ML19323D946

Application for Amend of Licenses DPR-44 & DPR-56,changing Facility Tech Specs to Conform to Model Tech Specs,Per DG Eisenhut 800410 Request.Certificate of Svc Encl

ML19323D946
Person / Time
Site:	Peach Bottom
Issue date:	05/20/1980
From:	Bauer E, Bradley E, Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML19323D943	List: ML19323D941 ML19323D946
References
NUDOCS 8005220577
Download: ML19323D946 (17)

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BEFORE THE UNITED STATES NUCLEAR REGULATCRY CCMMISSICN In the Matter cf  :

Docket Nos. 50-277 PIIILADELPHIA ELECTRIC CCMPANY  : 50-278 APPLICATIO;1 FOR AMENCMENT OE FACILITY OPERATING LICENSES DPR-44 & CPR-56 Edward G. Bauer, Jr.

I Eugene J. Bradley 2301 Market Street Philadelphia, Pennsylvania 19101 l

Attcrneys for Philadelphia Electric Ccapany 8006220577

BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of  :

Docket Nos. 50-277 PHILADELPilIA ELECTRIC COMPANY  : 50-278 l

APPLICATION FOR AMENDMENT OF i l

FACILITY OPERATING LICENSES DPR-44 S DPR-56 1

Philadelnhia Electric Company, Licensee under Facility Operating Licenses DPR-44 and DPR-56 for Peach Bottom Units i and 3, hereby requests that the Technical Specifications contained in Appendix A of the Operating Licenses be amcnded by revising certain sections as indicated by a vertical bar in the margin of attached pages 3, 4, 34, 35, 145a, 146, 173, 176, and 238, and by the addition of new pages 34a, and 34b.

Correspondence from Mr. Darrell G. Eisenhut, Acting Director, Division of Operating Reactors, NRC, to All Power Reactor Licensees, dated April 10, 1980, requested the submission of a license amendment application to conform with certain sections of the model Technical

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Specifications. The purpose of the requested changes is to clarify the meaning of the term operable, to provide action statements for those Limiting Conditions of Operation that do not address multiple outages of redundant components, and to address the effects of outages of any support systems, such as electrical power or cooling water, that are relied upon to maintain the operability of the particular system. The changes in response to Mr. Eisenhut's request are shown on pages 3, 9 ., 34, 34a, and 34b. The proposed amendment agrees with the Model Technical Specification, submitted with the letter referenced above, except where changes were necessary to reflect system designs that are plant specific, and to improve comprehension.

The operational made terminology and their definitions,as presently stated in the Peach Bottom Technical Specifications, are consistent with the Mod 3l Technical Specifications; therefore, no changes in this area are proposed.

Additionally, action statements were added or revised to clarify the requirements of several Limiting conditions of Operation. These proposed changes are shown on pages 35, 145a, 146, 173, 176, and 238 of the Tuchnical Specifications. The following revisions were based on the . Standard Technical Specifications for General Electric Boiling Water Reactor, Nureg 0123, (Revision of April 1, 1978).

Peach Bottom Tech. Spec. Standard Tech. Spec.

Section Page Section 3.6.B.3 145a 3.4.4.a.2

3. 6. B. 3 (c) 146 3.4.4.a.2 3.7.A.6.c 173 3.6.6.4.a 3.7.C.2 176 3.6.5.1a and b

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l The proposed changes ta) page 173 i.elete obsolete notes regarding inerting makeup system requirements prior to the first Peach Bottom refueling outage.

Pursuant to 10 CFR 170.22, " Schedule o f Fees for Facility License Amendments", Philadelphia Electric Company proposes that this Application for Amendment be considered a Class II Amendment for Unit 2, and a Class I Amendment for Unit 3, since the proposed changes are deemed to be administrative in nature.

The Plant Operation Review Committee, and the Operation and Safety Revie' Committee have reviewed these proposed changes to the Technical Specifications, and have concluded that they do not involve an unreviewed safety question or a significant hazards consideration, and will not endanger the health and safety of the public.

Respectfully submitted, PHILADELPHIA ELECTRIC COMPANY By \ -~ d '-/~'

Vice' President i t

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col,'*OlMEALTH OF PENNSYLVANIA  :

ss.

COUNTY OF PHILADELPHIA  :

S. L. Daltroff, being first duly sworn, deposes and says:

That he 2.s Vice President of Philadelphia Electric Company, the Applicant herein; that he has read the foregoing Application for Amendment of Facility Operating Licenses and knows the contents thereof ; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.

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Subscribed and sworn to

?L before me this

day of Q.

3 lh CY 1L:9A C. % /

NotaryPublic}

EUJUETH H. 80 /

21aryfut!!c. Fhita., Phita. Co, hg dmminion Egirea Jan,30. ID*.2 l

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CERTIFICATE OF SERVICE I certify that service of the foregoing Application was made upon the Board of Supervisors, Peach Bottom Township, York County, Pennsylvania, by mailing a copy thereof, via first-class mail, to Albert R. Steele, Chairman of the Board of Supervisors, R. D. No. 1, Delta, Pennsylvania 17314; upon the Board of Supervisors, Fulton Township, Lancaster County, Pennsylvania, by mailing a copy thereof, via firsti-class mail, to George K. Brinton, Chairman of the Board of Supervisors, Peach Bottom, Pennsylvania 17563; and upon the Board of Supervisors, Drumore Township, Lancaster County, Pennsylvania, by mailing a copy thereof, via first-class mail, to Wilmer P. Bolton, Chairman of the Board of Supervisors, R. D. No. 1, Holtwood, Pennsylvania 17532; all this 20th day of May, 1980.

e be- llhet L gene . Bradley Attorney for j Philadelphia Electric Company

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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 represent margin with ncrmal cperation lying below these settings. The margin has been established so that with proper operation of the instrumentation, the safety limits will never be exceeded.

Logic - A logic is an arrangement of relays, contacts and other components that produce a decision output.

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

(b) Actuation - A logic that receives signals (either drcm  !

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

Logic System Functional Test - A lcgic system functional test I means a test of all relays and contacts cf a logic circuit to insure all components are operable per design intent. Where practicable, action will go to completion; i.e., pumps will be started and valves operated.

Maximum Fraction of Limiting Power Density (MFLPD) - The Maximum Fraction at Limiting Power Density (MFLPE) is the highest value existing in the core of the Fraction of limiting Power Density (FLPD).

Minimum Critical Power Ratio I,4CFR1 - The minimum in-core critical power ratio correspor.31ng to the most limiting fuel assembly in the core.

Mode of Operation - A reactor mode switch selects the proper interlocks for the operational status of the unit. The following are the modes and interlocks provided: Fefuel Mode, Run Mcde, Shutdown Rode, Startup/ Hot Standby Mode.

OPERABLE - OPERABILITY - A syster, subsystem, train, ccmponent, or device is OPERAELE or has OPEEAEILITY when it is capable of performing its specified function and all instrumentation, controls, normal and emergency electrical power sources, cooling or seal water supplies, lubrication systems, and other auxiliary -

equipment that are required for the system, subsystem, train, PBAPS 1.0 DEFINITIONS (Cont ' d) component, or device to perform its functicn are also capable of perf orming their related support f unction.

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

Operating Cycle - Interval between the end of one refueling outage for a particular unit and the end of the next subsequent refueling outage for the same unit.

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

1. All ncn-automatic containment isolation valves on lines connected to the reactor coolant system or containment which ,

are nct required to be open during accident conditions are  !

closed. These valves may be opened to perform necessary  !

operational activities.  !

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

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

4. All blind flanges and manways are c1csed.

Protective Action - An actior initiated by the protection system when a limit is reached. A p2 otective action can be at a channel or system level.

Protective Function - A system protective action which results from the protective action of the channels monitcring a particular plant condition.

Rated Power - Rated power refers tc operation at a reactor power of 3,293 NWt; this is also termed 100 percent power and is the maximam pcwer 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. Design power, the power to which the safety analysis applies, is 105% of rated power, which corresponds to 3440 MHt.

LIMITING CONDITIONS FOR OPERATION 3.0 APPLICAEILITY A. Limiting Conditions for Operation and action requirements are applicable during the operational conditions and other states specified for each specificaticn.

B. Adherence to the requirements cf the Limiting Condition of Operation and associated action within the specified time interval ccnstitute compliance with the specification if the Limiting condition for Operaticn is restored before the specified time interval expires.

C. If a limiting Condition for Cperation or associated action requirements cannot be satisfied, the unit shall be placed in HOT 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 SHUTEOWN 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 satisfy the Limiting Condition for Operaticn or action requirement, or until the reactor is placed in an operatic 4.a1 cond.'. tion in which the specification is not applicable. Exceptions to this requirement are stated in the individual specifications.

D. When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, cr solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of the Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is CPERABLE; and (2) all of its redundant systems, subsystems, trains, components and devices are OPERAELE, or satisfy this specification. Unless both conditions (1) and (2) are satisfied, the unit shall be placed in HOT 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 SHUTDOWN 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.

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BASES - LIMITING CCNDITICN FOR OFEFAT::CN AFPLICAEILITY 3.0.C This specification delineates the action to be taken for circumstances not directly provided for in the action statements and whose occurrence would violate the intent of the specification. For example, a specification 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 specifications, then the unit is to be in at least Hot 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 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 continue, consistent with the action statements for power sources,

when a normal or emergency power source is not cperable.

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

The provisions ot this specification permit the action statements associated with individual systems, subsystems, trains, components or devices to te consistent with the action statements of the associated electrical power source. It allows operation to be governed by the time limits of the action statement associated with the 3s Limiting Condition for Operation for the normal or emergency power source, not the individual acticn statements for each system, subsystem, train, ccuponent or device that is determined tc be inoperable solely because of the inoperability of its normal or emergency power source.

For example, Specification 3.5.F.1 provides f or an out-of-service time when one of the four diesel generators is not operable. If the definition of operable were applied without consideration of Specification 3. 0.D, all systems, subsystems, trains, components, and devices supplied by the inoperable emer: ency power source would alsc be incperable. This would dictate invoking the applicable acticn statements for each cf the applicable Limiting Conditions for Operation. However, the provisicns of Specification 3.0.D permit the time limits for continued operaticn to be consistent with the action statement for the inoperable emergency diesel generator instead, prcvided the other specified conditions are satisfied.

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BASES - LIMITIEG CCNDITION FOR OPEEAT::CN APPLICAEILITY (Cont ' d)

In this case, this would nean that the corresponding normal power source must te operatle (as must be the corpenents supplied by the normal . power source) and all redundant systems, subsystems, trains, components and devices in the other divisicn must be operable, or likewise satisfy Specification 3. 0.D (i.e., be capable of performing their design f unctions and have an energency 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, Specification 3.0.D is not applicable; and thus, the individual action statements for each applicable Limiting Condieicn for Operation in these conditions must te adhered to.

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PBAPS LIMITING CONDITIONS FOR OPERATION ,

SURVEILLANCE REQUIREMENTS 3.1 REACTOR; PROTECTION SYSTEM 4.1 R E A C T O R _ P R 0_ T E C T I O_ N S Y S_T E_M Agglicabilitt:, A,p,plicability:

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

Objective O b je c.t i ve, To assure the operability To specify the type and of the reactor protection frequency of surveillance system. to be applied to the pro-teccion instrumentation.

Sgecification: Sp,ecification:

A. When there is fuel in the vessel, A. Instrumentation systens the setpoint, minimum number shall be functionally of trip systems, and mininum tested and 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.

given in Table 3.1.1.

n. The designed system response times from B. Daily, during reactor power the opening of the s e r. 'r contact up operation, the maximum f ract ion to and including the ops ing of the of limiting density factor shall' trip actuator contacts shall not exceed 100 milliseconds. Other- be checked and the SCRAM and APR%

Rod Block settings given by wise, the affected trip systen equations in Specification shall be placed in the tripped 2.1.A.1 and 2.1.B 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 shall be taken, unless density exceeds the fraction of a safety evaluation, approved by rated power.

PORC and the O&SR Committee, has confirmed that the higher response time will not result in t ra ns ie n t parameters in excess of the Safety Limits specified in sections 1.1 and 1.2 of these Technical Specifications.

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PEAPS LIMITING COEDITICNS FCR OPERATION SURVEILLANCE REQUIREMENTS 3.6.B Coolant Chemistry 4.6.B. Coolant Chemistry

2. The follcwing limits shall be 2. A sample of reactor coolant shall observed for reactor water be 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) Conductivity 5.0 umho/cm chloride icn centent.

at 25 C b) Chloride concen- 0.2 ppm b) At least every day during startups 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 tion 3.6.B.2 only for the rates telow 100,000 pounds time limits specified below. per hours for chloride ion If these time limits or the content if the conductivity 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 Hct Shutdown within umho/cs/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 week for analysis, approved by FCRC and total iodine concentration when OSSR Ccmmittee, has confirmed the air ejector offgas monitor that the higher impurity levels indicates that the stack release will nct damage primary system rate wculd be in excess of materials. 100,000 uci/sec assuming a 30 min. holdup.

a) Conductivity at 25 "C Time atove 1 weeks / year l 5 umho/cm Maximun limit 10 umhos/cm l

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PEAFS LIMITING CONDITICNS FCR OPERATION SURVEILLANCE REQUIREMENTS 3.6.B Coolant chemistry (Cont ' d) 4.6.B Coolant Chemistr'j (Cont ' d) b) Chloride Concentration Time above 2 weeks / year O.2 ppm i Maximun limit 1.0 ppm c) pH During operations, if the conductivity exceeds 1.0 umho/cm, pH shall Le 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 corrected, or if the pH is outside a range of 4 to 10, the unit shall be placed in i 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 Shutdcwn within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

C. Coolant Leakage C. Coolant Leakage

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

unidentified sources shall not exceed 5 gpn.. In addition, the total reactor 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 one of these systers is made or found to be inoperable for any reason, reactor power oFeration is permissible only during the succeeding seven days unless the system is made operable sooner.

3. If the ccnditions in 1 or 2 cannot be met, an orderly shutdown shall be initiated  ;

and the reactor shall be in 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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l PEAFS LIMITING CONDITICNS FCR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A.6.c. (Con t ' d) 4.7.A.6.a (Cont'd) the unit shall te in Hot The CAD system H2 and 02 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 O2 cnce per month and shall be calibrated once per 6 months. The atmospheric analyzing system shall be func-tionally tested once per operating cycle in conjunction with the specification 4.7.A.6.a.

Should one of the twc H2 or 02 analyzers serving the dryuell or suppression pool be found inoperatle the remaining analyzer of the same type serving the same compartment shall be testd for operability once per week until the defective analyzer is made operable.

d. A 30 psig limit is the maximum containment repressurization allowable using the CAD system. Venting viT the SBGT system to this stack sust to initiated at 30 psig following the initial peak pressure at 49.1 psig.

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PEAFS LIMITING CONDITIONS FCR OPERATION SURVEILLANCE REQUIREMENTS 3.7.C Seccndary containment 4.7.C Seccndary Centainment

1. 1econdary containment 1. Secondary containment surveillance

_ntegrity shall be maintained shall te performed as indicated during all nodes of plant below:

operation except when all of the f cllcwing conditions a) A preoperational secondary con-are met. tainment capability test shall be conducted after isolating a) the reactor is subcritical and the reactor building and placing and Specification 3.3.A is either standby gas treatment ,

met. system filter train in operaticn. '

b) the reactor water temperatures Such teFts 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 can reduce the shutdown 10,500 cfm.

margin below that specified b) Additional tests shall be perf ersed in Specificiation 3.3.A. during the first operating cycle i d) The fuel cask cr irradiated under an adequate number of l fuel is not being moved in different environmental wind l the reactor building. ccnditions to enable valid extrapolation of the test results.

c) Secondary containment capability

2. It 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) l placed in Hot 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 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, irradiated 10,500 cfm, shall be demonstrated fuel handling operations in at each refueling outage prior the secondary containment, to refueling.

core alterations, and acti- d) After a secondary containment vic-vities which could reduce lation is determined, the standby the shutdown margin shall be gas treatment system will te suspended. operated immediately after the affected zones are isolated from the remainder of the secondary containment to ccnfirm its ability to maintain the remainder of the secondary ccntainment at 1/4 inch of water negative pressure under calm wind conditions.

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l PEAPS l LIMITING CCNDITICNS FCR OPERATIOE SURVEILLANCE REQUIREMENTS C. Level Instrumentation C. Level Instrumentation

1. Two of the three river 1. River water level shall be water level indicators in legged once each shift.

the control room shall be continuously operable.

2. Should less than 2 indicators 2. Operability shall be be available, prompt action checked once each shift shall te taken to restore by visual observation during at least 2 indicators to level logging continuous cperation.

Shutdown of the reactor is not required.

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