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EPID:L-2018-LLA-0060, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise the Updated Final Safety Analysis Report (SQN-TS-17-04) (Approved, Closed) |
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Category:E-Mail
MONTHYEARML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 ML23319A1662023-11-0202 November 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant, and Watts Bar Nuclear Plant, Exemption Request Related to 10 CFR 37.11(c)(2) ML23275A0272023-09-29029 September 2023 Submittal of Discharge Monitoring Report (DMR) Quality Assurance Study 43 Final Report 2023 ML23236A2562023-08-24024 August 2023 NRR E-mail Capture - Acceptance Review Results for the Sequoyah and Watts Bar License Amendment Request to Adopt TSTF-567 (L-2023-LLA-0106) ML23165A2862023-06-14014 June 2023 Tennessee Multi-Sector Permit (Tmsp), 2023 Annual Discharge Monitoring Report for Outfalls SW-1, SW-16, SW-17, SW-18, SW-19, and SW-21 ML23072A0722023-03-10010 March 2023 NRR E-mail Capture - (External_Sender) State Consultation - Sequoyah Nuclear Plant, Units 1 and 2; and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML23058A1312023-02-27027 February 2023 FW: TVA Intentions on EA-22-129 ML23062A5952023-02-27027 February 2023 Staff follow-up Questions to Tva'S 12/19/2022 Response of the Staff'S Rsi Regarding 08/04/2022 SQN Exemption Request ML23052A0792023-02-21021 February 2023 NRR E-mail Capture - Acceptance Review for Browns Ferry and Sequoyah License Amendment Request to Adopt TSTF-541 ML23046A3552023-02-15015 February 2023 Annual Water Withdrawal Report 2022 ML23019A3442023-01-19019 January 2023 Tennessee Multi-Sector Permit (Tmsp), 2022 Annual Discharge Monitoring Report for Outfalls SW-1, SW-16, and SW-19 ML23013A0382023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML23013A0362023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML23026A0282023-01-12012 January 2023 001 Radiation Safety Baseline Inspection Information Request ML22348A0972022-12-14014 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML22348A0442022-12-13013 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22348A0432022-11-28028 November 2022 NRR E-mail Capture - State Consultation - Sequoyah Nuclear Plant, Units 1 and 2, License Amendment Request to Modify the Approved 10 CFR 50.69 Categorization Process (L-2022-LLA-0033) ML22227A0712022-08-15015 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 (EPID L-2022-LLA-0103) - Corrected ML22227A0262022-08-12012 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22215A2752022-08-0303 August 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-554 ML22214A1582022-08-0202 August 2022 NRR E-mail Capture - Request for Additional Information for Sequoyah Units 1 and 2 License Amendment Request for Fire and Seismic PRA Modification to 10 CFR 50.69 (L-2022-LLA-0033) ML22196A0732022-07-15015 July 2022 NRR E-mail Capture - (External_Sender) State Notification for Sequoyah Units 1 and 2 Amendment Issuance - TSTF-505 RICT (L-2021-LLA-0145) ML22194A8762022-07-13013 July 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-529 ML22173A0332022-06-17017 June 2022 NRR E-mail Capture - (External_Sender) State Notification for Sequoyah Units 1 and 2 Amendment Issuance - Reactor Trip System Instrumentation (L-2021-LLA-0200) ML22166A4292022-06-0606 June 2022 NRR E-mail Capture - LAR to Adopt TSTF-577 ML22151A0102022-05-27027 May 2022 NRR E-mail Capture - Revised Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3322022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Related to Sequoyah Nuclear Plant'S LAR to Adopt TSTF-505 ML22151A0092022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3342022-05-25025 May 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Relief Requests (EPID L-2022-LLR-0045 - 0047) ML22137A2692022-05-17017 May 2022 Notice of Termination, TNR192066, Gravel Lot Restoration Project ML22136A0182022-05-16016 May 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah Nuclear Plant, Units 1 and 2, Alternative Request RP-11 and Watts Bar Nuclear Plant, Units 1 and 2, Alternative Request IST-RR-9 ML22132A1762022-05-12012 May 2022 Tennessee Multi-Sector Permit (Tmsp), 2021 Annual Discharge Monitoring Report for Outfalls SW-2, SW-3, SW-4, SW-6, SW-8, SW-9, and SW-13 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML22123A1812022-05-0303 May 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-577 ML22095A0182022-04-0404 April 2022 NRR E-mail Capture - Sequoyah Nuclear Plant - Acceptance of Request for Alternative - Pressure Isolation Valve Leakage ISTC-3630 (L-2022-LLR-0034) ML22125A1422022-03-22022 March 2022 1 and 2 - March 22, 2022 e-mail - Sequoyah TSTF-505 LAR Supplemental Information ML22075A0942022-03-16016 March 2022 NRR E-mail Capture - Acceptance Review for Sequoyah Units 1 and 2 - LAR to Use of Fire and Seismic PRAs to Modify Approved 10 CFR 50.69 Categorization Process ML22046A2742022-02-15015 February 2022 NRR E-mail Capture - Audit Question (Snsb 02) for Sequoyah Units 1 and 2 LAR to Adopt TSTF-505, Revision 2 (L-2021-LLA-0145) ML22047A0552022-02-15015 February 2022 Annual Water Withdrawal Report 2021 ML22038A1882022-02-0404 February 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Revise the TVA Radiological Emergency Plan ML22035A0182022-02-0303 February 2022 NRR E-mail Capture - Audit Questions (Eeb follow-up) for Sequoyah Units 1 and 2 LAR to Adopt TSTF-505, Revision 2 (L-2021-LLA-0145) ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML21347A9022021-12-13013 December 2021 Discharge Monitoring Report (DMR) Quality Assurance Study 41 Follow-up Report 2021 ML21336A3942021-12-0101 December 2021 NRR E-mail Capture - Audit Questions for Sequoyah Units 1 and 2 - LAR to Adopt TSTF-505, Revision 2 (L-2021-LLA-0145) ML21323A0432021-11-18018 November 2021 NRR E-mail Capture - Acceptance Review for Sequoyah Units 1 and 2 - LAR to Eliminate the High Negative Flux Rate Trip Requirement ML21252A2152021-09-0909 September 2021 NRR E-mail Capture - Sequoyah Nuclear Plant, Unit 2 - Acceptance of Request for Alternative Inspection for Upper Head Injection J-groove Welds (L-2021-LLR-0059) ML21239A0712021-08-27027 August 2021 Acceptance of License Amendment Request to Adopt TSTF-505, Revision 2 ML21237A4952021-08-25025 August 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-04 2024-01-31
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23307A0832023-11-0808 November 2023 Enclosure - Request for Additional Information HDI-Sequoyah NDE Exemption Request 10-30-2023 ML23307A0822023-11-0808 November 2023 Request for Additional Information August 4, 2022, Exemption Request for Deviating from the Conditions of Certificate of Compliance No. 1032, Amendment No. 3, Related to Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation ML23062A5952023-02-27027 February 2023 Staff follow-up Questions to Tva'S 12/19/2022 Response of the Staff'S Rsi Regarding 08/04/2022 SQN Exemption Request ML23062A5942023-02-27027 February 2023 Enclosure - NRC SQN Exemption Rsi Response Staff Follow Up Questions ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22257A0622022-09-14014 September 2022 Requalification Program Inspection - Sequoyah Nuclear Plant ML22255A0842022-09-0909 September 2022 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-04 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22214A1582022-08-0202 August 2022 NRR E-mail Capture - Request for Additional Information for Sequoyah Units 1 and 2 License Amendment Request for Fire and Seismic PRA Modification to 10 CFR 50.69 (L-2022-LLA-0033) ML22151A0102022-05-27027 May 2022 NRR E-mail Capture - Revised Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22151A0092022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3322022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Related to Sequoyah Nuclear Plant'S LAR to Adopt TSTF-505 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML21237A4952021-08-25025 August 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-04 ML21160A0352021-06-0303 June 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-03 ML21095A0482021-04-0505 April 2021 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Request to Transition to Westinghouse Fuel ML21092A0972021-04-0202 April 2021 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20259A4782020-09-15015 September 2020 Emergency Preparedness Program Inspection Request for Information ML20261H4172020-09-14014 September 2020 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Hydrologic UFSAR Update ML20261H4162020-09-0202 September 2020 NRR E-mail Capture - Draft Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request to Revise UFSAR Hydrologic Analysis ML20189A2112020-07-0101 July 2020 Request for Additional Information Regarding Hydrologic UFSAR Update ML20106F1042020-04-14014 April 2020 Request for Additional Information Regarding the Hydrologic Analysis LAR ML20161A3902020-04-0909 April 2020 Request for Supporting Information for the Sequoyah SPRA Audit Review - Follow-up to Plant Response Question 5 ML20098D8612020-04-0707 April 2020 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000327/2020012 and 05000328/2020012) and Request for Information) ML20036E2842020-02-0505 February 2020 20200123 - Sequoyah Radiation Safety Inspection Document Request Letter ML19323D7562019-11-18018 November 2019 Nrc'S Request for Additional Information - Exigent Amendment ML19235A0992019-08-22022 August 2019 Emergency Preparedness Program Inspection Request for Information ML19162A2462019-06-11011 June 2019 RP Inspection Document Request 2019-03 ML19149A6222019-05-29029 May 2019 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request for Alternative to 18-ISI-1 EPID: L-2019-LLR-0006 ML19148A7912019-05-28028 May 2019 NRR E-mail Capture - Sequoyah Nuclear Plant and Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request for Alternative to OM Code Requirements ML19015A4192019-01-15015 January 2019 NRR E-mail Capture - RAI - Sequoyah Nuclear Plant, Units 1 and 2, LAR to Adopt 10 CFR50.69 Risk-informed SSC ML18344A0752018-12-10010 December 2018 NRR E-mail Capture - Request for Additional Information - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04) ML18296A0022018-10-22022 October 2018 NRR E-mail Capture - Additional Information Needs - Sequoyah Units 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers Revise Updated Final Analysis Report (SQN-TS-17-04) ML18283B0592018-10-10010 October 2018 NRR E-mail Capture - Additional Information Needs Identified During Audit - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers Revise Updated Final Analysis Report (SQN-TS-17-04) ML18283A6232018-09-25025 September 2018 04 RP Inspection Document Request ML18233A1942018-08-21021 August 2018 NRR E-mail Capture - Additional Information Needs Identified - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04) ML18138A1102018-05-17017 May 2018 Enclosurequest for Additional Information (Letter to E. D. Schrull Request for Additional Information Regarding Tennessee Valley Authority'S Decommissioning Funding Plan Update for Browns Ferry and Sequoyah Isfsis) ML18057A6372018-02-23023 February 2018 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet Topical Report TVA-NPG-AWA16 - EPIC: L-2016-TOP-0011) ML17191A2062017-07-0606 July 2017 NRR E-mail Capture - Sequoyah Nuclear Station, Unit 1 & 2 - Request for Additional Information Related to LAR for Technical Specification 3.8.1.17 Note Modification (CAC Nos. MF9398 and MF9399) ML17150A0792017-05-23023 May 2017 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet LAR for EAL Change to Adopt NEI-99-01 Rev.6 (CAC Nos. MF9054 - MF9060) ML17112A0402017-04-20020 April 2017 NRR E-mail Capture - Sequoyah Nuclear Station, Unit 1 & 2 - Request for Additional Information Related to LAR for Technical Specification 3.8.1, AC SOURCES-OPERATING ML17004A0612017-01-0404 January 2017 Notification of NRC Triennial Fire Protection Inspection (Team)(Report 05000327/2017007 and 05000328/2017007) ML15194A3882015-07-13013 July 2015 Request for Additional Information Related to LAR to Revise Ice Condenser Ice Mas Tech Spec ML15175A2912015-06-24024 June 2015 E-mail Re. Request for Additional Information RR RP-07 ML15159B1642015-06-22022 June 2015 Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application-Set 25 (TAC Nos. MF0481 and MF0482) ML15050A0962015-02-19019 February 2015 E-mail Re. Request for Additional Information Related to LAR to Ice Condendser Inc Mass Tech Spec ML15042A4702015-02-11011 February 2015 E-mail Re. Request for Additional Information Related to License Amendment Request to Revise Technical Specification on Ultimate Heat Sink ML14318A8052014-11-12012 November 2014 Requalification Program Inspection - Sequoyah Nuclear Plant ML14254A2042014-09-22022 September 2014 Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application - Set 22 (TAC Nos. MF0481 and MF0482) ML14220A2132014-08-0808 August 2014 E-mail Re. Request for Additional Information Regarding Voluntary Risk Initiative National Fire Protection Association Standard 805 2023-02-27
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NRR-DMPSPEm Resource From: Lee, Samson Sent: Tuesday, August 21, 2018 8:41 AM To: Wells, Russell Douglas Cc: Hon, Andrew
Subject:
additional information needs identified during audit - Sequoyah Nuclear Plant, Units 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04) (EPID: L-2018-LLA-0060)
Attachments: additional information needs during audit - electrical engineering (8-21-18).docx Mr. Wells, The NRC staff is continuing the regulatory audit for the subject Sequoyah license amendment request.
Attached are additional information needs identified in the electrical engineering area. Please propose logistics to facilitate the audit.
- Thanks, Sam 1
Hearing Identifier: NRR_DMPS Email Number: 529 Mail Envelope Properties (Samson.Lee@nrc.gov20180821084000)
Subject:
additional information needs identified during audit - Sequoyah Nuclear Plant, Units 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04) (EPID: L-2018-LLA-0060)
Sent Date: 8/21/2018 8:40:57 AM Received Date: 8/21/2018 8:40:00 AM From: Lee, Samson Created By: Samson.Lee@nrc.gov Recipients:
"Hon, Andrew" <Andrew.Hon@nrc.gov>
Tracking Status: None "Wells, Russell Douglas" <rdwells0@tva.gov>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 273 8/21/2018 8:40:00 AM additional information needs during audit - electrical engineering (8-21-18).docx 33270 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
8/21/2018 ADDITIONAL INFORMATION NEEDS IDENTIFIED DURING THE REGULATORY AUDIT FOR SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, TO SUPPORT REVIEW OF THE LICENSE AMENDMENT REQUEST (LAR) REGARDING REMOVAL OF KIRK KEY INTERLOCK FROM FEEDER BREAKERS AND TIE BREAKERS FOR ESSENTIAL RAW COOLING WATER MOTOR CONTROL CENTER DOCKET NOS. 50-327 AND 50-328 (EPID: L-2018-LLA-0060)
BACKGROUND By letter dated March 9, 2018 (Agencywide Document Access Management System (ADAMS)
Accession No. ML18071A349), as supplemented by letter dated April 11, 2018 (ADAMS Accession No. ML18102B430), Tennessee Valley Authority (TVA), the licensee for Sequoyah Nuclear Plant (SQN), Units 1 and 2, requested the U.S. Nuclear Regulatory Commission (NRC) staff approval to modify Essential Raw Cooling Water (ERCW) Motor Control Center (MCC)
Breakers and revise the Updated Final Safety Analysis Report (UFSAR) for SQN Units 1 and 2 to clarify the normal and alternate power supply for ERCW.
In accordance with a Regulatory Audit Plan dated July 18, 2018 (ADAMS Accession No. ML18199A322), the NRC staff began the audit with an entrance phone call on July 26, 2018.
The NRC staff has identified additional information needs in the electrical engineering area, which are discussed below as talking points. As necessary, please make available technical staff or contractors who are familiar with the information to assist the NRC staff during the audit.
ADDITIONAL INFORMATION NEEDS IDENTIFIED DURING THE REGULATORY AUDIT Regulatory Requirements General Design Criterion (GDC) 17 requires, in part, that the onsite electric power supplies, including the onsite electric distribution system, shall have sufficient independence and redundancy to perform their safety functions assuming a single failure.
General remark No 1 in the UFSAR, Table 8.2.1-1, states: All normal and alternate breakers which supply a given bus are interlocked to prevent paralleling sources. According to this table, all ERCW MCCs 1A-A, 1B-B, 2A-A, and 2B-B have both normal and alternate power supplies which are interlocked.
Talking Point 1 In the LAR, the licensee stated that the original design of the 480V ERCW MCCs included a mechanical interlock (Kirk Key), which prevented paralleling of the normal and alternate power supply on each MCC. The mechanical interlock was provided with the original MCC procurement in the original purchase specification. The Kirk Key provides a mechanical interlock between these same-train normal and alternate power sources.
Provide a discussion that explains the technical basis for the mechanical interlock in the original
MCC procurement, and the technical basis for why the need for mechanical interlock is no longer applicable in its design, use, and operation as described in the UFSAR.
Talking Point 2 In the LAR, the licensee stated that the existing ERCW feeder breakers are obsolete. The replacement breakers were evaluated through TVAs equivalency process. However the replacement breakers have a slightly different physical footprint, which prevents the existing Kirk Key interlocking scheme to be mounted onto the breaker. Therefore, the removal of the Kirk Key interlock was required to install the new ERCW MCC feeder breakers. The existing mechanical interlock was replaced with administrative controls.
Please provide a discussion of the following:
(1) Describe the physical and mechanical difference in the make and footprint of original and replacement breakers; (2) UFSAR Figure 8.1.2-1 shows that ERCW MCC tie-breakers as normally closed (NC).
According to UFSAR, Table 8.2.1-1, each ERCW MCC is supplied from only one source (either a normal or alternate source). Please provide a discussion that clarifies this discrepancy including a markup of UFSAR Chapter 8, Table 8.2.1-1, Figure 8.1.2-1, as necessary.
Talking Point 3 In the LAR, the licensee stated that replacing the Kirk Key mechanical interlocks with administrative controls does introduce the possibility of aligning two ERCW transformers to a single MCC in the event that the administrative controls are not effective. However, this action would not affect the ability of the ERCW system to perform its safety function. The paralleling of the two ERCW transformers onto a single MCC increases the available short circuit current and causes circulating currents that can heat and damage equipment. The effects of circulating currents are minimized in this case, due to the high impedance of the connection and similarity/symmetry of the circuit design.
Please provide a discussion of the following:
(1) Describe the potential increase in current and voltages and subsequent possible tripping of breakers connected to 6.9 kV shutdown boards (1A/2A, or 1B/2B), and ERCW MCCs (1A/2A, or 1B/2B), if inadvertently paralleled (by operator error) through the ERCW MCCs tie-breakers under the following scenarios: (a) two 6.9 kV shutdown boards (1A/2A, or 1B/2B) when fed by two offsite power sources with out-of-phase conditions; (b) two 6.9 kV shutdown boards when fed by EDGs with out-of-phase conditions.
(2) Describe potential increase in current and voltages and subsequent possible tripping of EDG(s), if the EDGs are inadvertently paralleled (by operator error) through ERCW MCCs tie-breakers, with out-of-phase conditions.
Talking Point 4 In the LAR, the licensee stated that the breakers interrupting capability and selective coordination ensures that only the affected train ERCW MCCs are electrically isolated. The result of this
failure is the loss of 480V power supply to one train of ERCW MCCs.
The LAR does not describe the availability of both trains of ERCW MCCs required for safe shutdown of the plant can be adversely impacted by the similar common mistake of operator(s).
Provide a discussion explaining whether other considerations of other possible methods to avoid the connection between the same-train normal and alternate power sources such as: (a) rack-out/disconnection of tie-breakers, (b) shunt tip of one of the main breakers to the MCCs if two sources are paralleled through tie-breakers, (c) alarm in the control room if the normal and alternate sources are inadvertently closed in any train were evaluated.