ML20079B855

Proposed Tech Specs Re Verification of Operability of Equipment by Exam of Appropriate Plant Records

ML20079B855
Person / Time
Site:	Cooper
Issue date:	06/07/1991
From:	NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20079B852	List: ML20079B855 NLS9100363, Application for Amend to License DPR-46,consisting of Proposed Change 96 to Tech Specs Re Verification of Equipment Operability by Exam of Appropriate Plant Records
References
NUDOCS 9106180016
Download: ML20079B855 (35)

Text

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L. , Mode - The reactor mode is established by the mode selector-switch. The

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- modes include ~ refuel, run, shutdown and startup/ hot ~ standby which~are' ~ ~ - -

defined as follows: 1

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l. Refuel Mode - The reactor is in the refuel mode when the modo switch is in the REFUEL position. k' hen the mode switch is in the REFUEL ,

position, the refueling interlocks are in service.

2. Run Mode - In this mode the reactor system pressure is at or above j 8;'5 psig and the reactor protection system is energized with APRM i protection (excluding the 15% high flux trip) and RBM interlocks

in service.

3. Shutdown Mode - The reactor is in the shutdown mode when the mode switch is in the SHUTD0k'N position.

4. Startup/ Hot Standby - In this mode the reactor protection scram trips initiated by the main steam line isolution valve closure are bypassed, the low pressure main steam line isolation valve closure trip is bypassed, the reactor protection system is energized with APRM (15%

SCRAM) and IRM neutron monitoring system trips and control rod withdrawal interlocks in service.

L.A Normal Ventilation - Nonnal ventilation is the controlled process of discharging and replacing air from/to a confinement to maintain temperature, humidity, or other conditions necessary for personnel safety and entry. The contents of the atmosphere being discharged f rom the confinement will have been established 1

y 4 prior to establishing normal ventilation following a purging / venting operation.

. Offsite Dose Assessment Manual (ODAM) - An 0FFSITE DOSE ASSESSMENT MANUAL (0 DAM) shall be a manual containing the methodology and parameters to be used in the

{

calculation of offsite doses due to radioactive gaseous and liquid effluents, calculation of gaseous and liquid ef fluent monitoring instrumentation alarm / trip i N, setpoints, and describes the Environmental Radiation Monitoring Program.

--tt Operable - Operability - Operating l

1. Operable - Operability - A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified functiorw.(s) . Implicit in this definition shall be one sssumption i that all necessary attendant instrumentation, controls, normal and emer p acy f electrical power sources (except as specified in Section 1.0.J and 3.9),

! cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its functione-(s) are also capable of performing their related support func ;. ion *(s) ,

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2. Operating - Operating means a system, subsystem, train, component, or device is perfirming its intended function in its required manner.

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, 0. Operating Cycle - Interval between the end of one refueling outage and the end of the next subsequent refueling outage.

P. Primary Containment Integrity - Primary containment integrity means that the drywell and pressure suppression chamber are intact and all of the following conditions are satisfied?

1 All manual containment isolation valves on lines connected to the reactor coolant system or containment, and which are not required to be open during accident conditions, are closed.

2. At least one door in each airlock is closed and sealed.

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. LIMITING CONDITIONS FOR OPERATIOr - SURVEILLANCE REQU7REMENa?

3.4 4 4.A.2.c (Cont'd.)

pump demineralized water into the reactor vessel from the test tank.

These tests check the actuation of the explosive charge of the tested loop proper operation of the valves, and pump operability.

The replacement charges to be installed will be selected from the same manufactured batch as a previously tested chargo,

d. Both systems, incP .;g both ex-plosive valver, shall be tested in the course of two operating cycles.

B. Operation with Inoperable Components: B. Surveillance with Inoperable Com-ponents:

1. From and after the date that a redun-dant component is made or found to 1. When a component is found to be inop-be inoperable, Specification 3.4.A.1 erable, its redundant component shall be considered fulfilled and shall be -demonsgrated to be operable continued operation permitted pro- immed'.:ely and daily thereafter vided that the component is returned until the inoperable component is to an operable condition within repaired. fr v-seven days. vec;[;21 C. Sodium Pentaborate Solution C. Sodium Pentaborate Solution At all times when the Standby Liquid The following tests shall be performed Control System is required to be op- to verify the availability of the erable the following conditions shall Liquid Control Solution:

be met:

1. The net volume versus concentration 1. Volume: Check and record at least once-of the Liquid Control Solution in per day, the liquid control tank shall be main-tained as required in Figure 3.4.1.

2. The temperature of the liquid control 2. Temperature: Check and record at least solution shall be maintained above the once per day.

curve shown in Figure 3.4.2.

3. Concentration: Check and record at least once per month. Also check con-centration anytime water or boron is

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• a %ASES STANDBY LIQUID CONTROL SYSTDi A. The conditions under which the Standby Liquid Control System must provide shutdown capability are identified via the Plant Nuclear Safety Operational ,

Analysis (Appendix G). If no more than one operable control rod is with-drawn, the basic shutdown reactivity requirement for the core is satisfied and the Standby Liquid Control system is not required. Thus, the basic reactivity requirement for the core is the primary determinant of when the liquid control system is required.

Tha purpose of the liquid control system is to provide the capability of '

bringing the teactor from full power to a cold, xenon-free shutdown condition assuming that none of the withdrawn control rods can be in-serted. To meet this objective, the liquid control system is d1 signed to inject a quantity of boron that produces a concentration of 600 ppm of boron in the reactor core in less than 125 minutes. The 600 ppm con-centration in the reactor core is required to bring the reactor from full power to a 3.0 percent ak suberitical condition, considering the hot to cold reactivity dif ference, xenon poisoning, etc. The time require-ment for inserting the boron solution was selected to override the rate of reactivity insertion caused by cooldown of the reactor following the xenon poison peak.

The minimum limitation on the relief valve setting 'is .ntended to prevent

( the recycling of liquid control solution via the lif ting of a. relief valve at teo low a pressure. The upper limit on the relief valve settings provides system protection from overpressure.

B. Only one of the two standby liquid control pumping loops is needed for operating the system. One inoperable pumping circuit does not immediately threaten shutdown capability, and reactor operation can continue while the circuit is being repaired. Assurance that the remaining system will perform its intended function and that the long term average availability of the system is not reduced is obtained for a one out of two system by an allowable equipment out of service time of one third of the normal surveillance frequency. This method determines an equipment out of service time of ten days. Additional conservatism is introduced by reducing the allowable out of service time to seven daysg.and-by-increased-4as tin g-o f--the-o pe r a ble-r ed u nd a n t-componen eg C. Level indication and alarm indicate whether the solution volume has changed, which might indicate a possible solution concentration change.

The test interval has been established in consideration of these factors.

Temperature and liquid level alarms for the system are annunciated in the control room.

The solution is kept at least 100F above the saturation temperature to guard against boren precipitation. The margin is included in Figure 3.4.2.

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IJ1tITitJG CONDITIONS FOR Of1BATION SURVEILINJCE REQUIREttENTS I 3.5.A (cont'd.) 4.5,A (cont'd,)

2. From and after the date that one of 2. When it is determined that one core the core spray subsystems is made or spray subsystem is inoperable, the found to be inoperable for any operable core spray subsystem and reason, continued reactor operation the LPCI subsystem chall be is permissible during the succeeding amonat= rated- to be operable seven days provided that during such ' g'mmediately.

. The operable core seven days all active components of spray subsystem shall be the other core spray subsystem and y wonstrated- to be operable daily d

.nc e ive components of the LPCI thereafter.

subsystem and the diesel generators 'W' are operable. WPIb'd 3, Both LPCI subsystems shall be 3. LPCI subsystem testing shall be as operable: follows:

(1) prior to reactor startup from IIfe.gl Frequenqx a Cold Condition, except as a. Simulated once/ Operating specified in 3.22.B.1, or Automatic Actuation Cycle Test (2) when there is irradiated fuel in the vessel and when the b. Pump Operability once/ month reactor vessel pressure is greater than atmospheric c. Motor Operated Once/ month pressure, except as specified Valve Operability k in 3.5.A.4 and 3.5.A.5 below,

d. Pump Flow Rate Once/3 months During single pump LPCI, each RitR pump shall deliver at least 7700 CPM but no more than 8400 CPM against a system head equivalent to a reactor vessel pressure of 20 psid above drywell pressure with water level i below the jet pumps. At the same conditions, two LPCI flow shall be at least 15,000 CPM.

e. Recirculatiesn pump discharge valves

1. shall be tested each refueling cp d outage to verify full open to full closed in t 5 26 seconds.

4 From and after the date that one of . 4 When it is determined that one of the RHR (LPCI) pumps is made or the RllR (LPCI) pumps is ineperable found to be inoperable for any e a time when it is required to be l

reason, continued reactor operation q a r a t i g- the remaining active l

! la permissible only during the components of the LPCI subsystems, l succeeding thirty days provided f. hat the containment cooling subsystem I during such thirty days the and both core spray systems shall be remainin6 active components of the to be operable LPCI subsystem and all active /,.4emonst immediately rated- and the operable LPCI i

components of both core spray [Wbmimps daily thereaf ter, i subsystems and the diesel generators are operable. '/f'r M ed

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l.IttlTING CONDITIONS FOR OPERATION. SURVEll.l.ANCE REQUIREMENTS _

3.5.A (Cont'd.) 4.5 A. (Cont'd.)

5. From and after the date that one 5. When it is determined that the 1.PCI 1.PCI subsystem in made or found to subsystem i r. inoperable, both core be inoperable for any reason, contin- spray subt 4tems and the containment ued reactor operation in permissible r only during tha succeeding 7 days, un- coolingsubyatemshnllbe6btely

--*t4 *t *4. t o be ope rab l e innied less it is sooner made operable, pro- and daily thereafter.

vided that during such 7 days all active components of both core spray  %

subsystems, the containment cooling subsystems (including 2 LPCI pumps) and the diesel generators required Y,[Vf for operation of such components  %

shall be operable, i 6. All recirculation pump discharge 6. All 'ccirculatio) pump discharge 4

valves shall be operable prior to valves shall be tested for

! reacter startup (or closed if operability during any period of l permitted elsewhere in these Reactor cold shutdown exceeding

! specificatiens). 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if operability tests have l not been perf ormed during the preceding 31 dcys.

, 7. The reactor shall not he started up with the RilR system supplying cooling to the fuel pool, s . If the requirements of 3.5.A 1,2,3,4, i

5.6 or 7 cannot be met, an orderly I shutdown of the reactor shall be

! initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B. Containment Cooling Subsystem B. Containment Cooling Subsystem (RllR 1RHR Service Water) Service Water)

1. Except as specified in 3.5.B.?., 1. Containment Cooling Subsystem Testing 3.5.B.3, and 3.5.F.3 below both con- shall be as follows:

tainment cooling subsystems loops shall be operable whenever irradiated item Frequency fuel is in the reactor vessel and reactor coolant temperature is great- a. Pump & Valve Once/3 months er than 212*F, and prior to reactor Operability startup from a Cold Condition.

b. Pump Capacity Test. After pump rc.ain-Each RllR service tenance and every water booster pump 3 months shall deliver 4000 gpm.

c. Air test on dry- Once/5 years well and torus headers and noules. '

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. LIMITING

• CONDITIO S'EdR 0EER'5E50'N" ~ l 'SFRVEILilAN'Cf! REQUIREMENTS

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3. 5. B (Cont ' d . ) 4.5.B (Cont'd.) }

( When it is determined that any RHR

2. From and after the date that any RHR 2. l service water booster pump is made '

service water booster pump in inoper- j or found to be inoperable for any able, the remaining active componentsI reason, continued reactor operation of the contain' ment' cooling subsystemsi is permissible only during the suc- shall be 4 sparat*d. to be operable ceeding thirty days, unless such immediatelyfund weekly thereafter.

pump is sooner made operable pro- i vided that during such thirty days V all other active components of the g gM containment cooling subsystem are J operable. #

3. From and after the date that one con- 3. When one containment cooling subsystem tainment cooling subsystem loop is loop becomes inoperable, tpe operable made or found to be inoperable for subsystem loop shall be -de monst ret +.I.

any reason, continued reactor oper- to be operable immediately and daily tion is permissible only during the thereafter.

succeeding seven days unless such ,

subsystem loop is sooner made operable; provided that all active components  !

of the other containment cooling sub-system loop, including its associated diesel generator, are operable.

4. If the requirements of 3.5.B.1, 3.5 B.2

(, or 3.5.B.3 cannot be met, an orderly shutdown shall be initiated and the reactor shell be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C. HPCI Subsystem C. HPCI Subsystem

1. The HPCI Subsystem shall be operable 1. HPCI subsystem testing shall be per-whenever there is irradiated fuel in formed as follows:

l th- reactor vessel, reactor pressure is greater than 113 psig, and prior Item Frequency to reactor startup from a Cold Condi-tion, except as specified in 3.5 C.2 a. Simulated once/ operating and 3.5.C.3 below. Automatic Cycle Actuation Test 1

i b. Pump Operability Once/ month l

I

c. Motor Operated Once/ month Valve Operability l

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LI QTING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.5.C HPCI Subsystem (cont'd.) 4.5.C HPCI subsystem (cont'd.)

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2. From and after the date that the HPCI Item Frequency Subsystem is made or found to be in-operable for any reason, continue d d. Flow Rate at once/3 months reactor operation is permissable only approximately 1000 during the succeeding seven days psig Steam Press.

unless such subsystem is sooner made operable, providing that during such e. Flow Rate at once/ operating seven days all active components of approximately 150 cycle the ADS subsystem, the RCIC system, psig Steam Press, the LPCI subsystem and both core spray subsystems are operable. The HPCI pump shall be demonstrated to be capable of delivering at least

3. With the surveillance requirements of 4250 gpm for a system head correspond-4.5 C not performed at the required ing to a reactor pressure of 1000 to intervals due to reactor shutdown, a reactor startup may be conducted 150 psig.

s

, gy provided the appropriate surveillance 2. When it is deter ined that the RPCI is performed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of Subsystem is in ,crable the SIC , the achieving 150 psig reactor steam LPCI subsystem, both core spray sub-pressure. s y a t emsf.-an&-the-ADS *ubs ypettm-

-etion-4egie shall be demmetw>tel to l4. If the requirements of 3 b.C.1 cannot be met. a orderly shutdown shall bc be operable immediately. -The-kGIG-

.-system-and ADS subsystem logic shalb initiated and the reactor pressure be demonstrated to be operable, daily shall be reduced to 113 psig or less thereafter. Ano within ' hours. .

EEPLAtt Wl1W mmedtdel, snd cr n /heMcIC i system .r;.<// bx m;p;,j

% be erv=U6 dsd y %,.e py,.,

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~. A s y , p, D. Reactor Core Isolation Cooling (RCIC) D. Reactor Core Isolation Cooling (RCIC)

Subsystem Subsystem

1. The RCIC Subsystem shall be operable 1. RCIC Subsystem testing shall be per-whenever there is irradiated fuel in formed as follows:

the reactor vessel, the reactor pressure is greater than 113 psig. Item Frequency and prior to reactor startup from a Cold Condition, except as a. Simulated Once/ operating specified in 3.5.D.2 and 3.5.D.3 Automatic cycle below. Actuation Test

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L1HITINbCONDITIONSFOROPERATION. SURVEILLANCE REQUIREMENT 3.5.D (cont'd.) 4.5.D (cont'd.)

( _I_t em goguency

b. Pump Operability Once/ mon'.h

c. Motor Operated Once/ month Valve Operability

d. Flow Rate at Once/3 months approximately 1000 psig Steam Pressure

e. Flow Rate at Once/ operating approximately 150 cycle psig Steam Pressure The RCIC pump shall be demonstrated to be capable of delivering at least 400 gpm for a system head corresponding to a reactor pressure of 1000 to 150 psig.

2. From and after the date that the 2. When it is determined that the RCIC RCICS is made or found to be in- subsystem is inoperable, the HPCIS operable for any reason, continued shall be -femongtgetsi,Q.be o etable reactor power operation is per- immedia 41y{and-waak.ly-thacaattag missible only during the succeeding -

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seven days provided that during such seven days the HPCIS is op- VFeiCied etable.

3. With the surveillance requirements of 4.5.D not performed at the required intervals due to reactor shutdown, a reactor startup may be conducted provided the appropriate surveillance is performed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving 150 psig reactor steam pressure. .

4 If the requirements of 3.5.D 1 & ?

cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall be reduced to 113 psig or less within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

E. Automatic Depressurization System (ADS) E. Autemat te Depressurization System (ADS)

1. The Automatic Depressurization Sub- 1. During each operating cycle the follow-system shall be operable whenever ing tests shall be performed on the there is irradiated fuel in the ADS:

reactor vessel and the reactor pressure is greater than 113 psig A simulated automatic actuation test and prior to a startup from a Cold shall be performed prior to startup Condition, except as specified in after each refueling outage.

3.5.E.2 and 3.5.E.3 below.

_gyg_ 4/27/77

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.LIMITINb.CONDITIONSFOROPERATION SURVEILLANCE REQUIRDIENTS

'4.5.E (cont'd)

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3.) . E (cont'd)

2. From and after the date that one 2. When it is determined that one .

I I valve in the automatic depressurir.a- valve of the ADS is inoperable, the tion subsystem is made or found to be ADS subsystem actuation logic for the !

inoperable for any reason, continued other ADS valves +nd-the-WCI Wye-reactor operation is permissible only -+ee- shall be demongatedg er- i during the succeeding seven days un- able demediately and M eas' - le '

less such valve is sooner made opera- -therea hes s I ble, provided that during such seven In AddEo^. 44r N/tf days the SIPCI subsystem is operable, g, 6 g g gg,.y 4,

3. With the surveillance requirements of g S %,J;4 l ,

4.6.D.5 not performed at the required intervals due to reactor shutdown, a -ve I reactor startup may be conducted pro- ApD 7c /M A v,y, f.1 vided the appropriate surveillence is i performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of achieving 113 psig reactor steam pressure.

4. If the requirements of 3.5.E.1 or 3.5.E.2 cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall be reduced to at least 113 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

F. Minimum Lov Pressure Cooling and F. Minimum Low Pressure Cooling and Diesel Generator Availability Diesel Generator Availability

1. During any period when one diesel 1. When it is determined that one generator is inoperable, continued diesel generator is inoperable, ,

reactor operation is permissible all low pressure core cooling and only during the succeeding seven containment cooling subsystems days unless such diesel generator is shall be-.44,apnetrated to be oper-sooner made operable, provided that all of the low pressure core and con- able immediptely and daily there-after. In tainment cooling subsystems and the dieselgenI'rator addition,theoperable shall be demon-remaining diesel generator shall be strated t'be operable immediately

operable and the requirements of and every three days thereafter.

3.9.A.1 are met. if this require-l ment cannot be met, the require-ments of 3.5.F.2 shall be met, vt'M be k l 2. During any period when both diesel l

generators are inoperable, continued g reactor operation is permissible only during the succeeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless one diesel generator is sooner made l operable, provided that all the low pressure core and containment cooling subsystems are operable and the reactor power level is reduced to 25%

of rated power and the requirements of 3.9.A.1 are met. If this requirement cannot be met, either the requirements l

l shall be met or an orderly shutdown

} shall be initiated and the reactor placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

N.- 11/21/85

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3.5.A BASES (cont'd.)

l core spray subsystems and LPCI constitute a 1 out of 3 system; however, the combined effect of the two systems to limit excessive clad t9mperatures must also be considered. The test interval specified in Specification 4.5 is 1 month. 4hould-a-subsystem-fa il , d = 14 y-t+s t-4&-cal 4+4-f o r-en-the-remining.

-sy+tems-t o-e n s u r e-t ha t-they-*144-fu ne t4eg Should one core spray subsy tem become inoperable, the remaining core spray and To assure the LPCI system are available should that the remaining core spray and LPCI subsystems are available,the need for core cooling arise.they are-deme d l

-et-r*wd- to be operable immediately. -This deaanstent-sen-hehdee-e-wanue4-fM-t-i-

- atier ef-the-pumps-and-easoe4et+d-veha g i Should the loss of one LPCl pump occur, a nearly full compicment of core and containment cooling equipment is available. Three LPCI pumps in conjunction with the core spray subsystem will perform the core cooling function. Because of the availability of the majority of .the core cooling equipment, which will be strated- to be operable, a thirty day repair period is justified. If e LPCI subsystem is not available, at least 1 LPCI pump must be available to fulfill the containment cooling function. The 7 day repair period is set on Wrip;d this basis.

B. Containment Cooling Subsystem The containment cooling subsystem for CNS consists of two loops cach with 2 RHR (LPCI) pumps serving one side of the RHR heat exchanger and two RHR Service Water Booster Pumps serving the other side. The design of the loops is predicted upon the use of one RHR Service Water Booster Pump and one RHR heat exchanger, for heat removal after a design basis accident. Thus, there are ample spares for margin above design conditions. Loss of margin should be avoided and the equipment maintained in a state of operation. So a 30 day out-of-service time is chosen for this equipment. If one loop is out-of-service reactor operation is permissible for seven days with daily testing of the operable loop. pg (

w -

With components or subsystems out-of-service, overall core and containment t

cooling reliability is maintained by-demenet-r#t4ng- the operability of the re-maining cooling equipment. The degree;cf Operabilit.; to be demonstrated depende

the n tu:: ef-+he rece:- f.ee-ehe - cu; af rervi:: ; pi,,2:nt3 For routine out-of-service periods caused by preventive maintenance , etc. , the--pump-and-va4g p:r bi1ity ch::h ei11 h p:: krm d :: demenet-en:: :p:::b41i:; - f t h e ~ %,4*he-carpenent; However, if a failure, design deficiency, etc., caused the out-of-service period, then he-demonstration of operability .ehou14-be-phorough.

-enough to assurA ths a similar problem does not exist on the remaining com-ponents d example, if an out-of-service period were caused by f ailure of d g, a pump to deliver rated capacity, the other pumps of this type mighu be sub-jected to a capacity test. 4n any :.v nt, cuev 112cac prc::dur:0,%-r+9Mw4 y by S :tica - 6 ef-these-speef fieatiens , det*i4-the-requi-ted-ent+nt--M--t-ee449 v The pump capacity test is a comparison of measured um p jy g g ce parameters {

May be needed 80 x

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3 . .' . C BASES (cont'd.)

'ication to assure that when the reactor is being started up from a Cold Condition, the HPC1 is not known to be inoperable.

D. RCIC System The RCIC is designed to provide makeup to the nuclear system as part of the planned operation for periods when the main condenser is unavailable. The nucicar saf ety analysis, FSAR Appendix G, shows that RCIC provides water to cool the fuel when feed water is lost. In all other postulated accidents and transients, the ADS provides redundancy for the HPCI. Based on this and judgements on the reliability of the HPCI system, an allowable repair time of 7 days is specified, immedia te -and "=hly den.onu *nw of HPCI operability during RCIC outage is considered adequate based on judgement and practicality.

E. Automatic Depressurization System (ADS) W c The limiting conditions f or operating the ADS are derived f rom the Station Nuclear Operational Ar.alysis (Appendix C) and a detailed functional analysis of the ADS (Section VI.).

This specification ensures the operability of the ADS under all conditions for which the automatic or manual depressurization of the nuclear system is an essen-tial response to station abnormalities.

The nuclear system pressure relief system provides automatic nuclear system depressurization for small breaks in the nuclear system so that the low pressure coolant injection (LPCI) and the core spray subsystems can operate to protect the fuel barrier.

Because the Automatic Depressurization System does not provide makeup to the reactor primary vessel, no credit is taken for the steam cooling of the core caused by the system actuation to provide further conservatism to the CSCS.

Performance analysis of the Automatic Depressurization System is considered cnly with respect to its depressurizing effect in conjunction with LPCI or Core Spray. There are six valves provided and each has a capacity of 800,000 lb/hr at a set pressure of 1080 psig.

The allowable out of service time for one ADS valve is determined as seven days because of the redundancy and because the HPCIS is h-'ry to be operable during this period. Therefore, redundant protection for the core with a small break in the nuclear system is still available.

The ADS test circuit permits continued surveillance on the operabl relief valves to assure that they will be available if required. 7 Minimum Low Pressure Cooline and Diesel Generator Availability verihiPd-g,J F.

The purpose of Specification F is to assure that adequate core cooling equip-Change No. 19

-127- 10/31/75

4 4.5 BASCS ,

Core and Containment Coolin ; Systems Surveillance Frequencies The testing interval for the core and containment cooling systems is based on industry practice, quantitative reliability analysis, judgement and practicality.

The core cooling systems have not been designed to be fully testable during operation. For example in the case of the HPC1, automatic initiation during power operation would result in pumping cold water into the reactor vessel, which is not desirable. Complete ADS testing during power operation causes an undesirable loss-of-coolant inventory. To increase the availability of the core and containment cooling systems, the components which make up the system; i.e., instrumentation, pumps, valves, etc., are tested frequently.

The pumps and motor operated injection valves are also tested each month to assure their operability. A simulated automatic actuation test once each cycle combined with frequent tests of the pumps and g ection valves is deemed to be adequate testing of these systems. Y'M Wrd wbH overall core and contain-When ment coolingcomponents reliability and subsystemsbyare is maintained out-of-service,Iet4*g the operability of the 4emanet+

remaining equipment. -;ha dagree-of-operabil11y-to-be-demoneteted-depend , < ..

tha-na t u re-of--t he-rea son -fo r-the-ou t* fwervi ce- squ ipa % For routine out-of-service periods caused by preventative maintenance, e t c . , -the pump and-vake- 7 yrab11ity checks.-ut11 be-periormed-to damonatrate-operab111ty-of-the-aeu.alning-[

-sompo % However, if a failure or design deficiency caused the outage, then demonstration of operability .should ba4horougljygh to assure that a generic problem does not exist. For example, if an out-of-service period were E

caused by failure of a pump to deliver rated capaci ty due to a design deft-ciency, the other pumps of this type might ted to a flow rate test. ,4

( Ja-addit 44n-to-t-he- opereh M4 t y c he c k g ]besubg[:7[ Enermtsath

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W, Aadundant-operabla-componena-ara-subjected-to-increased-test 4ng-during-equi "l -eut-o f-se rv ice-t imes v--Th is-ad d s - f u r t he rwonee rva t-i sm-end -i nc rea se a-o asu roner

$

• ha t adequat4 -cooling-is-ava14able-should-the-need-*r4 ce 3 l h

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p \, / f #

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40 f f ke gec . h:l:Ly d See sy bre ad comevh will be ve c;9:e d ~ yen in ha hLiwi &re, hec.hons.

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-13l-

a

.s *

' LIMITING CONDITION FOR OPERATION St'RVE!LLANCE REOUID EMENT 3,*.3 (con:'d) ..'.3 (cont'd)

b. The results of labora:ory carbon b. Cold DOP tes:ing shall be performed saep'.e snalysis shall shou 299% af er each comple:e or par:ia' raci:a :ive to:hyl iodide removal replacement of :he HE?A f t'.:e:

vi:h ir.le: condt: ions :f: velocity bank or af ter any s::ue: ural l 242 FPM, al.~5 mg/m' inle: methyl main:enance on :he system housing.

iodide :encen:rs: ion, 270 R.H.

and s20':  :. Halogena:ed hydrocarbon tes:ing shall be performed af:er eacn

c. Each fan shall be shown to provide complete or par:ial replacemen:

1780 CMT :10%. of :he char:oal adsorcer bank or af:er any strue: ural main:enance

3. From and af:er :he da:e :ha: one on :he sys:em housing, s:andby gas ::ea: ment system is mace or found to be inoperable for any d. Each system shall be opera:ed reason. reac:or opera: ion is with :he heaters on a: leas:

permissible only during the 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month, succeeding seven days unless such e. .es; . sealing o:. gaskets :or housing sys:em is sooner made operable. doors downstream of the . dE?A provided :ha: during such seven ,il:ers

. and :harcoal adsorbers days all ac:ive components o,. :he shatl be per.,ormed 4:, and in o:her standby 5as treatman: sys:3m, con., romance vi:h, each :es:

and i:s associa:ed diesel genera:er, per,or:ed

. ,or

. compliance vi:5 sha.,,. be operable. ,

S p e c t.,ic a: t o n .,.3..,.a and 3pecift:a:Len J.7.3.2.a.

ue,. handling requiremen:s are spec t'ied in Specifica: ion 3.13.E. J. Sys:e= drains where presen; sha'1 .

be inspected quarteriv for adequate -

4 ,'

. these condi: tons cannot be me:. va:e: love,. .n ,. cop seals.

procedures shall be initiated immedia:ely :o es:ablish reac:o .

• .a. A: ,eas: A once pe: ope:a:in5 CVC, e -

condi: ions .,or which the s:andbv- automatic int:,.ac, .on o., each branch o,.

gas :rea:=en sys:em is not the s:andby gas treatmen; system sna..

required. be demonstra:ed.

l b. At leas: once per operating cycle j

t manual operabill:7 of the bypass valve for fil:e cooling shall be demons::ated.

l

'  :. When one standbv ~zas ::ea::en: svs:e Verihtf bacomes inoperaele the other s a'nchy f gas : eatmen: system shall be de= ens::stad :s be operable

-112 ^1f and dai'.y :hereafter.

A demons::sti:n of diesel generator operability is no:

required by :his specifica:Lon.

C. S e c e -d a r-' ~ 7 - t a i n-a n t C. 3ec?ndsr" So"TainNa":

1 Secondary contain=en: in:egri:y '.. 3*concary :an:ain=en: su rve ; . lan; s sha'.1 be maintained curing 211  ! snal'. Se pe rio::ec 2s ' nci:a:sc :e ' :W '

modes :f p'.an: 2:e:2:ian inceo .

wnen a'.1 si :he f o ' . s v '. n g conci: ions ars me:. ,

EC9"cre.. 1c. 30..aE.'1' .;: a-

l 1 .

,4.7.B & 4.7.C BASES '

with an adsorbent qualified according to Table b1 bf ANSI N5091980. The l replacement tray for the adsorber tray removed for the test should meet

[ the same adsorbent quality. Tests of the HEPA filters with DOP aerosol shall be performed in accordance to ANSI N5101980. Any filters found defective shall be raolaced with filters qualified pursuant to Regulatory Position C.3.d. of Regulatory Cuide 1.52, Revision 2, March,1978.

All elements of the heater should be demonstpated to be functional anj operable during the test of heater espacity. Operation of the heaters will prevent moisture buildup in the filters and adsorber system.

With doors closed and fan in operation, DOP aerosol shall be sprayed externally along the full linear periphery of each respective door to check the gasket seal. Any detection of DOP in the fan exhaust shall be considered an unacceptable test result and the Baskets repaired and test repeated.

If system drains are present in the filter /adsorber banks, loop seals must be used with adequate water level to prevent by pass leakage from the banks.

If significant painting, fire or chemical release occurs such that the HEPA filter or charcoal adsorber could bacome contaminated from the fumes, chemicals or foreign material, the same tests and sample analysis shall be performed as required for operational use. The determination of significance shall be made by the operator on duty at the time of the incident. Knowledgeable staff members should be consulted prior to making this determination.

Demonstration of the automatic initiation capability and operability If of

(

filter coolins is necessary to assure system performance capability.

I one standby gas treatment system is inoperable, the other -systes-cu t b-

-c+a t+4. daily . This substantiates the availability of the operable system and thus reactor opera,'.on or refueling operation can continue for a limited period of time. -.

3.7.D s ' 7.0 BASES gffeds opemb;///g /t wriSed WuMW Primary Containment Isolation Va ves Double isolation valves are provided on lines penetrating the primary '

containment and open to the free space of the containment. Closure of one of the valves in each line vould be sufficient to maintain the integrity of the pressure suppression system. Automatic initiation is required to minimi:e the potential leakage paths from the containment in the event of a loss-of coolant accident.

The maximum closure ei=es for the automatic isolation valves of the primarf containment and reactor vessel isolation control system have been selected in consideration of the design intent to prevent core uncovering following pipe breaks outside the primary containment and the need to contain released fission products following pipe breaks inside the primary containment.

These valves are highly raliable. have a low serrice requirement, and most are normally closed. The initiating sensors and associated trip channels are also checked to demonstrate the capability for automatic isolation.

~he test interial of once per operating cycle for automatic initiation 132 02/25/9'.

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.10.5 (Cont'd) 4.10 (Cont'd)

T 4 During spiral reload, SRM operability, vill be verified by using a portable external source every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> until the required amount of fuel is loaded to maintain 3 cps. As an alternative to the above, two fuel assemblies will be loaded in different cells contain-ing control blades around each SRM to obtain the required 3 cps. Until these two assemblies bsve been loaded, the 3 cps requirement is not necessary.

C. Spent Fuel Pool Water Level C. Spent Fuel Pool Water Level Whenever irradiated fuel is stored in When irradiated fuel is stored in the the spent fuel pool, the pool'vate* spent fuel pool, the water level shall level shall be maintained at or above be recorded daily.

8\ above the top of the fuel.

D. Time Limitation Irradiated fuel shall not be handled in or above the reactor prior to 24 yfri[ipd hours after reactor shutdown.

E. S,tandbv Cas Treatment System E. Standbv Cas Treatment System From aad after the date that one When one standby gas treatment system standby gas treatment system is becomes inoperable, the other standby

( '

made or found to be inoperable gas treatment system shall be en--

for any reason, fuel handling is 4tsaa*4-to be operable immediately permissible only during tne suc- and daily thereafter. A demonstra-ceeding seven days unless such tion of diesel generator operability system is sooner made operable. is not required by this specification.

provided that during such seven days all active components of the other standby gas treatment system, and its associated diesel generator, shall be operable.

At least one diesel generator shall be operable during fuel handling operations. This one diesel shall be capable of supplying power to an operable Standby Gas Treatment System.

F. Core Standby Cooling Systems During a refueling outage, refuel-ing operation may centinue with one core spray system or the LPCI mode of RHR inoperable for a period of 30 days. Refueling is permitted with the suppression chamber drain-ed provided an operable core spray system or subsystem of the LPCI mode of RHR is aligned to take a suction on the condensate storage

.) tank containing at least 150,000 gallons (114 ft. indicated level).

-205a- 04/09/86

t1MITING CONDITIONS FOR OPFRATION SURVEILI.ANCE REQUIREMENTS y A.

B. r Building Closed Cooling Water B. Reactor Building Closed Cooling Water Reacto System hQ Svatem (KlC) ,s, -m . m REC System Testing 7\ Ql2 (v ,d))

1. Both reactor building closed cooling 1. j water loops and their associated item Freclugp[v ' ggg pumps shall be operable whenever irradiated fuel is in the vessel or a. Pump Operability once/ Month the spen *. fuel pool, except as speci- a. Motor operated once/ Month fled in 3.12.11. 2 and 3.12. B. 3 Valve Operability below, c. Pump flow rate once/3 months and m, Each pump shall after pump mainten-j .. . ,n, y deliver 1175 gpm ance i

f,IL b' ' y 1.

d.

at 65 paid, System head tank Daily

\s, . f f level shall be monitored.

2. From and after the date that any 2. When it is determined that any active coteponen t in one loop becomes in- component inanRECloopisinoperable.l operable continued reactor operation all cotoponents in the other loop shall is pertnissible during the succeeding be dee**etysted-operable immediately thirty days provided that during and weekly ithereafter, 1

such thirty days all the components of the other loop and the active com- . k y.

ponents of the engineered safeguards /

compartment cooling s>'tems, the diesel G' ,', [- i t' d

(,>y t' r i

- generator associated with thu operable ~

loop are operable.

(s .

The allowable repair time does not apply when the reactor is in the shutdown mode and reactor pressure is less than 75 psig.

3. Both reactor building closed cooling water loops with one puwp per loop shall be operable as stated in 3.12.

B.1 and 3.12.B.2 above d' iring reactor head-off operations requiring LPCI or Core Spray System availability or service water cooling shall be available.

4 If the requirements of 3.12.B.1 through 3.12.B.3 cannot be met, the reactor shall be shutdown in an orderly manner and in the Cold Shut-down condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or operations requiring LPC1 or core spray system availability shall be halted.

\

6 / 21. / B 2 g3

Lit 41TI_NG CdNDITIONS Foh OPERATION

- -- lSURVE1LLANCI: __M LO.Ul trMENTS 3.12 (cont'd) 4.12 (cont'd) l Service Water Syst em, C. Service Water System

1. Both service water subsystems with 1. Service Water System Testing '

both pumps in each subsystem shall be operable when ever irradiated item Functional fuel is in the vessel or spent fuel pool and prior to reactor startup a. pump 7perability Once/ Month except as specified in 3.12.C.2 below.

b. Motor Operated once/Honth Valve Operability

c. pump discharge Once/3 months '

head tests Ann

2. From and 6.ter the date that any com- 2. Vnen it is determined that any (.p-e fergg nonent in the service water subsystem service water system component is made or found to be inoperable for inoperable, the operabic service i reason, continued reactor operation water subsystem components shall Au permissibic during the succeeding be iteww.u to be operable thfrty days provided that during such immediately nd weekly thereafter, thirty days all active components of a the other service water subsystem and ggp;,j its associated diesel generator are operable.

If the requir a nt of 3.12.C.1 and

)3.12.C.2cannotbemet, an orderly shutdown of the reactor shall be initiated and the reactor shall be in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. Battery Room "tntilation D. Battery Room Ventilation A. Battery room ventilation shall be 1. The spare battery room ventilation operable on a continuous basis when- fan shall be checked for operability ever specification 3.9 A is required once/ week.

to be satisfied.

2. From and after the date that either of l the two battery room vent f ans is made or found to be inoperable for any reason, continued reactor operation is permissible during the succeeding 7 days.

3. If the requirements of 3.12.D.1 & 2 i cannot be met, an orderly shutdown of the reactor shall be-initiated and the reactor shall be in Cold Shutdown with-in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Change No. 19 l 1

-215c-I

_ _ - _ _ , _ . ~ . . - . . - _ , , , .- . _ . - _ . , _ . . . , _ . _ . . ~ - - , _ . . . , _ . - . - _ . . ., , _

i.

1. llode The reactor mode in entablished by t he mode nelector r. witch. The nmden loclude r e f uel, t un, shut down airl nt at t up/ hot nt atulhy which nte delined ns f ollows:

1. lWf uel_.}lede 1hn tenctor in in t he refuel niode when thn mode swit ch in in the RilVEh position. Vhen the mode switch is in the REl tIEl, posit ion, the icfueling interlocks are in service.

1. Ihntijode. - In t his modo the t enct or systein press ut e in at or nhove 825 psig and the renctor protection system is energized with APRii protection (ext.luding the 15% high flux tiip) and RBH interlocks in nervice.

3. Bhut dowitJJwle. - The renetor is in the nhut down mode when tho inode nwltch in in the SiltrfDnWN posit ion.

4. Staripp/[lo LSlandby - In this inode the renetor prot ect ton nernm trips int t Int ed by the main stenm line innintion vnive clonure are bypanned, the low pi csnut e main st enm line inolation valve closure trip in hypansed, the renet or pi ot ect ion syst em is energized with APF11 (15% SCRAti) and Itti umitt on omnitor ing syst em trips and cont rol rod wit hdrawnl interlocks in nervice, l.. a potmnLY.cnt ilMJ on Normn1 vent ilnt ton in thn controlled procons of dinchniging and repincing air f rom /to a confinement t o unint ain t empernt ure, ouvidi t y , or ot her cotulitionn necensnt y f or personnel saf et y and ent ry. The cont ent of t he nt mosphnie being discharged from the confinement will have been esti inhed pilor to establishing normal ventilation following a purging / venting ope. .lon.

11 . Ofhitr._ Pope _ Msemenkjlanw1LLOlWil - An DITSITE DOSE ASSESSMENT liANUA1. (ODAM) l shall be a mnnunt containing the methodology and parameters to be used in the eniculatien of offsito doses due to radionctive gaseous nnd liquid effluents, eniculation of ganeoun and liquid effluent monit oring inst rument at ion nintm/t rip notpoints, and describen the Envi roinnent al Radint ion Moni t ori ng program.

H. Operchlt_.:_0ptrnh1111y - Optrot.11ig l

1. Operchj e Opel:6billiy - A system, subsystem, train, component or device shall be OPERABhE or have OPERAltII.lTY when it. is capable of perfoaming its specified function (s). Impileit in this definit ion shall be the nnsumption l t hat all necensnry attendant instrumentat ion, cont rols , noi mal and eme rgency electrient power sources (except as speelfied in Sect ion 1.0..I and 3.9),

cooling or t;e n t water, lubrient ton or other auxiliary equipment that nio requiied for the system, subsyn t em , t rain, compoto nt or devtoo t o perf orm it n f unct ion (s) are also enpable of per f orming their relat ed support function (n). l A veriftention of OPERAB1hlTY is an administrative check, by examination of appropriate plant records (logs, sutveillance test records), to de t e rini ne t.hn t a system, nuh sy s t ein , t rain, component or device in not inoperable. Such ver t f icnt ion does not. pi eclude t he demount rat ion (t ont ing) of a given nyst em, r;ubsy n t em, tinin, component or device t o det e t mine OPER ABil.lTY.

2. Prerat lug - Operat inn mennn n nynt r m, nuhnynteti, t rnin, component , or device in periorining it s intended functlon in it.s requited manner.

I 0 Opetating Cycle, - Int erval bet ween t he end of one refueling outage and t ho etut of the next subsequent refueling outage P J't Imary_ Cont,n !.tuitent _Integr i ty - Pr imary c ont n i nment, i nt ent I ty means t hnt t he drywell nivl prescut e supprennion chan,het ni e intact ntel nll of t he f ollowing cotuli t ionn nie nntisfled'

1. All m,nunt cont ninment i nnint ion valves on lines connected to the tenctor coolnnt syst em or cont alnment , and which nec not required to be npen during accident conditlonn, nte cloned.

? At least one door in each nirlock in cloned niul vented.

4

411111EllG_GONDJJ1014LirtL.DIIl%ILOf1 l'ME1L11dlCLRLOU1RilitfiTS 3.4 4.4.A.2.c (Cont.'d.)

pump dernincralir.ed water into tho ,

tenctor vessel frotn the test tank. I l

These teals check the actuation of  !

the explosive charge of t he tested loop, proper operation of the valves, and pump operabilit y. The repIncenient charges to be lontailed will be selected from the samo i manufactured batch as n previously tested chargo,

d. Bot h systemn, including bot h ,

explosive valven, shall be test ed in the course of two operating cycles. l D. Dr.ernt19n_YlilLimTcI4 hic B. Eutvstl.lfulst VltlLitmptrahlu i WtuniultitLA: Ottnuntnia: '

1. From and alter the datn that n 1. When a component is found to ho r edundant. component is made or found inoperable, its redundant component to be inoperahin, Specification shall be verified to be operable '

3.4.A.1 r'all be considered immediately and daily t hereni t er '

fulfilled e a continued operation until the inoperable component in i perin t t t ed provided that thn repaired.

coniponent in returned to an opernble condition within seven days.

G. Sedium pentnborate Solution C. Sodium pentaborate Solut.lon At all times when the Standby 1.iquid The following tests shall 1,c Control System is required to be performed to verify the availability opera' ale tho following conditions of the 1.lquid Control Solution:

shall be met: l

1. The not volume versus concent ration 1. Vol on,o : Check and record at least I cf ths Liquid Control Solut lon in once per day. ,

the 1iquid cont rol t ank shalI be ,

ina l nt a ined as required in Figure 3.4,1.

2. The temperature of the liquid 2. Tempnrature: Check and record at control solut ion shall be maintained least once per day.

above the curve shown in rigure 3.4.2. 3. Concentration: Check and record at least once per mont h. Also check concent rat lon anyt.ittie unter or boron is l

-108

~

iI a.

.

• i 3.4 JMSI,S STAtil*Y LIQttilt.cottrROL SLS1r ( i A. The conaltions under veha the :r m

• winnid cont t ol Syntem nnia t piovide i shut down enpahi1It y are @ ,,.;4 sed vin the pl e.nt Nuclent- Snfet y Operat lonni I Analynis (Appendlx G). If no moi e t hnn one opet oble coot rol t od is vi tlutt nwn, i the basic s. hut down reac t ivi t y re<pii rernent. f or the core is antisfied niul the f St andby 1.t quid Cont rol system is not acquired. Thus, the basic t enet tvit y l requ i re ment for the core in the primaty det ertalunut of when t he liquid contiel  ;

system is reqntred. j The purpose of the liquid control system is to provide the enpnhilit y of bringing the react or f rorn f ull power t o a cold, xenon f ree shut down condition assuming t hat none of t he withdrnwn cotit rol rodn enn he Inivert ed. To ince t thin  !

obj ec t ive , t he liquid cont rol syst em is designed t o inject a quant (ty of horon f t hat pt oduces n concent rat ion of 600 ppm of boron in t he tenetor core in lens Ihan 125 ininut es. The 600 ppm concesit rot lon in the enet or cot e is rerpiired t o brliin t he react or t roen full power t o n 3.0 pea cetit Ak nubcrit ical condit lott, considering the hot t o cold reactivi t y dif ference, xenon polnoning, etc. The t Iw i espil i emen t Ior innet i Ing i he hos on r.olut ion wan neleee ed Io ovci i ido 4 he i aate of renet ivl t v innert ion enuned by cooldown of Ihe ienetor Iollowlog the ,

xenon poison peak.

1ho ininimum limitation on the relief valve sett ing in intended t o prevent the recycling of 11guld control solution via the lifting of a relief vnivi nt t on l' low a piemsure. The upper limit on t he relief valve net t lugn pr oviden s.ynt em protectton iroin overpressure. [

t

n. Only on* of the twn standby liqu!d control pumping loopn is needed for '

operatis<g the system. One inoperable pumping circuit. doen not i mrned i n t e ly threaten shut down capabili ty, and renetor operat ion can continue while the  !

4 circuit in being repnired. Ansurance that the remaining system will perform  !

it s intended funct ton and that t he long t erm average availnhilit y of t he nynt ein '

is not reduced in obtnined for a one out. of two nystem by an nilowable ,

equipment out of service t inie of one third of the normal survellinnce r frequency. Thin met hod deterrninen an equiprnent out of service time of ten days, Additional connervat ism is introduced by reducing t he allownble out of ,

j service time to seven dnys, i

C. l. eve l ludiention and alarm Indiente whether the solution volume has changed, which mi ght. Indicate a posalble solution concent rat ion chnnge. 't he test intervnl han been est ablished in considerat ioni of t hene f act ors. Temperature r i

and li<pild level alnians for t he syst em are annunciat ed in t he cont i ol inom, l The solution is l' e p t at lennt 10*r nhove t he sat urat ion t errperat ure to guard i ngninst horon precipitation. The mnrgin is included in Figure 1,4.2. ,

I 110-

_l.yll'1 !!JG .00!?D1110!$ ,10lL Ol'l P,MlUt! _ .

Wl'El ll # Nil. .P l W l U l AllJili_._._ . - _ . _ _

3,%.A (cont'd.) 4.5.A (cont'd.)

? 1 i eiti and n(t er 'he dat e tbnt ene of 7. Whett it i n det et tnined t hat tne rote t he cor e spi ny subsyst emn in made on sp ay snhmyst ein is inopetnble, tbe foutui to be inope nhle Iot any operable eos e nptny r.nbs y n t ein niul t cas.on, coot itoied I ene t or opet nt inn t he I l'Cl subsvnt om shnll be vet i f ic<l l in petininniple dnilog t he sncreeding to be opetable t ermed i n t e l y . 't ho

. even days. pi ovide <1 t hnt dnt Ing noch

. opernblo rote rpray tuihnynt eni thnl l teven dayn al' netIve component 4 of be ve t i i 10:1 ta be opttable dally the other ro'o s.pt ny nnhnynt oin and theteaftet, netIve componctit ti of the I PCI sohnynt om mul t he illenel genet at ot s ate opetable 3 1 PC] onht y N t ein te?.tltin shall be nn T, P,o t h  ! PCI e.nb t y n t e m n 'hnlI he iol1own opeiable j t. e m l'te<pieto y (1) ptiot to t e ac t o r n t a t- t op ( t om a, ';imul a t ed Duce /Upetaling n t,old t,.olull t l o n , ei:r e p t an Atit omat le Art nat loit t..vrle F.pe c i f l ed in 1. 2 2 . h . l 01-

,l.ent (2) when thete is irradiat ed f uel h. Pump Opetability Duc e /niont h in the vers.el aion when the t eact en ventel pt ostut e 15. c Mot ot Oper.ited unre/ month gtcatei than a t mo! phe t ir Valve Opetahl1ity pi e va n e , except an pecifica i n 3. 5 A .4 aint 3. 5. A. 5 he l ow , d. Pump l' low Pate onec/ t mont hn During ningle pump I.PCI, each Hilu pump shall delivet at leant / /On Gilt but no mote t han F.400 Gill ar,a i nn t n n yr,t r m he tul c<pil va l ent to a scartor v e s r.e l pt enut e of /0 psid above

<h ywell preunt e with wat er level below the jet pumps At the s nine eocult t ions , two 1.PC I I!ow shalI be at leant 15,000 G111.

e P oc i renl ai loti pump dinrhatne valve-nhall he tested varh iofueling outage to verifv inll open ta f itl l c l o r.e d in t -

N reconds

4. When it in dr t e rin i ned t hat otu- of

/. . I t e.m cuid a f t < i the date t hnt one of the Hillt ( i .PC I ) pun pn is inopeinble the PilR ( l.PC I ) pumpr i? erade 01- at a t inte when it i! torpilted to ho foutui to be i nopei ab l e ior any opetable the i e ma l til ng netive l reacon, cont itumd i ear t nr opernt t on componentn of the 1.PC I nub e y n t enm ,

I' pe l fH l t n lill e olil V di t t ( 11f, ihe the r ot)I a I nfre11t roollog 'uhnyntom .

r ucre eding i hl r t v days pr ovided i hat atul bot h rot e spiny cyttrmn chalI be dutinn su< h Ihitiy dayn tbe ve t i f letl t o be opeiable imme<ll a t e l v l

, <. , i n i m n ,, o v,. ....,-non,. o. t h, amd t h,. ,ei .do e u ci pu,s da n v 1 Pt.1 ni.h e , e t o m ,u ut al1 act Ive tbeicafter l

< on ponent n of hoth cote spi ay .

' i d * *. y e; t e m n a t u l t l a dletel yetu'tatot'n ,

ate opeinhie l1

- 1 1 '. -

1

.1, Hill .llMU Millll(TUi_1 VB J1'l 1M1101( ___ _ _ . MT81;1Ll/dKL_}19VlfdMLUl3 3,5 A (Cont'el.) 4.5.A. ( Cotit ' <l . )

5. Pi oin n nel alter the cla t e that ette 5 When 1t is <1et et mlnert t hnt the 1PCI l .im i subsvs t < m in tr aile or ininut to subsp t ein in i tu.pe t able , hot h < of e he inopeiable (ot any 1enton, spt ny subsys t enm atul Ibe cont niturient

(^ (itll l tu tt'll i e a r tfit filtc I a t litil iN r oo l I tif, 8.illin y '. t t itt niitil 1 lit

• ye t i I \ eil pe n nil n s i bl e only clut i nr, the to be opetnhle ( muicill a t o l y ntul <1n t l y r uc c e ecil or- 1 'lav s , util e s s 8. t t r. thetenfter

.nonet inntle opetable, provitlect t hat slu r l t y', such / tiny n nil notIve cou potient n of both cete sprny suhrvstenin, t he cont alnment coolinr, tuhny s t eins ( i nc lutli ng, 2 1 PCI pturps) niul the all e s e l r,ene rn t ot s iequitetl for opeint ton of 5,uc h components

• ltnlI he Opt'l nhl e

6. AlI rectiruintlon putop <llschntge 6 All tecticulntton pump <li n c ha r r,e valveN 7 hall be operable print to valves shall be t e t, t c el for tenctor startup (or clow 1 l' operability < luting any pet itui of pe t ini t t eil eIsewhere in tbese 1:ene t on c o l el < hut ilown

. e x c e eili ng spec t Ilent lont) . 48 hourn, If operabillty tests have not been pe t i ol metl slut itig the pi ece<li ty', 31 tiny n .

7. 'I n e i ene t o r s' <d I nnt he st at t ett up with the l ilR system supplying cooling t o the fuel pool, 8 If the i cipil retti nt i, of T . 'i , A 1 , ? ,1, .'s . S . (* or / cannot he ine t , an ottlerly s nut (lown nf the reactor f.hnIl be itil t Int oil atul the reartor chall be in the c o l(1 t.ho t tlown r onill t 101) Vithiti 26 hoitt s .

B. Co.itt ititutJent A01 llin Julgys tMn._(l'llR B. Cent ,iligrent_CopJJ pg _ Sul.isys t em_. (}<llE Fe 13'i Ef Jid 0 L1 &lY1( CA120

1. 1:x c e p t nu o per i f ic<l in 3.5.h ?, 1. f.ont ninmetit Cool i ng ';nbs y n t em 1.5.B,3, niul 3.5,F.3 below hoth Test Ing shall be as follown cont niturent coollug subnyst ems loops

<.h n l l be operabic whenever J..t e m h eipacucy l i vnill a t ed fuel in in the tenctor

'/ t stel n nel t ear t tir coolant a. putep h Valve Onc e/ l iront hs t etr pe rn t ur e Is r,1 c a t e r than 2 } ?

• 1' , Opetahl111y atul pl lor t o t e n e t 01' 8' A r t up it oin n Col el 1:onell t 1 on . h. Punp Capactty Test Altet piimp Farli l'illt nervice toal ut eliance neul watea boontei piimp eve t y 'l mont hs i.ha l I tle 1 i ve r 4nOO gput .

r Ait tett on Once/5 y e n i e; drywo l I aint t o g ii ,

hearleir a nil no r r. i t. n 116-

piu O

e 4

y , , . ' .

T 5 . It (cont'd ) 4 'i . fi (Cont ' d . )

/ l'i om niul a f t e r t ho vin t e t lvit any Pill! 2. Wheti lt is de t e t mliied that any PilR

=civire watei booster puit p is ionde noivire water boo f, t e t puitp 19 or iound to be loopeiable foi any liinp e i nhl e , tbe i e mn i n liir, netIve i enton, cont l ooed i ene t or opei nt t on componetit n of the cont n i nment I ri p e t :P l fi n i h l e only thii I nf, t ile cool liif, Oubby A t enin filniI I be ve I f l ed l t u< r e e d i nr. t h i r t y d <y n , unters turb to be opernhle in*edintely nnel po'ep is sooner insole opernble weekly t het enf t ei piovided that dui l ny, such thitty

<h y n nl) ofbei netIve cortponent n of the cont al oment c ool l or. 5,ubnyn t ein aie opeinhle

3. l'i om niul nfter the ihte t hnt one 3. When one e ont nitunent cooling, containment ronliny, ruhrystem loop onbsyntem loop heronien inopeinble, Is iNHle o: I ntilMI to be Inopeinble t he opel Ahle Cnhnynt em loop FhhlI be for nny renson, cont inued ienetor vei i f led t o be npetable i nime d i a t c l y l

< pernt ion is pern>lsnible only duiInr. and daily thetenfter th* r ur r o r d i n r. seven ih y s untern such nuhsyntem loop is r onne r in *i;le opeinble, ptovided t lin t all not Ive roftpot)eilt N ol t lie o t he l' cont n i teinet)t C on I I i)r, s Uh 4 V f;1 clu 1oop, I nr } ud I of, i t n nst.ociat ed diesel renerat or , ni e opoiahlo

4. }( the rerpili e ment s of 1, 5 , tt .1,

3. 5. n , 2 o r 1. 'i li . 3 e ninio r be ice t , an oi dot ly shutdown thall be initinted and the react oi shall be in a cold shui down condi t ion wi t hin ?4 hoorn C llPC I Subsyntem C 11PC 1 Subsyn t em I_ llic }\pCl Suhty%t ein filial } be operable }, llpCl  !.Uhb y S t e m t e n t i n f, OhnlI be wheneve r t hri e in liindlnt ed f uel in perfotmed an follows therenctoi vensel , i enet or pressure is r.i o n t e i than 113 pr.1 r,, aint pt Io r i t elij 1iequetiry to i rne t oi st art up from a Cold condltlon, ,xcept as sportfled in n. S i n>ul a t ed onre /opei a t l or, 3 'i . G . / nini 1.5,C.1 helow. Automatic Cyrle Art unt loti lent

b. puitp Opciahl1ity Unr e/niont h r tiot or One rat ed onee/nonth Va1Ve Op0 inh lIiiy

-1I/-

-g. " " " " ' " " " " " " " " " ----

h 4

e 4

e * * . L -

+~ as -

+=*="+ r*

1. 5. c lirrl r,uh n y n t eni (cont'd.) 4. s C llrCl Subuyri een (cont'd.)

? Ti om neul nfIer the dat e Ihat the j t (in l'I totur iir y llPC1 Subsynieea is n nele on i out ul 1o be innpetable for nity i nnroii, d. I' low Hnte at onre/ l n.ont he conf loural tenetof oprintton in nppi ox i nia t o l y 1000 po l nit s n i b l e only during the pn i g St e ron Picsn.

tue reeding teven anyn untenn noch subty t t een in (oonet innde opcinble, e f l ow lin t e nt Onec/opetnting pioviding ihnt dusliin noch seven nppi ox itnnt el y l'io (yrle dayn all nettve compotietit s of the pnig Stenm Pi cn n ,

ADS nuhnysten., the PClc synteni, the

! PCl N uh n y s t a ni neul hot h rot t optny *lhe ill Cl punpu r.hnl I he doinnno t t n t ed nuhn y n t eins nie opni nb le t o be enpable of de livet in,; nt lennt 6750 rpm ior a p.v o t e en head 3 W1th the un vei1innre i c<pil einent n ron i espointing t o n 1 ene t ot piensnie of 4.5.C not peifoimed at the of 1000 to 150 psig ierpilitd liit e t'vn) r due to renetor

!luit dowti, a ienetof s t at t up inny be /, Who si i l in det e t inlin d I hat t he lil'Cl condurt ed pt ovidt d the appioptInte S ub >. v n t ein io inopetable the HCIC, noiveiIlance it petiormed witbin the 1 l'c l r.uh..y s t e in , niet hot h coi e 48 houts of n<bleving 150 pntg *ptny r. u h s, y r i e m % rhall lie vetifled ienetof n t enin p i e s. u n e to be opernble imn.ed i n t e l y 'l h e ItCIC nyst ein rhnlI be voi i f le d t o be

4. If the s erpil rement s of 3.5.C.1 opernble dnlly t herenf t en in entinot be ene t , an onderly shutdown addi t lon, the ADS nnhoysteni l o g i c.

I r.h n ) 1 be ini t int ed niul Ihe 1enctar shnlI he den.onnt rat ed t o be opet able piestute nhnll be reduced to 113 insediately niul dai ly t hni enf t et psig or lets within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. Penctet Core I so l nt ion.. Cool ing 1) . Ih; a r t o t _ .Co r t loo.lation Coolliin

( RCICL S_ubsys t etn .(RC.lc)l ohnyM em I 't he 1:Cic suhnvnt ein olinil be operable 1. 10: 1C Subsys t em testing shall ho whenever t hei e in li rndlat e d f uel in perfoined .v, follow-the scartor veuel, Ihe i ene t or pienbute it gt eat el than 11) pqlg, j t ein j't orpie tu;y niul prior tri t ene t or st art up fiom a Col d Con <ll t i on , excr pt as rpecified a. s i n.u l a t e d Otu e/ ope t at l og i ti 3.5,D.7 and 3.5 D.1 helow. Automatic cycle Ac t ua t i on 'le n t Il8

s e

illut lil0_G!Mli10RL10!LQf LIM 10ll JHVr11nycr n1:otnitrmr -

1. 5 . fi (cont'd.) 4.5.D (cont'd.)

lLtJll fitq(ICDCX

h. purnp Opetability Otic e/mont h

c. flotor Operat ed Onc o/inont h Valvo Operability

d. Flow Itat e at once/3 montha ,

approxitnntely 1000 i psig Stenn Frennure i

7. fl otn and after the date that the itCICS la made or found to be c. Plow Rat e at once/operat ing inopernble f or atiy tenson, continued approxipntely 150 cycle t seActor power operation in psig Stenm prennurn petnissihto only during the eucceeding seven anya provided t hat The itCIC punip rhall be demountinted ivor itig such seven dayn t he lipCJ S 19 to be enpable of delivet liin nt innnt operable. 400 gpm for a system .iend corresponding to a renet or pt ennut o

3. Wtth the surveillance requirement m of 1000 to 150 psig. ,

of 4.5.D not performed at the i required intervala due to reactor  ?. When it. is deterrnined that the itClc shutdown, a teactor startup rnay he subsystem in inoperable, the lipCIS conducted provided the appropriato shall be verified to be operable surveillance in performed within 1:nmedia t e l y .

4ll hourn of arbleving 150 pnig .

reactor st enm picanure.

4 I f the requirement s of 3. 5.D 1 (. ?

cane.ot he rnet, an ogderly shutdown shall be tultlated and the renclot pressure shall he reduced to 113 psig or less within 74 hourn. ,

I? . butnttMIL DentfM9titM19tLSy1 Lea E. AutmaL1LittlitsturianthjLSyM!39 1616 l IADItl

1. the Aut oren t i c Deprenturiention 1. During each opernting cycle the Subsystern shall he operahin whenever following tests shall he pet f otined thete la irradiated fuel its the ott the ADS:

reactor vensel and the react or pressure is greater than 113 pstg A sitnulat ed automatic net ont jon t ent and prior to a startup f rom a Cold shall he performed prior to startup condition, except am specified in after each refunling outnge.

1.S.E.? and 3.$.E.3 below.

119

_ _ _ _ _ ,_ _. _ . - _ _ . _ _ . . . _ _ _ _ . . . . ~ _ - .--

• s 1111111J10 001{L)111PJiS l'Olt OIT11ATION S UitV E 1 Ll M C 1' .. R J,10U 1 It l' H I: flT S_ .

4 . $ . l:, (cotit ' d) 4.5.0 (cont'd)

2. p roin atid aftet the date that olie 2. When it is det et tnined that olie valve valve in the n o t o tn a t i c of the ADS is inoperable, the ADS depressurization subsystem is made subnystem actuation logic for the or found to be inoperable for any other ADS valves shall be l t enson, cont inued react or operat ion demonstrnted to be operable ,

in petminalble only during the immediately. In addit ion, t he llPCI l 1 soerceding savon anyn unless such sub sys t ern shn11 he veilfled to be valve in ,annet made operable, opernble l inme d i a t e l y ,

pr ovided t hat during such seven dayn the lipcl suhaystem is opetable.

3. With the surveillnnce requi rement n of 4 . fi , D . $ not perfortned n t. the ,

toquired i nt e rval s due to tenctor

e. hut down , a enet or st nrt up inny be conduct ed pt ovided the appropriate ,

surveillance la perforreed within 17 i hout s of achieving 11.3 psig reactor I ateam pressure, i

4. If the retin t r ement s of 3.5 E.1 oi 3 5 E.2 cannot he me t. , an onderly  :

shut down shalI be ini t inted and t he t enctor pressure shnll be reduced t o at least 113 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

f. Illnitnittipw _f tr.s atil P._Crelloc atal l> Lere1Jene. McL Av/tilobility r. tlin hm ptkw_l'.t nini tLSe e l lot .alul

1. Daring any period when one diesel itin0L0nwrMrtavallah111t3 generntor in i tiope r abl e , cotit ltiued 1. When i t- is dele t mitted that one i renetor operntion in poi m i s s i bl e dienel genernt or in inopolnble, all only during the r.ucceeding seven low presnuie cort ecoling and dayn unless much diesel genet at ot i t. cont aintnetit cooling subnyst eing thall sooner made operable, provided that he verified tn he opernble l all of the low pressure core and immediately and dnily thereafter.

contninment cooling subsyst ems and in addi t ion, the operable dicact the remnining diesel generntor ahn11 generator shnll be demount rat ed t a be operable and t he requi einent s of he opetable immedintoly nnel every 3.9.A.1 are nie t . if this three days thereafter, requi rernent cannot he met, the requiremet t s of 3.$.F.2 shall be mnt.

2. Ihtring any period when bot h diesel generntorn nie inoperable, continued tenctor operation is permissible only during t.he succeeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless one diesel generator is .

I sooner innde operable, provided t hat l n11 the low pressure core and contninment cooling subsynt emn are operable nent the react or power level is r educed t o 25% of rated power and t he iequirement n of 3.9. A.1 nre met.,

1f this equ i reine n t cannot he ram t: ,

ei t her t he requi rement s r.hn11 he met or an orderly shutdown ohn11 he ini t inted nint t he renetor pinced in Ihe co n ci r. hut down rotuli t lon wI t bin 24 hout n.

-120- ,

3.5.A (%sf.fi (cout ' d. )

core spray subsyst ems and 1.PCI const itute n 1 out of 3 syst em: however , t he combined effect nf the two systems to limit excessive clad temperatutes munt also be considered. The test Interval speelfled in Specification 4.5 is I month. l Should one rote spray subsystem becoren inoperable, the remaining cot e sprny and the 1.001 system are available should the need for core cooling nelse. To nssure thnt the remaining cote spray and 1.PCI subnystems nie available, they are verified to ho l operchio insediatoly.

Should the loss of one 1.PC I pump occur, a nearly full c on pl ement of core and cont a i ntnent cooling equipioent is nyniinble. Three I.PC1 pumps in conjunct ion wit h t he rote spray subsystem will perform the core cooling function. Beenuse of the availabilit y of t he ma jorit y of the core cooling equipment , which will be verified l to be operable, a thirty day repair period in justified. If the 1.PCI subnystem in not: availabic, at leant i 1.P01 pump must be nynlinble to fulfill the cont ainment cooling f unct lon. 't he 7 day sepair period is net on thin basis.

B. Containment _ Coding.19 h fygte

'the containment cooling subsystem for CNS consists of two loopn each wi t h ? Itllit (1.0C1 ) purops anrving one side of the RilR heat exchnnger and two RilR Setvice Water Boost er Pun.ps serving t he other side. The design of the loops in predicted upon the use of one pilR Setvice Unt er Boost er Pump and ono Rl(R heat exchanger, for heat removal af t et a design basis accident. Thus, there are ample spares for rnargin nbove design condit ions, l.ons of rnargin should be avoide d and t he equipment maintained in a st ate of operation, So a '10 day out of.scrvice t ima in chosen f or this equipment .

If one loop is out of rervice renetor opeintion is permissible for seven days.

With coupenents or subsyntens out-of-service, overall core and containment cooling reliability is maintained by verifying the operability of the remaining cooling equipment. Por routine out of service periods caused by prevent Ive maintennnco, etc., the opernbility of other systems and components will be verified na given in t he Technleni Speci ficat ions. Ilowever, i f a fallute, design def iciency, et c. , enused the out of service period, then a demonstration of operablilty may be needed to nasure that a similar problem does not exist on the rernnining component s. For

exnmple, i f an out -of service period we re caused by failure of a pump to deliver rat ed capaci t.y, the other pumps of this type might be subjected to a enpacit y test, l 'Ihc purep enpaci t y test is a cotoparison of monsured pump performt ic o pnrnmetein

-125-

e s

' .i . 5 . 0 MSUi (cont 'd. )

fication to assure that when the renct or la heing nt art ed up f rom n Cold condit inn, the llPCI is not known to be inoperable.

D. RClq Sylitm The f(CIC in designed t o provide innkeup to t he nucient system as part of the pinnned oprintion f or periods when the main condenser is unnvnilable. 1he nuclear safety  !

analysis, pSAit Appendix G, shows that Pcic provides vnter to cool the fuel when feed water is lost, in all other postuinted occident n and t ransients, the AUS piovides t edundancy for the llPC1. Jinsed on this and judgement s on the rellnbility of the llPCI ,

system, an allowable t epair t iine of 7 dayn in specified. Immediate verlficat ions of l, 110C1 opernhility during RCIC outage is considered adequato be ,d on judgeitent and practienlity.

E. Atit ornall q.ye, itemirj g n t.imt Fyg(trrt.] ADS 1  ;

The litniting condit lonn for opernt.ing the ADS are derived from the Station thic1 car Operationni Analysis ( Appendix G) and a detailed f unct.ional annlysin of the ADS (Section VI.).

This specificat ion ensures the operabilit y of the ADS under all condit tons for which the not omat.ic or manunt dept essurt znt ion of the nucient system in nn essentint  ;

response to station abnorrealities. ,

The nuclear sys t ern pressure relief system provides automatic nucienr nyrtem ,

depressuttrntion for small brenha in the nuclenr nyst em so that the low pressuie coolant inject ion (1.PCI) and the core sptny subsystems can operate to protect the fuel barrier.

Because the Automatic Depressurirntion System does not provide makeup to t he reactor l primary vessel, no credit is te. ken f or the steam cooling of the core enused by the '

system actuation to provide further conservatisrn to the CSCS, Performance analysis of the Automatic Depressurization System is considered only with respect to its depressurizing effect in conjnnetion with 1.PCI or Core Spray. There are six valves ptovided and each has a capacity of 800,000 lb/hr at a net pressure of 1080 psig, The allownble out of nervice time for one ADS valve is determined as seven days beenune of the redundancy and because the 11PC15 is verified t o be operable during l this period. Therefore, redundant protection for the corn with a small bienk in the nuclear system is still avntlable.

The ADS test circuit permit s cont innad surveillance on the operable re11er valves to ansure that they will he avnlinble if required.

T. tilulRurLisw_l'r_e s.stu tn._Geq11pg. a tulkief cLCtn mtinr_Mdl abJ11t.y The purpose of Specification F in to assure that adequate cote cooling equip.

127-

- . . . _ . ._ , ._. _ _ _ . _ . ._ _ ~ _ . . _ ,_ _ . . . _ _ _ _ _ _

o

+ e

'e ,

4 . 'i FAM;.S R t_ctMent alnicut_fn9Unc.Sys tems_SMtytillnuta.Jrrsturdna The testing interval for the core and cont ainment, cooling . sys t erns is based on tiniust ry prnet ten, quantitative s eliability analysis, judgement and pract ien t.i t y.

The come cooling systems have not been dekinned to be fully tentable during opttotlon. For exnnple , in the ense of the lipC1, nut omat ic init int ton during power opeintion would result in pumping cold wnter into the reactor vens.el, which is not desirnble. Complete ADS testing during power operat ton enuses an undenirnble loss-of coolnut inventory. To incrense thn availability of the core and cont ninment cooling syst ems, the components which tenke up the system; i.e., i nn t.t uine nt a t i on ,

pumps, valven, etc.. ni c t est ed f rerpiently. The pumps nnd anot or operat ed inject ion valves nic nt no t est ed ench mont h t o annnre t heir opernbilit y. A simuint ed nut ornnt ic actuntion test once each cycle cornhi ned with frequent tests of the ptunps nnd injectinn volves is deemed to be adequate testing of these systems, k' hon components and subsystems nie out-of-service, overall cose nnd containment cooling relinhility is maintained by verifying the operability of the temnining c<tulpment. For routine out of service periods caused by pi event.nt ive inn i nt ennnce ,

etc., t,io opernbilit y of other syntems nnd components will be verified an given in the Techntent Specifications. Ilowever, if a failure or design deficiency enused by outage, then a demonstration of operability may be needed to rusure that a generic problem does not exist. For example, if an out of service period were enus:ed by fnllut e of a pump to deliver rated enpacit y due to n design defielency, the ot her pumps of this type rnight be subjected to n flow rate test.

l l

1 131-

n

= l j , e

,JyHRMQ COND1TIGl POR OprPAT10!( SURVEIUMCE !!LOUIRLH0tfr _ ,

L l

3.7.8 (cont'd) 4.7.B (cont'd) i

h. *t he resulta of l aborat ory catbon b. Cold Dop testing shall be performed  !

sample annlynis shnll show ;> 991 after each coropicte or pattial radionetIvo methyl lodide removal replacernent of t he llEpA filt er bank wit h inlet condit tons of: velocity or af t er any si n uet urnt innint ennnco <

M42 llH, Pl . 75 ing/in' Inlet methyl on the systein housing. I lodide concent rat lon, 7.70% R.it, and ,

<;3 0 ' O . c. linlogennt ed hydrorntbon testing  !

shall he pe r f orrned after each l

c. Each fan shall be shown to provide cornpl e t e or partini repinecment of  !

1/R0 CHP fl0%. the charconi adsorber banl: or af ter i any s t.ruc t ui n ) inn i nt e nn ne e ett the  :'

3, prern and after the date that onn ,4ystem housing, HLatidhy gas t reat ment syst em is made or found to be inopeinble for any d. Each syst om abalI be operated vit h reason, reactor ope rn t.i on is the henters on at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> perini s s ibl e only during the every mont h,  ;

succeeding seven dnyn unless anch l nystem is sooner undo operable, n. Test sealing of ganitet s for housing ,

provided that during such seven days doot a downst ream of the llEpA fli t ers '

nll nctise componetit s of the other nod charcoal ndmotbets shall be  !

s t andby ga s treatment system, and performed at, and in conformance ,

its associat ed diesel generator, with, each test performed for shall be operable. compliance with Speciffentton 4.7.n.?.n and Spect f tent ton roel handllug requirements nre 3.7.B.2 n. ,

specified in Specifient. ion 3.10.E.

3. System drains where present shall be

4. If these conditions cannot be met, inspected qun rt erly for adequate p r.>c edu r e s ahn11 be initinted water level in loop senis, ,

i nonadi n t e l y to cu nbl i sh reactor '

conditions for which the standby gas 4.n, At least once per opernt ing cycle treatment system is not required, automatic initintion of each branch ,

of the st andby gas t reat ment system shall be demonstrated.

1

h. At lenst once per opernt.ing cycle mnnuni opernbility of the bypass volve for filt er cooling shall bo demonstrated, c, k' hen one standby gas t reat ment. 'i nynt ein becomon inopeinblo Ihe ofher standby gns treatment nystem shalI be verifled to be operablo immediately and daily t hereni t e r.

A demonst ration of diesel generator

• opernhillty 1a not required by this spec!ftentlon.

C liteonda ry Sont a1intTnt, C. Eienendo.ty._CMt* ! I utnent,

1. Sec ndary containment integrity 1. Secondary cont ainment suivoillance shall be maintnined during all modes shalI be pe r f ornad an indicated '

of pinnt. operation except when all below: ,

of Ibe followli,n condit ions are mot .

5 16Sn-

(

e

, e

• e 4 ? i . h /, 4 . / . C

+ J'.4 '4 5 e

wi t h nti nih oi be nt epin l f f l eil necot eling to Tnble 5.1 of AIM I IP404. l Wu . 1he i <-pi nr e me nt tiny foi the nitr oi be s tiav re emveil for the tent s houlcl mee t the onme tulso t be nt epial i t y . Tentt o f I he 111 PA f i l t e r e, wi t h linP net osol shnll br pe t i ol meil i n ai rotilntm e to AtG 1 th l O 10 f.0 Any filteis f otnul cle f ect ive Slull be t eplareil wi t h ii1t et n <piniifIcti poirunnt t o Per,ulat on y Ponit ion C 4 . (1. of Por.nlatony cu l <le 1.5/,

1:ev i s i on 7, ll.o rh , in/8.

All elemente of the he.it e s rbnul<l be elemonc t i nt eil to be functional neul opeinble ilot ing t he test of hentet enpael t y. Operatioti of t he heat ei n will pt event ico l o t ni e huililup in t he f i 1 t e t s atul nilnot he t sy s t e m .

Wi t h cloot s cloteti anel f nti in opernt lon, bnP net osol shall be sprove el ext ei nally nlong the full linear pet lplu n y of ench torpective <lo o t to check the gasket 'enl. Any clet ect ion of bnP in t he inn exhnust r hnll be connliten cel an unarrept able tent troult nnit t he gasl+ts s epali eel niul t en t t open t eil .

If cy n t ein <ltn i nn nie pi e nent in t he f i l t e r/rulsot be r batik n , loop realn nio t t he u s eil wi t h n<leeptat e watet level to prevent by pass l e n k n r,e Itom the b n n h, .

If ni rni f t enni paintinn, fite or chemient tolense orrut n such thnt the illTA i11tet or charront ailcothet c ou l ti be r on>e cent nuilant ett irom t he fumos, c hoin t r a i n et Ioieigo mat e r ial , the nnme tecto a n<l snwple nnnlysit ohnll be petformeel nn teepilisit for opeintional oro lhe <1et er minnt t on of nigni f irnnre rhnll be inzute hv t he opeiatut on elut y ni tbe iime of tlu f or tilent P oow l eitge nb l e ctaf( membeio shoulet be . oio.u l i e<l pi lot to mation t his <le t ri mina t i on.

twmonnt rat ion of flu- not oinn t i c ini t iat inn capability anil opernbility of fillet rooling is ni c e r, r n i y Io n e nu t'e syn t e in pei i on malice capnhility. If ono o t niplhy gns t reat nmnt nyclem ic inopeinhle, the other nystem'n opei nbi l l' y in vei l f leel <lal ly . l 1hlt substanilates Ihe wall nhilI t y of f he opet able cyst om ntul t hum i ear t oi opeiatlon or i e f noI log opei at init c ait cont i nne Iof n i lini t ett pe r l aul o f t lino

1. / . !: 1, 4 . 7 . li TM S I .'i Pi lical V Cont a i nment I noiat lon Vnives

])ntili j e lro]ntlOtgya)veq at'e p1 oy{tjeg] of) } l tie s, potte( rat { ng ( }ge pt { fiia] y q 03){ a l tnimt){ ;) t pl opt n to the f i er spare of I he rout altunent . Closure of one of Ihe valves in carh Iine voul<l be sufflelent to maint ain t he tot egrit y of t he piersute suppresolon r, y s t e ni .

Aut om,t i c init int ion is rerpiire<l to minimire the pot ent i al leakage pathy from the cent alnment in the e ve n t. of n loss of-coolant acc lilent .

1he omximum closuie times for the automatic isoint ion valven of the pilicary C on t n i titDD!il Diul I e n<' t o r VesMel i solnl j oil c on t. t o l 8.y S t i tri have lic e i t Ee ler t ett i ti conslilernt lon of the desi gn liit ent to prevent r ot e uncovering f ollowing pipe bients out slete the pt imni y cont n lim.ent and the need t o cont nin ie1ented finnion pi oihir t m following pipe breaks inside the priinary c ont ninment .

1 he e.e valves are highly reliable, have a low sei vire re< pili ement , atul most nie n'O iln l l y Clo?ed, The ini t i nt i ng s e n F o r !. niUI nsNorint ett trip Chanuel5 nie alto therini t o ib n onnt rnt e the rapability foi not omat ic isolation. The t e s t int er "al of once per opei at log cycle f~or cut omnt ic init Int ion

- 185

s e

• #'o

,J9111 t lR 11 Hl' LT J O!$_l PIL0 rl M11W . MTVl:111NM 't'WlAIJ1ULM_. _ __

3.10,B (f:ont 'cl) 4.10 (Cont ' <1)

4. Ihn lug spital t elonel, SIMI ,

ope t abi li t y will i+c ve r i f i c<l by  !

nsInn a poitnhle externnt source eVelV I / llolii N tilit 1 I (he i o f[u l i e tl ,

aniount of f ue l i n l otitleil t o ninliit nin 1 rpn An an alternntive to the nhove, two I 6ic 1 anrettihl (en vi l I be lontlett ill tilI f ei'eist Ce l I N Colit til flitif cont i ol b l neto s ni outul ent h SRh to eht alti the i espil i etl I cpf! Viet il ibese two nuenihlles have been i l omleil, t!te 1 epn t e< nut s enient is tiot slet emit al y . O, $pppl I tie ) _ jlpr }_Wp t. eti _ l, eve {

c, SpentrueI r.001 Unt et 1,cve1 Whenevet li g nell at ert fuel is st oi e<1 Vhen i t i mli n t eel fuel is cl ot tal (ti l ei the S pe tit fuel pool, the pool t he spent f uel pool , t he wnt ei level l watei level shall be inn i nt n i ne.1 a t shnli he s crortle<l ein t ly .

or above SY nhove t lie top of the foni, 11 T lino I,I nil t a t i on li s milat eil f ool shall not he hatulleil lit or above the tenetor ptlor to

/4 hosti s al t et i enet os ohntdown, I

l'. . S t, nipihy Qt h . Tl eNij ttetR. Sy(i t.ptn 1; S t.nnelby_ y RifLit en UtleHL Syn t chi l's ein anel niter the <lat e t hat oto-etatuihy gnN I t eni fnent A y n t e sti i m inntle Wheti one n t ninthY gan Iiontnmut oi ( ous ed i ce he I nopei nbl e* foi ntly sys t ein beroine t inopeinble, t he o t hn t' i e nt.oti, f ool hntulling is pelinissible sininihy nas t s cat nient n yn t ein i, hall only thit isig the sticceedi tir, seveti dnys untenn such n ys t eni is soono he verified i niined i a t e l y nini daily theteniter, to be opei nbl e l,'

nuole ope rabl e , piovided tlint. during A detuotistintton of diesel generator such neven einyn all active opeinbility in not t orpill ed by t hi n ron ponetit s of t he ot he r st atulhy gan speciftention, t i ent rnent sys t eni, nini itn associated dierel gener at os , t.hnll be opernble.

At lenst otic dierel generator t. hall be ope i nb l e <hning fuel handling operntlovet. 'lhls one diesel shall be capnble of supplying power t o an opeinble Standby Gnn 'I t e n t ine n t Syn t ein ,

l' f oi 0.. S.t Antihy tioo l l pg. .Sy s ( pmq .

lini lug n re lov ll tig otit age , tefueling opeiation nmy root linie with one Cole f.pi'ay N y k t 01n or t lie 1,pC I thotlf*

of IUIR inopernble foi a perlott of 10 dayn. l.e i o, *'e in pe rini t t ed I

wi t h t he t,uppi esn ion ebanibe r (Irn i ned

! piovided an opernble core *. p i n y nytt ein or nnhsynt ein of t he 1.pCI inode t#l l!jd5 ID n] l {lH11 10 a h' e /t %lle t j oli

<.n the rninleiisn t e stofage t ntil:

cont aining ni lennt l '> 0 , 000 gnilonn

(?l4 ft. I rulica t ed levn)) .

l

c

, 4 '

, 1"AII.T1!KLO.M'111WLJ DJLOllIMlJ(H_ _.- - E!11VL11JAEL_Jil.WJJUJ11X1J 3.17 (cont 'il) 4.17 (cont'il)

In . P r o c t on_ltu l l slJ ng __Gl o t; td ,_f eg l {ng li . Portrion_14L10l og ._glo sal._ _Gml l og Wa t en.Sn te m_IIO hl h'attrJysi tJLmlio

1. bot h ren'e t or buil < ling c lost (I cool i ng 1. REG system Testing water loops anel their n r. s oc i n t e(I j.t tm D.cquency pompn s.hn l l be opernble whetiever li i ndint eil f uel is in t he versel or n, pon.p opeinbility On 'o/ lion t h the f. pe n t inel pool, except an li , llot o r opetatcel Onr e/llon t h meerificel in 1.17. h. 2 nnel 1.12 . It , 3 Valve Opernbility below, e pump flow inte Once/ l n,ont hs Each pump shnll nnel ni t e r pturp delivet 11/$ Opm mn i nt ennner-at 65 paid, (l . System henit tank Onlly level rint I be monitoted.

7. l'i otti and a t t e i- the dat e that af ty 7. Vht t) It In determinetl that any romponent in ene loop becomes netIve component in an Rf C loop in Inoperchie continueel renetor inopernble, nll component s in the operation in poiminible during the other loop thall be vetified l norceerling i hi t t y days "Iovidetl Ihat openable timeell a t e l y neut we ekly ebu inn such thisty ..nyn n11 the thetentter eomponent9 of ihe of her loop noel t be art Ive component s of t he engineered r:a f eguns ein compnitwrnt cooling synt emn, the d i e r.e i gene r n t on an ser i nt eil with the operable loop are opernble

'l h e nilownble ternia t(me does not apply when the s enrt or is i ti the

f. hut down tende atnl enetor pressure is less than 75 psig.

3. not h rene t on hul idinr, r ior.cel cooling wnt er loopn vith one pump per loop charl be opot able as st at ed in 1 17.h.1 niul 3.11.h.7 nhovn during reactor hend olI opetatlons rerpii r t on 1.Pf:1 or Core Spray Synt ern emnllability or nervice watei rooling nh.ill be evallanlo, 4 If the r erpii re ment n of 3.17.h.)

tinough 3.12.h.1 ennoot be met, the renetor shall he rhutdown j :1 si n oidenly n.n nt :e r and in the Cold sino down romil t ion wi t hin 74 hoorn or operat lonn t e< pili Ing 1.I Cl or core o pi n y r.yntem nyn i l nbi l i t y r.hn] ] he haited.

I l

1

- 21 '> h -

s 0 O e

e J-]d11)!!!LCDF!!1T.101?S lQRRITAllpli 1,l'RY1H1 AUGJ1!A11EinUQ S _,

3.17 (cont ' d) 4.12 (cont ' d)

C F e tv_!r e._Wi ctSy s t r. rn C. .Sxtyltth'nieLFynt e n)

1. I',o t h P. e r v i c e water subsystems with 1. Service Water r,y s t ein T e n t i hr.

both pumps in each subsyst etn shall be opernble whenever it r ndlat ed f uel j uni j'unu l poo l, in in the vensel or spent fact pool niel pt los' t o Ienc t on s t nr t tip except n. puitip Ope t ahl1 i t y Onc e/llon t h as 7.pecified itt 3.12.t!.2 helow.

h. 110 t o r Ope n t e d Onc e/lloit t li Valve Opetahllity c l'itrop di a.chn t r,e Ofice/ 3 nietit hs head testn

2. I' rom etid aftet the date that atly 2. When it is d e l e t itil ned thnt nny con postent l ti the setylce watet r e t'pil l e d betylce water n y n t e ni s ub r.y s , in tride or fotend to be comportetit is 11opetable, ihn inopet .1' foi eny tentoti, cotit I tiued opetable setvice water nuhn ym t eni tenet operation in petmissible cornponent s shall be verifled to be the succeed itir, t hi t t y dayn operable isnmedint ely nnel weel ly dut ptovli itly{' d t h 'i t du r i tif, such thitty thetenfter tinys 1 #ic t i ve componefit s of the

• ot he r}#ervice water nithsys t ein atul it s as ocjated diesel p,enerator are opernb!c.

3. I f t he rerpil v enient of 1.17.C.1 atul 3.17. C . 7 caritiot be met, an orderly shutdovn of the tenctor shall be initit4ted and the reactor shall he in the Cold Shut down Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. linilf1LRoom , Vent j )Ild on It bo t.t e ty_.llooni_.Ye ntil nt l on

1. luttety inom ventflatton chall be 1. The sparn hattery room ventilntton operable on n cont inuous basin f an shall be checked for opei nbilit y whenever speciflentton 1.9.A is once/ week i cipii red t o be sntisfied.

? Ft om nr i af t er t he date that either o f t he '.wo ha t t e ry ronin vent lans is uvule of f outid t o be inopernble fot a tiy 1 e n s oli, c en t i tined reactor ope! a t loti I s periPI o n t hle duritif, t he suc cee ditir, / days .

3 If t he rc<pil ement n of 3.l?.D.1 f. ?

cnquot be ino t , an orderly e.hutdown of the t e ne t.o r sluil l be i ni t. i n t ed and the teactor ebnll be In Cold

'; hut dowti uttbin 24 houts.

l -?lSc-l l