Text

Amends 152 & 136 to Licenses NPF-04 & NPF-07,respectively, Revising TS to Ensure Design Basis Is Met for Svc Water Sys
	ML20086L746
Person / Time
Site:	North Anna
Issue date:	12/13/1991
From:	Berkow H; Office of Nuclear Reactor Regulation
To:	;
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ML20086L749	List: ML20086L746; ML20086L760;
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	NUDOCS 9112170054
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'49.....g VIRGINTA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT NO. 1 AMENDMENT TO FACit1TY OPERATING LICENSE Amendment No. 152 License No. NPF-4 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated October 3, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities wi-' be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied, 9i12170054 911213 PDR ADOCK 03000338 P

PDR

e' 2-2.

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

(?) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.152, 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 the date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMt11SSION t rbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: December 13, 1991

4

.e ATTACHMENT TO LICENSE At!ENDMENT NO. 182 TO FACILITY OPERATING LICFilSE tIO. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are alto provided to maintain document completeness, pace F 7-18 3/4 7-18a (new) 3/47-18b(new)

B 3/4 7-4 8 3/4 7-4a(new)

B 3/4 7-4b(new)

PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SUBSYSTEM LIMITING _ CONDITION FOR OPERATION 3.7.3.1 At least two component cooling water subsystems (shared with Unit 2) shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With only one component cooling water subsystem OPERABLE, restore at least two subsystems to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at 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 SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.3.1 At least two component cooling water subsystems shall be demon-strated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position, l

NORTH ANNA - UNIT 1 3/4 7-17 i

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plANTSYSTB6 SM.7.4 SERVICE WATER SYSTEM 3Ad 7 d 1 RFRVICE WATER SYSTEM. OPEg

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3.75.1 Two service water loops (shared with Unit 2) shall be OPERABLE whh each loop consisting of:

a. Two OPERABLE service water pumps (excluding auxiliary servloe water pumps) with their associated normal and emergency power supplies, and

b. An OPERABLE flow path capable of providing cooling for OPERABLE plant components and transferring heat to the service water reservoir.

AEP.M.CABILITY:

Either Unit in MODES 1,2,3 or 4.

AGEE:

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 cooling water heat exchanger flows, in accordance with approved operating procedures, 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 and restore at least one service water pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or place both units in HOT STANDBY within the next six hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With one service water loop inoperable, except as provided in ACTION 3.7.4.1.a.

1 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 units in HOT STANDBY within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-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 time that one of the two service water loops can be inoperable as l

specified 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 servios water system upgrades

provided 3 out of 4 servios water pumps (the third pump does not require auto start capabluty) and 2 out of 2 auxillery servios water pumps have been OPERABLE since initial entry into the aallon statement and remain OPERABLE during the extended action statement or be in if least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in 001.D SHUTDOWN

~

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

i Isolation of one service water loop 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 upgrados. System upgrades inchde modAcetion and maintenance activities associadd with the installation of new discharge headers and spray arrays,.

mechanical and chemical cleaning of service water piping and valves, pipe repair and replacement, valve repair and replacement, installation of corrosion mitigation measures and inspections of and repairs to buried piping interior coatings and pump or l

wdve house components.

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NORTH ANNA-UNrT 1 3/4 7 18 Amendment No. 3.57;79,152

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l PLANTSYSTEMS 3/4 7.4 SERVICE WATER SYSTEM 3/4.7.4.1 SERVICE WATER SYSTEM OPERAT&lQ UMITNG CONDmON FOR OPERATON

e. With two service water loops Inoperable for reasons other than described in ACTION 3.7.4.1.b, place both units in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and within the following hour, initiate actions to place both units in COLD SHUTDOWN and continue actions until both units are in COLD SHUTDOWN.

SURVBU.ANCE REQUIREMENTS 4.7.4.1 At least two service water loops shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position,

b. At least once per 6 months by measurement of the rnovament of the pumphouse and wing walls,

c. At least once per 18 months during shutdown, by:

1. Verifying that each automatic valve servicing safety related equipment actuates to its correct position on an actual or simulated safety injection rignal.

2. Verifying that each automatic service water vane actuates to its mrrect position on an actual or simulated containment high high signal.

d. Each service water pump will be tested in accordance with Specification 4.0.5.

NORTH ANNA UNIT 1 3/4 7-18a Amendment No.152

- -__-______- - - __--______-______-_- _-__-_____---_-____- _ J__L

PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM 3/4 7 42 SERVICE WATER SYSTEM SHUTDOWN UMrTNG CONDmON FOR OPERATION 3.7.4.2 One service water bop (shared with Unit 2) tha!I be OPERABLE consisting of:

a. Two OPERABLE service water pumps (or auxiliary service water pumps) with their associated normal and emergency power supplies, and

b. An OPERABLE flow path capable of providing moting for OPERABLE plant components and transferring heat to the service water reservoir or, if using auxiliary service pumps, to the North Anna reservoir.

APPLICABILITY:

Both Units in MODES S or 6.

ACTION.

a. With only one service water pump OPERABLE, restore an additional service water pump to OPERABLE statas w! thin 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or immediately suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concer,tration of the Reactor Coolant System,

b. With no service water pumps OPERABLE, immediately suspend all operations invoMng an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System.

SURVEILLANCE REQUIREMENTS 4.7.4.2 At least one service water loop shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

b. At least once per 6 months by measurement of the movement of the pump house and wing walls,

c. Each service water pump will be tested in accordance with Specification 4.0.5.

l NORTH ANNA UNIT 1 3/4 718b Amendment No.152

T I

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.0PERABILITY of the emergency condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the-RCS at HOT STANDBY conditions for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months with steam discharge 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 ACT!VITY-

-The limitatiens 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 MAIN STEAM ~ TRIP VALVES-The'0PERABILITY of the main-steam trip valves ensures that no more than-one steam generan,r will blowdown in the event of a steam line rupture. This restriction is required to 1) minimize the positive reactivity effects-of the Reacto" Coolant System cooldown associated with-the blowdown, and 2) limit the pressure rise within containment in.the-event the' steam line rupture occurs within containment.- The OPERABILITY of ~ the main steam trip valves within the closure times of the surveillance requirements are consistent with the assumptions used in the

~.

accident analyses.

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

1 PvwrSYSTEMS IMSES 3/4.7.1.8 and 3/4.717 STEAM TURBINE and OVERSPEED PROTECTION The turbine generator at the North Anna facility is arranged in a nonpeninsular orientation. Analysis has shown that this arrangement is such that if a turbine failure occurs as a result of destructNe overspeed, potentially damaging missies could impact the auxiliary building, containment, control room and other structures housing safety related equipment. The

-requirements of these two specifications provide addlional assurance that the facility will not be operated with degraded vaNo performance arw1/or flawed turbine material which are the major contributors to turbine failures.

3/4.72 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generatora do not exceed the maximum ellowable fracture toughness 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 73 COMPONENT COOLING WATER SUBSYSTEM The OPERABlWTY of the component cooling water subsystem ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions.

1 1

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l NORTH ANNA-UNIT 1 B 3/4 7 4 Amendment No J$. 152

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7 E,J PLMSYSTEMS i

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3/d.7 d 1 RERVL^E WATER SYSTN. OPERATING j[

L The OPERABluTY of me service water system ensures that sufficient cooling capedty is available for safety related equipment during normal and sooident condtions. The system is designed to meet the assumption of a single failure. During a design basis socident, both loops of service water cross connect at the affected units recircu'ation spray heat exchangers to create a single large service water bystem. The affected units component cooling heat exchangers isolate so that sufficient flows are provided to both the non affected and affected units components. -

WHh four normal service water pumps OPEllABLE, the unthrottled flow resistance of the system is such that greater than design flows are ac*rved if a single pump or power supply tallure occurs following an socident. When three notmal service water pumps are OPERABLE, the flow resistance of the system.'s adjusted to ensure that design flows are achieved if a single

_ pump or power supply failure occurs following an accident. The required resistance is determined during periodic flow baianos testing and is obtained by thmit4ng flow through me component cooling water heat exchangers. Ramer than marking and specifying exact component cooling water heat exchanger outlet throttle vahre positions, operating procedures have been established to set system resistance at or greater than the required resistance. When only two l

normal service water pumps or a single loop are OPERABLE, the design basis function can sel he met provided met the flow resistance of me system is a4usted and no additional failures occur. The allowed outage time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is consistent with other LCOs tor loss of one train of ESF systems, and is based upon an industry accepted practice considering the low probability of e

an accident occuring.

if more than two normal service water pumps or both service water loops are inoperable, me units are not prepared to_ respond to the design bases events for which the servios water system is required. Both units must be placed in HOT SHUTDOWN within twelve hours and actions initiated within one hour thereafter to pleos the units in COLD SHUTDOWN.

Twelve hours is a reasonable time based on operating experience to place me units in HOT SHUTDOWN from full power without challenging safety systems or operators. The units may I

remain in HOT SHUTDOWN und a method to further cool the units becomes available, but actions to develop the method must be started within one hour aher reaching HOT SHUTDOWN.

Auxillary servios water pumps are strictly a bedtup suMystem and are not taken credt lor in a d6alen basis accident. However, these pumps are taken credit for in the 10 CFR 50, Appendix R analysis. Therefore, these pumps are maintained OPERABLE in MODES 1,2,3, and

- 4 to meet mese requirements.

L NORTH ANNA-UNIT 1 B 3/4 7-4a Amendment No.152 a

Pt.NR SYSTEMS, 4

EMSES 3/4 7.42 SERVICE WATER '3YSTEM SHt1TDOWN_

The OPERABILITY of the service water system when both units are in COLD SHUTDOWN or REFUEUNG ensures that an adequate heat sink is maintained for the residual h4at removal system. Requiring two service water pumps to be OPERABLE is consistent with the residual 1: sat removal system requirements.

If only one service water pump is OPERABLE, an additional service water pump must be restored to an OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , if an additional service water pump cannot be restored within the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months time frame, all operations invoMng an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System should be irnmediately suspended.

With no service water pumps OPERABLE, all operations invoMng an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System must be immediately suspended.

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NORTH ANNA. UNIT 1 B 3/4 7 4b Amendment No.152

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VIRGINTA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION,llNIT NO. 2 AMEN 0 MENT TO FAClllTY OPERATillG LICENSE Amendment No. 136 License No. NPF-7 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated October 3,1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 f.ct, and the rules and regulations of the Comission; 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

,, 2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. hPF-7 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 136, ure 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 the date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMfilSSION Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of 1

'ce: December 13, 1991 L

l l

4 ATTACHMENT TO LICENSE AMENDMENT NO.136 T0. FACILITY OpERATil4G LICENSE NO. NpF-7 DOCKET NO. 50-339 Replace the following pages of the Appendix "A" Technical Specifications n<tth the enclosed pages as indicated. The revised pages art identified by amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness, k7-15 3/47-15a(new) 3/4 7-15b (r.ew) 3/4 7-16*

B 3/4 7-4 8 3/4 '/-4a new B 3/4 7-4b new

There are no changes on this page, it is included to maintain docur,ent completeness.

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i PLMvT5Y51 5 5 2/4.7.4 REAMCE WATER BYSTEM S/d.7.d.1 SERVICE WATERSYSTEM OPERATag UMmNG CONDm0N FOR OPERATION 5.7.4.1 Twer no

'er loops (shared whh Ur* 1) h N b OPERABLE with each loop L

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cent, w e a, Twn.

'En OLE service water pumps (escluding evaluary service water pumps) whh th. a=%ed normal and emergency power ogplies, and t An OPERABLE now path capable of pnwiding cooling for OPERABLE piant i

components and transferring heat to the servios water reservoir.

A2tMCABILIIX:

EJther UnN in MODES 1,2,3, or 4.

ACI M:

a _WMh one servios water pump inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months throttle component _

coolmg water heat exchanger flows, in accordance with approved operating procedures, to ensure the remainin0 service water pumps are onpable of providing adequate flow to the recirculation spray heat exchan0ers.

b. With two servios water pumps inoperable, perform ACTION 3.7.4.1.s within i hour and restore et least one service water pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or place both unita in HOT STANDBY whhin the next six hours and in COLD SHUTDOWN whhin the lollowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. WIth one servios water loop inoperable, except as provided !n ACTION 3.7.4.1.a.

restore the inoperable loop to OPERABLE status whhin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or place both unhs in HOT STANDSY within the next S hours and in COLD SHUTDOWN wthin the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d The allowabia time that one of the two servios weler loops een be inoperable as spoolned 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 160 hours0.00185 days 0.0444 hours 2.645503e-4 weeks 6.088e-5 months as part of service water system upgrades' pnwided 3 out of 4 servloe water pumps (the third pump does not require auto stari capabluty) and 2 out of 2 ausliiery mytoe water pumps have been OPERABLE sinos inblal entry into the annon statnwnl and remain OPERABLE wring the extended anson etelement er be in at Nast 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 .

leoistion of one servios water hop for up to 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months is permined only as part of.

service wetw ersten upgrades. system egrades include modulosson and maintenance nadvities ew nh the instamation of new discharge headers and sprey arrays, w

mechaniosi and chemical cleaning of service water piping and valves, p5e repair and replacement, volve repair and replacement, installation of corrosion mhlgation measures and inspections of and repairs to buried Ms;; interior coatings and porm or valve house components.

l NORTH ANNA. UNIT A 3/4 7 15 Amendment No. 37.56. 136

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PL ANT SYSTEMS E2,4 RERVICE WATER SYSTEM M 7.4.1 RFRVICE WATER SYSTEM. OPERATitQ UMITNG OCND(TION FOR OPERATON

e. With two serv %e water loops inoperable for reasons other than described in ACT!ON 3.7.4.1.b place both units in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and witain the following hour, initiate actions to place both units in COLD SHUTDOWN and continue actions until both units are in COLD SHUTDOWN.

_ SURVEILLANCE REQUIREMENTS 4.7.4.1 At least two service water loops shall be demonstrated OPERABLE:

a. At lesst once per 31 days by verifying that each vaNo (manual, pcwor operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position,

b. At least once per 6 months by measurement of the movement of the pumphouse and wing walls.

c. At least once per 18 months during shutdown, by:

1. Verifying met each automatic vane servic!ng safety related equipment actuales to its correct position on an actual of simulated safety injection signal.

2. Verifying that each automatic' service water vake actuales to its correct 1

position on an actual or simulated containment high high signal.

d, Each service water pump will be tested in socordance with Specification 4.0.5.

I i

l NORTH ANNA UNIT 2 3/4 715a Amendment No.136 L

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PLANT SYSTDAS 1/4.7.4 SERVICE WATER SYSTEM l'4.7.43 SERVICE WATER SYSTEM. SHUTDOWN UMITNG 00NDITO4 FOR OPERATO4 3.7.4.2 One service water loop (shared with Unit 1) shall be OPERABLE consisting of:

a. Two OPERABLE service water pumps (or auxillary service water pumps) with their associated normal and emergency power supplies, and

b. An OPERABLE flow path capable of providing cooling for OPERABLE plant componefits and transferring heat to the service water reservolt or, if using auxiliary service pumps, to the North Anna reservoir.

APPLICABILITY:

Both Units in MODES 5 or 6.

ACTYJN:

a. Whh only one servlee water pump OPERABLE, restore an additional service water pump to OPERABLE status withlr.12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or immediateN suspend all operations invoMng an increase in the reactor decay heat lost' te a reduction in boron concentration of the Reactor Coolant System,

b. With no service water pumps OPERABLE,immediately suspend all operations invoMng an increase in the reactor decay heat lcad or a reduction in boron concentration of the Reactor Coolant System.

SURVEll!.ANCE REQUIRDAENTS 4.7.4.2 At least one service water loop shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each vahre (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position,

b. At least once per 6 rnor.;hs by measurement of the movement of the pump house and wing walls,

c. Each service water pump will be tested in accordance with Specification 4.0.5.

NORTH ANNA. UNIT 2 3/4 715b Amendment No. 136

7 PLANT SYSTEMS 3f4.7.5 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.5.1 The ultimate heat sinks shall be OPERABLE:

a.

Service Water Reservoir with:

1.

A minimum water level at or above elevation 313 Mean Sea level, USGS datum, and 2.

An average water temperature of less than or equal to 95'F as measured at the service water pump outlet.

b.

The North Anna Reservoir with:

1.

A minimum water level at or above elevation 244 Hean Sea Level, U3GS datum, and 2.

An average water temperature of less than or equal to 95'F as measured at the condenser inlet.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the requirements of the above specification not satisfied, be in at least HOT STANDBY within 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 .

SURVEILLANCE REQUIREMENTS 4.7.5.1 The ultimate heat sinks shall be determined OPERABLE at least ^nce per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the average water temperature and water level to be within their limits.

4.7.5.2 Data for calculating the leakage from the service water reservoir shall be obtained and recorded at least once per 6 months.

NORTH ANNA - UNIT 2 3/4 7-16 l

4 PLANT SYSTEMS BASES Each electric driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 340 gpm at a pressure of 1064 psig to the entrance of the steam generators.

The steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 700 gpm at a pressure of 1064 psig to the entrance of the steam generators.

This capacity is sufficient to ensure that adequate feedwater flow is 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 minimum water volume ensures that sufficient water is available to maintain the RCS at

- HOT STANDBY conditions for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months with steam discharge 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 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-rite radiation dose will be Ilmited 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 MAIN STEAM TRIP VALVES The OPERA 81LITY of the main steam 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 the

- 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 containment.

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

l NORTH ANNA - UNIT 2 B 3/4 7-3

~ -

4 l

PUM5Y3755 M

3/d 7.ta and S/d.71. 7 - BTEAM TURBINE and OVER2 PEED PROTECTION The turbine generator at the North Anna foollity is arranged in a nonpeninsular orientadon. Analysis has shown that this arrangement k such that N a turbine faibre occurs as a result of destructive overspeed, potentially damaging missies could impact the auxiliary building, containment, control room and other structures housing safety related equipment. The requirements of these two specifications provide addtional assurancs that the facility will not be operated w6th degraded valve performance ardor flawed turbine material which are the I

major contributors to turbine tallures.

S/d 7.2 BTEAM tk8NERATOR PR5tellRE/ TEMPERATURE I tufTATION The umhallon on steam generator pressure and temperature ensures that the pressure i

induced stresses in the steam generators do not escoed the maximum allowable fracture toughness stress bmits. 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, t

r i

SidD COWONENTC00LfBWATER SURRYSTEM The OPERABluTY of the component cooling water subsystem ensures that sufficient

. cooling capacity is available for continued operation of safety related equipment during normal and accident constions.

1 I

e NORTH Af#dA UNIT 2 B 3/4 7 4 Amendment No.136

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IUNT SYSTES 4

l SW 3/d.7.4.1 RERVM %(ATER BYSTEM OPERATalo The OPERAtluTY of he servloe water system ensures that sufflaient cooling capacity is avaRable for safety related equipment during normal and sooident condtions. The system la designed to meet the assumption of a single failure. During a design basis accident, both loops of servios water cross-connect at the affected units recirculation spray heat excha.gers to create a single large service water system. The affected units component cooling heat exchangers isolate so that sufflaient flows are provided to both the non.affooted and aflooted units components.

Wie leur normal service water pumps OPERABLE, the unthrottled flow resistance of the system is such hat greater man design flows are achieved if a single pump or power supply failure occurs follow 6ng an sooident. When three normal service water pumps are OPERABLE, the flow resistance of the system is adjusted to ensure that design flows we achieved if a single pump or power supply failure occurs following an econdent. The required resistance is determined during periodic flow balance testing and is obtained by throttling flow trough the component cooling water heat exchangers. Ramor than meAlng and specNying enant component cooling water heat exchanger outlet throttle vake poshions, operating procedures have been estabitshed to set system resistance at or greater than the required resistance. When only two normal servios water pumps or a single loop are OPERABLE, the design basis function can sel be met provided that the flow resistance of ths system is edusted and no additional failures occur. The allowed outage time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is consistent with other LCOs ter loss of one train of ESF systems, and is based sport an industry accepted practico considering the low p##" / of j

- an accident occuring.

H more than two normal service water pumps of bom service water loops are inoperable, the unha are not propwed to respond to the design bases events for which the -

servios water system is required. Both units must be pleoad in HOT SHUTDOWN within twelve hours and actions initiated within one hour thoroafter to place the units in COLD SHUTDOWN.

Twelve hours is a reasonable time based on operating experience to place me units in HOT SHUTDOWN from fun power without challeneng safety tems or operators. The units may remain in HOT SHUTDOWN until a method to further the units becomes available, but actbns to develop the method must be started within one hour after reaching HOT SHUTDOWN.

Auxiliary service water pumps are strictly a bedtup subsystem and are not taken credt

~ tor in a design beels accident. However, mese pumps are tahan credit for in the 10 C*M 110 Appendh R, analysis. Therefore, these pumps are maintained OPERABLE in MODES 1. 2. 3, and 4 to meet mese requirements.

I NORTH ANNA. UNIT 2 B 3/4 7 4a Amendment No.136

w-s Pt>NT SYSTEMS IMSES 3/4.7.4.2 SERVICE WATER SYSTEM. SHUTDOM The OPERABILITY of the service water system when both units are in COLD SHUTDOWN or REFUEUNG ensures that an adaquate heat sink is maintained for the residual heat removal system. Requiring two service water pumps to be OPERABLE is consistent with the residual heat removal system requirements, if ony one service water pump is OPERABLE, an additional service water pump must be restored to an OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . if an additional service water pump cannot be restored within the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months time frame, all operations invotving an increase in the fonctor decay heat load or a reduction in boron concenttallon of the Reactor Coolant System should be immediately susperded.

With no service water pumps OPERABLE, all operations invoMng an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System must be immediately suspended.

NORTH ANNA UNIT 2 B 3/4 7 4b Amendment No.136

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