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Category:Letter
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Summer Power Nuclear Stations - Nuclear Property Insurance Coverage IR 05000280/20230042024-02-0909 February 2024 Integrated Inspection Report 05000280/2023004 and 05000281/2023004 IR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 IR 05000280/20230102024-01-18018 January 2024 – Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010 ML23312A1922024-01-18018 January 2024 Issuance of Amendment Nos. 316 & 316 Regarding a Risk Informed Approach for Tornado Classification of the Fuel Handling Trolley Support Structure 2024-09-03
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information ML24130A1192024-05-0707 May 2024 Inservice Test Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests - Response to Request for Additional Information Regarding Alternative Request V-1 ML23220A1482023-08-0707 August 2023 Proposed Emergency Plan Revision - Relocation of the Technical Support Center (TSC) Response to Request for Additional Information ML23208A0922023-07-26026 July 2023 Request for Approval of Appendix F of Fleet Report DOM-NAF-2-P Qualification of Framatome ORFEO-GAIA and OORFE-NMGRID CHF Correlations in the Dominion Energy Vipre-D Computer Code Response L-04-002, Stations - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to Request for Additional Information2023-05-0808 May 2023 Stations - 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Request for Approval of Alternative Request V-01 Use of Mechanical Agitation Process for Pressure Isolation Valve 1-SI-241 Seat Leakage Testing ML22342A4242022-12-0707 December 2022 Response to 3/12/2012 Request for Information Enclosure 2, Recommendation 2.0, Flooding Focused Evaluation Integrated Assessment Submittal Revised Commitment Completion Date ML22312A4432022-11-0707 November 2022 NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Fleet Response to RAI ML22300A1882022-10-27027 October 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater Cross-Connect Capability Response to Request for Additional Information ML22220A2162022-08-0808 August 2022 License Amendment Request 10-Day Allowed Outage Time for Opposite Unit Auxiliary Feedwater (AFW) Cross-Connect Capability Supplemental Information ML22164A8532022-06-13013 June 2022 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - 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Subsequent License Renewal Application (SLRA) Environmental Review, Response to Request for Additional Information Concerning Aquatic Resources ML20181A4222020-06-29029 June 2020 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Response to Request for Additional Information ML20181A3082020-06-23023 June 2020 Response to Request for Additional Information on 2019 Steam Generator Inservice Inspection Report ML20269A4072020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 316(b) 40 CFR 122.21(r)(2)-(13), Part 2 of 3 ML20269A4062020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 316(b) 40 CFR 122.21(r)(2)-(13), Part 3 of 3 ML20269A4082020-06-0202 June 2020 Enclosure 2 - Dominion Energy Surry Power Station Vpdes Permit No. VA0004090: Application for Permit Reissuance - 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Response to Requests for Additional Information - Set 1 ML19148A4212019-05-10010 May 2019 All Enclosures with Coversheets ML18304A3302018-10-25025 October 2018 Proposed License Amendment Request TSTF-490 & Update of Alternative Source Term Analyses Response to Request for Additional Information & Revised Proposed Technical Specifications ML18302A1212018-10-18018 October 2018 Response to Request for Additional Information, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules ML18303A2882018-10-18018 October 2018 Response to Request for Additional Information Regarding Relief Request S2-I5-LMT-P01 Examination Category R-A, Preservice Weld Examinations 2024-05-07
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VIRGINIA ELEOTRIO AND POWER COMPANY RxoHMOND,VXRGINIA 23261 September 26,
- Mr. Edson G. Case, Acting Director Serial No. 234A/060377 Nuclear Reactor .Regulation PO&M/TAP:das U. S. Nuclear Regulatory Commission Docket Nos~ 50-280 Washington, D. C. 20555 50-281 License Nos. DPR-32 Attn: Mr. Robert W. Reid, Chief -- -- -*--DPR-37* -:---- --
Operating Reactors Branch 4
Dear Mr. Case:
This letter is to present. the results of our analyses of your June 3 ,* 1977, request for further information on our system's capabilities of handling degrad-ed voltage conditions. We have reviewed our system with your staff and believe that our present system capabilities are adequate. Also, .we are submitting for your study a proposed addition to our surveillance requirements.
Specifically, our responses to your Staff Positions as discussed at our meeting of September 6, 1977,* follow:
- 1) Position 1: Second Level of Under-or-Over Voltage Protection With a Time Delay We require that a second level of voltage protection for the onsite power system be provided and that this second level. of voltage protection shall satisfy the following criteria:
a) The selection of.voltage and time set points shall be.
determined from an analysis of the voltage requirements of the safety~related loads at. all onsite system distri-bution.levels.
Response
Our letter serial number 197 /081276 dated November 3, 1976,
.thoroughly.describes the voltage protection.features employed.
We will.briefly summarize our system capabilities.
The emergency buses are fed from the Reserve Station Service Transformers which each have an automatic tap changing feature.
This tap changer is activated by a. change in output voltage of +/-1.25%
for greater *than *thirty* seconds at which time the tap changer changes in *increments of
- 625% .per second for* 16 steps. Thus, our first . level of protection protects the emergency buses, plus or minus 10%, around the normal line volt_age.
e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Edson G. Case Page No. 2 Our undervoltage detection and actuation is by coincidence logic of 2/2 relays per bus. The relays have LV coils which.have response characteristics as shown on the attachment. Therefore, even though the setpoint of diesel start at 84% of nominal voltage and of isola-tion from off-site power at 79.5% of nominal voltage occurs at 12 se-conds from the time of reaching.the setpoint, other conditions of.
undervoltage will also.be detected. For exi:i.ID.ple, on complete loss of voltage the* relays will trip in 1.2 seconds.
With these two levels of protection, the emergency bus is pro-tected at all points except for the range of 80-90% undervoltage.
However, our safety grade motors were all purchased to start *at 70%
of rated voltage and thus the motors*will all start and accelerate through the range of 80-90% of nominal voltage. If the transient de-graded voltage condition does not last longer than normal starting times (10~30 seconds) the motors will suffer no harm. Any longer period than that may b_egin to reduce their useful. life, but they still will respond as required during the postulated problem.
The vital buses are r_egulated to compensate for unusual volt_age conditions and the margin of setpoint charrge under the worst cases will.
be. minimal.
Another .level of disconnecting the en:e.rgency buses from the off-site power source occurs at 45.8% of nomin.il voltage as sensed on each of the transfer buses, the method of sensi~g is similar to that on the emergency buses.
Therefore, we consider our system to be in compliance with the intent of Staff Position 1. The attached proposed (for study only)
.Technical Specification change will place.our. Technical Specifications in compliance *.
2). Position 2:. Interaction of.Ortsite *Power Sources.with*Load Shed .Feature
Response
Our system does not have a.feature to load shed the ' emergency buses once.the onsite source is supplying power.
Therefore, we are in compliance with Staff Position.2 *.
.3) Position 3: Onsite Power Source Testing
- Response The full operability*at full.load of the on-site power source is tested per Technical Specification requirement monthly.
Our Technical Specification includes a.requirement for simulating
e VIRGINIA ELECTRIC AND POWE!i COMPANY TO Mr. Edson G. Case Page l'j'o. 3 loss of offsite power in conjunction with a safety injection actua-tion signal at each refueling. The high head and low head safety injection pumps are not started but the breakers are placed in test to preclude a RCS overpressure accident per a prior NRC commitment.
This serves the intent as the pumps are proved operable monthly and this test proves the starting sequencing during accident conditions and proper diesel loading. The difference in.diesel load is minimal as we have no load sequencer, and the other heavy loads are not start-ed immediately during a SI condition (containment spray and contain-ment recirculation spray pumps) but would be required later.
Therefore, the monthly testing proves the operability under full
.load of the onsite power source; the refueling testing proves these-quencing of diesel start and load; and the refueling testing proves the starting of required loads.
We are in compliance with the intent of Staff Position 3 except for interrupting the load on the diesel. As during emergency condi-tions our diesel is only protected by mechanical overspeed trip, we do not feel this test is appropriate nor do we believe that further trips 011 the diesel are proper during emergency conditions. Justi-fication for this load interruptiqn test is also minimal as we have no load sequencer or load shed feature on our onsite power source which could cause this postulated load interruption.
Therefore, we believe that we are in compliance with the full intent of Staff Positions 1, 2 and 3 as they apply to our facility.
Very truly yours,
,/ ' ;,,- *.
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'-=-' . --* !... ,, .-or.::..-,,... ,.,..'--- I C*. M. Stallings Vice President-Power Supply and Production Operations Attachments cc: Mr. James P. O'Reilly
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e e ATTACHMENT Proposed (for study only) Technical Specification Change for Surry Power Station T.S. 4,6 D Emergency Bus Undervoltage Detection
- 1. Tests and Frequencies.
The undervoltage relays on the emergency buses shall be checked each refueling to be.within the trip values stated below:
Functional Unit Trip Value (_allowable tolerance)
Loss of Power a) 4.16 KV Emergency bus 45.8% (~5.0, -5.0%)
(D,E,F) Undervqltage 12 Second delay (+/- 1.0 secon<l)
~Loss of Voltage) b) 4.16 KV F.mergency bus 80.5% (+5.0%, -5.0%)
(Il, J) Uuder--.;ol tagc 12 Second delay (1. 0 second)
(Degraded Vol~age)