ML20197K142

Amend 241 to License DPR-59,proposing to Change Ja Fitzpatrick TSs to Incorporate Inservice Testing Requirments of Section XI of ASME Code

ML20197K142
Person / Time
Site:	FitzPatrick
Issue date:	12/02/1997
From:	Bajwa S NRC (Affiliation Not Assigned)
To:
Shared Package
ML20197K146	List: ML20197K142 ML20197K150
References
NUDOCS 9801050231
Download: ML20197K142 (26)

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4 UNITED STATES i

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NUCLEAR REGULATORY COMMISSION 2

WASHINoTON. D.C. 2055fM001

%...../

POWER AUTHORITY OF THE STATE Oc NEW YORK DOCKET NO. 50-333 JAMES A FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING llCENSE Amendment No.

241 License No. DPR-59 1.

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

A.

The application for amendment by Power Authority of the State of New York (the licensee) dated December 14, 1995, as supplemented September 26, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission'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.

The"a is reasonable assurance (i) that the activities authorized 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 connon 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 Connission's regulations and all applicable requirements have been satisfied.

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-59 is hereby amended to read as follows:

9001050231 971202 PDR ADOCK 050J0333 P

PDR

, (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.241, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of'its issuance to be implemented within 90 days.

FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Director Project Directorate I-l Division of Reactor Projects - I/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: December 2, 1^97

ATTACHMENT TO LICENSE AMENDMENT NO. 241 FACIllTY OPERATING LICENSE N0. DPR-59 DOCKET NO. 50-333 Revise Appendix A as follows:

Remove Paaes itLtert Paaes i

i 30a 30a 30b 30b 30c 30c 30d 30d 30e 30e 30f 30f 30g 30s 30h 30h 301 301 96 96 105 105 106 106 109 109 113 113 115a 115a 116 116 121 121 121a 121a 122 122 122a 122a 123 123 240 240

JAFNPP TECHNICAL SPECIFICATIONS l

TABLE OF CONTENTS enn 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 HEQUIREMENTS 3.0 General 4.0 30 3.1 Reactor Protection System 4.1 30i l

3.2 Instrumentation 4.2 49 A.

Primary Centsinment isolation Functions A.

49 B.

Core and Containment Cooling Systems -

B.

50 Initiation and Control C.

Control Rod Block Actuation C,

50 D.

Radiation MonitorMg Systems - Isolatien 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 I.

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.

Opersoon With inoperable Components B.

106 C.

Sodum Pentaborne Solution C.

107 3.5 Core and Containment Cooing Systems 4.5 112 A.

Core Spray and LPCI Systems A.

112 B.

Containment Cooling Mode of the RHR B.

115 System C.

HPCI System C.

117 D.

Automatic Depressurization System (ADS)

D.

119 E.

Reactor Core Isolation Cooling (RCIC) c.

121 System Amendment No. " ' '^ ' ' "' ' ^^ '" " " " 241 i

JAFNPP 3.0 Continued 4.0 Continued D.

Entry into an OPERATIONAL CONDITION (mode) or other that a Surveillance Requirement inas 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 for 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 'ime 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 do not have to be CONDITION (model or specified condition may be made in performed on inoperable equipment.

accordance with ACTION requirements when conformance to them permits cor:tinued 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 Surveillanco Requirement (s) associated 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 M. des as required to comply with ACTION E.

When a system, subsystem, train, camponent or device is Requirements.

determined to be inoperable sole 8y because its emergency power source is iaoperable, or solely because its normal power E.

Surveillance Requirements for inservice testing of components 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 and 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 50.5baff)(6)(i). The inservice testing SHUTDOWN within the 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 epproved 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 l

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.

Amendment No. 83r484,198, 227, 241 30a

1

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4.0 Continued 2.

Surveillance intervais specified in Section XI of the ASME Boiler and Pressure Vessel Code and apphcatdo Addende for the inservice testing activities required by the Code and opplicable Addenda shell be opphcable es defined in Tectwwcal Specification 1.0.T.

3.

The provisions of Specification 4.0.8 are applicable to the frequencies specified in Technical Specification 1.0.T for performing inservice testing activities.

4.

Performance of the above inservice testing activities shall be in addition to other specified Surveillance Requirements.

5.

Nothing in the ASME Boiler and Pressure Vessel Code shell be construed to supersede the regJirements of any Technical Specification.

Amendment No. 241 30b

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JAFNPP

3.0 -BASES A.

This specification states the appiscatnkty of each sps ification D.

Continued in terms of defined OPERATIONAL CONDITION (mode) and is provided to dehnoste specNiceNy when each specification is applicable.

the status of the plant before or after en OPERATIONAL -

i CONDITION (modo) change. Therefore in this case, entry into B.

This specification defines thoes conditions necess6ty to en OPERATIONAL CONDITION (mode) or other specified -

i constitute cw.itw. witis the terms of an individual Limiting condition may be made in accordance with the prowseons of l

Condeteen for Operation and areociated ACTION requerement.

the ACTION requirements. The proviseens of this specsfecation l-should not, howowr, be interprated as endorsing the fadure to C.

This specsfication delineates the ACTION to be taken for axercise good practice in restoring systems or components to circtenstances not directly provided for in the ACTION OPERABLE status before startup.

statements and whoes occurrence would veolate the intent of the spacehcotson. Under the terms of Specification 3.0, the Exceptions to this provision may be made for a limited number i

L facility is to be plocod i6 COLD SHUTDOWN wvthin the of specifications when s+ertup with inoperable equipment would not affect plant safety. These exceptions are stated in followmg 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.

the required OPERATIONAL CONDITION (model wethin the L

i required times by proopptly initiating and carrying out the E.

appropriate ACTION atatement.

This specification dehnostes what addetu,not conditions must be satisfied to permit operation to continue, consistent with D.

This specification provedes that entry into are OPERABLE the ACTION statements for power sources, when a normel or

~

i CONDITION imode) must be made with (a) the full emergency power source is not OPERABLE. it specifically cst 7: ;,wa of regasred systems, equipment or components prohibets operation when one devision is inoperatia b-its :

i OPERABLE and (b) all other parameters as specified in the normal or emergency power source is inoperable'end a Limiting Cc idetions for Operation being met without regard for system, subsystem, train, component or device in another i

allowable devistoons and out of service provisions contained in division is inoperable for another reason.

i i

the ACTION statements.

j The provisions of this specificateen permit the ACTION The intent of this provision is to insure that facility operation is statements assocested with indevidual systems, subsystems,-

l not initiated with either required equipment or systems trains, components or devices to be consestent with the inoperable or other hmets boeng exceeded. Cswir.ce with

' ACTION statement of the associated electrical power source.

ACTION rtwirements that perrmt contmuod operation of the it allows operation to be governed by the time I

facility for an unismited period of time provides en acceptable level of safety for continued operation without the regard to Amendment No. Sar.?St, Mi, 241 30c ll t

l 3.0. BASES - Continued E.

Continued E.

Continued i

limits of the ACTION atatement associated with the Limiting As a further example, Specifiestion 3.9.A. requires in port that l

Corstion for Operation for the normal or emergency power source, and not by the indvidual ACTION statements for each two 115KV lines and recorve station transformers be avedelde.

system, subsystem, train, component or oevice that is The ACTION statement provides a 7 day out-of-service time.

1 determened to be inoperable solely because of the inoperability when both requwed offsite ciecuits are not OPERABLE. If the of its normal or emergency power source.

definition of OPERA 8LE were apphed without considers'. son of Specification 3.0.E., all systems, subsystems, trains,-

- For example, Specification 3.9.A. requires in part that both components aM devices supphed by the inoperstdo normal emergency diesel generator systems be OPERABLE. The power sources, both of the offsite circuits, would aise be l

ACTION statement provides for a 7 day out-of-service time inoperable. This would dictate invoking the appbcatdo ACTION j

when emergency diesel generator system A or B is not statements for each of the opphesbie LCOs. However, the i

OPERABLE. If the definition of OPERABLE were apphed provisions of Specification 3.0.E. permet tN time limits for.

t without considwation of Opocification 3.0.E., all systems.

continued operation to be consisten* with the ACTION subsystems, trasns, components and devices suppbed by the statement for the inoperable normal power sources insteed, inoperable emergency power source, diese: generator system provided the other specified conditions are satisfied. In this A or B, would also be inoperable. This would dictate invoking case, this would mean that for one division the emergency.

the applicable ACTION statements for each of the applicable power source must be OPERABLE tes must be the components -

Limiting Conditions for Operation. However, the provisoons of

• • 5-Cj trf the emergency power sourcel and all redundant Specification 3.0.E. permet the time limits for continued systems, subsystems, trains, components and devices in the i

operanon to be consistent with the ACTION statement for the other division must be OPERABLE,'or likewise satisfy j

j inoperable emergency diesel generator system instead, Specification 3.0.E. li.e., he capable of performing their desegn provided the other specified conditions are satisfied. If they forw* ions and have an smorgency power source OPERABLE).

l are not satisfied, shutdown is required in accordance with this in other words, both emergency pova sources A and 8 must I

I specification.

be OPERABLE ard all redu.Jant systems, subsystems, trains, i

components and devices in both divisions must also be :

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

i in Cold Shutdown and Refuel Modes, Specification 3.0.E. is not applicatts, and thus the indevidual ACTION statement for each apphcable Limiting Condition for Opration in these j

OPERATIONAL CONDITIONS (modt mut be adhered to.

Amendrnent No. S3,10", 241 3Od a

JAFNP'

' 3.0 Beans - Coewinued

. F. :

LCO 3.0.F estabbshes the allowance for restonng equipment to' service under admenestrative controls when it j

has been removed from service or declared inoperable to i

comply with requered actions. The sole purpose of this Specification is to provide en excepoon to LCO 3.0.B to allow testing to demonstrate: tal the operability of the equipment being retumed to service: or (b) the operability of i

other equipment.

j l

The administrative controls ensure the time the equipment l

is retumed to service in confhet with the requerements of the required octione is hmited to the time absolutely necessary to perform the aNowed testing. This i

i Specification does not provide time to perform any other I

preventive or corrective memtenance.

1 L

An example of demonstrating the operability of the equipment being retumed to service is~ reopening a

[

_ containment isolation valve that has been closed to comply with the required actione and must be reopened to perform _

the testing.

t An example of demonstrating the operability of other

}

equipment is taking an inoperable channel or trip system out i

of the tripped condition to prevent the trip function from occurring dunne the performerra of testing on another channelin the other trip system. A similar example of i

demonstratirig the operability _ of other equipment is taking l

en inoperable channel or trip system out of the tripped condition to permit the logic to function and indscate the

~

i appropriate response during'the performance of testing on another channel in the some trip system.

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1 i

i 1

Amendme,. uo. -e. :ee. ne. =, m 3oe

- l l

v

.~

5

'JAFNPP 4.0 BASES A.

This specification provides that surveellence 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 Primary Contamment met and will be performed during the OPERATIONAL

' Leekage Rate Testing Program." Thi exception is proveded L

. CONDITIONS imodes) for which the Lim Conditions for because the program already inciudes prowessons for ~

'(

Operation are applicable. Provisions for

~ ional extension of intervals t

surveillance activities to be performed without regard to the applicable OPERATIONAL CONDITIONS (modes) are provided

-C.

in the individual Survesence Requirements.

This specification establishes the feelure to perform e Surveellance Requirement within the allowed surveillence

~B.

Specification 4.0.B establishes the limit for which the-interval, defined by the provisions of Specification 4.0.8, as a condition that constitutes a failure to meet the

'specified time interval for Surveillance Requerements may be

.OPERABluTY requirements for a Limiting Condetion for extended. It permits an allowable extension of the normal Operation.. Under the prowissons of this specification, -

surveillance interval to facilitate surveellence scheduleng and consideration of plant operating condetions that may not be systems and components are nssumed to be OPERABLE suitable for conducting the surveillance (e.g., transient when Surveillance Requirements have been satisfactorily-conditions or other ongoing surveillance or maintenanco perfe med within the specified time interval. However, ;

i activities), it also provedes flexibility to accommodate the nothmg in this provision is to be construed as implying that -

i length of a fuel cycle for surveillances that are performed at systems or components are OPERABLE when they are found or known to be snoperable although still moete' g the each refueling outage a.1d are specified with a 24 month surveillance interval it is not intended thct this provision be Surveillance Requirements. This specification also clarifies used repeatedly as a convenience to extend surveillance thrit the ACTION requerements are applicable when Surve.T...nce Requirements have not beert comple:sd wsthin intervals beyond ti.dt specified for surveillances that are not the allowed surveillance interval and that the time limits of '

1 performed during refueling outages. The limitation of this specification is based on engineering judgement and the -

the ACTION requirements apply from the poent in time it is recognition that the most probable result of my particular identified that a surveillance has not been performed and not i

I surveillance being performed is the verification of at the time that the allowed surveillance was exceeded.

Completion of the Survemance Requirement within the conformance with the Surveillcnce Requirements. The limit allowable outage time limits of the ACTION r

' ements on extension of the normal surveillance interval ensures that u.c reliability confirmed by survei::ance activities is not restores compliance with the requerem~nts of focation significantly reduced below that obtained from the specified 4.0.C. However, this does not negate the fact that the surveillance interval. The exceptions to Specification 4.0.8 failure to have performed the surveellence within the allowed 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 OPERABlWTY -

interval specified does not apply. These exceptions are requirements of a Limiting Condition for Operation that is i

stated in the individual Technical Specifications. The requirements of regulations take precedenw over the subject to enforcement action. Further, the failure to 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 i

Containment Leakage Rate Testing Program," which states Amendment No. 83, 188, 188, 227, 234, 241 g

.f 30f

JAFNPP O.O BASES - Continued C.

Continued C.

Continued perform a surveillance within the provisions of Specification Surveillance 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, thnrefore, a reportable event under the requirements define the remedial measures that apply. However, the of 10 CFR 50.75(a)(2)(i)(B) because it is a condition Surveillance Requirements have to be met to demonstrate prohibited by the plant Technical Specifications.

that ir, operable 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 requirement that all allowance is provided to permit a delay in implementing the applicable surveillances must be met before entry into an ACTION requirements. This provides an adequate tirne 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 OPERABILITY requirements or parameter limits are met comply with ACTION requirements or before other remedial before entry into an OPERATIONAL CONDITION or other measures would be required thet may preclude completion c!

specified condition associated with plant shutdown as well l

a surveillance. The basis for this allowance includes as startup.

consideration for plant conditioas, adequate planning, availability of personnel, the time required to perform the Under the provisions of this specification, the applicable surveillance and the safety significance of the delay in Surveillance Requ&sments must be performed within the i

l completing the requked surveillance. This provision also specified surveillance interval to ensure that the Limiting l

provides a time lirait for the completion of Surveillance Conditions for Operation are met during initisi plant startup or Requirements that become applicable as a consequence of following a plant outage.

i OPERATIONAL CONDITION (mode) changes imposed by i

ACTION requirements and for completing Surveillance When a shutdown is required to comply with ACTION Requirements that are applicable when an exception to the requirements, the provisions of this specification 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 *he 24-hour allowaace, 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 1

Amendment No. 49, Si, SS,109,162,183, 227, 234, 241 30g l

l

~

yy

-1 4.0 BASES - Contmuod E.

This specdicaten ensures that inservice testing of pumps appbcatmiity condition takes precedence over the ASME ONEar and and volves will be performed in accordence with a periodiceNy updated version of the FitzPatrick pient Pressure Vessel Code provision which allows pumps to bm And up "eneervice Teenne Program

• to comply with Seuden XI of to 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after return to normel cperobon. As another saample, the ASME Boiler and Pressure Vessel Code and Addende the Technical Specificatson definition of OPERA 8LE does not pont a es required by 10 CFR 50.55e. The plant program grece period before a device that is not capetde of performing its identifies cisearfications required by 10CFR50.55a and specified function is declared inoperable and takes precedence over Reguietary Guide 1.26. Roguest for relief from any o; the ASME Bosier and Pressure Vessel provision which aSows a vehe those requirements is provided in wnting to the NRC ard to be incapable of performme its specified function for up to 24 is not a port of these Technical Specifications.

hours before being dociered inoperable.

i This specification includes a reference to Technical Specification Section 1.0.T which defines the frequencies fw performing the inservice testmg activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addende. This reference is provided to ensure consistency in survossence intervals throughout these Techrical Specificatioris and to remove any ambigusties relative to the frequencies for performing the required inservice testmg actrvaties.

i Under the terms of this specification, the mom restrictive requirements of the Technical Specifications take i

precedence over the ASME Boder and Pressure Vessel Code and appbcable Addenda. For example, the requirements of Specification 4.0.D to perform surveillance activities prior to entry into an OPERATIONAL CONDITION or other specified J

i Amendment No. 241 L

3Oh

JAFNPP 3.1 LIMITING CONDITIONS FOR OPERATION 4.1 SURVEILLANCE REQUIREMENTS 3.1 REACTOR PROTECTION SYSTEM 4.1 REACTOR PROTECTION SYSTEM Acolicability:

Acolicability:

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 operabi!ity of the Reactor Protection System.

To specify the type of frequency of surveillance to be applied to the protection instrumentation.

l Soecification:

Specification:

A. The setpoints and minimum number of instrument A.

Instrumentation systems shall be functionally tested and calibrated channels per trip system that must be operable for each as indicated in Tables 4.1-1 and 4.1-2 respectively.

ition of the reactor mode switch, shall be as shown in TN resmo tim M h aw peh we @ feim listed below shall be demonstrated to be within its limit once per 24 months. Neutron detectors are exempt from response time testing. Each test shall include at least one channel in each trip system. All channels in both trip systems shall be tested within two test intervals.

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

2. Drywell High Pressure (05PT-12A, B, C, D)

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

4. Main Steam Line Isolation Valve Closure (29PNS-80A2,82, C2, D2)

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

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

6. Turbine Control Valve Fast Closure (94PS-200A, B, C, D)

7. APRM Fixed High Neutron Flux

8. APRM Flow Referenced Neutron Flux

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

l l

Amendment No. 227, 233, 235, 241 30i l

l

JAFNPP c

3.3.C (cont'd).

4.3.C (cont'd)

P 2.-

The average of the scram insertion times for the three 2.

At 16-week intervals,10 percent of the operable control

~!

fastest operable control rods of all groups of four control rods in a two-by-two array shall be no greater than:

rod drives shall be scram timed above~ 950 peig.~ The same control rod drives should not be tested each interval. Whenever such scram time measurements are Control Rod Average Scram made, an evaluation shell be made to provide reasonoble Notch Position Insertion Time Observed (Seconds) assurance that proper control rod drive performance is t

being maintamed.

1 46 0.361 38 0.977 24 2.112

[

04 3.764 3.

The maximum scram insertion time for 90 percent insertion of any operable control rod shall not exceed 3.

7.00 sec.

All control rods shall be determined operable by demonstrating the scram discharge volume drain and vent valves are:

item Freauency.

a.

Verified Open Once per 31 Days b.

Cycled Fully Closed in accordance with and Open

. the Inservice Testing Program c.

Verified to close within Once per 24 3G seconds after receipt Months of an actual or semulated scram signal and open when.

3 the actual or semulated scram signal is reset.

Amendment No. 49, S2, 75, 85, t 55, 202, 232, 241 96

~

JAFNPP

. 3.4 LIMITW3 CONDITIONS FOR OPERATION -

4.4 SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIOUID CONTROL SYSTEM 4.4 STANDBY LIQUID CONTROL SYSTEM Apolicability:

Apolicability:

" Applies to the operating status of the Standby Liquid Control App'ies to the periodic testing requirements for the Standby Liquid -

Sy; tem.

Control System.

Obiective Obiective:

To assure the availability of a system with the capability to shut To verify the operability of the Standby Liqui.; Control System.

down the reactor and maintain the sht:tdown condition without Specification:

control rods.

A. Normal Or.,eration Specification:

4 A.

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

During periods when fuelis in the reactor and p.ior to startup item from a cold condition, the Standby Liquid Control System shall Frecuency I

be operable except as specified in 3.4.B below. This system 1.

Verify each valve (manual, Once per 31 Days i

need not be operable when the reactor is in the cold condition, all rods are fully inserted and Specification 3.3.A is met.

power operated, or automatic) in the system flowpath that is not locked, sealed or other-wise secured in position, is in the correct positicn.

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 tank.

Amendment No. 444, 241 105

i

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l JAFIIsPP

~

^ 4.4 { cont'd) item Frequency.:

3.

Manually initiate the system, except Once per -

the explosive. valves and pump

' ' ~

24 Months solution in the recirculation path 4.

Explode one of three primer' Once per assemblies manufactured in same.

. 24 Months -

batch to verify proper function.

Then install the two remammg primer..

assemblies of the same batch in-the explosive velves.

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 not clogged.

6.

Test that the setting of the system -

In accordance pressure relief valves is between 1.400 ' with the -

i and 1,490 psig.

Inservice Testing '

Program i-7.

Disassemble and inspect one explosive'.. In accordance valve so that it can be established -

.with the :

that the valve is not clogged. Both.

B.

Operation with inoperable Components valves shall be inspected within

-- inservice

- Testing i

two test intervals.

Program j

From ated after the date that a redundant component is made ~

B.

i or found to be inoperable, Specification 3.4.A shall be Operation with Inoperable Components coessidered fulfilled, and continued operation permitted, provided that:

When a component becomes inoperable its redundant component shall be verified to be' operable immediately and daily thereafter..

1.

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

t Ar ser.dment No. 39,134, 'iS, 232, 241 106 1

Y w

y

-i#--y

..yn-

,.m.,

-c y

JAFNPP ATWS requirements are satisfied at all concentrations above 10 weight percent for a minimum enrichment of 34.7 atom Because components of the system are checked periodically as percer't of B-10.

described above, a functional test of the entire system on a 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 sodium pentaborate solution volume versus concentration contbuous check of the finng circuit continuity is provided by graph. This curve was developed for 34.7% enriched 8-10 pilot lights in the control room, and a pumping rate of 50 gpm. Each point on this curve provides a minimum of 660 ppm of equivalent natural boron in The relief valves in the Standby Liquid Control System protect the system piping and positive displacement pumps, which are the reactor vessel upon injection of SLC solution. At a solution volume of 2200 gallons, a weight concentration of 13%

nominally designed for 1,500 psig, from overpressure. The pressure relief valves discharge back to the standbv tiquid sodium pentaborate, enriched to 34.7% boron-10 is needed to control pump suction line.

meet shutdown requirements. The maximum storage volume of the solution is 4780 gallons which is the net overflow B.

Operation with inoperable Components volume in the SLC tank.

Only one of two standby liquid control pumping circuits is Boron concentration, isotopic enr'

.ent of boron-10, solution needed for operation. If one circuit is inoperable, there is no temperatuie, and volume are checked on a frequency adequate immediate threat to shutdown capability, and reactor operation to assure a high reliability of operation of the system should it may continue during repairs. Assurance that the remaining 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 flowy?. are verified to be in the proper position on a monthly basis. This requirement does not apply to explosive To guard against precipitation, the solution, including that in valves or to valves that cannot be inadvertently misaligned, the pump suction piping, is kept at least 10'F above saturation such as check valves. Verifying the correct alignment of temperature. Figure 3.4-2 shows the saturation temperature manual, power operated, or automatic valves in the system including 10*F margin as a function of sodium pentaborate flowpath provides assurance that the proper flowpath will exist solution concentration. Tank heater and heat tracing system for system operation. The month frequency is based on are provided to assure compliance with this requirement. The engineering judgement and is supported by procedural controls set points for the automatic actuation of the tank heater and heat tracing system are established based on the solution governing valve operation that ensure correct valve positions.

concentration. Temperature and liquid level alarms for the system annunciate in the control room. Pump operability is The only practical time m test the Standby Liquid Control checked on a frequency to assure a high reliability of operation System is during a refueling outage and by irJ"ation f:om local of the system should it ever be required.

stations.

Amendment No. 3S, ' 1S,1 d8, 232, 2 109

i JAFNPP 3.5 (cont'd) 4.5 (cont'd) b.

Flow Rate Test -

in accordance with the Core spray pumps inservice Testing shall deliver at Program least 4,265 gpm against a system head corresporxling to e reactor vessel pressure greater than or equal to 113 psi above primary conteinment pressure.

c.

Verify that each valve Once per 31 Days (manual, power operated or automatic) in the flow path that is not locked, sealed or otherwise secured in position, is in the correct position.

d.

Motor operated valves.

In accordance with the Inservice Testing Program e.

Core Spray Header op Instrumentation Check Once/ day Calibrate Once/3 months Test Once/3 months f.

l.ogic System Refer to Table 4.2-2 Functional Test g.

Testable Check in accordance with the l

Valves inservice Testing Program Amendment No. 40,'49,204,233, 241 113

JAFNPP 3.5 (cont'd) 4.5 (cont'd) 5.

All recirculation pump discharge valves shall be operable 5.

All recirculation pump disci arge valves shall be tested for prior to reactor startup (or closed if permitted elsewhere operability any time the reactor is in the cold condition in these specifications).

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 duririg the proceding 31 days.

6.

If the requirements of 3.5.A cannot be met, the reactor shall be placed in the cold condition within 24 hrs.

B. Containment Ccolino Mode fof the RHR System)

D.

em) 1.

Subsystems of the containment cooling mods shall be demonstrated operable by performing:

1.

Both subsystems of the containment cooling mode, each including two RHR and two RHRSW pumps, shall be item 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 Surveillerce coolant temperature a:212*F except as specified below.

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 Inservice Testing I

mode motor operated Program valves.

l c.

an operability test on the in accordance with RHRSW pumps and the inservice Testing associated motor Program l

operated valves.

d.

a flow rate test verifying in accordance with a flow rate of 4000 gpm the Inservice Testing for each RHRSW pump Program and a total flow rate of 8000 gpm for two RHRSW pumps operating in parallel.

I Amendment No. 2S,95,101,131,118, % 241 115a

JAFNPP 3.5 (cont'd) 1 4.5 (cont'd) 11ain.

Freauency e.

a verification that each Once per 31 Days valve amenuel, power l

operated, or automatic) in the flowpeth that is not locked, sealed or i

otherwise secured in -

position, is in the 1

correct position..

t t

f.

an air test shell be Once per 5. Years l

performed on the conteenment spray headers and noules.

f 2.

Should one RHRSW pump of the components required in When it is determined that one RHRSW pump of the i

2.

3.5.8.1 above be made or found inoperable, contmuod components required in 3.5.8.1 above is inoperable, the reactor operation is permissible only during the remaining components of the containment cochng mode succeeding 30 days provided that during such 30 days all subsystems shell be verified to be operable immodestely

[

and daily thereafter.

remaining components of the containment cooieng mode subsystems are operable.

[

3.

When one containment cochng subsystem becomes 3.

Should one of the containment cooling subsystems inoperable, the redundent containment cooling subsystem

(

(

become inoperable or should one RHRSW pump in each shall be verified to be operable immediately and dedy subsystem become inoperable, continued reactor thereafter. When one RHRSW pump in each subsystem.

i operation is permissible for a period not to exceed 7 becomes inoperable, the remeimng components of the days.

containment coolme subsystems shell be verified to be t

operable immediately and daily thereafter.

4.

If the requirements of 3.5.8.2 or 3.5.8.3 cannot be met, t

the reactor shall be pieced in a cold condition within 24 hr.

.i t

5.

Low power physics testing and reactor operator training shall be permitted with reactor coolant temperature

< 212*F with an inoperable component (s) as specified in 3.5.8 above.

+

4 Amendment No. - 3, '", t '", t 51, t 53,171, =3, 241 116 i

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4 JAFNPP 3.5 (Cont'd)-

4.5 (Cont'd)

E.

Reactor Core 8=as tion Cac ba (RCIC) System e

a E.

Reactor Core Isalation CaaMa (RCIC) Shi s

1.

' The RC?C System shell be operable whenever there 1.

is irradiated fuel in the roector vessel and the reactor RCIC System testeg shell be performed as follows

pressure is greater then 150 psig and reactor coolant provided a reactor steem supply is available. N t

temperature is greater then 212*F except from the steam is not available at the time the survedience

. time that the RCIC System is made or found to be test is scheduled to be performed, the test shall be inoperable for any reason, continued reactor xwer performed within ten days 'of continuous operation operation is permissible during the succeedmg 7 days from the time steem becomes avadable.

unless the system is made operable earher provided that dering thesa 7 days the HPCI System is llem Freauency

operable, a.

Simulated Automatic Once per 24 Months 2.

If the requirements of 3.5.E cannot be met, the Actuation (and Restart *)'

Test reactor shall be placed in the cold condition and pressure 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 l

3.

Low' power physics testing and reactor operator (manual, power operated; training shall be permitted with inoperable or automatic) in the i

components as specified in 3.5.E.2 above, provided system flowpath that that reactor coolant temperature is s212*F.

is not locked, sealed or otherwise secured 4.

The RCIC system is not required to be operable.

in position, is in the 1

during hydrostatic pressure and leakage testing with correct position.

reactor coolant temperatures between 212*F and c.

Motor Operated Once per 92 Days 3OO*F and irradiated fuelin the reactor vessel provided all control rods are inserted.

Valve Operability Automatic restart on a low water level segnal which is subsequent to a high water level trip.

i i

e Amendment No 40, ?^?, ? ?^, ' ??, 233, 241 121 d

W.

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4 t'

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

Item -

Freauency d.

Flow Rate Test -

Once per 92 Days The RCIC pump shall deliver at least 400 gpm against a system head corresponding to a reactor vessel pressure of 1195 psig to 150 psig.

e.

Testable Check Tested for operability Valves any time the reactor is in the cold condition 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 during the preceding 92 days.

l f.

Logic System Once per 24 Months Functional Test 2.

When it is determined that the RCIC System is inoperable at a time when it is required to be operable, the HPCI System shall be verified to be opercble immediately and -

daily thereaf ter.

t Amendment No. 40, 'ie, 239, 241 i

121a e

i

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

F.

ECCS-Coki Constion F.

ECCS-Cold Corwhe=n 1.

A rnenimum of two low pressure Emergency Core Surveellence of the low pressure ECCS systems required Cochng subsystems shell be operable whenever irradisted fuelis in the roector, the reactor is in the by 3.5.F.1 and 3.5.F.2 shen be es fogows:

cold condition, and work is bom0 performed with 1.

the potential for draining the reactor vessel.

In accordence with the inservice Testeg Program,

'l perforrn a flowrote test on the required Core Sprey

' 2.

A minimum of one low pressure Emergency Core pump (s) and/or the RHR pump (s). Each Core Spray I

Cochne subsystem shell be operable whenever pump shell dehwer at least 4,265 spm against a l

irradioted fuel is in the reactor, the reactor is in the system head corresponding to a reactor vessel i

cold condition, and no work is being performed pressure grooter then or aquel to 113 poi above

' with the potential for draming the reactor vessel.

pnmery contamment pressure. Each RHR pump shen dekver at least 8g10 gpm against a system hocd 3.

Emergency Core Coolmg subsystems are not correspondmg to a reactor vessel to primary requwed to be operable provided that the reactor containment differential pressure of m 20 poid.

veneel head is removed, the cavity is flooded, the 2.

t spent fuel pool gates are removed, and the water In accordance with the "a n-v;c. Testing Program, l"

level above ths fuel is in accordence with perform an operability test on the required Core Specsfication 3.10.C.

~

Spray and/or LPC1 motor operated velves.

j 3.

Once each shift verify the suppression ' pool water 4.

Wsth the requirements of 3.5.F.1,3.5.F.2. or level is greater then or equel to 10.33 ft. whenever L

3.5.F.3 not satisfied, s,uspend core alterations and the low pressure ECCS subsystems are abgned to I

su operations with the potential for drainmg the the suppression pool.

reactor vessel. Restore at loest one system to 4.

i operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or establish Once each shift verify a minimum of 324 inches of Secondary Containment Integrity withen the next 8 water is avedoble in the Condensate Storage Tanks hours.

(CST) whenever the Core Spray System (s) is shgned to the tanks.

5.

Once per 31 days, verify that each vobe (manuel, power operated, or automatici in the flowpeth that is t

not locked, sealed, or otherwise secured in position, is in the correct poestion for the required RHR and/or

?

core spray system (s).

i I

s' Amendment No. 4, ??t,153,13 c404, 241 122

.e q

+

3.5 '(cont'd) 4.5 (cont'd).

,G.

Maintenance'of Filled Discharae Pipe G. Maintenance of Filled Discharge. Pee Whenever core spray subsystems, LPCI subsystems, HPCI, or

.- RCIC are required to be operable,' the discharge piping from.

The following. surveillance requirements shall be adhered to, in the pump discharge of these systems to the last block valve '

order to assure that the discharge pipeg of the cor ? sprayi

~

subsystem, LPCI subsystem, HPCI, and RCIC are filled:

. i shall be filled.'.

1.

l.1.

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

F

?

s i

1

.t i

,i Amendment No. 448. 241 i

122a

^

1

.w-

JAFNPP 3.5 (cont'd) 4.5 (cont'd) condstion, that pump shall be considered incperable for 2.

Fo!Iowing any period where the LPCI subsystems or core purposes of satisfying Specifications 3.5.A 3.5.C. and 3.5.E.

rpray subsystems have not been maintained in a fe!!ed condition; the discharge piping of the affected subsystem shafi be vented from the high point of the systern and water flow observed.

3.

Whenever the HPCI or RCIC System is lined up to take suction from the condensate storage tank, the discharge pipir.g of the HPCI or RCIC shall be vented from the high point of the system, and water flow observed on a monthly basis.

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

[

each month.

H.

Averaae Pfanar Linear Heat Generation Rate (APLHGR)

H.

Averace Planar Linear Heat Generatio : Rate (APLHGR)

During power operation, the APLHGR for each type of ft.el as a 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 f-Ypective fue; and lattice types.

i These values are specified in the Core Operating Lirnits Report.

If at anytime during reactor power operation greater than 25%

of rated power it is determined that tne 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 returned to within the prescribed

[

limits within two (2) hours, the reactor power shall be reduced to !ess than 25% of rated power within the next four hours, nr until the APLHGR is returned to within the prescribed Irmits.

Amendment No. '8, S4, '4, 93., 03,109, ' ' 7, ? 2 2,131,162,190,192 123, 241

i l

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

D. Erperaency Service Water System D.

Emerver,cv Service Water System

1. Surveillance of the ESW system shall be performed as

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

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

a.

Simulated Automatic Once every 24 months Actuation Test b.

Flow Rate Test - Each in Accordance with ESW pump shall deliver the Inserv ce at least 1500 gpm to its Testing Program respective loop. The loop. The pump tota!

developed head shall be greater than or equal to the corresponding point on the pump curve, reduced l

by a maximum of 7%, for j

the measured flow.

l c.

Verify that each valve Once per 31 Days (manual, power operated, or automatic) in the i

system flowpath that is not locked, scaled or l

otherwise secured in position, is in the correct position.

I d.

Motor Operated In Accordance with Valves the inservice Testing Program Amendment No.

7', 13', 223, 230, 241 240

___