ML17292A910

From kanterella
Jump to navigation Jump to search
Amend 150 to License NPF-21,revising TS SR 3.3.1.1.15,RPS Response Time Functions 3 & 4 & SR 3.3.6.1.7,PCIS Response Time,Functions 1.a,1.b & 1.c,adding Note to Indicate That Sensor Excluded
ML17292A910
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 06/11/1997
From: Colburn T
NRC (Affiliation Not Assigned)
To:
Shared Package
ML17292A911 List:
References
NUDOCS 9706270029
Download: ML17292A910 (38)
v • d • e


Text

~.Q) ~

pe Af00 0

Cy I

0O N0 t7

~O

++*++

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 NUCLEAR PROJECT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 150 License No.

NPF-21 1.

The Nuclear Regulatory Commission (the Commission) has found that A.

The application for amendment by the Washington Public Power Supply System (licensee) dated March 22, 1997.

as supplemented by letters dated April 2. April 3, April 9, April 15, May 14.

and telefax dated May 19,

1997, 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 2.

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.

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 Operating License No.

NPF-21 is hereby amended to read as follows:

9706270029, 9706%i PDR ADQCK 05000397 POR II

~

l ii

~

I j I'

)

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A. as revised through Amendment No. 150 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 its date of issuance and is to be implemented within 30 days of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Timothy G. Colburn. Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

3une 11, 1997

L.

TABLE OF CONTENTS 3.3 3.3.6.2 3.3.7.1 3.3.8.1 3.3.8.2 3.4 3.4.1 3.4.2 3.4.3 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.4.10 3.4.11 3.4.12 3.5 3.5.1 3.5.2 3.5.3 3.6 3.6.1.1 3.6.1.2 3.6.1.3 3.6.1.4 3.6.1.5 3.6.1.6 3.6.1.7 3.6.1.8 3.6.2.1 3.6.2.2 3.6.2.3 INSTRUMENTATION (continued)

Secondary Containment Isolation Instrumentation Control Room Emergency Filtration (CREF) System Instrumentation Loss of Power (LOP) Instrumentation Reactor Protection System (RPS) Electric Power Monitoring REACTOR COOLANT SYSTEM (RCS)

Recirculation Loops Operating Jet Pumps

~

Safety/Relief Valves (SRVs) ~ 25K RTP Safety/Relief Valves (SRVs) < 25K RTP RCS Operational LEAKAGE RCS Pressure Isolation Valve (PIV) Leakage RCS Leakage Detection Instrumentation RCS Specific Activity.

Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown Residual Heat Removal (RHR) Shutdown Cooling System-Cold Shutdown RCS Pressure and Temperature (P/T) Limits Reactor Steam Dome Pressure EMERGENCY CORE COOLING SYSTEMS (ECCS)

AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ECCS-Operating ECCS Shutdown RCIC System CONTAINMENT SYSTEMS Primary Containment Primary Containment Air Lock Primary Containment Isolation Valves (PCIVs)

Drywell Air Temperature Residual Heat Removal (RHR) Drywell Spray Reactor Building-to-Suppression Chamber Vacuum Breakers Suppression Chamber-to-Drywell Vacuum Breakers Main Steam Isolation Valve Leakage Control (MSLC) System Suppression Pool Average Temperature Suppression Pool Water Level Residual Heat Removal (RHR) Suppression Pool Cooling 3.3-59 3.3-63 3.3-68 3.3-72 3.4-1 3.4-1 3.4-5 3.4-7 3.4-8 3.4-10 3.4-12

3. 4-1'4 3.4-16 3.4-18 3.4-21 3.4-23 3.4-31 3.5-1 3.5 i 3.5-7 3.5-11 3.6-1 3.6-1 3.6-3 3.6-8 3.6-16 3.6-17 3.6-19 3.6-22 3.6-25 3.6-27 3.6-30 3.6-31 continued WNP-2 Amendment No. 449, 150

ll

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 150 TO 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 areas of change.

The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE ll 3.3-6 3.3-42 3.3-43 3.3-44 3.3-45 3.3-54 3.5-5 3.5-6 3.5-7 3.5-8 3.5-9 3.5-10 3.5-11 3.5-12 INSERT 11 3.3-6 3.3-42 3.3-43 3.3-44 3.3-45 3.3-54 3.5-5 3.5-6 3.5-7 3.5-8 3.5-9 3.5-10 3.5,-11 3.5-12 3.5-13

~ f If

~

RPS Instrumentation 3. 3. 1. 1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.15 NOTES'-

1.

Neutron detectors are excluded.

2.

Channel sensors for Functions 3 and 4 are excluded.

3.

For Function 5, "n" equals 4 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.

Verify the RPS

RESPONSE

TINE is within limits.

24 months on a

STAGGERED TEST BASIS WNP-2 3.3-6 Amendment No. 449,150

~

r

0 ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS NOTES 1.

Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Survei llances, entry into associated Conditions and Required Actions may be delayed as follows:

(a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 3.c. 3.f, and 3.g; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions other than 3.c, 3.f, and 3.g provided the associated Function or the redundant

- Function maintains ECCS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> k

SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.5.1.3 Perform CHANNEL CALIBRATION.

92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION.

18 months SR 3.3.5.1.5 Perform CHANNEL CALIBRATION.

24 months SR 3.3.5;1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months WNP-2 3.3-42 Amendment No. 449,150

A l

i 4

II' j

il h

g

ECCS Instrumentation 3. 3. 5. 1 Table 3.3.5.1-1 (page 1 of 4)

Emergency Core Cooling System Instrunentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS COND IT IONS REFERENCED REQUIRED FROM CHANNELS PER REQUIRED FUNCTION ACTION A.1 SURVEILLANCE ALLOWABLE REQUIREMENTS VALUE 1.

Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)

Subsystems a.

Reactor Vessel Water Level - Low Low Low, Level 1

1,2,3, 4(a) 5(a) 2(b)

SR 3.3.5.1 '

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.F 1.6

~ -148 inches b.

Drywell Pressure - High 1,2,3 2(b)

SR 3.3.5.1.2 s 1.88 psig SR 3.3 '.1.4 SR 3.3 '.1.6 c.

LPCS Pump Start LOCA Time Delay Relay d.

LPCI Punp A Start LOCA Time Delay Relay e.

LPCI Pump A Start LOCA/LOOP Time Delay Relay f.

Reactor Vessel Pressure Low (Injection Permissive) 1'I3I 4(a) 5(a) 1,2,3, 4(a) 5(a) 1.2.3 4(a) 5(a) 1.2.3 1 per valve SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5 '.5 SR 3.3.5 '.6 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 SR 3.3.5.1.2 SR 3.3 '.1.4 SR 3.3.F 1.6 i 8.53 seconds and s 10.64 seconds R 17.24 seconds and s 21 ~ 53 seconds

> 3.04 seconds and s 6.00 seconds

>'448 psig and s 492 psig g.

LPCS Pump Discharge Flow-Low (Mininnnn Flow) h.

LPCI Pump A Discharge Flow Low (Mininnln Flow) i.

Manual Initiation 4

5 1 per valve 1,2,3, 4(a) 5(a) 1,2,3, 4(a) 5(a) 1I2I3I 4(a) 5(a)

E SR 3.3.5.1.2 SR 3.3.F 1.4 SR 3.3.5.1.6 SR 3.3.5.1.2 SR 3.3.5 '.4 SR 3.3.5 '.6 SR 3.3 '.1.2 SR 3.3.5 '.4 SR 3.3.5.1.6 i 448 psig and s 492 psig a 668 gpn and s 1067 gpm

> 605 gpm and s 984 gpn C

"'R 3.3.5 '.6 HA (a)

When associated subsystem(s) are required to be OPERABLE.

(b)

Also required to initiate the associated diesel generator (DG).

(cont inued)

WNP-2 3.3-43 Amendment No. 449,150

'\\

~

i/

ECCS Instrumentation 3.3.5.1 Table 3.3 ~5.1-1 (page 2 of 4)

Emergency Core Cooling System Instrunentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS COHD IT IOHS REFERENCED REQUIRED FROM CHANNELS PER REQUIRED FUNCTION ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 2.

LPCI 8 and LPCI C

Subsystems a.

Reactor Vessel Water Level Low Low Low, Level 1

b.

Drywell Pressure - High 1I2I3 ~

4(a) 5(a) 1,2,3 2(b) 2(b)

SR 3.3.F 1.1 SR 3.3.5.1.2 SR 3.3.5 '.4 SR 3.3.5.1.6 k

SR 3.3.5 ' '

SR 3.3.5 '.4 SR 3.3 '.1.6

~ -148 inches s 1.88 psig c.

LPCI Pump 8 Start LOCA Time Delay Relay d.

LPCI Pump C Start LOCA Time Delay Relay e.

LPCI Pump 8 Start LOCA/LOOP Time Delay Relay f.

Reactor Vessel Pressure Low (Injection Permissive) 1,2,3, 4(a) 5(a) 1I2I3I 4(a) 5(a)

I ~ 2 I3 I 4(a) 5(a) 1,2,3 1 per valve SR 3.3.5.1.5 SR 3.3.5.'1.6 SR 3.3.5.1.5 SR 3.3.5 '.6 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3 '.1.6 SR 3.3.5.1.2 SR 3.3.5 '.4 SR 3.3.5.1.6 a 17.24 seconds aAd

< 21.53 seconds

~ 8.53 seconds and s 10.64 seconds a 3.04 secoAds aAd s 6.00 seconds a 448 psig and

< 492 psig g.

LPCI Pumps 8 8 C

Discharge Flow Low (Minimml Flow) h.

Manual Initiation 1'I3I 4(a) 5(a) 1,2,3, 4(a) 5(a) 1 per pump 4(a>> 5(a) 1 per valve SR 3.3'.1 '

SR 3.3.5.1.4 SR 3.3.5.1.6 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6

'SR 3.3.5.1.6 a 448 psig aAd s 492 psig

> 605 gpm aAd s 984 gpm NA 3.

High Pressure Core Spray (HPCS) System a.

Reactor Vessel Water Level Low Low, Level 2 1,2,3, 4(a) 5(a) 4(b)

SR 3.3.5 '.1 SR 3.3.5 '.2 SR 3.3.5.1.4 SR 3.3.5.1.6

> -58 inches (continued)

(a)

When associated subsystem(s) are required to be OPERABLE.

(b)

Also required to initiate the associated DG.

WNP-2 3.3-44 Amendment No. 449,150

0 I,

0 ECCS InstrumentatIon 3. 3. 5. 1 Table 3.3.5.1-1 (page 3 of 4)

Emergency Core Cooling System InstrwIentation FUNCTION APPLICABLE NODES OR OTHER SPECIFIED CONDITIONS CONDITIONS REFERENCED REQUIRED FROH CHANNELS PER REQUIRED FUNCTION ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 3.

HPCS System (continued) b.

Drywall Pressure High 1.2.3 4(b)

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.'1.6 s 1.88 psig c.

Reactor Vessel Mater Level High, Level 8 1.2.3.

4(a) 5(a)

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3 ~5.1.6 s 56.0 inches d.

Condensate Storage Tank Level Low e.

Suppression Pool Mater Level High f.

HPCS System Flow Rate Low (HinimNI F low) g.

Hanual Initiation 1,2,3, 4(c) 5(c) 1,2,3 1 2.3.

4(a) 5(a)

'1,2,3, 4(a) 5(a)

SR 3.3.5 '.2 SR 3.3.5. 1.4 SR 3.3.5.1.6 SR 3.3 ' '.2 SR 3.3.5.1.4 SR 3.3.5.'1.6 SR 3.3.5.1.2 SR 3.3.F 1.4 SR 3.3.F 1.6

> 448 ft 1 inch elevation s 466 ft 11 inches elevation 2 1200 gpm and s 1512 gpm SR 3.3.5.1.6 NA 4.

Automatic Depressurization System (ADS) Trip System A a.

Reactor Vessel Mater Level Low Low Low, Level 1

b.

ADS Initiation Timer C.

Reactor Vessel Mater Level Low, Level 3 (Permissive) d.

LPCS Pump Discharge Pressure High 1 2(d) 3(d) 1 2(d) 3(d) 1 2(d) 3(d) 1 2(d) 3(d)

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5 '.4 SR 3.3.5.1.6 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 SR 3.3.5.1.1 SR 3.3.5 ' '

SR 3.3.5.1.4 SR 3.3.5.1.6 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6

> -'148 inches s 115.0 seconds

> 9.5 inches

> 119 psig and s

171 psig (continued)

(a)

When associated subsystem(s) are required to be OPERABLE.

(b)

Also required to initiate the associated DG.

(c)

Mhen HPCS is OPERABLE for compliance with LCO 3.5.2,

>>ECCS Shutdown,>>

and aligned to the condensate storage tank while tank water level is not within the limit of SR 3.5.2.2.

(d)

Mith reactor steam dome pressure

> 150 psig.

WNP-2 3.3-45 Amendment No. 449,150

i

Primar y Containment olati on Instrumentati on 3.3.6.1 SURVEILLANCE REQUIREMENTS

-NOTES 1.

Refer to.Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2.

When a channel is placed in an inoperable status solely for performance of requi red Survei llances, entry into associated Conditions and Required Actions may be delayed for up to 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> s provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6. 1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.6. 1.3 Perform CHANNEL FUNCTIONAL TEST.

184 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION.

18 months SR 3.3.6.1.5 Peirform CHANNEL CALIBRATION.

24 months SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months SR 3.3.6.1.7

-NOTE Channel sensors for Functions l.a, 1.b, and 1.c are excluded.

Verify the ISOLATION SYSTEM RESPONSE TIME is within limits.

24 months on a

STAGGERED TEST BASIS WNP-2 3.3-54 Amendment No. 449,150

j

ECCS-Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

\\

SYSTEM FLOW RATE TOTAL DEVELOPED HEAD SR 3.5. 1.4 Verify each ECCS pump develops the specified flow rate with the specified developed head.

In accordance with the Inservice Testing Program LPCS LPCI HPCS

> 6350 gpm

> 7450 gpm

> 6350 gpm

> 128 psid 26 psid

~ 200 psid SR 3.5.1.5

-NOTE Vessel injection/spray may be excluded.

Verify each ECCS injection/spr ay subsystem actuates on an actual or simulated automatic initiation signal.

24 months SR 3.5.1.6 NOTE Valve actuation may be excluded.

Verify the ADS actuates on an actual or simulated automatic initiation signal.

24 months SR 3.5.1.7

-NOTE-Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify each required ADS valve opens when manually actuated.

24 months on a

STAGGERED TEST BASIS for each valve solenoid (continued)

WNP-2 3.5-5 Amendment No. 449.150

I J~

l' I[,'

ECCS-Operating 3.5.1 SURVEILLANCE RE UIREHENTS continued SURVEILLANCE FREQUENCY SR 3.5.1.8 NOTE ECCS actuation instrumentation is excluded.

Verify the ECCS

RESPONSE

TINE for each ECCS 24 months injection/spray subsystem is within limits.

WNP-2 3.5-6 Amendment No.

150

,II ll

ECCS - Shutdown 3.,5. 2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM 3.5.2 ECCS Shutdown LCO 3.5.2 Two ECCS injection/spray subsystems shall be OPERABLE.

APPLICABILITY: MODE 4, MODE 5 except with the spent fuel storage pool gates removed and water level

~ 22 ft over the top of the reactor pressure vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A:

One required ECCS injection/spray subsystem inoperable.

A.l Restore required ECCS injection/spray subsystem to OPERABLE status.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B.

Required Action and associated Completion Time of Condition A not met.

8.1 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).

Immediately C.

Two required ECCS injection/spray subsystems inoperable.

C.1 AND Initiate action to suspend OPDRVs.

Immedi ately C.2 Restore one ECCS injection/spray subsystem to OPERABLE status.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (continued)

WNP-2 3.5-7 Amendment No. 449.iS0 l

0 s.

jt I

1 I,

ECCS - Shutdown 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

Required Action C.2 and associated Completion Time not met.

D. 1 Initiate action to restore secondary containment to OPERABLE status.

AND Immedi ately D.2 AND Initiate action to restore one standby gas treatment subsystem to OPERABLE status.

Immediately

'.3 Initiate action to restore isolation capability in each required secondary containment penetration flow path not isolated.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each required low pressure ECCS injection/spray subsystem, the suppression pool water level is > 18 ft 6 inches.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)

WNP-2 3.5-8 Amendment No. 449. ig0

v'~

h II t

I 11 I'

ECCS - Shutdown 3.5.2

'URVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.2 Verify, for the required High Pressure Core Spray (HPCS) System, the:

a.

Suppression pool water level is

~ 18 ft 6 inches; or b.

Condensate storage tank (CST) water level is ~ 13.25 ft in a single CST or

~ 7.6 ft in each CST.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.5.2.3 Verify, for each requi red ECCS injection/

spray subsystem, the piping is filled'ith water from the pump discharge valve to the injection valve.

31 days SR 3.5.2.4 NOTE-One low pressure coolant injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned and not otherwise inoperable.

Verify each required ECCS injection/spray subsystem

manual, power operated, and automatic valve in the flow path. that is not locked, sealed, or otherwise secured in position, is in the correct position.

31 days (continued)

WNP-2 3.5-9 Amendment No. 449,1SD

\\ 4 0

1 k

l,

ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SYSTEM FLOW RATE TOTAL DEVELOPED HEAD SR 3.5.2.5 Verify each required ECCS pump develops the specified flow rate with the specified developed head.

In accordance with the Inservice Testing Program LPCS LPCI HPCS

> 6350 gpm

> 7450 gpm

~ 6350 gpm

~ 128 psid 26 psid

~ 200 psid SR 3.5.2.6

-NOTE Vessel injection/spray may be excluded.

Verify each required ECCS injection/spray subsystem actuates on an actual or simulated automatic initiation signal.

24 months WNP-2 3.5-10 Amendment No. 449.150

i Il l

II

RCIC System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM 3.5.3 RCIC System LCO 3.5.3 The RCIC System shall be OPERABLE.

APPLICABILITY:

MODE 1, MODES 2 and 3 with reactor steam dome pressure

> 150 psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

RCIC System inoperable.

A.l Verify by administrative means High Pressure Core Spray System is OPERABLE.

AND A.2 Restore RCIC System to OPERABLE status Immediately 14 days B.

Required Action and associated Completion Time not met.

B.l Be in MODE 3.

AND B.2 Reduce reactor steam dome pressure to s 150 psig.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours WNP-2 3.5-11 Amendment No. 449,150

~1 ll 1

I

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3. 1 Verify the RCIC System piping is filled with water from the pump discharge valve to the injection valve.

31 days SR 3.5.3.2 Verify each RCIC System manual.

power

operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position. is in the correct position.

31.days SR 3.5.3.3 NOTE-Not requi red to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure

< 1035 psig and ~ 935 psig, the RCIC pump can develop a

flow rate > 600 gpm against a system head corresponding to reactor pressure.

92 days SR 3.5.3.4 NOTE-Not required to be performed unti 1 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure s 165 psig, the RCIC pump can develop a flow rate

> 600 gpm against a system head corresponding to reactor pressure.

24 months (continued)

WNP-2 3.5-12 Amendment No. 449,150

(

f I

I I

Fl

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.3.5

, -NOTE-Vessel injection may be excluded.

Verify the RCIC System actuates on an actual or simulated automatic initiation signal.

24 months WNP-2 3.5-13 Amendment No.=449,160

I' I

I

Retrieved from "https://kanterella.com/w/index.php?title=ML17292A910&oldid=5089896"