ML22278A169
| ML22278A169 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/05/2022 |
| From: | Shell J Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 22-308 | |
| Download: ML22278A169 (9) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 5, 2022 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 Serial No.:
22-308 SPS-LIC/SCN: RO Docket Nos.:
50-280 50-281 License Nos.: DPR-32 DPR-37 ANNUAL SUBMITTAL OF TECHNICAL SPECIFICATIONS BASES CHANGES PURSUANT TO TECHNICAL SPECIFICATION 6.4.J Pursuant to Technical Specification 6.4.J, Technical Specifications (TS) Bases Control Program," Dominion Energy Virginia hereby submits changes to the Bases of the Surry Power Station TS implemented between October 1, 2021, and September 30, 2022.
Bases changes to the TS that were not previously submitted to the NRC as part of a License Amendment Request were reviewed and approved by the Facility Safety Review Committee (FSRC).
It was determined that the changes did not require a revision to the TS or operating licenses, nor did the changes involve a revision to the Updated Final Safety Analysis Report (UFSAR) or Bases that required Nuclear Regulatory Commission (NRC) prior approval pursuant to 10 CFR 50.59.
These changes have been incorporated into the TS Bases. A summary of these changes is provided in Attachment 1.
TS Bases changes that were submitted to the NRC for information along with associated License Amendment Request transmittals, submitted pursuant to 1 0CFR50.90, were also reviewed and approved by the FSRC. These changes have been implemented with the respective License Amendments.
A summary of these changes is provided in Attachment 2.
Current TS Bases pages reflecting the changes discussed in Attachments 1 and 2 are provided in Attachment 3.
Serial No.22-308 Docket Nos. 50-280, 50-281 Page 2 of 3 If you have any questions regarding this transmittal, please contact Stephen C. Newman, Surry Power Station Licensing Group at (757) 365-3397.
Sin~~
James D. Shell Director Station Safety and Licensing Surry Power Station Attachments:
- 1. Summary of TS Bases Changes Not Previously Submitted to the NRC
- 2. Summary of TS Bases Changes Associated with License Amendments [none]
- 3. Changed/Current TS Bases Pages Commitments made in this letter: None
cc:
U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue NE Suite 1200 Atlanta, GA 30303-1257 State Health Commissioner Virginia Department of Health James Madison Building - 7th Floor 109 Governor Street Room 730 Richmond, VA 23219 Mr. J. Klos NRC Project Manager - Surry Power Station U.S. Nuclear Regulatory Commission Mail Stop O 9E 3 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mr. G. E. Miller NRC Senior Project Manager - North Anna Power Station U. S. Nuclear Regulatory Commission Mail Stop O 9E 3 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Surry Power Station Serial No.22-308 Docket Nos. 50-280, 50-281 Page 3 of 3 Summary of TS Bases Changes Not Previously Submitted to the NRC Surry Power Station Units 1 and 2 Virginia Electric and Power Company (Dominion Energy Virginia)
Serial No.22-308 Docket Nos. 50-280, 50-281 Page 2 of 2 Technical Specifications Basis (TSB) Change Request Number 472 As a clarifying enhancement, this TSB change revised the Bases for TS 3.4 and TS 3.8 to increase the containment depressurization profile following a Loss of Coolant Accident (LOCA) and was a follow-up activity associated with previously implemented Technical Specification Amendments (TSA) 306/306. TSA 306/306 updated the LOCA alternate source term radiological dose analysis bases to increase the assumed containment depressurization profile and to reduce refueling water storage tank backleakage in support of the low-head safety injection net positive suction head margin recovery effort and the chemical addition tank removal project.
Summary of TS Bases Changes Associated with License Amendments
[NONE]
Surry Power Station Units 1 and 2 Virginia Electric and Power Company (Dominion Energy Virginia)
Changed/Current TS Bases Pages
[TS Bases pages 3.4-3 and 3.8-5]
Surry Power Station Units 1 and 2 Virginia Electric and Power Company (Dominion Energy Virginia)
Serial No.22-308 Docket Nos. 50-280, 50-281 Page 2 of 3 TS.1.4-~
07-05-22 The spray,ystems in each n~uctor unil consist <:if lwo sepamte parallel Containment Spray Subsystems. each of I<X) percent capacity, and four separate parallel Redrculation Spray Sut>s.y:i-tcms. each of 50 percent cap;rity.
Each Containment S(lfay Subsystem draws waler indef.('.ndently from the refueling waler s.tomge Lank {R:WST). The water in the tank is cc<:>kd to 45°1: or below by circulatin~ tile wat,:r thmugh Ollie of th,: two R \\VST nmkrs with one of th,: two n.-circulating pumps.. Tb,:
water tempcruture is mwntaint'd by two mechanical rcfri~ernting units us required. In tach Containmcm Spray Subsystem, I.he water lfows from lhe tank through an electric motor drivr:n rnntu.inmcnl spray pump and is spmyt'1:l into the containment a.tmm.pherc thrnugh two,epu.mte set! of spray 001.1:les. The capudty of the,pray ;ys.lems tc, dcpri.-ssurizc tbr:
ccmtainment in the,:vent of,1 Design Bu.sis Accident is n function or tht pressure Ulld temperature <if the nmtainment 11tmospherc. the s,:r\\'ice water tempemture, and the t,:mpr:raturr: in tht refueling water storage lank as discussed in the Basis or Spcdflcalion JX Each lkcirculation Spray Subsyslt.'111 draws water from the common comuinment sump. In each suhsy,tem the water t1ows lhrnug.h u ri:circulation ;pmy pump Ulld ri:circulation spruy cool.er. :md is spray,:d into the rnntajnment atmosphere thmug.h a sepurale set of spray nm:l.lr:s. Two of the rt."Circuli!!ion spruy pumps ure locaLL'3/4I insidr: tht: containm!.'nl and two outsidr: thr: containment in tile contwnmr:nt auxilia.f)' s;tructure.
With one-Contaimnr:nt Spray Subsyi;tr:m and two lk,;:irculutim, Spra.y Subsystemi.
opemting together. the spray systems,1rr: capabk of cooling and deprcssurizing th,:
cm,tainmr:nt to :!.O psig in less than 60 minutes und tu suhatmosphC"ric pressure within
<7, fmurs foll.owing the Design Basis Accident. Thi: R:1.,,::in:ula1ion Spray Subsysttm~ ari:
ca.pa.bk of maintaining ~ubaini,;).sphtric PfL'SSU re in the conta.inmi:nt i 11,;klinitely following the Di:s.ign Hasis Acd:knt when usL-d in rnnjunctiDn with the Containment Vacuum System to remove any kmg term air inkukage. The radiological consequr:ncts. u.nulysis dem,:mstrates acceptahle results pn:)\\'idL'd th,: containmr:nt prr:ssurc does not exctcd 2.0 psig (from I h-:mr tL1 o hours*) and is maintuin,:d !es~ thllll 0.0 psig (ufter t.:, hour!-1.
Serial No.22-308 Docket Nos. 50-280, 50-281 Page 3 of 3 TS 3.8-5 07-05-22 lfthic contllinmc-nl air partial pressure rises to a r,:)inl above the allowable yalue the reactor shall be bmughl to the HOT SHUTDOWN rnnditfon. lf a LOCA <xcurs at the tim!:' th!:'
conlainmc-nt air partial r,rcssure is at the milXirnum allowable value, the maximum containment pressure will be !t:ss than design pressure 145 psigJ. the containment will deprcs.s.uri1.c to 2.0 psig within I hour and less than 0.0 psig *,vithin 6 houri-. The radiological nrnsc-qucnccs analy!-i.s. demon~trntes ai:ceptabli: results provided the containmt'flt pressure does 11nt exceed 2.0 pE-ig for lhc interval from I to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following the Dcs.ign Basis Accident.
If the rnotainment air partial pressure cannot be maintained greater than or equal Lo the minimum pr1.':-lsurc in Figure J.8-1. the reactor shall be brought lo Lhi: HOT SHUTDOWN condition. Thie shell and <.1-,;:.mi: plate liner or thr-containment are capable of with!itunding un internal prer--sure as low as J p!-i;L and the hottmn maL liner is capable of withslumling, an internal prer--sure a-.; I DW a,; 8 psia.
References UFSAR St-ction 4.2.2.4 lkaclor Cnolant Pump UFSAR St-,;:tion 5.2 UFSAR St.'Ction 5.2.1 Design Hll.Ses UFSAR St.'Ction 5.2.2 UFSAR St-ctilln 5.3.4 Containment Vacuum Syskm