Letter Sequence RAI |
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TAC:MF2574, Clarify Application of Setpoint Methodology for LSSS Functions (Withdrawn, Closed) |
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MONTHYEARML13247A0802013-08-13013 August 2013 Full Scope Implementation of the Alternative Source Term Project stage: Request ML13247A0782013-08-31031 August 2013 WCAP-17746-NP, Rev. 0 Westinghouse Setpoint Methodology as Applied to the Wolf Creek Generating Station Project stage: Request ML13247A0792013-08-31031 August 2013 WCAP-17602-NP, Rev. 0, Westinghouse Setpoint Calculations for the Wolf Creek Generating Station Control, Protection, and Indication Systems Project stage: Request ML13345B3352013-12-13013 December 2013 Request for Additional Information, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternative Source Term Project stage: RAI ML13357A2502013-12-23023 December 2013 NRR E-mail Capture - FW: Wolf Creek Generating Station - Request for Additional Information Transition to Westinghouse Core Design and Safety Analysis Project stage: RAI ML13357A2522013-12-23023 December 2013 NRR E-mail Capture - Wolf Creek Generating Station - Request for Additional Information Transition to Westinghouse Core Design and Safety Analysis Project stage: RAI ET 14-0003, Operating Corporation - Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2014-01-28028 January 2014 Operating Corporation - Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis Project stage: Response to RAI ML14028A1702014-01-28028 January 2014 NRR E-mail Capture - Acceptance Review Project stage: Acceptance Review ML14027A1622014-01-28028 January 2014 Redacted, Request for Additional Information, Round 2, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term Project stage: RAI ET 14-0009, Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2014-02-25025 February 2014 Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis Project stage: Response to RAI ML14058A0882014-03-0505 March 2014 Request for Additional Information, Nrr/De/Eeeb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term Project stage: RAI ML14056A1162014-03-0505 March 2014 Request for Withholding Information from Public Disclosure - 8/9/2013 Affidavit Executed by J. Gresham, Westinghouse WCAP-17446-P, Revision 0, and WCAP-17602, Revision 0 Project stage: Withholding Request Acceptance ML14070A0622014-03-14014 March 2014 Request for Withholding Information from Public Disclosure - 2/14/14 Affidavit Executed by J. Gresham, Westinghouse SAP-14-27-P Attachment Project stage: Withholding Request Acceptance WO 14-0031, Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2014-03-20020 March 2014 Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis Project stage: Response to RAI WO 14-0032, Supplemental Information for Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2014-03-26026 March 2014 Supplemental Information for Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis Project stage: Supplement ML14083A4002014-04-0303 April 2014 Request for Additional Information, Nrr/Dra/Arcb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term Project stage: RAI ML14111A1002014-04-30030 April 2014 Request for Additional Information, Nrr/Dss/Srxb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term Project stage: RAI WO 14-0043, Supplemental Information in Support of the License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis Methodologies2014-05-13013 May 2014 Supplemental Information in Support of the License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis Methodologies Project stage: Supplement ET 14-0017, Withdrawal of License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis2014-06-18018 June 2014 Withdrawal of License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis Project stage: Withdrawal ML14176A5052014-06-25025 June 2014 Letter, Withdrawal of License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term Project stage: Withdrawal ML14176A5202014-06-25025 June 2014 FRN, Withdrawal of License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term Project stage: Withdrawal NRC-2014-0054, FRN, Withdrawal of License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term2014-06-25025 June 2014 FRN, Withdrawal of License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term Project stage: Withdrawal 2014-03-20
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Category:E-Mail
MONTHYEARML23360A1562023-12-26026 December 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request to Revise the Ventilation Filter Testing Program in Technical Specifications ML23166A0622023-06-15015 June 2023 NRR E-mail Capture - Acceptance Review - Wolf Creek Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded post-tensioning System Components ML23090A1042023-03-31031 March 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ML23090A0072023-03-31031 March 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request for Relief for Follow-Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Peened Surface ML23080A0652023-03-21021 March 2023 NRR E-mail Capture - Wolf Creek Generating Station Evacuation Time Estimate Analysis Review ML23026A0222023-01-25025 January 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements ML23009A4082023-01-0909 January 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request to Revise TS to Adopt Technical Specification Task Force (TSTF)-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22361A0052022-12-27027 December 2022 NRR E-mail Capture - Request for Additional Information Wolf Creek Request for Deviation from Fire Protection Program Requirements ML22321A2662022-11-16016 November 2022 January 2023 Emergency Preparedness Program Inspection - Request for Information ML22307A1372022-11-0202 November 2022 August 2022 Emergency Preparedness Exercise Inspection Unresolved Item - Request for Information ML22251A1312022-09-0808 September 2022 NRR E-mail Capture - Acceptance Review - Wolf Creek Request for Deviation from Fire Protection Program Requirements to Allow Use of Portable Lighting ML22215A2742022-08-0202 August 2022 Inservice Inspection Request for Information ML22208A1322022-07-27027 July 2022 NRR E-mail Capture - Wolf Creek Table of Contents LAR ML22166A3222022-06-14014 June 2022 August 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22131A0522022-05-11011 May 2022 NRR E-mail Capture - Draft Supplemental Information Needed for Acceptance - Wolf Creek Inservice Inspection Relief Request for Reactor Pressure Vessel Head Penetration Nozzles with Peened Surface ML22055A1142022-02-23023 February 2022 NRR E-mail Capture - Request for Additional Information - Wolf Creek Request to Revise Diesel Generator Completion Time ML22045A4512022-02-14014 February 2022 NRR E-mail Capture - Request for Additional Information - Wolf Creek Steam Generator Inspection Report 24th Refueling ML22026A4392022-01-26026 January 2022 NRR E-mail Capture - Wolf Creek Acceptance Review Results - Removal of TS Table of Contents (L-2022-LLA-0008) ML22025A3612022-01-21021 January 2022 PI&R RFI Final ML21327A2602021-11-23023 November 2021 NRR E-mail Capture - Request for Additional Information - Wolf Creek Revision of Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21309A0332021-11-0505 November 2021 NRR E-mail Capture - Acceptance Review - Wolf Creek Revision of Technical Specification 3.8.1, AC Sources - Operating ML21307A4202021-11-0303 November 2021 NRR E-mail Capture - Acceptance Review - Wolf Creek Revision of Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21271A1952021-09-28028 September 2021 E-mail 9-28-21 RFI for Wc EP Inspection Nov 2021 ML21259A0652021-09-16016 September 2021 NRR E-mail Capture - Draft Supplemental Information Needed for Acceptance - Wolf Creek License Amendment and Exemption Requests Regarding GSI-191 (EPIDs L-2021-LLA-0152 and L-2021-LLE-0039) ML21221A1282021-08-0505 August 2021 NRR E-mail Capture - Urgent: Draft Request for Additional Information - Wolf Creek one-time Request for Exemption from the Biennial Emergency Preparedness Exercise ML21189A0252021-07-0101 July 2021 NRR E-mail Capture - Acceptance Review - Wolf Creek Request Revision to the Emergency Plan Related to on-shift Staffing ML21230A3922021-05-19019 May 2021 May 19, 2021 Dricks Response to Gurdziel Letter Dated May 13, 2021 - August 17, 2021 ML21102A3342021-04-12012 April 2021 Email 4-12-21 RFI for In-Office Rvw of Recent RERP and a Related EPIP Change ML21064A0342021-03-0404 March 2021 NRR E-mail Capture - Wolf Creek Generating Station Upcoming Steam Generator Tube Inservice Inspection ML20353A2712020-12-18018 December 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange ML20349A3092020-12-14014 December 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek License Amendment Request for Change to Owner Licensee Names ML20297A3022020-10-22022 October 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML20262A7512020-09-17017 September 2020 NRR E-mail Capture - Requests for Additional Information: Wolf Creek Amendment Request to Modify Technical Specification Surveillance Frequency Consistent with TSTF-425 ML20191A0222020-07-0606 July 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Request in Support of Replacement Engineered Safety Features Transformers with Load Tap Changers ML20162A1642020-06-0909 June 2020 Email June 9, 2020 - RFI in Preparation for Wolf Creek EP Program Inspection ML20149K4272020-05-22022 May 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek License Amendment Request Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) ML20133J8972020-05-12012 May 2020 12 May 2020 E-mail - RFI for NRC In-Office Inspection of Recent Wcngs Eplan_Eal Changes ML20132A3442020-05-11011 May 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Generating Station License Amendment Request to Revise Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML20009E4802020-01-0909 January 2020 Relief Request to Utilize Code Case N-666-1 for Wolf Creek Generating Station - Request for Additional Information ML19273A0232019-09-30030 September 2019 NRR E-mail Capture - Acceptance Review - License Amendment Request to Revise Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System, ML19268B7172019-09-25025 September 2019 NRR E-mail Capture - Acceptance Review - Inservice Inspection (ISI) Program Relief Request to Use Code Case N-666-1 ML19261A2272019-09-18018 September 2019 NRR E-mail Capture - Regulatory Audit Plan - Wolf Creek Generating Station License Amendment Request to Revise Technical Specification 3.3.5 ML19255H3032019-09-12012 September 2019 NRR E-mail Capture - Acceptance Review - Relief Request I4R-07 to Utilize Code Case N-513-4 ML19224A5242019-08-12012 August 2019 NRR E-mail Capture - Request for Additional Information - License Amendment Request to Revise Wolf Creek Generating Station Technical Specification 3.3.5 ML19274D2752019-07-31031 July 2019 Request for Information-IR 05000482 2019-004, Dated 7/31/2019 ML19203A2362019-07-19019 July 2019 LTR-19-0291 Tom Gurdziel, E-mail July 18, 2019, Confirmatory Order on Wolf Creek ML19112A1772019-04-22022 April 2019 NRR E-mail Capture - Acceptance Review - License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ML19091A0362019-03-29029 March 2019 NRR E-mail Capture - Acceptance Review - License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange ML19065A0982019-03-0606 March 2019 NRR E-mail Capture - Acceptance Review - Wolf Creek License Amendment Request for Revision to Technical Specifications to Adopt TSTF-529 ML19036A6832019-02-0505 February 2019 LTR-18-0498 - Email Response - Sheryl Sweet, Licensing Engineer, Wolf Creek Nuclear, E-mail Acronyms for NRC Personnel 2023-06-15
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Text
1 NRR-PMDAPEm Resource From: Lyon, Fred Sent: Monday, December 23, 2013 11:05 AM To: Wideman Steve G Cc: Muilenburg William T; Fici Melanie R; Blair Jeff T
Subject:
RE: Wolf Creek Generating Station - Request fo r Additional Information Re: Transition to Westinghouse Core Design and Safety Analysis (TAC No. MF2574)That works for us. Replace the original ESGB-RAI-1 and -2 with the question below, and call it ESGB-RAI-1. Thanks, Fred From: Wideman Steve G [1]
Sent: Monday, December 23, 2013 9:57 AM To: Lyon, Fred Cc: Muilenburg William T; Fici Melanie R; Blair Jeff T
Subject:
RE: Wolf Creek Generating Station - Request for Additional Information Re: Transition to Westinghouse Core Design and Safety Analysis (TAC No. MF2574)
Fred - in looking at revised ESGB-RAI-2, it really appears to be essentially the same as ESGB-RAI-1 with the exception of describing the analysis methodology. It would appear to me that the revised ESGB-RAI-2 should replace the original ESGB-RAI-1 and ESGB-RAI-2.
Steve ESGB-RAI-1
Please identify all sources of post-loss-of-coolant accident (LOCA) strong acid generation in containment and time dependent values of strong acid concentrations in the sump for a period of 30 days post-LOCA.
ESGB-RAI-2 Please describe the ORIGEN-S computer code used to determine the pH in the sump water post-LOCA and the differences between it and ORIGEN-2/ARP. Please provide the input and output data of the program.
Describe the analysis methodology used to determine the pH in the sump water during the period of 30 days post-LOCA. Include detailed calculations of time dependent pH values in the sump during a 30 day period post-LOCA to demonstrate that the pH remains basic throughout this time period.
From: Lyon, Fred [mailto:Fred.Lyon@nrc.gov
] Sent: Monday, December 23, 2013 8:39 AM To: Wideman Steve G Cc: Muilenburg William T
Subject:
FW: Wolf Creek Generating Station - Request for Additional Information Re: Transition to Westinghouse Core Design and Safety Analysis (TAC No. MF2574)
Steve, you were right. Please see the revised question below, and replace ESGB-RAI-2 in my RAI letter. You can reference this email in your response. Thanks, Fred
From: Obodoako, Aloysius Sent: Monday, December 23, 2013 9:31 AM 2 To: Lyon, Fred
Subject:
RE: Wolf Creek Generating Station - Request for Additional Information Re: Transition to Westinghouse Core Design and Safety Analysis (TAC No. MF2574)
Hi Fred, I reviewed the RAI and draft licensee response and it answers my question. I think I must have confused the reactor vessel environment and the post-LOCA sump analyses. The intent of ESGB-RAI-2 was to request for the following information:
Describe the analysis methodology used to determine the pH in the sump water during the period of 30 days post-LOCA. Include detailed calculations of time dependent pH values in the sump during a 30 day period post-LOCA to demonstrate that the pH remains basic throughout this time period.
How do you propose we move forward. Should I draw up another RAI, which we will issue formally to gather this information or can we modify ESGB-RAI-2 such that it reflects the above request?
Aloysius From: Lyon, Fred Sent: Friday, December 20, 2013 8:03 AM To: Obodoako, Aloysius Cc: Kulesa, Gloria
Subject:
FW: Wolf Creek Generating Station - Request for Additional Information Re: Transition to Westinghouse Core Design and Safety Analysis (TAC No. MF2574)
Please see the proposed answer below to your RAI question. The licensee wants to make sure they understand what you're asking for and why. The question didn't seem to be logical since they didn't use a computer code to do the pH determination. Let me know if you need to chat with them.
Thanks, Fred (x2296)
From: Wideman Steve G [2]
Sent: Thursday, December 19, 2013 10:11 AM To: Lyon, Fred Cc: Fici Melanie R
Subject:
RE: Wolf Creek Generating Station - Request for Additional Information Re: Transition to Westinghouse Core Design and Safety Analysis (TAC No. MF2574)
Fred - per our discussion on December 18, 2013 regarding RAI ESGB-RAI-2, provided below is the draft response for your discussion with the technical branch.
ESGB-RAI-2: "Please describe the ORIGEN-S computer code used to determine the pH in the sump water post-LOCA and the differences between it and ORIGEN-2/ARP. Please provide the input and output data of the program."
DRAFT RESPONSE: In Enclosure VI of the LAR, Section 4.4.2.1 (page 4-105) it indicates that no computer codes were used in this analysis (referring to the containment sump pH analysis). This section specifically states:
"No computer codes were used in this analysis. To determine the pH in the CLB analysis, NaOH and H3BO3 molarities were first calculated and then used with Oak Ridge National Laboratory (ORNL) titration curve data to determine the pH of the spray and sump solutions during the injection and recirculation phases of ECCS
operation."
3The information provided in Section 4.4.2.1 is similar to a V. C. Summer Nuclear Station letter submitted on June 15, 2009 (ADAMS Accession Number ML091680063) in response to a similar RAI question.
Steve Wideman WCNOC Licensing 620-364-4037 Cell - 620-490-0449
From: Lyon, Fred [mailto:Fred.Lyon@nrc.gov
] Sent: Monday, December 16, 2013 2:46 PM To: Wideman Steve G Cc: Muilenburg William T
Subject:
FW: Wolf Creek Generating Station - Request for Additional Information Re: Transition to Westinghouse Core Design and Safety Analysis (TAC No. MF2574)
From: nrc_mail_1-2 Resource [mailto:nrc_mail_1-2.Resource@nrc.gov
] Sent: Monday, December 16, 2013 10:46 AM To: Lyon, Fred
Subject:
Wolf Creek Generating Station - Request for Additional Information Re: Transition to Westin ghouse Core Desi g n and Safety Analysis (TAC No. MF2574)
Wolf Creek Generating Station - Request for Additional Information Re: Transition to Westinghouse Core Design and Safety Analysis (TAC No. MF2574)
ADAMS Accession No.: ML13345B335
--- The attached document is being sent to you per your request to receive electronic mailings, if you wish to be removed follow the instructions below. The document is publicly available and will be accessible via the public web site Electronic Reading Room in the Agency Document Access and Management System (ADAMS),
http://www.nrc.gov/reading-rm/adams.html , generally within six days. To access this document use the ADAMS number provided in this email. Documents containing proprietary or safeguards information are not publicly available and will not be sent using the electronic mailing system. You are currently subscribed to wolfcreek as:
Fred.Lyon@nrc.gov . To unsubscribe: Please go to the NRC's public website http://www.nrc.gov/public-involve/listserver/plants-by-region.html Once at the site, type in your e-mail address in the space provided and check the box(es) that correspond to the list(s) you would like to unsubscribe from.
Then click the Un subscribe button.
4 or send an email to lyris@nrc.gov with the following information in the subject line unsubscribe wolfcreek Fred.Lyon@nrc.gov
Hearing Identifier: NRR_PMDA Email Number: 969 Mail Envelope Properties (Fred.Lyon@nrc.gov20131223110400)
Subject:
RE: Wolf Creek Generating Station - Request for Additional Information Re: Transition to Westinghouse Core Design and Safety Analysis (TAC No. MF2574) Sent Date: 12/23/2013 11:04:43 AM Received Date: 12/23/2013 11:04:00 AM From: Lyon, Fred Created By: Fred.Lyon@nrc.gov Recipients: "Muilenburg William T" <wimuile@WCNOC.com> Tracking Status: None "Fici Melanie R" <mefici@WCNOC.com> Tracking Status: None "Blair Jeff T" <jeblair@WCNOC.com>
Tracking Status: None "Wideman Steve G" <stwidem@WCNOC.com> Tracking Status: None
Post Office: Files Size Date & Time MESSAGE 7290 12/23/2013 11:04:00 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: