ML082620181
| ML082620181 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/09/2008 |
| From: | Stang J Plant Licensing Branch II |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| Lingam, Siva NRR/DORL 415-1564 | |
| References | |
| TAC MD7242, TAC MD7243 | |
| Download: ML082620181 (20) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 9, 2008 Mr. David A. Christian President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING LCO 3.8.7 AND 3.8.9, SHARED COMPONENTS (TAC NOS. MD7242 AND MD7243)
Dear Mr. Christian:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 253 and 234 to Renewed Facility Operating License Nos. NPF-4 and NPF-7 for the North Anna Power Station, Unit Nos. 1 and 2. The amendments change the Technical Specifications (TSs) in response to your application dated October 24, 2007, as supplemented August 7, 2008.
These amendments revise TS Limiting Conditions for Operations 3.8.7 and 3.8.9 to address shared component operability on the opposite unit for the Emergency Core Cooling System Pump Room Exhaust Air Cleanup System.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, ~
J n Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339
Enclosures:
- 1. Amendment No. 253 to NPF-4
- 2. Amendment No. 234 to NPF-7
- 3. Safety Evaluation cc w/encls: See next page
North Anna Power Station, Unit Nos. 1 and 2 cc:
Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO.1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 253 Renewed License No. NPF-4
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et aI., (the licensee) dated October 24, 2007, as supplemented August 7, 2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-4 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 253
, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1t(t~ C.lJ41vf Melanie C. Wong, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-4 and the Technical Specifications Date of Issuance: October 9, 2008
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO.2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 234 Renewed License No. NPF-7
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et aI., (the licensee) dated October 24, 2007, as supplemented August 7, 2008, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-7 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 234
, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/(J\\-efeu.tu ( Id{ 0 Melanie C. Wong, Chie~
Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-7 and the Technical Specifications Date of Issuance: October 9, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 253 RENEWED FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 AND TO LICENSE AMENDMENT NO. 234 RENEWED FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Licenses and the Appendix "A" Technical Specifications (TSs) with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Pages Insert Pages Licenses Licenses License No. NPF-4, page 3 License No. NPF-4, page 3 License No. NPF-7, page 3 License No. NPF-7, page 3 TSs TSs 3.8.7-1 3.8.7-1 3.8.7-2 3.8.9-1 3.8.9-1 3.8.9-3 3.8.9-3
- 3*
(2)
Pursuant to the Act end 10.CFA Part 70. VEPCO 10 racelole, possess, and use at any dm8 specIaJ l1uaear material as reactorfuel, In accordance PAth the nmnaUons for 51013(18 Bnd amounls required for reaolor operatlon,.1IS desafbed rn the Updated FInl!I Safety Analylls Repor1:
(3)
Pursuant 10 the Ad and 10 CFR Par1s 3D. 40, end 70, VEPCO CD receive.
possess, 811d USe It 8l1Y Pme any byproduct. soun:e, IIJId spedal nuclear material as selled neutron 1D\\ICeS far reactor slaJ1Up. sealed SDUICeS for re.ctor InstrumenlaUon and raclaUan monnomg equlpmenl caDbralJon, and as fission ~"dcn.1n ~ ~ required;'
(4)
PUI3uant 10 the Ad IIid 10 CFR Pens 30. 40; and 70, VEPCO to receIVe, pcuess. and till kl arnaunEs..hlquJred any byproduct, 1OUIC8, Of.
&pedal nudel' malerlal, without restltclfon 10 chemical or physIcal form, for sample anaIyfll or InItlUMlnt cdJwatlcn Dr assoclatad with rudloacUve epparetus or component: and (5)
Pursuant to the Ad and 10 CFR PIU1S 80 and 70, VEPCO ID possess, bill not separate, such byproduc:I and Special nuclear materials as may be pl'Oduced by 1h8 gperallon of Ihe faclB\\y.
- c.
ThIs renewed qJeratlng lcensl _haD be d.smed 10 conilln and Is subject 10 !he ClOrdions speetned In'lhefo/lQwlng' COrnmJulon I1lgulalJons In.
10 CFR.Chapter I: Part 20, S8cUon 30.34 of Part 3D, Section 40.41 of Part 40.
8ectlons 50.54 and 80.59 of PIIIt SO, end SlClIon 70.32 01 Part70; Is subject to
..appDc8b1e provlsfons of the Acllll1d 191h. !'JIll. regulations, and ciidell.of the CorM1fsslon now or here.afler In e"eel; snd IS subject to the IIddillonaI c:ondlllonS
~e~d CII' 1ncorporated below:
(1)
~xlmtm PoWMI.evII VEPCO rsaulhoJlzed to operate Ole NOIth Anna Power SlallDn, URll No.1, at reBGfDr care.power levelll not In excelS 012883 megawalls
. (thermal).
(2)
Tech.' SpeclUc8110ns I
111. Technlcals.,er.llcallans conlalned InAppe~~ A. as revlsed'ihro~gh Amendment No. 253ere hereby Incorporaled In the renewed Dcense.
Thitlcensee IhiB operate the faclllly rn accordance wI1h the TechnIcaJ
. SpeciDcaUDns., '.
I Renewed lICense No. NPF-4 A.endment No~253
-3 (3)
PUl1luant 1o.1h' Act and 10 eFR Parts 30.40. ind 70. VEPCO 10 receive.
possess.*and use el any.lime any byproduct, source. and.pedal nuclear material 8I18-"d ne~on IOUrcllfor relCtOlltartup,.....d&OUIC81 'or ruetor In&trumenlalon end radlallon montorfng 8q~ c:dbrallon, and as fllsIon deledOR... ImounIB u requ".dj
(.c)
Pursuant 10 the Act and 10 eFR PalU30, 40, and 70, VEl'CO 10 recelva, possess, Ind use In emounli is,.qubd any byprDlb:t, 1aUn:I, or apllCla' nudeat maI./fIJ, wIIhout restJIcIIori to chernlcBJ fX ph)'llcal 'onn, tDr umple anslyals or lnIIrumena cdnlJon Dr.,sodatedwIh" radioactive IIppU8tua Of c:ampanentr, and (5)
PurSuant 10 the Act and 10 CFR P.rla 30, 410. lind 70,VEPCO to POsSI", but nol.1Ip.....,.uch b)'product end speclll nuclearmat.dals u may.b, plDlilced by 1111 cpe..1Ian or Ihe facllllr.
C:
ThIs renewed lIc8nse IhaI be deemed ID Cl)nIaJn and Is SubjlCl io Ihe cXmdtaoN cpedllec;t In the Comm1uIon'& rtguill/ons II.e' fDlth In 10 OF.R eMpIer 1and Is IUbJect 10 all appbbl. provtllons oIlhe AtA.~ 10 Ihe ruIei, reguIdonI, and '
od... 01 the CornmIubn now or he".',.r... eHeet and...ubJ-c:t 10 1M IddillonaJ condtJonIspecllJed or lnc:orparaled below:'
(1)
MaxImum Ppwtr lIV.'
VEPCO II autholtzad 10 ape,.18 lIle tacIIIl)' al IlBadrnil rellClDr core power IIMIs not '".,.11 of 2893 megaWlllts (""nnaIJ.
- 12)
ItChnICl' ".!ft:aUpO!
111, Techn1cli1 epedDJ:llon& conllNd In Appaildbt A. u""'ltnugh. I Amendment Na234 e,. hereby ~o,.t..~ In &h...UWlId license.
111-.1Ice"..**hllA aparallt IhIt 'Bc:IIIly In BClCGrctanc:.I wfIh....TedInfca..
8pecIRcadon..
(3)
.AddjIIejo,1 pgodb!n.
The made,..ep.clfftd rn 1118 foflowII.18 condlUDns... be CDmpIele4 to 1h...UlfacIIon of Ihe CommIuIan wRhIn the IWIIId line"'".
follovMg IhIlsIuancl 0181. r:DDdIIon Dr wIthh.1hI apnInI resIrfcIJonI n_led. The rwnovaI allblle candIIJonIlhd bell18d9 by an amendmtnt ~ the ren_wed IJcenu lupported try. favrnble evaluaUon by the CommIssIon:
"~._"n
- e.
If VEPCO plan. to J1lmove or 10 moe s/gnlJlc:&nt c:hanPs In the noriJaJ operaUon of equlpmenl thai ~ the IUIJO\\I1I at radlDaclMly In.muenls from the North Anna POWIr stallon, Ihe
.I.
Renewed ~No NPF-7.
". I:lDendlint "0.234
Inverters-operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Inverters-Operating LCO 3.8.7 The following inverters shall be OPERABLE.
- a. The Train Hand Train J inverters; and
- b. The necessary inverters on the other unit for each required shared component.
- - - - - - - - - - - - NOTE - - - - - - - - - - -
One inverter may be disconnected from its associated DC bus for S 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform an equalizing charge on its associated battery. provided:
- a. The associated AC vital bus is energized from its constant voltage source transfonner; and
APPLICABILITY:
MODES 1. 2. 3. and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One inverter required by LCD 3.8.7.a inoperable.
A.l
NOTE-------
Enter applicable Conditions and Required Actions of LCD 3.8.9, "Distribution Systems-Operating" with any vital bus de-energized.
Restore inverter to OPERABLE status.
7 days North Anna Units 1 and 2 3.8.7-1
3.8.7 Inverters-operating ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.
One or more inverters required by LeO 3.8.7.b i noperabl e.
B.l
NOTE-------
Enter applicable Conditions and Required Actions of LCO 3.8.9.
"Distribution Systems-operating" with any vital bus de-energ; zed.
Declare associated shared components inoperable.
7 days C.
Required Action and associated Completion Time of Condition A not met.
C.1 AND Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> C.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEI LLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage and 7 days alignment to required AC vital buses.
North Anna Units 1 and 2 3.8.7-2
Distribution Systems-operating 3.8.9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems-Operating LCO 3.8.9 The following distribution subsystems shall be OPERABLE:
APPLICABILITY:
MODES I, 2. 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more LCO 3.B.9.a AC electrical power distribution subsystem(s) inoperable.
A.I
NOTE-------
Enter applicable Conditions and Required Actions of LCO 3.8.4, "DC Sources-operating, II for DC train(s) made inoperable by inoperable distribution subsystem(s).
Restore AC electrical 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> power distribution subsystem(s) to OPERABLE status.
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from discovery of failure to meet LCO North Anna Units I and 2 3.B.9-1
Distribution Systems-Operating 3.8.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F.
NOTE---------
Separate Condition entry is allowed for each AC vital subsystem.
One or more required LCO 3.B.9.b AC vital electrical power distribution subsystem(s) inoperable.
F.l Declare associated shared components inoperable.
Irrmediately G.
Required Action and associated Completion Time for Condition A, B, or C not met.
G.1 AND Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> G.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> H.
Two or more LCD 3.B.9.a el ectrical power distribution subsystems inoperable that result in a loss of safety function.
H.1 Enter LCD 3.0.3.
Irrmediately SURVEILLANCE REQUIREMENTS SURVEI lLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to required AC. DC. and AC vital bus electrical power distribution subsystems.
7 days North Anna Units 1 and 2 3.8.9-3
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 253 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-4 AND AMENDMENT NO. 234 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-338 AND 50-339
1.0 INTRODUCTION
By letter dated October 24, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072980167), as supplemented August 7, 2008 (ADAMS Accession No. ML082210012), Virginia Electric and Power Company (the licensee) submitted a request for changes to the North Anna Power Station, Unit Nos. 1 and 2 (North Anna 1 and 2), Technical Specifications (TSs). The requested changes would revise TS limiting Conditions for Operations (LCOs) 3.8.7 and 3.8.9 to address shared component operability on the opposite unit for the Emergency Core Cooling System (ECCS) Pump Room Exhaust Air Cleanup (PREAC) system.
The supplement dated August 7, 2008, provided clarifying information that did not change the scope of the original application and the initial proposed no significant hazards consideration determination.
The proposed changes would ensure that the TSs for both units reflect the dependency of shared components of the ECCS PREAC system fed from the 120 V AC Inverters of the opposite unit.
2.0 REGULATORY EVALUATION
The Nuclear Regulatory Commission (NRC) staff used the following requirements and guidance documents during the review of the license amendment request (LAR):
Section 50.36(dX2), of Title 10 of the Code of Federal RegUlations (10 CFR), "Technical Specifications," requires a licensee's TSs to establish LCOs for equipment that is required for safe operation of the facility.
Appendix A of Part 50 of 10 CFR, General Design Criterion (GDC) 17, "Electric power systems,"
requires, in part, that nuclear power plants have onsite and offsite electric power systems "to permit the functioning of structures, systems, and components that are important to safety. The
- 2 onsite system is required to "have sufficient independence, redundancy, and testability to perform its safety function, assuming a single failure." The offsite power system is required to be supplied by two physically independent circuits that are "designed and located so as to minimize, to the extent practical, the likelihood of their simultaneous failure under operating and postulated accident and environmental conditions." In addition, this criterion requires provisions "to minimize the probability of losing electric power from the remaining electric power supplies as a result of' loss of power from the unit, the offsite transmission network, or the onsite power supplies.
GDC 18, "Inspection and testing of electric power systems," requires that electric power systems that are important to safety must be designed to permit appropriate periodic inspection and testing.
3.0 TECHNICAL EVALUATION
3.1 Description of the ECCS PREAC System (As stated by the licensee)
The Safeguards Area exhaust flow and Auxiliary Building Central Exhaust subsystem flow, when actuated, diverts flow through the auxiliary building HEPA filter and charcoal absorber assembly for the operating train. In case of a DBA [design-basis accident]
requiring their use, auxiliary building central exhaust flow is diverted manually through the filters and the safeguards area exhaust can be diverted manually as a backup feature to the required automatic realignment function.
Emergency Core Cooling System (ECCS) Pump Room Exhaust Air Cleanup System (PREACS) includes both the Safeguards Area exhaust subsystem and the Auxiliary Building Central exhaust subsystem. Following an accident, the Safeguards Area exhaust subsystem is automatically aligned to the auxiliary building filter banks upon a CDA
[containment depressurization actuation] signal, and the Auxiliary Building Central exhaust subsystem is manually aligned to the filter banks by post-LOCA [Ioss-of-coolant accident]
emergency procedures...The Safeguards Area exhaust subsystem may be manually aligned to the filter banks if needed using control switches on the associated unit's Control Room Ventilation Panel.
Two trains of electrical control circuits powered by the alternate current AC [alternating current] vital buses are required to maintain operability of the Auxiliary Building Central exhaust subsystem filter and bypass dampers. One circuit is associated with the manual control switch on the Unit 1 Ventilation Panel and is powered from Vital Bus 1-1 via inverter 1-1. The other circuit is associated with the manual control switch on the Unit 2 Ventilation Panel and is powered from Vital Bus 2-111 via inverter 2-1/1. Either circuit will realign all dampers to the filter position. As currently written, the LCO [3.8.7 and 3.8.9] does not address shared components on the opposite unit's AC vital bus. Loss of either Vital Bus 1-1 or Vital Bus 2-111 will result in the loss of the associated control circuit; and, therefore, loss of one of the two required trains of ECCS PREACS. Revision of the TS LCOs will ensure that proper consideration is given to the effect that the loss of a vital bus or inverter has on both units.
The licensee stated that "the two trains of controls for the auxiliary building central exhaust subsystem filter and bypass dampers consist of the following:"
-3 a) "There are two trains of electrical control circuits. One circuit is associated with the manual control switch on the Unit 1 Ventilation Panel and is powered from Vital Bus 1-1." This circuit provides power to solenoid valves SOV-HV-103-1A and 1B (controlling dampers AOD-HV-103-1/2/3/4). "The other circuit is associated with the manual control switch on the Unit 2 Ventilation Panel and is powered from Vital Bus 2-111." This circuit provides power to solenoid valves SOV-HV-103-2A and 2B (also controlling dampers AOD-HV-1 03-1/2/3/4). The licensee stated that "either circuit realigns all associated dampers to the filter position." Loss of power to one train of solenoid operated valves (SOVs) (either SOV-HV-103-1A and 1B, or SOV-HV-103-2A and 2B) prevents operation of air-operated dampers AOD-HV-103-1/2/3/4 for the auxiliary building central exhaust.
b) There are two trains of air supplies. The licensee stated that "one supply is from air accumulator 1-IA-TK-1 03A and supplies 1-HV-AOD-1 03-2 and 103-4. The other supply is from air accumulator 1-IA-TK-103B and supplies 1-HV-AOD-103-1 and 103-3. Either supply will realign one filter damper and one bypass damper to prevent unfiltered release (either of the two supplies may be used with either ECCS PREACS train). Either instrument air or both air accumulators are required for manual filtration alignment one-hour after the accident...The dose analyses for a LOCA require the auxiliary building central exhaust subsystem to be manually aligned to the auxiliary building charcoal filter banks within 60 minutes following the accident. To perform this post-accident function, either one of the two electrical control circuits, and either one of the two trains of air supplies are required."
The licensee stated that "in order to ensure that the sUbsystem remains single failure proof and can perform its intended safety function when called upon to function," the proposed TS revisions "clarify the operability requirements of the inverters and vital busses" as they support the operability of the shared components of the ECCS PREAC system.
3.2 Evaluation of Proposed Change 3.2.1 LCOs 3.8.7 and 3.8.9 Changes The licensee identified that presently TSs do not clearly address the condition of an operating unit with a required shared component powered from a shutdown unit's 120 volt vital AC bus when the associated inverter is inoperable. This condition is present when Unit 1 is operating with Unit 2 shutdown and the 2-111 inverter is removed from service (one train of PREAC system SOVs is powered from the 2-111 vital bus) or Unit 2 is operating with Unit 1 shutdown and inverter 1-1 is removed from service (one train of PREAC system SOVs is powered from the 1-1 vital bus).
In the LAR dated October 24, 2007. the licensee proposed to revise TS LCOs 3.8.7 and 3.8.9 for North Anna 1 and 2. The proposed changes reflect the dependency of the ECCS PREAC system on shared components powered by Units' 1 and 2 inverters and vital AC busses.
3.3 Summary The NRC staff evaluated the system functions described in the LAR, supplemental information submitted by letter dated August 7, 2008, and the Updated Final Safety Analysis Report to confirm the description of the ECCS PREAC system and its dependence'on shared components powered
-4 by inverters/vital AC busses from each unit. With the proposed changes to LCOs 3.8.7 and 3.8.9, the NRC staff determined that the TSs will now reflect the dependency of the ECCS PREAC system on the inverters/busses from both units, ensuring the ECCS PREAC system operability of either unit. Based on the NRC staffs review of the items listed above, it was confirmed that the proposed changes will not impact the electrical design of the ECCS PREAC system to provide sufficient independence, redundancy and testability to perform its safety function, assuming a single failure in accordance with GDCs 17 and 18.
Based on the above evaluation, the NRC staff finds the proposed revision to the North Anna 1 and 2 TSs will continue to provide reasonable assurance of the operability of the ECCS PREAC system in accordance with the requirements of 10 CFR 50.36 and GDCs 17 and 18. Therefore, the NRC staff finds the proposed changes acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Virginia State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (72 FR 71717). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Kenneth Miller, NRR Date: October 9, 2008