Latest revision as of 06:59, 4 February 2020

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Proposed Tech Specs Modifying Response Time Testing SR for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation
	ML17292A758
Person / Time
Site:	Columbia
Issue date:	03/22/1997
From:	; WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	;
Shared Package
ML17292A757	List: ML17292A756; ML17292A758;
References
	NUDOCS 9704010341
	Download: ML17292A758 (39)
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REQUEST FOR AMENDMENTTO OPERATING LICENSE REGARDING TECHNICAL SPECIFICATION RESPONSE TIME TESTING Technical Specification Pages e70OOXOsna 9703m /7 PDR ADGCK 05000S97i P PDRj I

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RPS Instrumentation 3.3.1.1 SURVEILLANCE REgUIREHENTS continued SURVEILLANCE FREQUENCY SR 3.3.1.1.15 NOTES

1. Neutron detectors are excluded.

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

Verify the RPS RESPONSE TINE is within 24 months on a limits. STAGGERED TEST BASIS P., C.AAUM6L SGM<oas co a. 5udovioAs R. Qb 0 &,Ke Gee.c uW aZ WNP-2 3.3-6 Amendment No. 149

/

1

ECCS Instrumentation 3.3.5.I 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 Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 3.c,'.f, and 3.g; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 hours 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 Ra<E7C. SR 3.3.5.1 Verify the EC RESPONSE TIME for~el 24 month~ n a required injection/spray system STAgGEREO, TEST is w'n S limits.

s AXIS WNP-2 3.3-42 Amendment No. 149

ECCS Insti"umentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of C)

Emergency Core Cooling System lnstrunentatian APPLICABLE COND IT IONS NODES OR REFERENCED OTHER REOUIRED FRCH SPECI FIED CHANNELS PER REQUIRED SURVEILLANCE ALLOMABLE FUNCT ION CONDITIONS FUNCTION ACTION A.'I RECUIRENEMTS VALVE

1. LOM Pressure Coolant Injection.A (LPCI) and Lau Pressure Care Spray (LPCS)

Subsystems

a. Reactor Vessel Mater 1,2,3, 2(b) SR 3.3.5.1.1 L -148 inches Levet Lou LOM Low, sR 3.3.5.1.2 Levet 1 4('),5 sR 3.3.5.1.4 Sll 3.3.5.1.6

b. Dryuet t Pressure - High 1,2,3 2(b) SR 3.3.5.1.2 S 1.88 psig SR 3.3.5 1.4 sR 3.3.5.1.6

c. LPCS Pimp Start - LOCA 1,2,3, SR 3.3.5.1.5 8 8.53 Time Delay ReLay SR 3.3.5.1.6 seconds and 5 10.64 seconds

d. LPCI Pimp A 1.2r3. SR 3.3.5.1.5 8 17.24 Start LOCA Time Delay SR 3.3.5.1.6 seconds and Relay (a),5 5 21.53 seconds

e. LPCI Pulp 1,2,3, 3.3.5.1.2 Start - A LOCA/LOOP Time 4(a) 5(a)

SR SR 3.3.5.1.3 R 3.0C seconds and Delay Retay N 3.3.5.1.6 5 6.DD seconds Reactor Vessel 1,2,3 1 per valve C N 3.3.5.1.2 8 448 psig Pr assure LoM SR '.3.5.1.4 and (Injection Permissive) SR 3.3.5.1.6 c 492 psig 4,5 1 per valve SR 3.3.5.1.2 8 448 psig SR 3.3.5.1.4 and N 3.3.5.1.6 S 492 psig

g. LPCS Punp Discharge 1,2,3, SR 3.3.5.1.2 b 668 gpn and Flou Lau (Hinimm SR 3.3.5.1.4 + 1067 gpn Ftou) 4(a) 5(a) SR 3.3.5.1.6

h. LPCI Puap A Discharge 1,2,3, 3.3.5.1.2 F I ou - Lov (Hiniaxm 4(a) 5(a)

SR SR 3.3.5.1.4 b 605 gpn and S 984 gpn Ftou) sR 3.3.5.1.6

i. Manual Initiation 1,2,3, sR 3.3.5.1.6 MA 4(a) 5(a)

(continued)

(a) Mhen associated subsystem(s) are required to be OPERABLE.

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

WNP-2 3.3-43 Amendment No. 149

CCS Instrumentation 3.3.5.)

~ ~ ~

Table 3.3.5.1-1 (page 3 of 4)

Emergency Core Cooling System Instrunentation APPLICABLE COHO I TIOHS KCOES OR REFEREHCED OTHER RECUIRED FROK SPECIFIED CHAHHELS PER REQUIRED SURVE I LLAHCE ALLOMABLE FUHCT IOH COHO I T IOHS FUHCTIOH ACTIOH A.1 REQUIREKEHTS VALUE

3. HPCS System (continued)

b. Drywell 1,2,3 4(b) 3.3.5.1.2 < 1.88 psig Pressure - High SR SR 3.3.5.1.4 3.5.1.6

c. Reactor Vessel 1,2,3, 3.3.5.1.1 < 56.0 inches Mater Level High, 4(a) 5(a)

SR SR 3.3.5.1.2 Level 8 SR 3.3.5.1.4 SR 3.3.5.1.6

d. Condensate Storage

- 1,2,3, SR 3.3.5.1.2 i 448 ft 1 inch Tank Level Low SR 3.3.5.1.4 elevation 4(c) 5(c) SR 3.3.5 ~ 1.6

e. Suppression Pool

- 1,2,3 SR 3.3.5.1.2 < 466 ft Mater LeveL High SR 3.3.5.1.4 11 inches SR 3.3.5.1.6 elevation

f. System Flow 1,2,3, 3.3.5.1.2 + 1200 gpn and HPCS Rate Low (KininL!n 4(a) 5(a)

SR SR 3.3.5.1.4 < 1512 gpm Flow) SR 3.3.5.1.6

g. KanuaL Initiation 1,2,3, SR 3.3.5.1.6 HA I(a) 5(a)

4. Automat'ic Depressurization System (ADS) Trip System A

a. Reactor Vessel Z(d) 3(d) 3.3.5.1.1 + -148 inches Mater Level Low- 1 SR SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.4 SR 3.3.5.1.6

b. ADS initiation 1 2(d) 3(d) SR 3.3.5.1.2 < 115.0 seconds Timer SR 3.3.5.1.3 SR 3.3.5. I.6

c. Reactor Vessel 2(d) 3(d) 3.3.5.1.1 > 9.5 inches Mater Level Low, 1 SR SR 3.3.5.1.2 Level 3 SR 3.3.5.1.4 (Permissive) SR 3.3.5.1.6

d. LPCS'wy (d) 3(d) 3.3.5.1.2 > 119 SR psig and Discharge SR 3.3.5.'1.4 < 171 psig Pressure- High SR 3.3.5.1.6

{continued)

(a) Mhen associated subsystem(s) are required to be OPERABLE.

(b) Also required to initiate the associated DG.

(c) 'when 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.

MNP-2 3.3-45 Amendment No. 149

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

Emergency Core Cooling System Instrunentation APPLICABLE, COND IT I ONS HGOES OR REFERENCED OTHER REQUIRED FROM SPECI F I ED CHANHELS PER REQUIRED SURVEILLANCE ALLOMABLE FUNCTION COND I T I ONS FUNCTION ACTION A. 1 REQUIREMENTS VALUE

2. LPCI B and LPCI C Subsystems

a. Reactor Vessel Mater 1,2,3, 2(b) SR 3.3.5.1.1 > -148 inches Level LoM Low Lou, SR 3.3.5.1.2 Level 1 ,s SR 3.3.5.1.4 SR 3.3.5.1.6

b. DryMell Pressure - High 1,2,3 Z<b SR 3.3.5.1.2 < 1.88 ps ig SR 3.3.5.1.4

.1.6

c. LPCI Punp B Start-LOCA 1,2,3, SR 3.3.5;1.5 > 17.24 Time Delay Relay SR 3.3 5.1.6

~ seconds and 4(a) 5(a) < 21.53 seconds

d. LPCI Pwp C Start LOCA 1,2,3, SR '3.3.5.1.5 8 8.53 Time Delay Relay SR 3.3.5.1.6 seconds and 4(a) 5(a) < 10.64 seconds

e. LPCI Punp B 1,2,3, 3.3.5.1.2 8 3.04 Start - LOCA/LOOP Time 4(a) 5(a)

SR SR 3.3.5.1.3 seconds and Delay Relay SR 3.3.5.1.6 < 6.00 seconds

f. Reactor Vessel 1,2,3 per valve 3.3.5.1.2 > C48 Pressure - Low 1 SR SR 3.3.5.1.4 and psig (Injection Permissive) SR 3.3.5.1.6 < C92 psig 5 1 per valve SR 3.3.5.1.2 > 448 psig SR 3.3.5.1 ' and SR 3.3.5.1.6 < 492 psig

g. LPCI Pumps B 8 C 1,2,3, per pmp 3.3.5 1.2 > 605 gpa Discharge FloM - Lou 1 SR SR

~

3.3.5.1 4 and (Miniaxsn Floe) s<a) SR 3.3.5.1.6 S 984 gpm

h. Manual Initiation 1,2,3, SR 3.3.5.1.6 NA 4<a) 5<a)

3. High Pressure Core Spray (HPCS) System

a. Reactor Vessel Mater 1,2,3, 4(b) 3.3.5.1-1 > -58 inches Level Low Log, Level 2 SR SR 3.3.5.1.2 4<a),S SR 3.'3.5.1.4 S 3 .16 (continued)

(a) Mhen associated subsystem(s) are required to be OPERABLE.

(b) Also required to initiate the associated DG.

WNP-2 3.3-44 Amendment No. 149

t c ~

t

Primary Containment lation Instrumentation 3.3.6.1 SURVEILLANCE RE(UI REMENTS 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 required Surveill'ances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. 12 hours 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 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6. 1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SR 3.3.6. 1.7 Verify the ISOLATION SYSTEM RESPONSE TIME 24 months on a is within limits. STAGGERED TEST BASIS MNP-2 3.3-54 Amendment No. 149

e 0 1

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ECCS Operating 3.5.1 SURVEILLANCE REOUIREHENTS continued SURVEILLANCE FREQUENCY SR 3.5. 1.4 Verify each ECCS pump develops the In accordance specified flow rate with the specified with the E developed head. Inservice Program

'esting TOTAL DEVELOPED SYSTEM 'LOM RATE .

HEAD LPCS ~ 6350 gpm ~ 128 psid LPCI ~ 7450 gpm 26 psid "

HPCS ~ 6350 gpm a 200 psid SR 3.5.1.5 NOTE Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem 24 months actuates on an actual or simulated automatic initiation signal..

SR 3.5.1.6 NOTE Valve actuation may be excluded.

Verify the ADS actuates on an actual or 24 months simulated automatic initiation signal.

SR 3.5.1.7 NOTE Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.

Verify each required ADS valve opens when 24 months on a manually actuated. STAGGERED TEST BASIS for each valve solenoid E.E. IMSE.R.T MNP-2 3. 5-5 Amendment No. 149

l kl 5 E R.T ECCS Operating 3.5.1 SURVEILLANCE RE(UIREMENTS continued SURVEILLANCE FRE(UENCY SR 3.5.1.8 NOTE ECCS actuation instrumentation is excluded.

Verify the ECCS RESPONSE TIME for each ECCS. 24 months injection/spray subsystem is within limits.

WNP-2 3.5-6 Revision A

1 h i r a c"'a~ v ~ s r ~

t 4

TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.6.2 Secondary Containment Isolation Instrumentation 3.3-59 3.3.7.1 Control Room Emergency Filtration (CREF) System Instrumentation . . . . . . . . . . . . . . . 3.3-63 3.3.8.1 Loss of Power (LOP) Instrumentation 3.3-68 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring . . . . . o ~ ~ ~ ~ ~ ~ 3.3-72 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4-1 3.4.1 Recirculation Loops Operating 3.4-1 3.4.2 Jet Pumps 3.4-5 3.4.3 Safety/Relief Valves (SRVs) a 25% RTP 3.4-7 3.4.4 Safety/Relief Valves SRVs) < 25% RTP 3.4-8 3.4.5 RCS Operational LEAKAGE 3.4-10 3.4.6 RCS Pressure Isolation Valve (PIV) Leakage . . 3.4-12 3.4.7 RCS Leakage Detection Instrumentation 3.4-14 3.4.8 RCS Specific Activity 3.4-16 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System Hot Shutdown 3.4-18 3.4.10 Residual Heat Removal (RHR) Shutdown Cooling System Cold Shutdown . . . . . . . . . . . 3.4-21 3.4.11 RCS Pressure and Temperature (P/T) Limits 3.4-23 3.4.12 Reactor Steam Dome Pressure 3.4-31 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5-1 3.5.1 ECCS Operating 3.5-1 3.5.2 ECCS Shutdown . 3.5-7 3.5.3 RCIC System 3.5-11 3.6 CONTAINMENT SYSTEMS 3.6-1 3.6.1.1 Primary Containment 3.6-1 3.6.1.2 Primary Containment Air Lock . 3.6-3 3.6.1.3 Primary Containment Isolation Valves (PCIVs) 3.6-8 3.6.1.4 Drywell Air Temperature 3.6-16 3.6.1.5 Residual Heat Removal (RHR) Drywell Spray 3.6-17 3.6.1.6 Reactor Building-to-Suppression Chamber Vacuum Breakers . . . . . . . . . . . .,. . 3.6-19 3.6.1.7 Suppression Chamber-to-Drywell Vacuum Breakers 3.6-22 3.6.1.8 Main Steam Isolation Valve Leakage Control (MSLC) System . . . . . . . . . . . . . . . 3.6-25 3.6.2.1 Suppression Pool Average Temperature . 3.6-27 3.6.2.2 Suppression Pool Water Level 3.6-30 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling . . . . . . . . . . . . . . . . 3.6-31 continued WNP-2 Amendment No. 150

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 24 months on a limits. STAGGERED TEST BASIS WNP-2 3.3-6 Amendment No. 150

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 Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 3.c, 3.f, and 3.g; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 hours 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. 150

~, ~ I ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 4)

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

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

Subsystems

a. Reactor Vessel Water 1,2,3, 2(b) SR 3.3 '.1.1 h -148 inches Level Low Low Low, 4(a) 5(a)

SR 3.3.5.1.2 Level 1 SR 3.3.5.1 '

SR 3.3.5.1.6

b. Drywall Pressure High 1 ~ 2I3 2(b) SR 3.3.5 '.2 S 1.88 psig.

SR 3.3.5.'I.4 SR 3.3.5.1.6

c. LPCS Pump Start LOCA 1,2,3, SR 3.3 '.1.5 h 8.53 Time Delay Relay SR 3.3 '.1.6 seconds and 4(a) 5(a) < 10.64 seconds

d. LPCI Punp A 1,2,3, SR 3.3.5 '.5 2 17.24 Start LOCA Time Delay SR 3.3.5.1.6 seconds and Relay 4(a) 5(a) < 21.53 seconds

e. LPCI Pump A 1,2,3, SR 3.3 ' '-2 2 3 '4 Start LOCA/LOOP Time SR 3.3 '.1.3 seconds and Delay Relay 4(a) 5(a) SR 3.3.5.1.6 5 6.00 seconds

f. Reactor Vessel 1,2,3 1 per valve SR 3.3.F 1.2 2 448 psig Pressure Low SR 3.3 '.1.4 and (Injection Permissive) SR 3.3.5.1.6 < 492 psig 4(a),5(a) 1 per valve 8 SR 3.3.5 1.2

~ 2 448 psig SR 3.3.5.1.4 and SR 3.3.5 '.6 S 492 psig

g. LPCS Pump Discharge Ie2e3i SR 3.3.5.1.2 > 668 gpll and Flow Low (Minimun SR 3.3.5.1.4 5 1067 gpm Flow) 4(a) 5(a) SR 3.3.5 '.6

h. LPCI Pump A Discharge 1,2,3, SR 3.3.5.1.2 ? 605 gpm and Flow Low (Minimun SR 3.3.5.1.4 < 984 gpm Flow) 4(a) 5(a) SR 3.3 '.1.6

i. Manual Initiation 1,2,3, SR 3.3 '.1.6 HA 4(a) 5(a)

(continued)

(a) When associated subsystem(s) are required to be OPERABLE'b)

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

MNP-2 3.3-43 Amendment No. 150

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

Emergency Core Cooling System Instrunentation APPLICABLE COND I T I ON S MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER, REQUIRED SURVEILLANCE ALLOMABLE FUNCTION COND IT IOHS FUNCTION ACTION A.1 REQUIREMENTS VALUE

2. LPCI 8 and LPCI C Subsystems

a. Reactor Vessel Mater Ii2I3I 2(b) SR 3.3.5.1.1 2 -148 inches Level Low Low Low, SR 3.3.5.1.2 Level 1 4(a) 5(a) SR 3.3.5.1.4 SR 3.3.5.1.6

b. Drywall Pressure - High 1 2i3 2(b) SR 3.3.5.1.2 S 1.88 psig 3.3 '.1.4

~

SR SR 3.3.5.1.6

c. LPCI Pump B Start LOCA g 2/ 3@ SR 3.3.5.1.5 2 17.24 Time Delay Relay SR 3.3.F 1.6 seconds and I(a) 5(a) < 2'1.53 seconds

d. LPCI Punp C Start - LOCA 1 g2$ 3g SR 3.3.5.1.5 2 8.53 Time Delay Relay SR 3.3.5.1.6 secoAds aAd 4(a) 5(a) S 10.64 secoAds

e. LPCI Pump 8 1,2,3, SR 3.3.5.1.2 2 3.04 Start - LOCA/LOOP Time 4(a) 5(a)

SR 3.3.5.1.3 secoAds aAd Delay Relay SR 3.3.5.1.6 S 6.00 seconds

f. Reactor Vessel 1,2,3 per valve C SR 3.3 '.1.2 2 448 psig Pressure - Low 1

SR 3.3.5.1.4 SAd (Injection Permissive) SR 3.3.5.1-6 < 492 psig 4,5 1 per valve 8 SR SR 3.3.5.1.2 3.3.5.1.4 2 448 aAd psig SR 3.3.5.1.6 < 492 psig

g. LPCI Pumps 8 8 C 1,2,3, 1 per pump SR 3.3.5.1.2 2 605 gpm Discharge Flow Low SR 3.3.5.1.4 SAd (Minilmia Flow) 4(a) 5(a) SR 3.3.5.1.6 < 984 gpm

h. Manual Initiation 1 ~ 2I3I SR 3.3 '.1.6 HA 4(a) 5(a)

3. High Pressure Core Spray (MPCS) System

a. Reactor Vessel Mater 1,2,3, 4(b) SR 3.3.5.1.1 2 -58 inches Level Low Low, Level 2 SR 3.3 '.1.2 4(a) 5(a) SR 3.3.5.1.4 SR 3.3.5.1.6 (continued)

(a) Mhen associated subsystem(s) are required to be OPERABLE.

(b) Also required to initiate the associated DG.

WNP-2 3.3-44 Amendment No. 150

g>>

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

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

3. HPCS System (continued)

b. Drywall 1 ~ 2/3 4(b) SR 3.3.5.1.2 5 1>>88 pslg Pressure High SR 3.3.5.1.4 SR 3.3.5.1.6

c. Reactor Vessel 1,2,3, SR 3.3.5.1.1 5 56.0 inches Water Level High, SR 3.3.5.1.2 Level 8 4(a) 5(a) SR 3.3.5.1.4 SR 3.3.5.1.6

d. Condensate Storage 1,2,3, SR 3.3.5.1.2 > 448 ft 1 inch Tank Level Low SR 3.3.5.1.4 elevation 4(c) 5(c) SR 3.3 '.1.6

e. Suppression Pool 1,2,3 SR 3.3.5.1.2 < 466 ft Water Level High SR 3.3.5.1.4 11 inches SR 3.3.5.1.6 elevation

f. HPCS System Flow 1I2I3I SR 3.3 '.1.2 > 1200 gpm and Rate Low (Miniaam SR 3.3.5.1.4 S 1512 gpm Flow) 4(a) 5(a) SR 3.3 '.1.6

g. Manual Initiation SR 3.3 5.1.6

~ NA 4(a) 5(a)

4. Automatic Depressurization System (ADS) Trip System A

a. Reactor Vessel 1 2(d) 3(d) SR 3.3.5.1.1 > -148 inches Water Level Low SR 3.3.5.1.2 Low Low, Level 1 SR 3.3 '.1.4 SR 3.3.5.1.6

b. ADS Initiation (d) 3(d) SR 3.3.5.1.2 5 115.0 seconds Timer SR 3.3.5.1.3 SR 3.3.5.1.6

c. Reactor Vessel 2(d) 3(d) SR 3.3.5.1 1 > 9.5 inches

- 1 ~

Water Level Low, SR 3.3.5.1.2 Level 3 SR 3.3.5.1.4 (Permissive) SR 3.3.5.1.6

d. LPCS Pump 1 2(d) 3(d) SR 3.3.5.1 ' k 119 psig and Discharge SR 3.3.5.1.4 S 171 psig Pressure - High SR 3.3.F 1.6 (continued)

(a) When associated subsystem(s) are required to be OPERABLE'b)

Also required to initiate the associated DG>>

(c) When 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 '.2.2.

(d) With reactor steam dome pressure > 150 psig.

WNP-2 3.3-45 Amendment No. 150

) ~

I Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE RE(UIREMENTS 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 required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6. 1. 1 Perform CHANNEL CHECK. 12 hours 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 Perform 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 24 months on a is within limits. STAGGERED TEST BASIS WNP-2 3.3-54 Amendment No. 150

ECCS Operating 3.5.1 SURVEILLANCE RE UIREMENTS continued SURVEILLANCE FREQUENCY SR 3.5.1.4 Verify each ECCS pump develops the In accordance specified flow rate with the specified with the developed head. Inservice Testing Program TOTAL DEVELOPED SYSTEM FLOW RATE HEAD LPCS a 6350 gpm a 128 psid LPCI a 7450 gpm 26 psid HPCS a 6350 gpm a 200 psid SR 3.5.1.5 NOTE Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem 24 months actuates on an actual or simulated automatic initiation signal.

SR 3.5.1.6 NOTE Valve actuation may be excluded.

Verify the ADS actuates on an actual or 24 months simulated automatic initiation signal.

SR 3.5.1.7 NOTE-Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify each required ADS valve opens when 24 months on a manually actuated. STAGGERED TEST BASIS for each valve solenoid (continued)

WNP-2 3.5-5 Amendment No. 150

ECCS Operating 3.5.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FRE(UENCY 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

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required ECCS A. 1 Restore required ECCS 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months injection/spray injection/spray subsystem inoperable. subsystem to OPERABLE status.

B. Required Action and Bil Initiate action to Immediately associated Completion suspend operations Time of Condition A with a potential for not met. draining the reactor vessel (OPDRVs).

C. Two required ECCS Ci I Initiate action to Immediately injection/spray suspend OPDRVs.

subsystems inoperable.

AND C.2 Restore one ECCS 4 hours injection/spray subsystem to OPERABLE status.

(continued)

WNP-2 3.5-7 Amendment No. 150

(

Iy a> ~ A ECCS Shutdown 3.5.2 ACTIONS continued CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 D. 1 Initiate action to Immediately and associated restore secondary Completion Time not containment to met. OPERABLE status.

AND 0.2 Initiate action to Immediately restore one standby gas treatment subsystem to OPERABLE status.

AND 0.3 Initiate action to Immediately restore isolation capability in each required secondary containment penetration flow path not isolated.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2. 1 Verify, for each required low pressure ECCS 12 hours injection/spray subsystem, the suppression pool water level is a 18 ft 6 inches.

(continued)

WNP-2 3.5-8 Amendment No. 150 i

ECCS Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY

'R 3.5.2.2 Verify, for the required High Pressure Core 12 hours Spray (HPCS) System, the:

a. Suppression pool water level is w 18 ft 6 inches; or

b. Condensate storage tank (CST) water level is a 13.25 ft in a single CST or a 7.6 ft in each CST.

SR 3.5.2.3 Verify, for each required ECCS injection/ 31 days spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

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, ifand capable of being manually not otherwise inoperable.

realigned Verify each required ECCS injection/spray 31 days 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.

(continued)

WNP-2 3.5-9 Amendment No. 150 i

ECCS Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FRE(UENCY SR 3.5.2.5 Verify each required ECCS pump develops the In accordance specified flow rate with the specified with the developed head. Inservice Testing Program TOTAL DEVELOPED SYSTEM FLOW RATE HEAD LPCS a 6350 gpm a 128 psid LPCI a 7450 gpm 26 psid HPCS a 6350 gpm a 200 psid SR 3.5.2.6 NOTE Vessel injection/spray may be excluded.

Veri fy each required ECCS injection/spray 24 months subsystem actuates on an actual or simulated automatic initiation signal.

WNP-2 3.5-10 Amendment No. 150 i

tl 4

~

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

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

B. Required Action and B.l Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months dome pressure to x 150 psig.

WNP-2 3.5-11 Amendment No. 150 i

0 RCIC System 3.5.3 SURVEILLANCE RE(UIREHENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled 31 days with water from the pump discharge valve to the injection valve.

SR 3.5.3.2 Verify each, RCIC System manual, power 31 days operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.3.3 -NOTE Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure c 1035 psig 92 days a psig, the RCIC pump can develop and 935 flow rate ) 600 gpm against a system head a

corresponding to reactor pressure.

SR 3.5.3.4 -NOTE Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure x 165 psig, 24 months the RCIC pump can develop a flow rate a 600 gpm against a system head corresponding to reactor pressure.

{continued)

WNP-2 3.5-12 Amendment No. 150

[

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 24 months actual or simulated automatic initiation signal.

MNP-2 3.5-13 Amendment Ne. 150

[

~c4

~ t a l

REQUEST FOR AME vfENT TO OPERATING LICENSE GARDING TECHNICAL SPECIFICATION RESPONSE TIME TESTING Attachment 3 Page 1 of 3 I NIFICANT HAZARD SIDERATION In accordance with 10CFR50.91, a licensee must provide to the staff analysis of a proposed amendment to the operating license using the standards in 10CFR50.92 concerning the issue of.

no significant hazards consideration. The Supply System has evaluated the proposed amendment to the operating license and determined that it does not involve a significant hazards consideration.

The following evaluation is provided for the three categories of no significant hazards consideration standards:

Operation of WNP-2 in accordance with the proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated.

The purpose of the proposed license change is to eliminate response time testing requirements for selected instrumentation in the Reactor Protection System (RPS), Primary Containment Isolation Actuation, and Emergency Core Cooling System (ECCS). However, because of the continued application of other existing Technical Specification required testing such as channel calibrations, channel checks, channel functional tests, and logic system functional tests, the response time of these systems will be maintained within the limits assumed in plant safety analyses and required for successful mitigation of an initiating event. The proposed license change does not affect the capability of the associated systems to perform their intended functions within the required response time, nor do the proposed changes affect the operation of any equipment.

The Reference 1 evaluation demonstrates that response time testing is redundant to the other Technical Specification required testing listed in the preceding paragraph. This evaluation was reviewed and approved by the staff. These other tests, in conjunction with actions taken in response to NRC Bulletin 90-01, "Loss of Fill-Oil in Transmitters Manufactured by Rosemount," and Supplement 1, are sufficient to identify failure modes or degradations in instrument response time and ensure operation of the associated systems within acceptable limits.

Furthermore, all known failure modes that are detected by response time testing are also detected by other Technical Specification tests.

In addition, two categories of components were included in this change in testing methodology which were not identified in the table of components in Reference 1. These components are used within the logic circuits addressed in Reference 1. These components were inadvertently omitted from lists provided to General Electric in support of preparation of the Reference 1 tables.

.pC..; s

-.'EQUEST FOR AMEN ~ ENT TO OPERATING LICENSE GARDING TECHNICAL

'-'r, v" SPECIFICATION RESPONSE TIME TESTING Attachment 3 Page 2 of 3 These components have been reviewed for similarity to the items contained within the Reference 1 component tables and have been found to be similar to other equipment referenced in the table.

These components are also subject to periodic functional testing by CFTs and LSFTs. The Supply System verified instrument response of these components at an appropriate interval using the alternate methodology for instrument verification described in Reference 1.

The two categories of components referenced above which are not included in the Reference 1 component list have no postulated functions or affects which may cause an accident. These devices are tested periodically to verify functionality. Sufficient time margin is available in the station accident analysis to account for the amount of time delay allowed by the Reference 1 methodology.

, For the changes dealing with moving the surveillance requirement for ECCS RESPONSE TIME testing from the Instrumentation section to the System section of the Technical Specifications, no change in testing requirements (other than the elimination of the instrument loops implemented as part of the Reference 1 change) has been introduced. The relaxation in Applicability does not increase the probability or the consequences of an accident previously evaluated, since there are no design basis events which credit ECCS during MODES 4 and 5.

Therefore, the proposed amendment request does not involve a significant increase in the probability or consequences of an accident previously evaluated.

Operation of WNP-2 in accordance with the proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed amendment only applies to the testing requirement for the components identified and does not result in any physical change to these or other components or their operation. The changes do not affect the capability of the associated systems to perform their intended function within the acceptable limits assumed in plant safety analyses and required for successful mitigation of an initiating event. The proposed amendment does not change the way in which any plant systems are operated or create the possibility of a new or different kind of accident.

As, a result, no new failure modes are introduced.

The two categories of components referenced above which are not included in the Reference 1 component list have no postulated functions or affects which may contribute to the initiation of an accident.

i The proposed amendment represents reliance on a different, and previously staff approved, method to verify selected components remain fully functional and will not create the possibility of a new or different kind of accident from any accident previously evaluated.

REQUEST FOR AMENDMENTTO OPERATING LICENSE LARDING TECHNICAL SPECIFICATION RESPONSE TIME TESTING Page 3 of 3 Operation of WNP-2 in accordance with the proposed amendment change will not involve a significant reduction in the margin of safety.

The current response times are based on the maximum allowable values assumed in the plant safety analyses. These analyses conservatively establish the margin of safety. As described above, the reliance on an alternate methodology for instrument response verification (Reference

1) will not affect the capability of the associated systems to perform their intended function within the allowed response time used as the basis for the plant safety analyses.

The two categories of components referenced above which are not included in the Reference 1 component list are qualitatively tested periodically by channel calibrations, CFTs and LSFTs.

This testing verifies the proper function and response of these components. Adequate time margins have been verified to be available within the applicable analyses which enable qualitative assessment of the proper performance of these devices.

Plant and system response to an initiating event will remain in compliance with the assumptions of the safety analyses, and therefore the margin of safety is not affected.

Referee ce

1. GE Nuclear Energy, BWR Owners'roup Licensing Topical Report, NEDO-32291-A, "System Analysis for the Elimination of Selected Response Time Testing Requirements,"

October, 1995.

ENVIR NMENTALCONSIDERATIONS Based on the above evaluation, this proposed change to the license does not result in a significant hazards considerations. In addition, the proposed change does not create a potential for a

,significant change in the types, or a significant increase in the amount of any effluent that may be released offsite, nor does the change involve a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the amendment meets the eligibility criteria for a categorical exclusion as set forth in 10CFR51.22(c)(9). Therefore, in accordance with 10CFR51.22(b), an environmental assessment of this amendment is not required.

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