ML20045H920

Amend 192 to License DPR-59,revising Certain TS LCO Action Statements to Adopt Consistent Terminology for Action Statements

ML20045H920
Person / Time
Site:	FitzPatrick
Issue date:	07/12/1993
From:	Capra R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20045H921	List: ML20045H920 ML20045H929
References
NUDOCS 9307220114
Download: ML20045H920 (17)

Text

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ft UNITED STATES o

[I*k(.j NUCLEAR REGULATORY COMMISSION

's WASHINGTON. D.C. 20E0001

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POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENPMENT TO FACILITY OPERATING LICENSE Amendment No.192 License No. DPR-59 1.

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

A.

The application for amendment by Power Authority of the State of New York (the licensee) dated February 25, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I;

~

l B.

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

There is reasonable assurance (i) that the activities authorized

)

by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations-D.

The issuance of this amendment will not be inimical to the common I

defense and security or to the health and safety of the public; and E.

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:

l 9307220114 930712 PDR ADOCK 05000333 P

PDR

\\

i

T (2)

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 192, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION wa.(p Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - I/II Of# ice of Nuclear Reactor Regulation

Attachment:

Changes to the Technical

• Specifications Date of Issuance: July 12,1993

=.

1 ATTACHMENT TO LICENSE AMENDMENT NO.192 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 1

Revise Appendix A as follows:

Remove Paaes Insert Paces l

42 42 65 65 77d 77d 107 107 123 123 124 124 124b 124b 142 142 178 178 180a 180a 186 186 217 217 238 238 241 241 1

k l

i t

A

s.

JAFNPP TABLE 3.1-1 (cont'd)

REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Minimum No.

Modes in Which Function of Operable Must be Operable Total Number of la estrument instrument Channels Channels per Refuel Startup Run Provided by Design Action Trip System (1)

Trip Function Trip Level Setting (6) )16) for Both Trip Systems (1) 4 Turbine Stop s10% valve X(4)(5) 8 Instrument Channels A or C Valve Closure closure NOTES OF TABLE 3.1-1

1. There shall be two operable or tripped trip systems for each function, except as specified in 4.1.D.

From and after the time that the minimum number of operable instrument channel for a trip system cannot be met, that affected trip system shall be placed in the safe (tripped) condition, or the appropriate actions listed below shall be taken.

A. Insert all opereble control rods within four hours.

l B. Reduce power level to IRM range and place Mode Switch in the Start;p Position within eight hours.

C. Reduce power level to less than 30 percent of rated within four hours.

l

2. Permissible to bypass, if Refuel and Shutdown positions of the Reactor Mode Switch.

3. Deleted.

4. Bypassed when turbine first stage pressure is less than 217 psig or less than 30 percent of rate.

5. The design permits closure of any two lines without a scram being initiated.'

6. When the reactor is subcritical and the reactor water temperature is less than 212*F, only the following trip functions need to be Cperable:

A. Mode Switch in Shutdown.

B. Manual Scram.

1M,1-[,192 Amendment No.

42

JAFNPP TABLE 3.2-1 (Cont'd)

INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION NOTES FOR TABI c 3.2-1

1. Whenever Primary Containment integrity is required by Section 3.7, there shall be two operable or tripped trip systems for each function.

2. From and after the time it is found that the first column cannot be met for one of the trip systems, that trip system shall be tripped or the appropriate action listed below shall be taken.

A. Place the reactor in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B. Isolate the main steam lines within eight hours.

C. Isolate Reactor Water Cleanup System within four hours.

D. Isolate shutdown cooling within four hours.

3. Deleted

4. Deleted

5. Two required for each steam line.

6. These signals also start SBGTS and initiate secondary containment isolation.

7. Only required in run mode (interlocked with Moda Switch).

8. Bypassed when mode switch is not in run mode and turbine stop valves are closed.

9. The trip level setpoint will be maintained at s3 times normal rated full power background. See note 16 to Table 3.1-1 for re-setting trip level setpoint just prior to and following the Hydrogen Addition Test.

Amendment No.[f,k,)d,1[,1[9, d

192 65

JAFNPP TABLE 3.2-8 (Cont'd)

ACCIDENT MONITORING INSTRUMENTATION NOTES FOR TABLE 3.2-8 A. With the number of operable channels less than the required minimum, either restore the inoperable channels to operable status within 30 days, or be in a cold condition within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B. With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirements, initiate an altemate method of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and: (1) either restore the inoperable channel (s) to OPERABLE status within 7 days of the event, or (2) prepare and submit a Special Report to the Commission within 14 days following the event outlining the cause of the inoperability, the action taken, and the plans and schedule for restoring the system to OPERABLE status.

C. Each Safety / Relief Valve is equipped with two acoustical detectors, one of which is in service. Each SRV also has a backup thermocouple detector. In the event that a thermocouple is inoperable, SRV performance shall be monitored daily with the associated in service acoustical detector.

D. From and after the date that both of the acoustical detectors are inoperable, continued operation is permissible until the next outage in which a primary containment entry is made provided that the thermocouple is operable. Both acoustical detectors shall be made operable prior to restart.

E. In the event that both primary (acoustical detectors) and secondary (thermocouple) indications of this parameter for any one valve are disabled and neither indication can be restored in forty-eight (48) hours, the reactor shall be in a Hot Shutdown condition within twelve (12) hours and in a Cold Shutdown within the next twenty-four (24) hours.

F. Refer to Specification 3.7.A.9.

1 G. This parameter and associated instrumentation are not part of post-accident' monitoring.

H. This instrument shall be operable in the Run, Startup/ Hot Standby, and Hot Shutdown modes.

J. This instrument shall be operable in the Run and Startup/ Hot Standby modes.

Am:ndment No. [1,192 77d

JAFNPP 3.4 (Cont'd) 4.4 (Cont'd)

C.

Sodium Pentaborate Solution C.

Sodium Pentaborate Solution The standby liquid control solution tank shall contain a boron The availability of the proper boron bearing solution shall be bearing solution with a minimum enrichment of 34.7 atom verified by performance of the following tests:

percent of B-10 that satisfies the volume-concentration requirements of Fig. 3.4-1 at all times when the Standby 1.

At least once oer month -

Liquid Control System is required to be operable and the solution temperature including that in the pump suction pioing Boron concentration shall be determined. In addition, the shall not be less than the temperature presented in Fig. 3.4-2.

boron concentration shall be determined any time water Tank heater and the heat tracing system shall be operable or enriched sodium pentaborate is added or if the solution whenever the SLCS is required in order to maintain solution temperature drops below the limits specified by temperature in accordance with Fig. 3.4-2. If these Fig. 3.4-2.

requirements are not met, restore the system to the above limits within eight hours or take action in accordance with 2.

At least once oer day -

Specification 3.4.0.

Solution volume and the solution temperature shall be checked.

3.

At least once per coeratino cycle -

a.

The temperature and level elements shall be calibrated.

b.

Enrichment of B-10 (in atom percent) shall be checked.

D.

If specifications 3.4.A through C are not met, the reactor shall D.

Not Used l

l be in at least hot shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Am:ndment No. 1%,192 107

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

Following any period where the LPCI subsystems or core purposes of satisfying Specifications 3.5.A, 3.5.C, and 3.5.E.

spray subsystems have not been maintained in a filled condition; the discharge piping of the affected subsystem shall be vcnted from the high point of the system and water flow observed.

3.

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

4.

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

H.

Averaae Planar Linear Heat Generation Rate (APLHGR)

H.

Averaoe 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 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.

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 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 l

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

Amendment No. [

Jfd,Jd,1[,1[, JBI,196,192 123

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

Linear Heat Generation Rate (LHGR) 1.

Linear Heat Generation Rate (LHGR)

The linear heat generation rate (LHGR) or any rod in any fuel The LHGR shall be determined daily during reactor operation at assembly at any axial location shall not exceed the maximum 2:25% rated thermal power.

allowable LHGR specified in the Core Operating Limits Report.

If anytime during reactor power operation greater than 25% of rated power it is determined that the limiting value for LHGR is being exceeded, action shall then be initiated within 15 minutes to restore operation to within the prescribed limits. If the LHGR 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 four hours, or until the LHGR is returned to within the prescribed limits.

Am:ndment No. [f,[ 1ps,1)d,192 d

124

JA?NPP 3.5 (cont'd) 2.

Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after completing an increase in thermal power of 5 percent or more of rated thermal power.

b.

If the APRM and LPRM neutron flux noise levels are greater than 5 percent and greater than three times their established baseline noise levels, initiate corrective action within 15 minutes to restore the noise levels to within the required limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, by increasing core flow and/or ieducing thermal power.

3.

If during single-loop operation, core thermal power is greater than the limit define-I by line A of Figure 3.5-1, and core flow is less than 39 percent, immediately initiate corrective action to restore core thermal power and/or core flow to within the limits, specified in Figure 3.5-1, by increasing core flow and/or initiating an orderly reduction of core thermal power by inserting control rods.

4.

The requirements applicable to single-loop operation in Specifications 1.1.A, 2.1.A. 3.1.A. 3.1.B, 3.2.C and 3.5.H shall be in effect within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following the removal of one recirculation loop from service, or the reactor shall be placed in at least the hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Am:ndment No. g,192 124b b

JAFNPP 3.6 (cont'd) 4.6 (cont'd) 5.

With the Primary Containment Sump Monitoring System 3.

Drywell Continuous Atmosphere Radioactivity Monitoring (Equipment Drain Sump Monitoring or Floor Drain Sump System instrumentation shall be functionally tested and Monitoring) inoperable, restore the system to operable calibrated as specified in Table 4.6.2.

status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in the cold condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

6.

With the Primary Containment Atmosphere Radioactivity Monitoring System (gaseous) or the Primary Containment Atmosphere Radioactivity Monitoring System (particulate) inoperable, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Otherwise be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Am:ndment No. g,)HI, J62, 192 142

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

5.

Pressure Suppression Chamber - Dryweli Vacuum 5.

Pressure Suppression Chamber - Drywell Vacuum Breakers Breakers a.

When primary containment integrity is required, all a.

Each drywell suppression chamber vacuum breaker drywell suppression chamber vacuum breakers shall shall be exercised through an opening - closing cycle be operable and positioned in the fully closed monthly.

position except during testing and as specified in 3.7.A.5.b below.

b.

One drywell suppression chamber vacuum b.eaker 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 l' 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 returned to normal service.

c.

One drywell suppression chamber vacuum breaker c.

Once each operating cycle, each vacuum breaker may be determined to be inoperable for opening.

valve shall be visually inspected to insure proper maintenance and operation.

l d.

Deleted

,d.

A leak test of the drywell to suppression chamber structure shall be conducted once per operating cycle; the acceptable leak rate is s0.25 in.

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

Amendment No. [4,-192 178

r JAFNPP 3.7 (Cont'd) 4.7 (Cont'd)

(1) This differential pressure shall be established within a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period subsequent to placing the reactor in the run mode. The differential pressure may be reduced to less than 1.7 psid 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a scheduled shutdown.

(2) The differential pressure may be decreased to less than 1.7 psid for a maximum of four (4) hours during required operability testing of the HPCI, RCIC, and Suppression Chamber -

Drywell Vacuum Breaker System.

(3) If the specifications of item a, above, cannot be met, and the differential pressure cannot be restored within the subsequent six (6) hour l

period the reactor shall be in a Hot Shutdown condition in six (6) hours and a Cold Shutdown condition in the following eighteen (18) hours.

8.

If the specifications of 3.7.A.1 through 3.7.A.6 cannot 8.

Not applicable.

be met the reactor shall be in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

\\

t Am:ndment No. g,192 180a

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

(2.) With the reactor at reduced power level, trip main steam isolation valves and verify closure time.

d.

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

e.

The RBCLCWS isolation valves shall be fully closed and reopened any time the reactor is in the cold condition exceeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if 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 inoperable, the inoperable, maintain at least one isolation valve operable position of at least one other valve in each line having an in each affected penetration that is open and:

inoperable valve shall be recorded daily.

a.

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

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

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

3.

If Specifications 3.7.D.1 or 3.7.D.2 cannot be met the 3.

Not Used

[

I reactor shall be in the cold condition within 24 hrs.

, 1)i/4, 1 [ 3, 192 Am:ndment No. 1 186

. = -

(

JAFNPP 3.9 (cont'd) 4.9 (cont'd) 3.

From and after the time that one of the Emergency Diesel 3.

The emergency diesel generator system instrumentation Generator Systems is made or found to be inoperable, shall be checked during the monthly generator test.

continued reactor operation is permissible for a period not to exceed 7 days provided that the two incoming power sources are available and that the remaining Diesel Generator System is operable. At the end of the 7 day period, the reactor shall be placed in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless the affected diesel generator system is macc operable sooner.

4.

When both Emergency Diesel Generator Systems are 4.

Once each operating cycle, the conditions under which made or found to be inoperable restore at least one the Emergency Diesel Generator System is required will system to operable status within two hours or place the be simulated to demonstrate that the pair of diesel reactor in the cold condition within the following 24 generators will start, accelerate, force parallel, and hours.

accept the emergency loads in the prescribed sequence.

l 5.

Deleted 5.

Once within one hour and at least once per twenty-four hours thereafter while the reactor is being operated in accordance with Specifications 3.9.B.1,3.9.B.2, or 3.9.B.3 the availability of the operable Emergency Diesel Generators shall be demonstrated by manual starting and force paralleling where applicable.

T Amnndment No. g,g,Jgl',1)d, go,192 217

JAFNPP 3.11 (cont'd) 4.11 (cont'd) i ventilation air supply fan and/or filter may be out of b.

Di-octylphtalate (DOP) test for particulate filter service for 14 days.

efficiency greater than 99% for particulate greater l

than 0.3 micron size.

l c.

Freon-112 test for charcoal filter bypass as a measure of filter efficiency of at least 99.5% for halogen removal.

d.

A sample of charcoal filter shall be analyzed once a year to assure halogen removal efficiency of at least 99.5%.

2.

The main control room air radiation monitor shall be 2.

Operability of the main control room air intake radiation operable whenever the control room emergency monitor shall be tested once/3 months.

ventilation air supply fans and filter trains are required to be operable by 3.11.A.1 or filtration of the control room ventilation intake air must be initiated.

3.

The control room emergency ventilation system shall not 3.

Temperature transmitters and differential pressure be out of service for a period exceeding 3 days during switches shall be calibrated once/ operating cycle.

normal reactor operation or refueling operations. In the event that the system is not returned to service within 3 days, the reactor snail be in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and any handling of irradiated fuel, core alterations, and operations with a potential for draining the reactor vessel shall be suspended as soon as practicable l

4.

Not Used 4.

Main control room emergency ventilation air supply system capacity shall be tested once every 18 months to assure that it is i10% of the design value of 1000 cfm.

Am:ndment No.1/,1[,192 4

238

7-.

i..

JAFNPP 3.11 (cont'd) 4.11 (cont'd) e ESW Once/ day instrumentation-Once/3 months check calibrate test Once/3 months f.

Logic System Once/each Functional Test operating cycle 2.

From and after the time that one Eme e Service 2.

ESW will not be supplied to RBCLC system during a

Water System is made or found to tn - arable for any testing.

reason continued reactor operation ir *.missible for a l

period not to exceed 7 days, provided that:

the operable Emergency Diesel Generator System is demonstrated to be operable immediately and daily thereaf ter; ar d, all Emergency Diesel Generator System emergency loads are verified operable immediately and daily thereafter.

I 3.

If specification 3.11.D.2 cannot be met the reactor shall 3.

Not Used l

l be placed in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Am:ndment No.1jts,192 241