Letter Sequence RAI |
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EPID:2019, CoC 1042 Eos A2 Issuance Package to Tn (Open) EPID:L-2019-LLA-0223, License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter Testing Program (Vftp), and 5.5.14, Control Room Envelope. (Approved, Closed) |
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MONTHYEARL-19-099, License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter Testing Program (Vftp), and 5.5.14, Control Room Envelope.2019-10-20020 October 2019 License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter Testing Program (Vftp), and 5.5.14, Control Room Envelope. Project stage: Request ML19323F4992019-11-19019 November 2019 Acceptance Review for Control Room Envelope Habitability Control LAR (Epids L-2019-LLA-0223) Project stage: Acceptance Review ML20072N0402020-03-12012 March 2020 Request for Additional Information - Control Envelope Habitability LAR Project stage: RAI L-20-097, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity,.2020-04-14014 April 2020 Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity,. Project stage: Supplement L-20-161, Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter .2020-06-0909 June 2020 Response to Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter . Project stage: Response to RAI ML20197B4802020-07-15015 July 2020 Acceptance Review for Beaver Valley - Steam Generator Tube Sleeve Inspection and Repair LAR Project stage: Acceptance Review ML20213A7312020-09-23023 September 2020 Issuance of Amendment Nos. 305 and 195 to Modify Primary and Secondary Coolant Activity Technical Specifications Project stage: Approval ML20288A9162020-09-30030 September 2020 E-mail Regarding Corrections to Issuance of Amendment Nos. 305 and 195 to Modify Primary and Secondary Coolant Activity Technical Specifications Project stage: Other ML20285A2662020-10-21021 October 2020 Correction to Safety Evaluation for Amendment Nos. 305 and 195 Issued September 23, 2020, Modify Primary and Secondary Coolant Activity Technical Specifications Project stage: Approval L-20-293, Response Correction to a Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.162020-11-30030 November 2020 Response Correction to a Request for Additional Information Regarding License Amendment Request to Modify Technical Specifications 3.4.16 Project stage: Request ML21244A2992021-09-15015 September 2021 4 NUHOMS_EOS_Amd_2_FSER Project stage: Other ML21244A2952021-09-15015 September 2021 CoC 1042 Eos A2 Issuance Package to Tn Project stage: Request ML21244A2982021-09-15015 September 2021 3 Final Tech Specs - CoC 1042 Amd 2 Rev 7 Project stage: Other ML21244A2972021-09-15015 September 2021 2 Final CoC 1042 Amendment 2 Issued to Tn Americas, LLC Project stage: Other ML21244A2962021-09-15015 September 2021 1 Issuance Letter_For Tn Americas, LLC CoC No. 1042 for Amendment 2 for NUHOMS Eos System Project stage: Other 2020-04-14
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Category:E-Mail
MONTHYEARML23129A3122023-05-0909 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 ML20310A1632020-11-0404 November 2020 Acceptance of Requested Licensing Action: Beaver Valley One-time Exemption App. B Sect. VI.C.3.(I)(1) Force on Force (COVID-19) ML20307A5762020-11-0202 November 2020 Acceptance of Requested Licensing Action: Beaver Valley Adv Non-Conservative TS LAR ML20297A3222020-10-22022 October 2020 Final Request for Additional Information - Steam Generator Tube Sleeve LAR ML20283A7722020-10-0909 October 2020 Submittal of Pennsylvania Letter Requesting Exemption from Biennial Exercise Requirements for Pennsylvania Nuclear Power Plants in Calendar Year 2020 2023-05-09
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23143A0272023-05-23023 May 2023 Licensed Operator Positive Fitness-For-Duty Test 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 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 ML14218A7622014-12-11011 December 2014 RAI Request to Implement 10 CFR 50.61a Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events ML14316A3902014-11-14014 November 2014 Request for Additional Information Review of Licensee Security Plans 2023-05-05
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From: Tobin, Jennifer To: rpenfield@firstenergycorp.com Cc: Lashley, Phil H (EH); McCreary, Dave M (EH)
Subject:
Beaver Valley Units 1 and 2 - Request for Additional Information - Control Envelope Habitability LAR (EPID L-2019-LLA-0223)
Date: Thursday, March 12, 2020 11:00:00 AM
Dear Mr. Penfield,
By letter dated October 20, 2019, First Energy Nuclear Operating Company. (FENOC), the licensee, submitted a license amendment request to revise Beaver Valley Power Station Units 1 and 2 Technical Specifications (TS). The requested changes revise TS 3.4.16, RCS Specific Activity, 3.7.13 Secondary Specific Activity, 5.5.7, Ventilation Filter Testing Program (VFTP), and 5.5.14, Control Room Envelope Habitability Program. The proposed changes to TSs 3.4.16 and 3.7.13 would reduce the allowed reactor coolant system and secondary coolant specific activities for Unit 2 and make administrative changes to Unit 1 TS. The proposed changes to TS 5.5.7 for the control room emergency ventilation system (CREVS) change the acceptance criteria for the CREVS penetration and system bypass requirement and CREVS charcoal adsorber removal efficiency based on the licensees evaluation in the LAR. The proposed change to the Control Room Envelope (CRE) Habitability Program in TS 5.5.14 would add a note allowing a one-time extension of three years to the unfiltered air inleakage test frequency following the test failure that occurred in October 2017.
Regulatory Analysis Basis (one-time extension of testing)
Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36(b) requires each license authorizing operation of a production or utilization facility of a type described in § 50.21 or § 50.22 will include technical specifications. The technical specification will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to § 50.34.
In Section 3.4 of the LAR the licensee provided an evaluation of the proposed change to add a note allowing a one-time extension of three years to the unfiltered air inleakage test frequency following the test failure that occurred in October 2017.
Licensee clarifications and explanations of items in section 3.4 of the LAR are required for the staff to make a conclusion regarding whether or not the TS, as amended by the proposed changes, will continue to be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto provide thereby continuing to provide reasonable assurance of adequate protection of public health and safety.
- 1) The licensee stated the following in the second paragraph of Section 3.4: FENOC has high confidence that the CRE has not continued to degrade based upon improving test results between 2015 and 2017 due to plant modifications and system rebalancing efforts for the normal and recirculation (isolation) modes. However the issue that triggered the need for a test after 3 years is the failure in 2017. It does not appear appropriate to justify the proposed test extension using test results prior to the failure in 2017. Please provide an appropriate justification for the proposed test extension or revise the request to not include a proposed test extension.
- 2) The licensee also made the following statements in Section 3.4 of the LAR:
For the Unit 1 and Unit 2 pressurization (emergency) modes, the step change that occurred between 2008 and 2015 has remained essentially unchanged over the most recent two-year test period; therefore, it is not anticipated to degrade any further. Additionally, the proposed acceptance criteria in this license amendment request are expected to provide sufficient margin for potential CRE boundary degradation in the future.
While the first sentence appears to support the justification for the need for the proposed changes, the second sentence appears to refute the statement that further boundary degradation is not expected and therefore refute the justification for the need for the proposed changes. Please clarify whether or not the licensee expects the boundary to continue to degrade and why a test extension would be appropriate.
- 3) In the third paragraph of Section 3.4 of the LAR the licensee stated:
Therefore, with the last test performed in October 2017, the next CRE unfiltered air inleakage would be performed no later than April 2025 with the current provisions of TS 5.5.14.f included. FENOC intends to perform the three-year self-assessment that would be required by Figure 1 in RG 1.197 as if the periodic CRE testing were on the normal six-year cycle.
Please provide an explanation regarding a proposed next test date of April 2025. Given the failure occurred in October 2017 and the program suggests a test 3 years later (October 2020) and the request for a 3 year extension in addition to the program suggested test date would appear to indicate a proposed nominal test date of October 2023.
- 4) It does not appear appropriate to use the 25% extension of TS 5.5.14.f for any amount of time associated with the proposed request for a three year extension. Please provide further justification for use of the 25% extension for the entire proposed nominal 6 year interval or revise the request to not use the extension.
Regulatory Analysis Basis (revision of accident dose consequence analyses)
The proposed changes in this LAR will affect the current licensing basis (CLB) accident dose consequence analyses for the eight design basis accidents: LOCA; control rod ejection accident (CREA); main steam line break (MSLB) outside of containment; steam generator tube rupture (SGTR); reactor coolant pump (RCP) locked rotor accident (LRA);
loss of alternating current power (LACP); fuel handling accident (FHA) in the fuel pool or in containment; and small line break (SLB) accident outside of containment. FENOC stated the waste gas system rupture (failure) events previously addressed in Amendment Nos.
275 (BVPS-1) and 156 (BVPS-2) was not addressed in this LAR as the proposed changes have been assessed and may be implemented accordance with 10 CFR 50.59.
As stated in NRC Regulatory Issue Summary (RIS) 2006-04, Experience with Implementation of Alternative Source Terms, dated March 7, 2006 (ADAMS Accession No. ML053460347), the level of detail contained in LARs should contain enough details (e.g.,
assumptions, computer analyses input and output) to allow the NRC staff to confirm the dose analyses results in independent calculations. The provision of sufficient detail is necessary for the NRC staff to be able to conclude, with reasonable assurance, whether
the licensees analyses and changes are acceptable.
RG 1.183, Section 1.5, Submittal Requirements, states in part, that, The amendment request should describe the licensees analyses of the radiological and nonradiological impacts of the proposed modification in sufficient detail to support review by the NRC staff.
The staff recommends that licensees submit affected FSAR pages annotated with changes that reflect the revised analyses or submit the actual calculation documentation. If the licensee has used a current approved version of an NRC-sponsored computer code, the NRC staff review can be made more efficient if the licensee identifies the code used and submits the inputs that the licensee used in the calculations made with that code.
NUREG-0800 Standard Review Plan (SRP) Section 15.0.1, Radiological Consequence Analyses Using Alternative Source Terms, dated July 2000 (ADAMS Accession No. ML003734190) states, in part, that, models, assumptions and parameter inputs used by the licensee should be reviewed to ensure that the conservative design basis assumptions outlined in RG 1.183 have been incorporated. In addition, SRP Section 15.0.1 states, in part, that, independent calculations should be performed as necessary to conclude, with reasonable assurance, that the applicants analyses are acceptable. , Comparison of Important Analysis Parameters, of the proposed LAR presents a comparison between the design input values used in the CLB radiological dose consequence analyses, for BVPS-1 and BVPS-2, to those used in the radiological dose consequence analyses. The information is arranged by design basis accident in tabular format. FENOC stated only those design parameters that have undergone a change are listed. As a result of the proposed LAR changes, the calculated radiological doses for several design basis accidents appear to either challenge the NRCs regulatory dose criteria and/or substantially increase in comparison with those in the CLB.
- 5) The NRC staff intends to perform independent calculations, as discussed above, to support its evaluation of this LAR to facilitate the staffs review, please provide additional information describing, for each design basis accident and unit affected by the proposed LAR changes, all the basic parameters used in the radiological dose consequence analyses. To support a timely NRC review, this information should include the CLB value, the revised value where applicable, the basis for any changes to the CLB on all basic parameters whether or not the individual parameter is being changed in separate tables for each affected design basis accident and unit.
- 6) Please provide additional information describing the models, assumptions, and parameter inputs used in BVPS calculations of the radiological dose consequence analyses affected by the proposed LAR changes for the revised LOCA, SGTR, and RCP LRA. Alternatively, to support a timely NRC review, the calculation packages which typically contain this information and in sufficient detail may be provided for the selected design basis accidents.
Please submit your response to this request for additional information by April 13th. A clarification call on the draft RAI was held March 11th and resulted in the deletion of one sentence in which NRC determined that information was not needed for the review.
If you have questions please dont hesitate to contact me.
Thanks!
-Jenny