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Category:Letter type:ET
MONTHYEARET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components ET 23-0005, 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peen2023-03-16016 March 2023 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened ET 23-0003, License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications2023-03-0101 March 2023 License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2023-02-0707 February 2023 Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 23-0004, Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2023-01-26026 January 2023 Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0006, Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-12-0101 December 2022 Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 22-0010, License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2022-08-0202 August 2022 License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0011, Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface2022-05-31031 May 2022 Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface ET 22-0005, Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-04-13013 April 2022 Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0003, CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads2022-04-0606 April 2022 CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads ET 22-0002, Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head .2022-04-0404 April 2022 Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head . ET 22-0004, Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report2022-03-15015 March 2022 Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report ET 22-0001, Removal of the Table of Contents from the Technical Specifications2022-01-12012 January 2022 Removal of the Table of Contents from the Technical Specifications ET 21-0017, Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-12-22022 December 2021 Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0009, Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage2021-11-0101 November 2021 Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage ET 21-0015, Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-20020 October 2021 Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0012, Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-11011 October 2021 Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0004, License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2021-09-29029 September 2021 License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 21-0010, License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-09-29029 September 2021 License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0005, Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-1912021-08-12012 August 2021 Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 20-0013, Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415)2020-10-26026 October 2020 Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415) ET 20-0011, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-10-0101 October 2020 Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ET 20-0007, License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers2020-06-0808 June 2020 License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ET 20-0008, Operating Corporation Update for Full Implementation of Open Phase Detection System2020-05-20020 May 2020 Operating Corporation Update for Full Implementation of Open Phase Detection System ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2020-04-27027 April 2020 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) ET 20-0002, Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 12020-01-29029 January 2020 Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 ET 19-0021, Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-12-0909 December 2019 Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0020, Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-11-13013 November 2019 Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0019, Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-09-10010 September 2019 Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0018, Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-08-22022 August 2019 Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0014, lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 12019-08-15015 August 2019 lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 1 ET 19-0002, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-03-18018 March 2019 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0008, Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption.2019-03-0505 March 2019 Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption. ET 19-0003, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange2019-02-25025 February 2019 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange ET 19-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-01-23023 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 ET 18-0032, Operating Corporation Change of Date for Full Implementation of Open Phase Detection System2018-12-0707 December 2018 Operating Corporation Change of Date for Full Implementation of Open Phase Detection System ET 18-0035, Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-12-0606 December 2018 Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0029, (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection2018-10-31031 October 2018 (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-06-19019 June 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0016, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information2018-05-29029 May 2018 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information ET 18-0014, Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-05-29029 May 2018 Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0013, Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld2018-05-0202 May 2018 Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld ET 18-0011, (WCGS) - Guarantee of Payment of Deferred Premiums2018-04-30030 April 2018 (WCGS) - Guarantee of Payment of Deferred Premiums ET 18-0012, Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-04-19019 April 2018 Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0010, Financial Protection Levels2018-03-29029 March 2018 Financial Protection Levels ET 18-0007, Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-02-15015 February 2018 Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0005, Withdrawal of License Amendment Request for Revision to the Emergency Plan2018-02-0505 February 2018 Withdrawal of License Amendment Request for Revision to the Emergency Plan ET 18-0004, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-01-29029 January 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 17-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-11-14014 November 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term 2023-05-17
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W LF CREEK VNUCLEAR OPERATING CORPORATION John P. Broschak Vice President Engineering January 28, 2014 ET 14-0006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
References:
- 1) Letter dated March 12, 2012 from E. J. Leeds and M. R. Johnson, USNRC, to M. W. Sunseri, WCNOC, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)
Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident"
- 2) Letter dated May 31, 2012 from D. L. Skeen, USNRC, to A. P.
Heymer, NEI, "Endorsement of Nuclear Energy Institute (NEI) 12-07, Guidelines for Performing Verification Walkdowns of Plant Flood Protection Features"
- 3) Letter ET 12-0013, dated June 5, 2012, from J. P. Broschak, WCNOC, to USNRC
- 4) Letter ET 12-0031, dated November 27, 2012, from J. P.
Broschak, WCNOC, to USNRC
- 5) Letter dated December 23, 2013, from R. J. Pascarelli, USNRC, to M. W. Sunseri, WCNOC, "Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Flooding Walkdowns"
Subject:
Docket No. 50-482: Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Flooding Walkdowns Gentlemen:
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status and specifically issued a 10 CFR 50.54(f) letter to Wolf Creek Nuclear Operating Corporation (WCNOC). In Reference 3, WCNOC confirmed that it will use the flooding walkdown procedure endorsed by Reference 2 as the basis for performing flooding walkdowns at Wolf Creek Ap.
P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET
ET 14-0006 Page 2 of 3 Generating Station. Reference 4 provided WCNOC's final response to Reference 1, Enclosure 4, "Recommendation 2.3: Flooding." Reference 5 transmitted a Request for Additional Information (RAI) associated with Recommendation 2.3. The attachment to this letter provides WCNOC's response to the RAI.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4085, or Mr. Michael J. Westman at (620) 364-4009.
Sincerely, John P. Broschak JPB/rlt Attachment cc: M. L. Dapas (NRC), w/a E. J. Leeds (NRC), w/a C. F. Lyon (NRC), w/a N. F. O'Keefe (NRC), w/a Senior Resident Inspector (NRC), w/a
ET 14-0006 Page 3 of 3 STATE OF KANSAS )
SS COUNTY OF COFFEY )
John P. Broschak, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
Joh . Broschak Vieresident Engineering SUBSCRIBED and sworn to before me this 2A day of .l.. k(.-
Lc' ,2014.
CAYLE SHEPHEARD Not ublic ackryputjIiý - Stateofan S pi tA ,_rt. S_ l K Expiration Date I m12-L6
Attachment to ET 14-0006 Page 1 of 3 Response to Request for Additional Information The Nuclear Regulatory Commission (NRC) issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status and specifically issued a 10 CFR 50.54(0 letter to Wolf Creek Nuclear Operating Corporation (WCNOC). In Reference 3, WCNOC confirmed that it will use the flooding walkdown procedure endorsed by Reference 2 as the basis for performing flooding walkdowns at Wolf Creek Generating Station. Reference 4 provided WCNOC's final response to Reference 1, Enclosure 4, "Recommendation 2.3:
Flooding." Reference 5 transmitted a Request for Additional Information (RAI) associated with Recommendation 2.3. This attachment provides WCNOC's response to the RAI. The specific NRC questions are shown in italic type.
- 1. Confirmation that the process for evaluating the APM was reviewed.
Response: Wolf Creek Nuclear Operating Corporation has completed a review of the process used at Wolf Creek Generating Station to evaluate available physical margin (APM).
- 2. Confirmation that the APM process is now or was always consistent with the guidance in NEI 12-07 and discussed in this RAI.
Response: The original walkdown effort followed the guidance provided in NEI 12-07, "Guidelines for Performing Verification Walkdowns of Plant Flood Protection Features."
However, a small margin evaluation had not been performed for any of the flood protection features. Although a small margin value was not pre-established, the original walkdown effort confirmed that the seals can perform their intended safety function against floods up to the current licensing basis flood height. Condition Report (CR) 78295 has been entered into the corrective action program to perform a small margin evaluation for specific flood protection features in accordance with NEI 12-07, Section 5.8.
- 3. If changes are necessary, a general description of any process changes to establish this consistency.
Response: A small margin value will be defined. APMs calculated during the walkdown will then be compared to the small margin value. Any flood protection feature found to have small margin will be identified and entered into the corrective action program.
Attachment to ET 14-0006 Page 2 of 3
- 4. As a result of the audits and subsequent interactionswith industry during public meetings, NRC staff recognized that evaluation of APM for seals (e.g., flood doors, penetrations,flood gates, etc.) was challenging for some licensees. Generally, licensees were expected to use either Approach A or Approach B (describedbelow) to determine the APM for seals:
a) If seal pressure ratings were known, the seal ratings were used to determine APM (similarto example 2 in Section 3.13 of NEI 12-07). A numerical value for APM was documented. No further action was performed if the APM value was greaterthan the pre-establishedsmall-margin threshold value. If the APM value was small, an assessment of "significantconsequences" was performed and the guidance in NEI 12-07 Section 5.8 was followed.
b) If the seal pressure rating was not known, the APM for seals in a flood barrieris assumed to be greaterthan the pre-establishedsmall-margin threshold value if the following conditions were met: (1) the APM for the barrierin which the seal is located is greater than the small-margin threshold value and there is evidence that the seals were designed/procured,installed, and controlled as flooding seals in accordance with the flooding licensing basis. Note that in order to determine that the seal has been controlled as a flooding seal, it was only necessary to determine that the seal configuration has been governed by the plant's design control process since installation. In this case, the APM for the seal could have been documented as "not small".
As part of the RAI response, state if either Approach A or Approach B was used as part of the initial walkdowns or as part of actions taken in response to this RAI. No additional actions are necessary if eitherApproach A or B was used.
If neither Approach A or B was used to determine the APM values for seals (either as part of the walkdowns or as part of actions taken in response to this RAI), then perform the following two actions:
Enter the condition into the CAP (note: it is acceptable to utilize a single CAP entry to capture this issue for multiple seals). CAP disposition of "undetermined" APM values for seals should consider the guidance provided in NEI 12-07, Section 5.8. The CAP disposition should confirm all seals can perform their intended safety function against floods up to the current licensing basis flood height. Disposition may occur as part of the Integrated Assessment. If an IntegratedAssessment is not performed, determine whether there are significant consequences associated with exceeding the capacity of the seals and take interim action(s), if necessary, via the CAP processes. These actions do not need to be complete priorto the RAI response.
Report the APM as "undetermined"and provide the CAP reference in the RAI response Response: Approach A was used to determine the APM values for seals. Seal ratings were used to determine APM and a numerical value for APM was documented. Although a small margin value was not pre-established, the original walkdown effort confirmed that the seals can perform their intended safety function against floods up to the current licensing basis flood height. CR 78295 has been entered into the corrective action program to perform a small margin evaluation for specific flood protection features in accordance with NEI 12-07, Section 5.8.
Attachment to ET 14-0006 Page 3 of 3
References:
- 1. Letter from E. J. Leeds and M. R. Johnson, USNRC, to M. W. Sunseri, WCNOC, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," March 12, 2012; ADAMS Accession No. ML12053A340.
- 2. Letter from D. L. Skeen, USNRC, to A. P. Heymer, NEI, "Endorsement of Nuclear Energy Institute (NEI) 12-07, Guidelines for Performing Verification Walkdowns of Plant Flood Protection Features," May 31, 2012.
- 3. WCNOC letter ET 12-0013, "Wolf Creek Nuclear Operating Corporation's 90-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.3, Flooding, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," June 5, 2012; ADAMS Accession No. ML12165A244.
- 4. WCNOC letter ET 12-0031, "Wolf Creek Nuclear Operating Corporation 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)
Recommendation 2.3 (Flooding) of the Near- Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," November 27, 2012; ADAMS Accession No. ML12340A397.
- 5. Letter from R. J. Pascarelli, USNRC, to M. W. Sunseri, WCNOC, "Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Flooding Walkdowns," December 23, 2013; ADAMS Accession No. ML13325A891.