ML20211H080

Revised Proposed TS Changes to ASME Section XI, Surveillance Testing

ML20211H080
Person / Time
Site:	FitzPatrick
Issue date:	09/26/1997
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20211H072	List: JAFP-97-0359, Informs That Util Is Revising TS Amend Application Submitted Under to Withdraw Proposed Changes to Sections 3.5.G & 4.5.G & SRs of Sections 4.7.A.5.a & 4.7.D.2.Revised TS & Se,Encl ML20211H080 ML20211H086
References
NUDOCS 9710060188
Download: ML20211H080 (31)

Text

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Attcchm:nt I to JAFP 97-0359 PROPOSED TECHNICAL SPECIFICATION CHANGES ASME SECTION XI SURVEILLANCE TESTING TECHNICAL SPECIFICATION PAGE CHANGER (JPTS 93-003)

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i New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 9710060188 970926 PDR ADOCK 05000333 P PDR ,

JAFNPP TECHNICAL SPECIFICATIONS TABLE OF CONTENTS East 1.0 Definitions 1 LIMITING SAFETY SAFETY LIMITS SYSTEM SETTINGS 1.1 Fuel Cladding Integrity 2.1 7 1.2 Reactor Coolant System 2.2 27 SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENTS 3.0 General 4.0 30 3.1 Reactor Protection System 4.1 30i l

3.2 instrumentation 4.2 49 A. Primary Containment Isolation Functions A. 49 B. Core and Containment Cooling Systems - B. 50

, Initiation and Control C. Control Rod Block Actuation C. 50 D. Radiation Monitoring Systems - Isolation D. 50 and initiation Functions E. Drywell Leak Detection E. 53 F. Feedwater Pump Turbine and Main Turbine Trip F. 53 G. Recirculation Pump Trip G. 53 H. Accident Monitoring Instrumentation H. 53 1, 4kV Emergency Bus Undervoltage Trip 1. 53 J. Remote Shutdown Capability J. 54 3.3 Reactivity Control 4.3 88 A. Reactivity Limitations A. 88 B. Control Rods B. 91 C. Scram insertion Times C. 95 D. Reactivity Anomalies D. 96 3.4 Standby Uguid Control System 4.4 105 A. Normel Operation A 105 B. Operation With inoperable Components B. 106 C. Sodium Pentaborate Solution C. 107 3.5 Core and Containment Cooling Systems 4.5 112 A. Core Spray and LPCI Systems A. 112 B. Containment Cooling Mode of the RHR B. I 'l 5 System ,

C. HPCI System C. 117 D. Automatic Depressurization System (ADS) D. 119 E. Reactor Cora isolation Cooling (RCIC) E. 121 System Amendment No. ' '^ ' " ' "' ' ^^ ' ' " '' "'4 i

r-JAFNPP.

' 3.0 Continued 4.0 Continued D. Entry into an OPERATIONAL CONDITION (mode) or other that a Surveillance Requirement has not been performed. - The specified condition shall not be made when the conditions for ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Limiting Condition fnr Operation are not met and the permit the completion of the surveillance when the allowable associated ACTION requires a shutdown if they are not met , outage time limits of the ACTION requirements are less than within a specified time interval. Entry into an OPERATIONAL 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance requirements rio not have to be CONDITION (mode) or specified condition may be made in' performed on inoperable equipment.

accudance with ACTION requirements when conformance to them permits continued operation of the facility for an D. Entry into an OPERATIONAL CONDITION (mode) shall not be' ,

unlimited period of time. This provision shall not prevent .made unless the Surveillance Requirement (s) anociated with . ,

passage through OPERATIONAL CONDITIONS (modes) . the Limiting Condition for Operation have been performed '

required to comply with ACTION requirements. . Exceptions to within the applicable surveillance interval or as otherwise these requirements are stated in the individual specifications. specified. This provision shall not prevent passage through or to Operational Modes as required to comply with ACTION E. When a system, subsystem, train, component or device is . Requirements.

determined to be inoperable solely because its emergency power source is inoperable,' or solely because its normal power E. Surveillance Requirements for inservice testing of components a source is inoperable, it may be considered OPERABLE for the shall be applicable as follows:

purpose of satisfying the requirements of its applicable Limiting '

Condition for Operation, provided: (1) its corresponding 1. Inservice testing of pumps and valves shall be performed normal or emergency power source is OPERABLE; and (2) all of in accordance with Section XI of the ASME Boiler anc' its redundant system (s), subsystem (s), train (s), component (s) Pressure Vessel Code and applicable Addenda'as required. ,

and device (s) are OPERABLE, or likewise satisfy the - by 10 CFR 50, Section 50.55a(f), except where specific l requirements of this specification. -Unless both conditions (1) written relief has been granted by the NRC pursuant to and (2) are satisfied, the unit shall be placed in COLD 10 CFR 50, Section 50.55a(f)(6)(i). The inservice testing ' '

SHUTDOWN within tne following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.' This specification and inspection. program is based on an NRC approved ,

is not applicable when in Cold Shutdown or Refuel Mode. edition of, and addenda to, Section XI of the ASME Boiler and Pressure Vessel Code which is in effect 12 months F. Equipment removed from service or declared inoperable to prior to the beginning of the inspection interval.

comply with required actions may be returned to service under -

administrative control solely to perform testing required to demonstrate its operability or the operability of other equipment. This is an exception to LCO 3.0.B.

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Amendment No. 83,18',188,227 305

4.0 Continued '

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2. Sur.f": c6 intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addende ,

for the incorvice testing activities required by the Code and appicable Addenda shell be appicable as defined in Technical Specification 1.0.T.

3. The provisions of Specification 4.0.B are applicable to the frequencses specified in Technical Specification 1.0.T for '

performing inservice testin2 activities.

4. Performance of the above inservice testeg activities shall I be in addition to other specified Survesitance Requirements.  !

5. Nothing in the ASME Boiler and Pressure Vessel Code shall be constroed to supersede the requirements of any Techrucal Specification.

t t

l Amendment No.

3Ob

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JAFNPP

.i 3.0 BASES 1.

A. This specification states the applicability of each specification D. Continued in terms of defined OPERATIONAL CONDITION (mode) and is  :

provided to delineate specsfically when sech specification is the status of the plant before or after an OPERATIONAL '  ;

CONDITION (mode) change. Therefore in this case, entry into . i applicable.

en OPERATIONAL CONDITION (mode) or other specifood '.

B. This specification defines those conditions necessary to condetion may be made in accordance with the provisions of a constitute comphance with the terms of an indevidual Limiting the ACTION requirements. - The provisions of this specifscation l I

Condition for Operation and ===ariated ACTION requeroment. should not, however, be interpreted as endorsing the fadure to exercise good practice in restonne systems or components to : c C. This specification delenostos the ACTION to be taken for OPERABLE status before startup.  ;

circumstances not directly provided for in the ACTION i statements and whoes occurrence would violate the intent of - Exceptions to this provision may be made for a limited number the specification. Under the terms of Specification 3.0, the of specifications when startup with inoperable equipment  ;

facility is to be placed in COLD SHUTDOWN within the would not affect plant safety. These exceptions are stated in ,

! following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. It is assumed that the unit is brought to the ACTION statements of the appropriate specifications. l the required OPERATIONAL CONDITION (model within the required times by promptly initiating and carrying out the E. This specification delinestes what addetsonal condstions must appropriate ACTION statement. be satisfied to permet operation to continue, consistent with . I the ACTION statements for power sources, when a normal or  !

D. This specification provides that entry into an OPERABLE emergency power source is not OPERABLE. it specifically .

CONDITION (mode) must be made with (a) the full prohstnts operation when one divisoon is inoperable because its  !

complement of required systems, equipment or components normal or emergency power source is inoperable and a i OPERABLE and (b) all other parameters as specsfied in the system, subsystem, train, cornponent or device in another  !

Limiting Conditions for Operation being met without regard for division is inoperable for another reason. .;

allowable deviations and out of service provisions contained in  !

the ACTION statements. The provissons of this specification permit tho' ACTION statements associated with individual systems, subsystems, i The intent of this provision is to insure that facility operation is trains, components or devices to be consistent with the not initiated with either required equepment or systems ACTION statement of the associated electrical power source.

inoperable or other limits bemg exceeded. - Coi --77.ce with it allows operation to be govemed by the time ACTION requirements that permit continued operation of the facility for an unlimited period of t.'me provides an acceptable level of safety for continued operation without the regard to ,

Amendment No. "3,134,1*4 30c ^

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i JAFWPP i

3.0 BASES - Continued i f

E. Continued E. Continued limits of the ACTION statement associated with the Limiting As a further example, Specification 3.9.A. requires in part that

' Condition'for Operation for the normal or emergency power two 115KV lines and reserve station transformers be available. ,

source, and not by the individual ACTION statements for each The ACTION statement provides a 7 day out-of-service time  !

system, subsystem, train, component or device that is when both required offsite circuits are not OPERABLE. If the '

determined to be inoperable solely because of the inoperabdsty definstion of OPERABLE were appleed without consideration of .

of its normal or emergency power source. Specification 3.0.E., all systems, subsystems, trains, components and devices supphed by the inoperable normal For example, Specification 3.9.A. requires in part that both power sources, both of the offsite circuits, would also be emergency diesel generator systems be OPERABLE. The inoperable. This would dictate invoking the applicable ACTION j

ACTION statement provides for a 7 day out-of-service time statements for each of the applicable LCOs. However, the when emergency diesel generator system A or B is not - provisions of Specification 3.0.E. permit the time limits for OPERABLE. If the definition of OPERABLE were apphed continued operation to be consistent with the ACTION j without consideration of Specification 3.0.E., all systems, . statement for the inoperable normal power sources instead,'-

subsystems, trains, components and devices suppbed by the provided the other specified conditions are satisGd. In this i inoperable emergency power source, diesel generator system case, this would moon ti et for one division the emergency A or B, would also be inoperable. This would dictate invoking power source must be OPERABLE (as must be the components - ,

the applicable ACTION statements for each of the appiscable suppbed by the emergency power source) and all redundant Limiting Conditions for Operation. However, the provisions of systems, subsystems, trains, components and devices in the Specification 3.0.E. permit the time Ismits for continued other division must be OPERABLE, or likewise satisfy operation to be consistent with the ACTION statement for the Specification 3.0.E. (i.e., be capable of performeng their desegn 4

inoperable emergency diesel generator system instead, functions and have an emergency power source OPERABLE).

provided the other specified conditions are satisfied.' If they in other words, both emergency power sources A'and B must are not satisfied, shutdown is required in accordance with this be OPERABLE and au redundant systems, subsystems, trains.

specification. components and devices in both divisions must also be '

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

In Cold Shutdown and Refuel Modes, Specification 3.0.E. is not appiscable, and thus the individual ACTION statement for each applicable Limiting Condition for Operation'in these OPERATIONAL CONDITIONS (modes) must be adhered to.

Amendment No. 83r488 sod

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JAMEpP l

3.0 Banas - Continued F. LCO 3.0.F estatdeshes the allowance for restoring g equ9 ment to service under administrative controls when it -

has lasen removed from sorwece or deciered inoperaide to comply with required aceiens. The solo purpose of this

?; 3_ zi+. is to provide an secophon to LCO 3.0.8 to aNow testing to demonstrate: W the operability of the equyment being retumed to sorwice; or (b) the operability of other equipment.

The administratwo controis anosm the time the equipment is retumed to service in conflict with the requirements of the required actions is limiend to the time M*=sy necessary to perform the a5ouwsd testing. This 0;3-::C+. does not provide time to perform any other preventswo or corrective sneintenance.

An example of demonstranne the operabikty of the '

squipment being retumed to service is~esepening a -

containment isoletion volve that has been closed to comply with the required actions and must be reopened to perform the techng.

Ar; example of demonstrating the operability of other equipment is talung an inoperaide channel or trip system out .

of the tnpped condmon to prevent the trip functicr: from occumng dunne the perfonnance of testing on another channoiin the other trip system. A sim5er exampio of -

demonstraang the operabibty of 00p t equipment is taking an inoperable chonnel or trip system out of the tripped ~

condition to permit the logic to functson and irwan .e= the apprognate tw during the ;;A..._.s of testing on :

another channel in the semo trip system.

Amendment No. 22,

• S", 2M, 227 1

JAFNPP 4.0 BASES A. This specification provides that surveillance activities "The provisions of Specification 4.0.8 do not apply to the necessary to insure the Limiting Conditions for Operation are test frequencies specified in the Pnmary Containment met and will be performed during the OPERATIONAL Leakage Rate Testmg Program.* This exception is provided CONDITIONS (modes) for which the Limiting Conditions for because the program already includes provisions for Operation are applicable. Provisions for additional extensio, of intervals.

4 survei!!ance activities to be performed without regard to the applicable OPERATIONAL CONDITIONS (modes) are provided C. This specification establishes the failure to perform a in the individual Surveillance Requirements. Surveillance Requirement within the allowed surveellance interval, defined by the provisions of Specification 4.0.B. as B. Specification 4.0.B establishes the limit for which the a conditim that constitutes a failure to meet the specified time interval for Surveillance Requirements may be OPERAB:LITY requirements for a Lamating Condetion for extended. It permits an allowable extension of the normal Operation. Under the provisions of this specification. ,

surveillance interval to facilitate surveillance scheduling and systems and compermiu are assumed to be OPERABLE  :

consideration of plant operating conditions that may not be when Surveillance Requirements have been satisfactorily i suitable for conducting the surveillance (e.g., transient perfor ned within the specified time interval. However, conditions or other ongoing surveillance or maintenance nothing in this provision is to be construed as implying that activities). It also provides flexibility to accommodate the systems or components are OPERABLE when they are found length of a fuel cycle for surveillances that are performed at or knowr to be moperable although still meetmg the each refueling outage and are specified with a 24 month Surveillance Requirements. This specification siso clarifies surveillance interval It ic not intended that this provision be that the ACTION requirements are applicable when used repeatedly as a convenience to extend survei!!ance Survei!!ance Requirements have not been completed within intervals beyond that specified for surveillances that are not the a!! owed surveillance interval and that the time limits of performed during refueling outages. The limitation of this the ACTION requirements apply from the point in time it is specification is based on engineering judgemet and the identified that a surveillance f.as not been performed and not recognition that the most probable result of ray particular at the time that the allowed s xveillance was exceeded.

surveillance being performed is the verificat;on of Completion of the Surveillance Requirement within the conformance with the Surveillance Requirrments. The limit allowable outage time limits of the ACTION requirements on extension of the normal surveillance interval ensures that restores compliance with the requirements of Specification the reliability confirmed by surveillance activities is not 4.0.C. However, this does not negate the fact that the significantly reduced below that obtained from the specified failure to have performed the surveillance within the allowed surveillance interval. The exceptions to Specification 4.0.8 surveillance interval, defined by the provisions of are those surveillances for which the 25% extension of the Specification 4.0.B. was a violation of the OPERABILITY interval specified does not apply. These exceptions are requirements of a Limiting Condition for Operation that is stated in the individual Technical Specifications. The subject to enforcement action. Further, the failure to requirements of regulations take precedence over the Technical Specifications. Therefore, when a test interval is specified in the regulations, the test interval cannot be extended under the provisions of 4.0.B, and the surveillance requirement will be identified as an exception. An example of an exception when the test interval is not specified in the regulations is the Note in Specification 6.20, " Primary Containment Leakage Rate Testing Program,* which states Amendment No. 83,1SS,198, 227, 231 20f [

JAFNFP 4.0 BASES - Continued C. Continued C. Continued perform a surveillance within the provisions of Specifmation Survehnce Requirements do not have to be performed on 4.0.8 is a violation of a Technical Specification requirement inoperable equipment because the ACTION requirements and is, therefore, a reportable event under the requirements define the remedia! measures that apply. However, the of 10 CFR SO.73(a)(2)(i)(B) because it is a condition Surveillance Requirements hsve to be met to demonstrate prohibited by the plant Techikal Specifications. that inoperable equipment has been restored to OPERABLE status.

If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with ACTION requirements, a 24-hour D. This specification establishes the requireme .c that all allowance is provided to permit a delay in impicmenting the applicable surveillances must be met before entry into an ACTION requirements. This provides an adequate time limit OPERATIONAL CONDITION or other condition of operation to complete Surveillance Requirements that have not been specified in the Applicability statement. The purpose of this performed. The purpose of this allowance is to permit the specification is to ensure that system and component completion of a surveillance before a shutdown is required to OPERASILITY requirements or parameter limits are met i comply with ACTION requirements or before other remedial before entry into an OPERATIONAL CONDITION or other measures would be required that may prec!ude completion of specified condition associated with plant shutdown as well a surveillance. The basis for this allowance includes as startup.

consideration for plant conditions, adequate planning, i availability of personnel, the time required to perform the Under the provisions of this specircation, the applicable surveillance and the safety significance of the delay in Surveillance Requirements must be performed within the completing the required survei!!ance. This provision also specified surveillance interval to ensure that the Limiting provides a time limit for the completion of Surveillance Conditions for Operation are met during initial plant startup or Requirements that become applicable as a consequence of following a plant outage.

OPERATIONAL CONDITION (mode) changes imposed by ACTION requirements and for completing Surveillance When a shutdown is required to comply with ACDON Requirements that are applicable when an exception to the requirements, the provisions of this specificction do not requirements of Specification 4.0.C is allowed. If a apply because this would delay placing the facility in a lower surveillance is not completed within the 24-hour allowance, CONDITION of operation.

the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are ,

applicable at the time the surveillance is terminated.

I Amendment No. 49, Si, SS,109,152,1 S3, 227, 234 3Og l

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JAFNPP l 3.1 LIMITING CONDITIONS FOR OPERATION 4.1 SURVEILLANCE REQUIREMENTS 3.1 REACTLR PROTECTION SYSTEM 4.1 REACTOR PROTECTION SYSTEM Anolicability- Apolicability-Applies to the instrumentation and associated devices which Applies to the surveillance of the instrumentation and associated initiate the reactor scram. devices which initiate reactor scram.

Obiective: Obiective:

To assure the operability of the Reactor Protection System. To specify the type of frequency of surveiRance to be appred to the protection instrumentation.

Specification: Soec:fication:

A. The setpoints and minimum number of instrument A. Instrumentation systems shah be functionally tested and calibrated channels per trip system that must be operable for each as indicated in Tab!es 4.1-1 and 4.1-2 respectively.

ition of the reactor mode switch, shall be as shown in g g  ;

~ ~

Iisted below shall be demonstrated to be within its limit once per 24 months. Neutron detectors are exempt from response time testing. Each test sha!! include at least one channel in each trip system. A!! channels in both trip systems shall be tested within two test intervals.

1. Reactor High Pressure (02-3PT-55A, B, C, D) *

2. Drywell High Pressure (05i'T-12A, B, C, D)

3. Reactor Water Level-Low (L3) (02-3LT-101 A, B, C, D) *

4. Main Steam Line isolation Valve Closa.sre (29PNS-80A2, B2, C2, D2)

(29PNS-86A2, B2, C2, D2)

5. Turbine Stop Valve Closure (94PNS-101,102,103,104)

6. Turbine Control Valve Fast Closure (94PS-2OOA, B, C, D)

7. APRM Fixed High Neutron Flux

8. AP.lM Flow Referenced Neutron Flux

• Sensor is eliminated from response time testing for the RPS actuation logic circuits. Response time testing and conformance to the ttist acceptance criteria for the remaining channel components includes trip unit and relay logic.

Amendment No. 227,233,235 30i l

l JAFNPP ,

i 3.3.C (cont'd) 4.3.C (cont'd) i

2. The average of the scram insertion twnes for the three 2. At 16-week intervals,10 percent of the operable control fastest operable control rods of all groups of four control rod drives sher be scram timed above 950 poig. The rods in a two-by-two array shall be no greater than: same control rod dnves should not be tested each interval. Whenever such scram time measurements are j Control Rod Average Scram made, an evaluation sher be made to provide reasonable ,

Notch Position Insertion T'wne assurance that proper control rod drive performance is t i Observed (Seconds) being maintained. i i

46 0.361 l

38 0.977 24 2.112 04 3.764 i The maximurn scram insertion time for 90 percent 3.

insertion of any operable control rod shall not exceed All control rods shall be determined os.vable by i 3.

7.00 sec. demonstratmg the scram discharge volurce drain and vent valves are: '

Item Freauency t

a. Venfied Open Once per 31 Days i

! b. Cycled Fully Closed in accordance with l and Open the Inservice l Testing Program i  !

c. Verified to close withm Once per 24  ;

30 seconds after receipt Menths of an actual or semulated scram signet and open when j the actual or simulated scram segnal is reset. ,

I t Amendment No. 49,52,75,85,155,203,233  ;

96 i

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JAFNPP 3.4 - LIMITING CONDITIONS FOR OPERATION 4.4 SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIOUID CONTROL SYSTEM 4.4 STANDBY LIQUID CONTROL SYSTEM Apolicability: Apo!icability:

Applies to the operating status of the Standby Liquid Control Applies to the periodic testing requirements for the Standby Liqued l System. Control System.

Obiective

- Obiective: _

To verify the operability of the Standtr; Liquid Control System.

. To assure the availability of a system with the capability to shet Specification:

down the reactor and maintain the shutdown condition without control rods.

A. Normal Operation Specification:

The operability of the Standby Liquid Control System shall be A. Normal Operation verified by performance of the following tests:

Item Freauency During periods when fuel is in the reactor and prior to startup from a cold condition, the Standby Liquid Control System shall

' be operable except as specified in 3.4.B below. This system 1. Verify each valve (manual, Once per 31 Days

- need not be ope <able when the reactor is in the cold condition, power operated, or automatic) all rods are fully inserted and Specification 3.3.A is met. in the system flowpath that is not locked, sealed or other-wise secured in position, is in the correct position.

y 2 Pump minimum flow rate of 50 in accordance with gpm shall be verified against a the Inservice Testing system head of 11,275 psig Program using demineralized water from the test tanit.

Amendment No. 446 105

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JAFNPP 4.4 (cont'd)

Item Frecuency

3. Manually initiate the system, except Once per the explosive valves and pump 24 Months l

solution in the recirculation path

4. Exviode one of three primer Once per assemblies manufactured in same 24 Months batch to verify proper function.

l Then install the two remaining primer assemblies of the same batch in the explosive valves.

5. Demineralized water shall be injected Once per into the reactor vessel to test that 24 Months valves (except explosive valves) not checked by the recirculation test are notc. logged.

l 6. Test that the setting of the system in accordance i pressure relief valves is between 1,400 with the and 1,490 psig. Inservice i Testing Program

7. Disassemble and inspect one explosive In accordance valve so that it can be established with the that the valve is not clogged. Both Inservice valves shall be inspected within Testing B. Operation with inoperable Components two test intervals. Program From and after the date that a redundant component is made B. Ooeration with inoperable Components or found to be inoperable, Specification 3.4.A shall be considered fulfilled, and continued operation permitted, When a component becomes inoperable its redundant provided that: component shall be verified to be operable immediately and daily thereafter.

1. The component is returned to an operable condition within 7 days.

l Amendment No. 28, ? ?i, ' 48, 222 106

JAFNPP s

ATWS requirements are satisfied at all concentrations above Because components of the system are checked periodically as 10 weight percent for a minimum enrichment of 34.7 atom described above, a functional test of the entire system on a percent of B-10. frequency of more than once every 24 months is unnecessary.

A test of explosive charges from one manufacturing batch is Figure 3.4-1 shows the permissible region of operation on a made to assure that the charges are satisfactory. A , ,

" " "" "* check of the firing circuit contmuity is provided by sodium pentaborate solution volume versus concentration -

pilot lights in the control room.

graph. This curve was developed for 34.7% enriched B-10 and a pumping rate of 50 gpm. Each point on this curve The relief valves in the Standby Liquid Control System protect provides a minimum of 660 ppm of equivalent natural boron in the system piping and positive displacement pumps, which are the reactor vessel upon injection of SLC solution. At a solution nominally designed for 1,500 psig, from overpressure. The volume of 2200 gallons, a weight concentration of 13% pressure relief valves discharge back to the standby liquid sodium pentaborate, enriched to 34.7% boron-10 is naeded to control pump suction line.

meet shutdown requirements. The maximum storage volume B. Operation with Inoperab!e Components of the solution is 4780 gallons which is the net overflow volume in the SLC tank. Only one of two standby liquid control pumping circuits is needed for operation. If one circuit is inoperable, there is no Boron concentration, isotopic enrichment of boron-10, solution immediate threat to shutdown capability, and reactor operation temperature, and volume are checked on a frequency adequate may continue during repairs. Assurance that the remaining to assure a high reliability of operation of the system should it system will perform its function is obtained by verifying pump ever be required. Experience with pump operability indicates operability in the operable circuit at least daily.

that periodic testing in accordance with the IST Program is adequate to detect if degradation has occurred. Valves in the C. Sodium Pentaborate Solution system flowpath are ve.ified to be in the proper position on a To guard against precipitation, the solution, including that in monthly basis. This requirement does not apply to explosive the pump suction piping, is kept at least 10'F abova saturation valves or to valves that cannot be inadvertently misaligned, temperature. Figure 3.4-2 shows the saturation temperature such as check valves. Verifying the correct alignment of including 10'F margin as a function of sodium pentaborate manual, power operated, or automatic valves in the system solution concentration. Tank heater and heat tracing system flowpath provides assurance that the proper flowpath will exist are provided to assure compliance with this requirement. The for system operation. The month frequency is based on set points for the automatic actuation of the tank heater and engineering judgement and is supported by procedural controls heat tracing system are established based on the solution goveming valve operation that ensure correct valve positions. concentration. Temperature and liquid level alarms for the system annunciate in the control room. Pump operability is checked on a frequency to assure a high reliability of operation The only practical time to test the Standby liquid Contro of the system should it ever be required.

System is during a refueling outage and by initiation from local stations.

Amendment No. 2S, ' ? S S, 222 109

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JAROPP 3.5 (cont'd) 4.5 (corit'd)

b. Flow Rate Test - in accordance with the Core spray pumps inservice Testmg shell deliver at Program leest 4,265 gym against a system heed corresponding to a reactor vessel pressure greater then or equel to *13 poi above primary containment preneure.

c. Verify that each volve Once per 31 Days (manuel, power operated or automatic) in the -

flow poth that is not locked, seeied or otherwise secured in posrtion, is in the correct position.

d. Motor operated valves. In accardence with the

Inservice Testeg

Program I

e. Core Spray Header Ap instrumentation

Check Once/ day Calibrate Once/3 months

! Test Once/3 months

f. Logic System Refer to Table 4.2-2 Functional Test l g. Testable Check in accordance with the 1 Valves inservice Testeg Program Amendment No. 'O, n, 2^', 222 113 4

JAFNPP 3.5 (cont'd) 4.5 (cont'd)

5. AN recirculaten pump discherpe volves shell be operable 5. AN reewculation pJmp discherge vehes shen be tested for prior to reactor startup (or closed if permetted elsewhere operability any time the reactor is in the cold condition ,

in these specW. exceeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if operability tests have not been performed dunng the preceding 31 days.

6. If the requirements of 3.5.A cannot be met, the reactor shell be pieced in the cohi condition within 24 hrs. B. Contanment Coolina Mode (of the RHR Systerrd C. Containment Cochna Mode (of the RM System) 1. Subsystems of the containment cooling modo shen be demonstrated operable by performing:

1. Both subsystems of the containment cooling mode, each including two RHR and two RHRSW pumps, shen be ]Ian Freauency operable whenever there is irradiated fuel in the reactor vessel, prior to startup from a cold condition, and reactor a. a pump operability and Per Surveillence coolarc temperature se212'F except as specified bebw. flow rate test on the RHR Requirement 4.5.A.3 pumps.

b. an operability test of the in accordance with RHR containment cooling the Inserwce Testing mode motor operated Program vehms.

c. an operability test on the in accordance with RHRSW pumps and the Inservice Tesang W motor Program operated valves.

d. a flow rate test verifying in accordence with a flow rate of 4000 gym the insendce Tesang for each RHRSW pump Prograrn and a total flow rate of 8000 gpm for two RHRSW pumps cperating in perallet.

I Amendment No. 26,95,101,134,*i",151 115e

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JAFNPP 3.5 (Cont'd) 4.5 (Cont'd)

I E. Reactor Core isolation Coolina (RCICI System E. Reactor Core Isolation Coolino (RCIC) System

1. The RCIC System shall be operable whenever there 1. RCIC System testing shall be performed as follows is irradiated fuel in the reactor vessel and the reactor provided a reactor steam supply is available. If pressure is greater than 150 psig and reactor coolant steam is not available at the time the survei!!ance temperature is greater than 212*F except from the Mst is scheduled to be performed, the test shall be time that the RCIC System is made or found to be performed within ten days of continuous operation inoperable for any reason, continued reactor power from the time steam becomes available.

operation is permissible during the succeeding 7 days unless the system is made operable earlier provided Jigm Freauency that during these 7 days the HPCI System is operable. a. Simulated Automatic Once per 24 Months Actuation (and Restart *)

2. If the requirements of 3.5.E cannot be met, the Test reactor shall be placed in the cold condition and pressore less than 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. b. Verify that each valve Once per 31 Days (manual, power operated

3. Low power physics testing and reactor operator or automatic) in the training shall be permitted with inoperable system flowpath that components a'; specified in 3.5.E.2 above, prov;ded is not locked, sealed that reactor coolant temperature is s212 F. or otherwise secured in position, is in the

4. The RCIC system is not required to be operable correct position.

during hydrostatic pressure and leakage testing with reactor coolant temperatures between 212*F and c. Motor Operated Once per 92 Days 3OO'F and irradiated fuel in the reactor vessel Valve Operability provided all control rods are inserted.

• Automatic restart on a low water level signal which is subsequent to a high water level trip.

Amendment No. 'O, ? O7, ? ?O, '79, 233 121 l

L

T JARIPP 3.5 (cont'd) 4.5 (corit'd) - j t

' Item Frequency

d. Flow Rate Test- Once per 92 Days  ;

The RCIC pump shall }

deliver at least 400 i gpm against a system  !

head corresponding to i a reactor vessel  !

pressure of.1195 psig j to 150 psig.  ;

e. Testable Check Tested for operability [

Valves any time the reactor is l in the cold condition l exceeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if l operabelity tests have not been performed  !

during the precedeng 92 days. l [

l

f. Logic System ' Once per 24 Months l Functional Test  !

i

2. When it is determined that the RCIC System is inoperable [

at a time when it is required to be operable, the HPCI f Systun shall be verified to be operable immediately and i daily thereafter.

f i

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i Amendment No. SO, 'iS, 239 121a i

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< JAFNPP ~l l

3.5 (cont'd) 4.5 (cont'd) l G. Ms;ntenance of Filled Discharae Pioe G. Maintenance of Filled DischarrJe Pipe The following surveitlance requirement; shall be adhered to, in i Whenever core spray subsystems, LPC! subsystems, HPCI, or RCIC are required to be operable, the discharge piping from order to assure that the discharge piping of the core spray the pump discharge of these systems to the last block valve subsystem, LPCI subsystem, HPCI, and RCIC are filled:

shall be filled.

1. Every month prior to the testing of the LPCI subsystem From and after the time that the pump discharge piping of the and core spray subsystem, the discharge piping of these l1. HPCI, RCIC, LPCI, or Core Spray Systems cannot be systems shall be vented from the high point, and water maintained it. a fi!!ed flow observed.

Amendment No. 448, 122a

l l

JAFNPP 3.5 (cont'd) 4.5 (cont'd) condition, that pump shall be considered inoperable for 2. Fo!!owing any period where the LPCI subsystems or core purposes of satisfying Specifications 3.5.A,3.5.C, and 3.5.E. spray subsystems have not been maintained in a filled condition; the discharge piping of the affected subsystem sha!I be vented from the high point of the system and.

water flow observed.

3. Whenever the HPCI or RCIC System is Uned up to take suction from the condensate storage tank, the discharge piping of the HPCI or RCIC shall be vented from the high wint of the system, and water flow observed on a n.nnthly basis.

4. The level switches located on the Core Spray and RHR System discharge piping high points which monitor these 1 lines to ensure they are full shall be functionally tested l each month.

H. Averace Planar Linear Heat Generation Rate (APLHGR) H. Averace Planar Linear Heat Generation Rate (APLHGR)

During power operation, the APLHGR for each type of fuel as e The APLHGR for each type of fuel as a function of average function of axiallocation and average planar exposure shall be planar exposure shall be determined daily during reactor within limits based on applicable APLHGR limit values which operation at 225% rated thermal power.

have been approved for the respective fuel and lattice types.

These values are specified in the Core Operating Limits Report.

If at anytime during reactor power operation greater than 25%

of rated power it is determined that the limiting value for APLHGR is being exceeded, action shall then be initiated within 15 minutes to restore operation to within the prescribed limits. If the APLHGR is not retumed to within the prescribed l limits within two (2) hours, the reactor power shall be reduced to less than 25% of rated power within the next four hours, or until the APLHGR is returned to within the prescribed limits.

Amendment No. 48, Ed, '4,SS,99,109,7,132,134,162,190,192, 123

I JAFNPP 4.5 BASES The testing interval for the Core and Containment Cooling With components or subsystems out-of-service, overall core and Systems is based on a quantitative reliability analysis, industry contamment cooieng reliability is maintained by verifying the practice, judgement, and practicality. The Emergency Core Operability of the remaining cooling equipment. Consistent with Cooling Systems have not been designed to be fully testable the definition of operable in Section 4.0.C. demonstrate means during operation. For example, the core spray final adtrission conduct a test to show: verify means that the associated valves do not open until reactor pressure has fallen to 450 psig; surd. ca actnnues have been satisfactorily performed withm the thus, during operation even if high drywell pressure were specified time interval.

simulated, the final valves would not open. In the case of the HPCI, automatic initiation during power operation would result in The RCIC flow rate is described in the UFSAR. The flow rates to pumping cold water into the reactor vessel which is not be delivered to the reactor core for HPCI, the LPCI mode of RHR, desirable. and CS are based on the SAFER /GESTR LOCA analysis. The flow rates for the LPCI mode of RHR and CS are modified by a 10 )

The systems will be automatically actuated once per 24 months. percent reduction from the SAFER /GESTR LOCA analysis. The in the case of the Core Spray System, condensate storage tank reductions are based on a sensitivity analysis (General Omcd water will be pumped to the vessel to verify the operability of MDE-93-0786) performed for the parameters used in the the core spray header. On a monthly basis, correct alignment SAFER!GESTR analysis.

shall be verified for manual, power operated, or automatic valves I in ECCS and RCIC system flow paths to provide assurance that The CS surveillance requirement includes an a!!owance for system proper flow paths will exist for system operation. For the HPCI leakage in addition to the flow rate required to be delivered to the and RCIC Systems, this requirement also includes the steam reactor core. The leak rate from the core spray piping inside the flowpath for the turbines and the flow controller position. This reactor but outside the core shroud is assumed in the UFSAR and surveillance requirement does not apply to va!ves that cannot be includes a known loss of less than 20 gpm from the 1/4 inch inadvertently misaligned such as check valves, or to valves that diameter vent hole W t'ie core spray T-box connection in each of are locked, sealed, or otherwise secured in position. A valve the loops, and in the mp, a potential additional loss of less than that receives an initiation signal is allowed to be in a non- 40 gpm from a clamshell repair whose structural weld covers only accident position provided the valve willautomatically reposition 5/6 of the circumference of the pipe. Both of these identified in the proper stroke time upon receipt of the initiation signal. sources of leakage occur in the space between the reactor vessel The monthly frequency of this requirement is based upon wall and the core shroud. Therefore flow lost through these leak engineering judgement and is supported by procedural controls sources does not contribute to core cooling.

governing valve operation that ensure correct valve positions.

This frequency is further supported by the Ir. service Testing Program, which demonstrates system pump and power operated valve operability. Thiscombination of automatic actuation tests, periodic pump and valve testing, and monthly flow path verification is adequate to demonstrate operability of these systems.

Amendment No. , 'iS, 204,233 132

1 JAFNPP l

i '

4.5 BASES (cont'd) 4 i

The surveslience requwements to ensure that the discharge pipsng of the core sprey, LPCI mode of the RHR, HPCI, and RCIC Systems are filled provideo for a visual oboorvation that water

{ flows from a high point vent. This ensures that the line is in a '

l full condition. Instrumentation has boon provided in the Core l Spray System and LPCI System to monitor the presence of water in the discharge piping. This . instrumentation is ft.nctionally tested monthly to ensure that dunne the interval i

j between the monthly checks the status of the discharge piping

is monitored on a continuous basis.

Normally the low pressure ECCS subsystems required by '

Specification 3.5.F.1 are demonstrated operable tiy the surveillence testsin Specifications 4.5.A.1 and 4.5.A.3. Section

]' 4.5.F specifies periodic survesNonce tests for the low pressure ,

ECCS subsystems which are applicable when the roector is in l' 3

the cold condition. These tests in conjunctioit with the requirements on filled discharge piping (?-;+:;'-::f -s 3.5.G),

i and the requirements on ECCS actuation instrumentation

! (Specification 3.2.B), assure adequet's ECCS capability in the cold condition. The water level in the suppression pool, or the L Condensate Storage Tanks (CST) when the suppression pool is inoperable, is checked once each shift to ensure that sufficient water is available for core cooling.  ;

i i

i. -

I Amend:nent No.

• 1,1 SS  :

133 I

JAFNPP 3.7 (cont'd) 4.7 (cont'd) -

4. Pressure Suppression Gnamber Reactor Building Vacuum 4. Pressure Suppression Chamrer-Reactor Building Breakers Vacuum Breakers

a. Except as specified in 3.7.A.4.b below, two a. The pressure suppression chamber-reactor building Pressure Suppression Chamber Reactor Building vacuum breakers shall be checked for proper Vacuum Breakers shall be operable at all times operation in accordance with the Inservice Testing when the primary containment integrity is required. Program. ,

The setpoint of the differential pressure instrumentation which actuates the pressure. b. Instrumentation associated with pressure suppression chamber reactor building vacuum suppression chamber-reactor building vacuum breakers shall be s0.5 psi below reactor building breakers shall be functionally tested once per 92 pressure. days.

b. From and after the date that one of the pressure suppression chamber reactor building vacuum breakers is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding 7 days, unless such vacuum Amendment No.130, ? ?i,139 177

JAFNPP 3.7 (cont'd) 4.7 (cont'd) breaker is sooner made operable, provided that the repair procedure does not violate primary containment integrity, i

5. Pressure Suppression Chamber - Drywe!I Vacuum 5. Pressure Suppression Chamber - Drywell Vacutan l Breakers Breakers j

a. When primary containment integrity is required, all a. Each drywell suppression chamber vacuum breaker drywell suppression chamber vacuum breakers shall shall be exercised through an opening - closing cycle be operable and positioned in the fully closed monthly.

position except during testing and as specified in 3.7.A.S.b below.

b. One drywell suppression chamber vacuum breaker b. When it is determined that one vacuum breaker is may be non-fully closed so long as it is determined inoperable for fully closing when r 7 ability is to be not more than 1' open as indh ated by the required, the operable breakers "- e exercised position lights. immediately, and every 15 c ,4 the er until the inoperable valve has been returned to noi. -I service.

c. One drywell suppression chamber vacuum breaker c. Each vacuum breaker valve shall be visually l may be determined to be inoperab!e for opening. inspected to insure proper maintenance and operation in accordance with the Inservice Testing Program.

d. Deleted

d. A leak test of the drywell to suppression chamber structure shall be conducted once per 24 months; the acceptable leak rate is sO.25 in. water / min, over a 10 min period, with the dryweII at 1 psid.

Amendment No. 134,192.232 178

JAFNPP

. 3.7 (cont'd) ' - 4.7 (cont'd)

2. Secondary containment capability to maintain a 1/4 in.

c' water vacuum' under calm wind conditions with a titer train flow rate of not more than 6,000 cfm, shall be demonstrated at each refueling outage prior to refueling.

D. Primary Containment Isolation Velves D.  ; Primary Containment isolation Valves

-1. Whenever primary containment integrity is required per 1. The primary contamment isolation valves surveillance shall 3.7.A.2, containment isolation valves and all instrument . be performed as follows:

line excess flow check valves shall be operable, except as specified in 3.7.D.2. The containment vent and purge item Freauency valves shall be limited to opening angles less than or equal to that specified below: a. The operable isolation in accordance with valves that are power the Insennce I- Valve Number &ximum Openina Anale operated and Testing Program 27AOV-111 40' automatically initiated

. 27AOV-112 40' shall be tested for 27AOV-113 40' simulated automatic

! 27AOV-114 50' initiation and for i 27AOV-115 50* closure time.

27AOV-116 50'

, 27AOV-117 50' b. Instrument line excess in accordance with

! 27AOV-118 50'- flow check valves shall the Insennce be tested for proper Testing Program l operation.

c. All normally open power- In accordance with operated isolation valves the Insennce (except for the main Testing Program j; steam isolation valves)

! shall be fully closed and reopened.

l' 3

Amendment No. 154,'73,1L*,232,233 185

JAFNPP I

3.7 (cont'd) 4.7 (cont'd) h Frecuency

d. With the reactor at a in accordonce with reduced power level, the inservice Testing fast close each main Program steam isoletion vehe, one at a time, and venfy closure time.

e. Mein steem isoletion Twice por Week valves shes be exercised

. by partisi closure and subsequent reopening.

2. With one or more of the containment isolation valves 2. Whenever a containment isolation valve is inoperable, the inoperable, maintain at least one isolation valve operable position of at loost one other valve in each line hewing an in each affected penetration that is open and: inoperable valve shell be recorded daily.

a. Restore the inoperable valve (s) to operable status within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s: or

b. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the closed position. Isolation valves closed to satisfy these requirements may be reopened on an intermettent basis under administrative control or

c. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or a blind flange.

3. If Specifications 3.7.D.1 or 3.7.D.2 cannot be met the reactor shall be in the cold condition within 24 hrs.

Amendment No. 13',15','?3,192.203 186

1 JAFNPP 5

4.7 BASES (cont'd)

,, The main steem line isolation valves are functioneNy tested on a more frequent interval to establish a high degree of reliability.

The pnmary contamment is penetrated by several smeN diameter w' .strument lines connected to the reactor cooient

, system. Each instrument line contams a 0.25 in. restricting 4' orifice inside the primary containment and an excess flow check valve outside the pnmory containment.

l.

A list of contaenment isolation valves, including a brief description of each valve is included in Section 7.3 of the updc::d FSAR.

a i

4 4

1 i

t 4

1 i

i 1

'l Amendment No. 15','73,203,232

+

197 i

- - - , , , -,c .-. . . , - -- , . - _ - _ _ _ - - - - --__--_ - _ .-

JAFNPP 4.11 (Cont'd) 3.11 (cont'd)

D. Emeroency Service Water System D. Eme.m Service Water System

1. Surveslience of the ESW system shell be performed as

1. To ensure adequate equipment and area cooieng,' both ESW follows:

. systems shall be operable when the requirements of specification 3.5.A and 3.5.8 must be satisfied, except as item Freauency specified below in specification 3.11.D.2.

a. Simulated Automatic Once every 24 months Actuation Test

b. Flow Rate Test - Each in Acco.4( .ce with ESW pump shell deliver the inservice at least 1500 gpm to its Testeg Program respective loop. The loop. The pump total developed head shall be greater than or equal to the corresponding point on the pump curve, reduced by a maximum of 7%, for the measured flow.

c. Verify that each valve Once per 31 Days (manuel, power operated, or automatic) in the system flowpath that is not locked, sealed or otherwise secured in position, is in the correct position.

d. Motor Operated in Accordance with Valves the inservice Testing Program Amendment fio. 7',134,223,230 240

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