ML20006C436

Proposed Tech Specs,Consisting of Tech Specs Change Request 89-17,eliminating Redundant Testing Requirements from Section 4.5, Core & Containment Cooling Sys.

ML20006C436
Person / Time
Site:	Peach Bottom
Issue date:	01/30/1990
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20006C421	List: ML20006C420 ML20006C422 ML20006C436
References
NUDOCS 9002080039
Download: ML20006C436 (53)

Text

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,, , ATTACMENT 2 j 4-(

l PEACH BOTTOM ATOMIC POWER STATION i UNITS 2 and 3 i l

J Docket Nos. 50-277 50-278 ,

i License Nos. DPR-44 l DPR-56 I i

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1 REVISED TECHNICAL SPECIFICATION PAGES i

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List of Attached Pages  :

59 139 l 120 141 .;

125 205 126 209 128 210 128a 214 ,

128b 216a

• 129 216a-5 *

-130 240t 131 254 134 256 >

135 257 136 -

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1 9002080039 900130 PDR ADOCK 05000277

.p PDC

Unit 2

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PBAPS E LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.2.D. Radiation Monitoring 4.2.0. Radiation Monitoring Systems-Isolation and Systems-Isolation and '

Initiation Functions initiation functions

1. Reactor Building Isolation 1. Reactor Building Isolation '

and Standby Gas Treatment and Standby Gas Treatment

-System System L The limiting conditions Instrumentation shall be j' for operation are given in functionally tested, cali- l Table 3.2.D. brated and checked as indi- '

cated in Table 4.2.0. l System logic shall be functionally tested as J ind1ceted in Table 4.2.0.

i ' E. D_ryg g Leak Drtection

. I. Dryye_1_1 leak Detection

.The liniting conditions of Instru--Antetion shall te operatton for the instru-calibrated and checked as

mentation that nonitors indicated in Table 4.2 E.

drytell Irak detection ~ere given in Section.3.6,C,

'< Coo'lant Larkage". ~

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i Unit 2 PBAPS I ia 3.4 BASES l,

STANDBY LIQUID CONTROL SYSTEM The Standby Liquid Control System is also required to meet i 10 CFR 50.62 (Requirements for reduction of risk from anticipated transients without scram (ATWS) events for i light-water-cooled nuclear power plants). The Standby '

Liquid Control System must have the equivalent control ,

capacity of an 86 gpm system of 13% weight natural sodium ,

pentaborate in order to satisfy 10 CFR 50.62 requirements.  !

This equivalency requirement is fulfilled by having a system t which satisfies the equation given in 3.4.B.3. Each parameter (sodium pentaborate solution concentration, pump flow rate, and Boron-10 enrichment) is tested at an interval  ;

consistent with the potential for that parameter to vary and

• also to assure proper equipment performance. Boron-10 enrichment testing is only required when chemical addition  :

occurs since change cannot occur by any process other than i the addition cf new chemicals to the Standby Liquid Control Solution Tank. ,

Normally, pre-mixed dry eodlun pentaborate enriched in \

Boren-10 is added to dominarr.11 red vater to form the velution. The pre-mixed soditu pentaborate is purchased with certification of its Boron-10 enrichment. The solution could be made by combining natural borax and Boron-10 enriched boric acid in stoichiometric quantities in  ;

demineralized water. Since both the borax and boron-10 i enriched boric acid have known Boron-10 enrichments, the resulting Boron-10 enriched sodium pentaborate also would have a known Boron-10 enrichment. This process is adequate  ;

for use in determining immediate compliance with 3.4.B.3 i following chemical addition. The solution Boron-10 enrichment shall be subsequently verified by analysis to be acceptable.

l The volume of solution stored is checked at a frequency to assure high reliability of the system. Solution level is &

indicated and alarmed in the control room.

C. 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.

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, PBAPS W -'llHillNG? CONDITIONS:FOR OPERATION SURVEILLANCE REQUIREMENTS P

1) '

3.5.A Core Spray & 4.5.A Core Spray &

,LPCISubsystem(cont'd) LPCI Subsystem (cont'd)

Both CSS shall be operable Item frequency whenever irradiated fuel is in the vessel _and prior (d) Pump Flow Rate Once/3 months to reactor startup from a j Cold Shutdown condition Each pump in each-loop shall l 1

-except as specified in deliver at least 3125 gpm 1 3.5.A.2 and 3.5.F.3 below: .against a system head i corresponding to a reactor vessel pressure of 105 psig, (e) Core Spray Header l AP Instrumentation  ;

Check Once/ day l Calibrate Once/3 months (f) DELETED

2. From and after the date 2. DELETED that one of the core l 1

spray subsystems is i made or found-to be inoperable for any reason, l continued reactor operation i is permissible only-during the succeeding seven days provided that during such  !

seven days all active I components of the other core spray subsystem and ,

active components of the LPCI subsystem are operable.

3. LPCI Subsystem Testing shall be as follows:

Item Frequency (a) Simulated Automatic Once/ operating Actuatlon Test Cycle (b) Pump operability Once/1 month

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l'IMIIIN'G CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS E 3.5.A Core Spray and LPCI 4.5.A Core Spray and LPCI Subsystem (cont'd) Subsystem (cont'd) 3,:Two independent Low Pressure item Frequency Coolant Injection (LPCI) subsystems will'be operable (c) Motor Operated- Once/ month with each subsystem valve operability comprised of:

a. (Two 33-1/3%) capacity pumps, (d) Pump Flow Rate Once/3 months

b. An operable flow path Each LPCI pump shall deliver capable of taking cuction 10,900 gpm agtiinst a system head from the suppression pool corresponding to a vessel pressure and transferring the water of 20 psig based on individual to the reactor pressure pump tests.

vessel, and

c. During power operation (e) DELETED' the LPCI system cross-tie valve closed and the associated valve motor operator circuit breaker locked in

.the off position. '

Both LPCI subsystems shall be operable "

whenever irradiated fuel is in the reactor vessel, and prior to reactor startup from the Cold Shutdown Condition, except as specified in 3.5.A.4 and 3.5.A.5 below.

4. From and after the date that one 4. DELETED of the four LPCI pumps is made or-found to be inoperable for any reason -continued reactor operation istpermissible only during the succeeding seven days provided that during such seven days the remaining active components-of the LPCI subsystems, and all active components of both core spray subsystems are operable.

5. From and after the date that one 5. DELETED LPCI subsystem-is made or found to be inoperable for any reason, continued reactor operation is permissible only during the succeeding 7 days unless it is sooner made operable.

provided that during such 7 days all active components of both core spray subsystems and the remaining LPCI subsystem are operable.

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( ' IM NING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.B Containment Coolina 4.5.8 Containment Cooling System (cont'd) System (cont'd)

J 2. From and after the date that 2. DELETED

' any two'_HPSW pumps are made or.

-found:to be inoperable for any reason, continued reactor opera-tion-is permissible only during the succeeding thirty days, unless such pump is sooner.made operable, provided that during such thirty days the remaining HPSW pumps are operable.

3. 1From and after the date that 3. DELETED

any three HPSW pumps are made or

-found to be inoperable for any reason, continued reactor operation is permissible only during the. succeeding' fifteen

' days.unless such pumps are sooner made operable provided the remaining HPSW pump is operable.

L 4a. The torus. cooling mode of 4. DELETED RHR shall>be operable with two independent-loops.

Each loop consists of:-

(1)~At least one operable RHR, pump.

(2) An operable flow path to

. pump water from the torus through an operable RHR heat exchanger and back-to.the torus via the flow test line.

L (3)_An_ operable ~HPSW flow path through the operable-heat exchanger associated with the 4 operable'RHR pump. .

b.-With one torus cooling loop inoperable. restore the inoperable }

j Lloop to operable status within seven days.- i l

l -c. With both torus cooling loops einoperable, restore at least one loop to operable status

.within eight hours. )-

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,. . , , PBAPS N IM1$1NG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

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3.5.B~ Containment Coolina- 4.5.B Containment Cooling System (cont'd) System (cont'd) s ..

l' Sa;-The'drywell: spray mode of RHR 5. DELETED n

L shall-be operable with two. independent loops.

Each' loop consists of:

L (1) At least one operable

' RHR pump.

'(2): An operable flow path toLpump water from the t

H _.!orus through_an operable

.RHR heat exchanger to the drywell spray sparger.

'(3) An' operable HPSW flow path through the operable heat exchanger associated with the operable'RHR pump.

b. With one drywell spray loop.

inoperable, restore the-inoperable loop to. operable

-status within seven days.

c. With_both drywell spray loops inoperablei restore-at least one loop to operable status

.within eight hours.

-.6a. The torus. spray mode of RHR 6. DELETED shall be operable with two independent loops.- Each loop consists of:-

s (l)' At least one_ operable RHR pump.

-(2) .An operable flow path to' pump' water from the torus through an operable:

q RHRfheat exchanger to L

the torus spray sparger. l (3) An operable HPSW flow path  ;;

through the operable heat exchanger associated with I the operable RHR pump.

b.;With one torus spray loop inoperable, restore the  :

inoperable loop to operable l !

~ status within seven days. k l c. With both-torus spray loops inoperable -restore at

'least one loop to operable status within eight hours.

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'd LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3;5.B Containment Cooling 4.5.B Containment Cooling-

, System (cont'd) System (cont'd)

7. If the' requirements of 3.5.B cannot be met, an orderly

shutdown shall be initiated'and the reactor shall 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 />.

CL HPCI-Subsystem- C. HPCI Subsystem

1. 3The HPCI Subsystem shall be 1. HPCI Subsystem testing-operable whenever there is shall be performed as follows:

irradiated fuel in the reactor l vessel, reactor steam pressure item Frequency is greater-than 105 psig, and prior to reactor startup (a) Simulated Once/ operating from a Cold. Condition. Automatic cycle except>as specified in- Actuation 3.5.C.2 and 3.5.C.3 below. Test

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'; LIMillNG CONDIT10N'S FOR OPERATION SURVEILLANCE REQUIREMENTS --3.5 C- HPCI Subsystem (cont'd.) .4.5.C HPCI Subsystem (cont'd.)

Item Frequency (b) Pump Once/ month Operability (c)MotorOperated Once/ month Valve Operability (d)FlowRateat Once/3 months 1000 psig Steam Pressure (e)FlowRateat Once/ opera-150 psig _

ting cycle Steam Pressure The HPCI pump shall deliver-at least 5000 gpm for a system head corresponding to a reactor pressure of 1000 to 150 psig.

2. From and after the date that 2. DELETED the HPCI Subsystem is made or found'to.be inoperable for any reason, continued reactor operation-is permissible only during the succeeding seven days unless such' subsystem is sooner.made operable, provi-

-ding that during such seven days'all active components of sthe ADS-subsystem,,the-RCIC system, the LPCI subsystem-and both core spray subsys-tems are operable.

3.- If the requirements of 3.5.C cannot be met, an. orderly shut-down'shall be initiated and the reactor shall 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 />.

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[LIMITINGCONDITIONSFOROPERATION SURVEILLANCE REQUIREMENTS 3.5.D Reactor Core Isolation' 4.5.D- Reactor Core Isolation I Cooling (RCIC) Subsystem Cooling (RCIC) Subsystem l l; 1.'The RCIC Subsystem shall be 1. RCIC Subsystem testing shall -

1 operable whenever there is be performed as follows:

irradiated fuel in the reactor i vessel, the reactor steam pressure Item frequency i is greater than 105 psig, and  ;

prior to reactor startup from (a) Simulated Once/ Operating a Cold Condition, except as Automatic Cycle specified in 3.5.0.2 below. Actuation Test *

(b) Pump Once/ Month Operability t (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 Cycle-150 psig Steam Pressure **

(f)Verifyauto- Once/ Operating ***

matic transfer Cycle from CST to suppression pool on low CST water-level

2. From and after the date that 2. DELETED l- the RCIC Subsystem is made or found to be inoperable for any reason, continued reactor power opera-tion is permissible only during the succeeding seven days provided.that during such I seven days the HPCI Subsystem is' operable.

3. If the requirements of 3.5.D *Shall include automatic restart cannot be met, an orderly shut- on low water level signal.

down shall be initiated and the reactor pressure shall **The RCIC pump shall deliver be reduced to 105 psig within at least 600 gpm for a system 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. head corresponding to a reactor pressure of 1000 to 150 psig.

• • • Effective at 1st refueling outage after Cycle 7 reload.

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'* LIMITING CONDITIONS FOR OPERATION- SURVEILLANCE REQUIREMENTS 3.5.E Automatic Depressurization 4.5.E Automatic Depressurization <

System (ADS) System (ADS)

1. The Automatic Depressuriza- 1. During each operating cycle tion Subsystem shall be oper- the following tests shall be

'able whenever there is irra- performed on the ADS:

diated fuel in the reactor l vessel and the reactor steam A simulated automatic pressure is greater than 105 psig actuation test shall be and prior to a startup from a Cold performed prior to l Condition, except as.specified startup after each '

in 3.5.E.2 below. refueling outage. i

2. From and after the date that 2. DELETED one valve in the automatic depressurization subsystem is made or found to be inoperable for any reason,-continued reactor operation;is permissible only during the succeeding seven j days unless such valve is sooner made -

operable, provided that during 4 such seven days the HPCI subsystem is operable.

3. If the_ requirements of 3.5.E

{

cannot be met, an orderly '

shutdown shall be initiated and the. reactor pressure shall be reduced to at least 105 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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',' L3.5. A'. BASES tore Spray and LPCI Subsystems Core Spray Subsystem (CSS)

The CSS is provided to assure that the' core is adequately cooled following a loss-of-coolant accident. Tworedundantloopseacgprovide adequate core cooling capacity for all break sizes from 0.2 ft 'up to and including the double-ended reactor recirculation line break, and i for smaller breaks following depressurization by the Automatic DepressurizationSystem(ADS).

The CSS specifications are applicable whenever irradiated fuel is in the core because the CSS is a primary source of emergency core cooling after the reactor vessel is depressurized and also provides a source for flooding of the core in case of accidental draining.

With one CSS inoperable, the verified operability (see 4.5 Bases) of l >

the redundant full capacity CSS and the full capacity Low Pressure i L Coolant Injection system provides assurance of adequate core cooling

,_ and justifies the specified 7 days out-of-service period.-

The surveillance requirements provide = adequate assurance-that the CSS-will be operable when required. Although all-active components are '

testable and full flow can be demonstrated by recirculation during reactor operation, a complete functional test requires reactor shutdown. .The pump discharge piping is maintained full to prevent water hammer damage to piping and to start cooling at the earliest  ;

moment.

Low Pressure Coolant In.iection System (LPCIS)

The LPCIS is provided to assure that the core is adequately cooled following a loss-of-coolant accident. Two loops each with two pumps provide adequate core flooding for all break sizes from 0.2 ft2 up to and including the double-ended reactor recirculation line break, and-

,for small breaks following depressurization by the ADS.

The LPCIS specifications are applicable whenever there is irradiated fuel in the. reactor vessel because LPCIS is a primary source of water for flooding the core after the reactor vessel is depressurized.

With one LPCIS pump inoperable, or one LPCIS loop inoperable, adequate core flooding is assured by the verified operability (see 4.5 Bases) of l the redundant LPCIS pumps or loop, and both CSS loops. The reduced redundancy justifies the specified 7 day out-of-service period.

' The surveillance requirements provide adequate assurance that the LPCI will be operable when required. Although all active components are testable and full flow can be demonstrated by recirculation during reactor operation, a complete functional test requires reactor shutdown. The pump discharge piping is maintained full to prevent water hammer damage to piping and to start cooling at the earliest moment.

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. Unit 2 PBAPS i

- 3;5.A- BASES (Cont'd). 1

'The allowable repair times are established so that the average risk rate for repair would be no greater than the basic risk rate using the l

methods described in Reference (1). Using.the results developed in 1

-this reference, the repair period is found to be 1/2 the test interval.

This assumes that the core spray subsystems and LPCI constitute a 1 out o_f 3 system; however, the combined effect of the two systems.to limit excessive clad temperatures must also be considered._ The test interval specified in Specification 4.5 is 1 month.

Should one core spray-subsystem become inoperable, the remaining core spray and the-LPCI system are available should the need for core cooling arise. To assure that the remaining core spray and LPCI subsystems are available, they are verified to be operable (see 4.5 Bases).

Should the loss of one LPCI pump occur, a nearly full complement of core-and containment cooling equipment is available. Two 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 coolingequipment,whichwillbeverifiedtobeoperable(see4.5 Bases)..a thirty day repair period is justified. If the.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 this basis.

(1) Jacobs, I. M., " Guidelines for Determining Safe Test Intervals and Repairs Times for Engineered Safeguards", General Electric Co.

A.P.E.D., April, 1969 (APED 5736)

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Unit 2 o P8APS f3.5.B1 BASES '

Containment Cooling System 1 The Peach Botton Containment Cooling System consists of the High PressureServiceWater(HPSW)systemandthedrywellspray,torusspray  ;

and torus cooling modes of the Residual Heat Removal System (RHRS).- ,

The torus cooling mode of RHR consists of two independent loops. A loop.is defined as a flow path to pump water..with an RHR pump, from the torus through an RHR heat exchanger, then back to the torus via the i flow test line. A flow path-from an operable HPSW pump through that RHR heat exchanger completes the' functional loop.

The'drywell spray mode of RHR consists of two independent loops. A loop is defined as a flow path to pump water, with an RHR pump, from the torus through an RHR heat exchanger to the drywell spray sparger.

A flow path from an operable HPSW pump through that RHR heat exchanger completes the functional loop.

The torus spray mode of RHR consists of two independent loops. A loop is defined as a flow path to pump water from the torus, with an RHR pump,'through an RHR neat exchanger to the torus spray sparger. A flow path from an operable HPSW pump through'that RHR heat exchanger completes the functional loop.

The design of.these systems is predicated upon use of 1 RHR and 1 HPSW pump for heat removal after a design basis event. Thus, there are ample spares for margin above the design conditions. Loss of margin should be avoided and the equipment maintained in a. state of operability so a 30-day out-of-service time is chosen for two HPSW pumps.

.With components or subsystems out-of-service, overall core and '

containment cooling reliability is maintained by verifying the operability (see 4.5 Bases) of the remaining cooling equipment.

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3.5.C BASES (Cont'd)

The HPCI and RCIC as well as all other Core Standby Cooling Systems

.must be operable when starting up from a Cold Condition. It is realized that the HPCI and RCIC systems are not designed to operate until reactor pressure exceeds 150 psig and are automatically isolated before reactor pressure decreases below 100 psig. It is the intent of-Specifications 3.5.0 and 3.5.D to assure that when the reactor is being started up from a Cold Condition, the HPCI and RCIC Systems are not 6 known to be inoperable, g D. RCIC System The RCIC is designed to provide makeup to the nucleSe system as part of the planned operation for periods when the main conoenser is unavailable. The nuclear safety analysis FSAR Appcndix G, shows that' RCIC also serves for decay heat removal 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 I week is specified. Additional discussions on RCIC are included in the HPCI Bases above.

-E. Automatic Depressurization System (ADS)

The limiting conditions for operating the ADS are derivedifrom the Station Nuclear Operational Analysis (Appendix G) and a detailed functional analysis of the ADS (Section 6).

This specification ensures the operability of the ADS under all d conditions for which the automatic or manual depressurization of the '

nuclear system is an essential-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 lcw 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.

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, 4 PBAPS 3.5.E BASES (Cont'd.)

With one ADS valve known to be incapable of automatic operation, four  ;

valves remain operable to perform their_ ADS function. However, since the ECCS Loss-of-Coolant Accident analysis for small line breaks assumed that all five ADS valves were operable, reactor operation with one ADS valve inoperable is only allowed to continue for seven (7) days provided that the HPCI system is verified to be operable and that the  :

actuation logic-for the operable (see 4.5 Bases)(remaining) four ADS valves is verified to be F.. Minimum Low Pressure Cooling and Diesel Generator Availability ,

1 The purpose of Specification F is to assure that adequate core cooling capability is available at all times. It is during refueling outages ,

that major maintenance is performed and during such time that all. low pressure core cooling systems may be out of service. This specification provides that should this occur, no work will be ,

performed on the primary system which could lead to draining the vessel. This work would include work on certain control rod drive components and recirculation system. Additionally, the specification provides minimum core flooding requirements during refueling operations. Specification 3.9 must also be consulted to determine other requirements for the diesel generators.

G. Maintenance of Filled Discharge Pipe If the discharge piping of the core spray, LPCI mbsystem HPCI, and RCIC are not filled, a water hammer can develop in this piping when the '

pump and/or pumps are started. If a water hammer were to-occur at the time at which the system were required, the system.would still perform its design function. However, to minimize damage to the discharge piping and to ensure added margin in the. operation of these systems, this Technical Specification' requires the discharge lines to be filled whenever the system is in an operable condition.

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PBAPS 4.5 -BASES Core and' Containment Cooling Systems Surveillance Frequencies i The performance of individual emerg'ency core cooling' systems (HPCI, LPCI.-Core' Spray and ADS) and the integrated performance of the emergency core cooling systems are described in analyses referenced in Section 6.5 of the Updated Final Safety Analysis Report. Periodic  :

surveillance of pumps and valves is performed in accordance with ASME Code,Section XI, to the extent described in the Inservice Testing Plan, to verify that the systems will provide the flow rates required by the respective analyses. -HPCI and RCIC flow tests are performed at l

two pressures so that the systems' capability to provide rated flow  ;

over their operating range is verified. HPSW flow tests verify that ,

rated flow can be delivered to the RHR heat exchangers.  ;

The testing interval for the core and containment cooling systems is i based on industry practice, sound engineering judgment and l [

practicality. The core cooling systems have not been designed to be  ;

fully testable during operation. For example, in the case of the HPCI, '

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 1 each cycle combined with frequent' tests of the pumps and injection valves is deemed to be adequate testing of these syst' ems.-

When components-and subsystems are out-of-service, overall' core and containment cooling reliability is maintained by verifying the operability of the remaining redundant cooling systems that the

. Limiting Conditions for Operation require to be operable during the allowable out-of-service time period. Verifying operability in this y

-context means to administratively ensure that the remaining required- J systems or subsystems are not known to be inoperable (for example: -

confirming that equipment necessary for the systems or subsystems to perform their safety functions are not blocked out of service for i maintenance). Performance of operability tests is not required. 1

-4.5 I&J Surveillance Reauirements Bases ,

Average and Local LHGR The LHGR shall be checked daily to determine if fuel burnup or control rod movement has caused changes in power distribution. Since changes i due to burnup are slow and only a few control rods are moved daily, a l daily check of power distribution is adequate. -

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., e F c

'ILIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS to < '.06 mrem to the tota 1Lbody-and.to

< 20;0 mrem to any organ.

' When the-calculated-dose from the' release-of radioactive 1 materials in L liquid: effluents exceeds

- any of the aboveHlimits, e ,

, preparefand submit to the Commission within 21 tworking days,Lpursuant~to

l. Specification 6.9.2,-a

.Special Report which identifies the causes for exceeding the-limits

=and corrective actions that r

have been taken to reduce-lthe' releases of" radioactive materials in liquid

. effluents and= proposed

-corrective actions to be taken to-assure that-subsequent-releases are 3within the' limits.

This Special. Report.

shall1also. include (1) results of' radiological analyses of'the drinking water source and-(2)-the radiological impact on'the potentially affected drinking water supplies with-regardito 40 CFR 141, Safe ~ Drinking-Water Act. Reactor shutdown

-is not-required.

~3.. During release of radioactive 3a. The liquid radwaste wastes,_the:following effluents radiation monitor conditions shall be met: shall be calibrated every a..The minimum dilution- 12 months with a known

-water required to radioactive source positioned satisfy 3.8.B.1 shall in a reproducible geometry be met. with respect to the sensor

b. The gross activity and every quarter by means of monitor and flow monitor a source check. Additionally, on the waste effluent line shall be operable an instrument functional test shall be performed every except as specified in l

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.. o-kiMITINGCONDITIONSFOROPERATION SURVEILLANCE REQUIREMENTS

'i 2.. The. air dose in areas at

'and beyond the SITE-2; Cumulative doce contributions Ew for noble gases shall be  !

BOUNDARY (see Figure- determined in'accordance ,

3.8.1)!due to noble gases with the methodology and '

in gaseous effluents released parameters in-the ODCM

-from the two reactors at the. at least once per month, site shall be limited to'the following:

^

a fDuring any~ calendar

. quarter for gamma radiation: <-10 mrad.- '

During;any calendar quarter for-beta radiation: $ 20 mrad.

i

-b. During any calendar year.

'for gamma radiation:

<-20 mrad.

.During any calendar year for beta

. radiation:'$ 40 mrad.

When-the-calculated air- '

dose.from radioactive

noble gases in gaseous effluents exceeds any of the.above limits, prepare

and submit to the Commission

<within'21 working days, . ,

-l ~ pursuant,to' Specification.6.9.2, .

a'Special-Report which identifies t o .the causes for exceeding the

-limitscand defines the corrective actions that have been taken to reduce.the releases and proposed i corrective actions to'be taken to assure that subsequent j releases will be within the

~cbove limits. Reactor shutdown

?is not. required.

'3.- The dose'to a MEMBER OF 3, Cumulative dose contributions 1THE PUBLIC from iodine-131, for iodine-131, iodine-133, iodine-133, tritium and tritium, and radionuclides '

from all radionuclides in particulate form with half

-in particulate form with lives greater than 8 days 209 y

[ MT Unit 2:

a- <..

i

( ,, P3APS

[

f . p' w e a 4 L1'MITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS i- -

? half-lives-greater than shall be determined in -3 0 8 days in gaseous effluents- accordance with the-released.from the two methodology and parameters

! . reactors'at the' site to in the ODCM:at~1 east once

i. areas at and beyond the .per month.

SITE BOUNDARY-(see' Figure

'["

3.8.1') shall be limited -

'to the following:- '

I-

.-a. During any calendar  ;

quarter: $ 15 mrem.

b. During any calendar-year: $ 30 mrem.

.When the-calculated dose-from

~

the release of iodine-131, iodine-133', tritium and radionuclides-in' particulate

• form, with half-lives greater

.than 8 days in gaseous effluents exceeds any of the- ,

above limits,? prepare and submit to the Commission within 21Eworking days,.

pursuant to Specification 6.9.2, a Special Report. The report shall identify the causes for. exceeding

.i

'the-limita and define'the corrective 4 cetions.that have been taken and proposed corrective. actions to

-to assure that subsequent releases will be within the above limits.

,'. Reactor shutdown is not required.

4W . During/ release of-gaseous 4a. The reactor building wastes the following con- exhaust vent and main ditions shall be met to stack noble gas radiation

. avoid exceeding the monitors shall be cali-limits-specified in brated every 12; months with 3.8.C.1: a known radioactive' source

a. The main off gas ~ stack positioned in a reproducible minimum dilution' flow of geometry with respect to 10,000 cfm shall be- the sensor, and every-maintained. quarter by means of a b.-One reactor building functional test. The exhaust vent monitor channel functional test 210

Unit 2- ,

t

. .. g P APS .

!" LIMITING CONDITIONS-FOR OPERATION SURVEILLANCE REQUIREMENTS-  ;

pursuant to Specification +

1 6.9.2 a Special Report which includes-the following

~information:.

a. Explanation of why' gaseous radwaste was being dis .

• charged without treatment, identification of any inoperable equipment or .

subsystems and the reason '

for its inoperability.

.b. Action taken to restore the inoperable equipment to operable status,

c. Summary description of action taken to prevent a recurrence.

~ Reactor-shutdown is not required.

I

-214-

w-y m Unit 2

1. '

,, ., PBAPS- t

/e i * '

LLfMITING1 CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

made, including direct '

'  : radiation contributions 1from

the reactor units and from outsideLstorage tanks to

. determine whether the.llmits have been exceeded. If such is the case, prepare and '3 submit to the Commission,  !

within-21 working days, pursuant to Specification

.l 6.9.2,>a Special Report that i defines the corrective <

-action to be taken to reduce -

subsequent releases to prevent recurrence of exceeding the '

above limits and schedule for achieving conformance

' 'with the above limits.

iThisESpecial Report shall i

~1nclude'an analysis-that i estimates the radiation e exposure to a MEMBER OF

.!f THE PUBLIC,. including all effluent pathways and-direct-radiation, including l

.theEreleases-covered 1by.

this report,:for the

' calendar: year. It shall-also describe: levels of radiation and-concentrations of' radioactive-material involved and the cause. 4

'of7 the exposure. levels or

-concentrations. If the Lestimated dose exceeds ,

-the above limits and

if the' release condition

-resulting-in violation cf 40 CFR:190-has not Lalready been corrected,

~the Special Report shall

! include a request for_a-variance in-accordance-

.with 40 CFR 190. Submittal

-of~the report is~ considered a timelyLrequest and a Lvariance is granted until staff action on the request-is complete.

216a-1 c

GS ,

Unit 2

, ,.i .

PBAPS  !

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS-

.the. lowest calculated' dose or dose commitment

(via the same exposure j pathway) may be deleted

• from this monitoring 4, program after October 31 of the year in which this land use census was conducted. '

Identify the'new' location 2 inLthe next Radioactive Dose Assessment. Report and1 include in:the report revised' figures and tables for.the CDCM reflecting the new locations, i

3.- Analyses shall be performed 3a. A summary of the results son radioactive raaterials obtained as part of the

• supplied as part"of the EPA Interlaboratory Comparison'

.EnvironmentalfRadi'oactivity , Program ~shall be included  ?

Intercomparison Studies Program, ~in the Annual-Radiological Eor another Interlaboratory Environmental Operating- 4 Comparison Program-that has Report pursuant-to-

.been approved'by the' Commission. Specification.6.9.2. l a.1With analyses not being

. performed as required above, report the corrective; actions taken to prevent a recurrence =in the '

LAnnual< Radiological Environmental Operating Report.

- 3.8 F Solid Radioactive Waste 4.8.F Solid Radioactive Waste

1. .The' solid radwaste system 1. The PCl shall.be used to  !

shall be used in accordance ensure meeting-the burial

. with a Process Control ground and shipping re-

~ Program (PCP) to process quirements prior to shipment wet radioactive wastes to of radioactive wastes from meet shipping and. burial the site.

-ground requirements.

a. With the provisions of the Process Control Program

.not satisfied, suspend 4

shipments of defectively packaged solid radio-active waste from the site. Reactor shutde'T is not required. ,

216a-5

, u

Unit 2

,. . PBAPS L'IMITING CONDITIONS FOR' OPERATION SURVEILLANCE REQUIREMENTS .-

13.15- Seismic Monitoring- 4.15 Seismic Monitoring i Instrumentation Instrumentation Applicability Applicability Applies to the operational Applies to the surveillance status of the seismic requirements of the seismic monitoring instrumentation, monitoring instrumentation.

Specifications Specifications.

A. The seismic monitoring A. Each of the required instrumentation shown in seismic monitoring instruments Table 3.15 shall be shall be demonstrated operable. -operable-by the performance ,

of the Instrument Check, B. With one or more seismic Instrument Functional Test, monitoring instruments and Instrument Calibration

-inoperable for more than operations at the frequencies l 30 days, prepare and shown in Table.4.15.

submit a Special Report  !

to the NRC pursuant to B. Each of the required a Specification 6.9.2 within seismic monitoring instruments the next 10; working days actuated during a seismic outlining the cause'of the event shall be restored to malfunction =and the plans- operable status within for restoring the instrument (s) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ar.d an Instrument to operable status. Calibration-performed within 5 days following -

the seismic event. Data C. The provisions of Specification shall be retrieved i 3.0.c are not-applicable, from actuated instruments '

and analytod to detern.inc ,

the magnitude of the i vibratory-ground motion. A l Special Report shall be prepared and submitted to the NRC pursuant to Specification 6.9.2 within the next 10 working days describing the magnitude, frequency-spectrum and "

resultant effect upon facility features important to safety.

240t

[ Unit 2 (

4 .- j

., s- PBAPS i A -

6.8.2: Each procedure and administrative policy of 6.8.1'above,.

and changes thereto, shall be reviewed by the PORC and a approved by the Plant Manager or his designated ,

[- La1 ternate per Specification 6.1.1 prior to

-implementation and reviewed periodically as set forth in administrative procedures. .'

6.8.3 Temporary changes to procedures of-6.8.1 above may be  ;

made, provided:  !

a. .The intent of the original procedure is not altered.

< b.- 'The change is approved by two members of the plant management staff, at least one-of whom holds a Senior Reactor Operator's License on the unit ,

affected.

c.- The change is documented,. reviewed by the PORC and ',

approved by the Plant Manager within 14 days of implementation.

6.8.4 Written procedures shall be established, implemented and '

maintained covering the activities of the radiological i effluent technical specifications as referenced'below:-

a. Offsite Dose Calculation' Manual  ;

b. Quality Assurance Program for the environmental "

monitoring using the guidance in Regulatory Guide 4.1, Revision 1, April 1975.

6.9 Reporting Requirements In addition to the applicable reporting requirements of I Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the NRC in accordance with 10 CFR 50.4, " Written Communications".

-254-l

i Unit'2-

.p

r-C-

PBAPS-i 6.9.1 Routine Reports I

c. -Annual Safety / Relief Valve Report e

l>

Describe all challenges to the primary coolant system ~

safety and relief valves. Challenges are defined as (

the automatic opening of the primary coolant safety or relief valves in response to high reactor pressure,

d. Monthly Operating Report l

Routine reports of operating statistics and shutdown experience and a narrative summary of the operating experience shall be submitted on a monthly basis.

Each report shall be submitted no later than the 15th ofcthe month following the calendar month covered by ,

the report.

i 4

-256-I

Unit 12 t

,,.. .. a PBAPS.

4;-

-,1  !.

r 6.9.2 Unique Reporting Requirements-Special' reports shall be submitted to the NRC-in accordance with-10-CFR 50.4 within the time period specified herein-for each report. These reports shall be~ submitted covering the activities-identified below >

pursuant to the requirements of the applicable reference 1 specification:

a. Loss of shutdown margin, Specification 3.3.A and 4.3.A within 14 days of'the event.

b.. Reactor vessel inservice inspection, Specification '

3.6.G and 4.6.G within 90 days of the completion of the reviews,

c. Report seismic monitoring instrumentation >

inoperable for more than 30 days (Specification 3.15.B) within the next 10 working days. Submit a seismic event analysis (Specification 4.15.B) within 10 working days of the event.

d .- Primary containment leak rate testing approximately.

three months after the completion of the. periodic integrated leak rate test (Type A) required by

, Specification 4.7.A.2.c.2. For each periodic test,

. leakage. test results from Type A, B and C tests. '

shall-be reported. B and-C-tests are' local leak '

rate tests required by Specification 4.7.A.2.f.

The report shall contain an analysis and interpretation of the Type A test results and a summary analysis of periodic Type-B and Type,C tests that were performed since the.last Type A-1 test.

e. Calculated dose from release of radioactive effluents, Specification 3.8.B.2, 3.8.B.4, 3.8.C.2, 1

3.8.C.3, 3.8.C.5, 3.8.D, and 3.8.E.1.b. l 1

.f. Sealed source leakage in excess of limits, Specification 3.13.2.

l l -257-I l l

1 l I 1

l

m n -

p -

-Unit 3 1 I,  ;? -

~

% g; ' .*L .4 - q

'I' PBAPS I LIMITING CONDITIONS FOR' OPERATION SURVEILLANCE REQUIREMENTS

'3.2.D. Radiation Monitoring: -4.2.D. Radiation Monitoring.

Systems-Isolation and Systems-Isolation and  !

Initiation Functions Initiation Functions j o 1. Reactor Building Isolation. 1. Reactor Building Isolation and Standby Gas Treatment and Standby Gas Treatment System System The~ limiting conditions Instrumentation shall:be for operation are given in functionally tested, cali-

-Table 3.2.D. brated and checked as indi-cated in Table l4.2.0.

System logic shall be '

functionally tested as indicated in Table 4.2.D.

E Drywell Leak Detection E..DrywellEleak Detection The limiting' conditions of . Instrumentation shall be

operation'for the instru-calibrated and. checked as mentation that monitors indicated in Table 4.2.E. "

drywell-leak detection are '

,-given in Section 3.6.C.

" Coolant: Leakage".

Y t -

1

i }

~

Unit 3 3

, .. PBAPS' 1

3.4 . BASES

' STANDBY LIQUID CONTROL SYSTEM The Standby Liquid Control System is also required to meet 10 CFR 50.62 (Requirements for reduction of risk.from 4

anticipated transients without scram (ATWS) events for ,

light-water-cooled nuclear power plants).- The Standby Liquid Control System must have the equivalent control capacity of an 86 gpm system of 13% weight natural sodium <

pentaborate in order to satisfy 10 CFR-50.62 requirements..  !

This equivalency requirement is fulfilled by having a system which satisfies the equation given in 3.4.B.3. Each parameter (sodium.pentaborate solution concentration, pump flow rate, and Boron-10 enrichment) is tested at an interval consistent with the potential for that parameter to vary and

.also to assure proper equipment performance. Boron-10 enrichment testing is only required when chemical addition occurs since change cannot occur by any process other than the addition of-new chemicals to.the Standby Liquid Control Solution Tank, e

i Normally, pre-mixed dry sodium pentaborate enriched in ,,

' Boron-10 is added to demineralized water to form the solution. The pre-mixed sodium pentaborate is purchased with certification of its Boron-10 enrichment. The solution could be made by combining' natural borax and Boron-10 enriched boric acid in stoichiometric quantities-in demineralized water. Since both the' borax and Boron-10 enriched boric' acid have known Boron-10: enrichments, the resulting Boron-10 enriched sodium pentaborate also would have a:known Boron-10 enrichment. This process.is adequate for~use in' determining immediate compliance with 3.4.B.3' following-chemical addition. The solution Boron-10 enrichment shall be subsequently verified by analysis to be l

acceptable. l The' volume of solution stored is checked at a frequency to assure high reliability of the system. Solution level is l indicated and alarmed in the control room.

C. '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.

-120-

Unit 3'  :

,- l ..' PBAPS

~ '

I.IMITING'CONDITIONSFOROPERATION- SURVEILLANCE REQUIREMENTS s ' 3.5.A Core Spray & 4.5.A Core Spray &

LPCI Subsystem'(cont'd) LPCI Subsystem (cont'd)

Both CSS shall be operable Item Frequency

-whenever irradiated fuel i is .in the vessel and prior (d) Pump Flow Rate Once/3 months to reactor startup from a Cold Shutdown condition Each pump in each loop shall l except as specified in deliver at least 3125 gpm 3.5.A.2 and 3.5.F.3 below: against a system head

, corresponding to a reactor vessel pressure of 105 psig.

(e) Core Spray Header AP Instrumentation Check Once/ day Calibrate Once/3 months (f) DELETED

2. From and after the date 2. DELETED that one of the core spray subsystems is

.made or found to be inoperable for any reason, continued. reactor operation is permissible only during the succeeding seven days provided-that during such seven days all active components of the other

' core' spray subsystem and active components of the LPCI subsystem are operable.

3. LPCI Subsystem Testing shall be as follows:

Item Frequency (a) Simulated Automatic Once/ operating Actuation Test Cycle (b) Pump operability Once/1 month

-125-

Unit 3- ,

'PBAPS

, LIMITING CONDITIONS FOR OPERATION ~

. SURVEILLANCE REQUIREMENTS

~i f,3.5.A

^~

Core Spray and LPCI 4.5.A Core Spray and LPCI Subsystem (cont'd) Subsystem (cont'd)-

3.'Two" independent Low Pressure Item Frequency

-Coolant' Injection (LPCI) subsystems will be operable (c) Motor Operated Once/ month with each subsystem valve operability i comprised er.

~a. (Two 33-1/3%) capacity pumps. (d) Pump Flow Rate Once/3 months-

.b. An operable flow path Each LPCI pump shall deliver capable of taking suction 10,900 gpm against a system head from the suppression pool corresponding to a vessel pressure -

and transferring the water .of 20 psig based on individual to the reactor pressure pump tests, vessel, and

c. During power operation (e) DELETED the LPCI system cross-tie valve closed and the associated valve motor operator circuit '

breaker locked in ,

the off position. '

Both'LPCI subsystems.shall be operable whenever irradiated fuel is in the reactor vessel, and prior to reactor startup from the Cold Shutdown Condition, except as specified in 3.5.A.4 and 3.5.A.5 below.

4. From and after;the date that one 4. DELETED of the four LPCI pumps is made or found to be inoperable for any

' reason,' continued reactor operation'is permissible  ;

only-during the succeeding seven days provided that during such seven days the remaining active components of the LPCI subsystems,-and all active components of both core spray subsystems are operable.

l l' 5. From and af ter the date that one 5. DELETED LPCI subsystem is made or found to be inoperable for any reason.

l continued reactor operation is l permissible only during the

. succeeding 7 days unless

-it is sooner made operable, I provided that during such 7 days all active components of l both core spray subsystems and the remaining LPCI subsystem

.are operable.

-126-

/. .

Unit 3 e . PBAPS LINIT]NG CONDITIONS FOR OPERATION Si*dlLLANCE REQUIREMENTS 3 5.B Containment Coolina 4.5 B Containment Coolino i System (cont'd) System (cont'd) l

2. From and after the date that 2. DELETED '

any two HPSW pumps are made or found to be inoperable for any reason, continued reactor opera-tion is permissible only during ,

! the succeeding thirty days, unless such pump is sooner made operable, i provided that during such thirty

• days the remaining HPSW pumps are operable.

3. from and after the date that 3. DELETED I .any three HPSW pumps are made or

, found to be inoperable for any re:. son, continued reactor i operation is permissible only during the succeeding fifteen days unless such pumps'are '

sooner made operable provided  :

the remaining HPSW pump is operable.

'4a. The torus cooling mode of 4. DELETED RHR shall be operable with l

two independent loops.

l' Each loop consists of.

(1) At least one operable '

RHR pump.

t (2) An operable flow path to '

L pump water from the torus  !

through an operable RHR heat exchanger and back to the torus via the flow ,

test line.

(3) An operable HPSW flow path through the operable heat exchanger associated with the operable RHR pump.

b. With one torus cooling loop inoperable, restore the inoperable ,

loop to operable status within seven days. ~

c. With both torus cooling loops inoperable.. restore at least one loop to operable status ,

within eight hours.

-128-

Unit 3 F _,

, . PBAPS

[ " LIMlf1NG CONDITIONS FOR OPERATION SURVEllLANCE REQUIREMENTS i -

3.5.B Containment Cooling 4.5.B Containment Cooling System (cont'd) lystem (cont'd)

Sa, The drywell spray mode of RHR 5. DELETED shall be operable with two independent loops.

Each loop consists of:

(1) At least one operable RHR pump.

, .(2) An operable flow path

! to pump water from the torus through an operable RHR heat exchanger to the drywell spray sparger.

(3) An operable HPSW flow path through the operable heat exchanger associated with the operable RHR pump,

b. With one drywell spray loop inoperable, restore the inoperable loop to operable status within seven days, c.-With both drywell spray loops inoperable, restore at least one loop to operable status within eight hours.

6a. The torus spray mode of RHR 6. DELETED shall be operable with two independent loops. Each loop consists of:

(1) At least one operable RHR pump.

(2) An operable flow path to pump water from the torus through an operable

'RHR heat exchanger to the torus spray sparger.

(3) An operable HPSW flow path through the operable heat exchanger associated with the operable RHR pump, b.-With one torus spray loop inoperable, restore the inoperable loop to operable status within seven days,

c. With both torus spray loops inoperable, restore at least one loop to operable status within eight hours.

-128a- .

J

q ,m Unit 3-L .-

[

• go . PBAPS 11NITING CONDITIONS FOR OPERA 1,10N SURVEILLANCE REQUIREMENTS

• 3.5.B Containment Cooling. 4.5.B Containment Coolina-System (cont'd)- E tem (cont'd) i< :7. ::If the requirements of 3.5.B i 'cannot be met, an orderly H -shutdown shall be' initiated and the reactor shall 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 1. HPCI Subsystem testing

~ ; operable whenever there is shall be performed as follows:

irradiated fuel in the reactor l vessel, reactor steam pressure item Frequency is greater than 105 psig, and prior.to reactor startup (a) Simulated Once/ operating

-from a Cold Condition. Automatic cycle

!- -except as specified-in. Actuation 3.5.C.2 and 3.5.C.3 below.. Test I

'N I

r .

-128b-m

L Unit 3 l PBAPS

' LIMIT'hNGCONDITIONSFOROPERATION SURVEILLANCE REQUIREMENTS i

.3.5.C HPCI Sutnystem (cont'd.) 4.5.C HPCISubsystem(cont'd.)  :

Item frecuency (b) Pump Once/ month I

Operability  ;

I r (c)MotorOperated Once/ month i, Valve a Operability l f

(d) Flow Rate at Once/3 months 1000 psig i Steam Pressure *

(e) Flow Rate at Once/ opera-ting cycle 150 psia  :

Steam IW ssure The HPCI pump shall deliver at least 5000 gpm for a system head corresponding to a reactor .

, pressure of 1000 to 150 psig. '

2. From and after the date that 2. DELETED l the HPCI Subsystem is made or found to be inoperable for any reason, continued reactor i operation is permissible only during the succeeding seven days unless such subsystem is  ;

sooner made operable, provi-ding that during such seven days all active components of the ADS subsystem, the-RCIC i system, the LPCI subsystem i and both core spray subsys-tems are operable.

.3. If the requirements of 3.5.C cannot be met, an orderly shut-  ;

down shall be initiated and the reactor shall 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 />.

-129-

Unit 3

( ,

, . PBAPS

.LIMlflNGCONDITIONSFOROPERATION SURVEILLANCE REQUIREMENTS F

3 Reactor Core Isolation 4.5.D Reactor Core Isolation l.5.D Cooling (RCIC) Subsystem Cooling (RCIC) Subsystem l l' 1. The RCIC Subsystem shall be 1. RCIC Subsystem testing shall l operable whenever there is be performed as follows:

irradiated fuel in the reactor l Vessel, the reactor steam pressure item Frecuency is greater than 105 psig, and prior.to reactor startup from (a) Simulated Once/ Operating a Cold Condition, except as Automatic Cycle specified in 3.5.D.2 below. Actuation Test *

(b) Pump Once/ Month Operability (c)MotorOperated Once/ Month Valve Operability (d)FlowRateat Once/3 Months approximately 1000 psig Steam Pressure **

(e)FlowRateat Once/ Operating approximately Cycle 150 psig Steam Pressure **

(f)Verifyaute- Once/ Operating ***

matic transfer Cycle from CST to suppression poul on low CST water level

2. From and after the date that 2. DELETED l the RCIC Subsystem is made or found to be inoperable for any reason, continued reactor power opera-tion-is permissible only during the succeeding seven days provided that during such I seven days the HPCI Subsystem is operable.

3. If the requirements of 3.5.0 *Shall include automatic restart cannot be met, an orderly shut- on low water level signal.

down shall be initiated and the reactor pressure shall **The RCIC pump shall deliver be reduced to 105 psig within at least 600 gpm for a system 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, head corresponding to a reactor pressure of 1000 to 150 psig.

• • • Effective at 1st refueling outage after Cycle 7 reload.

-130-

Unit 3

. < PBAPS LIMITING CONDli10NS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.E Automatic Depressurization 4.5 E Automatic Depressurization System (AE5) System (ADS)

1. The Automatic Depressuriza- 1. During each operating cycle tion Subsystem shall be oper- the following tests shall be able whenever there is irra- performed on the ADS:

diated fuel in the reactor I vessel and the reactor steam A simulated automatic pressure is greater than 105 psig actuation test shall be and prior to a startup frot) a Cold performed prior to Condition, except as specified startup after each in 3.5 E.2 below. refueling outage.

2. from and after the date that 2. DELETED one valve in the automatic depressurization subsystem is made or found to be inoperable for any reason, continued reactor operation is permissible only during the succeeding seven days unless such valve is sooner made operable, provided that during such seven days the HPCI subsystem is operable.

3. If the requirements of 3.5.E cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall be reduced to at least 105 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

-131-

Unit 3 l

.' 4 PBAPS w

-l 1

'3.5.A BASES tore Spray and LPCI Subsystems

~

Core Spray Subsystem (CSS) i The CSS is provided to assure that the core is adequately cooled following acore adequate loss-of-coolant accider.t.

cooling capacity for allTworedundantloopseacgprovide break sizes from 0.2 ft up i

to and including the double-ended reactor recirculation line break, and  ;

for smaller breaks following depressurization by the Automatic  !

DepressurizationSystem(ADS).  ;

The CSS specifications are applicable whenever irradiated fuel is in the core because the CSS is a primary source of emergency core cooling >

after the reactor vessel is depressurized and also provides a source  :

for flooding of the core in case of accidental draining.  :

With one CSS inoperable, the verified operability (see 4.5 Bases) of I the redundant full capacity CSS and the full capacity Low Pressure  :

Coolant Injection system provides assurance of adequate core cooling and justifies the specified 7 days out-of-service period.

The surveillance requirements provide adequate assurance that the CSS '

- will be operable when required. Although all active components are i testable and full flow can be demonstrated by recirculation during reactor operation, a complete functional test requires reactor '

shutdown. The pump discharge piping is maintained full to prevent I water hammer damage to piping and to start cooling at the earliest i moment.

Low Pressure Coolant Injection System (LPCIS)

The LPCIS is provided to assure that the core is adequately cooled I following a loss-of-coolant accident. Two loops each with two pumps provide adequate core flooding for all break sizes from 0.2 ft2 up i to and including the double-ended reactor recirculation line break, and for small breaks following depressurization by the ADS. .,

The LPCIS specifications are applicable whenever there is irradiated fuel in the reactor vessel because LPCIS is a primary source of water ,

for flooding the core after the reactor vessel is depressurized.

With one LPCIS pump inoperable, or one LPCIS loop inoperable, adequate '

core flooding is assured by the verified operability (see 4.5 Bases) of l the redundant LPCIS pumps or loop, and both CSS loops. The reduced redundancy justifies the specified 7 day out-of-service period.

The surveillance requirements provide adequate assurance that the LPCI will be operable when required. Although all active components are testable and full flow can be demonstrated by recirculation during reactor operation, a complete functional test requires reactor shutdown. The pump discharge piping is maintained full to prevent water hammer damage to piping and to start cooling at the earliest i moment.

-134-.

l

r_

Unit 3 PBAPS 3.5.A ' BASES (Cont'd)

(

The allowable repair times are established so that the average risk rate for. repair would be no greater than the basic risk rate using the methodsdescribedinReference(1). Using the results developed in this reference, the repair period is found to be 1/2 the test interval.

This assumes that the core spray subsystems and LPCI constitute a 1 out of 3 system; however, the combined effect of the two systems to limit excessive clad temperatures must also be considered. The test interval specified in Specification 4.5 is 1 month.

Should one core spray subsystem become inoperable, the remaining core spray and the LPCI system are available should the need for core cooling arise. To assure that the remaining core spray and LPCI subsystems are available, they are verified to be operable (see 4.5 Bases).

Should the loss of one LPCI pump occur, a nearly full complement of core and containment cooling equipment is available. Two 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 coolin Bases)g , aequipment, which will thirty day repair be verified period to be operable is justified. (see If the LPCI 4.5 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 this basis.

(1) Jacobs, I. M., " Guidelines for Determining Safe Test Intervals and Repairs Times for Engineered Safeguards" General Electric Co.

A.P.E.D., April, 1969 (APE 0 5736)  ;

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PBAPS 3.5 B RASES Contairment Cooling System The Peach Botton Containment Cooling System consists of the High Pressure Service Water (HPSW) system and the drywell spray. torus spray and torus cooling modes of the Residual Heat Removal System (RHRS).

The torus cooling mode of RHR consists of two independent loops. A loop is defined as a flow path to pump water, with an RHR pump from the torus through an RHR heat exchanger, then back to the torus via the flow test line. A flow path from an operable HPSW pump through that RHR heat exchanger completes the functional loop.

The drywell spray mode of RHR consists of two independent loops. A loop is defined as a flow path to pump water, with an RHR pump, from the torus through an RHR heat exchanger to the drywell spray sparger.

A flow path from an operable HPSW pump through that RHR heat exchanger completes the functional loop.

The torus spray mode of RHR consists of two independent loops. A loop is defined as a flow path to pump water from the torus, with an RHR pump, through an RHR heat exchanger to the torus spray sparger. A flow path from an operable HPSW pump through that RHR heat exchanger completes the functional loop.

The design of these systems is predicated upon use of 1. RHR and 1 HPSW pump for heat removal after a design basis event. Thus, there are ample spares for margin above the design conditions. Loss of margin should be avoided and the equipment maintained in a state of operability so a 30-day out-of-service time is chosen for two HPSW pumps.

With components or subsystems out-of-service, overall core and containment cooling reliability is maintained by verifying the operability-(see4.5 Bases)oftheremainingcoolingequipment.

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3.5 BASES (Cont'd).

The HPCI and RCIC as well as all other Core Stanuby Cooling Systems must be operable when starting up from a Cold Condition. It is rnalized that the HPCI and RCIC systems are not designed to operate until reactor pressure exceeds 150 psig and are automatically isolated before reactor pressure decreases below 100 psig. It is the intent of Specifications 3.5.C and 3.5.D to assure that when the reactor is being started up from a Cold Condition, the HPCI and RCIC Systems are 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 nuclear safety analysis. FSAR Appendix G, shows that RCIC also serves for decay heat removal 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 1 week is specified. Additional discussions on RCIC are included in the HPCI Bases above.

E. Automatic Depressurization System (ADS)

The limiting conditions for operating the ADS are derived from the Station Nuclear Operational Analysis (Appendix G) and a detailed functional analysis of the ADS (Section 6).

This specification ensures the operability of the ADS eder all conditions for which the automatic or manual depressurization of the nuclear system is an essential 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 only with respect to its I depressurizing effect in conjunction with LPCI or Core Spray and is based on 4 valves. There are five valves provided.

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3.5.E BASES (Cont'd.)

With one ADS valve known to be incapable of automatic operation, four valves remain operable to perform their ADS function. However. since the ECCS Loss-of-Coolant Accident analysis for small line breaks assumed that all five ADS valves were operable, reactor operation with one ADS valve inoperable is only allowed to continue for seven (7) days provided that the HPCI system is verified to be operable and that the actuation logic for the operable (see 4.5 Bases)(. remaining)fourADSvalvesisverifiedtobe F. Minimum low Pressure Cooling and Diesel Generator Availability The purpose of Specification F is to assure that adequate core cooling capability is available at all times. It is during refueling outages that major maintenance is performed and during such time that all low pressure core cooling systems may be out of service. This specification provides that should this occur, no work will be performed on the primary system which could lead to draining the vessel. This work would include work on certain control rod drive components and recirculation system. Additionally, the specification provides minimum core flooding requirements during refueling operations. Specification 3.9 must also be consulted to determine other requirements for the diesel generators.

G. Maintenance of Filled Discharge Pipe If the discharge piping of the core spray, LPCI subsystem HPCI, and RCIC are not f111ed, a water hammer can develop in this piping when the pump and/or pumps are started. if a water hammer were to occur at the time at which the system were required, the system would still perform its design function. However, to minimize damage to the discharge piping and to ensure added margin in the operation of these systems, this Technical Specification requires the discharge lines to be filled whenever the system is in an operable condition.

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4.5 BASES Core and Containment Coolino Systems Surveillance frequencies i The performance of individual emergency core cooling systems (HPCI,  !

LPCI, Core Spray and ADS) and the integrated performance of the  !

emergency core cooling systems are described in analyses referenced in t Section 6.5 of the Updated Final Saftty Analysis Report. Periodic surveillance of pumps and valves is performed in accordance with ASME Code,Section XI, to the extent described in the Inservice Testing  !

Plan, to verify that the systems will provide the flow rates required by the respective analyses. HPCI and RCIC flow tests are performed at two pressures so that the systems' capability to provide rated flow over their operating range is verified. HPSW flow tests verify that  :

1 rated flow can be delivered to the RHR heat exchangers. }

The testing interval for the core and containment cooling systems is +

based on industry practice, sound engineering judgment and l l practicality. The core cooling systems have not been designed to be fully testable during operation. For example, in the case of the HPCI, i 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 i pumps and motor operated injcction 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 injection valves is deemed to be adequate testing of these systems.

When components and subsystems are out-of-service, overall core and containment cooling reliability is maintained by verifying the operability of the remaining redundant cooling systems that the Limiting Conditions for Operation require to be operable during the allowable out-of-service time period. Verifying operability in this context means to administratively ensure that the remaining required systems or subsystems are not known to be inoperable (for example:

l confirming that equipment necessary for the systems or subsystems to perform their safety functions are not blocked out of service for ,

maintenance). Performance of operability tests is not required. '

4.5 1&J Surveillance Requirements Bases l

! Average and Local LHGR l

The LHGR shall be chacked daily to determine if fuel trnup or control rod movement has caused changes in power distribution. Since changes l due to burnup are slow and only a few control rods are moved daily, a daily check of power distribution is adequate.

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' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS _

to < 6.0 mrem to the total body and to 5 20.0 mrem to any organ.

When the calculated dose from the release of radioactive materials in liquid-effluents exceeds any of the above limits, prepare and submit to the Commission within 21 working days, pursuant to l Specification 6.9.2, a Special Report which identifies the causes for exceeding the limits and corrective actions that have been taken to reduce the' releases of radioactive materials in liquid effluents and proposed corrective actions to be taken to assure that subsequent releases are within.the limits.

This Cpecial Report shall also include (1) results of radiological analyses of-the drinking water source and (2).the radiological impact on the potentially affected drinking water supplies with regard to

<40 CFR 141, Safe Drinking Water Act. Reactor shutdown is.not required.

3. During release of radioactive 3a. The liquid radwaste-wastes, the following effluents radiation monitor conditions shall be mets shall be calibrated every

a. The minimum dilution 12 months with a known water required to- radioactive source positioned:

satisfy 3.8.B.1 shall in a reproducible geometry be met. with respect to the sensor

b. The gross activity and every quarter by means of monitor and flow monitor a source check. Additionally,

'on the waste effluent an instrument functional test line shall be operable shall be performed every except as specified in 205

Unit 3 4

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[

L2MITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l l

2. The air dose in areas at 2. Cumulative dose contributions

and beyond the SITE for noble gases shall be '

BOUNDARY (see Figure determined in accordance- .

3.8.1) due to noble gases with the methodology and in gaseous effluents released parameters in the ODCM  !

from the two reactors at the at least once per month.  ;

eite shall be limited i

-to the following:

L a.;During any calendar quarter for gamma  !

i radiation: < 10 mrad. I During any calendar '

r quarter for beta '

radiation: 5 20 mrad.  !

b. During any calendar year t for gamma radiation

< 20 mrad.

During any calendar year for beta radiation: 5 40 mrad.-

When the calculated air L

dose from radioactive noble gases in gaseous offluents exceeds any of the above limits, prepare

-cnd submit to the Commission within 21 working days, l pursuant to Specification 6.9.2, a special Report which identifies the causes for exceeding the L limits and defines 1the corrective Cetions that have been taken to reduce the releases and proposed corrective actions to be taken to assure that subsequent releases will be within the cbove limits. Reactor shutdown

~is not required.

'3 . The dose to a MEMBER OF 3. Cumulative dose contributions THE PUBLIC from iodine-131, for iodine-132, iodine-133, iodine-133, tritium and tritium, and radionuclides from all radionuclides in particulate form with half in particulate form with lives greater than 8 days 209 4

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{.LIMITIMGCONDITIONSFOROPERATION SURVEILLANCE REQUIREMENTS half-lives greater than shall be determined in

'8 days in gaseous effluents accordance with the released from the two methodology and parameters reactors at the site to in the ODCM at least once areas at and beyond the per month.

SITE BOUNDARY (see Figure 3.8.1) shal be limited to the following:

a. During any calendar quarter: < 15 mrem,

b. During any calendar year: < 30 mrem.

When the calculated dose from L the release of iodine-131,

! iodine-133, tritium and radionuclides in ;erticulate form, with half-lives greater than 8 days in gaseous offluents exceeds any of the cbove limits, prepare and cubmit to the Commission within 21 working days, pursuant to Specification 6.9.2, o Special Report. The report shall identify the causes for exceeding the limits and define the corrcctive cetions that have been taken and proposed corrective actions to to asoure that subsequent releases will be within the above limits.

E Reactor < shutdown is not required.

~4.- During release of gaseous 4a. The reactor building wastes the following con- exhaust vent and main ditions shall be met to stack noble gas radiation cvoid exceeding the monitors shall be cali-limits specified in brated every 12 months with 3.8.C.1: a known radioactive source

c. The main off-gas stack positioned in a reproducible minimum dilution flow of geometry with respect to 10,000 cfm shall be the sensor, and every j maintained, quarter by means of a

b. One reactor building functional test. The i

exhaust vent monitor channel functional test 210 l

Unit 3

c. 'P

. PBAPS LIMITING CONDITIONS POR OPERATION SURVEILLANCE REQUIREMENTS pursuant to Specification l' 6.9.2 a Special Report which includes the following informations

a. Explanation of why gaseous radwaste was being dis-charged without treatment, identification of any inoperable equipment or subsystems and the reason for its inoperability.

b. Action taken to restore the inoperable equipment to operable status.

c. Summary description of action taken to prevent a recurrence.

Reactor shutdown is not required.

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.. PBAPS e I ,

r 'Li^MITING CONDITIONS POR OPERATION SURVEILLANCE REQUIREMENTS made, including direct F -radiation contributions from the reactor units and from l

outside storage tanks to l

}

determine whether the limits  ;

have been exceeded. If such is the case, prepare and submit to the Commission, within 21 working days, pursuant to Specification i 6.9.2, a Special Report that defines the corrective

. action to be taken to reduce subsequent releases to prevent '

recurrence of exceeding the above limits and schedule for achieving conformance

,with the above limits.

This Special Report shall include an analysis that estimates the radiation exposure'to a MEMBER OF THE PUBLIC, including all effluent pathways and direct radiation, including the releases covered by this report, for the calendar year. It shall clso describe levels of radiation and concentrations of radioactive material-involved and the cause of the exposure levels or concentrations. If'the Cstimated dose exceeds the above' limits and if the release condition resulting in violation of 40 CFR 190 has not-ciready been corrected, the Special Report shall

include a request for a variance in accordance with 40 CFR 190. Submittal of the report is considered c timely request and a variance is granted until Otaff action on the request is complete.

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.* PBAPS s b 't

-LIMITING CONDITIONS POR OPERATION SURVEILLANCE REQUIRF4ENTS the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use i census was conducted. '

Identify the new location '

in the next Radioactive

[ Dose Assessment Report

.and include.in the report revised figures and tables i P for the ODCM reflecting the new locations. ,

i

3. Analyses shall be performed 3a. A summary of the results on radioactive materials obtained as part of the  ;

' supplied as part of'the EPA Interlaboratory Comparison Environmental Radioactivity Program shall be included Intercomparison Studies Program, in the Annual Radiological Ecr.another Interlaboratory Environmental Operating Comparison Program that has Report pursuant to

[, been approved by the Commission. Specification 6.9.2. l i

a. With analyses not being performed as required above, report the corrective actions taken to prevent '

r recurrence in the

} Annual Radiological -

Environmental Operating Report.

3.8.F Solid Radjoactive Waste 4.8.F Solid. Radioactive Waste

1. The solid radwaste system 1. The PCP shall be.used to shall tue used in accordance ensure meeting the burial with a Process Control ground and shipping re-  !

Program (PCP) to process quirements prior to shipment- '

wet radioactive wastes to of radioactive wastes from meet shipping and burial the site.

ground requirements.

a. With the provisions of H

the< Process Control Program -

not satisfied, suspend shipments of defectively 4 l packaged solid radio-active waste from the site. Reactor shutdown

• l is not required.

1 216a-5

E Unit 3 k

,4 o PBAPS

,  ?

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.15 Seismic Monitoring 4.15 Seismic Monitoring i -Instrumentation Instrumentation Applicability Applicability Applies to the operational Applies to the surveillance status of the seismic requirements of the seismic monitoring instrumentation. monitoring instrumentation.

Specifications Specifications

, A. The. seismic monitoring A. Each of the required instrumentation shown in seismic monitoring. instruments Table 3.15 shall be shall be demonstrated operable, operable by the performance of the Instrument Check, B. With one or more seismic Instrument Functional Test, monitoring instruments and Instrument Ca31bration inoperable for more than operations at the frequencies l 30 days, prepare and shown in Table 4.15.

submit a Special Report to the NRC pursuant to B. Each of the required Specification 6.9.2 within seismic monitoring instruments the next 10 working days actuated during a seismic outlining the cause of the event shall be restored to malfunction and the plans operable status within for restoring the instrument (s) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and an Instrument to operable status. Calibration performed within 5 days following the seismic event. Data C. The provisions of Specification shall be retrieved 3.0.c are not applicable. from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. A l Special Report shall be prepared and submitted to the NRC pursuant to Specification 6.9.2 within the next 10 working days describing the magnitude, frequency spectrum and resultant effect upon facility features important to safety.

240t '

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.  ? PBAPS o

6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PORC and approved by the Plant Manager or his designated alternate per Specification 6.1.1 prior to implementation and reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of 6.8.1 above may be made, provided:

a. The intent of the original procedure is not altered.

b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.

c. The change is documented, reviewed by the PORC and approved by the P' ant Manager within 14 days of implementation.

6.8.4 Written procedures shall be established, implemented and maintained covering the activities of the radiological effluent technical specifications as referenced below

a. Offsite Dose Calculation Manual

b. Quality Assurance Program for the environmental monitoring using the guidance in Regulatory Guide 4.1, Revision 1, April 1975.

6.9 Reporting Requirements In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the NRC in accordance with 10 CPR 50.4, " Written Communications".

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PBjP_S S

, 6.9~1

. Routine Reports

c. Annual Safety / Relief Valve Report Describe all challenges to the primary coolant system safety and relief valves. Challenges are defined as the automatic opening of the primary coolant safety or relief valves in response to high reactor pressure.

4

. l d. Monthly Operating Report Routine reports of operating-statistics and shutdown experience and a narrative summary of the operating experience shall be submitted on a monthly basis.

Each report shall be submitted no later than the 15th of the month following the calendar month covered by the report.

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,- ?9 6.9.2 Unique Reporting Requirement,s Special reports shall be submitted to the NRC in t

accordance with 10 CFR 50.4 within the time period specified herein for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference Specificationt

a. Loss of shutdown margin, Specification 3.3.A and 4.3.A within 14 days of the event.

b. Reactor vessel inservice inspection, Specification 3.6.G and 4.6.0 within 90 days of the completion of f the reviews.

c. Report seismic monitoring instrumentation inoperable for more than 30 days (Specification 3.15.B) within the next 10 working days. Submit a seismic event analysis (Specification 4.15.B) within 10 working days of the event.

d. Primary containment leak rate testing approximately three months after the completion of the periodic integrated leak rate test (Type A) required by Specification 4.7.A.2.c.2. For each periodic test, leakage test results from Type A, B and C tests shall be reported. B and C tests are local leak rate tests required by Specification 4.7.A.2.f.

The report shall contain an analysis and interpretation of the Type A test results and a summary analysis of periodic Type B and Type C tests that were performed since the last Type A test.

e. Calculated dose from release of radioactive effluents, Specification 3.8.B.2, 3.8.B.4, 3.8.C.2, 3.8.C.3, 3.8.C.5, 3.8.D, and 3.8.E.1.b. l

f. Sealed source leakage in excess of limits, Specification 3.13.2.

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