voltage relays to reset, voltages at the safety related 4160-volt and 480-volt buses shall recover above 94.14 percent of the Maximum Allowable Dropout Voltage for the Loss of Voltage Relays This addendum determines maximum allowable dropout voltage for the loss of voltage relays. The maximum dropout voltage shall be less than the minimum voltage observed at the safety-related 4160-volt buses during reactor coolant pump starts.
Based on Conclusions/Acceptance Criteria in the above Calculations, the staff has interpreted that by manipulating the SSST [station service transformer] (138 kV-4.36 kV-4.36 kV) taps, the minimum voltage at the safety-related 4160 V buses during the A reactor coolant pump start(s) can be maintained above the maximum allowable dropout voltage for Loss of Voltage Relays (during non-accident conditions).
According to LAR, as a precaution to avoid spurious operation of Loss of Voltage Relays, the licensee has proposed to add a TS Note to TS 3.3.5 Required Actions C.1 and D.1 to facilitate temporary bypassing of the loss of voltage functions 1 and 2 (up to one hour) while starting a reactor coolant pump. The staff interprets that although according to Calculations, adequate voltage at the safety-related buses can be provided by manipulating the SSST [station service transformer] taps, the TS Note would provide additional measure/option to the licensee in case it is not able to provide adequate voltage at the safety-related buses by manipulating the SSST taps during A reactor coolant pump start(s). Please explain the reasons for the Note proposed to be inserted in TS 3.3.5 Required Actions C.1 and D.1 for allowing Functions 1 and 2 to be bypassed up to one hour.
RAI EICB - 4 In the LAR, the licensee requested to revise the loss of voltage (LOV) nominal trip setpoints (NTSs) and allowable values (AVs) of FUNCTION 1, 4160 V Emergency Bus DG start and FUNCTION 2, 4160 V Emergency Bus, Bus Separation. In Section 3.1 of the LAR, Loss of Voltage Relay Settings, the licensee provided the proposed changes of channel statistical allowance (CSA), NTS, and AV values.
Provide the following information regarding the proposed LOV setpoint and allowable values for Function 1 and 2.
a) Summary/excerpts from Calculation No. 8700-DEC-0212 Rev. 2 for Unit 1, 4.1 kV Emergency Bus Undervoltage functions (Trip Feed, Emergency Diesel Generator Start) [Pages 1 - 8 of the calculation].
b) Summary/excerpts from Calculation No.10080-DEC-0215 Rev. 2 for Unit 2, 4.1 kV Emergency Bus Undervoltage functions (Trip Feed, Emergency Diesel Generator Start) [Pages 1 - 8 of the calculation].
NRC staff will review the calculations that determined the proposed LOV, NTSs, AVs, and the uncertainties associated with these settings for Functions 1 and 2, that are shown in the Calculations 10080-DEC-0215 Rev. 2 and 8700-DEC-0212 Rev. 2.
RAI EICB-5 In the LAR, the licensee proposes to add Function 5, 4160 V Emergency Bus, Bus Separation, and Function 6, 480 V Emergency Bus, Bus Separation. The AV voltages remain the same as Functions 3 and 4, only the time delay differs. In Section 3.2, Degraded Voltage Time Delay with Safety Injection Signal,, the licensee provided the proposed values of the CSA, NTS, and AV values of the Degraded Voltage Relay (DVR) time delays for Functions 5 and 6.
Please provide the following information:
- 1. Summary/Excerpts of the Calculation E-529 Rev. 1, for BVPS-1 and BVPS-2, LOV Degraded Voltage (with safety injection signal) [Pages 1 - 7 of the calculation].
- 2. The relevant calculation information that determined the new DVR time delay setpoints, and the uncertainties associated with these settings for Functions 5 and 6 that are as shown in the Calculations E-529 Rev. 1.