ML071620201: Difference between revisions
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{{#Wiki_filter:July 6, 2007 LICENSEE: | {{#Wiki_filter:July 6, 2007 LICENSEE: | ||
Wolf Creek Nuclear Operating Corporation FACILITY: | |||
Wolf Creek Generating Station | |||
==SUBJECT:== | ==SUBJECT:== | ||
==SUMMARY== | ==SUMMARY== | ||
OF TELEPHONE CONFERENCE CALL HELD ON MAY 24, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING THE ANALYSIS OF SEVERE ACCIDENT MITIGATION ALTERNATIVES PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf Creek Nuclear Operating Corporation (WCNOC) held a telephone conference call on May 24, 2007, to discuss and clarify some of the responses provided by WCNOC to requests for additional information (RAIs) concerning the analysis of Severe Accident Mitigation Alternatives (SAMAs) for Wolf Creek Generating Station, Unit 1, license renewal application (LRA). The telephone conference call was useful in clarifying responses to RAIs previously provided by WCNOC to SAMA requests for additional information. provides a listing of the participants, and Enclosure 2 contains a listing of the SAMA questions discussed with the applicant, including a brief description on the status of the items. | OF TELEPHONE CONFERENCE CALL HELD ON MAY 24, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING THE ANALYSIS OF SEVERE ACCIDENT MITIGATION ALTERNATIVES PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf Creek Nuclear Operating Corporation (WCNOC) held a telephone conference call on May 24, 2007, to discuss and clarify some of the responses provided by WCNOC to requests for additional information (RAIs) concerning the analysis of Severe Accident Mitigation Alternatives (SAMAs) for Wolf Creek Generating Station, Unit 1, license renewal application (LRA). The telephone conference call was useful in clarifying responses to RAIs previously provided by WCNOC to SAMA requests for additional information. provides a listing of the participants, and Enclosure 2 contains a listing of the SAMA questions discussed with the applicant, including a brief description on the status of the items. | ||
The applicant had an opportunity to comment on this summary. | The applicant had an opportunity to comment on this summary. | ||
/RA/ | |||
Christian Jacobs, Project Manager Environmental Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-482 | Christian Jacobs, Project Manager Environmental Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-482 | ||
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: 2. List of SAMA RAIs cc w/encls: See next page | : 2. List of SAMA RAIs cc w/encls: See next page | ||
ML071620201 OFFICE | ML071620201 OFFICE PM:REBB:DLR LA:DLR BC:REBB:DLR NAME C. Jacobs Y. Edmonds R. Franovich DATE 06/29/07 06/29/07 07/06/07 TELEPHONE CONFERENCE CALL WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS May 24, 2007 PARTICIPANTS AFFILIATIONS Christian Jacobs U.S. Nuclear Regulatory Commission (NRC) | ||
Robert Palla | Robert Palla NRC Bruce Mrowca Information Systems Laboratories Charlie Medenciy Wolf Creek Nuclear Operating Corporation (WCNOC) | ||
Patrick Guevel | Patrick Guevel WCNOC David Alford WCNOC Mark Ferrel WCNOC J.C. Patel WCNOC Bill Ketchum WCNOC SEVERE ACCIDENT MITIGATION ALTERNATIVE ADDITIONAL QUESTIONS REGARDING WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION May 24, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf Creek Nuclear Operating Corporation (WCNOC) held a telephone conference call on May 24, 2007, to discuss the following questions regarding responses to requests for additional information (RAIs) analysis for Severe Accident Mitigation Alternatives (SAMAs) for Wolf Creek Generating Station Unit 1, license renewal application. | ||
SEVERE ACCIDENT MITIGATION ALTERNATIVE ADDITIONAL QUESTIONS REGARDING WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION May 24, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf Creek Nuclear Operating Corporation (WCNOC) held a telephone conference call on May 24, 2007, to discuss the following questions regarding responses to requests for additional information (RAIs) analysis for Severe Accident Mitigation Alternatives (SAMAs) for Wolf Creek Generating Station Unit 1, license renewal application. | |||
: 1. In response to Question 1b (QU-9) it is stated that internal flooding scenarios have not been included in Probalistic Safety Assessment updates and that new internal flooding criteria may identify new human-induced floods through consideration of errors of commission. State how this could impact the SAMA analysis. | : 1. In response to Question 1b (QU-9) it is stated that internal flooding scenarios have not been included in Probalistic Safety Assessment updates and that new internal flooding criteria may identify new human-induced floods through consideration of errors of commission. State how this could impact the SAMA analysis. | ||
Discussion: The applicant provided clarification of their RAI response in a follow-up e-mail. | Discussion: The applicant provided clarification of their RAI response in a follow-up e-mail. | ||
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Reference response in (ADAMS under Accession No. ML071590339). Issue resolved. | Reference response in (ADAMS under Accession No. ML071590339). Issue resolved. | ||
: 4. In response to Question 3c, it is stated that WCGS has high temperature seal material installed in only one RCP. State the seal LOCA model used. Discuss plans for installing qualified seals in the remaining RCPs. Provide a cost-benefit assessment for installing qualified seals in the remaining RCPs, if this is not currently planned. | : 4. In response to Question 3c, it is stated that WCGS has high temperature seal material installed in only one RCP. State the seal LOCA model used. Discuss plans for installing qualified seals in the remaining RCPs. Provide a cost-benefit assessment for installing qualified seals in the remaining RCPs, if this is not currently planned. | ||
Discussion: The applicant clarified that they have high temperature seals in all 4 RCPs. Issue resolved. | Discussion: The applicant clarified that they have high temperature seals in all 4 RCPs. Issue resolved. | ||
: 5. In response to Question 7a, it is stated that procedures exist at WCGS to operate the turbine driven auxilary feedwater pump after battery depletion. Describe these procedures, including the instrumentation used to effectively control SG level. State the human error probability or probabilities used for this action. | : 5. In response to Question 7a, it is stated that procedures exist at WCGS to operate the turbine driven auxilary feedwater pump after battery depletion. Describe these procedures, including the instrumentation used to effectively control SG level. State the human error probability or probabilities used for this action. | ||
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: 6. In response to Question 6.b.ii it is stated that extending the Emergency Diesel Generator (EDG) completion time actions 24/7 would potentially place Technical Specification Amendment #163 in jeopardy. This appears to be due to the presence of a reduced base risk profile as a result of implementing the proposed alternative making the removal of an EDG more significant (Its not that an EDG outage is more significant, it is that the plants risk profile is lower making the delta risk greater). Please clarify this. | : 6. In response to Question 6.b.ii it is stated that extending the Emergency Diesel Generator (EDG) completion time actions 24/7 would potentially place Technical Specification Amendment #163 in jeopardy. This appears to be due to the presence of a reduced base risk profile as a result of implementing the proposed alternative making the removal of an EDG more significant (Its not that an EDG outage is more significant, it is that the plants risk profile is lower making the delta risk greater). Please clarify this. | ||
Discussion: The applicant provided clarification of their RAI response. The applicant also suggested that NRC staff re-examine information provided on Pages 30-40 of SAMA RAI response, letter ET 07-0006 (ADAMS Accession No. ML071160203). Issue resolved. | Discussion: The applicant provided clarification of their RAI response. The applicant also suggested that NRC staff re-examine information provided on Pages 30-40 of SAMA RAI response, letter ET 07-0006 (ADAMS Accession No. ML071160203). Issue resolved. | ||
Memo to Wolf Creek Nuclear Operating Corporation from C. Jacobs dated July 6, 2007 | Memo to Wolf Creek Nuclear Operating Corporation from C. Jacobs dated July 6, 2007 | ||
==SUBJECT:== | ==SUBJECT:== | ||
==SUMMARY== | ==SUMMARY== | ||
OF TELEPHONE CONFERENCE CALL HELD ON MAY 24, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING THE ANALYSIS OF SEVERE ACCIDENT MITIGATION ALTERNATIVES PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION DISTRIBUTION: | OF TELEPHONE CONFERENCE CALL HELD ON MAY 24, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING THE ANALYSIS OF SEVERE ACCIDENT MITIGATION ALTERNATIVES PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION DISTRIBUTION: | ||
| Line 63: | Line 60: | ||
Wolf Creek Generating Station cc: | Wolf Creek Generating Station cc: | ||
Jay Silberg, Esq. | Jay Silberg, Esq. | ||
and Environment | Pillsbury Winthrop Shaw Pittman, LLP 2300 N Street, NW Washington, DC 20037 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-7005 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 311 Burlington, KS 66839 Chief Engineer, Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, KS 66604-4027 Office of the Governor State of Kansas Topeka, KS 66612 Attorney General 120 S.W. 10th Avenue, 2nd Floor Topeka, KS 66612-1597 County Clerk Coffey County Courthouse 110 South 6th Street Burlington, KS 66839 Thomas A. Conley, Section Chief Radiation and Asbestos Control Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366 Vice President Operations/Plant Manager Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Supervisor Licensing Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 U.S. Nuclear Regulatory Commission Resident Inspectors Office/Callaway Plant 8201 NRC Road Steedman, MO 65077-1032 Mr. Terry J. Garrett Vice President Engineering Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Kevin J. Moles, Manager Regulatory Affairs Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Lorrie I. Bell, Project Manager Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Ms. Julie Keys Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Ms. Valerie Williams, Branch Director Coffey County Library Burlington Branch 410 Juniatta St. | ||
Burlington, KS 66839}} | |||
Latest revision as of 23:18, 14 January 2025
| ML071620201 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/06/2007 |
| From: | Christian Jacobs NRC/NRR/ADRO/DLR/REBB |
| To: | NRC/NRR/ADRO |
| Logan, Dennis NRR/DLR/REBA - 415-0490 | |
| References | |
| Download: ML071620201 (7) | |
Text
July 6, 2007 LICENSEE:
Wolf Creek Nuclear Operating Corporation FACILITY:
Wolf Creek Generating Station
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON MAY 24, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING THE ANALYSIS OF SEVERE ACCIDENT MITIGATION ALTERNATIVES PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf Creek Nuclear Operating Corporation (WCNOC) held a telephone conference call on May 24, 2007, to discuss and clarify some of the responses provided by WCNOC to requests for additional information (RAIs) concerning the analysis of Severe Accident Mitigation Alternatives (SAMAs) for Wolf Creek Generating Station, Unit 1, license renewal application (LRA). The telephone conference call was useful in clarifying responses to RAIs previously provided by WCNOC to SAMA requests for additional information. provides a listing of the participants, and Enclosure 2 contains a listing of the SAMA questions discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
/RA/
Christian Jacobs, Project Manager Environmental Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosures:
- 1. List of Participants
ML071620201 OFFICE PM:REBB:DLR LA:DLR BC:REBB:DLR NAME C. Jacobs Y. Edmonds R. Franovich DATE 06/29/07 06/29/07 07/06/07 TELEPHONE CONFERENCE CALL WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS May 24, 2007 PARTICIPANTS AFFILIATIONS Christian Jacobs U.S. Nuclear Regulatory Commission (NRC)
Robert Palla NRC Bruce Mrowca Information Systems Laboratories Charlie Medenciy Wolf Creek Nuclear Operating Corporation (WCNOC)
Patrick Guevel WCNOC David Alford WCNOC Mark Ferrel WCNOC J.C. Patel WCNOC Bill Ketchum WCNOC SEVERE ACCIDENT MITIGATION ALTERNATIVE ADDITIONAL QUESTIONS REGARDING WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION May 24, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf Creek Nuclear Operating Corporation (WCNOC) held a telephone conference call on May 24, 2007, to discuss the following questions regarding responses to requests for additional information (RAIs) analysis for Severe Accident Mitigation Alternatives (SAMAs) for Wolf Creek Generating Station Unit 1, license renewal application.
- 1. In response to Question 1b (QU-9) it is stated that internal flooding scenarios have not been included in Probalistic Safety Assessment updates and that new internal flooding criteria may identify new human-induced floods through consideration of errors of commission. State how this could impact the SAMA analysis.
Discussion: The applicant provided clarification of their RAI response in a follow-up e-mail.
Reference response in (ADAMS under Accession No. ML071590339). Issue resolved.
- 2. The answer provided to Question 1b (TH-6) talks about the definition used in the Individual Plant Examination (IPE) while the Facts and Observations are focused on the Modular Accident Analysis Program (MAAP) calculation and states that the 30-minute criteria was not likely a factor in determining success or failure in many (if any) of the analyses performed for the IPE. State the issue associated with the core damage criteria used in the MAAP calculations and its impact on the SAMA evaluation.
Discussion: The applicant provided clarification of their RAI response. Issue resolved.
- 3. In response to Question 2b, it is stated that NUREG-1570 asserts that only 2 percent of the high pressure melt scenarios with dry steam generators (SG) would result in an induced Steam Generator Tube Rupture (SGTR) and that the applicability of percentage is predicated on the conditions that the secondary side is not depressurized and that the Reactor Coolant Pumps (RCPs) are not operated. A review of NUREG-1570 found that for cases where an RCP seal Loss of Coolant Accident (LOCA) occurs that the Thermally Induced SGTR failure probability for 3 steam generators (4 SG scenario is not available) is 1.0. State how this increased failure likelihood on RCP seal failure was accounted for in the response to Question 2b.
Discussion: The applicant provided clarification of their RAI response in a follow-up e-mail.
Reference response in (ADAMS under Accession No. ML071590339). Issue resolved.
- 4. In response to Question 3c, it is stated that WCGS has high temperature seal material installed in only one RCP. State the seal LOCA model used. Discuss plans for installing qualified seals in the remaining RCPs. Provide a cost-benefit assessment for installing qualified seals in the remaining RCPs, if this is not currently planned.
Discussion: The applicant clarified that they have high temperature seals in all 4 RCPs. Issue resolved.
- 5. In response to Question 7a, it is stated that procedures exist at WCGS to operate the turbine driven auxilary feedwater pump after battery depletion. Describe these procedures, including the instrumentation used to effectively control SG level. State the human error probability or probabilities used for this action.
Discussion: The applicant provided clarification of their RAI response. NRC understands the procedure that WCNOC is using for this turbine driven pump. Issue resolved.
- 6. In response to Question 6.b.ii it is stated that extending the Emergency Diesel Generator (EDG) completion time actions 24/7 would potentially place Technical Specification Amendment #163 in jeopardy. This appears to be due to the presence of a reduced base risk profile as a result of implementing the proposed alternative making the removal of an EDG more significant (Its not that an EDG outage is more significant, it is that the plants risk profile is lower making the delta risk greater). Please clarify this.
Discussion: The applicant provided clarification of their RAI response. The applicant also suggested that NRC staff re-examine information provided on Pages 30-40 of SAMA RAI response, letter ET 07-0006 (ADAMS Accession No. ML071160203). Issue resolved.
Memo to Wolf Creek Nuclear Operating Corporation from C. Jacobs dated July 6, 2007
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON MAY 24, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING THE ANALYSIS OF SEVERE ACCIDENT MITIGATION ALTERNATIVES PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION DISTRIBUTION:
E-mail P.T. Kuo / S. Lee (RidsNrrDlr)
R. Franovich (RidsNrrDlrReba)
E. Benner (RidsNrrDlrReba)
C. Jacobs A. Williamson Bobbie.hurley@earthtech.com V. Rodriguez J. Donohew G. Pick, RIV S. Cochrum, RIV C. Long, RIV OGC (RidsOGCMailRoom)
D. Roth, OGC DLR/REBB DLR/REBA
Wolf Creek Generating Station cc:
Jay Silberg, Esq.
Pillsbury Winthrop Shaw Pittman, LLP 2300 N Street, NW Washington, DC 20037 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-7005 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 311 Burlington, KS 66839 Chief Engineer, Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, KS 66604-4027 Office of the Governor State of Kansas Topeka, KS 66612 Attorney General 120 S.W. 10th Avenue, 2nd Floor Topeka, KS 66612-1597 County Clerk Coffey County Courthouse 110 South 6th Street Burlington, KS 66839 Thomas A. Conley, Section Chief Radiation and Asbestos Control Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366 Vice President Operations/Plant Manager Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Supervisor Licensing Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 U.S. Nuclear Regulatory Commission Resident Inspectors Office/Callaway Plant 8201 NRC Road Steedman, MO 65077-1032 Mr. Terry J. Garrett Vice President Engineering Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Kevin J. Moles, Manager Regulatory Affairs Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Lorrie I. Bell, Project Manager Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Ms. Julie Keys Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Ms. Valerie Williams, Branch Director Coffey County Library Burlington Branch 410 Juniatta St.
Burlington, KS 66839