Text

Amend 26 to License NPF-21,revising Tech Spec Table 3.6.3-1, Primary Containment Isolation Valves to Reflect Corrections & Additions to & Deletions from Listed Items
	ML17278A858
Person / Time
Site:	Columbia
Issue date:	05/23/1986
From:	Adensam E; Office of Nuclear Reactor Regulation
To:	;
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ML17278A859	List: ML17278A858; ML17278A860;
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	TAC-60953, NUDOCS 8605300359
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t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 26 License No. NPF-21 1.. The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment filed by the Washington Public Power Supply System (the Supply System, also the licensee),

dated January 17, and supplemented on February 18,

1986, 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 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 set forth in 10 CFR Chapter I; 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 regulations and all applicable requirements have been satisfied.

2.

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

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

26, 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.

Bb05300359 Bb0M3 PDR ADOCK 05000397 p

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3.

This amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION E~A Elinor G. Adensam, Director RMR Pro,iect Directorate No.

3 Division of BWR Licensina

Enclosure:

Chanaes to the Technical Specifications Date of Issuance:

May 23, 1986

I

ENCLOSURE TO LICENSE AMENDMENT NO. 26 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

REMOVE INSERT 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 V111 6-22 6-23 6-24 6-25 6-26 6-27 6-28 6-29 6-30 6-31 6-32 6-33 6-34 6-35 6-36 6-37 6-38 6-39 6-40 6-41 6-42 6-43 6-44 V111 3/4 6-22 3/4 6-23 3/4 6-24 3/4 6-25 3/4 6-26 3/4 6-27 3/4 6-28 3/4 6-29 3/4 6-30 3/4 6-31 3/4 6-32 3/4 6-33 3/4 6-34 3/4 6-35 3/4 6-36 3/4 6-37 3/4 6-38 3/4 6-39 3/4 6-40 3/4 6-41 3/4 6-42 3/4 6-43 3/4 6-44 3/4 6-45

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INDEX 1

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4. 6. 1 PRIMARY CONTAINMENT Pr imary Containment Integr ity.........................

Primary Containment Leakage.....

Primary Containment Air Locks.........................

MSIV Leakage Control System...........................

Primary Containment Structural Integrity..............

Drywell and Suppression Chamber Internal Pressure.....

Drywell Average Air Temperature.

Drywell and Suppression Chamber Purge System..........

3/4.6.2 DEPRESSURIZATION SYSTEMS S uppressson Chamber Suppression Pool and Drywell Spray....................

Suppression Pool Cooling.....

3/4 6"1 3/4 6-2 3/4 6"5 3/4 6-7 3/4 6-8 3/4 6"9 3/4 6"10 3/4 6-11 3/4 6-13 3/4 6-17 3/4 6-18 3/4.6,3 PRIMARY CONTAINMENT ISOLATION VALVES..................

3/4 6-19 3/4. 6.4 VACUUM RELIEF Suppression Chamber - Drywell Vacuum Breakers.........

Reactor Building - Suppression Chamber Vacuum Breakers........................................

~.

~

3/4.6.5 SECONDARY CONTAINMENT Secondary Containment Integrity.......

Secondary Containment Automatic Isolation Valves......

Standby Gas Treatment System..........................

3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL 3/4 6-34 3/4 6-36 3/4 6"38 3/4 6-39 3/4 6-41 Drywell and Suppression Chamber Hydrogen Recombiner Systems..

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

Drywell and Suppression Chamber Oxygen Concentration..

3/4 6-44 3/4 6-45 WASHINGTON NUCLEAR - UNIT.2 v111 Amendment No. 26

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VALVE FUNCTION AND NUMBER TABLE 3.6.3-1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES VALVE GROUP(a)

MAXIMUM ISOLATION TIME (Seconds)

Automatic Isolation Valves (Continued)

Equipment Drain (Radioactive)

EDR-V-19 EDR-V-20 Floor Drain (Radioactive)

FDR-V-3 FDR-V-4 Fuel Pool Cooling/Suppression Pool Cleanup FPC"V-149 FPC-V-153(f)

FPC-V"154(f)

FPC-V-156 Reactor Recirculation Hydraulic Control(e)

HY-V-17A,B HY-V-18A,B HY-V-19A,B HY"V"20A,B HY-V-33A,B HY-V-34A,B HY-V"35A,B HY-V-36A,B Traver sing Incore Probe TIP-V-1,2,3,4,5 15 15 35 15

-)

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VALVE FUNCTION AND NUMBER TABLE 3.6. 3-1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES VALVE GROUP(a)

MAXIMUM ISOLATION TIME (Seconds) ao Automatic Isolation Valves (Continued)

Reactor Closed Cooling RCC-V-5 RCC-V"21 RCC-V-40 RCC-V-104 Radiation Monitoring Supply 5 Return P I-VX-250 PI-VX-251 P I-VX-253 PI-VX-256 PI-VX-257 PI-VX-259 Residual Heat Removal RHR-V-123A,B(g)

RHR-V-8(g)

RHR-V-9(g)

RHR"V-23(g)

RHR-V-53A,B(g)

RHR-V-24A,B(c)

RHR-V-21 RHR-V-27A,B(c)

Reactor Water Cleanup System RWCU-V-l(d)

RWCU-V-4 5

6 6

10 10 10 60 15 40 40 90 40 270 270 36 30(j) 21(j)

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VALVE FUNCTION AND NUMBER TABLE 3. 6. 3-1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES VALVE GROUP a)

MAXIMUM ISOLATION TIME (Seconds) a.

Automatic Isolation Valves (Continued)

Reactor Core Isolation Cooling RCIC-V-8 RCIC-V-63 RCIC-V-76 Low Pressure Core Spray LPCS-V-12 High Pressure Core Spray HPCS-V"23 b.

Excess Flow Check Valves(e)

Containment Atmosphere PI-EFC-X29d PI-EFC-X29f'I-EFC-X30a PI-EFC-X30f PI-EFC-X42c PI"EFC-X42$

PI-EFC-X61c PI-EFC-X62b PI-EFC"X69f PI-EFC-X78a 10 13(j) 16(j) 22 180 180 N.A.

VALVE FUNCTION AND NUMBER TABLE 3.6. 3-1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES VALVE GROUP(a)

MAXIMUM ISOLATION TIME (Seconds) b.

Excess Flow Check Valves (e) (Continued)

Containment Atmosphere (Continued)

PI-EFC-X66 PI-EFC-X67 PI-EFC-X82b PI-EFC-X84a PI-EFC-X86A,B PI-EFC-X87A, B PI"EFC-X119 Reactor Pressure Vessel PI-EFC-X18A,B, C,D PI-EFC-X37e,f PI-EFC-X38a,b,c,d,e,f PI-EFC-X39a, b, d, e PI-EFC-X40c,d PI-EFC-X4lc, d PI-EFC-X42a,b PI-EFC-X44Aa,Ab,Ac,Ad,Ae,Af,Ag,Ah,Aj, Ak,Al,Am PI-EFC-X44Ba,Bb,Bc,Bd,Be,Bf,Bg,Bh,Bj, Bk,Bl,Bm PI-EFC-X61a,b PI-EFC-X62c,d PI-EFC-X69a, b, e PI-EFC-X70a,b,c,d,e,f PI-EFC-X71a,b,c,d,e, f PI-EFC-X72a PI-EFC-X73a PI-EFC-X74a, b, e, f N.A.

N.A.

VALVE FUNCTION AND NUMBER TABLE 3.6.3-1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES VALVE GROUP(a)

MAXIMUM ISOLATION TIME (Seconds)

C.

Excess Flow Check Valves (e) (Continued)

Reactor Pressure Vessel (Continued)

PI-EFC-X75a,b,c,d,e, f PI-EFC-X78b,c, f PI-EFC-X79a, b PI-EFC-X106 PI-EFC-X107 PI-EFC-X108 PI-EFC-X109 PI-EFC-X110 PI-EFC-Xlll PI-EFC-X112 PI-EFC-X113 PI-EFC-X114 PI-EFC-X115 Other PI-EFC-X40e, f PI-EFC-X41e, f Manual Containment Isolation Valves Demineralized Water DW-V-156 DW-V-157 Containment Air System CAS-VX-82e CAS-V-730 N.A.

N.A.

/

VALVE FUNCTION ANO NUMBER TABLE 3. 6. 3-1 (Continued PRIMARY CONTAINMENT ISOLATION VALVES VALVE GROUP a)

MAXIMUM ISOLATION TIME Seconds C.

Manual Containment Isolation Valves (Continued)

Service Air SA-V-109 Residual Heat Removal RHR-V-llA,B RHR-V-120 RHR-V-121 RHR-V-124A, B RHR-V-125A,8 Reactor Core Isolation Cooling RCIC-V-64 RCIC-V-742(g)(b)

Air Supply to Testable Check Valves N.A.

N.A.

~Ait Su 1

PI-VX-42d PI"VX-216 PI-VX-69c PI-VX-221 PI-VX-611 PI-VX-219 PI-VX-54Bf PI-VX-218 Check Valve RHR-V-50A RHR-V-50B RHR-V-41A RHR-V-41B

VALVE FUNCTION AND NUMBER TABLE 3.6.3-1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES VALVE GROUP(a)

MAXIMUM ISOLATION TIME (Seconds)

C.

Manual Containment Isolation Valves (Continued)

Air Supply to Testable Check Valves (Continued)

PI-VX-62f RHR-V-41C PI-VX-220 N.A.

LPCS-V-66 LPCS-V-67 HPCS-V-65 HPCS-V-68 RCIC-V-184 RCIC-V-740 LPCS-V-6 HPCS-V-5 RCIC-V-66 d.

Other Containment Isolation Valves Main Steam Leakage Control(b)

MSLC-V-3A,B,C,D Reactor Feedwater/RWCU Return RFW-V-10A,B RFW-V-32A,B RFW-V-65A)B RWCU-V-40 High Pressure Core Spray HPCS-V-4(g)(b)

HPCS-V-5(g)(b)

HPCS-V-12 HPCS-V-15(f)(b)

N.A.

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VALVE FUNCTION AND NUMBER TABLE 3.6.3-1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES VALVE GROUP(a)

MAXIMUM ISOLATION TIME Seconds) n foal I

Col CFI ItO O

Ol d.

Other Containment Isolation Valves (Continued)

High Pressure Core Spray (Continued)

HPCS-RV-14(e) (h)

HPCS-RV-35(e)(h)

Low Pressure Core Spray LPCS-V-1(f)(b)

LPCS-V-5(g)(b)

LPCS-V-6(g)(b)

LPCS-RV-18(e)(h)

LPCS-RV-31(e) (h)

LPCS-FCV-11 Standby Liquid Control SLC-V-7 SLC-V-4A,B Reactor Core Isolation Cooling RCIC-V-13(g)(b)

RCIC-V-19 RCIC-V-28 RCIC-V-31(f)(b)

RCIC-V-40 RCIC-V"66(g)(b)

RCIC-V-68 RCIC-V-69 N.A.

N.A.

VALVE FUNCTION ANO NUMBER TABLE 3.6.3-1 (Continued PRIMARY CONTAINMENT ISOLATION VALVES VALVE GROUP a)

MAXIMUM ISOLATION TIME Seconds) d.

Other Containment Isolation Valves (Continued)

Residual Heat Removal/Low Pressure Injection RHR-V-4A,B,C(f)(b)

RHR-V-16A,B RHR"V-17A,B RHR-V-41A,B(g)(b)

RHR-V-42A,B,C(g)(b)

RHR-V-SOA,B(g)(b)

RHR-V-73A,B RHR-V-134A,B(c)

RHR-V"209(g)(b)

RHR-RV-lA,B(e) (h)

RHR-RV-5(e)(h)

RHR-RV-25A,B,C(e)(h)

RHR-RV-30(e)(h)

RHR-RV-36(e)(h)

RHR-RV-SSA,B,C(e)(h)

RHR-FCV-64A,B,C Containment Atmosphere Control(c)(i)

(Hq Recombiner)

CAC-V-2 CAC-FCV-2A,B CAC-V-15 CAC"FCV-1A,B CAC"V-11 N.A.

N.A.

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TABLE 3.6.3-1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER d.

Other Containment Isolation Valves (Continued)

Containment Atmosphere Control(c)(i)

(Hq. Recombiner)

(Continued)

CAC-Y-6 CAC-V-4 CAC-FCV-4A,B CAC-V-13 CAC-V-17 CAC-FCV-3A,B CAC-V-8 CSP-V"5 CSP-V-6 CSP-V-7 Containment Purge System CSP-V-8 CSP-V-9 CSP-V-10 Reactor Recirculation (Seal Injection)

RRC-V-13A,B RRC-V-16A,B Containment Instrument Air CIA-V"20 CIA-V-21 VALVE GROUP(a)

MAXIMUM ISOLATION TIME (Seconds)

N. A.

N.A.

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VALVE FUNCTION AND NUMBER TABLE 3. 6. 3-1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES VALVE GROUP(a)

MAXIMUM ISOLATION TIME Seconds d.

Other Containment Isolation Valves (Continued)

Containment Instrument Air (Continued)

CIA-V-30A,B CIA-V"31A,B N.A.

Post-Accident Sampling System(c)

PSR-V-X73-1 PSR-V-X73-2 PSR-V-X77A1 PSR-V-X77A2 PSR-V-X77A3 PSR-V-X77A4 PSR-V-X80-1 PSR-V-XBO-2 PSR"V-X82-1 PSR-V-X82-2 PSR-V-X82-7 PSR-V-X82-8 PSR-V-X83-1 PSR-V-X83-2 PSR-V-X84-1 PSR-V-X84-2 PSR-V-X88-1 PSR-V-X88-2 N.A.

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TABLE 3.6.3-1 (Continued)

PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER d.

Other Containment Isolation Valves (Continued)

Radiation Monitoring PI-EFCX"72f PI-EFCX-73e Transversing Incore Probe System TIP-V-6 TIP-V-7,8,9,10,11(e)

-VALVE GROUP(a MAXIMUM ISOLATION TIME Seconds)

N.A.

TABLE NOTATIONS "But greater than 3 seconds.

PProvisions of Technical Specification 3.0.4 are not applicable.

(a)

See Technical Specification 3.3.2 for the isolation signal(s) which operate each group.

(b)

Valve leakage not included in sum of Type B and C tests.

(c)

May be opened on an intermittent basis under administrative control.

(d)

Not closed by SLC actuation signal.

(e)

Not subject to Type C Leak Rate Test.

(f)

Hydraulic leak test at 38.2 psig.

(g)

Not subject to Type C test.

Test per Technical Specification 4.4.3.2.2 (h)

Tested as part of Type A test.

(i)

May be tested as part of Type A test.

If so tested, Type C test results may be excluded from sum of other Type B and C tests.

(j)

Reflects closure times for containment isolation only.

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'ONTAINMENT SYSTEMS 3/4.6.4 VACUUM RELIEF SUPPRESSION CHAMBER - DRYWELL VACUUM BREAKERS LIMITING CONDITION FOR OPERATION 3.6.4.1 Each pair of suppression chamber - drywell vacuum breakers shall be OPERABLE and closed.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

'a ~

b.

C.

With one or more vacuum breakers in one pair of suppression chamber-drywell vacuum breaker s inoperable for opening but known to be

closed, restore the inoperable pair of vacuum breakers to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 .

With one suppression chamber

- drywell vacuum breaker open, verify the other vacuum breaker in the pair to be closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; restore the open vacuum breaker to the closed position within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 .

With one position indicator of any suppression chamber - drywell vacuum breaker inoperable:

l.

Verify the other vacuum breaker in the pair to be closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and at least once per 15 days thereafter, or 2.

Verify the vacuum breaker(s) with the inoperable position indicator to be closed by conducting a test which demonstrates that the hP is maintained at greater than or equal to 0.5 psi for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months without makeup within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once per 15 days thereafter.

3.

Otherwise, 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 .

WASHINGTON NUCLEAR - UNIT 2 3/4 6-34 Amendment No.

26

CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS 4.6.4. 1 Each suppression chamber - drywell vacuum breaker shall be:

a 0 b.

Verified closed at least once per 7 days.

Demonstrated OPERABLE:

l.

At least once per 31 days and w'ithin 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after any discharge of steam to the suppression chamber from the safety/relief valves, by cycling each vacuum breaker through at least one complete cycle of full travel.

2.

At least once per 31 days by verifying both position indicators OPERABLE by observing expected valve movement during the cycling test.

3.

At least once per 18 months by; a)

Verifying the opening setpoint, from the closed position, to be less than or equal to 0.5 psid, and b)

Verifying both position indicators OPERABLE by performance of CHANNEL CALIBRATION.

WASHINGTON NUCLEAR UNIT 2 3/4 6-35 Amendment No. 26 I

'ONTAINMENT SYSTEMS REACTOR BUILDING - SUPPRESSION CHAMBER VACUUM BREAKERS LIMITING CONDITION FOR OPERATION 3.6.4.2 All reactor building - suppression chamber vacuum breakers shall be OPERABLE and closed.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3

ACTION:

a ~

b.

C.

With one reactor building - suppression chamber vacuum breaker in-operable for opening but known to be closed, restore the inoperable vacuum breaker to OPERABLE status with 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN with 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 .

With one reactor building - suppression chamber vacuum breaker

open, verify the other vacuum breaker in the line to be closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; restore the open vacuum breaker to the closed position within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN with 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 .

With one position indicator of any reactor building - suppression chamber vacuum breaker inoperable, restore the inoperable. position indicator to OPERABLE status within 14 days or verify the 'vacuum breaker to be closed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by visual inspection.

Otherwise, declare the vacuum breaker inoperable 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 .

SURVEILI ANCE RE UIREMENTS 4.6.4.2 Each reactor building - suppression chamber vacuum breaker shall be:

a.

Verified closed at least once per 7 days.

b.

Demonstrated OPERABLE:

2.

At least once per 31 days by:

a)

Cycling each vacuum breaker through at least one test cycle.

b)

Verifying both position indicators OPERABLE by observing expected valve movement during the cycling test.

At least once per 18 months by:

a)

Demonstrating that the force required to open each vacuum breaker relying upon differential pressure to open does not exceed the equivalent of 0.5 psid.

b)

Visual inspection.

c)

Verifying both position indicators OPERABLE by performance of a CHANNEL CALIBRATION WASHINGTON NUCLEAR UNIT 2 3/4 6-36 Amendment No. 26

}

CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) 3.

By demonstrating the vacuum breaker actuation instrumentation OPERABLE by performance of a:

a)

CHANNEL FUNCTIONAL TEST at least once per 31 days.

. b)

CHANNEL CALIBRATION at least once per 18 months.

MASHINGTON NUCLEAR - UNIT 2 3/4 6-37 Amendment No.

26 I

III

CONTAINMENT SYSTEMS 3/4. 6. 5 SECONDARY CONTAINMENT SECONDARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.5.1 SECONDARY CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3, and ".

ACTION:

Without SECONDARY CONTAINMENT INTEGRITY:

a.

In OPERATIONAL CONDITION 1, 2, or 3, restore SECONDARY CONTAINMENT INTEGRITY within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 .

b.

In OPERATIONAL CONDITION ", suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.6.5.1 a ~

b.

C.

SECONDARY CONTAINMENT INTEGRITY shall be demonstrated by:

Verifying at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that the pressure within the secondary containment is less than or equal to 0.25 inch of vacuum water gauge.

Verifying at least once per 31 days that:

1.

All secondary containment equipment hatches and blowout panels are closed and sealed.

2.

At least one door in each access to the secondary containment is closed.

3.

All secondary containment penetrations not capable of being closed by OPERABLE secondary containment automatic isolation dampers/valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic dampers/valves secured in position.

At least once per 18 months:

1.

Verifying that one standby gas treatment subsystem will draw down the secondary containment to greater than or equal to 0.25 inch of vacuum water gauge in less than or equal to 120 seconds, and 2.

Operating one standby gas treatment subsystem for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and maintaining greater than or equal to 0.25 inch of vacuum water gauge in the secondary containment at a flow rate not exceeding 2240 cfm.

When 1rrad)ated fuel is being handled in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

WASHINGTON NUCLEAR - UNIT 2 3/4 6-38 Amendment No.

26

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CONTAINMENT SYSTEMS SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.5.2 The secondary containment ventilation system automatic isolation valves shown in Table 3.6.5.2-1 shall be OPERABLE with isolation times less than or equal to the times shown in Table 3.6.5.2-1.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3 and ".

ACTION:

With one or more of the secondary containment ventilation system automatic isolation valves shown in Table 3. 6. 5. 2-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months either:

a.

Restore the inoperable valves to OPERABLE status, or b.

Isolate each affected penetration by use of at least one deactivated valve secured in the isolation position, or c.

Isolate each affected penetration by use of at least one closed manual valve or blind flange.

Otherwise, in OPERATIONAL CONDITION 1, 2, or 3, 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 .

Otherwise, in OPERATIONAL CONDITION *, suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

The provisions of Specifica-tion 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.6.5.2 Each secondary containment ventilation system automatic isolation valve shown in Table 3.6.5.2-1 shall be demonstrated OPERABLE:

a 0 b.

C.

Prior to returning the valve to service after maintenance,

repair, replacement work is performed on the valve or its associated

actuator, control, or power circuit by cycling the valve through at least one complete cycle of full travel and verifying the specified isolation time.

During COLD SHUTDOWN or REFUELING at least once per 18 months by verifying that on a containment isolation test signal each isolation valve actuates to its isolation position.

By verifying the isolation time to be within its limit when tested pursuant to Specification 4. 0. 5 Amendment No.

26 I

When irradiated fuel is being handled in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

WASHINGTON NUCLEAR - UNIT 2 3/4 6-39

TABLE 3. 6. 5. 2-1 SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION VALVES VALVE FUNCTION MAXIMUM ISOLATION TIME (Seconds 1.

Reactor Building Ventilation Supply Valve ROA-V-1 2.

Reactor Building Ventilation Supply Valve ROA-V-2 3.

Reactor Building Ventilation Exhaust Val ve REA-V-1 4.

Reactor Building Ventilation Exhaust Valve REA-V-2 10 10 MASHINGTON NUCLEAR " UNIT 2 3/4 6-40 Amendment No.

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CONTAINMENT SYSTEMS STAND BY GAS TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.6.5.3 Two independent standby gas treatment subsystems shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3 and ".

ACTION:

a

~

b.

With one standby gas treatment subsystem inoperable, restore the inoperable subsystem to OPERABLE status. within 7 days, or:

1.

In OPERATIONAL CONDITION 1, 2, or 3, be in at least HOT SHUTDOWN within th'e 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 .

, 2.

In OPERATIONAL CONDITION ", suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

The provi-sions of Specification

3. 0. 3 are not applicable.

With both standby gas treatment subsystems inoperable in OPERATIONAL CONDITION ", suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS or operations with a potential for draining the reactor vessel:

The provisions of Specification 3.0.3.

are not applicable.

SURVEILLANCE RE UIREMENTS

4. 6. 5. 3 Each standby gas treatment subsystem shall be demonstrated OPERABLE:

a.

At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers

'and verifying that the subsystem operates for a least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters OPERABLE.

"When irradiated fuel is being handled in the secondary, containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

WASHINGTON NUCLEAR - UNIT 2 3/4 6"41 Amendment No.

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CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued b.

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber

housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the subsystem by:

1.

Verifying that the subsystem satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than

0. 05K and uses the test procedure guidance in Regulatory Posi-tions C. 5. a, C. 5. c, and C. 5.d of Regulatory Guide l. 52, Revision 2, March 1978, at a system flow rate of 4457 cfm + lOX.

2..

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 0.175K; and 3.

Verifying a subsystem flow rate of 4457 cfm + 10K during system operation when tested in accordance with ANST N510-1980.

C.

d.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C. 6. b of Regulatory Guide l. 52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 0. 175K.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 8 inches water gauge while operating the filter train at a flow rate of 4457 cfm + lOX.

2.

Verifying that the filter train starts and isolation dampers open on each of the following test signals.

a.

Manual initiation-from the control

room, and b.

Simulated automatic initiation signal.

3.

Verifying that the filter cooling bypass dampers can be manually opened and the fan can be manually started.

4.

Verifying that the heaters dissipate 20.7 + 2. 1 kW when tested in accordance with ANSI N510-1980.

WASHINGTON NUCLEAR - UNIT 2 3/4 6-42 Amendment No.

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CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued e.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter bank satisfies the inplace penetration and bypass leakage testing acceptance criteria of less than 0.05K in accordance with ANSI N510-1980 while operating the system at a flow rate of 4457 cfm + 10'.

f.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the inplace penetration and bypass leakage testing acceptance criteria of less than 0.05K in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 4457 cfm + lOX.

WASHINGTON NUCLEAR - UNIT 2 3/4 6-43 Amendment No. 26 l

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CONTAINMENT SYSTEMS 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL DRYWELL AND SUPPRESSION CHAMBER HYDROGEN RECOMBINER SYSTEMS LIMITING CONDITION FOR OPERATION 3.6.6.1 Two independent drywell and suppression chamber hydrogen recombiner systems shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2.

ACTION:

With one drywall and suppression chamber hydrogen recombiner system snoperable, restore the inoperable system to OPERABLE status within 30 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 .

SURVEILLANCE RE UIREMENTS 4.6.6. 1 Each drywell and suppression chamber hydrogen recombiner system shall be demonstrated OPERABLE:

a.

At least once per 6 months by verifying during a recombiner system warmup test that the minimum recombiner heater outlet temperature increases to greater than or equal to 500 F within 90 minutes.

b.

At least once'per 18 months by:

2.

3.

Performing a

CHANNEL CALIBRATION of all recombiner operating instrumentation and control circuits.

Verifying the integrity of all heater electrical circuits by per forming a resistance to ground test within 30 minutes following the above required functional test.

The resistance to ground for any heater'hase shall be greater than or equal to 10,000

ohms, Verifying during a recombiner system functional test that, upon introduction of 1X by volume hydrogen in a.140-180 scfm stream containing at least lX by volume oxygen, that the catalyst bed temperature rises in excess of 120'F within 20 minutes.

Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiner enclosure; i.e., loose wiring or structural connections, deposits of foreign materials, etc.

c.

By measuring the system leakage rate:

2.

As a part of the overall integrated leakage rate test required by Specification 3.6

~ 1.2, or By measuring the leakage rate of the system outside of the containment isolation valves at P

, 34e7 psig, on the schedule required by Specifiation 4.6. 1.2, and including the measured leakage as a part of the leakage determined in accordance with Specification 4.6.1.2.

WASHINGTON NUCLEAR UNIT 2 3/4 6-44 Amendment No.

26

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CONTAINMENT SYSTEMS DRYWELL AND SUPPRESSION CHAMBER OXYGEN CONCENTRATION LIMITING CONDITION FOR OPERATION 3.6.6.2 The drywell and suppression chamber atmosphere oxygen concentration shall be less than 3.5X by volume.

APPLICABILITY:

OPERATIONAL CONDITION 1", during the time period:

a 0 Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is greater than 15K of RATED THERMAL POWER, following startup, to b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing THERMAL POWER to less than 15K of RATED THERMAL POWER, preliminary to a scheduled reactor shutdown.

ACTION:

With the oxygen concentration in the drywell and/or suppression chamber exceeding the limit, restored the oxygen concentration to within the limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least STARTUP within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE RE UIREMENTS 4.6.6.2 The oxygen concentration in the drywell and suppression chamber shall be verified to be within the limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is greater than 15K of RATED THERMAL POWER and at least once per 7 days thereafter.

See Special Test Exception 3.10.5.

WASHINGTON NUCLEAR - UNIT 2 3/4 6"45 Amendment No. 26 I

v t e Letter Sequence Other
TAC:60953, (Open)
Initiation Request, Request Acceptance... Administration Meeting Questions Answers Results Approval Other: GO2-83-553, Recommends Deletion of All Refs to RHR Steam Condensing Sys from Encl Interim Deficiency Rept 216 Re RHR Relief Valve Vents.Steam Condensing Mode of RHR Sys Will Be Deactivated, ML17278A582, ML17278A603, ML17278A858, ML20236Y131
MONTHYEAR1986-02-18 [Table View]

ML17278A858

Text

Enclosure:

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