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| | number = ML13212A009 | | | number = ML13212A009 |
| | issue date = 07/30/2013 | | | issue date = 07/30/2013 |
| | title = Fort Calhoun, Unit 1, Request for Additional Information Email, Request to Revise Technical Specification (TS) 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem, or Component Due to Inoperable Pow | | | title = Request for Additional Information Email, Request to Revise Technical Specification (TS) 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem, or Component Due to Inoperable Power Source |
| | author name = Wilkins L E | | | author name = Wilkins L |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Hansher B R | | | addressee name = Hansher B |
| | addressee affiliation = Omaha Public Power District | | | addressee affiliation = Omaha Public Power District |
| | docket = 05000285 | | | docket = 05000285 |
| | license number = DPR-040 | | | license number = DPR-040 |
| | contact person = Wilkins L E | | | contact person = Wilkins L |
| | case reference number = TAC MF0691 | | | case reference number = TAC MF0691 |
| | document type = E-Mail, Request for Additional Information (RAI) | | | document type = E-Mail, Request for Additional Information (RAI) |
| | page count = 4 | | | page count = 4 |
| | | project = TAC:MF0691 |
| | | stage = RAI |
| }} | | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:Burkhardt, Janet From: Wilkins, Lynnea Sent: Tuesday, July 30, 2013 5:08 PM To: 'HANSHER, BILL R' Cc: 'LIPPY, DONNA L'; 'EDWARDS, MICHAEL L'; Burkhardt, Janet; Sebrosky, Joseph |
| | |
| | ==Subject:== |
| | DRAFT: Fort Calhoun RAI Re: Revisions to TS 2.01 and 2.7 (MF0691) |
| | Attachments: MF0691 email RAI.docx |
| | : Bill, By letter dated February 18, 2013 (Agencywide Documents Access and Management System (ADAMS) |
| | Accession No. ML13051A741), the Omaha Public Power District (the licensee) requested an amendment to Facility Operating License No. DPR-40 for Fort Calhoun Station (FCS), Unit 1. The proposed changes would revise the FCS Technical Specification (TS) as follows: (1) revise the definition for Operable-Operability, (2) modify the provisions under which equipment may be considered operable when either its normal or emergency power source is inoperable, and (3) revise the minimum requirement statement in TS 2.7 in previously approved Amendment 147. |
| | The NRC staff has reviewed the information provided and has determined that additional information specified in the Request for Additional Information (RAI) below is needed for the staff to complete its evaluation. |
| | Please contact Joe next week if a clarifying teleconference is needed for the RAI. |
| | Lynnea Wilkins, Project Manager Fort Calhoun Station, Unit 1 Cooper Nuclear Station Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: 301-415-1377 1 |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1 DOCKET NO. 50-285 By letter dated February 18, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13051A741), the Omaha Public Power District (the licensee) requested an amendment to Facility Operating License No. DPR-40 for Fort Calhoun Station (FCS), Unit 1. The proposed changes would revise the FCS Technical Specification (TS) as follows: (1) revise the definition for Operable-Operability, (2) modify the provisions under which equipment may be considered operable when either its normal or emergency power source is inoperable, and (3) revise the minimum requirement statement in TS 2.7 in previously approved Amendment 147. |
| | The NRC staff has reviewed your submittal and has determined that additional information is needed for the staff to complete its evaluation. |
| | |
| | ===RAI 1=== |
| | The proposed TS LCO 2.0.1(2) states: |
| | When the reactor coolant temperature is > 300°F and a system, subsystem, train, component, or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system(s), |
| | subsystem(s), train(s), component(s), and device(s) are OPERABLE, or likewise satisfy the requirements of this specification. |
| | : a. Within 4 hours from discovery of either diesel generator inoperability, declare the required feature(s) associated with the inoperable diesel generator inoperable, when its redundant required feature (including the steam driven auxiliary feedwater pump FW-10) is inoperable. |
| | : b. Within 24 hours from discovery of either house service transformer inoperability, declare the required feature(s) associated with the inoperable house service transformer inoperable, when its redundant required feature (including the steam driven auxiliary feedwater pump FW-10) is inoperable. |
| | The wording of the above proposed TS LCO 2.0.1(2) appears similar to NUREG-0212, Revision 2, LCO 3.0.5. However, the proposed TS wording does not include the 2-hour verification of (1) and (2) above is satisfied and it does not include the required action and completion times to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply as identified in the NUREG. Please explain this inconsistency with NUREG-0212 and Enclosure |
| | |
| | explain why continued safe operation is assured without timely (within 2-hours) verification and actions consistent with those identified in NUREG-0212. |
| | |
| | ===RAI 2=== |
| | The proposed relocation of a and b from TS 2.7, Electrical Systems, to TS LCO 2.0.1 is inconsistent with NUREG-0212 and NUREG-1432. Please explain how these changes more align Ft Calhoun TS with NUREG-0212 Revision 2, Standard Technical Specifications [STS] for Combustion Engineering Plants, as stated in the application. |
| | |
| | ===RAI 3=== |
| | TS 2.0 Limiting Conditions for Operation, 2.0.1 General Requirements, Applicability states: |
| | Applies to the operable status of all systems, subsystems, trains, components, or devices covered by the Limiting Conditions for Operation. |
| | Please identify all affected LCOs and the provide the reason(s) and safety justification for the proposed TS LCO 2.0.1(2) relaxation of the electrical power LCO Operability requirements for a system, subsystem, train, component or device when reactor coolant (RC) temperature is greater than 300 degrees F as compared to when the RC temperature is less than 300 degrees F (e.g., LCO 2.2, Chemical and Volume Control System Charging Pumps, Boric Acid Pumps, etc.) |
| | |
| | ===RAI 4=== |
| | In the LAR dated February 18, 2013, the licensee provided proposed changes to the TS 2.7 minimum requirements for the Limiting Condition of Operation (LCO) for Electrical Systems for the condition when reactor coolant temperature will be > 300° F (applicable to the availability of electrical systems for the operation of plant components). However, the staff did not find the minimum requirements for the LCOs and Surveillance Requirements (SRs) for electrical systems when reactor coolant temperature will be < 300° F. NUREG-0212 also contains minimum requirements for LCOs during shutdown condition for electrical equipment in TS 3.8.1.2, 3.8.2.2, 3.8.2.4 and related surveillance requirements (SRs) in TS 4.8.1.2, 4.8.2.2, 4.8.2.4.1 and 4.8.2.4.2 Please provide justification for deviation from NUREG-0212 for not including above LCOs and SRs for shutdown conditions when reactor coolant temperature < |
| | 300° F. Please provide an overview of all electrical equipment required to be operable for reactor coolant temperature < 300° F. |
| | |
| | ===RAI 5=== |
| | The proposed TS LCO 2.0.1, Specification (2) in the LAR dated February 18, 2013, states, in part its corresponding normal or emergency power sources is OPERABLE. This statement does not appear to be consistent with the proposed change in definition of Operable - |
| | Operability which reflects normal and emergency electrical power sources. |
| | : 1) Please explain the discrepancy between the proposed changes. |
| | : 2) License Amendment No. 264 approved changes to definitions of Operable-Operability and as a consequence, inadvertently changed the requirement for an operable emergency power source, when reactor coolant temperature is < 300° F. Please provide details on operability requirements of equipment that will be impacted if the proposed change to TS LCO 2.0.1, Specification (2) in the LAR with the requirement for normal or emergency power is approved. |
| | RAI 6 in Enclosure (TS Pages Retyped (Clean) Definitions Operable - Operability) of the LAR dated February 18, 2013, states, Implicit in this definition shall be the assumption that all necessary. does not appear to be consistent with NUREG-0212 Definition of Operable - |
| | Operability. The NUREG-0212 Definition of Operable - Operability does not include the underlined words as stated above. Please explain the reasons for adding additional words Implicit in this definition shall be the assumption that to the NUREG 02012 Definition of Operable - Operability in the proposed TS change.}} |
Letter Sequence RAI |
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MONTHYEARLIC-13-0001, License Amendment Request 13-01, Revision to Technical Specifications Sections 2.0.1 and 2.7 for Inoperable System, Subsystem or Component Due to Inoperable Power Source2013-02-18018 February 2013 License Amendment Request 13-01, Revision to Technical Specifications Sections 2.0.1 and 2.7 for Inoperable System, Subsystem or Component Due to Inoperable Power Source Project stage: Request ML13106A3422013-04-16016 April 2013 Acceptance Review Email, License Amendment Request, Revise Technical Specification (TS) 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem, or Component Due to Inoperable Power Source Project stage: Acceptance Review ML13212A0092013-07-30030 July 2013 Request for Additional Information Email, Request to Revise Technical Specification (TS) 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem, or Component Due to Inoperable Power Source Project stage: RAI ML13234A4352013-08-22022 August 2013 Request for Additional Information Email, Round 2, Request to Revise TS 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem. or Component Due to Inoperable Power Source Project stage: RAI ML14052A2042014-02-20020 February 2014 Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) to Revise Technical Specification Sections 2.0.1 and 2.7 Project stage: Response to RAI LIC-14-0089, Withdrawal of License Amendment Request (LAR) 13-012014-07-15015 July 2014 Withdrawal of License Amendment Request (LAR) 13-01 Project stage: Withdrawal ML14204A5922014-07-25025 July 2014 FRN, Notice of Withdrawal of License Amendment Application, Revise TS 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem, or Component Due to Inoperable Power Source Project stage: Withdrawal ML14204A5782014-07-25025 July 2014 Notice of Withdrawal of License Amendment Application, Revise TS 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem, or Component Due to Inoperable Power Source Project stage: Withdrawal ML14192A9822014-08-0606 August 2014 Summary of Meeting with Omaha Public Power District to Discuss License Amendment to Revise TS 2.0.1, General Requirements, and TS 2.7, Electrical Systems, for Inoperable System, Subsystem, or Component Due to Inoperable Power Source Project stage: Meeting 2013-08-22
[Table View] |
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Category:E-Mail
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[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24243A1042024-09-12012 September 2024 Proposed Revision to the OPPD FCS DQAP - Request for Additional Information (License No. DPR-40, Docket Nos. 50-285, 72-054, and 71-0256) ML24180A2062024-07-0808 July 2024 Phase 1 Final Status Survey Reports Request for Additional Information ML23151A0042023-06-0606 June 2023 Second Set RAIs Rev 4 ML22357A0672022-12-30030 December 2022 Enclosure RAI Re Approval of License Termination Plan ML22119A2472022-05-0303 May 2022 Review of Amendment Request to Add a LC to Include LTP Requirements, RAI for Environmental Review ML20111A2162020-05-20020 May 2020 Revised PSDAR Request for Additional Information - RAI ML19241A1812019-08-21021 August 2019 Request for Additional Information on Proposed Changes to the FCS Emergency Plan and Emergency Action Level Scheme to Reflect an ISFSI-only Status ML18067A1432018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to M. J. 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Inoperable Power Source ML13205A1252013-07-24024 July 2013 Request for Additional Information Email Round 2, Exigent Amendment Request to Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact ML13205A0182013-07-23023 July 2013 Request for Additional Information Email, Exigent License Amendment Request to Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact ML13144A4822013-05-23023 May 2013 Request for Additional Information Email, Decommissioning Funding Status Report ML13100A1752013-04-10010 April 2013 Request for Additional Information Email, Request for One-Time Exemption from Requirements of 10 CFR 26.205(d)(7) to Allow Less Restrictive Working Hour Limitations to Support Activities for Plant Startup ML13086A4732013-03-27027 March 2013 Request for Additional Information Email, Request to Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan ML13120A0842013-03-22022 March 2013 Request for Additional Information Email Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 20 (TAC No. D91660) 2024-09-12
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Text
Burkhardt, Janet From: Wilkins, Lynnea Sent: Tuesday, July 30, 2013 5:08 PM To: 'HANSHER, BILL R' Cc: 'LIPPY, DONNA L'; 'EDWARDS, MICHAEL L'; Burkhardt, Janet; Sebrosky, Joseph
Subject:
DRAFT: Fort Calhoun RAI Re: Revisions to TS 2.01 and 2.7 (MF0691)
Attachments: MF0691 email RAI.docx
- Bill, By letter dated February 18, 2013 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML13051A741), the Omaha Public Power District (the licensee) requested an amendment to Facility Operating License No. DPR-40 for Fort Calhoun Station (FCS), Unit 1. The proposed changes would revise the FCS Technical Specification (TS) as follows: (1) revise the definition for Operable-Operability, (2) modify the provisions under which equipment may be considered operable when either its normal or emergency power source is inoperable, and (3) revise the minimum requirement statement in TS 2.7 in previously approved Amendment 147.
The NRC staff has reviewed the information provided and has determined that additional information specified in the Request for Additional Information (RAI) below is needed for the staff to complete its evaluation.
Please contact Joe next week if a clarifying teleconference is needed for the RAI.
Lynnea Wilkins, Project Manager Fort Calhoun Station, Unit 1 Cooper Nuclear Station Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: 301-415-1377 1
REQUEST FOR ADDITIONAL INFORMATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1 DOCKET NO. 50-285 By letter dated February 18, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13051A741), the Omaha Public Power District (the licensee) requested an amendment to Facility Operating License No. DPR-40 for Fort Calhoun Station (FCS), Unit 1. The proposed changes would revise the FCS Technical Specification (TS) as follows: (1) revise the definition for Operable-Operability, (2) modify the provisions under which equipment may be considered operable when either its normal or emergency power source is inoperable, and (3) revise the minimum requirement statement in TS 2.7 in previously approved Amendment 147.
The NRC staff has reviewed your submittal and has determined that additional information is needed for the staff to complete its evaluation.
RAI 1
The proposed TS LCO 2.0.1(2) states:
When the reactor coolant temperature is > 300°F and a system, subsystem, train, component, or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system(s),
subsystem(s), train(s), component(s), and device(s) are OPERABLE, or likewise satisfy the requirements of this specification.
- a. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery of either diesel generator inoperability, declare the required feature(s) associated with the inoperable diesel generator inoperable, when its redundant required feature (including the steam driven auxiliary feedwater pump FW-10) is inoperable.
- b. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from discovery of either house service transformer inoperability, declare the required feature(s) associated with the inoperable house service transformer inoperable, when its redundant required feature (including the steam driven auxiliary feedwater pump FW-10) is inoperable.
The wording of the above proposed TS LCO 2.0.1(2) appears similar to NUREG-0212, Revision 2, LCO 3.0.5. However, the proposed TS wording does not include the 2-hour verification of (1) and (2) above is satisfied and it does not include the required action and completion times to place the unit in a MODE in which the applicable Limiting Condition for Operation does not apply as identified in the NUREG. Please explain this inconsistency with NUREG-0212 and Enclosure
explain why continued safe operation is assured without timely (within 2-hours) verification and actions consistent with those identified in NUREG-0212.
RAI 2
The proposed relocation of a and b from TS 2.7, Electrical Systems, to TS LCO 2.0.1 is inconsistent with NUREG-0212 and NUREG-1432. Please explain how these changes more align Ft Calhoun TS with NUREG-0212 Revision 2, Standard Technical Specifications [STS] for Combustion Engineering Plants, as stated in the application.
RAI 3
TS 2.0 Limiting Conditions for Operation, 2.0.1 General Requirements, Applicability states:
Applies to the operable status of all systems, subsystems, trains, components, or devices covered by the Limiting Conditions for Operation.
Please identify all affected LCOs and the provide the reason(s) and safety justification for the proposed TS LCO 2.0.1(2) relaxation of the electrical power LCO Operability requirements for a system, subsystem, train, component or device when reactor coolant (RC) temperature is greater than 300 degrees F as compared to when the RC temperature is less than 300 degrees F (e.g., LCO 2.2, Chemical and Volume Control System Charging Pumps, Boric Acid Pumps, etc.)
RAI 4
In the LAR dated February 18, 2013, the licensee provided proposed changes to the TS 2.7 minimum requirements for the Limiting Condition of Operation (LCO) for Electrical Systems for the condition when reactor coolant temperature will be > 300° F (applicable to the availability of electrical systems for the operation of plant components). However, the staff did not find the minimum requirements for the LCOs and Surveillance Requirements (SRs) for electrical systems when reactor coolant temperature will be < 300° F. NUREG-0212 also contains minimum requirements for LCOs during shutdown condition for electrical equipment in TS 3.8.1.2, 3.8.2.2, 3.8.2.4 and related surveillance requirements (SRs) in TS 4.8.1.2, 4.8.2.2, 4.8.2.4.1 and 4.8.2.4.2 Please provide justification for deviation from NUREG-0212 for not including above LCOs and SRs for shutdown conditions when reactor coolant temperature <
300° F. Please provide an overview of all electrical equipment required to be operable for reactor coolant temperature < 300° F.
RAI 5
The proposed TS LCO 2.0.1, Specification (2) in the LAR dated February 18, 2013, states, in part its corresponding normal or emergency power sources is OPERABLE. This statement does not appear to be consistent with the proposed change in definition of Operable -
Operability which reflects normal and emergency electrical power sources.
- 1) Please explain the discrepancy between the proposed changes.
- 2) License Amendment No. 264 approved changes to definitions of Operable-Operability and as a consequence, inadvertently changed the requirement for an operable emergency power source, when reactor coolant temperature is < 300° F. Please provide details on operability requirements of equipment that will be impacted if the proposed change to TS LCO 2.0.1, Specification (2) in the LAR with the requirement for normal or emergency power is approved.
RAI 6 in Enclosure (TS Pages Retyped (Clean) Definitions Operable - Operability) of the LAR dated February 18, 2013, states, Implicit in this definition shall be the assumption that all necessary. does not appear to be consistent with NUREG-0212 Definition of Operable -
Operability. The NUREG-0212 Definition of Operable - Operability does not include the underlined words as stated above. Please explain the reasons for adding additional words Implicit in this definition shall be the assumption that to the NUREG 02012 Definition of Operable - Operability in the proposed TS change.