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| | issue date = 11/19/2014 | | | issue date = 11/19/2014 |
| | title = Question on LAR to Add Astrum to COLR | | | title = Question on LAR to Add Astrum to COLR |
| | author name = Wideman S G | | | author name = Wideman S |
| | author affiliation = Wolf Creek Nuclear Operating Corp | | | author affiliation = Wolf Creek Nuclear Operating Corp |
| | addressee name = Lyon F E | | | addressee name = Lyon F |
| | addressee affiliation = NRC/NRR/DORL/LPLIV-1 | | | addressee affiliation = NRC/NRR/DORL/LPLIV-1 |
| | docket = 05000482 | | | docket = 05000482 |
Letter Sequence Other |
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MONTHYEARML14064A3292014-02-26026 February 2014 NP-Attachment to LTR-LIS-13-557, Rev 0, Application of Westinghouse Best-Estimate Large Break LOCA Methodology to the Wolf Creek Generating Station Project stage: Request ET 14-0008, Application for Amendment to Revise Specification 5.6.5, Core Operating Limits Report (Colr), for Large Break Loss-of-Coolant Accident Analysis Methodology2014-02-26026 February 2014 Application for Amendment to Revise Specification 5.6.5, Core Operating Limits Report (Colr), for Large Break Loss-of-Coolant Accident Analysis Methodology Project stage: Request ML14120A0202014-04-30030 April 2014 NRR E-mail Capture - Acceptance Review Project stage: Acceptance Review ML14182A3762014-07-14014 July 2014 Request for Withholding from Public Disclosure - 1/21/14 Affidavit Executed by J. Gresham, Westinghouse LTR-LIS-13-557P-Attachment, Revision 0 Provided as Enclosure 1 to 2/26/14 License Amendment Request Project stage: Other ML14324A0132014-11-19019 November 2014 NRR E-mail Capture - Question on LAR to Add Astrum to COLR Project stage: Other ML14324A8582014-11-20020 November 2014 NRR E-mail Capture - Question on LAR to Add Astrum to COLR (Wolf Creek TAC No. MF3518) Project stage: Other ET 14-0038, Supplemental Information Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology2014-12-0808 December 2014 Supplemental Information Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology Project stage: Supplement ET 15-0002, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology2015-01-21021 January 2015 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, for Large Break Loss-of-Coolant (LOCA) Analysis Methodology Project stage: Response to RAI ML15076A3132015-03-18018 March 2015 Request for Withholding Information from Public Disclosure - 1/15/2015 Affidavit Executed by J. Gresham, Westinghouse, Two Attachments to LTR-LIST-15-11, Revision 1 Project stage: Withholding Request Acceptance ML15091A3822015-03-20020 March 2015 Submission of 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes Project stage: Request WO 15-0044, Proposed License Condition Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology2015-07-15015 July 2015 Proposed License Condition Regarding License Amendment Request for Revision to Technical Specification 5.6.5 for Large Break Loss-of-Coolant Accident (LOCA) Analysis Methodology Project stage: Request ML15203A0052015-08-28028 August 2015 Redacted, Issuance of Amendment No. 213, Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large-Break Loss-of-Coolant Accident Analysis Methodology (Astrum) Project stage: Approval 2014-07-14
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Category:E-Mail
MONTHYEARML24296A0632024-10-22022 October 2024 NRR E-mail Capture - Acceptance Review Wolf Creek License Amendment and Exemption Requests for a risk-informed Resolution to GSI-191 ML24263A0832024-09-19019 September 2024 NRR E-mail Capture - Acceptance Review Wolf Creek Revision to Technical Specification to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions ML24250A0252024-09-0606 September 2024 NRR E-mail Capture - Acceptance Review Wolf Creek Revision to Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology) ML23360A1562023-12-26026 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 2024-09-06
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Text
1 NRR-PMDAPEm Resource From: Wideman Steve G [stwidem@WCNOC.com]
Sent: Wednesday, November 19, 2014 4:13 PM To: Lyon, Fred Cc: Muilenburg William T; Flannigan Richard D; Ketchum Bill H; Roland, Kevin
Subject:
RE: Question on LAR to add ASTRUM to COLR (TAC No. MF3518)Fred - In response to the teleconference held on November 10, 2014, WCNOC requests that the NRC continue with its review of our application as an interim solution to address the margin to the PCT limit. WCNOC will submit a schedule for performing a large break LOCA re-analysis that applies a NRC approved methodology, which includes the effects of fuel thermal conductivity degradation (TCD), within 6 months of NRC approval of WCAP-16996-P, Revision 0, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Size (FULL SPECTRUM LOCA Methodology)," and WCAP-17642-P, Revision 0, "Westinghouse Performance Analysis and Design Model (PAD5)."
WCAP-16996-P, Revision 0, was submitted to the NRC on November 23, 2010 by Westinghouse letter LTR-NRC-10-73. WCAP-17642-P, Revision 0, was submitted to the NRC on October 29, 2013 by Westinghouse letter LTR-NRC-13-72.
WCNOC will submit a formal letter documenting the regulatory commitment.
Steve Wideman Principal Licensing Engineer Wolf Creek Nuclear Operating Corp 620-364-4037 stwidem@wcnoc.com
From: Lyon, Fred [mailto:Fred.Lyon@nrc.gov
] Sent: Tuesday, October 28, 2014 1:46 PM To: Wideman Steve G Cc: Muilenburg William T
Subject:
RE: Question on LAR to add ASTRUM to COLR (TAC No. MF3518)
Steve, the reviewers would like to discuss options moving forward with the ASTRUM implementation.
There are basically 2 options: (a) adding license conditions to move to new methods (e.g., PAD5) when available, or (b) provide enough information to approve PAD4 as a plant-specific method.
Also, the reviewers need to know if there is there any relation between this amendment and the set-points amendment that was withdrawn (MF2574, Change to W Methodologies/AST).
They'd like to set up a phoncon for next Tuesday if possible. If not, please give me some other suggestions.
Thanks, Fred
From: Wideman Steve G [mailto:stwidem@WCNOC.com
] Sent: Wednesday, October 01, 2014 2:04 PM To: Lyon, Fred 2 Cc: Muilenburg William T; Koenig Steve R; Flannigan Richard D; Roland, Kevin
Subject:
RE: Question on LAR to add ASTRUM to COLR (TAC No. MF3518)
The current large break LOCA AOR (1981 BASH Code - WCAP-10266) results in a peak centerline temperature (PCT) of 2181 °F (increases to 2188 °F with the planned containment cooler modification) with the limit being 2200 °F. Given the minimal margin to the PCT limit, the decision was made to pursue WCGS specific approval of the LBLOCA analysis using the ASTRUM methodology in WCAP-16009-P-A. The initial LAR submitted on 11/4/10 was withdrawn on 8/23/12 when it was determined in discussions with the NRC staff that the LBLOCA analysis would require the incorporation of thermal conductivity degradation (TCD).
As you noted, WCAP-16996-P, "Realistic LOCA Evaluation Methodology Applied to the Full Spectrum of Break Size (FULL SPECTRUM LOCA Methodology," dated November 2010 is still under NRC review. Input from Westinghouse indicates that full resolution of TCD and 50.46c rulemaking is expected via FULL SPECTRUM TM LOCA and PAD5 on a timeframe consistent with the finalization of 50.46c.
Given the above minimal margin, WCNOC believed it prudent to update the best-estimate LBLOCA analysis and use PAD 4.0 + TCD (includes full runs of all 124 cases of first and second cycle fuel) and resubmit for NRC approval. This resubmittal was made with the knowledge that FULL SPECTRUM TM LOCA Evaluation Methodology was still under NRC review. The use of PAD 4.0 + TCD (full runs) is similar to the Watts Bar Unit 2 submittal currently under NRC review. The WCGS LBLOCA analysis is similar to the Turkey Point approved amendment that used PAD 4.0 + TCD for first cycle fuel with an evaluation that shows second cycle fuel is bounded by first cycle fuel.
From: Lyon, Fred [mailto:Fred.Lyon@nrc.gov
] Sent: Monday, September 29, 2014 10:07 AM To: Wideman Steve G Cc: Muilenburg William T
Subject:
Question on LAR to add ASTRUM to COLR (TAC No. MF3518)
What exactly are you all trying to accomplish with the LAR? The original application was withdrawn because NRC was not willing to approve implementation of a methodology known to contain an error (PAD 4 inputs to ASTRUM were non-conservative because PAD 4 does not account for TCD). What has changed? PAD 5, which explicitly accounts for TCD has still not been approved. The NRC approved some applications with conditions to convert to PAD 5 when it is approved, but those were for plants that already had ASTRUM, not for plants that didn't have it.
Hearing Identifier: NRR_PMDA Email Number: 1701 Mail Envelope Properties (3258E47FA4A47747BFA39985EE2B35413C2CC7)
Subject:
RE: Question on LAR to add ASTRUM to COLR (TAC No. MF3518) Sent Date: 11/19/2014 4:13:12 PM Received Date: 11/19/2014 4:28:31 PM From: Wideman Steve G Created By: stwidem@WCNOC.com Recipients: "Muilenburg William T" <wimuile@WCNOC.com>
Tracking Status: None "Flannigan Richard D" <riflann@WCNOC.com>
Tracking Status: None "Ketchum Bill H" <wiketch@WCNOC.com> Tracking Status: None "Roland, Kevin" <RolandK@westinghouse.com> Tracking Status: None "Lyon, Fred" <Fred.Lyon@nrc.gov>
Tracking Status: None Post Office: WC-E2010.wcnoc.com
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