ML17278A967

Proposed Tech Specs Re ECCS Actuation Instrumentation & Motor Operated Valve Thermal Overload Protection

ML17278A967
Person / Time
Site:	Columbia
Issue date:	08/04/1986
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17278A966	List: GO2-86-732, Supplemental Application for Amend to License NPF-21, Revising Tech Specs Re ECCS Actuation Instrumentation & Motor Operated Valve Thermal Overload Protection ML17278A967
References
TAC-59820, NUDOCS 8608130374
Download: ML17278A967 (8)

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INSTRUMENTATION 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUHEHTATION Lii4IITING CONOITION FOR OPERATION 3.3.3 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2 and with EMERGENCY CORE COOLING SYSTB/ RESPOHSE TII<E as shown in Table 3.3.3-3.

APPLICABILITY:

As shown in Table 3.3.3-1.

ACTIQN:

C.

With an ECCS actuation instrumentation channel trip setpoint less conservative

.han the value shown in the Allowable Values column of Table 3.3.3"2, declare the channel incperable until the channel is restored to OPERABLE status with its trip setpoint ad'us ed consis ent'i h the Trip Setpoint value.

With one or more ECCS actuation instrumentation channels inoperable, take the ACTiOH required by Table 3.3.3-1.

With either AOS trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status:

tS Within 7 days, provided that the HPC sys.em

~ OPERABLE; otherwise, 2,

Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Otherwise, be in at least HOT SHUTOOWN within the next 12 hcurs and reduce reactor s

earn dome pressur e to less han or equal to 128 psig within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REOUIREi~1ENTS 4.3.3.1 Each ECCS ac.uation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHAHNEL FUNCTIONAL TEST, and CHANNEL CALIBRAT'IQH cperations for the OPERATIONAL CONOITIONS and at the

",eouencies shcwn in Table 4.3.3.1-1.

4. 3, 3. 2 LOGiC SYSTEH FUNCTIONAL TESTS and s imulated automatic cperati cn cf all channels snail be performed at least onc per 18 months.

~.3.3.3 The ECCS R'ESPONSE TIIIE of each ECCS trip unc ion shown in Table 3.3.3-3 shall be demonstrated to be wi.hin the limit at Ieas once per 18 months.

Each test shall include at lezs one channel per trip system such that all channels are tested a

least once every H times 1S months where H is the total number of reaundant channels in z specific ECCS :r'.'p system.

WA HINGTGN NUC'AR - UNIT 2 3/4

-2B 8608130374 860804 PDR ADDCK 0500039'7 P

PDR

EMERGENCY CORE COOLING SYSTEMS LIMITING CONDITION FOR OPERATION Continued ACTION:

a.

For ECCS division 1, provided that ECCS divisions 2 and 3 are OPERABLE:

1.

Mith the LPCS system inoperable, restore the inoperable LPCS system to OPERABLE status within 7 days.

2.

Mith LPCI subsystem "A" inoperable, restore the inoperable LPCI subsystem "A" to OPERABLE status within 7 days.

b.

3.

Mith the LPCS system inoperable and LPCI subsystem "A" inoperable, restore at least the inoperable,'L'PCI subsystem "A" or the inoperable LPCS system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

4.

Otherwise, be in at least POT) SHUTOOHN 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 wit/in the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

For ECCS division 2, providedPthat ECCS divisions 1 and 3 are OPERABLE:

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With either LPCI subsystem "B" or "C" inoperable, restore the inoperable LPCI sub'system "B" or "C" to OPERABLE status within 7 days.

2.

Mith both LPCI)subsystems "B" and "C" inoperable, restore at least the i'noperable LPCI subsystem "B" or "C" to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

3.

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 />".

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For ECCS division 3, provided that ECCS divisions 1 and 2 ~~the~

1)

With ECCS division 3 inoperable, restore the inoperable division to OPERABLE status within 14 days.

2)

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 />.

d.

For ECCS divisions 1 and 2, provided that ECCS division 3 is OPERABLE:

1)

Mith LPCI subsystem "A" and either LPCI subsystem "B" or "C" inoperable, restore at least the inoperable LPCI subsystem "A"

or the inoperable LPCI subsystem "B" or "C" to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

"Whenever two or more RHR subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant tempei ature as low as practical by use of alternate heat removal methods.

WASHINGTON NUCLEAR - UNIT 2 3/4 5-2

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4 aGNilRGLLED GG TABLE 3.8. 4. 3-1 MOTOR OPERATED YALYES THERMAL OVERLOAD PROTECTION SYSTEM(S)

YALVE NUMBER AFFECTED SYSTEM(S)

VALVE NUMBER

,AFFECTED.

a 0 C.

d.

e.

CAC-V-2 CAC-Y-4 CAC"V-6 CAC-Y-8 CAC-V"11 CAC-V"13 CAC"V-15 CAC-V-17 CIA-V-20 CIA"V-30A CIA-V-30B FPC-V-149 FPC-V"153 FPC-V-154 FPC-V-156 FPC"V-172 FPC"V-173 F PC-V-175 F PC-V"181A F PC-V-181B F PC-V-184 HPCS-V-1 HPCS-V"4 HPCS-V"10 HPCS-V"ll

'HPCS" Y"12 HPCS" V-15 HPCS"V-23 LPCS"V-1 LPCS-V"5 LPCS-FCV"11 LPCS"V-12 HS-V-1 MS"V-2 MS"V-5 MS-V-16 HS-V-19 MS-V-20 HS-V"67A MS"V-67B HS-V"67C HS-V-67D HS"V"146 Containment Atmospheric Control System Containment Instrument Air System Fuel Pool Cooling System High Pressure Core Spray System Low Pressure Core Spray System Main Steam System g.

MSLC-V-lA MSLC"V-1B MSLC-V-1C MS LC-V-.10 MSLC"V-2A MSLC-V-2B MSLC-Y-2C MSLC-V"2D HSLC-V-3A MSLC"V-3B MSLC-V"3C MSLC-Y-3D MSLC-Y-4 MSLC-V-5 MSLC-Y"9 MS LC"V"10 h.

RCC-V-5 RCC-V-21 RCC-V-40 RCC-V-104 RCC-V-129 RCC"V-130 RCC-V"131 RCIC"V-8 Hain Steam Isolation Valve Leakage Control System Reactor Closed Cooling Water System eY-LaPVe, lH Reactor Core Isolation Cooling "

System

'DE,LE;TK WASHINGTON NUCLEAR " UNIT 2 3/4 8"26 Amendment No.

27

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'ABLE 3.8.4.3-1 (Continued)

MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION SYSTEM(S)

VALVE NUMBER, AFFECTED VALVE NUMBER SYSTEM(S)

AFFECTED RCIC-V RCIC-V j.

RFW-V-65A RFM"V-65B k.

RHR"V-3A RHR-V-3B RHR-V-4A RHR-V"4B RHR"V"4C

.RHR"V-6A RHR-V-6B RHR-V-8 RHR-V"9 RHR"V"16A RHR-V-16B RHR-V-17A RHR-V"17B RHR-V-21 RHR-V-23 RHR-V-24A RHR-V-24B RHR"V"27A RHR"V"27B RHR-V-40 RHR-V-42A RHR"V"42B Reactor Core Isolation Cooling System GK-LEAvE. 1Q Reactor Feedwater System Residual Heat Removal System RHR-V"42C RHR-V-47A RHR-V"47B RHR"V"48A RHR"V-48B RHR-V-49 RHR"V-53A RHR"V"53B RHR-V-64A RHR"V"64B RHR-V"64C RHR"V"68A RHR"V"68B RHR"V"73A RHR-V-73B RHR-V-74A RHR-V-74B RHR-V"115 RHR-V"116 RHR"V"123A RHR-V"123B RHR"V"134A RHR"V-134B RRC-V;16A RRC-V-16B RMCU-V-1.

RMCU"V"4 RMCU-V"40 Reactor Recirculation System Reactor Mater Cleanup System MASHINGTON NUCLEAR - UNIT 2:

3/4 8-27 I

I Amendment No. 27

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