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Category:Letter
MONTHYEARIR 05000482/20244202024-10-31031 October 2024 Security Baseline Inspection Report 05000482/2024420 05000482/LER-2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-10-22022 October 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing ML24296B1902024-10-22022 October 2024 10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program 05000482/LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-10-21021 October 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24283A0752024-10-0909 October 2024 Notification of Commercial Grade Dedication Inspection (05000482/2025012) and Request for Information ML24199A1712024-09-17017 September 2024 Issuance of Amendment No. 241 Revise Ventilation Filter Testing Program Criteria and Administrative Correction of Absorber in Technical Specification 5.5.11 ML24260A0712024-09-12012 September 2024 License Amendment Request for a Risk-Informed Resolution to GSI-191 IR 05000482/20240102024-09-10010 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000482/2024010 (Public) ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24248A2492024-09-0404 September 2024 Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 26 Owner’S Activity Report ML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML24241A2212024-08-29029 August 2024 Notice of Enforcement Discretion for Wolf Creek Generating Station ML24240A2642024-08-27027 August 2024 Corporation - Request for Notice of Enforcement Discretion Regarding Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24227A5562024-08-14014 August 2024 Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions ML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) IR 05000482/20240022024-07-18018 July 2024 Integrated Inspection Report 05000482/2024002 05000482/LER-2024-001, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-07-0202 July 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing IR 05000482/20244012024-07-0202 July 2024 Security Baseline Inspection Report 05000482/2024401 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24162A1632024-06-11011 June 2024 Operating Corporation – Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000482/2024010) ML24150A0562024-05-29029 May 2024 Foreign Ownership, Control or Influence (FOCI) Information – Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML23345A1602024-05-0909 May 2024 Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements ML24089A2622024-04-29029 April 2024 Financial Protection Levels ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report ML24113A1882024-04-19019 April 2024 Foreign Ownership, Control or Influence Information - Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24109A1212024-04-18018 April 2024 (WCGS) Form 5 Exposure Report for Calendar Year 2023 ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report IR 05000482/20240012024-04-17017 April 2024 Integrated Inspection Report 05000482/2024001 ML24114A1442024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37 ML24106A1482024-04-15015 April 2024 Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information ML24098A0052024-04-0707 April 2024 2023 Annual Environmental Operating Report ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24074A3312024-03-14014 March 2024 Missed Quarterly Inspection Per 40 CFR 266 Subpart N ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ML24068A1992024-03-0707 March 2024 Changes to Technical Specification Bases - Revisions 93 and 94 ML24066A0672024-03-0505 March 2024 4-2022-024 Letter - OI Closure to Licensee ML24061A2642024-03-0101 March 2024 Revision of Two Procedures That Implement the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) Commissioners ML24059A1702024-02-28028 February 2024 Annual Fitness for Duty Program Performance Report, and Annual Fatigue Report for 2023 IR 05000482/20230062024-02-28028 February 2024 Annual Assessment Letter for Wolf Creek Generating Station Report 05000482/2023006 ML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML24050A0012024-02-19019 February 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) 2024-09-06
[Table view] Category:Report
MONTHYEARML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23244A2142023-09-0101 September 2023 IAEA Osart Report ML23068A1962023-03-0909 March 2023 Biennial 50.59 Evaluation Report ML23135A2012022-12-0606 December 2022 EQSD-I, Rev 18, Equipment Qualification Design Basis Document ML23135A1932022-09-0101 September 2022 EQSD-II, Rev 34, Equipment Qualification Summary Document WO 22-0021, Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report2022-08-29029 August 2022 Technical Specification 5.6.8 - Post Accident Monitoring (PAM) Report ML22152A2042022-05-18018 May 2022 EQSD-I, Revision 16, Equipment Qualification Design Basis Document ML22152A1992022-05-18018 May 2022 EQSD-II, Revision 33, EQ Program Master List (Table 1) Plus Mild Environment SR Electrical Equipment List (Table 2) ML22152A1942022-05-18018 May 2022 EQSD-I, Revision 15, Equipment Qualification Design Basis Document ML23135A2072022-04-0606 April 2022 EQSD-I, Rev 17, Equipment Qualification Design Basis Document ML20290A6192020-07-23023 July 2020 Corrected Redacted Version of Rev. 33 to Updated Safety Analysis Report, EQSD-I, Rev. 14, Equipment Qualification Design Basis Document ML20182A4292020-06-30030 June 2020 Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating WO 20-0048, Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating2020-06-30030 June 2020 Request for Notice of Enforcement Discretion for Technical Specifications 3.8.1, AC Sources - Operating WO 20-0041, Rev. 32 to Equipment Qualification Summary Document-II (EQSD-II)2020-01-15015 January 2020 Rev. 32 to Equipment Qualification Summary Document-II (EQSD-II) ML19330F8632019-12-0606 December 2019 Regulatory Audit Summary Regarding License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation, ML19178A3392019-07-0909 July 2019 Staff Assessment of Aging Management Program and Inspection Plan of Reactor Vessel Internals ML19092A1562018-09-18018 September 2018 EQSD-I, Rev 14 ML18093B0112018-03-0808 March 2018 Revision 31 to Updated Safety Analysis Report, Equipment Classification Design Basis Document, EQSD-I Rev 13 ML18093B0132018-03-0808 March 2018 Revision 31 to Updated Safety Analysis Report, Equipment Qualification Summary Document, EQSD-II, Rev 30, Redacted WO 19-0010, EQSD-II, Rev 312018-02-19019 February 2018 EQSD-II, Rev 31 ML18023A1572018-01-18018 January 2018 Submittal of Blind Sample Error Investigation Report ML17241A2512017-11-0808 November 2017 Staff Assessment of Flooding Focused Evaluation ML17234A4002017-08-17017 August 2017 Summary of Changes to Three Forms That Implement Radiological Emergency Response Plan (RERP) ML17093A6652017-03-27027 March 2017 Report on Financial Protection Levels ML17151B0452017-03-0909 March 2017 Equipment Qualification Summary Document, Master List Section II, EQSD-II, Rev 28, Part 2 - Redacted ML17151B0442017-03-0202 March 2017 Equipment Qualification Summary Document, Master List Section II, EQSD-II, Rev 28, Part 1 ML17072A0512017-03-0202 March 2017 Biennial 50.59 Evaluation Report for 01/01/2015 - 12/31/2016 ML17151B0432017-01-26026 January 2017 Equipment Qualification Design Basis Document, EQSD-I, Rev 11 ML17054C2302017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - A-3788, Technical Report, Appendix a, Fission Product Removal Effectiveness of Chemical Additives in PWR Containment Sprays ET 17-0005, 16C4405-RPT-002, Revision 0, Seismic High Frequency Confirmation for WCGS2016-12-15015 December 2016 16C4405-RPT-002, Revision 0, Seismic High Frequency Confirmation for WCGS WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-I, Revision 9, Equipment Qualification Design Basis Document.2016-05-31031 May 2016 Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-I, Revision 9, Equipment Qualification Design Basis Document. ML16204A1802016-05-31031 May 2016 Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-I, Revision 9, Equipment Qualification Design Basis Document. WM 16-0008, Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-II, Revision 27 Redacted2016-05-31031 May 2016 Redacted Version of Revision 29 to Updated Safety Analysis Report, EQSD-II, Revision 27 Redacted ML15314A6572015-11-0404 November 2015 Submittal of 10 CFR 50.46 Thirty Day Report of Emergency Core Cooling System (ECCS) Model Changes ML17151B0392015-10-26026 October 2015 E-1F9915, Rev 8, Design Basis Document for Ofn RP-017, Control Room Evaluation ET 16-0003, Flood Hazard Reevaluation Report, Revision 12015-10-21021 October 2015 Flood Hazard Reevaluation Report, Revision 1 ML15216A3202015-08-12012 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights ML15075A0282015-03-0404 March 2015 Biennial 50.59 Evaluation Report ML15062A2752015-02-24024 February 2015 Pressure and Temperature Limits Report, Revision 2 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 WO 14-0095, Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-12-23023 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 ML14189A4982014-06-19019 June 2014 Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request 2024-09-04
[Table view] Category:Administrative
MONTHYEARML19178A3392019-07-0909 July 2019 Staff Assessment of Aging Management Program and Inspection Plan of Reactor Vessel Internals ML17241A2512017-11-0808 November 2017 Staff Assessment of Flooding Focused Evaluation ML17072A0512017-03-0202 March 2017 Biennial 50.59 Evaluation Report for 01/01/2015 - 12/31/2016 ET 06-0044, Operating Corporation'S Revised Commitment Regarding 10 CFR 50.55a Request I3R-052006-10-0202 October 2006 Operating Corporation'S Revised Commitment Regarding 10 CFR 50.55a Request I3R-05 ML0429500902004-09-29029 September 2004 Attachment I, Administrative Procedure AP 07B-003, Revision 5, Offsite Dose Calculation Manual. ML0429500942003-05-22022 May 2003 Attachment II, Administrative Procedure AP 07B-004, Revision 5, Offsite Dose Calculation Manual (Radiological Environmental Monitoring Program). ML0429500972002-03-0101 March 2002 Attachment III, Administrative Procedure AP 31A-100, Revision 4, Solid Radwaste Process Control Program. 2019-07-09
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W$LFCREEK -,NUCLEAR OPERATING CORPORATION March 2, 2017 Cynthia R. Hafenstine Manager Regulatory Affairs RA 17-0015 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Docket No. 50-482: Wolf Creek Generating Station Biennial 50.59 Evaluation Report Gentlemen:
This letter transmits the Biennial 50.59 Evaluation Report for Wolf Creek Generating Station (WCGS), which is being submitted pursuant to 10 CFR 50.59(d)(2). The attachment provides the WCGS Biennial 50.59 Evaluation Report including a summary of the evaluation results.
This r~port covers the period from January 1, 2015, to December 31, 2016, and contains a summary of 50.59 evaluations implemented during this period that were approved by the WCGS onsite review committee.
This letter contains no commitments. If you have any questions concerning this matter, please, I contact me at (620) 364-4204.
Sincerely,
~/.~
P' f,.,-
Cynthia R. Hafenstine CRH/rlt Attachment cc: K. M. Kennedy (NRC), w/a B. K. Singal (NRC), w/a N. H. Taylor (NRC), w/a Senior Resident Inspector (NRC), w/a P.O. Box 411 I Burlington, KS 66839 /Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET
'Attachment to RA 17-0015 Page 1 of 6 WOLF CREEK NUCLEAR OPERATING CORPORATION Wolf Creek Generating Station Docket No.: 50-482 Facility Operating License No.: NPF-42 BIENNIAL 50.59 EVALUATION REPORT Report No.: 25 Reporting Period: January 1, 2015 through December 31, 2016
Attachment RA 17-0015 Page 2 of 6
SUMMARY
This report provides a brief description of changes, test, and experiments implemented at Wolf Creek Generating Stc:ition (WCGS) and evaluated pursuant to 10 CFR 50.59(c)(1). This report includes summaries of the associated 50.59 evaluations that were reviewed and found to be acceptable by the Plant Safety Review Committee (PSRC) for the period beginning January 1, 2015 and ending December 31, 2016. This report is submitted in accordance with the requirements of 10 CFR 50:S9(d)(2).
On the basis of these evaluation of changes:
- There is less than a minimal increase in the frequency of occurrence of an accident
,, previously evaluated in the Updated Final Safety Analysis Report (USAR).
- There is less than a minimal increase in the likelihood of occurrence of a malfunction of a structure, system, or component (SSC) important to safety previously evaluated in the USAR.
- There is less than a minimal increase in the consequences of an accident previously evaluated in the USAR.
- There is less than a minimal increase in the consequences of a malfunction of an SSC important to safety previously evaluated in the USAR.
- There is no possibility for an accident of a different type than any previously evaluated in the USAR being created.
- There is no possibility for a malfunction of an SSC important to safety with a different result than any previously evaluated in the USAR being created.
- There is no result in a design basis limit for a fission product barrier as described in the USAR being exceeded or altered.
- There is no result in a departure from a method of evaluation described in the USAR used in establishing the design bases or in the safety analyses.
Therefore, all items. contained within this report have been determined not to require a license amendment.
i I
Attachment RA 17-0015 Page 3 of 6 Evaluation Number: 59 2015-0001 Revision: 0 Title: Review of Proposed Waverly Wind Farm Connection on LaCygne 345kV Line Activity
Description:
Westar Energy notified Wolf Creek Nuclear Operating Corporation (WCNOC) that the Southwest Power Pool has issued a directive to install a Wind Farm (approximately 200MW) that will be tied into the LaCygne 345kV Line approximately 5 miles from WCGS. The work will involve installation of the Waverly Switching Station that will split the LaCygne 345kV Line into two line segments, a WCGS to Waverly Switching Station 345kV Line and a Waverly Switching Station to LaCygne 345kV Line as well as add an approximate 5 miles of 345kV Transmission line from the Waverly Switching Station to the Waverly Collector Sub (tie in point for the Wind Farm). Additionally, instead of protection for a single line (Wolf Creek to LaCygne), the transmission line protection will now include separate protection for each of the two new line segments (WCGS to Waverly and Waverly to LaCygne). The configuration of the Waverly Switching Station will be a ring bus design. This evaluation does not include the impact of the additional 5 miles of 345kV Transmission line from the Waverly Switching Station to the Waverly Collector Sub or allowing the Wind Farm generation to be tied to the system because the design of the Wind Farm is still being developed and its impact will be reviewed on a separate 50.59 Evaluation. Until the separate 50.59 Evaluation is approved, Westar will keep the line switch located in the Waverly Switching Station for the 5 mile line to Waverly Collector Sub open so that it will be isolated and have no impact on the Westar power grid or to WCGS.
This evaluation will cover the Waverly Switching Station installation between WCGS and LaCygne near Waverly.
50.59 Evaluation:
The accidents listed in Chapter 15 were reviewed and it was determined that seven (7) accidents "Loss of External Electrical Load", "Turbine Trip", "Loss of Nonemergency AC Power to the Station Auxiliaries", "Loss of Normal Feedwater Flow", "Partial Loss of Forced Reactor Coolant Flow", "Complete Loss of Forced Reactor Coolant Flow", and "Anticipated Transients without Scram" were accidents where the loss of offsite power, loss of external load, and electrical grid disturbances were identified as contributing to the accident. The changes made to the LaCygne 345kV line for the Waverly Wind Farm will not alter the impact of the identified events. The impact of the changes is still bounded by the loss of the LaCygne 345kV Line and electrical disturbances on the LaCygne 345kV Line. On Question 1, there will be a small increase in the frequency of occurrence of the identified events that can contribute to an accident previously evaluated in the USAR due to the installation of the Waverly Switching Station. Since the Waverly Switching Station is being built in compliance with the USAR 8.2.1.3 identified design requirements, the increase in the frequency of occurrence is less than minimal. Additionally on Question 2, there will be a small increase in the likelihood of occurrence of a malfunction of the LaCygne 345kV Line, which is important to safety. However, the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the USAR is less than minimal because the Waverly Switching Station design is in compliance with the USAR 8.2.1.3 identified design requirements. On Questions 3 thru 7, there was no discernable impact that could be identified by the changes. Also, no new types of malfunction are introduced by the changes, since the new equipment is being built per the same design standards and requirements as the existing design and is being built in compliance with the USAR 8.2.1.3 identified design requirements.
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Attachment RA 17-0015 Page 4 of 6 Evaluation Number: 59 2015-0002 Revision: 0 Title: Review of Proposed Waverly Wind Farm Connection on LaCygne 345kV Line Activity
Description:
Westar Energy notified WCNOC that the Southwest Power Pool (SPP) has issued a directive to install a Wind Farm (approximately 200MW) that will be tied into the LaCygne 345kV Line approximately 5 miles from WCGS. The work will involve installation of the Waverly Switching Station that will split the LaCygne 345kV Line into two line segments, a WCGS to Waverly Switching Station 345kV Line and a Waverly Switching Station to LaCygne 345kV Line as well as adds approximately 5 miles of 345kV Generator Tie line from the Waverly Switching Station to the Waverly Collector Substation which is the tie in point for the Waverly Wind Farm which is also being added. The impact to WCGS for installing the Waverly Switching Station and splitting the LaCygne Line into two segments was determined on 50.59 Evaluation No. 2015-0001. This evaluation is for the impact of the new 5 mile 345kV Generator Tie line from the Waverly Switching Station to the Waverly Wind Farm Collector Substation and allowing the Wind Farm generation to be tied to the electric transmission system.
50.59 Evaluation:
The accidents listed in Chapter 15 were reviewed and it was determined that seven (7) accidents "Loss of External Electrical Load", "Turbine Trip", "Loss of Nonemergency AC Power to the Station Auxiliaries", "Loss of Normal Feedwater Flow", "Partial Loss of Forced Reactor Coolant Flow", "Complete Loss of Forced Reactor Coolant Flow, and "Anticipated Transients without Scram" were accidents where the loss of offsite power (LOOP), loss of external load, and electrical grid disturbances were identified as contributing to the accident. The changes made for the Waverly Wind Farm and the 5 mile 345kV Generator Tie Line will not alter the impact of the identified events. The impact of these changes and electrical disturbances on the LaCygne 345kV Line are bounded by LOOP, External Load Loss, and Grid Disturbances. On Question 1, there will be a small increase in the frequency of occurrence of the identified events that can contribute to an acCident previously evaluated in the USAR due to the installation of the Waverly Wind Farm and the 5 miles of 345kV Generator Tie line from the Waverly Switching Station to the Waverly Collector Substation. Since the Waverly Wind Farm and the associated 345kV Generator Tie Line are being built in compliance with the Ui=SAR 8.2.1.3 identified design requirements, the increase in the frequency of occurrence is less than minimal. Additionally on Question 2, there will be a small increase in the likelihood of occurrence of a malfunction of the LaCygne 345kV Line, which is important to safety. However.-
the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the USAR is less than minimal because the Waverly Wind Farm design along with the 5 mile 345kV Generator Tie Line are in compliance with the USAR 8.2.1.3 identified design requirements. On Questions 3 thru 7, there was no discernable impact that could be identified by the changes. Also, no new types of malfunction are introduced by the changes, since the results of any malfunctions would be bounded by the LOOP, Loss of External Load, and Grid Disturbances already evaluated.
Attachment RA 17-0015 Page 5 of 6 Evaluation Number: 59 2016-0001 Revision: O Title: Class 1 E Equipment Room Temperature Increase Activity
Description:
Engineering Configuration Change Package (CCP) 015011 was issued to evaluate an increase in the maximum allowable environmental temperatures in the Control Building Class 1E equipment rooms. The historical normal and accident environmental room conditions were a maximum of 90°F, and CCP 015011 increases this to 104°F, under specific conditions. This elevated room temperature will only occur if a single air conditioning unit (SGK05A/B) is nonfunctional concurrent with accident condition loss of coolant accident (LOCA) heat loads.
All equipment in the Class 1E equipment rooms that is critical to achieve safe plant shutdown was specified to have a maximum design temperature of at least 104 °F (some equipment was specified to 122°F) except for the 125V DC system (NK) batteries, which were procured for a normal environmental range of 60-90°F, without a maximum temperature specified.
50.59 Evaluation:
CCP 015011 provides a detailed evaluation of the impact to the Class 1E equipment due to the increase in the maximum allowable environmental temperatures to 104°F, under specific conditions. All equipment was inventoried and the design specification for each component of the Class 1E equipment was identified. The design specifications list a maximum ambient temperature environment for the equipment to be located in. With the exception of the NK batteries, all Class 1E equipment was specified to be located in a maximum temperature environment of 104°F or 122°F. The batteries were not specified with a maximum temperature environment, but a normal temperature range for operation. CCP 015011 evaluated the operation and impact to the batteries from this extended temperature environment and concluded that the effects on the batteries at 104°F is negligible for the limited time period the batteries could be exposed to the elevated temperature.
- j. ,;....*
Attachment RA 17-0015 Page 6 of 6 Evaluation Number: 59 2016-0002 Revision: O Title: Dedicated Operator to Support Maintenance Activity on Damper GKD0081 Activity
Description:
The activity involves replacing an automatic function with a dedicated operator manual action to open GKD0081, "Control Room A/C Unit 4A Control Room Discharge Isolation Damper," in support of a maintenance activity. The purpose of this activity is to maintain operability of the A-train of the Control Room Emergency Ventilation System (CREVS) during the performance of the maintenance activity of repairing the limit switches. The 50.59 Screen determined that this change involves a change to a procedure that adversely affects how USAR described SSC design functions are performed or controlled, as it replaces an automatic function with a manual operator action.
In order to perform maintenance on damper GKD0081, the actuator will need to be disengaged from the damper. During this time frame, if a Control Room Ventilation Isolation Signal (CRVIS) were to occur, the associated actuator, GKHZ0029B, would not be able to open damper GKD0081. Damper GKD0081 will need to be opened in order for the A-train of CREVS to be able to perform its Safety Design Basis Functions, specifically Safety Desigh Basis Seven
- - 'The control room air-conditioning system provides the control room with a conditioned atmosphere during all modes of plant operation, including post-accident operation (GDC-19)."
In order to ensure that the A-train of CREVS can perform its design basis functions, the proposed activity involves stationing a dedicated operator at damper GKD0081 in support of the maintenance activity. If a CRVIS is generated, then the dedicated operator would manually open damper GKD0081 to ensure that the A-train of CREVS could perform its specified safety functions.
50.59 Evaluation:
The change of using a dedicated operator to open GKD0081 in support of a maintenance activity affects the likelihood of occurrence of a malfunction of an SSC important to safety by replacing an automatic function with a manual action while performing maintenance on the damper.
The operator will position the damper within a time frame that is bounded by the time that the normal actuator, GKHZ0029B, would be able to position the damper. The dedicated operator will have 60 seconds to open damper GKD0081 from the time the control room filtration fan (CGK03A) starts, or 30 seconds from the time that the control room air conditioning unit (SGK04A) starts. Thus, there will be no impact on the ability of the A-train of CREVS to perform its specific safety functions.
It was concluded that the impact on the likelihood of occurrence of a malfunction of an SSC important to safety is not more than minimal as discussed in Question 2 of this evaluation.