Letter Sequence Draft RAI |
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MONTHYEARLIC-11-0017, License Amendment Request (LAR) 10-06, Proposed Change to Establish the Ultimate Heat Sink (UHS) Limiting Condition for Operation (LCO) and Addition of UHS Level and Temperature Surveillance Requirements2011-03-0404 March 2011
License Amendment Request (LAR) 10-06, Proposed Change to Establish the Ultimate Heat Sink (UHS) Limiting Condition for Operation (LCO) and Addition of UHS Level and Temperature Surveillance Requirements
Project stage: Request
ML1109605292011-04-0606 April 2011
Acceptance Review Email, License Amendment Request, Establish Ultimate Heat Sink LCOs in Technical Specification (TS) 2.16, River Level, and Add Surveillance Requirements to TS 3.2, Equipment and Sampling Tests.
Project stage: Acceptance Review
ML1125903392011-09-16016 September 2011
Draft Request for Additional Information, Amendment Request to Establish Ultimate Heat Sink LCOs in TS 2.16, River Level, and Add Surveillance Requirements to TS 3.2, Equipment and Sampling Tests
Project stage: Draft RAI
ML1125903342011-09-16016 September 2011
E-mail, Draft Request for Additional Information, Amendment Request to Establish Ultimate Heat Sink LCOs in TS 2.16, River Level, and Add Surveillance Requirements to TS 3.2, Equipment and Sampling Tests
Project stage: Draft RAI
ML1127703142011-10-19019 October 2011
Request for Additional Information, Amendment Request to Establish Ultimate Heat Sink LCOs in TS 2.16, River Level, and Add Surveillance Requirements to TS 3.2, Equipment and Sampling Tests
Project stage: RAI
LIC-11-0127, Retraction of License Amendment Request (LAR) 10-062012-01-0404 January 2012
Retraction of License Amendment Request (LAR) 10-06
Project stage: Request
ML1202701822012-02-0202 February 2012
Withdrawal of an Amendment Request to Establish Ultimate Heat Sink LCOs in TS 2.16, River Level, and Add Surveillance Requirements to TS 3.2, Equipment and Sampling Tests
Project stage: Withdrawal
2011-04-06
[Table View] |
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Category:Request for Additional Information (RAI)
MONTHYEARML23151A0042023-06-0606 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. Fisher Request for Additional Information Regarding Omaha Public Power District'S Decommissioning Funding Plan Update for Fort Calhoun Station ISFSI)
ML17236A3442017-08-24024 August 2017
NRR E-mail Capture - Final RAI for Fort Calhoun Exemption from 10 CFR 140.11(a)(4), Off-site Primary and Secondary Liability Insurance (MF9664)
ML17236A3462017-08-24024 August 2017
NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Permanently Defueled TS (MF9567)
ML17234A4692017-08-22022 August 2017
NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Removal of Dry Cask Loading Limits (MF9831)
ML17194A9732017-07-13013 July 2017
NRR E-mail Capture - Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525)
ML17112A0362017-04-20020 April 2017
NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Permanently Defueled EP and EAL Scheme Change LAR
ML17090A3942017-03-31031 March 2017
NRR E-mail Capture - Fort Calhoun - Final RAI Regarding Administrative Control TS Change LAR (MF8437)
ML17082A0022017-03-22022 March 2017
NRR E-mail Capture - Fort Calhoun Station - Final Nsir/Dpr RAI Regarding Proposed Emergency Planning Exemption
ML17081A0192017-03-21021 March 2017
NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Proposed Emergency Planning Exemption
ML17067A3862017-03-15015 March 2017
Request for Additional Information, Request for Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management
ML17033A9692017-02-0202 February 2017
NRR E-mail Capture - Fort Calhoun Station - Final Request for Additional Information Concerning Post-Shutdown Eplan Amendment
ML16263A0492016-09-20020 September 2016
Request for Additional Information, Request for Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management
ML16174A1502016-06-27027 June 2016
Request for Additional Information, Relief Request, Use of Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1
ML16146A1782016-05-27027 May 2016
Request for Additional Information, Round 2, Request to Revise Current Licensing Basis as Described in the Final Safety Analysis Report to Allow Equipment Classification Methodology from ANSI/ANS-58.14-2011
ML16106A0232016-04-29029 April 2016
Request for Additional Information, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ML16104A2872016-04-25025 April 2016
Request for Additional Information, License Amendment Request to Revise Current Licensing Basis to Use American Concrete Institute (Aci) Ultimate Strength Requirements
ML16048A1542016-02-23023 February 2016
Request for Additional Information, License Amendment Request, Revise Current Licensing Basis as Described in the Final Safety Analysis Report to Allow Equipment Classification Methodology from ANSI/ANS-58.14-2011
ML16048A0242016-02-23023 February 2016
Request for Additional Information, License Amendment Request to Adopt Technical Specification Task Force (TSTF)-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
ML15343A1082015-12-15015 December 2015
Request for Additional Information, License Amendment Request to Make Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and Relocate a Definition
ML15323A0362015-11-24024 November 2015
Request for Additional Information, Relief Requests P-1 - LPSI and CS Pumps and P-2 - Adjusting Hydraulic Parameters Consistent W/Code Case OMN-21, Fifth 10-Year Inservice Testing Interval
ML15194A2722015-07-14014 July 2015
Request for Additional Information, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
ML15057A0152015-03-0303 March 2015
Request for Additional Information, Materials Reliability Program (MRP)-227-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines, Implementation Review
ML15043A0612015-02-25025 February 2015
Request for Additional Information, Round 2, License Amendment Request to Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III
ML14353A0512014-12-22022 December 2014
Request for Additional Information, Request to Revise Updated Safety Analysis Report, Design and Evaluation of Seismic Class I Structures Using Ascm (Alternate Seismic Criteria and Methodologies) Developed Floor Response Spectra
ML14259A3652014-09-24024 September 2014
Request for Additional Information, License Amendment Request to Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III
ML14195A0862014-07-16016 July 2014
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Hazard and Screening Report
ML13317A5832013-11-25025 November 2013
Interim Staff Evaluation and Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
ML13304B4182013-11-0101 November 2013
Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns
ML13282A5362013-10-0909 October 2013
Request for Additional Information Email, Round 2, Exemption Request, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7)
ML13290A0022013-10-0909 October 2013
Request for Additional Information Email, License Amendment Request to Revise Current Licensing Basis of Pipe Break Criteria for High Energy Line Breaks
ML13270A2872013-09-27027 September 2013
Email, Request for Additional Information Round 4 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
ML13261A2122013-09-18018 September 2013
Request for Additional Information Email, Exemption Request, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage, in Lieu of 10 CFR 26.205(d)(7)
ML13233A2482013-08-26026 August 2013
Supplemental Information Needed for Acceptance of Requested Licensing Action; Request for Exemption, Use of Less Restrictive Work Hour Limitations During First 60 Days of Outage in Lieu of 10 CFR 26.205(d)(7)
ML13235A1682013-08-23023 August 2013
Draft Request for Additional Information Email, Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
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
ML13226A1222013-08-14014 August 2013
Email, Request for Additional Information Round 3 (Apla), Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
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
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)
ML13053A2262013-02-22022 February 2013
Email, Second Round Draft Request for Additional Information, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.
ML13016A4322013-01-16016 January 2013
E-mail, Request for Additional Information, Round 2, Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
2023-06-06
[Table view] |
Text
REQUEST FOR ADDITIONAL INFORMATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1 DOCKET NO. 50-285 By letter dated March 4, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110680093), Omaha Public Power District (OPPD, the licensee) requested an amendment to the Facility Operating License No. DPR-40 for Fort Calhoun Station, Unit 1. The proposed amendment would establish the limiting condition for operation (LCO) requirements for the ultimate heat sink (UHS) in Technical Specification (TS) 2.16, River Level, and adds two new surveillance requirements (SRs) for UHS level and temperature to TS 3.2, Equipment and Sampling Tests, Table 3-5, Minimum Frequencies for Equipment Tests.
Specifically, this proposed change: revises the title of LCO 2.16 from "River Level" to "Ultimate Heat Sink (UHS);" provides more explicit applicability for the LCO 2.16; removes the existing LCOs for river level in TS 2.16, Items 1) and (2); and, reformats TS LCO 2.16 to provide required actions for an inoperable UHS. In addition, two new SRs, Items 25 and 26, will be added to TS 3.2, Table 3-5, to test the river level and temperature on a daily frequency; and for consistency, the columns will be reformatted to allow adding the column header to Table 3-5 for Items 17 through 24. The Table of Contents is also revised to reflect the title change of LCO 2.16.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in your application and determined that the following additional information is required in order to complete its review.
- 1. FCS is committed to the draft GDC, which are similar to Appendix A, General Design Criteria for Nuclear Power Plants, in 10 CFR Part 50, and are contained in Appendix G, Response to 70 Criteria, of the FCS Updated Safety Analysis Report (USAR). FCS Design Criterion 2, Performance Standards, states, in part:
Those systems and components of reactor facilities which are essential to the prevention of accidents which could affect public health and safety or to mitigation of their consequences shall be designed, fabricated, and erected to performance standards that will enable the facility to withstand, without loss of the capability to protect the public, the additional forces that might be imposed by natural phenomena such as earthquakes, tornadoes, flooding conditions, winds, ice and other local site effects.
Regulatory Guide 1.59, Design Basis Floods for Nuclear Power Plants, requires, in part, that structures, systems and components (SSCs) importance to safety be designed to withstand the effects of natural phenomena such as floods without loss of capability to perform their safety functions.
Enclosure
In its letter dated March 4, 2011, the licensee states:
The proposed amendment would establish the limiting condition for operation (LCO) requirements for the ultimate heat sink (UHS) in the Technical Specification (TS) 2.16, River Level, and adds two new surveillance requirements (SRs) for UHS level and temperature to TS 3.2 Please provide the reason and justification to remove the high end (Flood) of the Missouri River level from the TS 2.16, and the new location of these requirements.
- 2. In its letter dated March 4, 2011, the licensee stated that flooding at FCS is highly unlikely and therefore, requested to remove the provision in TS requiring a plant shut down if the Missouri River level reaches 1009 feet. The licensee states that a high river level TS does not meet the requirements of 10 CFR 50.63.
10 CFR 50.63(c)(2)(ii)(D) Criterion 4 states a structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety. In addition, 10 CFR 50.36(c)(2)(ii)(B) requires the licensee to establish a TS limiting condition for a operating restriction that is a initial condition of a design basis accident or transient analysis. Based upon recent operating experience, please describe flooding as a risk to the plants ability to maintain safe shutdown capabilities.
In addition, please provide the latest data on river level peaking for the Missouri River at the FCS location and explain if the latest data on river level supports the current high level setpoint. Also, please describe how removing the high river level limit still provides assurance that the plant can safely shut down prior to losing equipment at the intake structure.
- 3. In the FCS Design Criterion 12, the licensee states instrumentation conforms to the applicable Institute of Electrical and Electronics Engineers (IEEE) standards. The licensee is proposing to add a new TS surveillance to limit the UHS temperature to 90°F.
The licensee credits existing instrumentation to monitor river temperature. The licensee states that it will encompass the loop uncertainty for UHS temperature in the surveillance test. Also, the licensee proposes to add a TS surveillance to limit the UHS to a river level of 976 feet 9 inches. However, the licensee states its current river level instrumentation is not very accurate and intends on replacing the river level instrumentation with a more reliable system. The licensee also designates a TS surveillance limit for the river water maximum temperature and minimum level at the assumed limit used in the design basis calculations which shows sufficient heat removal in order to mitigate a design basis accident.
Please provide the methods used for monitoring river water temperature and level to comply with the current licensing basis. Also, please explain how OPPD plans to capture the uncertainty in the instrumentation used for monitoring river temperature and level.
- 4. In its letter dated March 4, 2011, the licensee states:
Missouri River level is currently monitored by non-safety related loop L-1900.
The measurement technology is based on a bubbler system where air pressure is directly proportional to the depth of the bubbler outlet. The accuracy of this loop is very poor with an As Found/As Left loop tolerance of +/- 2 feet as documented in calibration procedure IC-CP-01-1900. This loop is in the process
of being replaced with loop L-2000 via engineering change EC 35741. This instrumentation is expected to be placed in service during 2011.
Please provide the test data (accuracy) and documentation (industry experience) to support the EC 35741.
- 5. In its letter dated March 4, 2011, the licensee proposed a TS SR for low level of 976 feet 9 inches of the UHS - Missouri River. The licensee states that a river level of 976 feet 9 inches is required for raw water pumps minimum submergence level.
10 CFR 50.36 requires the licensee establish limiting conditions for operation, and when they are not met, the licensee shall shut down the reactor. The licensee proposes a TS limit on low river level at the same level where the raw water pumps become unavailable for use; however, the raw water pumps are required to shut down the reactor. Please describe how this TS change will affect the availability of raw water pumps to bring the plant to cold shutdown conditions.
- 6. Please verify that no change is being made to any containment safety analysis or any parameter that could affect the containment safety analysis as part of this license amendment request. If this license amendment request is resulting in a change to any containment safety analysis or any parameter that could affect the containment safety analysis, please describe and justify these changes.
- 7. Please state if the calculation for the component cooling water heat exchangers heat removal capability to supply 160 degree return water with 90 degree river water has been reviewed by the NRC staff.
