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{{#Wiki_filter:August 28, 2007LICENSEE:Wolf Creek Nuclear Operating CorporationFACILITY:Wolf Creek Generating Station, Unit 1
{{#Wiki_filter:August 28, 2007 LICENSEE:       Wolf Creek Nuclear Operating Corporation FACILITY:       Wolf Creek Generating Station, Unit 1


==SUBJECT:==
==SUBJECT:==


==SUMMARY==
==SUMMARY==
OF TELEPHONE CONFERENCE CALL HELD ONAUGUST 17, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATIONThe U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf CreekNuclear Operating Corporation held a telephone conference call on August 17, 2007, to discuss and clarify the staff's requests for additional information (RAIs) concerning the Wolf Creek Generating Station, Unit 1, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's RAIs.Enclosure 1 provides a listing of the participants and Enclosure 2 contains a listing of the RAIsdiscussed with the applicant, including a brief description on the status of the items.The applicant had an opportunity to comment on this summary. A mutually agreeable date forthe response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3703 or e-mail vmr1@nrc.gov
OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 17, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION 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 held a telephone conference call on August 17, 2007, to discuss and clarify the staffs requests for additional information (RAIs) concerning the Wolf Creek Generating Station, Unit 1, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs RAIs. provides a listing of the participants and Enclosure 2 contains a listing of the RAIs discussed with the applicant, including a brief description on the status of the items.
./RA/Verónica M. Rodríguez, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor RegulationDocket No. 50-482
The applicant had an opportunity to comment on this summary. A mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3703 or e-mail vmr1@nrc.gov.
                                                /RA/
Verónica M. Rodríguez, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-482


==Enclosures:==
==Enclosures:==
: 1. List of Participants
: 1. List of Participants
: 2. List of Requests for Additional Informationcc w/encls: See next page  
: 2. List of Requests for Additional Information cc w/encls: See next page


ML072320452OFFICELA:DLRPM:RLRB:DLRBC:RLRB:DLRNAMEYEdmondsVRodríguezRAuluck DATE08/24/0708/27/0708/28/07 Letter to Wolf Creek Nuclear Operating Corp From V. Rodriguez Dated August 28, 2007
ML072320452 OFFICE      LA:DLR                PM:RLRB:DLR            BC:RLRB:DLR NAME        YEdmonds              VRodríguez            RAuluck DATE        08/24/07              08/27/07              08/28/07
 
Letter to Wolf Creek Nuclear Operating Corp From V. Rodriguez Dated August 28, 2007


==SUBJECT:==
==SUBJECT:==


==SUMMARY==
==SUMMARY==
OF TELEPHONE CONFERENCE CALL HELD ONAUGUST 17, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATIONDISTRIBUTION
OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 17, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION DISTRIBUTION:
:HARD COPY: DLR RFE-MAIL:PUBLICSSmith (srs3)
HARD COPY:
SDuraiswamy RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb
DLR RF E-MAIL:
 
PUBLIC SSmith (srs3)
RidsNrrDci RidsNrrDra RidsNrrDe RidsNrrDeEemb RidsNrrDeEeeb
SDuraiswamy RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDci RidsNrrDra RidsNrrDe RidsNrrDeEemb RidsNrrDeEeeb RidsNrrDss RidsOgcMailCenter RidsNrrAdes
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VRodriguez CJacobs JDonohew GPick, RIV SCochrum, RIV CLong, RIV


RidsNrrDss RidsOgcMailCenter RidsNrrAdes
Wolf Creek Generating Station cc:
Jay Silberg, Esq.                        Supervisor Licensing Pillsbury Winthrop Shaw Pittman, LLP    Wolf Creek Nuclear Operating Corporation 2300 N Street, NW                        P.O. Box 411 Washington, DC 20037                    Burlington, KS 66839 Regional Administrator, Region IV        U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission      Resident Inspectors Office/Callaway Plant 611 Ryan Plaza Drive, Suite 400          8201 NRC Road Arlington, TX 76011-7005                Steedman, MO 65077-1032 Senior Resident Inspector                Kevin J. Moles, Manager U.S. Nuclear Regulatory Commission      Regulatory Affairs P.O. Box 311                            Wolf Creek Nuclear Operating Corporation Burlington, KS 66839                    P.O. Box 411 Burlington, KS 66839 Chief Engineer, Utilities Division Kansas Corporation Commission            Lorrie I. Bell, Project Manager 1500 SW Arrowhead Road                  Wolf Creek Nuclear Operating Corporation Topeka, KS 66604-4027                    P.O. Box 411 Burlington, KS 66839 Office of the Governor State of Kansas                          Ms. Julie Keys Topeka, KS 66612                        Nuclear Energy Institute 1776 I Street, NW, Suite 400 Attorney General                        Washington, DC 20006-3708 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


-------------
TELEPHONE CONFERENCE CALL WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS AUGUST 17, 2007 PARTICIPANTS                AFFILIATIONS Verónica M. Rodríguez      U.S. Nuclear Regulatory Commission (NRC)
VRodriguez
William Koo                NRC Charles Medenciy            Wolf Creek Nuclear Operating Corporation (WCNOC)
Donald Naylor              WCNOC Eric Blocher                Strategic Teaming and Resource Sharing Alliance (STARS)
Paul Crawley                STARS Enclosure 1


CJacobs JDonohew GPick, RIV SCochrum, RIV CLong, RIV Wolf Creek Generating Station cc:Jay Silberg, Esq.Pillsbury Winthrop Shaw Pittman, LLP 2300 N Street, NW Washington, DC  20037Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX  76011-7005Senior Resident InspectorU.S. Nuclear Regulatory Commission P.O. Box 311 Burlington, KS  66839Chief Engineer, Utilities DivisionKansas Corporation Commission 1500 SW Arrowhead Road Topeka, KS  66604-4027Office of the GovernorState of Kansas Topeka, KS  66612Attorney General120 S.W. 10 th Avenue, 2 nd FloorTopeka, KS  66612-1597County ClerkCoffey County Courthouse 110 South 6 th StreetBurlington, KS  66839Thomas A. Conley, Section ChiefRadiation and Asbestos Control Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS  66612-1366Vice President Operations/Plant ManagerWolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS  66839Supervisor LicensingWolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS  66839U.S. Nuclear Regulatory CommissionResident Inspectors Office/Callaway Plant
REQUESTS FOR ADDITIONAL INFORMATION WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION AUGUST 17, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf Creek Nuclear Operating Corporation held a telephone conference call on August 17, 2007, as a followup discussion and request for clarification to the applicants response to the following requests for additional information (RAIs) concerning the Wolf Creek Generating Station (WCGS), Unit 1, license renewal application (LRA). The applicants response to these RAIs was submitted by letter dated July 26, 2007.
RAI B.2.1.34-1 The Nickel Alloy Aging Management Program (AMP) was submitted prior to the performance of pre-mitigation weld inspections for the application of weld overlays on pressurizer connections with dissimilar metal butt welds at WCGS. The pre-mitigation inspection performed in 2006 identified extensive circumferential cracking at three dissimilar metals welds associated with surge, relief, and safety nozzles. The staff requests that the applicant revise this AMP to incorporate information pertaining to the dissimilar metals butt weld inspection activities and findings. The revised AMP should: (1) discuss program enhancements incorporated as a result of the inspections, (2) provide information regarding the mitigation and preventive actions, taken or planned, to reduce the susceptibility of Alloy 600/82/182 components to primary water stress corrosion cracking (PWSCC), (3) discuss the inspection frequency and method of inspection of components susceptible to PWSCC covered under the scope of this program, and (4) provide justification that the AMP will provide reasonable assurance that PWSCC will be detected on a timely manner.
In addition, the staff requests that the applicant update the AMP Updated Safety Analysis Report (USAR) supplement to reflect all changes made to the program.
Discussion: Based on the discussion with the applicant, the staff indicated that the response to this RAI requires clarification. The staff requested that the applicant address the following:
(1)      The staff indicated that the applicants response did not address the steam generator primary nozzle and safe ends. The staff requested that the applicant address this Aging Management Review (AMR) line item.
The applicant indicated that the steam generator primary nozzle and safe ends AMR line items will be modified to provide a clarification.
(2)      The staff requested that the applicant clarify if WCGS has Alloy 600 components in the instrumentation nozzles.
The applicant indicated that WCGS only has Alloy 600 in the control rod drive mechanism. The applicant indicated that a footnote will be added to the RAI response to provide a clarification.
Enclosure 2


8201 NRC Road Steedman, MO  65077-1032Kevin J. Moles, ManagerRegulatory Affairs Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS  66839Lorrie I. Bell, Project ManagerWolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS  66839Ms. Julie KeysNuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC  20006-3708  Enclosure 1TELEPHONE CONFERENCE CALLWOLF CREEK GENERATING STATION, UNIT 1LICENSE RENEWAL APPLICATIONLIST OF PARTICIPANTSAUGUST 17, 2007PARTICIPANTSAFFILIATIONSVerónica M. RodríguezU.S. Nuclear Regulatory Commission (NRC)William KooNRC Charles MedenciyWolf Creek Nuclear Operating Corporation (WCNOC)Donald NaylorWCNOC Eric BlocherStrategic Teaming and Resource Sharing Alliance (STARS)Paul CrawleySTARS  REQUESTS FOR ADDITIONAL INFORMATIONWOLF CREEK GENERATING STATION, UNIT 1LICENSE RENEWAL APPLICATIONAUGUST 17, 2007The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf CreekNuclear Operating Corporation held a telephone conference call on August 17, 2007, as a followup discussion and request for clarification to the applicant's response to the following requests for additional information (RAIs) concerning the Wolf Creek Generating Station (WCGS), Unit 1, license renewal application (LRA). The applicant's response to these RAIswas submitted by letter dated July 26, 2007. RAI B.2.1.34-1 The Nickel Alloy Aging Management Program (AMP) was submitted prior to the performance ofpre-mitigation weld inspections for the application of weld overlays on pressurizer connections with dissimilar metal butt welds at WCGS. The pre-mitigation inspection performed in 2006 identified extensive circumferential cracking at three dissimilar metals welds associated with surge, relief, and safety nozzles. The staff requests that the applicant revise this AMP to incorporate information pertaining to the dissimilar metals butt weld inspection activities and findings. The revised AMP should:  (1) discuss program enhancements incorporated as a result of the inspections, (2) provide information regarding the mitigation and preventive actions, taken or planned, to reduce the susceptibility of Alloy 600/82/182 components to primary water stress corrosion cracking (PWSCC), (3) discuss the inspection frequency and method of inspection of components susceptible to PWSCC covered under the scope of this program, and (4) provide justification that the AMP will provide reasonable assurance that PWSCC will be detected on a timely manner.In addition, the staff requests that the applicant update the AMP Updated Safety AnalysisReport (USAR) supplement to reflect all changes made to the program. Discussion:  Based on the discussion with the applicant, the staff indicated that the responseto this RAI requires clarification. The staff requested that the applicant address the following: (1) The staff indicated that the applicant's response did not address the steam generatorprimary nozzle and safe ends. The staff requested that the applicant address this Aging Management Review (AMR) line item. The applicant indicated that the steam generator primary nozzle and safe ends AMR lineitems will be modified to provide a clarification.(2)  The staff requested that the applicant clarify if WCGS has Alloy 600 components in theinstrumentation nozzles. The applicant indicated that WCGS only has Alloy 600 in the control rod drivemechanism. The applicant indicated that a footnote will be added to the RAI response to provide a clarification.  (3) The staff requested that the applicant clarify the term "generator maintenance" providedin the table for this RAI response. The applicant indicated that WCGS performs generator maintenance every refuelingoutage. The applicant indicated that a footnote will be added to the RAI response to provide a clarification and details about the generator maintenance frequency.(4)The staff indicated that the applicant's response did not include the USAR supplementfor the Nickel Alloy AMP as requested in the RAI. The staff clarified that the USAR supplement should make reference to the AMP commitment (Commitment No. 30). In addition, the staff indicated that Commitment No. 30 should be supplemented to reflect the same language established in the commitment for pressure boundary nickel alloy components (Commitment No. 19).}}
(3) The staff requested that the applicant clarify the term generator maintenance provided in the table for this RAI response.
The applicant indicated that WCGS performs generator maintenance every refueling outage. The applicant indicated that a footnote will be added to the RAI response to provide a clarification and details about the generator maintenance frequency.
(4) The staff indicated that the applicants response did not include the USAR supplement for the Nickel Alloy AMP as requested in the RAI. The staff clarified that the USAR supplement should make reference to the AMP commitment (Commitment No. 30). In addition, the staff indicated that Commitment No. 30 should be supplemented to reflect the same language established in the commitment for pressure boundary nickel alloy components (Commitment No. 19).
                                              }}

Revision as of 04:23, 23 November 2019

Summary of Telephone Conference Call Held on August 17, 2007, Between the U.S. Nuclear Regulatory Commission and Wolf Creek Nuclear Operating Corp., Concerning Requests for Additional Information Pertaining to the Wolf Creek Generating Stat
ML072320452
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 08/28/2007
From: Veronica Rodriguez
NRC/NRR/ADRO/DLR/RLRB
To:
Wolf Creek
Rodriguez V NRR/DLR/RLRB 415-3703
References
Download: ML072320452 (7)


Text

August 28, 2007 LICENSEE: Wolf Creek Nuclear Operating Corporation FACILITY: Wolf Creek Generating Station, Unit 1

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 17, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION 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 held a telephone conference call on August 17, 2007, to discuss and clarify the staffs requests for additional information (RAIs) concerning the Wolf Creek Generating Station, Unit 1, license renewal application. The telephone conference call was useful in clarifying the intent of the staffs RAIs. provides a listing of the participants and Enclosure 2 contains a listing of the RAIs discussed with the applicant, including a brief description on the status of the items.

The applicant had an opportunity to comment on this summary. A mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3703 or e-mail vmr1@nrc.gov.

/RA/

Verónica M. Rodríguez, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-482

Enclosures:

1. List of Participants
2. List of Requests for Additional Information cc w/encls: See next page

ML072320452 OFFICE LA:DLR PM:RLRB:DLR BC:RLRB:DLR NAME YEdmonds VRodríguez RAuluck DATE 08/24/07 08/27/07 08/28/07

Letter to Wolf Creek Nuclear Operating Corp From V. Rodriguez Dated August 28, 2007

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON AUGUST 17, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION DISTRIBUTION:

HARD COPY:

DLR RF E-MAIL:

PUBLIC SSmith (srs3)

SDuraiswamy RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDci RidsNrrDra RidsNrrDe RidsNrrDeEemb RidsNrrDeEeeb RidsNrrDss RidsOgcMailCenter RidsNrrAdes


VRodriguez CJacobs JDonohew GPick, RIV SCochrum, RIV CLong, RIV

Wolf Creek Generating Station cc:

Jay Silberg, Esq. Supervisor Licensing Pillsbury Winthrop Shaw Pittman, LLP Wolf Creek Nuclear Operating Corporation 2300 N Street, NW P.O. Box 411 Washington, DC 20037 Burlington, KS 66839 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident Inspectors Office/Callaway Plant 611 Ryan Plaza Drive, Suite 400 8201 NRC Road Arlington, TX 76011-7005 Steedman, MO 65077-1032 Senior Resident Inspector Kevin J. Moles, Manager U.S. Nuclear Regulatory Commission Regulatory Affairs P.O. Box 311 Wolf Creek Nuclear Operating Corporation Burlington, KS 66839 P.O. Box 411 Burlington, KS 66839 Chief Engineer, Utilities Division Kansas Corporation Commission Lorrie I. Bell, Project Manager 1500 SW Arrowhead Road Wolf Creek Nuclear Operating Corporation Topeka, KS 66604-4027 P.O. Box 411 Burlington, KS 66839 Office of the Governor State of Kansas Ms. Julie Keys Topeka, KS 66612 Nuclear Energy Institute 1776 I Street, NW, Suite 400 Attorney General Washington, DC 20006-3708 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

TELEPHONE CONFERENCE CALL WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS AUGUST 17, 2007 PARTICIPANTS AFFILIATIONS Verónica M. Rodríguez U.S. Nuclear Regulatory Commission (NRC)

William Koo NRC Charles Medenciy Wolf Creek Nuclear Operating Corporation (WCNOC)

Donald Naylor WCNOC Eric Blocher Strategic Teaming and Resource Sharing Alliance (STARS)

Paul Crawley STARS Enclosure 1

REQUESTS FOR ADDITIONAL INFORMATION WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION AUGUST 17, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf Creek Nuclear Operating Corporation held a telephone conference call on August 17, 2007, as a followup discussion and request for clarification to the applicants response to the following requests for additional information (RAIs) concerning the Wolf Creek Generating Station (WCGS), Unit 1, license renewal application (LRA). The applicants response to these RAIs was submitted by letter dated July 26, 2007.

RAI B.2.1.34-1 The Nickel Alloy Aging Management Program (AMP) was submitted prior to the performance of pre-mitigation weld inspections for the application of weld overlays on pressurizer connections with dissimilar metal butt welds at WCGS. The pre-mitigation inspection performed in 2006 identified extensive circumferential cracking at three dissimilar metals welds associated with surge, relief, and safety nozzles. The staff requests that the applicant revise this AMP to incorporate information pertaining to the dissimilar metals butt weld inspection activities and findings. The revised AMP should: (1) discuss program enhancements incorporated as a result of the inspections, (2) provide information regarding the mitigation and preventive actions, taken or planned, to reduce the susceptibility of Alloy 600/82/182 components to primary water stress corrosion cracking (PWSCC), (3) discuss the inspection frequency and method of inspection of components susceptible to PWSCC covered under the scope of this program, and (4) provide justification that the AMP will provide reasonable assurance that PWSCC will be detected on a timely manner.

In addition, the staff requests that the applicant update the AMP Updated Safety Analysis Report (USAR) supplement to reflect all changes made to the program.

Discussion: Based on the discussion with the applicant, the staff indicated that the response to this RAI requires clarification. The staff requested that the applicant address the following:

(1) The staff indicated that the applicants response did not address the steam generator primary nozzle and safe ends. The staff requested that the applicant address this Aging Management Review (AMR) line item.

The applicant indicated that the steam generator primary nozzle and safe ends AMR line items will be modified to provide a clarification.

(2) The staff requested that the applicant clarify if WCGS has Alloy 600 components in the instrumentation nozzles.

The applicant indicated that WCGS only has Alloy 600 in the control rod drive mechanism. The applicant indicated that a footnote will be added to the RAI response to provide a clarification.

Enclosure 2

(3) The staff requested that the applicant clarify the term generator maintenance provided in the table for this RAI response.

The applicant indicated that WCGS performs generator maintenance every refueling outage. The applicant indicated that a footnote will be added to the RAI response to provide a clarification and details about the generator maintenance frequency.

(4) The staff indicated that the applicants response did not include the USAR supplement for the Nickel Alloy AMP as requested in the RAI. The staff clarified that the USAR supplement should make reference to the AMP commitment (Commitment No. 30). In addition, the staff indicated that Commitment No. 30 should be supplemented to reflect the same language established in the commitment for pressure boundary nickel alloy components (Commitment No. 19).