Text

Amends 159 & 140 to Licenses NPF-4 & NPF-7,respectively, Revising Current NA-1&2 TS to Ensure That Design Basis Met for Component Cooling Water Sys
	ML20096H541
Person / Time
Site:	North Anna
Issue date:	05/12/1992
From:	Berkow H; Office of Nuclear Reactor Regulation
To:	;
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ML20096H545	List: ML20096H541; ML20096H556;
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	NUDOCS 9205270281
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UNITED STATES o

3 1-NUCLEAR REGULATORY COMMISSION i

W4SHINoToN, D.C. $0066 4

VIRGINIA ELE {J.Ric AND POWER COMPANY OLD DOMINION.UEJRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT NO. 1

'I AMEN 0 MENT TO FACILITY OPERATING LICENSE i

Ainendment No.159 License No. NPF-4 q

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The Nuclear Regu16 tory Commission (the Commission) has found that:

A.

The application for amendrent by Virginia Electric and Power Company et al., (the licensee)irements of the Atomic Energy Act of 1954, as dated November 7, 1991, complies with the standards and requ amended (the Act), and the Commission's idles and regulations set forth in 10 CFR Chapter I;

8. --The facility will o)erate in conformity with the application,

.the provisions of tie 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 safetyTof the public, and (ii) that such activities will be conducted r

in compliance with the Commission's regula,tions;

- 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.

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Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.0.(2) of Facility Operating License No NPF-4 is hereby amended to read as follows:

(2) Itchnical Stecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 159, are hereby incorporated in the 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 30 days.

F HE NUCLEAR REGULATORY C0KMIS$10N

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ertN.Berkow,!'irector

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D Project Directorate 11-2 Division of Reactor Projects - I/11 Office of Nuclear Reactor Regulation

Attachment:

Chenges to the Technical Specifications Date of Issuance: May 12, 1992 l

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ATTACHMENT TO LICENSE AMENOMFIT NO. 159 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed ) ages as indicated. The revised pages are identified by amendment num)er and contain vertical lines indicating the area of chtnge.

The corresponding overleaf pages are ;lso provided to maintain document completeness.

Remove Elag.1 Inser1 Eingi 3/4 7-17 3/4 7-17 3/4 7-17a 3/4 7-18*

3/4 7-18*

B 3/4 7-4 8 3/4 7-4

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Ther) are no change; to this page.

It is-included to maintain document completeness.

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PLAT (T SYSTDAS T4.73 COMPONENT COOUNG WATER SYSTEM T4.731 COMPONENT COOUNG WATER SUBSYSTEM OPERATING UMTTING CONDITON FOR OPERATION 3.7.3.1 Three component cooling water subsystems (shared with Unit 2) shall be OPERABLE' with each subsystem consisting of:

a. One OPERABLE component cooling water pump and,

b. One OPERABl.E component cooling water heat exchanger.

APPUCAE M :

Elther Unit in MODES 1,2 '3, or 4.

ACTION:

a. With one required component cooling waL, subsystem inoperable, return the component cooling subsystem to OPERABLE status within the next 7 days, or place both units in HOT STANDDY within the tiert 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. With two required component cooling water subsystems inoperable, place both units in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and within the next hour, initiate actions to place both units in COLD SHUTDOWN and continue until COLD SHUTDOWN la schiwcd.

c. With no component cooling water avallable to supply the residual heat removal heat exchangers to cool the units, place both units in HOT SHUTDOWN vithin the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and remain in HOT SHUTDOWN until a!!emate means of c,ecay heat removal c.in be implemented. Continue actions until both units are in COLD SHllTDOWN.

SURVEILLANCE REQUIREMENTS m

4.7.3.1 Three component cooling water subsystems shall be demonstrated 0125RABLE:

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a. At least once per 31 days by verifying that each vatve (manual, power operated or automatic) servicing in the flow path of the residual heat removal system that l

Is not locked, sea!ed, or otherwise secured in position, is in its correct position.

b. Eich component cooling water pump shall be 19sted in accordance with Specification 4.0.5.

For the purpose of this Technical Specification, each suasystem is considered OPERABLE if it is operating or if !! can t:e placed in service from a standby condition by manually unisolating a standby heat exchanger and'or mar, ally starting a standby pump.

NORTH ANNA - UNIT 1 3/4 7 17 Amendment flo, 159

PLANT SYSTEMS 3/4 7.3 COMPONENTCOOUNGWATEF SYSTEM 1/4.712 COMPONENT COOUNG WATEA SUBSYSTEM SHUTDOWN UMITING CCNDIT10N FOR OPERATION L

3.7.3.2' Two component cooling water subsystems (shared with Unt' 2) shall be OPERABLE' with each subsystem consisting of:

a. One OPERABLE componont cooling water pump and.

It One OPERABLE component cooling water heat exdianger.

APPLICABluTY:

Both Units in MODES S or 6.

AC.IKE With one requir6d component cooling water subsystem inoperable, immediately suspend all operatiens involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System.

SURVEldANCE REQUIREMENTS 4.7.3.2 At least two component cooling water subsystems shal be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each vake (manual, power operated or automatic) the flow path of the residual heat removal system that is not locked, sealed, or otherwise aecured in position, is Irt_Its correct position, b.

Each component cooling water pump shall be tested in accordance with Specification 4.0.5.

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For the purposes of this Technical Specification, each subsystem is considered OPERABLE if it is o,:arating or if it can be placed in service from a standby condition by manually unisolating a standby heat exchanger and/or manually starting a standby pump, w

NORTH ANNA UN!T 1 3/4 717a Amendment No'.159, y

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PtM SYSTEMS 34.7.4 GERVICE WATER SYSTEM 32414.1 SERVICE WATER SYSTEM. OPERATING UMITN3 CONDmON FOR OPERATON a-3 3,7.4.1 Two service water bops (shared with Unit 2) shall be OPEP ABLE wtth each loop consisting of:

a. Two OPERABLE seMee water pumps (exduding auxillary service wt'ar pumps) with their associated normal and emergency power supplies, and

b. An OPERABLE fbw path capable ;f providing cooling for OPERABLE plant components and transferring heat to the service water reservoir.

APPUCABILTTY:

Elther Unit in MODES 1,2,3, or 4 t

ACT1CN:

a. With one service water pump inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months throttle component coolin water heat exchanger fbws, in accordance whh approved cperating proceusres, to ensure the remaining service water pumps are capable of providing adequate flow to the recirculation spray heat exchangers,

b. With two service water pumps inoperable, perform ACTION 3.7.4.1.a within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months aM restore at least one service water pump to OPERABLE status wtthin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or ptsee both units in HOT STANDBY within the next six tours and in COLD SHUTDOWN within the lollowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With one service water bop inooerable, except as provided in ACTION 3.7.4.1.a.

restore the inoperable loop to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or place both unhs in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d. The allowable t!me that one of the two service water loops can be inoperable as l

speelfled in ACTION 3.7.4.1.c may be extended beyond 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months up to 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months as part of service water system upgradas' provided 3 out of 4 service water pumps (the third pump does not require auto start capability) and 2 out of 2 auxiliary service water pumps have been OPERABLE sinoe inliial entry into the l

action statement and remain OPERABLE during the extended act% statement or l

be in it least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTOOWN l

within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

lsolation of one service water bop for up to 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months is permitted only as part of service water system upgrades. System worades include modincatbn and maintenance I

sctivhles associated with the installation of new @ charge headers and spray arrays, mechanical and chemical cleaning of service water piping and vanes, pipe repair and replacement, valve repair and replacomc 11, installation of corrosion mitightlon mensures and inspectbns of and repairs to buried piping interior costings and pump or l

vake house componwnts.

l NORTH ANNA. UNIT 1 3/4 7 18 Amendnent No. 3,57,70,152 i

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PLANT SYSTEMS _

BASES available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350 F when the Residual Heat Removal System may be placed into operation.

3/4.7.1.3 EMERGENCY CONDENSATE STORAGE TANK The OPERABILITY of the emergency condensate storage tank with the rinimum water volume ensures that sufficient water is available to maintain the RCS at H0T STANDBY conditions for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months with steam discharge c

to the atmosphere concurrent with total loss of off-site power. The contained water volume limit includes an allowance for water not usuable because of tank discharge line location or other physical characteristics.

3/4.7.1.4 A gT,I_VITY Tne limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture.

This dose also includes the effects of a coincident 1.0 GPM primary to secondary tube leak in the steam generator of the affected steam line.

These values are consistent with the assumptions used in the accident analyses.

3/4.7.1.5 MA!N STEAM TRIP VALVES The OPERABILITY of the main s'eam trip valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture.

This restriction is required to 1) minimize the positive reactivity effects of tne Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs within containraent.

The OPERABILITY of the main steam trip valves within the closure times of the surveillance requirements are consistent with the assumptions used in thc accident analyses.

NORTH ANNA - UNIT 1 B 3/4 7-3 Amendment No.16

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PLANT SYSTEMS E%SES L Cl 3 and 3 '41 L2, STEAM TURBINE and OVEPEPEED PAOTECT!ON The turbine generator at the North Anna facility is arranged in a nonpeninsular Ana!ysis has shown that this arranger ent is such tha if a turbine failure occurs as orientation.

a result of destructive overspeed, potentially damaging missles could impact the auxiliary budding, containment. control room and other structures housing safety related equipment. The requirements of these two specife,ations prNide additional assurance that the facility will not be operated with degraded valve performar.ce anci'or flawed turbine matenal which are the md}or Contributors to turbine failures.

3'412 STEAM GENEAATOR PRESSUr4E/TEMPERATUAE LIMITATION The 'im<tation on steam generater pressure and temperature ensures that the pressure induced stresses in the steam genstators do not exceed the max. mum allowable fracture tought:ess stress limits. The limitations of 70'F and 200 psig are based on average steam generator impact values at 10'F and are sufficient to prevent brittle fracture.

3'4 7 31 COMPONENT COOLING WATER SUBSYSTEM OPERATING The component cool:ng water system normally cperates continuously to remove heat from various plant com?onsnts and to transfer the heat to the service water system. The system consists of four subsystems shared between units, with each subsystem containing one pump and one heat exchanger, The current design basis for the component cooling water system is a fast cooldown of one mt while maintaining normal loads on the otheir unit. Three component cooling water Jbsystems need to be OPERABLE to accomplish this function. The fourth subsystem is a spare and may be out of service indefinitely. With only two component cooling water subsystems a slow cooldown on one unit while maintaining normalloads on the opposite unit can be accomplished.

The comoonent cooling water system is designed to reduce the temperature of the reactor coo! ant system from 350*F to 140'F within 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months dunng plant cooldown, based on a service water temperature of 95:F and on having two component cooling water pumps and two heat exchancers in service for the unit being cooled down. Therefore, to ensure cooldown of one unit within 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months and maintain the other unit in normal full power operation three of the four subsystems must be OPERABLE.

Because subsystems are placed in standoy by shutting down pumps and isolating heat exchangers and this system serves no accident mitigation functions, the subsystem is considered CPER ABLE in the standby Conditions since it can be easily placed in service quickly by manual operator actions.

3 C 3 2 COM NENT COOLING WATER SUBSYSTEM SWUTDOWN The OPERABILITY of the Component coonng water system when both units are in COLD SHUTDOWN or REFUELING ensures tnat an atecuate heat sink is maintained for the residual heat removal system NORTH /sNNA UNIT 1 B34 74 Arnendment No. 75,152,159,

ML20096H541

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