Text

Amend 96 to License NPF-21, Revising Tech Specs 3.3.7.5, Accident Monitoring Instrumentation & 3.4.2, Safety/Relief Values Concerning Acoustic Monitor Operating Requirements
	ML17286B195
Person / Time
Site:	Columbia
Issue date:	11/29/1991
From:	Virgilia M; Office of Nuclear Reactor Regulation
To:	;
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ML17286B196	List: ML17286B195; ML17286B197;
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	NUDOCS 9112180137
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50>>397 NUCLEAR PROJECT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

96 License No. NPF-21 1.

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

A.

The application for amendment by the Washington Public Power Supply System (the licensee) dated November 25, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

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

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 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 requlations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operatinq License No. NPF-21 is hereby amended to read as follows:

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Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised throuqh Amendment No. 96 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Hartin J. Virqilio, Assistant Director for Reqions IV and V

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Requlation

Attachment:

Chanqes to the Technical Specifications Date of Issuance:

November 29, 1991

I S

ENCLOSURE TO LICENSE AMENDMENT NO. 96 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the followinq paqes of the Appendix "A" Technical Specifications with the enclosed paqes.

The revised paqes are identified by amendment number and contain vertical lines indicatinq the areas of chanqe.

The correspondinq overleaf paqes are also provided to maintain document completeness.

REMOVE 3/4 3-71 3/4 4-7a INSERT 3/4 3-71 3/4 4-7a

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TABLE 3.3.7. 5-1 ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT 1.

Reactor Vessel Pressure 2.

Reactor Vessel Water Level 3.

Suppression Chamber Water Level 4.

Suppression Chamber Water Temperature 5.

Suppression Chamber Air Temperature 6.

Drywell Pressure 7.

Drywell Air Temperature 8;

Drywell Oxygen Concontration 9.

Drywell Hydrogen Concentration 10.

Safety/Relief Valve Position Indicators 11.

Suppression Chamber Pressure 12.

Condensate Storage Tank Level REQUIRED NUMBER OF CHANNELS 2/sector 2/val ve*

MINIMUM CHANNELS OPERABLE 1/sector 1/valve APPLICABLE OPERATIONAL CONDITIONS 1,

2 1,

2 1 ~

2 1,

2 ACTION 80 80 80 80 80 80 80 80 80 80 80 13.

Main Steam Line Isolation Valve Leakage Control System Pressure 2

1 1,

2 80

NOTE - The acoustic monitor for MS-RV-4D may be inoperable until the seventh Refueling Outage, scheduled for no later than May 15, 1992, or until the first forced outage of sufficient duration to effect repair/

replacement prior to that date, without applying the shutdown requirement of Action 80.a.

TABLE 3.3. 7. 5-I (Continued)

ACC IOENT HONITOR ING INSTRUNEHTATION INSTRUNENT 14.

Neutron Flux:

APRH I

IRH C

SRH 15.

RCIC Float 16.

HPCS Flet 17.

LPCS Flet 18.

Standby Liquid Control Systea Fine 19.

Standby Liquid Control Systea Tank Level 20.

RHR Flat 21.

RHR Heat Exchanger Outlet Teeperature CLa I+

O 22.

Standby Service Mater Fled 23.

Standby Service Mater Spray Pond Teeperature 24.-

25.

Eeergency Ventilation Damper Posftion 26.

Standby Pmer and Other Energy Sources 27.

Priaary Contafneent Valve Position 28.

Primary Contafneent Gross Radiation Honftorsf 29.

30.

Effluent Noble Gas Radiation Monitored I

31.

Reactor Sufldfng Post LOCA Grab Sampler REqUIREO NUMBER OF CHANNELS 2

2 2

1 1

1 1/loop 1/heat exchanger 1/loop 2

2/duct 2/source 1/valve 2

HININN CHANNELS OPERABLE 1

I, 2 1

1, 2 1

,1, 2 1

1f 2 1

1. 2 1

1, 2 1

1e 2 1/loop 1, 2 1/heat 1, 2 exchanger 1/loop 1

1, 2 1o 2 80 80 80 80 80 80 80 80 80 80 80 80 1/duct 1/source 1/line 1

1, 2 1,2 1,2 1, 2, 3 80 80 80 81 le 2e 3

1, 2, 3 81 81 APPLICABLE OPERATIONAL CONOITION5 ACTIOH NHigh range wenitors.

TABLE 3.3.7.5-1 (Cont)nued)

ACC IDENT MONITORING INSTRUMENTATION INSTRUMENT n

14.

Neutron Flux:

APRM I

IRM SRM 15.'CIC Floe 16.

HPCS Flmt 1?.

LPCS Flow 18.

Standby Uqufd Control Systea Flm 19.

Standby Uqu)d Control System Tank Level 20.

RHR Flee 21.

RHR Heat, Exchanger Outlet Temperature 22.

Standby Serv)ce Mater Flme 23.

Standby Serv)ce Mater Spray Pond Tewperature 24.

25.

Eeergency VenUlatfon Daeper Pos)tton 26.

Standby P~r and Other Energy Sources 27.

Primary Contafneent Valve Posit)on 28.

PHaary Containment Gross Radiation Non)torsi g

290 30.

Effluent Noble Gas lad)ation Non)tort 31.

Reactor Bu)ldlng Post LOCh Grab Sampler NH)gh range monitors.

REqUIREO NUMBER OF CHANNELS 2

2 2

1 1

1 1/loop 1/heat exchanger I/loop 2

2/duct 2/source 1/valve 2

'MINIMUM CHANNELS OPERABLE 1

1,2 1

1, 2 1

.1e 2 1

10 1

1,2 1

1I 2 1

1e 2 1/loop 1, 2 1/heat 1, 2 exchanger 1/loop 1

1,2 1,2 80 80 80

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80 80 80 80 80 80 80 1/duct 1/source 1/leone 1

I, 2 1,2 1,2 1, 2, 3 80 80 80 81 1, 2, 3 1, 2, 3 81 81 APPLICABLE OPERATIONAL CONDITIONS ACTION

REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY/RELIEF VALVES LIMITING CONDITION FOR OPERATION ACTION:

(Continued) valve(s) within 2 minutes or if suppression pool average water tempera-ture is 110'F or greater, place the reactor mode switch in the Shut-down position.

C.

With one or more safety/relief valve acoustic monitors inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .***

SURVEILLANCE RE UIREMENTS 4.4.2 The acoustic monitor for each safety/relief valve shall be demonstrated OPERABLE by performance of a a.

CHANNEL CHECK at least once per 31 days, and a

b.

CHANNEL CALIBRATION at least once per 18 months.**

- The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure is adequate to perform the test.

- - The acoustic monitor for MS-RV-4D may be inoperable until the seventh Refueling Outage, scheduled for no later than May 15, 1992, or until the first forced outage of sufficient duration to effect repair/replacement prior to that date, without applying the shutdown requirement.

WASHINGTON NUCLEAR - UNIT 2 3/4 4-7a Amendment No. N,96

REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.3.1 The following reactor coolant system leakage detect5on systems shall be OPERABLE:

a.

The prfmary contafnment atmosphere gaseous radfoact5vfty aonftorfng

system, b.

The primary contafnment sump flow aonftorfng system, and c.

The primary containment atmosphere particulate radfoactfvfty monitoring system.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

fifth only two of the above required leakage detection systems

OPERABLE, operation may continue for up to 30 days provided grab samples of the con-tainment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the required gaseous and/or partfculate radioactive monitoring system fs inoperable; otherwise, be fn at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE RE UIREMENTS 4.4.3.1 The reactor coolant system leakage detection systems shall be demonstrated OPERABLE by:

a.

Primary containment atmosphere particulate and gaseous monitoring syste-.,

performance of a CHANNEL CHECK at leas

. >nce per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a

CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

b.

Pr fmary containment sump flow monftorfng system-performance of a CHANNEL FUNCTIONAL TEST at, least once per 31 days and a CHANNEL CALIBRATION TEST at least once per 18 months.

WASHINGTON NUCLEAR - UNIT 2

REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEH LEAKAGE LEAKAGE DETECTION SYSTEKS UNITING CONDITION FOR OPERATION 3.1.3.l Thc followtng reactor coolant systci leakage detcctfon systcas sha11 bc OPERABLE:

~

a.

The prfmary-contafnment atmosphere gaseous radfoactfvfty oonftorfng system,,

I b.

The primary contafnmcnt sump tlow aonftorfng system, end c.

The primary contafnment atmosphere partfcu1ate radfoactfvfty monitoring system.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

fifth only two of the above requfrcd leakage detection systems

OPERABLE,

'peratfon may continue for up to 30 days provfded grab samp1cs of the con-tainment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the required gaseous and/or particulate radioactive monitoring system fs inoperable; otherwfse, be fn at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the fo11owfng 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE RE UIREHENTS 4.4.3.1 The reactor coolant systci liakage detectfon systems shall be demonstrated OPERABLE by:

a.

Primary containment atmosphere particulate and gaseous Nonftorfng systems-performance of 0 CHANNEL CHECK at lcas.

>nce. per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a

CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 aonths.

b.

Prfmary containment sump flow aonftorfng system-performance of CHANNEL FUNCTIONAL TEST at least once Per 31 days and a CHANNEL CALIBRATION TEST at least once per 18 months.

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ML17286B195

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