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Category:Letter
MONTHYEARIR 05000382/20230102024-01-31031 January 2024 Comprehensive Engineering Team Inspection Report 05000382/2023010 IR 05000382/20230032024-01-23023 January 2024 Acknowledgment of Reply to a Notice of Violation NRC Inspection Report 05000382/2023003 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23340A2292023-12-28028 December 2023 Withdrawal of an Amendment Request to Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability (EPID L-2022-LLA-0169)-LTR ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1442023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23312A1832023-11-14014 November 2023 Integrated Inspection Report 05000382/2023003 and Notice of Violation ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000382/20234012023-10-0404 October 2023 Cyber Security Inspection Report 05000382/2023401 (Cover Letter Only) IR 05000382/20230052023-08-21021 August 2023 Updated Inspection Plan for Waterford Steam Electric Station, Unit 3 - (Report 05000382/2023005) IR 05000382/20233012023-08-15015 August 2023 NRC Initial Operator Licensing Examination Approval 05000382/2023301 IR 05000382/20230022023-08-0808 August 2023 Integrated Inspection Report 05000382/2023002 IR 05000382/20234022023-08-0707 August 2023 NRC Security Inspection Report 05000382/2023402 (Full Report) IR 05000382/20230402023-07-12012 July 2023 Revised 95001 Supplemental Inspection Report 05000382/2023040, Exercise of Enforcement Discretion, and Follow-Up Assessment Letter ML23191A4562023-07-10010 July 2023 Notification of Comprehensive Engineering Team Inspection (050003822023010) and Request for Information ML23158A1042023-06-0808 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000382/2023401 ML23145A2272023-06-0202 June 2023 95001 Supplemental Inspection Report 05000382/2023040, and Exercise of Enforcement Discretion ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment IR 05000382/20230012023-04-24024 April 2023 Integrated Inspection Report 05000382/2023001, Independent Spent Fuel Storage Installation Report 07200075/2023001, and Exercise of Enforcement Discretion ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML23108A2542023-04-18018 April 2023 WCGS Information Request, Security IR 2023401 IR 05000382/20234032023-04-17017 April 2023 Security Baseline Inspection Report 05000382/2023403 ML23093A2122023-04-0303 April 2023 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2022 ML23089A0602023-03-30030 March 2023 Entergy Operations, Inc. - Fleet Project Manager Assignment ML23088A3922023-03-29029 March 2023 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML23080A2882023-03-21021 March 2023 Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc ML23059A2592023-03-0707 March 2023 Correction to Issuance to Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23065A2002023-03-0303 March 2023 EN 56252 Update - Flow Serve - Final Notification of Potential Part 21 on Peerless 56 Frame DC Motors ML23060A1092023-03-0101 March 2023 Proof of Financial Protection (10 CFR 140.15) IR 05000382/20220062023-03-0101 March 2023 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3, (Report 05000382/2022006) ML22322A1092023-02-17017 February 2023 Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b IR 05000382/20230902023-02-0101 February 2023 Final Significance Determination of a White Finding, NOV, and Follow-Up Assessment Letter; NRC Inspection Report 05000382/2023090 ML23032A5062023-02-0101 February 2023 Technical Specification Index and Bases Update to the NRC for the Period November 11, 2021 Through July 25, 2022 ML23030A6642023-01-27027 January 2023 Flowserve, Part 21 Second Interim Notification Report Re Peerless 56 Frame DC Motors IR 05000382/20220042023-01-26026 January 2023 Integrated Inspection Report 05000382/2022004 and Independent Fuel Storage Installation Inspection Report 07200075/2022001 ML23024A0822023-01-20020 January 2023 Stephens Insurance, Entergy - 2023 Nuclear Energy Liability Evidence of Financial Protection ML23018A2202023-01-18018 January 2023 Quality Assurance Program Manual Reduction in Commitment IR 05000382/20220912023-01-12012 January 2023 Emergency Preparedness Inspection Report 05000382/2022091 and Preliminary White Finding and Apparent Violation IR 05000382/20220032023-01-0505 January 2023 Revised Integrated Inspection Report 05000382/2022003 ML22342B1402022-12-0202 December 2022 56252-EN 56252 - Flowserve - Limitorque - Interim Report Potential Part 21 on Peerless 56 Frame DC Motors ML22300A2082022-11-30030 November 2022 Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22332A5292022-11-29029 November 2022 Notification of NRC Initial Operator Licensing Examination 05000382/2023301 IR 05000382/20220132022-11-28028 November 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000382/2022013 IR 05000382/20220022022-11-0101 November 2022 Revised Integrated Inspection Report 05000382/2022002 2024-01-31
[Table view] Category:Safety Evaluation
MONTHYEARML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22322A1092023-02-17017 February 2023 Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22300A2082022-11-30030 November 2022 Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22194A9012022-07-20020 July 2022 Issuance of Amendment No. 268 Adoption of Technical Specification Task Forcetraveler TSTF-569, Revise Response Time Testing Definition, Revision 2 ML22153A4452022-07-0808 July 2022 Issuance of Amendment No. 267 for Reactor Coolant System Pressure/Temperature Limits and Low Temperature Overpressure Setpoints Applicable for 55 Effective Full Power Years ML22145A0152022-05-27027 May 2022 Issuance of Amendment No. 266 to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22075A1022022-04-29029 April 2022 Issuance of Amendment No. 264 to Relocate Chemical Detection System Technical Specifications to Technical Requirements Manual ML22083A1242022-04-28028 April 2022 Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2 ML22061A2172022-03-15015 March 2022 Revision of the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML22007A3172022-01-18018 January 2022 1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ML21313A0082021-12-0808 December 2021 Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21166A1832021-09-15015 September 2021 Issuance of Amendment No. 261 Regarding Removal and Relocation of Boration System Technical Specifications ML21131A2432021-08-24024 August 2021 Issuance of Amendment No. 260 Digital Upgrade to the Core Protection and Control Element Assembly Calculator System ML21082A3022021-05-19019 May 2021 Issuance of Amendment No. 259 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML20280A3292020-10-20020 October 2020 Issuance of Amendment No. 258 Regarding Technical Specification 3/4.8.1 Surveillance Requirements ML20205L5742020-08-25025 August 2020 Issuance of Amendment No. 257 Control Room Air Condition System Technical Specifications ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML20022A2582020-01-28028 January 2020 Re-Issuance of Approval of Relief Request WF3-RR-19 2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control ML20002A0202020-01-13013 January 2020 Approval of Relief Request WF3-RR-19-2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control System ML19275D4382019-10-24024 October 2019 Redacted - Issuance of Amendment No. 256 for Use of the Tranflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Internal Components ML19282D8922019-10-15015 October 2019 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule ML19254A6032019-09-19019 September 2019 Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1 ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19247B1972019-09-0909 September 2019 Approval of Relief Request W3-ISI-032,Relief from the Requirements of ASME Code Section XI Regarding Volumetric Examination ML19232A0252019-08-27027 August 2019 Authorization of Proposed Alternative to ASME Code Section XI, IWA-4000, Repair/Replacement Activities ML19164A0012019-06-28028 June 2019 Issuance of Amendment No. 254 Regarding Revision of Technical Specification 3/4.7.4, Ultimate Heat Sink, ML19157A3162019-06-12012 June 2019 Authorization of Proposed Alternative to ASME Code Case N-770-2 ML19022A3372019-02-13013 February 2019 Issuance of Amendment No. 253 to Revise Section 15.4.3.1 of the Updated Final Safety Analysis Report to Account for Fuel Misload ML18282A0302018-10-18018 October 2018 Proposed Alternative to ASME Code, Section XI, Regarding Charging Pipe Visual Inspection ML18180A2982018-07-23023 July 2018 Issuance of Amendment No. 252 Adoption of the Raptor-M3G Code for Neutron Fluence Calculations ML18128A0672018-06-0808 June 2018 Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4 ML18026B0532018-04-26026 April 2018 Issuance of Amendment No. 251 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control,(Cac No. MF9537; EPID L-2017-LLA-0205) ML17341A1202017-12-11011 December 2017 Relief Request PRR-WF3-2017-3, Request for Alternative to ASME OM Code Requirements for Comprehensive Testing of High Pressure Safety Injection Pump AB (CAC No. MF9875; EPID L-2017-LLR-0049) ML17328A8822017-11-29029 November 2017 Requests for Relief GRR-1, PRR-1 and PRR-2, Alternatives to ASME OM Code Requirements for Inservice Testing for the Fourth 10-Year Program Interval (CAC Nos. MF9869, 9870, and 9871; EPID L-2017-LRM-0045-47) ML17192A0072017-07-27027 July 2017 Issuance of Amendment No. 250 Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3 ML17069A1872017-03-22022 March 2017 Request for Alternative to 10 CFR 50.55a(c) ASME Code Section III Code Case 1361-1, Relief Request W3-ISI-024 ML17045A1482017-03-0303 March 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16235A2282016-12-0909 December 2016 Request for Alternative Test Plan to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML16278A0172016-10-19019 October 2016 Entergy Fleet Relief Request RR-EN-ISI-15-1, Alternative to Maintain Inservice Inspection Related to Activities to the 2001 Edition/2003 Addendum of ASME Section XI Code ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16159A4192016-07-26026 July 2016 Issuance of Amendment No. 249 Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control ML16182A2702016-07-0606 July 2016 Relief Request PRR-WF3-2016-1, Alternative to the Inservice Testing Program ML16126A0332016-06-27027 June 2016 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) ML16096A2692016-06-0606 June 2016 Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1 ML16093A0282016-05-31031 May 2016 Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 ML16077A2702016-05-10010 May 2016 Issuance of Amendment No. 247 Regarding Cyber Security Plan Milestone 8 Full Implementation Schedule ML15289A1432015-11-13013 November 2015 Redacted - Issuance of Amendment No. 246 Changes to Technical Specification 3.1.3.4 Regarding Control Element Assembly Drop Times ML15267A7972015-10-0606 October 2015 Safety Evaluation Regarding the Aging Management Program for Reactor Vessel Internals ML15139A4832015-08-31031 August 2015 Issuance of Amendment No. 245 Change to Updated Final Safety Analysis Report Clarifying Pressurizer Heaters Function for Natural Circulation at the Onset of a Loss of Offsite Power 2023-05-01
[Table view] |
Text
March 5, 2002 Mr. Joseph E. Venable Vice President Operations Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - CORRECTION TO AMENDMENT NO. 180 RE: EMERGENCY DIESEL GENERATOR SURVEILLANCE REQUIREMENTS (TAC NO. MB2371)
Dear Mr. Venable:
The Commission issued on February 26, 2002, Amendment No. 180 to Facility Operating License No. NPF-38 for the Waterford Steam Electric Station, Unit 3. The amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated July 10, 2001, as supplemented by letter dated December 20, 2001. The amendment modified TS Surveillance Requirements (SR) 4.8.1.1.2.e to allow to allow performance of specific SRs (4.8.1.1.2.e.1, 2, 4, 6, 10, and 12) during any mode of plant operation. A copy of our related Safety Evaluation (SE) was also enclosed.
Errors were discovered on pages 1 and 4 of the SE, subsequent to the February 26, 2002, issuance, and were in Section 1.0, "INTRODUCTION," and Section 3.7, "SR 4.8.1.1.2.e.6."
Revised pages of 1 and 4 of the SE are enclosed with the corrections identified by a marginal vertical bar. Please replace pages 1 and 4 of the previous submittal with the enclosed, revised sheets.
Please call N. Kalyanam, at (301) 415 1480, with any questions you may have.
Sincerely,
/RA/
N. Kalyanam, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
Pages 1 and 4 of the Safety Evaluation cc w/encls: See next page
March 5, 2002 Mr. Joseph E. Venable Vice President Operations Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - CORRECTION TO AMENDMENT NO. 180 RE: EMERGENCY DIESEL GENERATOR SURVEILLANCE REQUIREMENTS (TAC NO. MB2371)
Dear Mr. Venable:
The Commission issued on February 26, 2002, Amendment No. 180 to Facility Operating License No. NPF-38 for the Waterford Steam Electric Station, Unit 3. The amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated July 10, 2001, as supplemented by letter dated December 20, 2001. The amendment modified TS Surveillance Requirements (SR) 4.8.1.1.2.e to allow to allow performance of specific SRs (4.8.1.1.2.e.1, 2, 4, 6, 10, and 12) during any mode of plant operation. A copy of our related Safety Evaluation (SE) was also enclosed.
Errors were discovered on pages 1 and 4 of the SE, subsequent to the February 26, 2002, issuance, and were in Section 1.0, "INTRODUCTION," and Section 3.7, "SR 4.8.1.1.2.e.6."
Revised pages of 1 and 4 of the SE are enclosed with the corrections identified by a marginal vertical bar. Please replace pages 1 and 4 of the previous submittal with the enclosed, revised sheets.
Please call N. Kalyanam, at (301) 415 1480, with any questions you may have.
Sincerely,
/RA/
N. Kalyanam, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
Pages 1 and 4 of the Safety Evaluation cc w/encls: See next page DISTRIBUTION:
PUBLIC PDIV-1 Reading RidsNrrDripRtsb (WBeckner)
RidsNrrDlpmPdiv (SRichards) RidsOgcRp RidsAcrsAcnwMailCenter G.Hill(2) RidsNrrDlpmPdivLpdiv1 (RGramm)
RidsNrrPMNKalyanam RidsNrrLADJohnson Om Chopra RidsRgn4MailCenter (KBrockman) L.Hurley, RIV D. Bujol, RIV M. McConnell Accession No.: ML020640201 OFFICE PDIV-1/PM PDIV-1/LA PDIV-1/SC NAME NKalyanam DJohnson RGramm DATE 02/28/02 02/28/02 03/05/02 OFFICIAL COPY
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 180 TO FACILITY OPERATING LICENSE NO. NPF-38 ENTERGY OPERATIONS, INC.
WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382
1.0 INTRODUCTION
By letter dated July 10, 2001, as supplemented by letter dated December 20, 2001, Entergy Operations, Inc. (Entergy, the licensee) submitted a request for changes to the Waterford Steam Electric Station, Unit 3, (Waterford 3) Technical Specifications (TSs). The proposed changes relate to Emergency Diesel Generator (EDG) surveillance testing and modify Surveillance Requirement (SR) 4.8.1.1.2.e regarding the testing of EDGs during any mode of plant operation. The purpose of the proposed change is to provide Entergy additional flexibility in the scheduling of maintenance activities, reduce plant refueling outage duration, and increase EDG availability when the plant is shut down. Currently, as directed by SR 4.8.1.1.2.e, SRs 4.8.1.1.2.e.1 through 4.8.1.1.2.e.12 are required to be performed at least once per 18 months during shutdown. The proposed change would permit SRs 4.8.1.1.2.e.1, 4.8.1.1.2.e.2, 4.8.1.1.2.e.4, 4.8.1.1.2.e.6, 4.8.1.1.2.e.10, and 4.8.1.1.2.e.12 to be performed during any mode of plant operation. SRs 4.8.1.1.2.e.3, 4.8.1.1.2.e.5, 4.8.1.1.2.e.7, 4.8.1.1.2.e.8, 4.8.1.1.2.e.9, and 4.8.1.1.2.e.11 will be performed only when the plant is shutdown. This is achieved by deleting the words "during shutdown" from 4.8.1.1.2.e and adding them to the specific SRs (4.8.1.1.2.e.3, 4.8.1.1.2.e.5, 4.8.1.1.2.e.7, 4.8.1.1.2.e.8, 4.8.1.1.2.e.9, and 4.8.1.1.2.e.11). The change to SR 4.8.1.1.2.c.1.a is editorial in nature.
This amendment is based on a similar evaluation and approval for Niagra Mohawk Power Corporation for Nine Mile Point Nuclear Station, Unit 2, dated March 7, 1995. Also, similar changes for testing of the EDG lockout features (SR 4.8.1.1.2.e.12) have been reviewed and approved by the Nuclear Regulatory Commission (NRC) for Millstone Nuclear Power Station, Unit 3 and Catawba Nuclear Stations, Units 1 and 2.
The December 20, 2001, supplemental letter provided additional information that did not change the scope of the request or the initial proposed no significant hazard consideration determination (66 FR 44168, published August 22, 2001).
2.0 BACKGROUND
General Design Criterion (GDC)-17, Electric Power Systems, of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 requires, in part, that nuclear power
During the test, the EDG operates in parallel with offsite power and is loaded to its continuous rating. To create load rejection, the EDG output breaker is manually opened. This results in EDG rejecting its load and isolating it from the 4160 V vital bus. The load is simultaneously picked up by the offsite power source. The licensee states that the previous full-load test data indicates that voltage on the 4160 V safety buses was within +/- 5% of the initial test voltage and stabilized within one second. This relatively minor transient was well within the capability of the loads on the vital buses. The + 5% value properly ensures stability of the safety bus and is within the design rating of the switchgear (4760 V). The - 5% falls above the instantaneous Loss of Voltage TS trip set point of greater than or equal to 3245 V. It is also above the degraded voltage values of 3675 V with inverse time characteristic of a high of 9 seconds to a low of 2 seconds time delay and sustained degraded voltage values of 3875 with a time delay of 12.5 seconds. The licensee states that the instantaneous loss of voltage trip was used for a tolerance value based on the Refueling Outage 9 EDG 100% load rejection test data that resulted in a voltage drop of approximately 2% with stabilizing in about 0.5 seconds.
Based on the previous test results, the staff concludes that since performance of this SR in the past did not cause significant perturbation to the electrical distribution system, the performance of this SR during power operation is acceptable.
3.6 SR 4.8.1.1.2.e.4 This SR requires, at least once per 18 months during shutdown, verification that on an SIAS, the EDG starts on the auto-start signal and operates on standby for greater than or equal to 5 minutes. The steady-state EDG voltage and frequency shall be 4160 +420, - 240 V and 60 +/- 1.2 Hz within 10 seconds after the auto-start signal, the EDG voltage and frequency shall be maintained within these limits during the test. The licensee has proposed to perform this test during power operation. The licensee states that the design of their ESF subgroup relays offers Waterford 3 the ability to start the EDG with the SIAS actuation test signal during power operation without causing any loads to shed or ESF loads to start. Based on the above, the staff concludes that since the SIAS to the EDG can be generated without causing any loads to shed or ESF loads to start, the performance of this SR during power operation is acceptable.
3.7 SR 4.8.1.1.2.e.6 This SR requires at least once per 18 months during shutdown, verification that the EDG operates for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. During 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this test, the EDG shall be loaded to greater than or equal to 4700 kW to 4900 kW and during 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of this test, the EDG shall be loaded to 4000 kW to 4400 kW. The EDG voltage and frequency shall be 4160 +420, -240 V and 60 +/-1.2 Hz within 10 seconds after the start signal, and the steady state EDG voltage and frequency shall be 4160 +/- 420 V and 60 +1.2, -.3 Hz during the test. Within 5 minutes after completing this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test, SR 4.8.1.1.2.a.4 is performed. This test is presently performed only during shutdown. The reason for the mode restriction is to prevent unnecessary perturbation to the electrical distribution systems, which could challenge steady state operation if the reactor is in Mode 1 or 2. The licensee has proposed to perform this surveillance during power operation.
The licensee states that each month the EDGs are run during power operation to satisfy monthly TS requirements. The EDG system lineup with the offsite power for the monthly test is the same as the lineup for the 24-hour endurance run. Therefore, performing the 24-hour
Waterford Generating Station 3 cc:
Mr. Michael E. Henry, Administrator Regional Administrator, Region IV and State Liaison Officer U. S. Nuclear Regulatory Commission Department of Environmental Quality 611 Ryan Plaza Drive, Suite 1000 P. O. Box 82135 Arlington, TX 76011 Baton Rouge, LA 70884-2135 Parish President Council Vice President, Operations Support St. Charles Parish Entergy Operations, Inc. P. O. Box 302 P. O. Box 31995 Hahnville, LA 70057 Jackson, MS 39286-1995 Executive Vice-President Director and Chief Operating Officer Nuclear Safety Assurance Entergy Operations, Inc.
Entergy Operations, Inc. P. O. Box 31995 17265 River Road Jackson, MS 39286-1995 Killona, LA 70066-0751 Chairman Wise, Carter, Child & Caraway Louisiana Public Services Commission P. O. Box 651 P.O. Box 91154 Jackson, MS 39205 Baton Rouge, LA 70825-1697 General Manager Plant Operations Waterford 3 SES Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Licensing Manager Entergy Operations, Inc.
17265 River Road Killona, LA 70066-0751 Winston & Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Resident Inspector/Waterford NPS P. O. Box 822 Killona, LA 70066-0751 January 2002