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Category:Letter type:ET
MONTHYEARET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components ET 23-0005, 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peen2023-03-16016 March 2023 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened ET 23-0003, License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications2023-03-0101 March 2023 License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2023-02-0707 February 2023 Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 23-0004, Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2023-01-26026 January 2023 Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0006, Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-12-0101 December 2022 Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 22-0010, License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2022-08-0202 August 2022 License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0011, Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface2022-05-31031 May 2022 Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface ET 22-0005, Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-04-13013 April 2022 Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0003, CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads2022-04-0606 April 2022 CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads ET 22-0002, Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head .2022-04-0404 April 2022 Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head . ET 22-0004, Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report2022-03-15015 March 2022 Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report ET 22-0001, Removal of the Table of Contents from the Technical Specifications2022-01-12012 January 2022 Removal of the Table of Contents from the Technical Specifications ET 21-0017, Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-12-22022 December 2021 Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0009, Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage2021-11-0101 November 2021 Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage ET 21-0015, Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-20020 October 2021 Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0012, Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-11011 October 2021 Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0004, License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2021-09-29029 September 2021 License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 21-0010, License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-09-29029 September 2021 License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0005, Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-1912021-08-12012 August 2021 Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 20-0013, Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415)2020-10-26026 October 2020 Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415) ET 20-0011, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-10-0101 October 2020 Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ET 20-0007, License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers2020-06-0808 June 2020 License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ET 20-0008, Operating Corporation Update for Full Implementation of Open Phase Detection System2020-05-20020 May 2020 Operating Corporation Update for Full Implementation of Open Phase Detection System ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2020-04-27027 April 2020 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) ET 20-0002, Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 12020-01-29029 January 2020 Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 ET 19-0021, Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-12-0909 December 2019 Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0020, Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-11-13013 November 2019 Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0019, Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-09-10010 September 2019 Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0018, Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-08-22022 August 2019 Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0014, lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 12019-08-15015 August 2019 lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 1 ET 19-0002, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-03-18018 March 2019 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0008, Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption.2019-03-0505 March 2019 Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption. ET 19-0003, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange2019-02-25025 February 2019 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange ET 19-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-01-23023 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 ET 18-0032, Operating Corporation Change of Date for Full Implementation of Open Phase Detection System2018-12-0707 December 2018 Operating Corporation Change of Date for Full Implementation of Open Phase Detection System ET 18-0035, Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-12-0606 December 2018 Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0029, (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection2018-10-31031 October 2018 (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-06-19019 June 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0016, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information2018-05-29029 May 2018 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information ET 18-0014, Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-05-29029 May 2018 Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0013, Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld2018-05-0202 May 2018 Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld ET 18-0011, (WCGS) - Guarantee of Payment of Deferred Premiums2018-04-30030 April 2018 (WCGS) - Guarantee of Payment of Deferred Premiums ET 18-0012, Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-04-19019 April 2018 Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0010, Financial Protection Levels2018-03-29029 March 2018 Financial Protection Levels ET 18-0007, Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-02-15015 February 2018 Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0005, Withdrawal of License Amendment Request for Revision to the Emergency Plan2018-02-0505 February 2018 Withdrawal of License Amendment Request for Revision to the Emergency Plan ET 18-0004, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-01-29029 January 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 17-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-11-14014 November 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term 2023-05-17
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W0LF CREEK NUCLEAR OPERATING CORPORATION July 15, 2013 John P. Broschak Vice President Engineering ET 13-0024 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Reference:
- 1) Letter ET 12-0018, dated September 19, 2012, from J. P. Broschak, WCNOC, to USNRC
- 2) Letter dated May 31, 2013, from C. F. Lyon, USNRC, to M. W.
Sunseri, WCNOC, "Wolf Creek Generating Station - Request for Additional Information Re: Revision to Technical Specification 3.8.1, "AC Sources - Operating," Surveillance Requirement 3.8.1.10 (TAC NO. ME9603)"
Subject:
Docket No. 50-482: Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification (TS) 3.8.1, "AC Sources - Operating" Surveillance Requirement 3.8.1.10 Gentlemen:
Reference 1 provided Wolf Creek Nuclear Operating Corporation's (WCNOC) application to revise Technical Specification (TS) 3.8.1, "AC Sources - Operating," to increase the voltage limit for the diesel generator (DG) full load rejection test specified by Surveillance Requirement (SR) 3.8.1.10. Reference 2 provided a Nuclear Regulatory Commission (NRC) request for additional information related to the application. The Attachment provides WCNOC's response to the request for additional information.
The additional information does not expand the scope of the application as originally noticed, and does not impact the no significant hazards consideration determination presented in Reference 1.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," a copy of this submittal is being provided to the designated Kansas State official.
P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET
ET 13-0024 Page 2 of 3 This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4085, or Mr. Michael J. Westman at (620) 364-4009.
Sincerely, John P. Broschak JPB/rlt Attachment Enclosure cc: A. T. Howell (NRC), w/a, w/e T. A. Conley (NRC), w/a, w/e C. F. Lyon (NRC), w/a, wie N. F. O'Keefe (NRC), w/a, w/e Senior Resident Inspector (NRC), w/a, w/e
ET 13-0024 Page 3 of 3 STATE OF KANSAS )
COUNTY OF COFFEY )
John P. Broschak, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
Johq PBroschak Vicd esident Engineering SUBSCRIBED and sworn to before me this 15C2z day of J Lj ,2013.
SGAYLE SHEPHEARD No nDey,-i 0 "
Notary Public - State of Kansasj My /,pr*t Expires l7/.jqjo J6 Expiration I Date - 5 I
Attachment to ET 13-0024 Page 1 of 3 Response to Request for Additional Information Reference 1 provided Wolf Creek Nuclear Operating Corporation's (WCNOC) application to revise Technical Specification (TS) 3.8.1, "AC Sources - Operating," to increase the voltage limit for the diesel generator (DG) full load rejection test specified by Surveillance Requirement (SR) 3.8.1.10. Reference 2 provided a Nuclear Regulatory Commission (NRC) request for additional information related to the application. The specific NRC question is provided in italics.
- 1. On page 4 of Attachment I of the LAR, the licensee states that the switchyard voltage varies throughout the day, resulting in voltages that are sometimes at nominal, sometimes less than nominal, and sometimes higher then nominal at the DG electrical terminals.
Section 2.2, "Reason for Proposed Change," of the LAR provides tabulated data of historical bus voltage variation and corresponding "Initial to Peak Voltage Difference."
This table indicates that the maximum observed initial to peak voltage difference was 580 Volts (V) for "A" DG and 545 V for "B" DG. Historicaltrends provide an indication of DG performance and the NRC staff recognizes that several factors impact the voltage difference during load rejection tests. The licensee proposes to raise the maximum allowable bus voltage to 4992 V during the load rejection test. This will provide a range of more than 1000 V if the test is performed at the minimum allowable bus voltage.
Please provide details on the maximum allowable "Initial to Peak Voltage" difference that will be used to validate performance capabilities of the DG voltage regulator when compared with historicaltrends.
Response: There is currently no procedurally established absolute value for peak voltage rise during a full-load rejection test for the purposes of historical trend comparisons. The full-load rejection test results are trended as a method of monitoring the performance of the DG voltage regulator as required by the site System Engineering Program. In this regard, the data is being used to confirm the voltage regulator is performing consistent with the prior successful test performances. WCNOC recognizes the surveillance criteria requirement as an absolute limit with variable acceptable initial conditions. Due to the allowed variance in the initial test conditions, variance in the resulting test data is expected. Factors such as the initial voltage, reactive power loading, real power loading, and voltage regulator constants and tuning contribute to variability of the peak voltage on full-load rejection; the former being subject to grid conditions from which the test is performed. The voltage rise, or initial to peak voltage, has been used to normalize the peak voltage to the initial voltage for the purposes of comparison.
Increased reactive loading has been identified as contributing the most to variability in the resulting peak voltage, though no clear way to normalize the data has been identified for this factor. When comparing test performance data it is first reviewed on the voltage rise alone as compared to past data. If the rise is noted to be beyond the upper or lower range of the past data it is further reviewed for initial test conditions that may explain such differences. If the higher than historical voltage rise is explained by, for instance, higher than prior reactive loading, then it would be considered a new trending data point, but not necessarily a potential performance deficiency of the voltage regulator. If however, a voltage rise in excess of the past historical data occurred with no clearly linkable initial condition variance factor, then it would be considered to be a potential performance deficiency of the voltage regulator. In this case, the load acceptance test traces would be considered for any deviations as compared to prior traces to further support any conclusions of a performance decline of the voltage regulator. The load acceptance test is performed on an isolated bus with loads and sequencing with much less historical variance as compared to grid conditions affecting the full-load rejection test. In the
Attachment to ET 13-0024 Page 2 of 3 load sequence test the voltage regulator constants and tuning become a predominant factor such that any possible performance decline of the voltage regulator is more readily apparent.
Systems or components may have declining performance while still meeting TS surveillance requirements. As such, site personnel review the test results taking into consideration variances in the associated initial conditions and historical data to determine if there is a potential performance deficiency. Any performance deficiency is entered into the Corrective Action Program.
- 2. The purpose of the full load rejection test is to verify and demonstrate the DG governor and the voltage regulatorfunctional capabilitiesduring system perturbations. The full load rejection test is generally simulated by opening the DG output breaker with the DG at full load and verifying that there is minimal impact on the DG and the safety buses. This test is intended to envelope the voltage and frequency variationsthat will be observed during a partialto full load rejection event with the DG connected to the safety buses.
In the event that the DGs are supplying the safety-related buses and a large load rejection event occurs, please discuss how the operating equipment on the safety-related buses will not be degraded if the DG output voltage spikes to 4992 V.
Response: The essential service water (ESW) pump motors are 1750 Hp and are the single largest load associated with the DG. License Amendment No. 101 (Reference 3) approved the deletion of the single-load rejection surveillance test. During the review of the license amendment request, WCNOC responded to a request for additional information (Reference 4) and provided information associated with the voltage swing during the single-load rejection test.
From Reference 4, WCNOC concluded that the voltage and frequency swings for the single-load rejection test stay within steady state values during the transient. The Enclosure provides Figure 4 (from Reference 4) that shows a recording of voltage and frequency during a single-load rejection test (pump trip followed by a pump start). The NRC safety evaluation (Reference
- 3) concluded, in part:
"Operation within the steady state criteria provides assurance of adequate voltages and frequencies for the continuous operation of the connected loads and specifically for induction motors."
The single-load rejection test has not been performed since implementation of License Amendment No. 101. However, in 2011, WCNOC performed a partial load rejection test on the
'A' DG from a grid load of 3450 kW. The initial bus voltage was 4095 V and the peak was 4384 V. The partial load rejection test was completed satisfactorily with no degradation to operating equipment.
For the Wolf Creek Generating Station (WCGS) electrical distribution system, overvoltage protection is provided by surge limiters that are installed on each phase of the 4.16kV switchgear breakers. The surge limiters have been sized to coordinate with the insulation levels of connected equipment and protect the plant equipment from damage caused by transient overvoltage conditions. Additionally, the generator, transformers, equipment cables and motors all have allowable overvoltage test values that exceed 5.5kV for a duration of over 10 seconds.
The transient overvoltage from a load reject lasts only a fraction of a second. Therefore, a 4992V DG transient overvoltage spike would not degrade operating equipment.
Attachment to ET 13-0024 Page 3 of 3
References:
- 1. WCNOC Letter ET 12-0018, "License Amendment Request To Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement," September 19, 2012.
ADAMS Accession No. ML12272A279.
- 2. Letter from C. F. Lyon, USNRC, to M. W. Sunseri, WCNOC, "Wolf Creek Generating Station - Request for Additional Information Re: Revision to Technical Specification 3.8.1, "AC Sources - Operating," Surveillance Requirement 3.8.1.10 (TAC NO. ME9603)," May 31, 2013. ADAMS Accession No. ML13149A160.
- 3. Letter from J. C. Stone, USNRC, to N. S. Cams, WCNOC, "Wolf Creek Generating Station - Amendment No. 101 to Facility Operating License No. NPF-42 (TAC NO.
M89995)," August 9, 1996. ADAMS Accession No. ML022040294.
- 4. WCNOC Letter WO 96-0037, "Response to Request for Additional Information Concerning the Revision to Technical Specification 3/4.8.1, "Electrical Power Systems -
A.C. Sources," March 8, 1996.
Enclosure to ET 13-0024 Figure 4 from WCNOC Letter WO 96-0037 (Reference 4)
(1 page)
7:: 7 I~L i~9~f IT a tJ N
SrA4Rr-LI 7'-nzi7 ITS iIL~7_
-4 _ __ _ AL,-*
Figure 4 Single-Load Rejection Test (followed by FSW pump start)
(Page I of 1)