ML19321A819

Amends 71 & 69 to Licenses DPR-44 & DPR-56,respectively, Clarifying Definition of Operable & Adding General Limiting Conditions for Operation & Action Statements for Tech Specs

ML19321A819
Person / Time
Site:	Peach Bottom
Issue date:	07/15/1980
From:	Reid R Office of Nuclear Reactor Regulation
To:
Shared Package
ML19321A820	List: ML19321A819 ML19321A825 ML19321A827
References
NUDOCS 8007240242
Download: ML19321A819 (30)

Text

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'o, UNITED STATES

',g NUCLEAR REGULATORY COMMISSION

, 5-,

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wasmwoToN. o. c. roess s

,9 PHILADELPHIl. ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GA5 COMPANY DELMARVA POWER AND LIGHT. COMPANY j

ATLANTIC CITY ELECTRIC COMPANY l

DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2

,AJENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. DPR-44 1.

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

A.

The application for amendnent by Philadelphia Electric Company, et al. (the licensee) dated May 20, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions'of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the. Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance 'f this amendment is in accordance with 10 CFR Part 51 of the Cor.aission's regulations and all applicable requirements have been s,atisfied.

l 8007240

L 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 71, are hereby incorporated in the license. PEC0 shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMilSSION sfs lt

~

g Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing

Attachment:

Chances to the Technical Specifications Date of Issuance:

July 15, 1980 I

0 ATTACHMENT TO LICENSE AMENDMENT NO. 71 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the' Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by arnendment number and contain vertical lines indicating the area of change.

Remove Pages Insert Pages 3

3 4

4 34 34 34a (added) 34b (added) 35 35 145a 145a

146, 146 173 173 176 176 237 237*

238 238

• 0verleaf; no changes on this page.

)

PBAPS 1.0 DEFINITIONS (Cont'd) the automatic protective action at a level such that the safety limits will not be exceeded.

The region between the safety limit and these settings represents margin witn normal operation lying j

~

below these settings.

The margin has been established so that with proper operstion of the instrumentation, the safety limits will never be exceeded.

Locic - A logic is an arrangement cf relays, contacts and cther components that produces a decision output.

(a) Initiating - A logic that receives signals frem channels and produces decision outputs to the actuation icgic.

' b) Actuaticn - A logic that receives signals (either frca

(

initiation icgic or channels) and prcduces decision cutputs to accomplish a protective action.

Logic system Functional Ter t - A 1cgic system functional test means a test of all relays and contacts cf a logic cire:uit to insure all components are operable per design intent.

Where practicable, action will gc to ccmpletion; i.e.,

pumps will be started and valves operated.

Maximum FracticTi gf Limiting Pcwer Density (MFLPD) - The Maximum Fraction cf Limiting Power Density (FJLPO) is the highest value existing in the core of the Fracticn of Limiting Power Density (FLPD).

Minimum critical Fewer Ratio (MCFB) - The minimum in-ccre critical power ratio correspondir.g to the most limiting fuel assembly in the core.

Mode of Oceration - A reactor mode switch selects the proper interlocks for t'he operational status cf the unit.

The folicwing are the medes and interlocks provided:

3efuel Mcde, Run Mcde, Shutdcwn Ecde, Startup/Ect Standby Mode.

CPERA2LE - CPIFASILITY - A syster, subsystem, train, ccmponent, or device is OPERAELE or has OPEBAEILITY when it is capatie of performing its specified function and all instrumentation, J

controls, normal and emergency electrical power sources, ccoling l

or seal water supplies, lubrication systems, and etner auxiliary l

equipment that are required for the system, subsystem, train, i

Amendment No.Xg71 t

o

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PBAPS 1.0 DEFINITIONS (Cont ' d) component, or device to perform its functicn are also, capable of performing their related support function.

=

ooeratina - Operating means that a syster er ccaponent is performing its intended functions in its required manner.

Crerating cycle - Interval between the end of cne refueling cutage for a particular unit and the end of the next subsequent refueling outage fcr the same unit.

Primary Containment Intecrity - Primary containment integrity means that the drywell and pressure suppression chamber are intact and all of the following conditions are satisfied:

1.

All ncn-automatic containment isolation valves on lines conn.act:4 to the reictor coolant system or containment which are net required to be open during accident conditions are closed.

These valves may he opened to perform necessary operational activities.

2.

At least one door in each air 1cck is closed and sealed.

3.

All autcmat{c containment isolation valves are operahle or deactivated in the isolated position.

l l

4.

All blind flanges and manways are c1csed.

Protective Action

- An action initiated by the protecticas system when a limit is reached.

A protective action.can be at a channel j

or system level.

Protective Function - A system prctective action which results from the protect)ve action of the channels monitcring a particular plant condition.-

Rated Power - Rated power refers to operation at a reactor power of 3,293 MWt; this is also tenned 100 percent power and is the maximum power level authorized by the operating license.

Rated steam flow, rated coolant flow, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters when the reactor is at rated power.

Amendment No.7, X 71

-4

i LIMITING CONOTTIONT FCR OPERATICE I

3.0 APPLICAEILITY A.

Limiting Ccnditions for Operation and action requirements are i

applicable during the operational conditions and other states specified for each specificaticn.

t B.

Adherence to the requirements cf the Limiting Condition of operation and associated action within the specified time

-interval ccnstitute compliance with the specification 11 the limiting condition for Cperaticn is restored before the specified time interval expires.

C, If a limiting Condition for Cperati39 or asscciated action requirements cannot be satisfied, the unit shall be placed in HCT SEUTDCWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in CCLC SBUTECWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> unless corrective measures are ccmpleted to satisf y the Limiting Ccndition for Cperatien or action requirer.ent, or until the reactor is placed in an operational condition in which the specification is not applicatie.

Exceptions to this requirement are stated in the individual specifications.

D.

When a system, subsystem, train, ccmponent or device is deterr.ined to be inoperable solely because its emergency pcwer scurce is inoperable, cr solely beca. :? its normal power scurce is inoperable, it may be considered OPERAELE for the purpose of satisfying the requirements of the limiting Conditien for Cperation, provided:

(1) its corresponding normal or emergency power source is CPERABLE; and (2) all of its redundant systems, subsystems, trains, components and devices are CPERAELE, or satisfy this specification.

Unless both conditicns (1) and (2) are satisfied, the unit shall be placed in BOI SHUTDCWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in COLD SHUTDCWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

This specification is not applicable in Cold Shutdcwn.

Amendment No. 71

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.n.

BASES - LIMITIEG CONDITIONS FOR OPERATION APPilCABILITY ~ ~

3.0.c This specification delineates the action to be taken for circumstances not directly provided for in the act3cn statements and whose occurrence wculd violate the incent of the specification.

For example, a specificaticn may require.two subsystems to be operable and provides explicit action requirements if one subsystem is incperable.

Under the terms of specification'3.0.C, if both of the required subsystems are inoperable, and an acticn requirement is not identified in the specificaticns, then the unit is to be in at least not shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 'and in Cold Shutdcun within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

3.0.D This specification delineates what additional ccnditions must be satisfied to permit operation to centinue, consistent with the action statements f or power scurces, when a normal cr emergency power source is not cperable.

It specifically prohibits operaticn when one divisicn is incperatie because its normal or emergency power source is incperatie and a system, sutsystem, train, ccmpenent or device in another division is inoperable fer ancther reascn.

The provisiens of this specification permit the action statements asscciated with individual systems, subsystems, trains, ccmponents or devices to te consiutent with the action statements of the associated electrical power source.

It allows operation to be governed by the time limits cf the action statement associated with the Limiting condition for Cperation for the normal or emergend gewer source, not the individus1 acticn statements for each system, subsystem, train, ccmponent or device that is determined tc he inoperable solely because of the incperability of its normal cr emergency power source.

For example, Specification 3.5.7.1 proyides f or an cut-of-service time when one of the four diesel generators is not operable.

If the definition of operable were applied withcut consideration of Specification 3.0.D, all systems, subsystems, trains, components, and devices supplied by the inope.rable emergency power source would aisc be incperatie.

This would dictate invoking the applicable acticn statements for each cf the applicable Limiting conditiens for operation.

However, the provisicns cf specificaticn 3.0.D permit the time limits f or continued operaticn to be consistent with the action statement for the inoperable emergency diesel generator instead, prcvided the other specified conditions are satisfied.

l Amendnent No. 71

-34a-l

- -.. ~. - -

CASES - LIMITIFG CONDITIONS FOR OPERATIOfLAPPLICABILITY (Cont'd).

In this case, this would mean that the corresponding normal power source must te operatie (as must be the corpenents supplied by the normal pcwer scurce) and all redundant systems, subsystems, trains, components and devices

• in the other divisicn must he operable-, or likewise satisfy specification 3. 0.D (i.e., he capable of performing their design functions and have an emergency power scurce operable).

If these conditions are not satisfied, shutdown is required in accordance with this specification.

In the cold shutdown condition and refuel mode, Specificatien 3. 0.D is not applicable; and thus, the individual action statements for each applicable Limiting conditien for Cperation in these conditions must te ashered to.

+

Amendment No. 7 I i

-34b-

...-- --.=...

=

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PDAPS L,IMITI]C CONDITIO.'!S F O R,0 P,E R AT I O N, 5,URVEILLANCE REQUI,REME,NTS 3*1 EE. A C,IO,3,P R O T E CT IO N,,,5 Y S,T EM 4.1 R E A C TO R,,P,R O,T E C TI,0 N SYS, TEM A gp li c a b ili t y,;,

A, p,p l i c a b ili t vi Applies to the instrumenta-Applies ~ to the surveillance tion and associated devices of the instrumentation and which initiate a reactor associated devices which scram. -

initiate reactor scram.

,0,b je c t i v e O b je c t ive To assure the operability To specify the type and of the reactor protection frequency of surveillance system.

to be applied to the pro-tection instrumentation.

'Soecification:

Sp,ecification:

A.

When there is fuel in the vessel, A.

Instrumentation systems the setpoint, minimim number shall be functionally of trip systems, and minimum is.L.i auf calibrated number of instrument channels as indicated in Tables that must be operable for 4.1.1 and 4.1.2 each position of the reactor respectively.

mode switch shall be as given in Table 3.1.1.

B.

The designed system response times from B.

Daily, during reactor power the opening of the sensor contact up operation, the maximum f raction to and including the opening of the of limiting power density shall trip actuator contacts shall not be checked and the SCRAM and APRE exceed 100 milliseconds. Other-Rod Block settings given by wise, the affected trip system equations in Specification shall be placed in the tripped 2.1.A.1 and 2.1.3 shall be condition, or the action listed calculated if the maximum in Table 3.1.1 for the specific fractio-of the limiting power trip function shall be taken.

densit, ixceeds the fraceton of rated power.

4 a

Amendment No..,6Y, X 7 1

-35

PEAPS LIMITING CCEDITICNS FCR CPERATION SURVIIILANCE RIOUIRENENTS 3.6.3 Coolant chemistry 4.6.B. Coolant chemistry

2. The folicwing limits shall be

2. A sample of reactor coolant chall observed for reactor water be analyzed:

quality pricr to any startup

{

and when operating at rated a) At irsst every 4 days at steaming 1

pressure:

rates above 100,000 pounds per hour fcr conductivity and a) Conductivity 5.0 umho/cm chloride icn centent.

i at 25 ' c

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by Chloride concen-0.2 ppm b) At least every day during startups tration and at steaming rates below 100,000 pounds p.er hour for conductivity and chloride icn content.

1

3. Reactor water quality may ex-c) At least every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during ceed the limits of Specifica-startups and at steaming i

tion 3.6.9.2 only for the rates below 100,000 pounds time limits specified below.

per hour + for chloride icn If these time limits or the content if the ccnductivity j

maximum quality limits specified is above 0.5 umhc/cn or if it are exceeded, the unit shall te increases at a rate of 0.2 placed in Ect Shutdown within umho/cm/hr or more.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown within 36 hcurs, unless a safety d) At least once every wtek for analysis, approved by FCRC and total iodine ccncentration when OCSR Ccamittee, has confirmed the air ejector offgas acnitor that the higher i.mpurity levels indicates that the stack release will nct darage primary system rate wculd be in excess of materials.

100,000 uci/sec assuming a 30 min. holdup.

a) Conductivity at 25

• C Time above 2 weeks / year 5 umho/cm Maximur limit 10 umhos/cm Amendment No. 71

-145a-

PEAFS i

LIMITING CCNDIIICNS FCR CPERATICE SURVEILLANCE REQUIREMENTS 3.6.B Coolant Chemistry (Conted) 4.6.3 Coolant Chemistry (Cont ' d) b) Chloride Concentration Time above 2 weeks / year 0.2 ppm Maxiini2r limit 1.0 ppm c) pH During operations, if the conductivity exceeds 1. 0 umho/ca, pH shall be measured and brcught within the 5.6 to 8.6 range within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the pH cannot be ccrrected, or if the pH is outside a range of 4 to 10, the unit shall be placed in Hot Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdcun within 36 bours.

C.

Coolant Ieakace C.

Coolant Leakage

1. Any tire irradiated fuel is 17 Reactor coolant system leakage in the reactor vessel and reacter shall be checked by the sump coolant temperature is above pump and air sampling system 212 degree F, reactor coolant leakage and recorded at least once to the primary containment frca per day.

unidentifieg sources shall not exceed S gyr.. In addition, the total reacter coolant system leakage into the primary con-tainment shall not exceed 25 gpr.

2. Both the sump and air sampling systems shall be operable during reactor power operation. From and after the date that on-of these systers is made or fo.nd to be incperable fer any reascn, reactor power operation is permissible only during the succeeding seven days unless the system is made operable sooner.

3. If the ccnditiens in 1 or 2 cannot be met,.an crderly shutdown shall be initiated and the reactor shall be in

. Cold Shutdcun Ccndition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

1 I

Amendment No. 71

-146-

PEAFS LIMITING CONDITICES FCR OPERATICE SURVE!LLANCE REQUIREMENTS 3.7.A.6.c.

(Cont ' d) 4.7.A.6.a (Cent'd) the unit shall be in Hot The CAD system H2 and C2 Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

analyzers shall te tested for operability using standard t

bottled H2 and 02 cnce per sonth and shall be calibrated once per 6 mcnths. The atmospheric analyzing system shall be func-ticnally tested once per operating cycle in conjuncticn with the specification 4.7.A.6.a.

Should one of the tuc B2 or C2 analyzers serving the 'drywell cr suppression pool be found incperatie the remaining analyzer of the same type serving the same ecmpartment shall be testd f or operability ence per week until the defective analyzer is made o,:erable.

d. A 30 psig limit is the maximur centainment repressurizatien allowable using the CAD system. Venting via the SEGI system to this stack sust te initiated at 30 psig follcwing the initial peak pressure at 49.1 psig.

Abendment No. % M ?1 i

-173-

PEALS LIMITING CCNDITICNS FCR OPERATICE SURVEILLANCE REOUIREMENIS 3.7.C Secendarv centainment 4.7.C Seccndary centainment 1.

Secondary centainment 1.

Secondary containment surveillance integrity shall be maintained shall te performed as indicated during all redes of plant below:

operation except when all of the fellcwing ccnditions a) A preoperational secondary con-are met.

tainment capability test shall be conducted after isolating a) the reactor is subcritical and the reacter building and placing and Specificaticn 3.3.A is either standby gas treatment met.

system filter train in operaticn.

b) the reactor water temperature Such tests shall demonstrate the is belcw 212 Degrees F and the capability to maintain 1/4 inch reactor coolant system is of water vacuum under calm wind vented.

(<5 mph) conditions with a filter c) No activity is being performed train flow rate of not more than which car reduce the shutdown 10,500 cfm.

1 margin belcw that speci:;ied b) Additional tests shall be perf ersed in Specificiaticn 3. 3. A.

during the first cperating cycle d) The fuel cask cr irradiated under an adequate number cf fuel is not being moved in different envircnmental wind the reactor building.

ccnditions to enable valid extrapolation of the test results.

c) Seccndary containrent capability

2. If Specification 3.7.c.1 can-tc maintain 1/4 inch of water not be met, the unit shall be vacuum under. calm wind (<5 mph) placed in Hct Shutdown within ccnditions with a filter train 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold Shutdown flow rate cf not more than witPin 3 6 hcurs, irradiated 10,500 cfm, shall be demonstrated j

fue_ handling operations in at each refueling outage prior the secondary containment, to refuel 2nc.

core alteraticns, and acti-d) After a secondary centainment vic-vities which could reduce lation is deterr.ined, the standby the shutdown margin shall be gas treatment system will he suspended.

operated immediately after the aff ected zones are isolated from the remainder cf the seccndary containment to ccnfirm its ability to maintain the remainder of the secondary centainment at 1/4 inch of water negative pressure under calm wind ccnditions.

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Amendment No. 71

-176-

PBAPS LIMITING CONDITIONS FC,a

• OPERATION SURVEILLANCE REQUIREMENTS 3.12 River' Level 4.12 River Level Applicability:

Applicability Applies to the status of Applies to the surveillance the river level.

requirements associated with river level.

Specification:

Specification:

A.

High River Water Level A.

High River Water Level 1.

If river level reaches a level of 113.0 ft. (C.D.) at Peach Bottom and the pre-dicted flow rate is greater than 840,000 cfs, the reac-tors will be shut down to the cold condition using normal operating proce-dures.

2.

7f the river level exceeds 114.0 ft.

(C.D.) at Peach Bottom, the reactor will be manu-allysserammed and placed in the cold condition according to the applic-able Special Event Pro-cedure.

B.

Low River Water Level B.

Low River Water Level 1.

In the event of an un-

~

scheduled drop in river level to 104.0 f t. (C.D.)

at Peach Bottom,the re-actors shall be shut down to the cold condition using normal operating procedures.

2.

In the event of an un-scheduled drop in water level to 98.5 ft. (C.D.)

at Peach BottonLthe re-actors will be manually scrammed and placed in the cold condition accord-ing to the applicable Special Event Procadure.

t

-237-APRIL 1973

.m.

y

PEAPS LIMITING CCNDITICNS FCF OPEFATION SURVEILLA11CE REQUIREMENTS C. Level Instrumentation C.

Level Instrumentatien 1.

Two of the three river

1. River water level shall be water leve1' indicators in legged once each shif t.

the control rocm shall be continuously cperable.

2.

Should less than 2 indicators

2. Operability shall me be available, prcmpt action

• checked once each shift shall te taken to restore by visual cbservation during at least 2 indicators to level logging centinucus cperation.

Shutdown of the reactor ic not required.

l

-238-Amendment No. 71

UNITED STATES'

/

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20655 y

j k.....,/

PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCXET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDTNT TO FACILITY OPERATING LICENSE Amendment No. 69

• License No. OPR-56 1.

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

A.

The application for amendment by Philadelphia Electric Company. et al. (the licensee) dated May 20, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confamity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities nthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

l l

1

' 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 69, are hereby incorporated in the license.

PECO shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY C0!HISSION PY.

4 W

TobertW.Reid, Chief Operating Reactors Branch #4 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: July 15,1980 9

a

ATTACHMENT TO LICENSE AMENDMENT NO. 69 FACILITY OPERATING LICENSE N0. OPR-56 DOCKET N0. 50-278 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

R P es Insert Pages 3

4 34 34-34a (added) 34b (added)

-35 145a 145a 146 6

173 176 237 238

• 0verleaf; no changes on this page.

l l

1,.,

PBAPS 1.0 DEFINITIONS (Cont'd) the automatic protective action at a level such that the safety l

limits will not be exceeded.

The regicn between the safety limit l

and these settings represents margin with normal operation lying

(

below these settings.

The margin has heen estahlished so that l

with proper operation of the instrumentation, the saf ety limits wiJ1 never be exceeded.

e Locic - A logic is an arrangement cf relays, contacts and cther compcnents that produces a decision output.

4 (a) Initiatina - A logic that receives signals from channels and produces decision outputs to the actuation icgic.'

(b) Actuatien - A logic that receives signals (either frcm initiation icgic or channels) and prcduces decision cutputs to accomplish a protective action.

logic System Functional Ter,t - A 1cgic system functional test means a test of all relays and contacts cf a lo3

• c cire:uit to insure all components are operable per design intent.

Where practicable, action will go to ccmpletion; i.e., pumps will be started and valves operated.

Maximum Fracticn of Limitinq Pcwer Density (MFLPD) - The Maximum Fraction cf Limiting Power Density (MFLP C) is the highest value existing in the ccre of the Fracticn cf limiting Power Density (FLPD).

Minimum Critical Fewer Fatio (MCPR) - The minimum in-ccre critical power ratio corresponding to the most limiting fuel assembly in the core.

Mode of Oceration - A reactor mode switch selects the proper interlocks for the operational status cf the unit.

The folicwing are the acdes and interlocks provided:

3efuel Mcde, Run Mcde, Shutdcwn Ecde, Startu p/ Hot Standby Node.

t l

CPERAELI - CPIRABIIITY - A syster, subsystem, train, ccmponent, or device is OPERABLE or has OPEEAEILITY when it is capable of performing its specified function and all instrur.entation, controls, normal and emergency electrical power sources, ccoling or seal water supplies, lubrication systems, and other auxiliary equipment that are required for the system, subsyr.em, train, i

~

Amendment nog 7, ff,6 9 1

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}

l

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PBAPS 1

1.0 DEFINITIONS (Cont' d) component, or device to perform its functicn are also capable of perf orming their related support function.

operatino - operating means that a system er ccaponent is performing its intended functions in its required manner.

l neerating cycle - Interval between the end of cne refueling cutage for a particular unit and the end of the next subsequent i

refueling outage fer the same unit.

1 Primarv 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 ncn-automatic containment isolation valves on lines i

connect:4 to the reactor coolant system or centainzent which are nct required to be open during accident conditions are closed.

These valves may he opened to perform necessary operational activities.

2..

At least one door in each airlcck is closed and sealed.

3.

All autcmat4c containment isolation valves are operable or deactivated in the isolated position.

4.

All blind flanges and manways are cicsed.

An action initiated by the protection system Protective Action when a limit is reached.

A protective action can he at a channel or system level.

a Protective Function - A system prctective action which results from the prctective action of the channels acniter.ng a particular plant condition.

Rated Power - Rated power refers tc cperaticn at a reacter power of 3,293 FWt; this is also termed 100 percent pcwer and is the maximum pcwer level authorized by the cperating license.

Rated steam ficw, rated coolant ficw, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters when the reacter is at rated power.

Design power, the pcwer to which the safety analysis applies, is 105% of rated power, which corresponds to 3440 met.

9 Amendment No. g/,6 9

LIMITING CONDITIONS FOR OPERATION 3.0 APPLICAEILITY A.

Limiting Ccnditions for Operation and action requirements ate applicable during the operational conditions and other s,tates I

specified.for each specificaticn.

3.

Adherence to the requirements cf the Limiting condition of

)

Operation and associated action within the specified time l

interval ccnstitute compliance with the specification if the Limiting Condition for Cperaticn is restored bef ore the specified time interval expires.

C.

If a Ilmiting condition for Cperation or asscciated action requirements cannot be satisfied, the unit shall be placed in HCT SHUTDCEN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in CCLE SBUTCOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> unless corrective measures are ccmpleted to satisf y the Limiting Ccndition for Operaticn or action requirer.ent, or until the reactor is placed in an operational condition in j

which the specification is not applicable.

Exceptions to this requirement are stated in the individual specifications.

D.

When a system, subsystem, train, ccmponent or device is determined to be inoperable solely because its emergency power scurce is inoperable, cr sclely beca.urt its normal power scurce is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of the limiting Conditicn for Cperation, provided:

(1) its corresponding normal cr emergency power source is CPERAELE; and (2) all of its redundant systems, subsystems, trains, ccmponents and devices are CPERAELE, or satisfy this specification.

Unless both condittens (1) and (2) are satisfied, the unit shall be placed in EOI SHUTDCWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in COLD SBUTCCWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

This specification is not applicable in Cold Shutdcwn.

Amendment No.,3476 9

-3

BASES - LIMITIEG CONDITIONS FOR OPERATION APPLICABILITY 3.0.C This specification delineates the action to be taken for circt 1 stances not directly provided for in the action statements and whose occurrence wculd violate the intent of the specification.

For example, a specificatica may i

require two subsystems to be operable and provides explicit action requirements if one subsystem is incperable.

Under the terms of Specification 3.0.C, if both of the required subsystems are inoperable, and an acticn requirement is not identified in the specificaticns, then the unit is to be in at least Bot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within 36-hours.

3.0.D This specification delineates what additicnal ccaditions must be satisfied to permit operation to centinue, consistent with the action statements f or power scurces, when a normal er emergency power source is not cperable.

It specifically prohibits operaticn when ene divisicn is incperable because its normal or emergency power source is incperable and a system, subsystem, train, ccmpenent or device in ancther division is inoperable fer ancther reascn.

The provisiens of this specification permic the action statements asscciated with individual systems, rutsystems, trains, ccmponents or devices to te consistent with the acticn statements of the associated electrical power i

source.

It allows operation to be governed by the time

, limits of the action statement associated with the Limiting condition for Cperation for the normal or emergench pcwer source, net the individual acticn statements for each system, subsystem, train, ccaponent or device that is determined tc te inoperable solely because of the incperability of its normal cr emergency power source.

For example, specification 3.5.7.1 provides for an cut-of-service time when one of the four diesel generators is not operable.

If the definition of operable were applied 4

withcut consideration of Specification 3.0.D, all systems, subsystems, trains, components, and devices supplied by the 1noperable emergency power source would alsc te incperatie.

This would dictate invoking the applicable acticn statements for each cf the applicable Limiting Conditicns for Operation.

However, the provisicas cf Specificaticn 3.0.D permit the time limits for continued operaticn to be consistent with the acticn statement for the inoperable emergency diesel generator instead, prcvided the other specified conditions are satisfied.

-34a-kmendmentNo.69 o

,n-

BASES - LIMITIEG CONDITIONS FOR OPERATION APPLICABILITY (Cont'd)

Ir. this case, this would mean that the corresponding no2. mal power source must be operable (as must be the i

carpenents supplied by the normal pcwer scurce) and a).1 redundant systems, subsystems, trains, components and devices in the other divisien must be operables or likewise satisfy specification 3.0.D (i.e., be capable of performing their design functions and have an emergency power scurce operable).

If these conditicns are not sa tisfied, shutdown is required in accordance with this specification.

In the cold shutdown condition and refuel mode, Specificatien 3.0.D is not applicable; and thus, the individual action statements for each applicable Limiting Conditien for Cperation in these conditions must he adhered to.

r Amendment No. 6 9

-3 e-

...r.

• :. ~. _

! -._. _ ; C --

p, PDAPS LIMITINC CONDITIONS FOR OPERATION SURVEILLANCE REOUIREME!iTS 3.1 REACTOR PROTECTION SYSTEM 4.1 REACTOR PROTECTION' SYSTEM I

Applicability:

Applicability:

Applies to the instrumenta-Applies to the surveillance tion and associated devices of the instrumentation and which initiate a reactor associated devices which scram.

initiate reactor scram.

Objective Ob je ctive i

To assure the operability To specify the type and of the reactor protection frequency,of surveillance system.

to be applied to the pro-tection instrumentation.

Seecification:

Specification:

A.

tihen there is fuel in the vessel, A.

Instrumentation systems the setpoint, miniwim number shall be functionally of trip systems, and minimum ie i.d an ! calibrated number of instrument channels as ind4cated in Tables that must be operable for 4.1.1 and 4.1.2 each position of the reactor respectively.

modet switch shall be as given in Table 3.1.1.

B.

The designed system response times from 3.

Daily, during reactor power the opening of the sensor contact up operation, the maximum f raction to and including the opening of the of limitt.6 density factor shall trip actuator contacts shall not be checked and the SCRAM and APRM exceed 100 milliseconds. Other-Rod Block settings given by wise, the affected trip system equations in Specifiestion shall be placed in the tripped 2.1.A.1 and 2.1.3 shall be condition, or the action listed calculated if the maximum in Table 3.1.1 for the specific fraction of the limiting power trip function shn11 he taken, density execeds the fraction of rated power.

l Amendment NO. g,6 9.

PEAPS IIMITING CCEDITICNS FCR CPERATION SURVEILLANCE REQUIREMENTS 3.6.3 Coolant Chemistry 4.6.B. Coolant chemist'ry

2. The folicwing limits shall be

2. A sample of, reactor coolant shall observed for reactor water he analyzed:

quality pricr to any startup and when operating at rated a) At least every 4 days at steaming pressure:

rates above 100,000 pounds per hour fcr conductivity and a) ccnductivity 5.0 umho/cm chloride icn centent.

at 25

• C b) Chloride concen-0.2 ppm b) At least every day during 7tartups tration and at steaming rates below 100,000 pounds per hour for conductivity and chloride icn content.

3. Reactor water quality may ex-c) At least every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during ceed the limits of Specifica-startups and at steaming tien 3.6.9.2 only for the rates telow 100,000 pounds time limits specified below.

per hour for chloride icn If these time limits or the content if tlie ccnductivity maximum quality limits specified is above 0.5 umho/cm or if it are exceeded, the unit shall te increases at a rate of 0.2 placed in Bct Shutdown within umbo /cm/hr or more, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown

. within 2 6 hcurs, unles s a s af ety d) At least once every week for analysis, approved by FCPC and total iodine concentration when OSSR Ccmmittee, has confirmed the air ejector offgas mcnitor that the higher impurity levels indicates that the stack release will nct darage primary system rate wculd be in excess of l,

materials.

100,000 uci/sec assuming a 30 min. holdup.

a) Conductivity at 25

• C Time above 2 weeks / year 5 umho/cm Maximur limit 10 umbos/cm Amendment No. 6 9

-145a-

~

PEAPS LIMITING CCNDITICNS FCR OPERATION SURVEILLANCE REOUIREMENTS 3.6.B Coolant Chemistry (Cent e d) 4.6.3 Coolant chemistry (Cont ' d) b) Chloride Concentration Time above 2 weeks / year 0.2 ppm Maximun limit

1. 0 ppm c) pH During operations, if the conductivity exceeds 1. 0 umho/cm, pH shall be measured and brought within the 5.6 to 8.6 range within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the pH cannot be ccrrected, or if the pH is outside a range of 4 to 10, the unit shall be placed in Hot Shutacwn within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdcwn within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

C.

Coolant Ieakace C. Coolant Leakace

1. Any time irradiated fuel is 17 Reactor coolant system leakage in the reactor vessel and reacter shall he checked by the sump coolant temperature is above pump and air sampling system 212 degree F, reactor coolant leakage and recorded at least once to the primary containment frca per day.

unidentified, sources shall not exceed 5 gpz. In addition, the total reacter ccolant system leakage into the primary con-tainment shall not exceed 25 gpr.

2. Both the sump and air sampling systems shall be operable during reactor power operation. Frcm and af ta.- the date that one of these s) aters is made or found to be ir operable fer any reasen, reactor power operation is permissible only during the succeeding seven days unless the syctem is made operable sooner.

3. If the ccnditicns in 1 or 2 cannot he met,,an crderly shutdown shall be initiated and the reactor shall be in Cold shutdcun Ccndition within

'24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i Amendment No. 6 9

-146-

PEAPS LIMITING CONDITICKS FCR OPERATICN SURVEILLANCE REOUIREMENTS 3.7.A.6.c.

(Cont ' d) 4.7.A.6.a (Cont'd) the unit shall be in Hot The CAD system H2 and C2' Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

analyzers shall te tested for operability using standard bottled H2 and 02 cnce per sonth and shall be calibrated once per 6 mcnths. The atmospheric analyzing system shall be. func-ticnally tested once per operating cycle in conjuncticn with the specification 4.7.A.6.a.

Should one of the tuc.B2 or c2 analyzers serving the drywell er suppression pool.be found inoperatie the remaining analyzer of the same, type serving the same ccmpartment shall be testd for operability once per week until the def ective analyzer is ande oJerable.

d. A 30 psig limit is the maximum centainment repressurizaticn allowable using the CAD system. Venting via the SEGI system to this stack rust te initiated at 30 psig folicwing the initial peak pressure at 4 9.1 psig.

W Amendment No. g.f 6 9

-173-

PEAPS LIMITING CCNDITICNS FCR OPERATION SURVEILLANCE REQUIREMENTS 3.7.C Secendary Centainment 4.7.C Secendary Centainm nt j

1.

Secondary centrinment 1.

Secondary containment surveillance integrity shall be maintained shall he performed as indicated l

during all sodes of plant below:

operation except when all of the fellcwing conditions a) A preoperational secondary con-are met.

tainment capability test 'shall be conducted af ter isolating a) the reactor is suberitical and the reactor building. and placing and Specificatien 3. 3. A is either standby gas treatment met.

system filter train.in operaticn.

L) the reactor water temperature Such tests shall demcnstrate the is belcw 212 Degrees F and the capability to maintain 1/4 inch reactor coolant system is of water vacuum'under calm wind vented.

(<5 mph) conditions with a filter c) No activity is being performed train flow rate of not more than which car reduce the shutdown 10,500 cfm.

margin belcw that speci:;ied b) Additional tests shall be perf crsed in Specificiaticn 3. 3. A.

during the first cperating cycle d) The fuel cask cr irradiated under an adequate number cf fuel is not being moved in dif ferent envircnmental wind the reactor building.

ccnditions to enatie valid extrapolation of the test results.

c) Secondary containment capability

2.. If Specification 3.7.C.1 can-tc maintain 1/4 inch of water net.be met, the unit shall be vacuum under calm wind (<5 mph) placed in Ecp Shutdown within ccnditions with a filter train 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown flow rate of not more than within 36 hcurs, irradiated 10,500 cfm, shall be demonstrated fuel handling operations in at each refueling outage prior the secondary containment, to refueling.

core alteraticns, and acti-d) After a secondary centainment vic-vities which could reduce lation is deterr.ined, the standby the shutdown margin shall be gas treatment system will be suspended.

operated immediately after the aff ected zones are isolated from the remainder cf the

.aeccndary containment to ccnfirm its ability to maintain the remainder of the secondary centainment at 1/4 inch of water negative pressure under calm waad ccnditions. -

Amendment No. 6 9

-176-l-

PBAPS LIMITING CONDITIONS FOR OPERATION

' SURVEILLANCE REQUIREMENTS *'

3.12 River Level 4.12 River Level Applicability:

Applicability:

Applies to the status of Applies to the surveillance the river level.

requirements associated with river level.

Specification:

Specification:

A.

High River Water Level A.

High River Water Level 1.

If river level reaches a level of 113.0 ft.(C.D.) at Peach Bottom and the pre-dicted flow rate is greater than 840,000 cfs, the reac-tors will be shut down to the cold condition using normal operating proce-dures.

2.

If the river level exceeds 114.0 ft.

(C.D.) at Peach Bottom, the reactor will be manu-ally scrammed and placed in the cold condition according to the applic-able Special Event Pro-cedure.

B.

Low River Water Level B.

Low River Water Level 1.

In the event of an un-scheduled drop in river level to 104.0 ft. (C.D.)

at Peach Bottom,the re-actory shall be shut down to the cold condition using normal operating procedures.

2.

In the event of an un-scheduled drop in water level to 98.5 ft. (C. D. )

at Peach Bottom,the re-actors will be manually scrammed and placed in the cold condition accord-ing to the applicable Special Event Procedure.

-237-APRIL 1973

PEAPS I.IMITI!IG CCNDIIICNS TCP OPEFATICE SURVEILLANCE RIQUIREMENTS C. Level Instrumentation C.

Level Instrumentaticn 1.

Two of the three river

1. River water level shall be water level indicators in icgged once each shif t.

the control roca shall be continuously cperable.

Shou'd less than 2 indicators

2. operability shall be 2.

1 be available, prompt action checked ence each sbift shall te taken to restore by visual chservation during at least 2 indicators to level logging centinucus cperatien.

Shutdown of the reactor is nct required.

1 e

Amendment No. 6 9

-238-

.