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Category:E-Mail
MONTHYEARML24002A7382024-01-0202 January 2024 NRR E-mail Capture - Request for Additional Information Regarding Duke'S August 20, 2023, License Amendment Request for Robinson, Unit 2 ML23262B4502023-09-19019 September 2023 NRR E-mail Capture - H. B. Robinson Steam Electric Plant, Unit 2 - Acceptance of License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures Based on Leak-Before-Break Methodology ML23220A2342023-08-0808 August 2023 NRR E-mail Capture - Robinson, Unit 2 - Acceptance Review Results for Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule ML23172A0132023-06-20020 June 2023 Duke Fleet - Correction to June 2, 2023, Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23153A1892023-06-0202 June 2023 Duke Fleet - Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23131A4192023-05-10010 May 2023 003 Radiation Safety Baseline Inspection Information Request ML23124A1212023-05-0404 May 2023 Acceptance of Requested Licensing Action Duke Fleet Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23073A2282023-03-13013 March 2023 Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review ML23058A0562023-02-27027 February 2023 Acceptance of Amendment to Revise Surveillance Frequencies for RCS Pressure Isolation Valve Operational Leakage Testing and Reactor Trip System Instrumentation ML23048A1512023-02-16016 February 2023 Acceptance Review - Proposed Alternative for Steam Generator Welds (L-2023-LLR-0003) ML23011A0152023-01-11011 January 2023 NRR E-mail Capture - Request for Additional Information to Duke'S Request for Robinson to Add Feedwater Isolation Function to TS 3.3.2 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML22285A1552022-10-12012 October 2022 NRR E-mail Capture - H. B. Robinson, Unit 2 - Acceptance of License Amendment Request Regarding the Addition of Feedwater Isolation Function to TS 3.3.2 and Removal of Obsolete Content from TS 2.1.1.1 and TS 5.6.5.b ML22222A1082022-08-10010 August 2022 NRR E-mail Capture - Request for Additional Information Regarding Duke'S Request to Remove 4.160 Kv Bus 2 from Surveillance Requirement 3.8.1.16 ML22146A3652022-05-25025 May 2022 Acceptance of Requested Licensing Action License Amendment Request for Application to Revise Surveillance Requirement 3.8.1.16 ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22112A1482022-04-22022 April 2022 Correction_H. B. Robinson Steam Electric Plant, Unit 2 - Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 ML22080A0042022-03-18018 March 2022 Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22038A1572022-02-0707 February 2022 NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2 ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22012A3662022-01-12012 January 2022 Acceptance of Requested Licensing Action License Amendment Re2uest for Application to Revise Technical Specification to Adopt TSTF-577, Revised Frequencies for Steam Generating Tube Inspections ML22005A0872022-01-0505 January 2022 Acceptance of Requested Licensing Action Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/Temperature Limit Cooldown Curves ML21361A0122021-12-23023 December 2021 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Relocate Emergency Operations Facility ML21295A2992021-10-22022 October 2021 Document Request for Robinson Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021004 ML21286A6612021-10-13013 October 2021 Acceptance for Review of Proposed Alternative ISI-05-017 for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML21119A2272021-04-29029 April 2021 NRR E-mail Capture - Robinson Relief Request Acceptance Review Results; IST-RR-9, EPID: L-2021-LLR-0024 ML21116A2592021-04-26026 April 2021 NRR E-mail Capture - Robinson Relief Request Acceptance Review Results; IST-RR-8, EPID: L-2021-LLR-0023 ML21116A2582021-04-26026 April 2021 NRR E-mail Capture - Robinson Relief Request Acceptance Review Results; IST-RR-3, EPID: L-2021-LLR-0020 ML21113A1312021-04-23023 April 2021 NRR E-mail Capture - Robinson Relief Request Acceptance Review Results; IST-RR-5, EPID: L-2021-LLR-0021 ML21110A1462021-04-20020 April 2021 NRR E-mail Capture - Robinson Relief Request Acceptance Review Results: IST-RR-7, EPID: L-2021-LLR-0022 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML20353A1302020-12-18018 December 2020 2021 Hbr 50.59 Info Request - E-mail Request- Upcoming 50.59 Inspection (IP71111.17T)- Week of March 1-5, 2021 ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20297A3102020-10-13013 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0191 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-5120, IWA-5213, IWA-5241, IWA-5242, and IWA-5250 (L-2020-LLR-0126) ML20297A3082020-10-0707 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0263 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI for Repair/Replacement (L-2020-LLR-0124) ML20297A3092020-10-0606 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0262 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-4540(b) (L-2020-LLR-0125) ML20063M1942020-02-21021 February 2020 NRR E-mail Capture - Accepted for Review - Robinson Unit 2 One-Time Pressure Relief Valve Test Frequency Extension EPID: L-2020-LLR-0019 ML20085F9312020-02-20020 February 2020 SPRA - Spr Audit Questions - 2nd Batch ML20049A0342020-02-16016 February 2020 NRR E-mail Capture - Accepted for Review - Robinson Unit 2 to Correct Administrative Renewed Facility Operating License Error in the 50.69 LAR EPID: L-2020-LLL-0000 ML20063L4562020-02-0404 February 2020 NRR E-mail Capture - RAI - Robinson Relief Req Rx Vessel Cold Leg Nozzle Dissimilar Meter Butt Weld Inspection Interval EPID L-2019-LLR-0072 ML20087N6632020-02-0303 February 2020 SPRA - Spr Audit Questions Redacted ML20027C2042020-01-27027 January 2020 Audit Documents Needed for the Robinson Seismic Probabilistic Risk Assessment Review - FLEX and HRA References ML20015A1892020-01-13013 January 2020 Audit Documents Needed for the Robinson SPRA Review - Fragility Analysis ML20009C0922020-01-0808 January 2020 Audit Documents Needed for the Robinson SPRA Review - Seismic Hazard Analysis ML19365A0482019-12-30030 December 2019 Request for Eportal Access for Audit Review of the Robinson SPRA Supporting Documents ML19365A0462019-12-18018 December 2019 Audit Documents Needed for the Robinson SPRA Review ML19288A2942019-10-15015 October 2019 NRR E-mail Capture - RAIs for Robinson Revision to RPV Surveillance Program Withdrawal Schedule ML19283A0372019-09-26026 September 2019 Draft Requests for Additional Information for H.B. Robinson LAR to Revise TS 3.8.2, AC Sources - Shutdown, SR 3.8.2.1 ML19235A1202019-08-21021 August 2019 Acceptance Review for Robinson LAR to Add Feedwater Bypass Valve to TS 3.7.3 (L-2019-LLA-0170) 2024-01-02
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24002A7382024-01-0202 January 2024 NRR E-mail Capture - Request for Additional Information Regarding Duke'S August 20, 2023, License Amendment Request for Robinson, Unit 2 ML23235A0552023-08-23023 August 2023 Notification of an Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000261/2023010) and Request for Information (RFI) ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23047A4512023-02-21021 February 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000261/2023402 ML23011A0152023-01-11011 January 2023 NRR E-mail Capture - Request for Additional Information to Duke'S Request for Robinson to Add Feedwater Isolation Function to TS 3.3.2 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML22222A1082022-08-10010 August 2022 NRR E-mail Capture - Request for Additional Information Regarding Duke'S Request to Remove 4.160 Kv Bus 2 from Surveillance Requirement 3.8.1.16 ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22112A1482022-04-22022 April 2022 Correction_H. B. Robinson Steam Electric Plant, Unit 2 - Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 ML22080A0042022-03-18018 March 2022 Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML20353A1312020-12-18018 December 2020 2021 Hbr 50.59 Info Request ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20191A2122020-07-0909 July 2020 012 FPTI Notification Letter ML20063L4562020-02-0404 February 2020 NRR E-mail Capture - RAI - Robinson Relief Req Rx Vessel Cold Leg Nozzle Dissimilar Meter Butt Weld Inspection Interval EPID L-2019-LLR-0072 ML20022A1942020-01-22022 January 2020 Emergency Preparedness Program Inspection Request for Information ML19365A0462019-12-18018 December 2019 Audit Documents Needed for the Robinson SPRA Review ML19288A2942019-10-15015 October 2019 NRR E-mail Capture - RAIs for Robinson Revision to RPV Surveillance Program Withdrawal Schedule ML19288A2462019-09-26026 September 2019 Request for Additional Information Regarding Change to Surveillance Requirement 3.8.2.1 H.B. Robinson Unit No. 2 ML19283A0372019-09-26026 September 2019 Draft Requests for Additional Information for H.B. Robinson LAR to Revise TS 3.8.2, AC Sources - Shutdown, SR 3.8.2.1 ML19072A0292019-03-13013 March 2019 50.69 LAR RAIs ML19011A1372019-01-10010 January 2019 NRR E-mail Capture - Duke Energy Fleet RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML19007A3422018-12-21021 December 2018 NRR E-mail Capture - Duke Energy Fleet Draft RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML18291A6442018-10-17017 October 2018 NRR E-mail Capture - Robinson RAIs - Duke Energy 10 CFR 50.46 Annual Report ML18288A0192018-10-12012 October 2018 NRR E-mail Capture - Robinson RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 (EPID L 2018-LLA-0095) and LAR to Adopt TSTF-425 ML18274A2632018-09-28028 September 2018 NRR E-mail Capture - Robinson Draft RAIs - LAR to Allow Implementation of the Provisions 10 CFR 50.69 (EPID L 2018-LLA-0095) and LAR to Adopt TSTF-425 ML18211A6042018-07-30030 July 2018 NRR E-mail Capture - Robinson Supplemental RAI - LAR to Revise TS to Add a 2nd Qualified Offsite Power Circuit and Revise UFSAR to Operate LTCs in Automatic Mode (CAC No. MG0276; L-2017-LLA-0308) ML18206B0612018-07-25025 July 2018 NRR E-mail Capture - Draft Robinson Supplemental RAI - LAR to Revise TS to Add a 2nd Qualified Offsite Power Circuit and Revise UFSAR to Operate LTCs in Automatic Mode (CAC No. MG0276; L 2017-LLA-0308) ML18116A1052018-04-25025 April 2018 NRR E-mail Capture - Harris/Robinson RAIs - Change Technical Specifications to Support Performance of Core Reload Design and Safety Analyses (L-2017-LLA-0356) ML18108A7602018-04-18018 April 2018 NRR E-mail Capture - Harris/Robinson Draft RAIs - Change Technical Specifications to Support Performance of Core Reload Design and Safety Analyses (L-2017-LLA-0356) ML18108A7592018-04-18018 April 2018 NRR E-mail Capture - Robinson RAIs - LAR to Revise TS to Add a 2nd Qualified Offsite Power Circuit and Revise UFSAR to Operate LTCs in Automatic Mode (CAC No. MG0276; L 2017-LLA-0308) ML18102B0812018-04-12012 April 2018 NRR E-mail Capture - Draft Robinson RAIs - LAR to Revise TS to Add a 2nd Qualified Offsite Power Circuit and Revise UFSAR to Operate LTCs in Automatic Mode (CAC No. MG0276; L 2017-LLA-0308) ML18074A0052018-03-15015 March 2018 Heat Sink Emailed Heat Sink RFI Request 2018 ML17345A8772017-12-11011 December 2017 NRR E-mail Capture - Harris and Robinson Supplemental RAI - LAR to Adopt DPC-NE-3009-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis, (L-2016-LLA-0012) ML17339A0722017-12-0404 December 2017 NRR E-mail Capture - Subject: Harris and Robinson Draft Supplemental RAIs - LAR to Adopt DPC-NE-3009-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis, (L-2016-LLA-0012) ML17248A0182017-08-31031 August 2017 NRR E-mail Capture - Robinson RAIs - Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) ML17235A2612017-08-22022 August 2017 NRR E-mail Capture - Robinson RAIs - Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) ML17192A4842017-07-11011 July 2017 NRR E-mail Capture - Duke Energy Fleet RAIs Alternative for Reactor Pressure Vessel Flange Threads Examination (MF9513 to MF9521) ML17114A0462017-04-21021 April 2017 Notification of Inspection and Request for Information ML16288A0782016-10-26026 October 2016 Shearon Harris Nuclear Power Plant, Unit 1, and H.B. Robinson Steam Electric Plant, Unit No. 2 - Redacted, Request for Additional Information Re: Request to Adopt DPC-NF-2010 and DPC-NF-2011 Nuclear Design Methodology (CAC Nos. MF7693 and MF7694) ML16130A5982016-05-0505 May 2016 Notification of Inspection and Request for Information ML16048A3492016-03-0202 March 2016 RAI Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants ML16019A0532016-02-0808 February 2016 Request for Additional Information Related to the Pressurized Water Reactors Internals Program Plan for Aging Management of Reactor Internals ML16026A0512016-01-25025 January 2016 Robinson EP RFI 2016-001 ML15344A0302015-12-17017 December 2015 Request for Additional Information Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5, Thermal Hydraulic Statistical Core Design Methodology (MF5872/MF5873) ML15215A6512015-08-10010 August 2015 Duke Energy Progress, Inc., for H. B. Robinson, Unit 2 and Shearon Harris, Unit 1, Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5 (TAC Nos. MF5872 ML15009A3352015-01-0808 January 2015 Requalification Program Inspection - H.B. Robinson Nuclear Plant RNP-RA/14-0118, Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Re-Evaluations Related to Southeastern Catalog Changes2014-11-12012 November 2014 Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Re-Evaluations Related to Southeastern Catalog Changes ML14268A5162014-10-23023 October 2014 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Re-evaluation Related to Southeastern Catalog Changes ML14057A6502014-02-26026 February 2014 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection 2024-01-02
[Table view] |
Text
1 NRR-PMDAPEm Resource From:Galvin, Dennis Sent: Tuesday, August 22, 2017 5:07 PM To:Pilo, Tony
Subject:
Robinson RAIs - Change Technical Specification Surveillance Requirement Frequencies
to Support 24-Month Fuel Cycles (MF9544)
Attachments:
Robinson LAR Month Fuel Cycle - Draft RAI Letter 1 2017-08-22 MF9544.pdfMr. Pilo, By letter dated April 3, 2017, as supplemented by letters dated April 3, 2017 and May 2, 2017, (Agencywide Documents Access and Management System Accession Nos. ML17093A787, ML17093A796, and ML17122A223) Duke Energy Progress, LLC (the licensee) submitted a license amendment request (LAR) for H. B. Robinson Steam Electric Plant Unit No. 2. The proposed amendment would revise certain Technical Specifications (TS) Surveillance Requirements (SRs) and administrative controls program frequencies from 18 months to 24 months to support 24-month fuel cycle operations.
To complete its review, the NRC staff has prepared requests for additional information (RAIs). The LAR divided the proposed TS changes into the following two categories: (1) changes to surveillance frequencies other than channel calibrations, identified as "Non-Calibration Changes," and (2) changes involving the channel calibration frequency identified as "Channel Calibration Changes." These draft RAIs are regarding non-calibration changes. RAIs regarding channel calibration changes, if any, will be provided by se parate correspondence. Please see the attached RAIs in DRAFT form.
Please submit your response to these RAIs within 30 days of this email. If you need a clarification call for the attached draft RAIs, or you need to change the RAI response due date, please contact me at (301) 415-6256.
Respectfully, Dennis Galvin Project Manager U.S Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Operating Reactor Licensing Licensing Project Branch 2-2 301-415-6256 Docket Nos. 50-261 Hearing Identifier: NRR_PMDA Email Number: 3682 Mail Envelope Properties (Dennis.Galvin@nrc.gov20170822170700)
Subject:
Robinson RAIs - Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) Sent Date: 8/22/2017 5:07:26 PM Received Date: 8/22/2017 5:07:00 PM From: Galvin, Dennis Created By: Dennis.Galvin@nrc.gov Recipients: "Pilo, Tony" <Tony.Pilo@duke-energy.com> Tracking Status: None
Post Office: Files Size Date & Time MESSAGE 1635 8/22/2017 5:07:00 PM Robinson LAR Month Fuel Cycle - Draft RAI Letter 1 2017-08-22 MF9544.pdf 156783 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT FREQUENCIES TO SUPPORT 24-MONTH FUEL CYCLES DUKE ENERGY PROGRESS, LLC H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 CAC NOS. MF9544 General RAI - 1 In Enclosure 1 of Generic Letter (GL) 91-04, "Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle," dated April 2, 1991 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML031140501), it is stated, in part:
Licensees should evaluate the effect on safety of an increase in 18-month surveillance intervals to accommodate a 24-month fuel cycle. This evaluation should support a conclusion that the effect on safety is small. Licensees should confirm that historical plant maintenance and surveillance data support this conclusion.
By letter dated April 3, 2017, as supplemented by letters dates April 3, 2017 and May 2, 2017, (ADAMS Accession Nos. ML17093A787, ML17093A796, and ML17122A223) Duke Energy Progress, LLC (the licensee) submitted a license amendment request (LAR) for H. B. Robinson Steam Electric Plant Unit No. 2 (Robinson). Attachment 8, "Non-Calibration Surveillance Failure Analysis" to the LAR lists the same three unique failure histories, as listed below, for a significant number of Surveillance Requirements (SRs):
- a. On 5/3/2007, CB-1 on Battery Charger A-1 failed to trip when power was removed from the charger.
- b. On 10/29/2008, input breaker CB1 on Battery Charger B-1 failed to trip on loss of alternating current voltage.
- c. On 6/20/2015, when placing the PZR HTR BACK-UP GROUP "A" switch to ON, the RTGB ON indication did not illuminate as expected.
The LAR states that the test procedure and preventive maintenance task implementing these SRs are very large and test a wide range of equipment. It is not clear how these failures are representative enough to demonstrate the lack of impact of the change in SR frequency for the wide range of and diversity of the SRs.
(1.) Clarify the shared characteristics of these SRs that allow them to be treated as a group.
(2.) Confirm that the same failure histories applies to all the SRs. (3.) Alternatively, provide the appropriate failure histories for the SRs.
The SRs with the same unique failure histories are below.
TS 3.3.1 Reactor Protection System (RPS) Instrumentation SR 3.3.1.14 Perform TADOT. Note: Verification of setpoint is not required.
Table 3.3.1-1, Function 16: Safety Injection (SI) Input from Engineered Safety Feature Actuation System (ESFAS)
TS 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation SR 3.3.2.3 Perform MASTER RELAY TEST. SR 3.3.2.5 Perform SLAVE RELAY TEST.
Table 3.3.2-1, Function 1.b: Safety Injection - Automatic Actuation Logic and Actuation Relays Table 3.3.2-1, Function 3.a.2: Containment Isolation - Phase A Isolation - Automatic Actuation Logic and Actuation Relays Table 3.3.2-1, Function 5.a: Feedwater Isolation - Automatic Actuation Logic and Actuation Relays SR 3.3.2.6 Perform TADOT. Note: Verification of setpoint is not required.
Table 3.3.2-1, Function 1.a: Safety Injection - Manual Initiation Table 3.3.2-1, Function 3.a.1: Containment Isolation - Phase A Isolation - Manual Initiation TS 3.3.3 Post Accident Monitoring (PAM) Instrumentation SR 3.3.3.3 Perform TADOT. Note: Verification of setpoint is not required.
Table 3.3.3-1, Function 9: Containment Isolation Valve Position TS 3.3.6 Containment Ventilation Isolation Instrumentation SR 3.3.6.3 Perform MASTER RELAY TEST.
SR 3.3.6.5 Perform SLAVE RELAY TEST.
Table 3.3.6-1, Function 2: Automatic Actuation Logic and Actuation Relays SR 3.3.6.6 Perform TADOT. Note: Verification of setpoint is not required.
Table 3.3.6-1, Function 1: Manual Initiation TS 3.3.8 Auxiliary Feedwater (AFW) System Instrumentation SR 3.3.8.3 Perform TADOT.
Table 3.3.8-1, Function 3: Automatic Actuation Logic and Actuation Relays TS 3.4.9 Pressurizer SR 3.4.9.2 Verify capacity of required pressurizer heaters is 125KW SR 3.4.9.3 Verify required pressurizer heaters are capable of being powered from an emergency supply TS 3.5.2 Emergency Core Cooling Systems (ECCS) - Operating SR 3.5.2.4 Verify each ECCS automatic valve in the flow path that is locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal SR 3.5.2.5 Verify each ECCS pump starts automatically on an actual or simulated actuation signal TS 3.6.3 Containment Isolation Valves
SR 3.6.3.5 Verify each automatic containment isolation valve that is not locked, sealed or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal TS 3.6.6 Containment Spray and Cooling Systems SR 3.6.6.7 Verify each containment cooling train starts automatically on an actual or simulated actuation signal TS 3.6.8 Isolation Valve Seal Water (IVSW) System SR 3.6.8.4 Verify each automatic valve in the IVSW System actuates to the correct position on an actual or simulated actuation signal
TS 3.7.4 Auxiliary Feedwater (AFW) System SR 3.7.4.3 Verify each AFW isolation valve that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal. Note: Not applicable in MODE 4 when steam generator is being used for heat removal.
SR 3.7.4.4 Verify each AFW pump starts automatically on an actual or simulated actuation signal - Note 1. Not required to be performed for the steam driven AFW pump until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after 100 psig in the steam generator. 2. Not applicable in MODE 4 when steam generator is being used for heat removal. TS 3.7.7 Service Water System (SWS)
SR 3.7.7.3 Verify each SWS pump and SWS booster pump starts automatically on an actual or simulated actuation signal.
TS 3.7.9 Control Room Emergency Filtration System (CREFS)
SR 3.7.9.3 Verify each CREFS train actuates on an actual or simulated actuation signal. TS 3.8.1 AC Sources - Operating SR 3.8.1.8 Verify each DG rejects a load greater than or equal to its associated single largest post-accident load and does not trip on overspeed. Notes: 1. This Surveillance shall not be performed in MODE 1 or 2. 2. If performed with the DG synchronized with offsite power, it shall be performed at a power 0.9. SR 3.8.1.10 Verify on an actual or simulated Engineered Safety Feature (ESF) actuation signal each DG auto-starts from standby condition and: a. seconds after auto-conditions seconds after auto-state conditions are reache energized from the offsite energized through the automatic load sequencer from the offsite power system. Notes: 1. All DG starts may be preceded by prelube period. 2. This Surveillance shall not be performed in MODE 1 or 2. 3. During periods when a diesel generator is being operated for testing purposes, its protective trips need not be bypassed after the diesel generator has properly assumed the load on its bus.
SR 3.8.1.9 Verify on an actual or simulated loss of offsite power signal: a. -starts from standby condition and: 1. energizes -connected shutdown loads through automatic load sequencer, 3. maintains steady state and 5. supplies permanently connected and auto-connected - Notes: 1. All DG starts may be preceded by an engine prelube period. 2. This Surveillance shall not be performed in MODE 1, 2, 3, or 4.
SR 3.8.1.15 Verify on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated ESF actuation signal: a. De-energization of -starts from standby condition and: 1. energizes permanently connected loads -connected emergency loads through load permanently connec- Notes: 1. All DG starts may be preceded by an engine prelube period. 2. This Surveillance shall not be performed in MODE 1, 2, 3, or 4. 3. During periods when a diesel generator is being operated for testing purposes, its protective trips need not be bypassed after the diesel generator has properly assumed the load on its bus.
TS 3.9.3 Containment Penetrations SR 3.9.3.2 Verify each required containment ventilation valve actuates to the isolation position on an actual or simulated actuation signal.
SRXB RAI - 1 In Enclosure 1 of GL 91-04 it is stated, in part:
Licensees should evaluate the effect on safety of an increase in 18-month surveillance intervals to accommodate a 24-month fuel cycle. This evaluation should support a conclusion that the effect on safety is small. Licensees should confirm that historical plant maintenance and surveillance data support this conclusion.
The staff noted that no failure histories were provided in Attachment 8 of the LAR for the following SR:
SR 3.4.1.4 Verify by precision heat balance that RCS total flow rate is 97.3 x 10 6 lbm/hr Attachment 8 of the LAR states in part for SR 3.4.1.4, "There is no evaluation required for extension of this SR." However, no justification for this statement was provided. The NRC staff requests the licensee to provide the failure histories of the above mentioned SR in accordance with the GL 91-04, or to provide justification as to why it is not required.
SBPB RAI - 1 (a) The LAR is proposing to change the test frequency in TS 5.5.17 "Control Room Envelope Habitability Program," item d from 18 to 24 months. However, the LAR did not propose a corresponding change in TS 5.5.17, item c.
The LAR is proposing to revise the frequency in TS 5.5.17, Item d, from 18 months to 24 months for taking measurements (e.g. control room envelope (CRE) pressure and control room emergency filtration system (CREFS) flow rate) on one of two trains of the CREFS on a staggered test basis. The two trains would then be tested on a 48 month or 4 year frequency TS 5.5.17, Item c references Regulatory Guide (RG) 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, dated May 2003 (ADAMS Accession No. ML031490664). TS 5.5.17 Item c (ii) requires assessing CRE habitability at the frequencies specified in Sections C.1 and C.2 of RG 1.197. RG 1.197, Section C.1, states that all CREs should be tested on a performance-based periodic frequency consistent with Figure 1. RG 1.197, Figure 1, has an assessment frequency of 3 years. With the proposed change to TS 5.5.17, Item d, the two trains would then be tested on a 48 month or 4 year frequency instead of the 3 year frequency in RG 1.197.
The NRC staff requests the licensee to address this conflict in TS 5.5.17. The licensee should identify deviations taken from RG 1.197, if any, as part of its response.
(b) While TS 5.5.17 references RG 1.197 in TS 5.5.17, the licensee has not included RG 1.197 in Section 1.8, "Conformance to NRC Regulatory Guides," of the Robinson Updated Final Safety Analysis Report (UFSAR). Also, based on the response to part (a) of this question, the licensee may identify deviations from RG 1.197. The staff notes that this is contrary to the approach the licensee took regarding RG 1.52 "Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants" Revision 2, dated March 1978 (ADAMS Accession No. ML003740139). Regarding RG 1.52, for TS 5.5.11, "Ventilation Filter Testing Program," the LAR proposes to change in filter testing frequency from 18 months to 24 months as an exception to RG 1.52. The LAR describes the exception in the proposed change to TS 5.5.11. In addition, in LAR , "Summary of License Commitments," the licensee made a commitment that UFSAR Section 1.8 will be modified to include the exception to RG 1.52 conformance.
Please clarify if conformance to RG 1.197, including any deviations, as applicable, will be included in Section 1.8 of the UFSAR?