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Category:Letter type:W
MONTHYEARW3F1-2023-0056, Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242023-12-19019 December 2023 Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2023-0055, Reply to a Notice of Violation2023-12-14014 December 2023 Reply to a Notice of Violation W3F1-2023-0052, Core Operating Limits Report (COLR) - Cycle 26, Revision O2023-11-0707 November 2023 Core Operating Limits Report (COLR) - Cycle 26, Revision O W3F1-2023-0049, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal2023-09-28028 September 2023 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal W3F1-2023-0048, Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-09-25025 September 2023 Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program W3F1-2023-0036, Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-05-0404 May 2023 Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0032, Annual Radioactive Effluent Release Report (ARERR) 20222023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) 2022 W3F1-2023-0033, Submittal of Annual Radiological Environmental Operating Report - 20222023-04-27027 April 2023 Submittal of Annual Radiological Environmental Operating Report - 2022 W3F1-2023-0025, Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.22062023-04-11011 April 2023 Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.2206 W3F1-2023-0018, Updated Final Supplemental Response to NRC Generic Letter 2004-022023-03-30030 March 2023 Updated Final Supplemental Response to NRC Generic Letter 2004-02 W3F1-2023-0022, Registration of Dry Fuel Storage Cask Use2023-03-22022 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0021, Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days2023-03-17017 March 2023 Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0016, Registration of Dry Fuel Storage Cask Use2023-03-0303 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0014, Reply to a Notice of Violation; EA-22-1192023-02-20020 February 2023 Reply to a Notice of Violation; EA-22-119 W3F1-2023-0013, Notification of Readiness for Supplemental Inspection2023-02-15015 February 2023 Notification of Readiness for Supplemental Inspection W3F1-2023-0007, Registration of Dry Fuel Storage Cask Use2023-02-0606 February 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0010, Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days2023-01-25025 January 2023 Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0002, SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days2023-01-0505 January 2023 SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days W3F1-2022-0067, Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-022022-12-20020 December 2022 Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-02 W3F1-2022-0054, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability2022-11-0101 November 2022 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability W3F1-2022-0063, Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 372022-10-27027 October 2022 Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 37 W3F1-2022-0059, Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-5052022-10-13013 October 2022 Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-505 W3F1-2022-0058, Reply to a Notice of Violation; EA-22-0332022-10-12012 October 2022 Reply to a Notice of Violation; EA-22-033 W3F1-2022-0049, Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-5052022-08-19019 August 2022 Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 W3F1-2022-0037, Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242022-08-0808 August 2022 Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2022-0044, SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-07-0606 July 2022 SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0042, SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-06-27027 June 2022 SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0015, Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf.2022-05-16016 May 2022 Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf. W3F1-2022-0026, Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 20222022-04-28028 April 2022 Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 2022 W3F1-2022-0028, Annual Radiological Environmental Operating Report - 20212022-04-26026 April 2022 Annual Radiological Environmental Operating Report - 2021 W3F1-2022-0029, Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.22062022-04-26026 April 2022 Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.2206 W3F1-2022-0009, Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2022-04-25025 April 2022 Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors W3F1-2022-0031, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-2842022-04-25025 April 2022 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-284 W3F1-2022-0020, Review of Preliminary Accident Sequence Precursor Report2022-04-11011 April 2022 Review of Preliminary Accident Sequence Precursor Report W3F1-2022-0017, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20212022-04-0707 April 2022 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2021 W3F1-2022-0019, WAT-2022-02 Post Exam Analysis2022-03-0909 March 2022 WAT-2022-02 Post Exam Analysis W3F1-2022-0011, Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-02-0808 February 2022 Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0008, SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days2022-02-0101 February 2022 SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days W3F1-2021-0074, Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-022021-12-16016 December 2021 Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-02 W3F1-2021-0064, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 2842021-11-30030 November 2021 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 W3F1-2021-0061, Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-10-14014 October 2021 Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0063, Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery2021-10-12012 October 2021 Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt W3F1-2021-0060, Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-09-30030 September 2021 Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0039, Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years2021-08-25025 August 2021 Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years W3F1-2021-0055, Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual2021-08-20020 August 2021 Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual W3F1-2021-0057, (Waterford 3) - Emergency Plan Revision 0522021-08-18018 August 2021 (Waterford 3) - Emergency Plan Revision 052 W3F1-2021-0054, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 20202021-07-29029 July 2021 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 2020 W3F1-2021-0051, Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator2021-07-19019 July 2021 Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator 2023-09-28
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Entergy Nuclear South Entergy Operations, Inc.
17265 River Road
-- Entergy Killona, LA 70057 Tel 504 739 6440 Fax 504 739-6698 bhousto@entergy.com Bradford Houston Director, Nuclear Safety Assurance Waterford 3 W3Fl-2004-0027 April 22, 2004 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Supplement to Amendment Request NPF-38-248 Relaxation of Ventilation System Heater Surveillance Acceptance Criteria Waterford Steam Electric Station, Unit 3 Docket No. 50-382 NPF-38
REFERENCES:
Entergy letter to the NRC dated September 12, 2003, License Amendment Request NPF-38-248, Relaxation of Ventilation System Heater Surveillance Acceptance Criteria (W3Fl-2003-0044)
Dear Sir or Madam:
By the referenced letter, Entergy Operations, Inc. (Entergy) proposed a change to the Waterford Steam Electric Station, Unit 3 (Waterford 3) Technical Specifications (TSs) to relax the heater acceptance criteria contained in surveillance requirements (SR) 4.6.6.1d.5, 4.7.6.1d.3, and 4.7.7d.4 for the shield building ventilation, control room ventilation, and controlled ventilation area systems, respectively.
On February 25, 2004, Entergy discussed two questions with a member of the NRC staff regarding emergency diesel generator loading and the root cause of the May 22, 2003 inoperability of the shield building ventilation heaters. As a result of the call, Entergy agreed to provide a formal response. Entergy's response is attached to this letter.
There are no technical changes proposed. The original no significant hazards consideration included in referenced letter is not affected by any information contained in the supplemental letter. There are no new commitments contained in this letter.
If you have any questions or require additional information, please contact Jerry Burford at 601-368-5755.
-6 atoI
W3Fl-2004-0027 Page 2 of 3 I declare under penalty of perjury that the foregoing is true and correct. Executed on April 22, 2004.
Sincerely, 2 Y/41 BLH/FGB/cbh
Attachment:
Response to Request for Additional Information
W3Fl-2004-0027 Page 3 of 3 cc: Dr. Bruce S. Mallett U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Senior Resident Inspector Waterford 3 P.O. Box 822 Killona, LA 70066-0751 U.S. Nuclear Regulatory Commission Attn: Mr. Nageswaran Kalyanam MS O-07D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway Attn: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn Attn: N.S. Reynolds 1400 L Street, NW Washington, DC 20005-3502 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P. 0. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers Attn: Library Town Center Suite 300S 29th S. Main Street West Hartford, CT 06107-2445
Attachment To W3FI-2004-0027 Response to Request for Additional Information
Attachment to W3Fl-2004-0027 Page 1 of 2 Response to Request for Additional Information Related to License Amendment Request NPF-38-248, Relaxation of Ventilation System Heater Surveillance Acceptance Criteria Question 1:
In the staff review of the licensee's submittal, we were unable to determine what value was used for the power of the heaters in the diesel load calculation EC-E90-006. Please confirm that Calculation EC-E90-006 considered +5 percent tolerance of the subject heaters ( i.e. 63 KVV, 21 KWV, and 10.5 KW). Are there any other loads that may be operating at more than nameplate rated values or at a service factor? The staff is concerned about the cumulative effect of all such loads. How will this additional KW load be captured in the calculation?
Response 1:
Calculation EC-E90-006 uses the nominal nameplate rating of the heaters (i.e., 60KW, 20K1W and 10 KW). This is based on the fact that the heater load is dependent on voltage at the heater terminals. During the emergency mode of operation, the emergency diesel generator (EDG) is expected to maintain approximately 4160V at the 4160V busses. The 4160/480V transformers have a typical impedance of approximately 9%. This implies that at 100%
transformer loading, there will be a 9% voltage drop across the transformer. The transformers have a 2.5% tap setting to boost the secondary voltage. The voltage drop associated with cable losses from the 4160V bus to the heater terminals is assumed to be 1%. Hence, if the transformer is loaded up to 100% of the rating, the voltage drop to the heater terminals is expected to be 7.5% (9.0+1 - 2.5). For the purposes of evaluating the heater rating, a voltage drop of 3.5% was conservatively assumed at the heater terminals. As the power consumed by the heater is a function of the square of the voltage, the heater load will be approximately 7% less than nameplate rating. Cable losses were added directly to the net heater load on the EDG. Including the impact of cable losses, the heaters will still consume less power than their respective nameplate rating.
The EDG loading is calculated using a time dependent methodology. Calculation EC-E90-006 uses motor brake horsepower to evaluate the EDG loading. The brake horsepower is derived in a supporting calculation EC-M89-032 "Calculations for Motors Driven by Emergency Diesel Generator.' Based on this methodology, the peak load on each EDG is less than 4200KW. After 75 minutes into the event, the loading is reduced due to recirculation actuation signal and the long term steady state loading for a large break loss of coolant accident is computed to be less than 3800KW.
Calculation EC-E90-006 Supplement A also evaluates the electrical loading on the EDG assuming all loads are at the "maximum expected brake horsepower.' Maximum expected brake horsepower values were obtained from pump/motor curves, technical manuals, specifications and nameplate data to determine the bounding horsepower for postulated EDG loading scenarios. Any motor service factor contributions are therefore not applicable because motors will not exceed the maximum expected brake horsepower values listed in Supplement A.
For most loads, the maximum expected brake horsepower is at or nominally below nameplate horsepower values, but some loads were evaluated at greater than their nameplate values
Attachment to W3F1-2004-0027 Page 2 of 2 (e.g. component cooling water pumps A, B & AB, emergency feedwater pumps A&B, AB fire pump) for the purposes of the calculations in Supplement A. The calculation concludes that the peak electrical load on EDG A will be about 4450KW (for about 45 minutes). This is due to an assumption that manual loads are added after 30 minutes into an event. This short term overload is well within the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating of 4840KW. EDG B has a slightly lower peak load.
A +10% increase in heater nameplate loading for the six heaters in question will result in a power consumption increase of 9 KW per EDG. In view of the margin available between the EDG rating and postulated accident loading (based on maximum expected brake horsepower) any minor deviations, such as the additional 9 KW of heater load, will not result in overloading the EDGs for extended durations.
Question 2:
The submittal stated in the background section that approximately half of the heating coils were replaced due to the shield building ventilation system being declared inoperable on May 22, 2003. Please provide us with the root cause of the change of heating coils resistance of B train SBVS on May 22, 2003? What is the reason that the new coils were able to pass the surveillance test and the old coils which had in the past found to be acceptable were no longer able to pass the surveillance test?
Response 2:
Based on the field measured resistance and voltage, the B train shield building ventilation system heater capacity was less than 63KW as the bus voltage was less than 480V. When the field readings were normalized to a common base of 480V, the resultant computed value was marginally over the 63KW technical specification limit.
Discussions with the vendor revealed that nuclear sites are intentionally provided heating coils near the minimum heater resistance tolerance to ensure excess heater capacity margin.
While some slight reduction in resistance can occur as a result of humidity, the overall degradation mechanism that indicates heater end of life remains higher resistance (lower output). Past experience has also shown that field measurement inaccuracies, especially voltage, can impact the results of the surveillance test. These conditions may have contributed to not passing the surveillance test on May 22, 2003.
Entergy Operations, Inc. personnel hand selected the replacement coils based on the individual coil resistance. Low resistance heating coils were replaced with higher resistance heating coils from stock to reduce the overall heater output. This enabled Waterford Steam Electric Station, Unit 3 to satisfy technical specification requirements.