ML15212A242
| ML15212A242 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/24/2015 |
| From: | Clark J Exelon Corp |
| To: | Nicholas Difrancesco Japan Lessons-Learned Division |
| References | |
| Download: ML15212A242 (13) | |
Text
1 NRR-PMDAPEm Resource From:
Clark, Jeffrey S.:(GenCo-Nuc) [Jeffrey.Clark2@exeloncorp.com]
Sent:
Friday, July 24, 2015 6:15 PM To:
DiFrancesco, Nicholas Cc:
Wyman, Stephen; Shams, Mohamed; Hughey, John; Marshall, Michael; Aggarwal, Vinod K:(GenCo-Nuc); Distel, David J:(GenCo-Nuc); Behrend, Chuck L.:(GenCo-Nuc); Ho, Wing:(GenCo-Nuc); Ritter Jr, Ralph R:(GenCo-Nuc); Lonsdale, Thomas S; Dunsmuir, Steven P:(GenCo-Nuc)
Subject:
[External_Sender] RE: Clarifying Questions for the Oyster Creek ESEP Report Attachments:
Oyster Creek ESEP NRC Question Response FINAL 7-24-15.docx Mr. DiFrancesco, In response to your initial email request below, Exelon is pleased to provide you with the attached response to your question on the Oyster Creek ESEP Report submittal. Based on our previous discussions we are providing you this information on our revised date of July 24, 2015, as accepted below. Please feel free to contact us with any further questions or clarifications needed to support the NRCs ESEP report reviews.
Thank You, Jeff Clark Jeffrey S. Clark, PE Fukushima Response Seismic Lead 630-657-3876 (Work) 224-419-1450 (cell)
From: DiFrancesco, Nicholas [1]
Sent: Monday, July 13, 2015 7:40 AM To: Clark, Jeffrey S.:(GenCo-Nuc)
Cc: Wyman, Stephen; Shams, Mohamed; Hughey, John
Subject:
[EXTERNAL] RE: Clarifying Questions for the Oyster Creek ESEP Report
- Jeff, Understand that this request will require additional time. Appreciate the update.
- Thanks, Nick From: Clark, Jeffrey S.:(GenCo-Nuc) [2]
Sent: Friday, July 10, 2015 5:57 PM To: DiFrancesco, Nicholas; Wyman, Stephen Cc: Devlin-Gill, Stephanie; Wyman, Stephen; Hughey, John; 50.54f_Seismic Resource; Ho, Wing:(GenCo-Nuc); Aggarwal, Vinod K:(GenCo-Nuc); Distel, David J:(GenCo-Nuc); Ritter Jr, Ralph R:(GenCo-Nuc); Gaston, Ronald:(GenCo-Nuc);
2 Behrend, Chuck L.:(GenCo-Nuc)
Subject:
[External_Sender] RE: Clarifying Questions for the Oyster Creek ESEP Report Mr. DiFrancesco / Mr. Wyman, As discussed earlier in the week with Mr. DiFrancesco, the Oyster Creek response effort for the NRC question we received on June 15, 2015 (below), identified the need to perform additional seismic evaluations on 15 reactor recirculating system valves to confirm their ability to close following a Ground Motion Response Spectra (GMRS) level seismic event in support of the Oyster Creek FLEX implementation strategies. The additional effort will require approximately 2 additional weeks to resolve. Based on progress to date, we are anticipating a July 24th, 2015 response to your question below. We apologize for the delay from our previously agreed date of July 10th, 2015. Please confirm that the revised July 24th, 2015 completion date is acceptable.
Please feel free to call me with any additional questions you may have.
Thank You, Jeff Clark Jeffrey S. Clark, PE Fukushima Response Seismic Lead 630-657-3876 (Work) 224-419-1450 (cell)
From: Clark, Jeffrey S.:(GenCo-Nuc)
Sent: Monday, June 29, 2015 4:38 PM To: 'DiFrancesco, Nicholas'; Wyman, Stephen (Stephen.Wyman@nrc.gov)
Cc: Devlin-Gill, Stephanie; Wyman, Stephen; Hughey, John; 50.54f_Seismic Resource; Ho, Wing:(GenCo-Nuc); Aggarwal, Vinod K:(GenCo-Nuc); Distel, David J:(GenCo-Nuc); Ritter Jr, Ralph R:(GenCo-Nuc)
Subject:
RE: Clarifying Questions for the Oyster Creek ESEP Report Mr. DiFrancesco / Mr. Wyman, Based on progress to date, we are anticipating a July 10th, 2015 response to your Oyster Creek question below. We are making good progress to date, but need some additional time due to the scope involved. We apologize for the delay from your requested date of June 30th, 2015. Please confirm that a July 10th, 2015 target date is acceptable.
Thank You, Jeff Clark Jeffrey S. Clark, PE Exelon Fukushima Response Seismic Lead 630-657-3876 (Work) 224-419-1450 (cell)
From: DiFrancesco, Nicholas [3]
Sent: Monday, June 15, 2015 2:41 PM To: Distel, David J:(GenCo-Nuc); Clark, Jeffrey S.:(GenCo-Nuc)
Cc: Devlin-Gill, Stephanie; Wyman, Stephen; Hughey, John; 50.54f_Seismic Resource
Subject:
[EXTERNAL] Clarifying Questions for the Oyster Creek ESEP Report
3 Mr. Distel and Mr. Clark, As mentioned, as part of the NRC review of the Oyster Creek ESEP report, the staff would appreciate clarification on the following technical items:
- 1. By letter dated December 19, 2014 (ADAMS Accession No. ML14353A332), Exelon Generating Company submitted the Oyster Creek Expedited Seismic Evaluation Process Report which concluded that it is not required to review all Expedited Seismic Equipment List [ESEL] components at the Ground Motion Response Spectra (GMRS) demand level. Please confirm that all components contained in Table A-1 Oyster Creek ESEL have demonstrated capacity at or above the GMRS demand level.
An email or letter response is sufficient to support the ESEP report review. A response around June 30, if practicable, would be greatly appreciated to support the established review schedule. An email response will be added to public ADAMS.
Please let me or Steve Wyman (at 301-415-3041) know if you would like to schedule a clarification call or any have questions.
- Thanks, Nick Senior Project Manager - Seismic Reevaluation Activities U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Japan Lesson Learned Project Division nicholas.difrancesco@nrc.gov l Tel: (301) 415-1115 This Email message and any attachment may contain information that is proprietary, legally privileged, confidential and/or subject to copyright belonging to Exelon Corporation or its affiliates ("Exelon"). This Email is intended solely for the use of the person(s) to which it is addressed. If you are not an intended recipient, or the employee or agent responsible for delivery of this Email to the intended recipient(s), you are hereby notified that any dissemination, distribution or copying of this Email is strictly prohibited. If you have received this message in error, please immediately notify the sender and permanently delete this Email and any copies.
Exelon policies expressly prohibit employees from making defamatory or offensive statements and infringing any copyright or any other legal right by Email communication. Exelon will not accept any liability in respect of such communications. -EXCIP
Hearing Identifier:
NRR_PMDA Email Number:
2263 Mail Envelope Properties (9717B5461B966646BAF3352111206D75793B0DFA)
Subject:
[External_Sender] RE: Clarifying Questions for the Oyster Creek ESEP Report Sent Date:
7/24/2015 6:15:09 PM Received Date:
7/24/2015 6:15:15 PM From:
Clark, Jeffrey S.:(GenCo-Nuc)
Created By:
Jeffrey.Clark2@exeloncorp.com Recipients:
"Wyman, Stephen" <Stephen.Wyman@nrc.gov>
Tracking Status: None "Shams, Mohamed" <Mohamed.Shams@nrc.gov>
Tracking Status: None "Hughey, John" <John.Hughey@nrc.gov>
Tracking Status: None "Marshall, Michael" <Michael.Marshall@nrc.gov>
Tracking Status: None "Aggarwal, Vinod K:(GenCo-Nuc)" <Vinod.Aggarwal@exeloncorp.com>
Tracking Status: None "Distel, David J:(GenCo-Nuc)" <David.Distel@exeloncorp.com>
Tracking Status: None "Behrend, Chuck L.:(GenCo-Nuc)" <chuck.behrend@exeloncorp.com>
Tracking Status: None "Ho, Wing:(GenCo-Nuc)" <Wing.Ho@exeloncorp.com>
Tracking Status: None "Ritter Jr, Ralph R:(GenCo-Nuc)" <ralph.ritter@exeloncorp.com>
Tracking Status: None "Lonsdale, Thomas S" <Thomas.Lonsdale@exeloncorp.com>
Tracking Status: None "Dunsmuir, Steven P:(GenCo-Nuc)" <Steven.Dunsmuir@exeloncorp.com>
Tracking Status: None "DiFrancesco, Nicholas" <Nicholas.DiFrancesco@nrc.gov>
Tracking Status: None Post Office:
EXCHM-OMF-25.exelonds.com Files Size Date & Time MESSAGE 6012 7/24/2015 6:15:15 PM Oyster Creek ESEP NRC Question Response FINAL 7-24-15.docx 38778 Options Priority:
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No Reply Requested:
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RESPONSE TO QUESTION FROM NRC ON ESEL ITEMS MEETING GMRS The Oyster Creek Seismic Hazard and Screening Submittal Report dated March 31, 2015 (ML14090A241) concluded that the Safe Shutdown Earthquake (SSE) envelops the Re-evaluated seismic hazard (GMRS) except at frequenciesbelow 1.9 Hz (Low Frequency exceedance), and at frequencies between 18 and 70 Hz (High Frequency exceedance).
The attached table, Oyster Creek ESEL and Associated Seismic Evaluations, lists the seismic evaluation documents for the components on the ESEL provided in Table A-1 of the Oyster Creek ESEP Submittal Reportdated December 19, 2014 (ML14353A332). These documents demonstrate that all non-high frequency susceptible components on the ESEL have seismic capacities at or above the GMRS level, with the exception of three instrument air regulating valves (items 86, 87 and 88). These valves are not required to implement the FLEX strategies. These valves support venting of the containment which is not required based on MAAP Analysis to Support FLEX Initial Strategy, OC-MISC-010, Rev. 1 dated June 9, 2015. The Oyster Creek FLEX strategies will be revised to exclude venting in the next 6-month update to the Overall Integrated Plan.
The only component that is susceptible to damage from low frequency spectral accelerations is the Diesel Generator Fuel Oil Storage Tank (ESEL item 43) which has been evaluated to the GMRS demand level and is documented in the Oyster Creek ESEP Submittal Report. To address the High Frequency exceedance, Exelon committed under Commitment 2 in Enclosure 2 of the Seismic Hazard and Screening submittal to perform a High Frequency Confirmation evaluation.
Since the low frequency item has been addressed in the ESEP Submittal Report, and the High Frequency exceedanceitems are being trackedwith an NRC commitment forfurther evaluation in the future, the components on the ESEL will all be considered for the GMRS seismic demand level. Further, the near endorsed DRAFT EPRI 3002004396 - HF Application Guidance states For the High Frequency Confirmation, these types of minor exceedances over limited frequency rangesdo not represent a significant high frequency concern and can be screened from further component evaluations. Given the limited high frequency exceedance of the GMRS to the SSE, it is expected that Oyster Creek will be screened from further component evaluations.
Oyster Creek ESEL and Associated Seismic Evaluations ESEL Item Number Equipment Operating State Notes Associated Seismic Evaluations ID Description Normal State Desired State 1
USS 1A2 480VAC Vital Reactor Bldg Bus A In Service In Service SQUG Report1 2
MCC 1A21 Power to Recirculation Loop Isolation Valves In Service In Service SQUG Report1 3
MCC 1A21A Power to Recirculation Loop Isolation Valves In Service In Service SQUG Report1 4
VMCC 1A2 Vital Motor Control Center 1A2 In Service In Service SQUG Report1 5
BTCHG C1 C Station Battery Solid State Static Charger C1 In Service In Service SQUG Report1 6
Battery Bank C Vital Bank C Station Battery In Service In Service SQUG Report1 7
DC-C 125V 125VDC Distribution Center C In Service In Service SQUG Report1 8
DC-F 125VDC Power Panel DC-F In Service In Service Isolation Condenser, Core Spray and EMRV control/logic power SQUG Report1 9
DC-2 125VDC 125VDC Motor Control CTR for Reactor Building In Service In Service SQUG Report1 10 CD-14-1B B Isolation Condenser (NE01B)
Standby In Service as required Passive component Technical Evaluation A2326264-896 11 LT-IG0006B B Isolation Condenser Shell Level XMITR In Service In Service The indicator for this transmitter is located in panel 1F/2F Technical Evaluation A2326264-874 12 LI-211-1215 B Isolation Condenser Local Shell Level Indication In Service In Service Mechanical instrument Test Report3 13 V-14-35 B Isolation Condenser Condensate Return Valve Closed Open/Closed SQUG Report1 14 USS 1B2 480VAC Vital Reactor Bldg Bus B In Service In Service SQUG Report1 15 VMCC 1B2 Vital Motor Control Center 1B2 In Service In Service SQUG Report1 16 VMCC 1AB2 Vital Motor Control Center 1AB2 (Recirculation Pump Isolation Valve Power)
In Service In Service ATS 1AB2 is contained in VMCC 1AB2 SQUG Report1 17 MCC 1B21A Power to Recirculation Loop Isolation Valves In Service In Service SQUG Report1 18 MCC 1B21 Power to Static Charger and Recirculation Pump Isolation Valves In Service In Service SQUG Report1 19 STATIC CHGR A/B Station Batteries Solid State Static Charger In Service In Service Technical Evaluation A2326264-874
Oyster Creek ESEL and Associated Seismic Evaluations ESEL Item Number Equipment Operating State Notes Associated Seismic Evaluations ID Description Normal State Desired State 20 Battery Bank B Vital Bank B Station Battery (Lead Acid)
In Service In Service SQUG Report1 21 DC-B 125V 125VDC Distribution Panel B In Service In Service SQUG Report1 22 DC-D 125VDC Power Panel D In Service In Service Isolation Condenser, Core Spray and EMRV control/logic power SQUG Report1 23 DC-1 125VDC 125VDC Isolation Valves Motor Control Center In Service In Service ATS DC-1 is contained in MCC DC-1 SQUG Report1 24 CD-14-1A A Isolation Condenser (NE01A)
Standby In Service as required Passive component Technical Evaluation A2326264-896 25 LT-IG0006A A Isolation Condenser Shell Level XMITR In Service In Service The indicator for this transmitter is located in panel 1F/2F Technical Evaluation A2326264-874 26 LI-211-1214 A Isolation Condenser Local Shell Level Indication In Service In Service Mechanical Indicator Test Report3 27 V-14-34 A Isolation Condenser Condensate Return Valve Closed Open/Closed SQUG Report1 28 V-20-15 Core Spray to Reactor Parallel Valve System 1 Closed Open AC powered valve which will be manually operated during ELAP SQUG Report1 29 RK-3 Instrument Rack 03 In Service In Service Contains separately powered PT-IP0007 instrument transmitter SQUG Report1 30 PT-IP0007 Containment Pressure Transmitter In Service In Service Phase 2 Transmitter mounted on Instrument Rack
- 03. See SQUG Report for RK-31 31 1F/2F MCR Control Reactor & Drywell Cooling Panel In Service In Service SQUG Report1
Oyster Creek ESEL and Associated Seismic Evaluations ESEL Item Number Equipment Operating State Notes Associated Seismic Evaluations ID Description Normal State Desired State 32 5F/6F Main Control Room Panel 5F/6F In Service In Service Contains separately powered instrument indicators SQUG Report1 33 RSP Remote Shutdown Panel In Service In Service Contains power supplies for, and elements of, credited instruments SQUG Report1 34 16R Containment H2/02 Panel In Service In Service Monitors containment parameters SQUG Report1 35 18R Main Control Room Panel 18R Reactor Protection In Service In Service Contains instruments from the IOP SQUG Report1 36 11F MCR Panel 11F In Service In Service Routes power to panel 12XR via internal fuse 6F7 SQUG Report1 37 V-23-13 Drywell N2 Purge Valve/Containment Isolation Valve for Hardened Vent In Service In Service SQUG Report1 38 V-23-14 Drywell N2 Purge Valve/Containment Isolation Valve for Hardened Vent In Service In Service SQUG Report1 39 V-23-15 Torus N2 Purge Valve/Containment Isolation Valve for Hardened Vent In Service In Service SQUG Report1 40 V-23-16 Torus N2 Purge Valve/Containment Isolation Valve for Hardened Vent In Service In Service SQUG Report1 41 DPT-622-1009 Reactor Fuel Zone Level Wide Range I Transmitter (Channel C)
Standby In Service The indicator for this transmitter is located in panel 5F/6F Technical Evaluation A2326264-874 42 PT-622-1018 Reactor Wide Range Pressure Transmitter (Channel C)
Standby In Service The indicator for this transmitter is located in panel 5F/6F Technical Evaluation A2326264-874 43 T-39-2 Diesel Generator Fuel Oil Storage Tank Standby Standby Passive Component ESEP Submittal dated December 19, 2014 (ML14353A332) 44 V-37-09 Reactor Recirculation Pump NG01-A-Suction Isolation Valve Open Closed Technical Evaluation A2326264-885
Oyster Creek ESEL and Associated Seismic Evaluations ESEL Item Number Equipment Operating State Notes Associated Seismic Evaluations ID Description Normal State Desired State 45 V-37-10 Reactor Recirculation Pump NG01-A Discharge Isolation Valve Open Closed Technical Evaluation A2326264-885 46 V-37-11 Reactor Recirculation Loop 'A' Bypass Valve NG08-A Open Closed Technical Evaluation A2326264-885 47 V-37-20 Reactor Recirculation Pump NG01-B Suction Isolation Valve Open Closed Technical Evaluation A2326264-885 48 V-37-21 Reactor Recirculation Pump NG01-B Discharge Isolation Valve Open Closed Technical Evaluation A2326264-885 49 V-37-22 Reactor Recirculation Loop 'B' Bypass Valve NG08-B Open Closed Technical Evaluation A2326264-885 50 V-37-31 Reactor Recirculation Pump NG01-C Suction Isolation Valve Open Closed Technical Evaluation A2326264-885 51 V-37-32 Reactor Recirculation Pump NG01-C Discharge Isolation Valve Open Closed Technical Evaluation A2326264-885 52 V-37-33 Reactor Recirculation Loop 'C' Bypass Valve NG08-C Open Closed Technical Evaluation A2326264-885 53 V-37-42 Reactor Recirculation Pump NG01-D Suction Isolation Valve Open Closed Technical Evaluation A2326264-885 54 V-37-43 Reactor Recirculation Pump NG01-D Discharge Isolation Valve Open Closed Technical Evaluation A2326264-885 55 V-37-44 Reactor Recirculation Loop 'D' Bypass Valve NG08-D Open Closed Technical Evaluation A2326264-885 56 V-37-53 Reactor Recirculation Pump NG01-E Suction Isolation Valve Open Closed Technical Evaluation A2326264-885 57 V-37-54 Reactor Recirculation Pump NG01-E Discharge Isolation Valve Open Closed Technical Evaluation A2326264-885 58 V-37-55 Reactor Recirculation Loop 'E' Bypass Valve NG08-E Open Closed Technical Evaluation A2326264-885 59 LSP-1AB2 Local Shutdown Panel Standby Standby Contains elements of control for valve V-37-54 SQUG Report1
Oyster Creek ESEL and Associated Seismic Evaluations ESEL Item Number Equipment Operating State Notes Associated Seismic Evaluations ID Description Normal State Desired State 60 3F Panel In Service In Service Contains control switches for recirculation pump valves.
Valve control power provided from MCC via internal control transformer SQUG Report1 61 IP-4 120V AC Vital Power Distribution Panel In service In service Provides power for credited instruments SQUG Report1 62 IT-4 Automatic Transfer Switch In Service In Service Provides power for 120V AC vital power distribution panel IP-4 SQUG Report1 63 IT-4B Transformer In Service In Service Provides power for automatic transfer switch IT-4 SQUG Report1 64 10R Panel In Service In Service Contains power supplies for, and elements of, credited instrumentatio n
SQUG Report1 65 ER-622-080 Panel In Service In Service Contains power supplies for, and elements of, credited instrumentatio n
SQUG Report SQ-OC-622-0011 66 ATS DC-D Automatic Transfer Switch In Service In Service Provides power for 125V DC distribution panel DC-D SQUG Report1
Oyster Creek ESEL and Associated Seismic Evaluations ESEL Item Number Equipment Operating State Notes Associated Seismic Evaluations ID Description Normal State Desired State 67 6K3A Isolation Condenser Valve Hi Flow Isolation Logic Energized Energized CR120AD042 41AA relay Relay seismic functionality review and evaluation2 68 6K3B Isolation Condenser Valve Hi Flow Isolation Logic Energized Energized CR120AD042 41AA relay Relay seismic functionality review and evaluation2 69 6K5A Isolation Condenser Valve Hi Flow Isolation Logic Energized Energized CR120AD042 41AA relay Relay seismic functionality review and evaluation2 70 6K5B Isolation Condenser Valve Hi Flow Isolation Logic Energized Energized CR120AD042 41AA relay Relay seismic functionality review and evaluation2 71 6K4A Isolation Condenser Valve Hi Flow Isolation Logic Energized Energized CR120AD042 41AA relay Relay seismic functionality review and evaluation2 72 6K4B Isolation Condenser Valve Hi Flow Isolation Logic Energized Energized CR120AD042 41AA relay Relay seismic functionality review and evaluation2 73 6K6A Isolation Condenser valve Hi Flow Isolation Logic Energized Energized CR120AD042 41AA relay Relay seismic functionality review and evaluation2 74 6K6B Isolation Condenser Valve Hi Flow Isolation Logic Energized Energized CR120AD042 41AA relay Relay seismic functionality review and evaluation2 75 6K7A Isolation Condenser Valve Hi Flow Isolation Logic Energized Energized 27s Time Delay Drop-Out Relay Model 700RTC11200 U1 Relay seismic functionality review and evaluation2 76 6K7B Isolation Condenser Valve Hi Flow Isolation Logic Energized Energized 27s Time Delay Drop-Out Relay Model 700RTC11200 U1 Relay seismic functionality review and evaluation2 77 6K8A Isolation Condenser Valve Hi Flow Isolation Logic Energized Energized 27s Time Delay Drop-Out Relay Model 700RTC11200 U1 Relay seismic functionality review and evaluation2
Oyster Creek ESEL and Associated Seismic Evaluations ESEL Item Number Equipment Operating State Notes Associated Seismic Evaluations ID Description Normal State Desired State 78 6K8B Isolation Condenser Valve Hi Flow isolation logic Energized Energized 27s Time Delay Drop-Out Relay Model 700RTC11200 U1 Relay seismic functionality review and evaluation2 79 Y-6-42 Back-Up Air Supply Accumulator for Valve V-23-0013 Functional Functional Passive Component Technical Evaluation A2326264-874 80 Y-6-43 Back-Up Air Supply Accumulator for Valve V-23-0014 Functional Functional Passive Component Technical Evaluation A2326264-874 81 Y-6-44 Back-Up Air Supply Accumulator for Valve V-23-0015&16 Functional Functional Passive Component Technical Evaluation A2326264-874 82 V-6-953 Pilot Solenoid Air Supply Valve for V-23-0015 De-Energized Energized Technical Evaluation A2326264-874 83 V-6-954 Pilot Solenoid Air Supply Valve for V-23-0016 De-Energized Energized Technical Evaluation A2326264-874 84 V-6-902 Pilot Solenoid Air Supply Valve for V-23-0013 De-Energized Energized Technical Evaluation A2326264-874 85 V-6-903 Pilot Solenoid Air Supply Valve for V-23-0014 De-Energized Energized Technical Evaluation A2326264-874 86 V-6-950 Instrument Air Regulating Valve Functional Functional McMaster-Carr Supply Co, 382M, Model:
4959K1 Not required to implement FLEX strategies7 87 V-6-899 Instrument Air Regulating Valve Functional Functional McMaster-Carr Supply Co, 382M, Model:
4959K1 Not required to implement FLEX strategies7 88 V-6-898 Instrument Air Regulating Valve Functional Functional Fisher Controls International LLC Model 67CFR-239 Not required to implement FLEX strategies7 89 CIP-3 Continuous Instrument Panel No. 3 Energized Energized SQUG Report1 90 ROTARY INVERTER 120V AC Supply for CIP-3 208/120V, 3PH, 4W Energized Energized SQUG Report1
Oyster Creek ESEL and Associated Seismic Evaluations ESEL Item Number Equipment Operating State Notes Associated Seismic Evaluations ID Description Normal State Desired State 91 12XR Panel In Service In Service Contains PNL-822-12XRCS1 Key lock bypass switch for purge
- valves, bypasses Isolation relays for hardened vent valves SQUG Report1 92 IT-3 Automatic Transfer Switch In Service In Service SQUG Report1 Notes:
- 1) SQUG Report denotes walkdown report prepared in accordance with the SQUG-GIP methodology. The title of the report is typically SQ-OC-(Equipment ID). The seismic demand used was based on the SSE*.
- 2) Relay seismic functionality review and evaluation denotes Report TDR 1149, Rev. 6, Relay Seismic Functionality Review and Calculation C-1302-900-5320-011, Rev. 5, USI A46 Resolution Essential Relay Evaluation. The seismic demand used was based on the SSE*.
- 3) Test Report denotes Trentec Report No.: 7T371.0, Rev. 1 associated with ECR 07-00154, Rev. 1. The seismic demand used was based on the SSE*.
- 4) Technical Evaluation A2326264-87: The seismic demand used was based on the GMRS*.
- 5) Technical Evaluation A2326264-88: The seismic demand used was based on the GMRS*.
- 6) Technical Evaluation A2326264-89: The seismic demand used was based on the GMRS*.
- 7) Not required to implement FLEX strategies denotes instrument air regulating valves that are not required to implement the FLEX strategies. These valves support venting of the containment which is not required based on MAAP Analysis to Support FLEX Initial Strategy, OC-MISC-010, Rev. 1 dated June 9, 2015. The FLEX strategies will be revised to exclude venting in the next 6-month update to the Overall Integrated Plan.
- Denotes the SSE and GMRS documented in the Oyster Creek Seismic Hazard and Screening Submittal, dated March 31, 2014 (ML14090A241).