Text

Proposed Tech Specs,Incorporating IST Requirements of Section XI of ASME Boiler & Pressure Vessel Code
	ML20095F709
Person / Time
Site:	FitzPatrick
Issue date:	12/14/1995
From:	; POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	;
Shared Package
ML20095F694	List: JPN-95-053, Forwards Application for Amend to License DPR-59,revising TSs to Incorporate IST Requirements of Section XI of ASME Boiler & Pressure Vessel Code; ML20095F705; ML20095F709;
References
	NUDOCS 9512190191
	Download: ML20095F709 (85)
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1 l Attachment I to JPN 95-053 1

, PROPOSED TECHNICAL SPECinCATION CHANGES I ASME SECTION XI SURVEILLANCE TESTING

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(JPTS-93-OO3)

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New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50 333 DPR-59 9512190191 951214 PDR ADOCK 05000333 P- PDR.

, JAFNPP TECHNICAL SPECIFICATIONS i TABLE OF CONTENTS EAat 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 REQ'JIREMENTS 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 j l. 4kV Emergency Bus Undervoltage Trip I. 53 J. Remote Shutdown Capability J. 54 l

! 3.3 Reactivity Control 4.3 88 A. Reactivity Limitations A. 88

8. Control Rods B. 91 C. Scram insertion Times C. 95 D. Reactivity Anomalies D. 96 i 3.4 Standby Liquid Control System 4.4 105 A. Normal Operation A. 105 B. Operation With inoperable Compeaents B. 106 C. Sodium Pentaborate Solution C. 107 3.5 Core and Containment Cooling Sptems 4.5 112 l

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) E. 121 System Amendment No. 22,130,131,183,190,216,225,227 i

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 time limits of the ACTION requirements are less than within a specified time interval. Entry into an OPERATIONAL 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance requirements do not have to be

. CONDITION (mode) or specified condition may be made in performed on inoperable equipment.

accordance 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) 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 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 shall be

source is inoperable, it may be considered OPERABLE for the applicable as follows

purpose of satisfying the requirements of its applicable ,

Limiting Condition for Operation, provided: (1) its 1. Inservice testing of pumps and valves shall be performed corresponding normal or emergency power source is in accordance with Section XI of the ASME Boiler and ;

OPERABLE: and (2) all of its redundant system (s), Pressure Vessel Code and applicable Addenda as required subsystem (s), train (s), component (s) and device (s) are by 10 CFR 50, Section 50.55a(f), except where specific OPERABLE, or likewise satisfy the requirements of this written relief has been requested to the NRC pursuant to i specification. Unless both conditions (5) and (2) are satisfied, 10 CFR 50, Section 50.55a(f)(6)(i). . The inservice testing the unit shall be placed in COLD SHUTDOWN within the and inspection program is based on an NRC approved following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . This specification is not applicable when edition of, and addenda to,Section XI of the ASME Boiler in Cold Shutdown or Refuel Mode. and Pressure Vessel Code which is in effect 12 months prior to the beginning of the inspection interval.

F. Equipment removed from service or declared inoperable to comply with required actions may be retumed 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. 82,1Si,1SS, 227 30a 4

4.0 Continued

2. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice testing activities required by the Code and applicable Addenda shall be applicable as defined in Technical Specification 1.0.T. .

3. The provisions of Specification 4.0.B 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 shall be construed to supersede the requirements of any l Technical Specification.

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i Amendment No.

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JAFNPP 3.0 ~ BASES

-A. This specification states the applicability of each specification D. Continued j' in terms of defined OPERATIONAL CONDITION (mode) and is provided to delineate specifically when each specification is the status of the plant before or after an OPERATIONAL i apolicable. CONDITION (mode) change. Therefore in this case, entry into an OPERATIONAL CONDITION (mode) or other specified !

B. This specification defines those conditions necessary to condition may be made in accordance with the provisions of '

. constitute compliance with the terms of an individual Limiting the ACTION requirements. The provisions of this specification Condition for Operation and associated ACTION requirement. .should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to. ,

C. This specification delineates the ACTION to be taken for OPERABLE status before startup. 'l circumstances not directly provided for in the ACTION _ .

' statements and whose 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 i

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . It is assumed that the unit is brought to the ACTION statements of the appropriate specifications.

the required OPERATIONAL CONDITION (mode) within the j required times by promptly initiating and carrying out the E. This specification delineates what additional conditions must i appropriate ACTION statement. be satisfied to permit operation to continue, consistent with the ACTION statements for power sources, when a normal or j

, D. This specification provides that entry into an OPERABLE emergency power source is not OPERABLE. It specifically i CONDITION (mode) must be made with (a) the full prohibits operation when one division is inoperable because its !

complement of required systems, equipment or components normal or emergency power source is inoperable and a OPERABLE and (b) all other parameters as specified in the system, subsystem, train, component 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 provisions of this specification permit the ACTION statements associated with individual systems, subsystems,

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 equipment or systems ACTION statement of the associated electrical power source. ;

inoperable or other limits being exceeded.- Compliance with it allows operation to be govemed by the time 1 ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without the regard to Amendment No. S3,131,1Si 30c

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., t JAFNPP 3.0 BASES - Continued

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

. Condition for Operation for the normal or emergency power two 115KV lines and reserve station transformers be available. i source, and not by the individual ACTION statements for each The ACTION statement provides a 7 day out-of-service time i 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 inoperability definition of OPERABLE were applied without consideration of ;

of its normal or emergency power source. Specification 3.0.E.', all systems, subsystems, trains, '

i components and devices supplied 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 l

i 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 applied continued operation to be consistent with the ACTION . :

! without consideration of Specification 3.0.E., all systems, statement for the inoperable normal power sources instead, i l subsystems, trains, components and devices supplied by the provided the other specified conditions are satisfied. In this [

inoperable emergency power source, diesel generator system case, this would mean that for one division the emergency l i 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 applicable supplied by the emergency power source) and all redundant i Limiting Conditions for Operation. However, the provisions of systems, subsystems, trains, components and devices in the !

Specification 3.0.E. permit the time limits 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 performing their design ,

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 l are not satisfied, shutdown is required in accordance with this be OPERABLE and all redundant systems, subsystems, trains, . !

j specification. components and devices in both divisions must also be _

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

l in Cold Shutdown and Refuel Modes, Specification 3.0.E. is !

. not applicable, and thus the individual ACTION statement for each applicable Limiting Condition for Operation in these

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5 OPERATIONAL CONDITIONS (modes) must be adhered to. !

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l Amendment No. 83,188 i

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. a JAFNPP 5 3.0 ~ Bases - Continued 4

- F. LCO 3.0.F establishes the allowance for restoring _

equipment to service under administrative controls when it has been removed frorn service or declared inoperable to .

l comply with required actions. The sole purpose of this L Specification is to provide an exception to LCO 3.0,.B to allow testing to demonstrate: (a) the operability of the equipment being returned to service; or (b) the operability of other equipment.

The administrative controls ensure the time the equipment 'l is returned to service in conflict with the requirements of -

the required actions is limited to the time absolutely j necessary to perform the allowed testing. This Specification does not provide time to perform any other ,

preventive or corrective maintenance. l An example of demonstrating the operability of the ;

equipment being returned to service is reopening a containment isolation valve that has been closed to comply with the required actions and must be reopened to perform

- the testing.

An example of demonstrating the operability of other equipment is taking an inoperable channel or trip system out 1 of the tripped condition to prevent the trip function from occurring during the performance of testing on another i channel in the other trip system. A similar example of demonstrating the operability of other equipment is taking

- an inoperable channel or trip system out of the tripped ;

condition to permit the logic to function and indicate the appropriate response during the performance of testing on another channel in the same trip system.

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Amendment No. 33,198,22S,227 ;

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JAFNPP 4.0 BASES A. This specification provides that surveillance activities C. Continued necessary to insure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL interval, defined by the provisions of Specification 4.0.B, as a CONDITIONS (modes) for which the Limiting Conditions for condition that constitutes a failure to meet the OPERABILITY Operation are applicable. Provisions for additional surveillance requirements for a Limiting Condition for Operation. Under the activities to be performed without regard to the applicable provisions of this specification, systems and components are OPERATIONAL CONDITIONS (modes) are provided in the assumed to be OPERABLE when Surveillance Requirements individual Surveillance Requirements. have been satisfactorily performed within the specified time interval. However, nothing in this provision is to be construed B. Specification 4.0.B establishes the limit for which the specified as implying that systems or components are OPERABLE when time interval for Surveillance Requirements may be extended. they are found or known to be inoperable although still it permits an allowable extension of the normal surveillance meeting the Surveillance Requirements. This specification also interval to facilitate surveillance scheduling and consideration clarifies that the ACTION requirements are applicable when of plant operating conditions that may not be suitable for Surveillance Requirements have not been completed within tha conducting the surveillance (e.g., transient conditions or other allowed surveillance interval and that the time limits of the ongoing surveillance or maintenance activities). It also ACTION requirements apply from the point in time it is provides flexibility to accommodate the length of a fuel cycle identified that a surveillance has not been performed and not for surveillances that are performed at each refueling outage at the time that the allowed surveillance was exceeded.

and are specified with an 24 month surveillance interval. It is Completion of the Surveillance Requirement within the not intended that this provision be used repeatedly as a allowable outage time limits of the ACTION requirements convenience to extend surveillance intervals beyond that restores compliance with the requirements of Specification -

specified for surveillances that are not performed during 4.0.C. However, this does not negate the fact that the failure refueling outages. The limitation of this specification is based to have performed the surveillance within the allowed on engineering judgement and the recognition that the most surveillance interval, defined by the provisions of Specification probable result of any particular surveillance being performed 4.0.B, was a violation of the OPERABILITY requirements of a is the verification of conformance with the Surveillance Limiting Condition for Operation that is subject to enforcement Requirements. The limit on extension of the normal action. Further, the failure to perform a surveillance within the surveillance interval ensures that the reliability confirmed by provisions of Specification 4.0.B is a violation of a Technical surveillance activities is not significantly reduced below that Specification requirement and is, therefore, a reportable event obtained from the specified surveillance interval. under the requirements of 10 CFR 50.73(a)(2)(i)(B) because it is a condition prohibited by the plant Technical Specifications.

C. This specification establishes the failure to perform a Surveillance Requirement within the allowed surveillance Amendment No. 83,188,188,227 30f

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-4.0 BASES -' Continued 1

C. Continued C. Continued if the allowable outage time limits of the ACTION requirements Surveillance Requirements do not have to be performed on are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply inoperable equipment because the ACTION requirements with ACTION requirements, a 24-hour allowance is provided to -define the remedial measures that apply. However, the permit a delay in implementing the ACTION requirements. Surveillance Requirements have to be met to demonstrate that l This provides an adequate time limit to complete Surveillance inoperable equipment has been restored to OPERABLE status.

Requirements that have not been performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION D. This specification establishes the requirement that all requirements or before other remedial measures would be applicable surveillances must be met before entry into an required that may preclude completion of a surveillance. The OPERATIONAL CONDITION or other condition of operation basis for this allowance includes consideration for plant specified in the Applicability statement. The purpose of this conditions, adequate planning, availability of personnel, the specification is to ensure that system and component time required to perform the surveillance and the safety OPERABILITY requirements or parameter limits are met before significance of the delay in completing the required entry into an OPERATIONAL CONDITION or other specified surveillance. This provision also provides a time limit for the condition associated with plant shutdown as well as startup.

completion of Surveillance Requirements that become applicable as a consequence of OPERATIONAL CONDITION Under the provisions of this specification, the applicable -

(mode) changes imposed by ACTION requirements and for Surveillance Requirements must be performed within the completing Surveillance Requirements that are applicable when specified surveillance interval to ensure that the Limiting an exception to the requirements of Specification 4.0.C is Conditions for Operation are met during initial plant startup or allowed. If a surveillance is not completed within the 24-hour following a plant outage.

allowance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed When a shutdown is required to comply with ACTION within the 24-hour allowance and the Surveillance requirements, the provisions of this specification do not apply Requirements are not met, the time limits of the ACTION because this would delay placing the facility in a lower requirements are applicable at the time the surveillance is CONDITION of operation.

terminated.

l Amendment No.10, Si, 33,100,1 S2,103, 227 3Og l

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JAFNPP i

4.0 BASES - Ccotinued -

' E. This specification ensures that inservice testing of pumps applicability condition takes precedence over the ASME Boiler and and valves will be performed in accordance with a Pressure Vessel Code provision which allows pumps to be tested up periodically updated version of the FitzPatrick plant to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after return to normal operation. As another example, .

" Inservice Testing Program" to comply with Section XI of the Technical Specification definition of OPERABLE does not grant a the ASME Boiler and Pressure Vessel Code and Addenda grace period before a device that is not capable of performing its as required by 10 CFR 50.55a. The plant program specified function is declared inoperable and takes precedence over ~

identifies classifications required by 10CFR50.55a and the ASME Boiler and Pressure Vessel pre-Msion which allows a valve -

Regulatory Guide 1.26. Request for relief from any of to be incapable of performing its specified function for up to 24 - l these requirements is provided in writing to the NRC and hours before being declared inoperable.

is not a part of these Technical Specifications.

i This specification includes a reference to Technical l

Specification Section 1.0.T which defines the frequencies

for performing the inservice testing activities required by i

Section XI of the ASME Boiler and Pressure Vessel Code l and applicable Addenda. This reference is provided to ;

ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any

ambiguities relative to the frequencies for performing the ,

required inservice testing activities.

4 Under the terms of this specification, the more restrictive l requirements of the Technical Specifications take i precedence over the ASME Boiler and Pressure Vessel c Code and applicable Addenda. For example, the

, requirements of Specification 4.0.D to perform l surveillance activities prior to entry into an l OPERATIONAL CONDITION or other specified l.

I Amendment No.

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

l 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 surveillance to be applied to the protection instrumentation.

Soecification: Soecification:

A. The setpoints and minimum number of instrument A. Instrumentation systems shall be functionally tested and channels per trip system that must be operable for each calibrated as indicated in Tables 4.1-1 and 4.1-2 position of the reactor mode switch, shall be as shown in respectively. _

Table 3.1-1.

The response time of the reactor protection system trip functions listed below shall be demonstrated to be within its limit at least once per 18 months. Neutron detectors are exempt from response time testing. Each test shallinclude 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)

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-2OOA, B, C, D)

7. APRM Fixed High Neutron Flux

8. APRM Flow Referenced Neutron Flux Amendment No. GG7 30i

l r JAFNPP I

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

! 2. The average of the scram insertion times for the three 2. At 16-week intervals,10 percent of the operable control i fastest operable control rods of all groups of four control rod drives shall be scram timed above 950 psig.

rods in a two-by-two array shall be no greater than: Whenever such scram time measurements are made, an evaluation shall be made to provide reasonable assurance Control Rod Average Scram that proper control rod drive performance is being i Notch Position Insertion Time maintained.

Observed (Seconds) t 46 0.361 38 0.977 24 2.112 04 3.764

3. The maximum scram insertion time for 90 percent 3. All control rods shall be determined operable by insertion of any operable control rod shall not exceed demonstrating the scram discharge volume drain and 7.00 sec. vent valves are:

Item Freouency

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 18 30 seconds after receipt Months of an actual or simulated scram signal and open when the actual or simulated scram signal is reset.

Amendment No. 10,52,75,SS,155,203 96

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JAFNPP 3.4 LIMITING CONDITIONS FOR OPERATION 4.4 SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 STANDBY LIQUID CONTROL SYSTEM Aoolicability: Acolicability:

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

Obiective Obiective:

To verify the operability of the Standby Liquid Control System.

To assure the availability of a system with the capability to shut down the reactor and maintain the shutdown condition without Soecification:

control rods.

A. Normal Ooeration Specification:

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

During periods when fuelis in the reactor and prior to startup Item Freauency from a cold condition, the Standby Liquid Control System shall be operable except as specified in 3.4.8 below. This system 1. Verify each valve (manual, Once per 31 Days need not be operable 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 flow path that is ;

not locked, sealed or other-wise secured in position, is in the correct position.

2. Pump minimum flow rate of 50 in accordance with gpm shall be verified against a the Inservice Testing system head of 2.1,275 psig Program using demineralized water from the test tank.

Amendment No. 444 105

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e JAFNPP t I

4.4 (cont'd) -.f;;ji J.tagn Frecuency l .

l 3. Manually initiate the system,' except Once per . 'i the explosive valves and pump 18 Months r solution in the recirculation path -

4. Explode one of three primer Once per assemblies manufactured in same 18 Months batch to verify proper function.

, Then install the two remaining primer assemblies of the same batch in -

the explosive valves. !

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5. Demineralized water shall be injected Once per .

into the reactor vessel to test that 18 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 ,

and 1,490 psig. Inservice 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 in the Testing -l' B. Operation with Inocerable Components course of two test intervals. Program -

From and after the date that a redundant component is made B. ' Ooeration with inocerable 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. t Amendment No. 3S,131, 'iS 106 ,

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JAFNPP ATWS requirements are satisfied at all concentrations above 10 Components of the system are checked periodically as described weight percent for a minimum eni chment of 34.7 atom percent t above and make a functional test of the entire system on a of B-10. frequency of more than once each refueling outage unnecessary.

A test of explosive charges from one manufacturing batch is made to assure that the charges are satisfactory. A continuous Figure 3.4-1 shows the permissible region of operation on a . check of the f,n,ng i c,rcu,it i continuity is provided by pilot lights in sodium pentaborate solution volume versus concentration graph. the control room.

This curve was developed for 34.7% enriched B-10 and a pumping rate of 50 gpm. Each point on this curve provides a The relief valves in the Standby Liquid Control System protect ,

minimum of 660 ppm of equivalent natural boron in the reactor the system piping and positive displacement pumps, which are ,

i vessel upon injection of SLC solution. At a solution volume of nominally designed for 1,500 psig, from overpressure. The ,

2200 gallons, a weight concentration of 13% sodium pressure relief valves discharge back to the standby liquid control l

! pentaborate, enriched to 34.7% boron-10 is needed to meet pump suction line. j shutdown requirements. The maximum storage volume of the Ocoration with inocerable Components B.

solution is 4780 gallons which is the net overflow volume in the SLC tank. Only one of two standby liquid control pumpmg circuits is i 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 '

j temperature, and volume are checked on a frequency adequate may continue during repairs. Assurance that the remaining '

l 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 that operability in the operable circuit at least daily.

periodic testing in accordance with the IST Program is adequate to detect if degradation has occurred. Valves in the system C. Sodium Pentaborate Solution

flowpath are verified to be in the proper position on a monthly To guard against precipitation, the solution, including that in the basis. This requirement does not apply to explosive valves or to pump suction piping, is kept at least 10*F above saturation i valves that cannot be inadvertently misaligned, such as check temperature. Figure 3.4-2 shows the saturation temperature valves. Verifying the correct alignment of manual, power including 10*F margin as a function of sodium pentaborate I operated, or automatic valves in the system flow path provides solution concentration. Tank heater and heat tracing system are ;

assurance that the proper flowpath will exist for system provided to assure compliance with this requirement. The set ;

I operation. The month frequency is based on engineering points for the automatic actuation of the tank heater and heat judgement and is supported by procedural controls goveming tracing system are established based on the solution valve operation that ensure correct valve positions. concentration. Temperature anxi l,i quid 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 Control System of the system should it ever be required.

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

t Amendment No. _., ., _

109

JAFNF?

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 1

against a system head corresponding

~

to a reactor vessel pressure greater than ,

or equal to 113 psi '

above primary containment 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 Ap Instrumentation Check Once/ day Calibrate Once/3 months Test Once/3 months

f. Logic System Once/ operating i

Functional Test cycle

g. Testable Check in accordance with the Valses inservice Testing Program Amendment No. 10,'19,201 113

e JAFNPP l I 1.- .i

[

l 3.5 (cont'd) 4.5 (cont'd) l l 5. All recirculation pump discharge valves shall be operable 5. All recirculation pump discharge valves shall be tested for !

j 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , if operability tests have not been !

performed during the preceding 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 Coolina Mode (of the RHR System)

.l I

B. Containment Coolina Mode (of the RHR System) 1. Subsystems of the containment cooling mode shall be j demonstrated operable by performing.

1. Both subsystems of the containment cooling mode, each ;

including two RHR and two RHRSW pumps, shall be ltem Freauency l

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 Surveillance coolant temperature 2: 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 mode motor operated Program

valves.

c. an operability test on the in accordance with RHRSW pumps and the Inservice Testing associated motor Program ;

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.

Amendment No. 26,95,101,134,'50,151 115a i

+

e JAFNPP i

3.5 (cont'd) 4.5 (cont'd) lism Freouency

e. a verification that each Once per 31 Days valve (manual, power '

operated, or automatic) in the flowpath that is not locked, sealed or otherwise secured m position, is in the correct position.

f. an air test shall be Once per 5 Years performed on the containment spray headers and nozzles. '!

2. When it is determined that one RHRSW pump of the

2. Should one RHRSW pump of the components required in components required in 3.5.B.1 above is inoperable, the :'

3.5.B.1 above be made or found inoperable, continued remaining components of the conta'manent cooling mode reactor operation is permissible only during the subsystems shall be verified to be operable immediately succeeding 30 days provided that during such 30 days all and daily thereafter.

remaining components of the containment cooling mode subsystems are operable. 3. When one containment cooling subsystem becomes inoperable, the redundant containment cooling subsystem

3. Should one of :Se containment cooling subsystems .

shall be verified to be operable immediately and daily become inoperable or should one RHRSW pump in each thereafter. When one RHRSW pump in each subsystem subsystem become inoperable, continued reactor becomes inoperable, the remaining components of the operation is permissible for a period not to exceed 7 containment cooling subsystems shall be verified to be days. operable immediately and daily thereafter.

4. If the requirements of 3.5.B.2 or 3.5.B.3 cannot be met, the reactor shall be placed in a cold condition within 24 hr.

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.B above.

Amendment No. 3, 95, ' iS,151,153, ' 71, 203 116'

_ _ _ _ __ _ _ _ _ _ __ _ . _. _ ._ _ _ _ . . - _ . . _ _ _ - . . - _ . _ . . . ~ . _ . _ .m _ _ _ _ _ . _ _ . _ m __. _ _ _ _ _ . _- ..

=

w y 1

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

. E. Reactor Core Isolation Coolina IRCIC) System E. Reactor Core isolation Coolina IRCIC) 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 surveillance temperature is greater than 212*F except from the test 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 i 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 llam Freauency provided that during these 7 days the HPCI System is operable. a. Simulated Automatic Once/ operating Actuation (and Restart') cycle

2. If the requirements of 3.5.E cannot be met, the Test reactor shall be placed in the cold condition and pressure less than 150 psig within M hours. 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 as specified in 3.5.E.2 above, provided is not locked, sealed that reactor coolant temperature is 5212*F. or otherwise secured in position, is in the l 4. The RCIC system is not required to be operable correct pocition.

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 i which is subsequent to a high water level trip.-

i Amendment No. 40,107,?20,'79 121

4 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 1120 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , if operability tests have not been performed during the preceding 92 days.

f. Logic System Once/ operating Functional Test cycle

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 operable immediately and daily thereafter.

Amendment No. 40, '18 121a

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

, F. ECCS-Cold Condition F. ECCS-Cold Condition l 1. A minimum of two low pressure Emergency Core Surveillance of the low pressure ECCS systems required l Cooling subsystems shall be operable whenever by 3.5.F.1 and 3.5.F.2 shall be as follows:

irradiated fuel is in the reactor, the reactor is in the

' cold condition, and work is being performed with 1. In accordance with the Inservice Testing Program, l the potential for draining the reactor vessel. perform a flowrate test on the required Core Spray l pump (s) and/or the RHR pump (s). Each Core Spray

2. A minimum of one low pressure Emergency Core pump shall deliver at least 4,265 gpm against a Cooling subsystem shall be operable whenever system head corresponding to a reactor vessel irradiated fuel is in the reactor, the reactor is in the pressure greater than or equal to 113 psi above cold condition, and no work is being performed primary containment pressure. Each RHR pump shall with the potential for draining the reactor vessel. deliver at least 8910 gpm against a system head <

corresponding to a reactor vessel to primary

3. Emergency Core Cooling subsystems are not containment differential pressure of 2: 20 psid.

required to be operable provided that the reactor vessel head is removed, the cavity is flooded, the 2. In accordance with the Inservice Testing Program, l spent fuel pool gates are removed, and the water perform an operability test on the required Core level above the fuel is in accordance with Spray and/or LPCI motor operated valves.

Specification 3.10.C.

3. Once each shift verify the suppression pool water level is greater than or equal to 10.33 ft. whenever

4. With the requirements of 3.5.F.1,3.5.F.2, or the low pressure ECCS subsystems are aligned to ;

3.5.F.3 not satisfied, suspend core alterations and the suppression pool.

all operations with the potential for draining the reactor vessel. Restore at least one system to 4. Once each shift verify a minimum of 324 inches of operable status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or establish water is available in the Condensate Storage Tanks Secondary Containment integrity within the next 8 (CST) whenever the Core Spray System (s) is aligned hours. to the tanks.

5. Once per 31 days, verify that each valve (manual, power operated, or automatic) in the flowpath that is not locked, sealed, or otherwise secured in position, is in the correct position for the required RHR and/or core spray system (s).

t Amendment No. 4,131,1 SS, ' 74, 204 122

JAFNPP N 3.5 (cont'd) 4.5 (cont'd) i L G. Maintenance of Filled Discharoe Pine G. Maintenance of Filled Discharoe Pine ,

1 l

!. Whenever core spray subsystems, LPCI subsystems, HPCI, or - The following surveillance requirements shall be adhered to, in --

l: . RCIC are required to be operable, the discharge piping from order to assure that the discharge piping of the core spray the pump discharge valve to the injection valve shall be filled. subsystem, LPCI subsystem, HPCI, and RCIC are filled:

l -l l 1. From and after the time that the pump discharge piping of the 1. The discharge piping of these subsystems and systems i

! HPCI, RCIC, LPCI, or Core Spray Systems cannot be shall be verified filled with water from the pump discharge !

maintained in a filled condition, that pump shall be considered valve to the injection valve once per 31 days. t inoperable for purposes of satisfying Specifications 3.5.A, 3.5.C, and 3.5.E. 2. Following any period where these subsystems or systems !

have not been maintained in a filled condition; the -

discharge piping shall be verified filled with water from the ;

pump discharge valve to the injection valve prior to declaring the subsystem or system operable.

3. 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 once per 31 days.

r

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Amendment No. 448 122a ,

I-

I l B JAFNPP l-3.5 (cont'd) 4.5 (cont'd) ;

H. - Averaae Planar Linear Heat Generation Rate (APLHGR) H. Averaae Planar Linear Heat Generation Rate (APLHGR) l During' power operation, the APLHGR for each type of fuel as The APLHGR for each type of fuel as a function of average l

j. a function of axiallocation and average planar exposure shall planar exposure shall be determined daily during reactor be within limits based on applicable APLHGR limit values operation at 2:25% rated thermal power. ,

l-l which 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 i 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 less than 25% of rated power within the next i four hours, or until the APLHGR is returned to within the prescribed limits.

I Amendment No. 13, Si, 71, SS, OS,100, '

7,132,131,162,100,192 123

JAFNPP

. 4.5 BASES .

i M overall core and r

l The testing interval for the Core and Containment Cooling With components or subsystems out-af - ,

l Systems is based on a quantitative reliability analysis, industry containment cooling reliability is by verifying the practice, judgement, and practicality. The Emergency Core operability of the remaining cooling & :. Consistent with Cooling Systems have not been designed to be fully testable the definition of operable in Section. N demonstrate means during operation. For example, the core spray final admission conduct a test to show; verify nm 4ns that the . associated

! valves do not open until reactor pressure has fallen to 450 psig; surveillance activities have been satisfactorily performed within l thus, during operation even if high drywell pressure were the specified time interval.

simulated, the final valves would not open. In the case of the HPCI, automatic initiation during power operation would result The RCIC flow rate is described in the UFSAR. The flow rates to in 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 during a refueling percent reduction from the SAFER /GESTR LOCA analysis. The outage. In the case of the Core Spray System, condensate reductions are based on a sensitivity analysis (General Electric ,

storage tank water will be pumped to the vessel to verify the MDE-93-0786) performed for the parameters used in the '

operability of the core spray header. On a monthly basis, correct SAFER /GESTR analysis.

alignment shall be verified for manual, power operated, or automatic valves in ECCS and RCIC system flow paths to The CS surveillance requirement includes an allowance for system provide assurance that proper flow paths will exist for system leakage in addition to the flow rate required to be delivered to the operation. For the HFCI and RCIC Systems, this requirement reactor core. The leak rate from the core spray piping insede the

also includes the steam flowpath for the turbines and the flow reactor but outside the core shroud is assumed in the UFSAR and i controller position. This surveillance requirement does not apply includes a known loss of less than 20 gpm from the 1/4 inch

to valves that cannot be inadvertently misaligned such as check diameter vent hole in the core spray T-box connection in each of valves, or to valves that are locked, sealed, or otherwise secured the loops, and in the B loop, a potential additional loss of less than in position. A valve that receives an initiation signal is allowed 40 gpm from a clamshell repair whose structural weld covers only to be in a non-accident position provided the valve will 5/6 of the circumference of the pipe. Both of these identified automatically reposition in the proper stroke time upon receipt of sources of leakage occur in the space between the reactor vessel the initiation signal. The monthly frequency of this requirement wall and the core shroud. Therefore flow lost through these leak is based upon engineering judgement and is supported by sources does not contribute to core cooling.

procedural controis goveming valve operation that ensure correct valve positions. This frequency is further supported by the inservice Testing Program, which demonstrates system pump and power operated valve operability. This combination of automatic actuation tests, periodic pump and valve testing, and monthly flow path verification is adequate to demonstrate operability of these systems.

Amendment No.

i, ' 40, 201 132

. . . . .. ... ~ . . - . ..- ...- .~ - - . . . . - . - - . - . - . - , . . . . . - . _ _ . - - . _ .

JAFNPP 4.5 BASES (cont'd) .

The surveillance requirements to ensure that the discharge piping of the core spray, LPCI mode of the RHR, HPCI, and RCIC Systems are filled provides for a visual observation that water flows from a high point vent. This ensures that the line is in a full condition. instrumentation has been provided in the Cote Spray. System and LPCI System to monitor the presence' of water in the discharge piping. This instrumentadon is functionally tested monthly to ensure that during the interval 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 b'y the surveillance tests in Specifications 4.5.A.1 and 4.5.A.3. Section 4.5.F specifies periodic surveillance tests for the low pressure ECCS subsystems which are applicable when the reactor is in the cold condition. These tests in conjunction with the -

requirements on filled discharge piping (Specification 3.5.G), ,

and the requirements on ECCS actuation instrumentation (Specification 3.2.B), assure adequate ECCS capability in the

! cold condition. The water levelin the suppression pool, or the Condensate Storage Tanks (CST) when the suppression pool is i inoperable, is checked once each shift to ensure that sufficient water is available for core cooling. .

l I

t 1

i Amendment No. 'i.1 SS 133

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

4. Pressure Suppression Chamber Reactor Building Vacuum 4. Pressure Suppression Chamber-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 I 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 50.5 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 l

1 i

i Amendment No. 130,134,139 177

i .-

r JAFNPP f.

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

5. Pressure Suppression Chamber - Drywell Vacuum 5. Pressure Suppression Chamber - Drywell Vacuum 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 openmg - closing cycle !

be operable and positioned in the fully closed in accordance with the Inservice Testing Program. l t position except during testing and as specificci in i 3.7.A.S.b below.

l

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 operability is to be not more than 1

open as indicated by the required, the operable breakers shall be exercised ;

position lights. immediately, and every 15 days thereafter until the !

inoperable valve has been retumed to normal service.

c. One drywell suppression chamber vacuum breaker c. Each vacuum breaker valve shall be visually may be determined to be inoperable for opening. inspected to insure proper maintenance and l i

operation in accordance with the Inservice Testing i Program. i l

d. Deleted l

d. A leak test of the drywell to suppression chamber structure shall be conducted once per operating l cycle; the acceptable leak rate is :sO.25 in.

water / min, over a 10 min period, with the drywell at 1 psid.

i i

[

Amendment No. 135,102 178

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

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

of water vacuum under calm wind conditions with a filter train flow rate of not more than 6,000 cfm, shall be demonstrated at each refueling outage prior to refueling, D. Primary Containment isolation Valves D. Primary Containment Isolation Valves

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

line excess flow check valves shall be cr -able, except as specified in 3.7.D.2. The containment unt and purge 11MB Freauency valves shall be limited to opening argles less than or equal to that specified below: a. The operable isolation In accordance with valves that are power the Inservice Valve Number Maximum Oranino Anole 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 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 Inservice be tested for proper Testing Program operation.'

c. All normally open power- In accordance with operated isolation valves the inservice (except for the main Testing Program steam isolation valves) shall be fully closed and reopened.

The current surveillance interval for testing instrument line excess flow check valves is extended until the end of the R11/C12 refueling outage scheduled for January,1995. This is a one-time extension, effective only for this surveillance interval. The next surveillance interval will begin upon completion of this surveillance.

Amendment No. 151,'73,195 185

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

Freauency .

Ham

d. With the reactor at a in accordance with reduced power level, the Inservice Testing fast close each main Program j steam isolation valve, one at a time, and verify closure time. .

4 i

e. Main steam isolation Twice per Week l valves shall be exercised ;

by partial closure and ;

subsequent reopening. i

2. With one or more of the containment isolation valves 2. Whenever a conta'mment isolation valve is inoperable, inoperable, maintain at least one isolation valve operable verify the affected penetration flowpath is isolated once f in each affected penetration that is open and: per 31 days.

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

b. Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve j secured in the closed position. Isolation valves closed to satisfy these requirements may be !

reopened on an intermittent basis under j administrative control; or ,

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

3. If Spe ifications 3.7.D.1 or 3.7.D.2 cannot be met the [

reactor shall be in the cold condition within 24 hrs.

P h

Amendment No. 131,151,*73,102,203 186 u-_ _ _- _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _

i t

l',- . !

JAFNPP 4.7 BASES (cont'd) operability results in a more reliable system.

4 The main steam line isolation valves are functionally tested on [

a more frequent interval to establish a high degree of - t j reliability. ;

i f The primary containment is penetrated by several small .

diameter instrument lines connected to the reactor coolant '

system. Each instrument line contains a O.25 in. restricting orifice inside the primary containment and an excess flow

!' check valve outside the primary containment.

I A list of containment isolation valves, including a brief j description of each valve is included in Section 7.3 of the updated FSAR. !

t Primary containment penetrations which have an inoperable ,

isolation valve (or valves) are verified to have the penetration (

flow path isolated monthly. When the closed isolation device is in a high radiation area, this verification may be performed i by administrative means. t i

r Amendment No. 154,173,203 197

.._. . . _ _. ~m _ _ m _. _ , . . _ - ._ . - . - . . . ___. . _ _ . . _ . . . _ _ . __ . .. . _ _ _ . _ . . - . _ . _ _ - - - _

JAFNPP 4.11 (Cont'd) 3.11 (cont'd) D. Emeroency Service Water System D. Emeroency Service Water System ;

1. Surveillance of the ESW system shall be performed as - i

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

systems shall be operable when the requirements of '

halB Freauency specification 3.5.A and 3.5.8 must be satisfied, except as specified below in specification 3.11.D.2. i

a. Simulated Automatic Once/ operating l '

Actuation Test cycle

b. Flow Rate Test - Each in Accordance with j ESW pump shall deliver the Inservice i at least 1500 gpm to its Testing 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 (manual, power operated, ;

or automatic) in the system flowpath that is i

not locked, sealed or !

otherwise secured in position, is in the correct position. l

d. Motor Operated in Accordance with Valves the Inservice Testing -

Program ,

Amendment No. 7*,131,223 -

240 t L

4 Attachment ll to JPN 95-053

\

SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES ASME SECTION XI SURVEILLANCE TESTING (JPTS 93-003) l 1

l i

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I New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR 59

Attachment ll to JPN-95 053 SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES ASME SECTION XI SURVEILLANCE TESTING (JPTS-90-003)

l. DESCRIPTION OF THE PROPOSED CHANGES The proposed change to the James A. FitzPatrick Technical Specifications (TS) incorporates the inservice testing requirements of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code and makes editorial corrections on the affected pages. The proposed change is described below.

Minor changer in format, such as type font, margins or hyphenation, are not described in this submittal. These changes are typographicalin nature and do not affect the content of the Technical Specification.

Incorocration of ASME Section XI

1. Revise page i to show Specification 3.1, Reactor Protection System, located on page 30i to reflect the renumbering of pages in item 2.

2. Renumber existing pages 30b,30c,30d,300,30f and 30g to read 30c,30d,30e, 30f,30g and 30i, respectively. The changes described in the following items 5 and 6 refer to these renumbered pagos and indicate where new pages are inserted.

3. Add a new Surveillance Regairement 4.0.E to revised page 30a and new page 30b which reads as follows:

"E. Surveillance Requirements for inservice testing of components shall be applicable as follows:

1. Inservice testing of pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(f), except where specific written relief has been requested to the NRC pursuant to 10 CFR 50, Section 50.55a(f)(6)(i). The inservice testing and inspection program is based on an NRC approved edition of, and addenda to,Section XI of the ASME Boiler and Pressure Vessel Code which is in effect 12 months prior to the beginning of the inspection interval.

2. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice testing activities required by the Code and applicable Addenda shall be applicable as defined in Technical Specification 1.0.T.

Attachm:nt 11 to JPN 95-053

. SAFETY EVALUATION Page 2 of 21

3. The provisions of Specification 4.0.B 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.

S. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification."

4. Add a new Bases Section 4.0.E to the newly created page "30h" which reads as follows:

"E. This specification ensures that inservice testing of pumps and valves will be performed in accordance with a periodically updated version of the FitzPatrick plant " Inservice Testing Program" and the " Weld and Support Inservice Inspection Program" to comply with Section XI of the ASME Boiler and Pressure Vessel Code and Aodeada as required by 10 CFR 50.55a. The plant programs identify classifications required by 10CFR50.55a and Regulatory Guide 1.26. Request for relief from any of these requirements is provided in writing to the NRC and is not a part of these Technical Specifications.

This specification includes a reference to Technical Specification Section 1.0.T which defines the frequencies for performing the inservice testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This reference is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. For example, the requirements of 2 Specification 4.0.D to perform surveillance activities prior to entry into an OPERATIONAL CONDITION or other specified applicability condition takes

, precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps to be tested up to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after return to normal operation. As another example, the Technical Specification definition of OPERABLE does not grant a grace period before a device that is not capable of performing its specified function is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable."

Attachm:nt ll to JPN-95-053

'. ~ SAFETY EVALUATION Page 3 of 21

5. On page 96, Surveillance Requirement 4.3.C.3:

i a) Revise and reformat Surveillance Requirement 4.3.C.3 from:

"All control rods shall be determined operable once each operating cycle by demonstrating the scram discharge volume drain and vent valves l' operable when the scram test initiated by placing the mode switch in the SHUTDOWN position is performed as required by Table 4.1-1 and by

verifying that the drain and vent valves:

a. Close in less than 30 seconds after receipt of a signal for control rods to scram, and l b. Open when the scram signalis reset."

i

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

I Ilam Frecuency

! a. Verified Open Once per 31 Days 4

b. Cycled Fully Closed and in accordance with the Open Inservice Testing Program l 1

c. Verified to close within 30 Once per 18 Months I seconds after receipt of an 1 actual or simulated scram i

signal and open when the actual or simulated scram

. signal is reset."

6. On page 105 and 106, Surveillance Requirement 4.4.A; a) Add a new Surveillance Requirement 4.4.A.1 which states the following:

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

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Attachm:nt 11 to JPN 95-053

. SAFETY EVALUATION Page 4 of 21 4

- b) Change Surveillance Requirement 4.4.A.1 to 4.4.A.2, change format to item and 1

Freauency as in 6.a above, and change frequency from: "At least Once per Month" to: "In accordance with the Inservice Testing Program".

c) Change Surveillance Requirement 4.4.A.2 to 4.4.A.3,4.4.A.4,4.4.A.5,4.4.A.6, and 4.4.A.7 and reformat to item and Freauency as in 6.a above.

d) Change the frequency of Surveillance Requirements 4.4.A.3,4.4.A.4, and 4.4.A.5 from "At least once during each operating cycle" to "Once per 18 months".

e) Change frequency of Surveillance Requirements 4.4.A.6 and 4.4.A.7 from "At least once during each operating cycle" to "In accordance with the inservice

Testing Program".

f) In Surveillance Requirement 4.4.A.7, delete the sentence reading "Both valves i shall be inspected in the course of two operating cycles."

7. On page 109, Bases Section 3.4.A, replace the sentence:

. " Experience with pump operability indicates that monthly testing is adequate

to detect if failures have occurred."

with

" Experience with pump operability indicates that periodic testing in accordance with the IST program is adequate to detect if degradation has occurred. Valves in the system flowpath are verified to be in the proper position on a monthly basis. This requirement does not apply to explosive valves or to valves that cannot be inadvertently misaligned such as check valves. Verifying the correct alignment for manual, power operated, or i automatic valves in the system flow path provides assurance that proper flow

, paths will exist for system operation. The monthly frequency is based on engineering judgement and is supported by procedural controls governing i

valve operation that ensure correct valve positions."

8. On page 113, Surveillance Requirement 4.5.A.1;

. a) Replace "Once/3 Moriths" with "In accordance with the Inservice Testing Program"in Surveillance Requirement 4.5.A.1.b.

b) Delete Surveillance Requirement 4.5.A.1.c and replace with the following:

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

~*

, Attechm@nt 11 to JPN 95-053

. SAFETY EVALUATION Page 5 of 21 c) Change the frequency of Surveillance Requirement 4.5.A.1.d from "once/ month" to "In accordance with the Inservice Testing Program".

d) Replace "31 days" with "In Accordance with the Inservice Testing Program"in Surveillance Requirement 4.5.A.1.g.

9. On pages 115a and 116, Surveillance Requirements 4.5.B.1; a) Change the format of Surveillance Requirement 4.5.8.1 to item and Frecuency as in 6.a above, b) Move the phrase "per Surveillance Requirement 4.5.A.3* from the llem description to the Freauency for Surveillance Requirement 4.5.B.1.a.

c) In 4.5.B.1.b replace "a monthly" with "an" and add "In accordance with the Inservice Testing Program" under Freauencv.

d) Change 4.5.B.1.c.1" to "4.5.B.1.c", replace "a monthly" with "an" and add "In accordance with the Inservice Testing Program" under Freauencv.

e) Change "4.5.8.1.c.2" to "4.5.8.1.d*, delete the phase "at least once every 3 months and* from the llem description and add "In accordance with the Inservice 1 Testing Program" under Freauencv. !

1 f) Add new Surveillance Requirement 4.5.B.1.e as follows:

"A verification that each valve Once per 31 Days (manual, power operated, or automatic) )

in the flowpath that is not locked, sealed, l or otherwise secured in position, is I in the correct position." l 1

g) Change "4.5.B.1.d* to "4.5.B.1.f", delete the phrase "during each five year period

in the llem description and add "once per 5 years" under Freauencv.

10. On pages 121 and 121a, Surveillance Requirement 4.5.E.1; a) Replace Surveillance Requirement 4.5.E.1.b with the following:

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

l I

1

, Attachm:nt 11 to JPN-95-053 SAFETY EVALUATION Page 6 of 21 b) Change the frequency of Surveillance Requirement 4.5.E.1.c from "once/ month" to "Once per 92 days".

c) For Surveillance Requirement 4.5.E.1.d, replace:

$ " Flow Rate Once/3 months" with

" 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 1120 psig to 150 psig."

l d) Replace "31 days" with "92 Days" in Surveillance Requirement 4.5.E.1.e.

t

11. On page 122, Surveillance Requirement 4.5 F; a) Revise the first sentence of Surveillance Requirement 4.5.F.1 to read:

"In accordance with the Inservice Testing Program perform a flowrate test I a on the required core spray pump (s) and/or the RHR pump (s)."

b) Revise Surveillance Requirement 4.5.F.2 to read: )

"In accordance with the Inservice Testing Program perform an operability test on the required core spray and/or LPCI motor operated valves."

c) Add a new Surveillance Requirement,4.5.F.5, which reads as follows:

1

. "Once per 31 days, verify that each valve (manual, power operated, or automatic) in the system flow path that is not locked, sealed, or otherwise secured in position, is in the correct position for the required RHR and/or core spray system (s)."

l l

1 i

Attachm:nt il to JPN 95-053

. SAFETY EVALUATION Page 7 of 21

12. On pages 122a and 123, LCO 3.5.G and Surveillance Requirement 4.5.G:

a) In LCO 3.5.G, change"... pump discharge of these systems to the last block valve..." to "... pump discharge valve to the injection valve...".

b) Change 4.5.G.1 from:

"Every month prior to the testing of the LPCI subsystem and core spray subsystem, the discharge piping of these systems shall be vented from the high point, and water flow observed."

to "The discharge piping of these subsystems and systems shall be verified filled with water from the pump discharge valve to the injection valve once per 31 days."

~

c) Change 4.5.G.2 from:

I

! "Following any period where the LPCI subsystems or core spray subsystems have not been maintained in a filled condition; the discharge piping of the affected subsystem shall be vented from the high point and water flow l observed."

l to ,

"Following any period where these subsystems or systems have not been maintained in a filled condition; the discharge piping shall be verified filled with water from the pump discharge valve to the injection valve prior to declaring the subsystem or system operable."

d) Delete 4.5.G.3.

1 e) Change 4.5.G.4 to 4.5.G.3 and change "... tested each month." to "... tested once l per 31 days."

I l

1 i

. . - . . ._ .. . = -. - - .- ..

Attachm:nt ll to JPN 95 053

. SAFETY EVALUATION Page 8 of 21

13. On page 132, Basos Section 4.5, replace in the second paragraph:

"To increase the availability of the individual components of the Core and Containment Cooling Systems the components which make up the system I.e., instrumentation, pumps, valve operators, etc., are tested more frequently.

The instrumentation is functionally tested each month. Likewise, the pumps and motor operated valves are also tested quarterly to assure their operability. The combination automatic actuation test and monthly tests of the pumps and valve operators is deemed to be adequate testing of these systems."

with "On a monthly basis, correct alignment shall be verified for manual, power operated, or automatic valves in ECCS and RCIC System flow paths to provide assurance that proper flow paths will exist for system operation. For the HPCI and RCIC Systems, this requirement also includes the steam flow path for the turbines and the flow controller position. This surveillance requirement does not apply to valves that cannot be inadvertently misaligned such as check valves, or to valves tilat are locked, sealed, or otherwise secured in position. A valve that receives an initiation signal is allowed to be in a non-accident position provided the valve will automatically reposition in the proper stroke time upon receipt of the initiation signal. The monthly frequency of this requirement is based upon engineering judgement and is supported by procedural controls governing valve operation that ensure correct valve positions. This frequency is further supported by the Inservice Testing Program, which demonstrates system pump and power operated valve operability. This combination of automatic actuation tests, periodic pump and valve testing, and monthly flow path verification is adequate to demonstrate operability of these systems."

4

]

4

Attachm:nt 11 to JPN 95 053

. SAFETY EVALUATION Page 9 of 21

14. On page 133, Bases Section 4.5, change the last three sentences in the paragraph at the top of the page from:

"Between the monthly intervals at which the lines are vented, instrumentation has been pmvided in the Core Spray System and LPCI System to monitor the presence of water in the discharge piping. This instrumentation will be calibrated on the same frequency as the safety system instrumentation. This period of periodic testing ensures that during the interval between the monthly checks the status of the discharge piping is monitored on a continuous basis."

to

" Instrumentation has been provided in the core Spray System and LPCI System to monitor the presence of water in the discharge piping. This instrumentation is functionally tested monthly to ensure that during the interval between the monthly checks the status of the discharge piping is monitored on a continuous basis."

15. On page 177, Surveillance Requirement 4.7.A.4:

a) Change Surveillance Requirement 4.7.A.4.a from:

"The pressure suppression chamber-reactor building vacuum breakers and associated instrumentations including setpoint shall be checked for proper operation every three months."

to "The pressure suppression chamber reactor building vacuum breakers shall be checked in accordance with the Inservice Testing Program."

Add new Surveillance Requirement 4.7.A 4.b:

"b. Instrumentation associated with pressure suppression chamber reactor building vacuum breakers shall be functionally tested once per 92 days."

l 1 - --- -- um e-----

', Att: chm:nt 11 to JPN 95 053

. SAFETY EVALUATION Page 10 of 21

16. On page 178, Surveillance Requirement 4.7.A 5:

a) Change Surveillance Requirement 4.7.A.S.a from:

4 "Each drywell suppression chamber vacuum breaker shall be exercised

through an opening - closing cycle monthly."

to "Each drywell suppression chamber vacuum breaker shall be exercised through an opening - closing cycle in accordance with the Inservice Testing Program."

b) Change Surveillance Requirement 4.7.A.S.c from:

"Once each operating cycle, each vacuum breaker valve shall be visually inspected to insure proper maintenance and operation."

i to "Each vacuum breaker valve shall be visually inspected to insure proper maintenance and operation in accordance with the Inservice Testing

Program."

17. On pages 185 and 186, Surveillance Requirement 4.7.D.1:

a) Change the format of Surveillance Requirement 4.7.D.1 to llem and Frecuency as in 6.a above.

b) Change Surveillance Requirement 4.7.D.1.a from:

"At least once per operating cycle, the operable isolation valves that are power operated and automatically initiated shall be tested form simulated automatic initiation and for closure time."

to "ltem Freauencv

a. The operable isolation valves that are in accordance with the power operated and automatically initiated Inservice Testing Program shall be tested for automatic or simulated automatic initiation and for closure time."

., Attachm:nt 11 to JPN 95-053

. SAFETY EVALUATION l Page 11 of 21 c) Change Surveillance Requirement 4.7.D.1.b from:

"At least once per operating cycle, the instrument line excess flow check valves shall be tested for proper operation."

to

" Instrument line excess flow check valves in accordance with the shall be tested for proper operation." inservice Testing Program d) Change Surveillance Requirement 4.7.D.1.c.(1) from:

"c. At least once per quarter:

(1.) All normally open power-operated isolation valves (except form the main stream line and Reactor Building Closed Loop Cooling Water System (RBCLCWS) power-operated isolation valves) shall be fully closed and reopened."

to "c. All normally open power-operated in accordance with the isolation valves (except for main Inservice Testing Program steam isolation valves) shall be fully closed and reopened."

e) Change Surveillance Requirement "4.7.D.1.(2)" to "4.7.D.1.d" and change text from:

"With the reactor at a reduced power level, fast close each main steam isolation valve, one at a time, and verify closure time."

to "llem Freauency With the reactor at a reduced power level, in accordance with the fast close each main steam isolation valve, . Inservice Testing Program one at a time, and verify closure time."

Attachm:nt ll to JPN-95-053

. SAFETY EVALUATION Page 12 of 21 f) Change Surveillance Requirement "4.7.D.1.d* to "4.7.D.1.e" and change text 4 from:

"At least twice per week, the main steam line power-operated isolation valves shall be exercised by partial closure and subsequent reopening."

to

" Main steam isolation valves shall be Twice per Week exercised by partial closure and subsequent reopening."

g) Delete Surveillance Requirement 4.7.D.1.e.

h) Change Surveillance Requirement 4.7.D.2 from:

"Whenever a containment isolation valve is inoperable, the position of at least one other valve in each line having an inoperable valve shall be recorded daily."

to

"Whenever a containment isolation valve is inoperable, verify tF a affected penetration flowpath is isolated once per 31 days."

18. On page 197, Bases for 4.7.D, primary containment isolation valves:

a) Delete next to last paragraph regarding test of RBCLCWS valves.

b) Add a new Bases paragraph at the end of Bases 4.7.D which states " Primary containment penetrations which have an inoperable isolation valve (or valves) are verified to have the penetration flow path isolated monthly. When the closed isolation device is in a high radiation area, this verification may be performed by ;

administrative means. l l

19. On page 240, Surveillance Requirement 4.11.D.1; a) Change "Once/3 months" to "In accordance with the Inservice Testing Program"in Surveillance Requirements 4.11.D.1.b and d.

l b) Replace Surveillance Requirement 4.11.D.1.c with the following:

" Verify that each valve (manual, power Once per 31 Days operated, or automatic)in the system flow path that is not locked, sealed, or ,

otherwise secured in position, is in i the correct position." l

Attachm:nt il to JPN 95-053

. SAFETY EVALUATION Page 13 of 21 Editorial Corrections

1. On page 105, Surveillance Requirement 4.4.A.2, delete the first sentence reading

" Demineralized water shall be recycled to the test tank." and revise the second sentence to read:" Pump minimum flow rate of 50 gpm shall be verified against a system head of 21,275 psig using demineralized water from the test tank."

2. On page 109, in the fourth line of the third paragraph, replace "...every..." with

" ever...".

3. On pa0e 113, replace the phrase "Once/each operating cycle" with "Once/ operating cycle" in Surveillance Requirement 4.5.A.1.f.

4. On page 115a, replace ":" with a "." at the end of Specification 3.5.B.1.

5. On page 122a, Specification 3.5.G.a, renumber specification "3.5.G.a" as specification "3.5.G.1."

6. On page 122a, Surveillance Requirement 4.5.G.3, replace "...to insure they..." to "...to ensure they...".

7. On page 133, reference to " calibration" of instrumentation is removed and wording l changed for clarification to reflect a change that should have been part of I Amendment 37.

8. On page 133 at the end of the first paragraph, replace "... bases." with "... basis.".

9. On page 240, Surveillance Requirement 4.11.D.1, replace the phrase "Each operating cycle" with "once/ operating cycle".

II. PURPOSE OF THE PROPOSED CHANGES GeneralIncomoration of ASME Section XI This proposed TS amendment incorporates the requirements of the NRC approved version ,

of the Section XI ASME B&PV Code (Reference 1) for inspecting and testing of ASME '

B&PV Code class 1,2, and 3 components. The purpose of this change is to eliminate unnecessary testing at power, consistent with the Nuclear Regulatory Commission policy l (Reference 2), by consolidating portions of the Technical Specification surveillance test program, inservice Test Program, and Weld and Support Inservice Inspection Program.

The changes will assure adequate testing for operability while eliminating component wear due to excessive testing. j

~ _ _. . _ - . -

1 .

Attachment ll to JPN-95-053

. SAFETY EVALUATION Page 14 of 21 10 CFR 50.55a(f) requires that the plant Inservice Testing and Inspection Programs be revised periodically. The revised programs must use, to the extent practicable, the testing requirements contained in the latest edition and addenda of the ASME Code that is in effect 12 months prior to the revision. The current inservice Testing Program was developed to meet ASME Section XI,1980 Edition through Winter 1981 Addenda. It will be revised for the third inspection interval (currently scheduled to begin September 1996).

The wording of the proposed Section 4.0.E is general enough to accommodate changes to the inservice test program without requiring future TS changes. The proposed testing program for pumps and valves follows the requirements of ASME Section XI, Paragraph IWP-3400, " Frequency of Inservice Tests," and Paragraph IWV-3400, " Inservice Tests, Category A and B Valves." In addition, testing program also follows the guidance of NRC Standard Technical Specifications (Specification S.5.7) and the NRC Standard Review Plan 3.9.6, " Inservice Testing of Pumps and Valves," which states in part, "The pump and valve test programs are acceptable if they meet the requirements for establishing reference values and the periodic testing schedule of IWP 3000 and IWV-3000, respectively, of Section XI of the ASME Code. The allowable ranges of inservice test quantities, corrective actions, and bearing temperature tests for pumps are established by IWP-3000 and lWP-4000. The pump test schedule in the plant technical specification is required to comply with these rules."

This change replaces the monthly Technical Specification surveillance requirement for I pumps and valves with the James A. FitzPatrick ASME B&PV Section XI Inservice Test l Program (Reference 3) in a manner consistent with the Standard Technical Specifications

) (STS)(Reference 6). This change also revises other Surveil!ance Requirements to be i consistent with the requirements of ASME Section XI (e.c;., methodologies for determining

( reference data, acceptable calibration frequencies, testing of specific parameters, acceptance criteria, etc.). The effect will be to eliminate unnecessary testing of safety l related pumps and valves, particularly during power operation.

l Editorial Corrections 1

Changes identified in Section i of this amendment submittal as editorial changes can be l

grouped as:

1. Typographical / Punctuation Corrections i

The correction on page 115a will clarify the sentence by correcting the punctuation.

Attachm:nt 11 to JPN-95 053

'. SAFETY EVALUATION Page 15 of 21

2. Editorial Changes Editorial changes have been made that clarify the Technical Specifications. They include clarification of the source of demineralized water for test of Standby Liquid Control pump testing (page 105), correction of a typographic error (page 109),

improvement of word usage (pages 113,122a,133, and 240), and correction to i numeration (page 122a).

3. Correction of Bases (page 133) to reflect an earlier Technical Specification Amendment Amendment 37 was issued on June 14,1978 and addressed, in part, the replacement of " keep full' instrumentation (pressure switches) with level switches on the high point vents on core spray and RHR (LPCI mode) discharge lines. The changes to Surveillance Requirement 4.5.G.4 reflected that the level switches do not require calibration. However, changes to the associated Bases on page 133 were overlooked. The changes to Bases page 133 provide clarification.

Ill. SAFETY IMPLICATIONS OF THE PROPOSED CHANGES Incorocration of ASME Section XI This amendment replaces the existing Technical Specifications Surveillance test requirements for pumps and valves with the requirements and criteria of ASME Section XI.

This revises the testing frequency of pumps and valves to be consistent with ASME Section XI. This change is both administrative and technicalin nature. The replacement of multiple individual test requirements with a single requirement (Section 4.0.E) is an administrative change which has a negligible impact on plant operations and safety. The extension of the specified surveillance intervals from monthly to quarterly is a technical change.

Reactor Core isolation Cooling (RCIC) system pump and valve testing (which is not part of the Inservice Testing Program) is also changed from monthly to once per 92 days. This makes RCIC testing consistent with ASME Section XI testing of ECCS.

The CitzPatrick Technical Specifications contain, in part, monthly pump and valve surveillance test requirements for the following systems:

Standby Liquid Control System (4.4.A)

Core Spray System and Residual Heat Removal System (4.5.A)

Containment Cooling (4.5.B)

High Pressure Coolant injection (4.5.C)

Reactor Core Isolation Cooling System (4.5.E)

Emergency Core Cooling System - Cold Condition (4.5.F)

Attachment 11 to JPN 95 053

. SAFETY EVALUATION Page 16 of 21 Primary Containment isolation Valves (4.7.D)

Pressure Suppression Chamber-Reactor Building and Pressure Suppression Chamber Drywell Vacuum Breakers (4.7.A.4 & 5)

Emergency Service Water System (4.11.D)

These Technical Specifications generally require that pumps and valves be tested once per month. These monthly surveillance tests (i.e., a pump functional test and a valve stroke test), demonstrate system availability by operating the starting circuits and verifying proper equipment operation. They are replaced by the requirements imposed by the new Surveillance Requirement,4.0.E (except for RCIC), which incorporates the FitzPatrick 4 inservice testing program, and will result in a quarterly testing cycle in place of the existing I monthly tests. Retained are the pump functional tests which demonstrate pump hydraulic performance by confirming an established discharge flow rate or discharge pressure.

Those tests and tests on other components (e.g., injection line testable check valves) have been revised to require quarterly testing. RCIC pump functional tests and RCIC system motor operated valve testing has been revised to quarterly which is consistent with ECCS system testing and Standard Technical Specifications (Reference 6). A monthly ;

verification is being incorporated to check proper valve position of valves that are not i locked, sealed, or otherwise secured in position to provide assurance that a proper system flow path will exist for system operation.

Verification that a containment penetration with an inoperable isolation valve is properly I I

isolated has been changed from once per day to once per 31 days. This is consistent with the new monthly verification of the proper positioning of valves in system flowpaths and is also consistent with Standard Technical Specifications 3.6.1.3, Action A.2.

Requiring the HPCI and RCIC discharge piping to be filled with water at all times when the system is required has been clarified and the requirement to verify the discharge piping of HPCI and RCIC to be filled with water prior to return to service after maintenance has also been clarified. The wording used in specifications 3.5.G,4.5 G.1,4.5.G.2 and 4.5.G.3 has been changed to make it consistent with Standard Technical Specifications, SR 3.5.1.2 and 3.5.3.1.

A review of the FitzPatrick FSAR and the Technical Specifications indicates no design basis licensing criteria which would preclude surveillance test extension.

l l

Att: chm:nt 11 to JPN 95 053

. SAFETY EVALUATION Page 17 of 21 In the late 1960s General Electric (GE), used simplified probabilistic techniques to establish a logical basis for both surveillance test intervals and the allowable outage times for BWR technical specifications. GE Report APED 5736 (Reference 5) and a 1968 article from the magazine Nuclear Safety (Reference 6) provide an in-depth discussion of these modeling techniques. These two documents were used as the rationale for the Bases Sections of the FitzPatrick Technical Specifications for the test intervals specified. These studies established the connection between system availability as a function of failure rates, repair timos, and the du'ation between operability tests. They concluded that frequent system testing would provide greater assurance of system operability since the likelihood of detecting a component suffering from degradation prior to failure was increased.

These studies did not recognize the reduction on system availability due to the fact that a system is considered unavailable while being tested in a mode that prevents automatic operation. A trade-off exists between the confidence in system operability due to frequent

, testing and system unavailability due to testing. Also, this approach did not recognize that a component which is repeatedly tested would experience further wear and degradation compared to a component which is in a static condition awaiting operation.

Following issuance of the FitzPatrick Operating License, both the Standard Technical Specifications (STS) and the ASME Code were revised to require quarterly pump and valve testing. These changes were based,in part, on concerns for accelerated component aging due to excessive testing and on a better understanding of the relationship between test frequency and component / system availability. These changes eliminated unnecessary monthly tests which are a burden on plant personnel and result in unnecessary additional wear on the components and equipment in the safety systems, and also reduced the risk of plant transients associated with testing at power.

A reduction in testing would, therefore, provide the benefits of reducing system unavailability and the associated possibility of a plant transient during such testing at power and reducing component degradation due to extensive testing and the need for i down time during component maintenance. Additionally, the ASME tests measure changes in pump and valve performance. Degradation can be detected and corrective action (i.e., further testing, repair, etc.) implemented to provide continuous assurance that safety equipment can fulfill their intended functions.

The proposed Section 4.0.E is consistent with the STS (Reference 6) for the requirement that the Technical Specifications take precedence whenever they are more stringent.

However, the proposed TS Section 4.0.E differs from the STS in that the proposed Section 4.0.E allows deviations from the ASME Section XI code where relief has been requested in writing to the NRC. The STS does not address the mechanism to obtain relief. This deviation reflects current practice and is consistent with 10 CFR 50.55a. !

1

Attachment il to JPN-95 053

. SAFETY EVALUATIOM Page 18 of 21 There is one surveillance for which the STS requires a greater frequency than the quarterly testing requirements of ASME Section XI.

Surveillance Requirement 4.7.A.5.a requires each vacuum breaker in the Suppression Chamber to Dryweil Vacuum Breaker System to be operated monthly. This exceeds the current quarterly stroke test required by the ASME Section XI program but is consisten+

with the monthly test requirement in Standard Technical Specification SR 3.6.1.8.2 wh'd is based on the harsh environment in which the valves are located. Since the pressure suppression chamber to drywell vacuum breaker valves at the FitzPatrick Plant are located in the Reactor Building rather than in the harsh environment of the pressure suppression chamber as described in the Standard Technical Specification SR 3.6.1.8.2 Bases, the Authority proposes to make the testing frequency consistent with Pressure Suppression Chamber Reactor Building Vacuum Braaker Surveillance Requirement 4.7.A.4.a. The valves are 30 inch diameter swing check valves with a counterweight to ensure that the valve remains seated until a pressure differential of 0.5 psid exists across the seat.

Revising the frequency of the stroke test to agree with the current quarterly stroke test required by the ASME Section XI program can be justified based upon the similarity to other swing check valves tested to this frequency and a demonstration that the environment has not resulted in operability concerns.

Editorial Corrections Various editorial or administrative changes to pages which were the subject of this amendment submittal are made to improve the consistency and clarity of the Technical Specifications. These have no adverse safety significance.

Attachment ll to JPN-95-053

. SAFETY EVALUATION Page 19 of 21 IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Operation of the FitzPatrick plant in accordance with the proposed Amendment would not involve a significant hazards consideration as defined in 10 CFR 50.92, since it would not:

1. involve a significant increase in the probability or consequerces of an accident previously evaluated.

The changes identified in this proposed amendment revise surveillance testing for various systems based upon the Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code. None of these changes involves a hardware modification to the plant, a change to system operation, a change to the manner in which the system is used, or a change in the ability of the system to perform its intended function.

The use of Section XI of the ASME B&PV Code as a basis for establishing surveillance testing and acceptance criteria will not alter existing accident analyses.

This has been acknowledged and accepted by the NRC in the Standard Technical Specifications. The change to surveillance testing frequencies reduces testing at power, increases the availability of systems important to the mitigation of a DBA, and minimizes component degradation due to excessive testing. The ASME B&PV l Code,Section XI testing tracks component performance allowing identification of component degradation and the code specifies that if a pump parameter enters the alert range, then the testing frequency is doubled until the cause of the degradation is determined and the condition corrected. Similarly, if a valve stroke time degrades, the valve testing frequency is increased to once per month until the cause is determined and the condition corrected.

The editorial changes are strictly non technicalin nature with no effect on existing analyses. They clarify the Technical Specifications by improving the legibility of this document.

2. create the possibility of a new or different kind of accident from those previously evaluated.

The proposed changes involve no hardware changes, no changes to the operation of t the systems, and do not change the ability of the systems to perform their intended functions. The use of ASME Section XI as the basis for testing involves the same testing alignments and practices previously used as part of either the IST program or Technical Specification Surveillance Requirements. The editorial changes have no effect on plant practices.

Attachm:nt il to JPN-95-053

. SAFETY EVALUATION Page 20 of 21

3. involve a significant reduction in the margin of safety.

There are no hardware modifications, changes to system operations, or effect on the ability of systems to perform their intended function associated with the proposed changes. The proposed changes to reference pump and valve testing to Section XI of the ASME B&PV Code and remove individual Surveillance Requirements in the Technical Specifications does not relax any controls or limitations. The resulting reduction in test frequency, while reducing the possibility of detecting a degraded component prior to failure, is offset by the increased availability of systems important to plant safety and an associated reduction in component wear and degradation due to excessive testing. Additionally, the ASME testing program evaluates components for degraded performance and willidentify such degradation early. There are no safety margins associated with the editorial corrections.

V. IMPLEMENTATION OF THE PROPOSED CHANGES

! Implementation of the proposed changes will not adversely affect the ALARA or Fire

Protection Program at the FitzPatrick plant, nor will the changes impact the environment.

The results of these changes are expected to reduce the occupational doses to plant personnel since the number of tests performed in radiation areas will be reduced. The proposed change will not change the testing process currently in place to meet ASME Section XI requirements and therefore can have no impact on the Fire Protection program or the environment.

VI. CONCLUSION This change, as proposed, does not constitute an unreviewed safety question as defined in 10 CFR 50.59. That is, it:

1. will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report;

2. will not increase the possibility for an accident or malfunction of a type different from ary evaluated previously in the safety analysis report; and

3. will not reduce the margin of safety as defined in the basis for any technical specification.

The change involves no significant hazards consideration, as defined in 10 CFR 50.92.

Attachm:;nt ll to JPN-95-053

, , SAFETY EVALUATION Page 21 of 21 Vll. REFERENCES I

1. ASME Boiler and Pressure Vessel Code,Section XI,1980 Edition through Winter 1981, Articles IWP and IWV.

4

2. SECY-88-304, " Policy issue Regarding Staff Actions to Reduce Testing at Power", ;

dated October 26,1988.

3. Inservice Testing Program for James A. FitzPatrick Nuclear Power Plant, Second 4

inservice Interval, Revision 4, dated May 1,1991.

! 4. APED-5736, " Guidelines for Determining Safe Test Intervals and Repair Times for Engineered Safeguards," dated April 1969.

5. " Reliability of Engineered Safety Features as a Function of Testing Frequency,"

. Nuclear Safetv Vol. 9, No. 4, July - August,1968.

i

6. NUREG-1433, " Standard Technical Specifications for General Electric Boiling Water Reactors (BWR/4)", Revision 1, dated April 1995.

7. NYPA letter, J. C. Brons to NRC, dated November 20,1989 regarding definition of the terms Demonstrate and Verify for the Technical Specifications (JPN-89-076).

8. NRC letter, D. LaBarge to J.C. Brons, dated January 3,1990, transmitting Technical Specification Amendment 148.

9. James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report, Sectio,1s 4.8,6.0, and 9.7.1.

10. James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report (SER), dated November 20,1972, and Supplements.

r 1

Attachment 111 to JPN 95-053 l

l PROPOSED TECHNICAL SPECIFICATION CHANGES I ASME SECTION XI SURVEILLANCE TESTING MARKUP OF TECHNICAL SPECIFICATION PAGES (JPTS-93-003) l I

l New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59

JAFNPP 4

. TECHNICAL SPECIFICATIONS 4

TABLE OF CONTENTS

E821 l

1.0 Definitions 1 LIMITING SAFETY SAFETY LIMITS SYSTEM SETTINGS 1.1 Fuel Cladding Integrity 2.1 7 j

1.2 Reactor Coolant System 2.2 27 SURVEILLANCE ( 30; ;

j LIMITING CONDITIONS FOR OPERATION REQUIREMENTS C 1

3.0 General 4.0 30 3.1 Reactor Protection System 4.1 30 l j 3.2 Instrumentation 4.2 49 i A. Primary Containment isolation Functions A. 49 i 8. Core and Containment Cooling Systems - 8. 50 l i Initiation and Control C. Control Rod Block Actuation C. 50 l

D. Radiation Monitoring Systems Isolation - D. 50

{

i and initiation Functione E. Drywell Leak Detection E. 53 l 53 F. Feedwater Pump Turbine and Main Turbine Trip F.

i

! G. Recirculation Pump Trip G. 53 H. Accident Monitoring Instrumentation H. 53 f 1. 4kV Emergency Bus Undervoltage Trip 1. 53 i J. Remote Shutdown Capability J. 54 l 3.3 Reactivity Centrol' 4.3 88 i A. Reactivity Limitations A. 88

8. Control Roda 8. 91 C. Scram insertion Times C. 95 D. Reactivity Anomalies D. 96 3.4 Standby Uguid Control System 4.4 105 A. Normal Operation A. 105

8. . Operation With inoperable Components 8. 106 C. Sodium Pentaborate Solution C. 107 3.5 Core and Containment Cooling Systems 4.5 112 A. Core . Spray and LPCI Systema A. 112

8. Containment Cooling Mode of the RHR 8. 115 System C. HPCI System C. 117 D. Automatic Depressurization System (ADS) D. 119 E. Reactor Core Isolation Cooling (RCIC) E. 121 .

System Amendment No. " "^ "' * * * * ^^ *" " " 29-i y

/

m ,.t 3.0 Continued 4.0 Conimued ;

D. Entry into an OPERATIONAL CONDITION (mode) or other that a Suiveillance Requirement has not been pedormed Tte specified condition shall not be made when the condihons for the ACTION requrements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to i

Limiting Condshon for Operation are not met and the associated permd the complebon of the surveillance when the allowable _

ACTION requires a shutdown if they are not met withm a outage time hmets of the ACTION requirements are less than 24 speedied time interval. Entry into an OPERATIONAL hours. Survedlance requirements do not have to be perfonred CONDITION (mode) or specihed condshon may be made in on inoperable equipment. i accordance with ACTION requirements when conformance to them pemuts conhnued operation of the facdity for an unhmited D. Entry into an OPERATIONAL CONDITION (mode) shaN not be ;

penod of time. This provision shaB not prevent passage through made unless the Surveillance Requiremerd(s) associated with tte i i OPERATIONAL CONDITIONS (modes) required to comply with Limihng Condition for Operahon have been performed wittun the l ACTION requirements. Eve.nawww to these requirements are apphcable survedlance interval or as otherwise specified. Ttis l l

l stated in the individual specahcations. provision shall not prevent passage through or to Operational Modes as required to comply with ACTION Requirements. j E. When a system, subsystem, train, component or device is detemuned to be inoperable solely because its emergency power l source is inoperabie, or soleiy be== its normai power source r l is inoperable, it may be considered OPERABLE for the purpose N W _' 4 (ADD MM

g'I- l of satisfymg the requwements of its apphcable Limihng Cons 9 tion :

l for Operation, provided- (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its [

! redundant system (s), subsystem (s), tran(s), component (s) and ( 4} Oad c oMh au# 5 dev6ce(s) are OPERABLE, or hkewise saksfy the requirements of this specshcahon. Unless both conditions (1) and (2) are cw y w y !

sabstied, the unit shau be placed in COLD SHUTDOWN wittun I the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . This specihcation is not apphcable when in Cold Shutdown or Refuel Mode.

F. Equipment removed from service or declared inoperable to L comply with required actions may be retumed to sesvice under [

l admmistrative 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.

s :

Amendsnent No. %, 1/4, 1/8, 227 30a ,

i

}

! JAFNPP 3.0 BMiEE i A. This spacefscation states the appbcab6ty of each specification D. Continued in tersns of defined OPERATIONAL CONDITION imodel and is .

i prowsdod to dehneses spectSceBy when each specdication is the status of the plant before or after an OPERATIONAL b!

- appaiemhim. CONDITION tenodel change. Therefore in this case, entry into Ii an OPERATIONAL CONDITION (model or other specified h B. This specsfication defines those con 6tions necessary to con &tson may be made in accordance with the provisions of t f(

copanihse cosnphence with the conne of an individual Limstang the ACTION requiresnents. The provisions of this specification ' /,

Condeion for Operation and W ACTION requerement. should not, however, he interpreted as endorsing the failure to ll esercise good practice in restonne systesns or components to 4 C. This ap.cassemeiani delineates the ACTION to be taken for OPERABLE status before startup. S ,

cercuenstances not drectly provided for in the ACTION staessnents and whose occurrence would wielete the intent of 8:--::;i-- to this prowesson may be made for a limited number tha , _ -t <- _ Under the tenne of SpecHication 3.0, the of specifications when startup with inoperable equipment facety is to be pieced in COLD SHUTDOWN wishen the would not affect plant safety. These exceptaans are stated in fo5 ewing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . It is aneumed that the unit is brought to the ACTION statements of the appropriate specifications.

the required OPERATIONAL CONDITION imodel wethan the required tienes by prompely initiating and carrying out the E. This specification dehneates what additional conditions must appropriate ACTION mamamanent. be satssised to pennst operation to continue, consistent with ,'

the ACTION statements for power sources, when a normed or D. This spacefication provides that entry into an OPERABLE esnergency power source is not OPERA 8LE. It specifically CONDITION (model must be snede with tal the fuE prohsits operation when one division is inoperable because its ,l comgdemont of requwed systesns, equipment or components normal or emergency power source is inoperable and a system, subsystem, train, component or dewsce in another lI

- OPERA 8LE and lid as other parameters as specedied in the (

~

Limiting Condicions for Operation being met without regard for &wisson is inoperabis for another reason. j f I

, anowable dewsesions and out of service provisions contained in '

, the ACTION atacaments. The prowessons of this specification permit the ACTION statements mamanared with individual systems, subsystems, _

The intent of this provision is to insure that facility operation is trains, components or devices to be consistent with the '

not inieimeant with esther required equipment or systems ACTION statement of the associated electrical power source.

inoperable or other lunsts beene exceeded. C-r;W.e with it allows operation to be governed by the time

, ACTION requweenents that permet contanued operation of the I facility for an unlunited period of time provides an acceptable level of safety for contmuod operation wethout the regard to N C- T4%7~ mo#D AZUw1

^ '

Amendment No. pfI,1/ A Pu 3o6)

Q*O ,

JArNPP 3.0 BASES - Continued 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 1ISKV 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 inoperability definition of OPERABLE were applied without consideration of of its normal or emergency power source. Specification 3.0.E., all syslems, subsystems, trains, components and devices s@ plied 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 inoperabic. This would dictate invoking the applicable ACTION 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 applied continued operation to be ccasistent with the ACTION without consideration of Specification 3.0.E., all systems, statement for the inoperable normal power sources instead, subsystems, trains, components and devices supplied by the provided the other specified conditions are satisfied. In this inoperable emergency power source, diesel generator system case, this would mean that for one division ttw emergency A or B, would also be inoperable. This would dictate invcking power source must be OPERABLE (as must be the components the applicable ACTION statements for each of the appiscable supplied by the emergency tower source) and all redundant Limiting Conditions for Operation. However, the provisions of systems, subsystems, traint, components and devices in the Specification 3.0.E. permit the time limits for continued other division must be OPEIABLE, or likewise satisfy operation to be consistent with the ACTION statement for the Specification 3.0.E. (i.e., be. capable of performing their design inoperable emergency diesel generator system instead, functions and have an eme+gency power source OPERABLEl.

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 all redundant systems, subsystems, trains, I

specification. components and devices in both divisions must also be OPERABLE. If these conditions are not satisfied, shutdown is ,

required in accordance with this specification. g v

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

Amendment No. pd -+98-30c e

m l

3.0 Beans - Contmund O .

l F. LCO 3.0.F establishes the aHowance for restonne j

j equipment to service under adminestrative controls when it I hos been removed from sendce or declared inoperable to l

I comply with required actions. The sole purpose of this l

Specification'is to provide an exception to LCO 3.0.B to

asow testmo to demonstrate: (a) the operebdity of the l

l equipment being returned to service; or (b) the opersinkty of 1

other equipment.

1' l The admirustrative contrais ensure the time the equipment is retumed to service in conflict with the requirements of k the required actions is limited to the time absolutely l necessary to perform the agowed testing. This 1

Specification does not provide time to perform any other l preventive or corrective meintenance.

l An example of demonstrating the operability of the

equipment being retumed to service is reopening a 1

I containment isolation valve that has been closed to comply l with the required actions and must be reopened to perform l

the testing.

l An example of demonstrating the operability of other equipment is taking an m ' operable channel or trip system out of the tripped condition to prevent the trip function from l ,

occurring during the performance of testing on another

[ channel in the other trip system. A simder example of T demonstrating the operability of other equipment is taking I an inoperable channel or trip system out of the tripped l l condition to permit the logic to function and indicate the appropriate response during the performance of testing on another channel in the same trip system. I 30e JdY7~ "0VGb fr20m P4c4 30 g Amendment No. 22,1SS, 22S[-2W--

g i

l - . ,-

~

JAFNPP 4.0 BASES A. This specification provides that survedance activities C. Continued ,

necessary to insure the Limitine Corxhtions for Operation are met and wiu be performed during the OPERATIONAL interval, defined by the proviseons of Specification 4.0.B. as a l CONDITIONS (modes) for which the Limiting Conditions for condition that constitutes a failure to meet the OPERABILITY Operation are applicable.' Ptowisions for additional survedlance requirements for a Limitmg Condetion for Operation. Under the activities to be performed without regard to the applicable provisions of this specsfication, systems and components are !

OPERATIONAL CONDITIONS (snodeel are provided in the assumed to be OPERABLE when Survedience Requirements individual Surveillance Requirements. have been satisfactorily performed within the specified time :

interval. However, nothmg in this provision is to be construed G. Specification 4.0.8 menhhehes the limit for which the specified as implying that systems w components are OPERABLE when i time interval for Surveitance Requirements may be extended. they are found or known to be inoperable although still it permsts an allowable extension of the normal surveillance meeting the Survenance Requirements. This specification also interval to facihtete survedence scheduimg and consideration clarifies that the ACTION requirements are appbcable when of plant operating condstions that sney not be suitable for Surveillance Requirements have not been completed within the conductmg the survedence (e.g., transient conditions or other allowed survedance interval and that the time limits of ths oneoing surveitance or meentenance actevices). It also ACTION requirements apply from the point in time it is ,

provides flexibility to accommodate the length of a fuel cycle identified that a survedlance has not been performed and not ;

for surveitances that are performed et each refueline outage at the time that the atowed surveellence was exceeded. '

and are specified with a 24 month surveitance interval. It is Completion of the Survedence Requirement within the not intended that this provision be used renestedly as a alloweide outage time limits of the ACTION requirements ;

convenience to extend surveillance intervals beyond that restores comphance with the requirements of Specification ;

specified for survedences that are not performed durMS 4.0.C. However, this does not negate the fact that the failure :

refuehng outages. The limitation of this specification is based to have performed the survedience within the aEowed l on engineering judgement and the recognition that the most surveillance interval, defined by the provisions of Specification ;

probable restit of any particular survestience beine performed 4.0.B. was a violation of the OPERABILi'Y requirements of a i is the verification of conformance with the Surveitance Lbniting Condition for Operation that b odsect to enforcement Requirements. The limit on extension of the normal action. Further, the failure to perform a survestience within the ;

l surveiEence interval ensures that the r=Enhnty confirmed by provisions of Specification 4.0.B is a violation of a Technical surveiEance activities is not significantly reduced below that Specification requirement and is, therefore, a reportable event i obtained from the specified survedlance interval. under the requirements of 10 CFR 50.73(aH2HiHB) because it is a condition prohibited by the plant Technical Specifications.

l C. This specification establishes the failure to perform a Survedlance Requirement within the allowed surveitance j yS TE x f M O W h h 20*t P W 3 0 Amendment No. 23,1SS,10 fN 4 l 7b 30e

l O

JAFNPP 1

4.0 BASES - Continued C. Continued C. Contmuod if the allowable. outage time brnsts of the ACTION requirements Survedlance Requirements do not have to be performed on l are less then 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply inoperable equipment hac- the ACTION requirements with ACTION requirements, a 244mur allowance is provided to define the remedaal measures that apply. However, the i permit a deley in implementing the ACTION requirements. Survedlance Requirements have to be met to demonstrate that This provides an adequate time Emit to complete Surveillance inoperable equipment has been restored to OPERABLE status.

Requirements that have not been performed. The purpose of this asowance is to pennit the completion of a surveigence i before a shutdown is required to comply with ACTION D. This specification establishes the requirement that all requirements or before other remedial measures would be appbcable survedlances must be snet before entry into an l required that may preclude cc-- ;*-^A-i of o surveillance. The OPERATIONAL CONDITION or other condition of operation basis for this eBowance includes consideration for plant specified in the Applicability statement. The purpose of this ,

condeons, adequate planning, availabshty of personnel, the specification is to ensure that system and csw.parwit ,

time required to perform the surveillance and the safety OPERASILITY requrements or parameter limits are met before significance of the delay in completing the required entry into an OPERATIONAL CONDITION or other specified surveeBance. This provision also provides a time limit for the condation samariated with plant shutdown as well as startup. '

completion of Surveillance Requirements that become applicable as a consequence of OPERATIONAL CONDITION Under the provisions of this specification, the appiscable '

(model changes imposed by ACTION ret;uirements and for Surveellence Requirements must be performed within tho' cc=-;t ^~--@ Surveisance Requirements that are applicable when specified surveeBance interval to ensure that the 1imiting r an e-- ;^':=i to the requirements of Specification 4.0.C is Condstions for Operation are met dunne initial plant startup or allowed. If a surveigence is not completed within the 24-hour fo5owing a plant outage.

allowance, the time limits of the ACTION requerements are ;

appbcable at that time. When a surveillance is performed When a shutdown is required to comply with ACTION i within the 24-hour allowance and the Survedlance requirements, the provisions of this specification do not apply i Requirements are not met, the time limsts of the ACTION because this would deley piscing the facility in a lower [

requirements are appbcable at the time the survedlance is CONDITION of operation.

terminated.

{TAYr movfb Mo*t *?" 30-$

Amendment No. 'S, S', SS,10^, IS2,123 BN- (

30f l

JARFP --

3.1 i sulTING CONDITIONS FOR OPERATION 4.1 SURVElLLANCE REQUIREMENTS 3.1 REACTOR PROTECTION SYSTFM 4.1 REACTOR PROTECTION SYSTEM Aophcability aggihcabskir i

l

Apphes to the instrumentaban and metad devur which Apphes to the survesitance of the instrumentation and associated devices wtuch initiate reactor scram.

instaate the reactor scram. ,

Ohgectsve: l Otyective:

To assure the operabshty of the Reactor Prnametum System. To speedy the type of frequency of survedlance to be apphed to 4

the protechon instrumensatum.

Specdicaban: Specdacahon.

A. The setpomis and mesmum number of instrument channels A. Instrumentahon systems shall be funchonally tested and l cabbrated as indicated in Tables 4.1-1 and 4.1-2 per trip system that must be operable for each posshon of the raartar mode switch, shat be as shown in Table 3.1-1. respectively. ,

l !

f The response time of the reactor protection system trip

/ funchons hsted below shall be demonstrated to be wittin its '

' limit at leact once per 18 months. Neutron detectors are i

sxempt from response time testing Each test shallinclude at !

least one channel in each trio system. All channels in both h i

trip systems shaR be tester *Athin two test intervals. -

2

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

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

3. Reactor Water Level-Low (L3) (02-3LT-101 A, B, C, 0) l I f ;

4. Main Steam Line isolabon Valve Closure (29PNS-80A2, B2, C2, D2) ,

I (2SPNS-86A2, B2, C2, D2) i

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

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

7. APRM Fixed High Neutron Flux 3OI 8. APRM Flow Referenced Neutron Flux pw 3Og Amendment No. 227

@) (TEF nroub A I i

._ . _ . _ _ . - _ . _ . _ _ ._. - - - - . _ _ _ . . _ _ . ~ . . _ . . _ _ _ _ . _ . . _ _ _.m_._. - -. _ ._

JAFNPP i

4.0 - BASES - Continued ,

E. This specification ensures that inservice inspection of applicability condition takes precedence over the ASME Boiler and -

components and inservice testing of pumps and valves Pressure Vessel Code provision which allows pumps to be tested up .

will be performed in accordance with a periodically to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after return to normal operation. As another example, .

updated version of the FitzPatrick plant " Inservice Testing the Technical Specification definition of OPERABLE does not grant a Program" to comply with Section XI of the ASME Boiler grace period before a device that is not capable of performing its and Pressure Vessel Code and Addenda as required by 10 specified function is declared inoperable and takes precedence over. '

CFR 50.55a. The plant program identifies classifications the ASME Boiler and Pressure Vessel provision which allows a valve required by 10CFR50.55a and Regulatory Guide 1.26. to be incapable of performing its specified function for up to 24

- Request for relief from any of these requirements is hours before being declared inoperable. .

provided in writing to the NRC and is not a part of these Technical Specifications.

This specification includes a reference to Technical Specification Section 1.0.T which defines the frequencies for performing the inservice inspection and testing -

activities required by Section XI of the ASME Boiler and '

Pressure Vessel Code and applicable Addenda. This reference is provided to ensure consistency in surveillance intervals throughout these Technical Specifit::ations and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive d *o. ;

2 requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel 8$ l Code and applicable Addenda. For example, the 9g5 requirements of Specification 4.0.D to perform surveillance activities prior to entry into an F p, gf ' !

OPERATIONAL CONDITION or other specified Amendment No.

3Oh

. __._ _ __ _ __ __ . . _ . _ _ _ _ _ _ _ _ _ _ . _ . _ . _ _ _ _ . _ _ _ _ . _ . _ . _ _..m _ . _ _ _ _ . _

JAFNPP 3.3.C (cont'd!

4.3.C (cont'd)

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 twc by :g array shou be no greater then: rod drives shou be scram timed above 950 psig. '

Whenever such scram time measurements are made, an Control Rod Average Scram evaluation shou be made to provide reasonable assurance Notch Position Insertion Tune that proper control rod drive performance is being maintained.

Ohaarved (Sacendal t

46 0.381 i

. 38 0.977 24 2.112 e

04 3.764

3. The maximum scram insertion time for 90 percent 3. Au control rods shen be determined operableConce ea%c J L- t j insertion of any operable control rod shen not exceed 7.00 sec. . S-Qperating cyctelby demonstrating the scram discharge {

volume drain and went valvesioperable when me scram fTest initiated by placing the modo switch in the '

SHUTDOWN position is performed as required by Table L4.1-1 and by worifying that the drain and went vd. s m-W [

l y7g, s. ,

\

i Close in less that 30 seconds after receipt of a '

l ** W 't' #34 0 #P64 segnal for control rods to scram, and l l

onc4 pgit si n ys )

b. C y c t-sE t> #m s.y C t.oS46 b Open when the scram signal as reset.

y# M ##8d d I

C. j i l

}

Ao ;>

o p,pg M i

sanYM YW6 l

[ashmiscos 1,~6stnic i

Pwk Am Mf0RMkT* Anb Abb IHOMNif C. Vtassige rs e,ta,,g ,g,,,,4 % M. p ass n o n ct u t a M 'l 30 s4 conks Afr%Il IWestFT UH *

f M Acrant oR- sensat ordi> -

h'C M N S~ **

s c st A *4 186N44. Adb *P44 IADMAJ Ysta?- ACfg46L trat. $s MesdLefWU 5 IGA R*- 15 124Sdy",

J

.m.ndrnent uo. p . g. p . pr. v t -

96 1

m _ . _ _. _ _ . _ . _ _ _ _ _ . _ . _ . . . . - _ _ _ _

~

JAFCPP 3.4 LH11TIIIG CONQlI[ pets _f0R_QPER_ATigej 4.4 SUtygI_LLANCEJEQutaEMENTS 3.4 STAJlppY LIOUJD_CONTROLSISIEM 4.4 STANDBY _LIQUIQ_f0NTRQL. SYSTEM APalleabi)Ity: Apell_catti tity: .

i Applies to the operating status of the Standby Liquid Applies to the periodic testing requirements for the j Control System. Standby Liquid Control System.

l l Ott.inctive: Qbits.tive.

l To assure the availability of a system with the To verify the operability of the Standby Liquid I capability to shut down the reactor and maintain the Control System.

, shutdown condition without control rods.

-Specifications Specificating:

A. Normal Ooeration ,

A. EnD!tal Operation '

During periods whom fuel is in the reactor and The operability of the Staedby Liquid Control System prior to startup from a cold condition, the

' shall be verified by performance of the following Standby Liquid Control System shall be operable tests:

except as specified in 3.4.B below. This system f. bD ** SK P44 ta8 54c7-need not be operable when the reactor is in the cold conditlom, all rods are fully inserted and M ,@t Isaat esce per mont; h i

Specification 3.3.A is met. p

( Domineralised water shall be recycled to tao (t==* tank./ Pump minimum flow rate of 50 gym l t

I, ,

R6 /6 44 sLT y shall be verified against a system head of 2 A S

X rts gs A s3b C j I P*I k *III L

n bdN *"WLc Mb MLA M*di'one W tw sT rw MK 7 82 ,

N .(At least east durin Ygooerating cyciD Manually initiate the system, except the Cuc6 M/t espl%ic; velves and gp

=

Amendment No 't-Hr-105 i

.. _ _ _ _ _ . _ _ _ _ - _ __ ___ _ _ ~. _= _ _. . _. _.__ _ ._ _ _ _ _ __. _ . . _ _ . . ._ _.

~

O JAFNPP onc4 P 4.4 (cont'd) L9 moords

. F pump solution in the recirculahon path.

//. Explode one of three primer assembhes manufactured in same batch to verify proper function. Then install the two remairung primer assembhes of the same batch in the,%

Rn#8/ 'w# explosive valves .

MW# [. Derraneralized water shall be injected into the reactor

' , g ,a ue.s ey' vessel to test that valves (except explosive valves) not j checked by the recirm hon test are not ravvywt. L

4. Test that the setting of the system pressure relief valves is l {

between 1,400 and 1,490 psig.

i

/ 7. h6 and inspect one explosive valve so that it can .-

be mtahhshed that the valve is not r*vvywi. Bot _h valves I b shall be inspected in the course of two@erating cyclep I risr B. Operation with inoperable Components *#"

' 0-When a component becomes anoperable its redundant From and after the date that a redundant corrporst is made or component shall be verified to be operable immediately and found to be inoperable, Specificahon 3.4.A shall be conssdered daily thereafter. l fulfilled, and conhnued operation permitted, provided that-

1. The component is retumed to an operable condition within I#

7 days.

Amendment No. ,'llf, }34 W 106

_ .. . _ _. . _ ._ . _ _ . . _ . _ _ _ _ . _ _ _ _ _ . _ _ . ~ . _ - _ _ . _ . . . . . . . . . _ _ _ _ . . . _ . _ _ _ _ . . _ - . - _

JAFNPP l

4 ATWS requirements are satisfied at all concentrations above 10 The relief valves in the Standby 1.JquK1 Control System protect'-

weight percent for a minimum enrichment of 34.7 atom percent the system piping and positive displacement pumps, which are of B-10. nominally designed for 1,500 psig, from overpressure. The Figure 3.4-1 shows the permissible region of operation on a presswe reW h dhge M to the standby hqwi

sodium pentaborate ddm volume versus concentration contrd pwnp e line.

graph. This curve was developed for 34.7% enriched 8-10 and B. Operation with inoperable Components .

a pumping rate of 50 gpm. Each pomt on this curve provides a moimum of 660 ppm of equivalent natural boron m the reactor d M % @ M d m h 4 is vessel upon W of SLC dh M a soluhon volume of needed for operahon. If one circuit is inoperable, there is no ;

2200 gallons, a weight concentrahon of 13% sodium e a1 shutdown W, W reacts opwh pentaborate, ennched to 34.7% baron-10 is needed to meet may rp. Asswance that the r%

shutdown requirements. The maximum storage volume of the "Y" "" m is N by @ pump pw in he opwable scuh at M @

l d dm is 4780 gallons which is the not overflow volume in the ,

! SLC tank. C. Sodium PerWahnrate Soluhon

.,t l Boron concentrabon, isotopic annchment of boron-10, d den To guard agamst precipitation, the enh dm, includog that in the j god temperature, and volume are checked on a frequency pump suchon pipeg, is kept at least 107 above saturation A artaryda to assure a high Z r" of operation of the system i temperature. Figure 3A-2 shows the saturation temperature should it(over91be required. Exponence with pump operabihty includmg 107 margin as a funchon of sodium pentaborate :

wwer'atm that)mgMthly testpit,) is adequajaf to detect failures solubon concentration. Tank heater and heat tracing system !

(have ocpGrred./f are provided to assure comphance with this requirement. The The only practical time to test the Standby Liquid Control set points W h h actuahon d the M Wer W System is. during a refuelog outage and by initiahon from local - heat tracog system are miahhshed haavi on the dding stahons. Components of the system are checked penodically h T w atw e W W W h W h as desenbed above and make a funchonal test of the entire span h e.in h Md mom. % opwM .is system on a frequency of more than once each refueing { checked on a frequency to assure a high rehability of operation outage urmar meary. A test of explosive charges from one of the system should it ever be required. I i

manufacturing batch is made to awre that the charges are satisfactory. A continuous check of the firing circuit continuity N154eT h is provided by pilot lights in the control room. ,

t l

I s

Amendment No. ;MI, Md -t40-109

_ _ _ _ _ _ _ . . _._m. . . ___ __. __ _ . . . . . _ . . _ _ _ _ _ _ _ _ _ . . ._. . . _ _.. _

JAFMPP /

fiJs //t T C. N 3.5 (cont'd) 45 (cat *Q

\

b. Flow Rate Test- COr)c6/3 ugadhsy

! f Core spray pumps sham deliver etleast 4,265 gun l against a system head JM

- g correspondng to a rear *w vesselpreneure greeler than or aquelto 113 poiabove primary containment .

prenews.

h PumpOperatsty Once/ month) f

d. Motor Operated (Once/monthM

. N

e. Core Spray Haartar

. @ Instrumentation Check Once/ day Calibrate Once/3 months Test Once/3 months

f. l.ogic System Once/each FunctionalTest operating cycle

g. TdmNa Check f Testedfor Valves ( operability 1

any time the reactor is in the cold condition exceedmg 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ,if operabihty tests have not been performed during h preceding 3 pays.

Amendment No. f.1 9 113 i

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ -_ - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - . - _ _ - . . - - _ _ _ -_______-________________-__________l

l

\

l

+

JAFNPP I

3.5 (cont'd)

! 4.5 (corfd) i

5. All recirt,dahnri pump discharge valves shaN be operable 5. AN recirtsdatinri pump dscharge valves shall be tested for '

prior to reactor startip (or closed if permaled elsewhere in

tese apardenharts). operabihty any time the reactor is in the cold constion arcaartrig 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , if operabsbty tests have not been

6. If the requrements of 35A cannot be met, the rancen, emng h preceeng 31 h ~

shen be placed in See cold condton washin 24 hrs. ;

h&" # Y l B. B.

Containment Cochna Mode (of the RHR System) h % h (m RHR SM

1. Both subsystems of the contenment cochng mode, each 1.

ysterns d #te N r% 6 M be i

' l includng two fHl and two RHRSW pamps, shaN be at zrgpabieby h ,

operable whenever there is irraremmari fuel in the rameenr Ly g,,,,g ;

a. a pump operabsty and Sow rate test on the RHR~j weasel, prior to startup from a cold condtion, and reactor 'i pumps (per Surveillance Requrement 4.5.A 3.

W h e 12 M mosptas W -

b.

a monthly operabsty test of the RHR contasnment p ggaa 47~ c cochng mode motor operated valves.

bl j a monthly operabsty test on the RHRSW pumps Ch g ' I rar e $ and maannmaart motor operated valves.

b i }'*.~ / #*4 "#I ,

c.2 d a Sow rate test at least once every 3 months and waC,2q a Aow rate of 4000 gpm for each p '

3 j RHRSW pump and a total Sow rate of 8000 gpm for two RHRSW pumps operating in parallel. ~ J' c

1 During each liveyear period, an air test shaN be n

f. performed on the contanment spray headers and ! !

L. nozzles. "

> I

e. (resaT S) ]

'ggWnT C Amendment No. J6, S6,19(,13(, 6 4

Isa f

w npp s

35 (Conr4 45 (Cors4 E. Ramr*w Core ladahan Coohng ARCIC) Systern E. Raarent Core enamainn s Cooling (RCIC) System

1. The RCIC Syalam shsE be operable whenever there is 1. RCIC System testme shaE be performed as foRows irrattated fuel in sie rear *v vessel and the rear 4ar provided a reactor steem supply is avadahaa. N steam is pressure is yester tien 150 peig and rear 4ar ennlant not avadaham at the time the survedance test is scMdad temperature is greater Wien 2127 encept from Wie time to be performed, the test shes be performed wehin ten that the RCIC System is made or found to be inoperable days of continuous operation from the time sleem for any reeman, consnued seactor power operation is harnmes avenetse. ouc4 eu.3 pomnameda during #se maannaarkg 7 days unless sie 97DV5 )

system is made operable essaar provided that during these hem Frequency 7 days #se W Syelemis operable.

a. Once/ operating

2. N to requirements of 35.E cannot be met, the reactor Simulated Ark'asinri (andAutomenc Restart ,) cycle sheE to pieced in the cold condblon and prosaure less Test % p g ,c r 8 then 150 peig wisiin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . ' / i

b. (pumpqmrate A C Onop/rhenWD

3. Low power physics toeling and reactor operator training shsE be permheed wth inoperable components as c. naotor Operated

@ ncef. m 9~

_M l apariend in 35.E.2 above, provided that rearent rvwdant h Operabusy

d. (Flow Rete Once/3 rnonths3 I

4. The RCIC system is not required to be operable during ^

hydrostatic pressure and leakage testing wth rear 4nr e. Wh M Tested for operabddy

" " '**C80' "

coolant temperatures between 2127 and 3007 and ""Y irrareadad fuel in the reartnr vessel provided a5 control in #m condeson

= 4 s, M rods are inserted. LashT g operability tests have I not been performed 42 during the precedng 31 .

l

f. Logc System Once/operalog l Functional Test cycle N

Automatic restart ori a low water level segnal whch is-Amendment No. f, Ih,1 479-- * %=it to a high water level taip.

r

/ 121 i .

l 1

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

The RCIC pump shall deliver at least 400 gpm for a system pgtg yg head correspondog to a reactor pressure of 1,120 psig to l (lMLottP0R M O 2. When it is determined that the RCIC System is inoperable I O , g 3 gg ;--

at a time when it is required to be operable,' the HPCI g o4 pg g1) System shall be verified to be operable immedetely and . l daily thereafter.

l l

I r

Amendment No. He-121a

I i

l JAFNPP t

l 3.5 (cont *4 4.5 (cont'd)

F. ECCS-Cold Condtion F. ECCS-Cold Constion

1. A minimum of two low pressure Emergency Core d h b possure EW systems r@M Naurig subsystems sheE be operable whenever by 31F.1 and 31F.2 shall be as fotows-irradated fuel is in Wie reactor, Wie reactor is in the /

cold W and work is being performed wth Wie 1. a Sowrate test (41 least once every 3 rnonsiD potendellordaining tieeW- n the required Core Spray pump (s) and/or the RHR pump (s). Eadi Core Spray pump shaN delswer at l

I

2. A minimum of one le preneure Emergency Core CooEng subsystem shes be operable whenever Ips/rz1-ineet 4.285 gprn aW a system head c neapondng 2 ae vessel pressure greater l'

irradated fuel is in tie reactor, Wie reactor is in the w 113 psi h pnmary N cold conditon, and no work is being portarmed whh c y pressure. Each RHR pump shad dehver at least Die potendel for &sining Wie reactor M 8910 spm agelnet a system head corresponding to a reactor vessel to primary containment differential

3. Emergency Core CooEng subsystems are not required to be operable provided that the reactor 2.

F***"M ._

Portormen montgoperatmhty test on the required veneet head is removed, tie cavity isenadarf, the Core Spray and/or LPCI motor operated vahms.

spent hael W gates are remowed, amie water

3. Once each shit verNy the suppression pool water abovetio M h h 4 level is greater tien or aquel to 10.33 ft. whenever

& 3. tac. the low preneuro ECCS subsystems are aligned to

4. wnh the requirements of 3AF.1,3AF.2, or 31F.3 i

not ==aimmad, suspend core storations and as 4. Once each shift verNy a minimum of 324 inches at l !

operations with tio potential for draining the reactor water is evetable in the Condensate Storage Tanks veneet. Restore at leset one system to operable (CST) whenever the Core Spray System (s) is abgned man = wnhin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or estennah Secondary to the tanks.

Containment integrity whhin the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

(S. f)as ,ua su mys,ua py rim ms

{ M6. (.n*+ans.,pwsoe ophoc+r4 an gg < Mar a ps Ar,c } in tw.f. me p,y .fp,s.y 6 Mor LOCMofb, Sht4b ott croWggssf SEcu e +b oa pos :riod, is ,,a ry,c coaMer POS # 71 C *4

\ & # cit. -Tshf /16424.s s ##b kIk $

Amendment No f.f.1f.1f4 L ""*lOtt to'zd ~59R*f sysnrove(s), '

- ,. - ~ .~,..-....-~,-n..,w a.--..,s.-.-.--,,.--...>>nsnu .

.sw -~, .,.- -,- ~>- s- ..saa In e

it!

2 p3! EI l Eij t Ig3# jjh l Il FH d!

Hb I

Ilef f 'I t,

4 a ; 'i

! p ly ! !!! i t ed I

w hb b l if b 5 382 22 ~

(

l 883 il l!>

l ff!

,a a N

i l l

I nll b-Ii lJ ei

! 8h hi l

glInal .

I fe I l

%o i

.-. . - - - . -.-. - - -.. -- . . . . - - . _ _ - . . -~-...- -.- . . . - -.- . -. .- -. .._. -

JAFNPP w gsg sueSistfors 3.5 (cont'd) 4.5 (cont'd) we vvW5 k.

condition, that pump shall be considered inoperable for 2. Following any period wherethe LPCI subsystess ortore) h purposes of satisfying Spacefications 3.5.A. 3.5.C, and 3.5.E. .9--Lspray sutaystemslhave not been mamtamed in a filled condition; the discharge pepmg[of the octed ystem s shall be ed from high point o the syst and

[sHm.L nt aga.uf sLD nu.a.gr> wary **# ~

so n g ,

/to svs rd pa *P br5N m se 7tr W IaiT M o^#t/4d6 presop.ro dset.ur.ed& r*6 --

(3. Whenever the HPCI or RCIC System,is lined up to take suction from the condensate storage tank, theI d S tassysrs., ,se sysrs., opgagets, prosr6. pepeng of the HPCI or RCIC shall be vented from the high j ( Rem u**C" -

point of the system, and water flow observed on a_

ea cw r4 o monthly bases. f

.a J. Aso#

k F,K The level switches located on the Core Spray and RHR N h rung] Systerp descharge pipeg high points which monitor these

{ lines t(wQthey are full shall be functionally tested

( Iuo46 w PMJavas PAG 6 y monm. osses pha. 21 o*Ys . >

~ J H. Aversoe F: nr.i Linear :' " G r r*=. 7 - (APLHGR) H. Averaae Planar Linear Heat Generation Rate (APLHGR)

During power operation, the APLHGR for each type of fuel as The APLHGR for each type of fuel as a function of average a function of axiallocation and average planer exposure shall planer exposure shall be determened daily during reactor ,

be within limits based on appbcable APLHGR limit values operation et a:25% rated thermal power.

which have been approved for the respecteve fuel and lettece types. These values are specified in the Core Operating Limits ,

Report. If at anyteme dunne reactor power operation greater .

' then 25% of rated power it is determened that the limiteng value for APLHGR is being ==emadad, action shell then be initiated within 15 manutes to restore operation to within the prescribed limits. If the APLHGR is not retumed to within the l prescribed limits within two (2) hours, the reactor power shall be reduced to less than 25% of rated power withen the next four hours, or until the APLHGR is retumed to within the prescribed limits.

,),d,1[,1/,JAd. N Amendment No. [ 123 ,

l

JAF90PP 4.5 BASES The testing intervel for Wie Core and Containment Cooling The RCIC Row rate is deactbed in the UFSAR. The Sow rates Systems is bened on a queneltallve r n.wusy analysis, industry practice, judgement, and practicailty. The Emergency Core to be delivered to the ra r4rw core for HPCI, the LPCI mode of RHR, and CS are bee 6d on the SAFER /GESTR LOCA analysis,

]i 4

i!

CooEng Systems hees not been designed to be fugy smalmNa The Bow rates for the LPCI mode of RHR and CS are modified during operation. For amarnpin, Wie core spray Snel admission by a 10 percent rarteninni Irom the SAFER /GESTR LOCA valves do not open untB seactor pressure has lagen to 450 peig; analysis. The rartchans are haamri on a 5(Cfi analysis i thus, during operadon even N hiWi drywse preneure were (General Electric MDE834786) performed for the parameters i simulated, the Snel values wodd not open. In the case of the usedin the SAFER /GESTR anafysis. j HPCI, automatic initiation durin0 power opereelon would reedt

"" "UI The CS surveitance requirement includes an aBowance for system leakage in arirening to the Row rate required to be I delivered to the reactor core. The leak rate from the core spray The systems wW be automaticap y arem durin0 a refueling piping inside the reactor but outside the core shroud is h; outage. In the case of Sie Core Spray System, condensate assumed in the UFSAR and irweh a known loss of less than L storage tank water wig be pumped to tie veneel to verify the_ 20 gun Irorn the 1/4 incit dameter vent hole in the core spray

--;+-r -'; of tie we w=d - ^-JTo increene the T-bou connocean in each of the loops, and in the B loop, a T of the indvidued of tie and potential adtStional loss of less than 40 gpm from a clamsheE i Cochng Systems cornponents mefes up the repair whose structural weld covers only 5/6 of the f; i.e., pumps, etc., Iseted circumference of the pipe. Both of these identified sources of

. The l

more is tested -

leakage occur in the space between the reactor vessel waN and

! each the and motor aled valves 3

are also the core shroutL Therefore Sow lost through these leak (

ends aneure . The sources does not cenertute to core cooling. y'

" FThe survelRance requirements to ensure that the discharge velve is deerned be W e ssang '

l d h system [s J piping of the core spray, t.PCI mode of the RHR, HPCI, and i RCIC Systems are Sued provides for a visual observahon that ' '

With components or missystems out-of-service, overaN core water Sows from a high point vent. This ensures that and containment cooEng reanNuty is maintained by venlying J

the operabiNty of the remaining moung equipment. Consistent with the deAnluon of operable in Mar 41nn 4.0.C demonstrate means conduct a test to show; verily means that the d

associated surveigance activities have been - ^ " -%ily JM# g " /W>in To performed within the specilled time interval.

gy7 peg Amendment No. }/,1[,-204--

132

e N '

\-

I 2 m,d,- )

l 4.5 BASES (cord *d) the line is in a full condinon[Between the monthly intervals at_I _

_ fcgpt+c4 W r-h 7 i wtuch the lines are vented, instrumentatxm has been provided in f the Core Spray System and LPCI System to monitor the #

l presence of water in the discharge piping. This instrumentation ~

l l (will be calibrated instrumerdmainrt This onoenod the same of penodic frequency testing as the safety ensures that system IasSrcu m f,,rer d iMs N8 **

fg g I during the interval between the monthly checks the status 3 Y###I TNN 4 ^8 h L pc.p discharge piping is monitored on a conhnuous StS, '

l Normally the low pressure ECCS subsystems required by

] 8"

{" P rs c4 of.

fmu g, Es Specificahon 3.5.F.1 are demonstrated operable by the " "30 M 'tf N5rso surveiRance tests in Speci5 cations 4.5.A.1 and 4.5.A 3. Section m o %I ,,,, #" M WM 4.5.F specifies periodic surveiNance tests for the low pressure "

f ECCS subsystems which are appncable when the reactor is in j

1 the cold condition. These tests in conjunction with the requirements on fi5ed discharge piping (Specifx:ation 3.5.G),

(}n.o9sMs ca g,p, apoa up f and the requirements on ECCS actuation instrumentation M*O NU#N D (Specincat;en 32.B), assure adequate ECCS capability in the CAL B(2. Anv4 o.(. INS r/2 u w/*3rA;70a/

cold condition. The water level in the suppressbn pool, or the Condensate Storage Tanks (CST) when the suppression pool is TW-ser sMcut b r/ W L gg y g,f g g inoperable, is checked once each shift to ensure that sometent 4 PH T~

wateris available for core cooling.

oF Amsond g u 3 7 b

b Amendment No. [

1,3

. . . . - - . . . . . - . . . - . . - . . . . . . . . . . . . . . . . _ . . . . . ~ . . - . - . _ . . . . . . . . . _

! e li t M

un !, ?.

! [] ~d .o I3 e l n! [

ll' ji f I !

3

!!i i

j !i i

l l(q"}ijD((ltl list 31 3 til Ill 1.j alhl 4a c + ni b n!

i 5 s c- 3

$ @!1 l 0

3

' g I11111ll!!

l III!b.j!jill I

il f lli li hl

11Indj'{ti>i i! il t

! L Illhinlli,j

11. .

(;

Z 1 '

W i 1 a

i

. . . - - -- . _ _ . _ _ _ _ - - _ - _ _ _ _ - _ _ _- - __ _-__ -__ -__ N

JAFNPP 3.7 (cont'd) 4.7 (cont'd) breaker is sooner made operable, provided that the ,

repeer procedure does rm violate primary ccatamment inesytty.

Pressure Suppression Chamber - DryweN Vacuum 5. Pressure Suppression Chamber - Drywet Vacuum 5.

Breakers Brookers When primary containment integnty is required, all s. Each drywe5 suppression chamber vacuum breaker a.

dryweN = . . :":7 chamber vacuum breakers shall shall be exercised through an opening - closing cycle

be operable and positioned in the fuNy closed {monttdy.} zuserc ,

position c.,t dming testmo and = ;:-; e in 3.7.A.5.b below.

b. One dryweg = . ; :::':-3 chamber vacuum breaker b. When it is determened that one vacuum breaker is -

may be non-fdy closed so long as it is determined inoperable for futy closing when operabHity is to be not more then 1

open as indicated by the required, the operable breakers shen be exercised immediately, and every 15 days thereafter until the position lights. -

moperable velve has been retumed to normal service.

One dryweN suppression chamber vacuum breaker c. (Once each operating c each vacuum breaker I c. valve shall be visually inspected to insure proper may be determined to be inoperable for opening. ._

moentenance and operation?

{

I

d. A leek test of the drywet to suppression chamber l . d. Deleted '

structure shell be conducted once per operating

, J -

.4454 W O cycle; the acceptable look rate is 50.25 in.

waterknin, over a 10 min period, with the drywell at 1 paid. ;

i t

Amendment No.1 . t90--

178

_ _ ~ . _ . . _ _ _ - . . ~ _ . _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ . _ .__ _ =_

JAFNPP .-

?-

3.7 (cont'd)

~;

4.7 (cont'd) '

c. Secondary contanment capabildy to mantan a 1/4 in. of water vacuum under calm wind condrhons with a fiher train now rate of not more tien 6,000 cim, shau be demonstrated at each refuehng outage prior to refuehng D. Pnmary Contanment lasiation Valves D. Pri=w Cop **gmani ke8% Vir

1. Whenever pdmary containment insegnty is required per 1. The pnmary contanment solagen valves survenance 3.7.A.2. containment isolation valves and ag instrument shag be performed as follows-line excess now check valves shs3 he operable, .freM_ "

.- M*N/

except as speciSed in 3.7.D.2. The containment vent and purgo valves shag be Emited to openmg angles

{a.

Et least once nor anaragma cyctOthe operable rQg isolamon valves that are power operated and less than or aquel to that aparMart below: automabcaEy watated shall be tested for O L j !

Vahm Numhar samdated automabc watahon and for closure naamanum Opem"ng Angle time.

. 27AOV-111 4Er

27AOV-112 40" b.

27AOV-113 At least once per operating cycle, the instrument ywEr i

' 40" line excess How check valves shag be tested for i d o l 27AOV-114 50" proper operation." -

27AOV-115 50*

27AOV-116 50" c. "

F At least once per quarter:)

27AOV-117 50*

27AOV-118 50* CW6, f-012 W D (1.) AE normaEy open poww-operated kahman vafves (except for the main streanfline and g j(

Haector Buiking Closed Loop Coolmg g 3 Trvw1 4 a W 62a#"'/ ~

Water System (RBCLCWS1 power-operatedisciamen valves) shaN be fuBy closed and reopened.

The current survedance interval for testing instrument line excess now check vafves is I !!

extended unta the end of the R11C12 refueing j outage scheduled for January,1995. This is a f one-time extensson, effective only for this survenance interval. The next survedance /.

interval will begm upon completion of this A v survedance.

4 eno.,eni uo. m.

185

JAFNPP #548T C S* ** fnfsued 3.7 (cont'd) 4.7 (cont'd) d (2.) With the reactor at a reduced power level close e.ch main steam isolation valve, one at a L time, and verify closure time.

s Q k ht leasMwice per weeV the main steam line power-operated isolation valves shaN be exercised by partial closure and =%w reopenmg. -

e. The RBCLCWS isolation valves shall be fully closed i and reopened any time the reactor is in the cold condition exceeding 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , if the valves have not been fully closed and reopened during the preceding 92 days.

2. With one or more of the containment isolation valves 2. Whenever a containment isolation valve is inoperableS inoperable, maintain at least one inciation valve operable position of at least one other valve in each isne having an in each affected penetration that is open and: inoperable valve shall be recorded daily.

a. Restore the inoperable valvoisi to operable status # #

within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or " " ** " ## " * * ""MA

~

b. Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the closed poestion. Isolation valves -

closed to satisfy these requirements may be /H A M 5 9 /R. d e 7. h. 2- co e 5 < s ru r reopened on an intermittant basis under administrative control; or )

j

' ID * D

- - Wi-f VA M

c. Isolete each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed menuel valve or a blind g, - -

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

Amendment No. , [4,1[ }d2 186

. - . . . . _ . . - _ _ - . _ . _ ~ - - - . .

e l

l 3AF88PP

\

l 4.7 BASES icont'd) operability results in a more r.kaham system.

! The qsain steem line isolpaion velves are functionally tested on l a r ore frequent interval to esteldish a high degree of l rostulity.

The primary containment le penetrated by several small diameter instrument lines connected to the reactor cooient system. Each instrument line containe a 0.25 in. restricting

. orifice inside the primary containment and an excess now l check volve aammida the primary containment.

L

. [The RSCLCWS volves ars ==chadad fatwn the quarterfy surveillance requirements hacasaam closure of those vehms will eliminate the cocient flow to the dryweg air and recirculation .

pumgHnotar coolers. Without corJing water, the dryweg air and equipment temperature wiu increene and may cause damage to the equipment during normal plant operations. f l

Therefore, testing of these vefwes would only be conducted in the cold condition. ;

I A list of containment isolation velves, including a brief

-i : *J:- . of each velve is iriehadad in Section 7.3 of the I updated FSAR. $hD , - g g .Bh 6' 5 #'" A--

( Pa, - y u, n a a r. y ,u rain ~ s ~ a w Ad isopa rouc isoe m a use,c lua m us) +ns

\[ g1 w ef.,,.w, ,cx . ,, rW

, , w o,a s

$Utfi N b Yo rF#s!d T~4ri fif/&rpA-FMd fLuel Po*-FA l g gpo/

W" i < >0wm> ousa m t. m s us,a rw + red b 4 t- r s e 4 + st:Sh rwp,gog A-u y1 -n+rS ,. 'd A'Sh Rhb W 4 AK'F t A-Tim an 4 f sac 9 4 rt s s a et 4 p r; } t o r n

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Amendment No. If, [ N 197 li

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

D. Emeroency Service Water System D. Emeroency Service Water System

1. To ensure adequate equipment and area cooling, both 1. Surveillance of the ESW system shall be performed as ESW systems shall be operable when the requirements of follows:

specification 3.5.A and 3.5.8 must be satisfied, except as specified below in specification 3.11.D.2. 11mm Frecuency

a. Simulated Automatic ating cycle Actuation Test g

b. Flow Rate Test - Each ESW (Once/3 months]

pump shall deliver at least '

b' I

1500 gpm to its respective loop. The pump total developed I

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head shall be greater then or equal p to the corresponding point on the (}

pump curve, reduced by a maximum ,

r2 of 7%, for the n== red flow. I frHW D 1

_[ Pump Operability Once/ month]

d. Motor Operated Valves (Once/ month]

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Amendment No. [,1/4 fe3--

240

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Attachment III to JPN-95-053 MARKUP OF TECHNICAL SPECIFICATION PAGES INSERTS (Pg. 1 of 3)

Ins ert ... A E. Surveillance Requirements for inservice testing of

-components shall be applicable as follows:

1. Inservice-testing of pumps and valves shall be performed in accordance with Section XI.of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(f), except where specific written relief has been requested to the NRC pursuant to 10 CFR 50, Section 50.55a (f) (6) (i) .

The inservice testing and inspection program is based on an NRC approved edition of, and addenda to,Section XI of the ASME Boiler and Pressure Vessel Code which is in effect 12 months or lesc prior to the beginning of the inspection interval.

2. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice testing activities required by the Code and applicable Addenda shall be applicable as defined in Technical Specification 1.0.T.

3. The provisions of Specification 4.0 B 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 shall be. construed to supersede the requirements of any Technical Specification.

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Attachment III to JPN-95-053 MARKUP OF TECHNICAL SPECIFICATION PAGES INSERTS (Pg. 2 of 3)

Insert B Verify each valve (manual, power operated, or once per 31 automatic) in the system flowpath that is not Days locked, sealed or otherwise secured in position, is in the correct position.

Insert C In accordance with the Inservice Testing Program.

Insert D periodic testing in accordance with the IST Program is adequate to detect if degradation has occurred. Valves in the system flowpath are-verified to be in the proper position on a monthly l I

basis. This requirement does not apply to explosive valves or to valves that cannot be inadvertently misaligned, such as check valves. Verifying the correct alignment of manual, power operated, or automatic valves in the system flowpath provides assurance that the proper flowpath will exist for system operation.- The monthly frequency is based on engineering judgement and is supported by procedural controls governing valve operation that ensure correct valve positions.

Insert E Flow Rate Test - The RCIC pump shall deliver at Once per 92 least 400 gpm against a system head Days corresponding to a reactor vessel pressure of 1120 psig to 150 psig.

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,4 Attachment III to JPN-95-053 i

! MARKUP OF TECHNICAL SPECIFICATION PAGES 1

i !

4 INSERTS J (Pg. 3 of 3) r Insert F l On a monthly basis, correct alignment shall be verified for.

manual, power operated, or automatic valves in ECCS and RCIC

System flow paths to provide assurance that proper flow paths will exist-for system operation. For the HPCI and RCIC Systems,

.this requirement also includes the steam flow path for the

. turbines and the flow controller position. This surveillance ;

requirement does not-apply to valves that cannot be inadvertently i _ misaligned such as check valves, or to valves that are locked, i sealed,.or otherwise secured in position. A valve that receives an initiation signal is allowed to be in a non-accident position provided'the valve will automatically reposition in the proper stroke time upon receipt of the ini'tiation signal. The monthly i frequency of this requirement :bs based upon engineering judgement I l and is supported by procedural controls governir.g valve operation that ensure correct valve positions. This frequency is further ;

. supported by the Inservice Testing Program, which demonstrates i j system pump and power operated valve operability. This combination of automatic actuation tests, periodic pump and valve /

' testing, and monthly flow path verification is adequate to demonstrate operability of these systems.

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ML20095F709

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