ML17292A758
| ML17292A758 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/22/1997 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17292A757 | List: |
| References | |
| NUDOCS 9704010341 | |
| Download: ML17292A758 (39) | |
Text
REQUEST FOR AMENDMENTTO OPERATING LICENSEREGARDINGTECHNICAL SPECIFICATION RESPONSE TIMETESTING Technical Specification Pages e70OOXOsna 9703m
/7 PDR ADGCK 05000S97i P
PDRj I
'll 'q ll
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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 limits.
24 months on a
STAGGERED TEST BASIS P.,
C.AAUM6L SGM<oas co a.
5udovioAs R. Qb 0
&,Ke Gee.c uWaZ 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 3.c,'.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 /> 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 required S injection/spray s
system is w'n limits.
24 month~
n a
STAgGEREO, TEST 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 FUNCT ION APPLICABLE NODES OR OTHER SPECI FIED CONDITIONS CONDITIONS REFERENCED REOUIRED FRCH CHANNELS PER REQUIRED FUNCTION ACTION A.'I SURVEILLANCE RECUIRENEMTS ALLOMABLE VALVE 1.
LOM Pressure Coolant Injection.A (LPCI) and Lau Pressure Care Spray (LPCS)
Subsystems a.
Reactor Vessel Mater Levet Lou LOM Low, Levet 1
1,2,3, 4('),5 2(b)
SR 3.3.5.1.1 L -148 inches sR 3.3.5.1.2 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 Time Delay ReLay d.
LPCI Pimp A Start LOCA Time Delay Relay e.
LPCI Pulp A Start - LOCA/LOOP Time Delay Retay Reactor Vessel Pr assure LoM (Injection Permissive) 1,2,3, 1.2r3.
(a),5 1,2,3, 4(a) 5(a) 1,2,3 1 per valve C
SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.2 SR 3.3.5.1.3 N
3.3.5.1.6 8 8.53 seconds and 5 10.64 seconds 8 17.24 seconds and 5 21.53 seconds R 3.0C seconds and 5 6.DD seconds N
3.3.5.1.2 8 448 psig SR '.3.5.1.4 and SR 3.3.5.1.6 c 492 psig g.
LPCS Punp Discharge Flou Lau (Hinimm Ftou) h.
LPCI Puap A Discharge F Iou - Lov (Hiniaxm Ftou) i.
Manual Initiation 4,5 1 per valve 1,2,3, 4(a) 5(a) 1,2,3, 4(a) 5(a) 1,2,3, 4(a) 5(a)
SR 3.3.5.1.2 SR 3.3.5.1.4 N
3.3.5.1.6 8 448 psig and S 492 psig b 668 gpn and
+ 1067 gpn SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 sR 3.3.5.1.6 MA SR 3.3.5.1.2 b 605 gpn and SR 3.3.5.1.4 S 984 gpn sR 3.3.5.1.6 (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 FUHCT IOH APPLICABLE KCOES OR OTHER SPECIFIED COHO ITIOHS COHO ITIOHS REFEREHCED RECUIRED FROK CHAHHELS PER REQUIRED FUHCTIOH ACTIOH A.1 SURVEILLAHCE REQUIREKEHTS ALLOMABLE VALUE 3.
HPCS System (continued) b.
Drywell Pressure - High 1,2,3 4(b)
SR 3.3.5.1.2 SR 3.3.5.1.4 3.5.1.6
< 1.88 psig c.
Reactor Vessel Mater Level - High, Level 8 d.
Condensate Storage Tank Level - Low e.
Suppression Pool Mater LeveL - High 1,2,3, 4(a) 5(a) 1,2,3, 4(c) 5(c) 1,2,3 SR 3.3.5.1.1 SR 3.3.5.1.2 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 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6
< 56.0 inches i 448 ft 1 inch elevation
< 466 ft 11 inches elevation f.
HPCS System Flow Rate - Low (KininL!n Flow) g.
KanuaL Initiation 1,2,3, 4(a) 5(a) 1,2,3, I(a) 5(a)
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6
+ 1200 gpn and
< 1512 gpm SR 3.3.5.1.6 HA 4.
Automat'ic 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'wy Discharge Pressure-High 1 Z(d) 3(d) 1 2(d) 3(d) 1 2(d) 3(d)
(d) 3(d)
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5. I.6 SR 3.3.5.1.1 SR 3.3.5.1.2 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
< 115.0 seconds
> 9.5 inches
> 119 psig and
< 171 psig
{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 FUNCTION APPLICABLE, HGOES OR OTHER SPECI F IED COND ITIONS COND IT I ONS REFERENCED REQUIRED FROM CHANHELS PER REQUIRED FUNCTION ACTION A. 1 SURVEILLANCE REQUIREMENTS ALLOMABLE VALUE 2.
Subsystems a.
Reactor Vessel Mater Level LoM Low Lou, Level 1
b.
DryMell Pressure - High 1,2,3,
,s 1,2,3 2(b)
Z -148 inches
< 1.88 ps ig c.
LPCI Punp B Start-LOCA Time Delay Relay d.
LPCI Pwp C Start LOCA Time Delay Relay 1,2,3, 4(a) 5(a) 1,2,3, 4(a) 5(a)
SR '3.3.5.1.5 SR 3.3.5.1.6 8 8.53 seconds and
< 10.64 seconds SR 3.3.5;1.5
> 17.24 SR 3.3 ~5.1.6 seconds and
< 21.53 seconds e.
LPCI Punp B
Start - LOCA/LOOP Time Delay Relay f.
Reactor Vessel Pressure - Low (Injection Permissive) 1,2,3, 4(a) 5(a) 1,2,3 1 per valve 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 3.3.5.1.4 SR 3.3.5.1.6 8 3.04 seconds and
< 6.00 seconds
> C48 psig and
< C92 psig g.
LPCI Pumps B 8 C
Discharge FloM-Lou (Miniaxsn Floe) h.
Manual Initiation 5
1 per valve 1,2,3, 1 per pmp s<a) 1,2,3, 4<a) 5<a)
SR 3.3.5.1.2 SR 3.3.5.1 '
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
> 448 psig and
< 492 psig
> 605 gpa and S 984 gpm NA 3.
High Pressure Core Spray (HPCS) System a.
Reactor Vessel Mater Level - Low Log, Level 2 1,2,3, 4<a),S 4(b)
SR 3.3.5.1-1
> -58 inches SR 3.3.5.1.2 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 t
c
~
Primary Containment lation 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 Surveill'ances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 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 is within limits.
24 months on a
STAGGERED TEST BASIS MNP-2 3.3-54 Amendment No.
149
e 0 1 ~
(it
~- t g C r
ft 4
~ ~
ECCS Operating 3.5.1 SURVEILLANCE REOUIREHENTS continued SURVEILLANCE FREQUENCY SYSTEM 'LOM RATE TOTAL
. DEVELOPED HEAD SR 3.5. 1.4 Verify each ECCS pump develops the specified flow rate with the specified E
developed head.
In accordance with the Inservice
'esting Program LPCS
~ 6350 gpm LPCI
~ 7450 gpm HPCS
~ 6350 gpm
~ 128 psid 26 psid a 200 psid SR 3.5.1.5 NOTE Vessel injection/spray may be excluded.
Verify each ECCS injection/spray 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 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.
injection/spray subsystem is within limits.
24 months WNP-2 3.5-6 Revision A
1 h
a c"'a~
v
~
s r
~
i r
t 4
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 o
~
~
~
~
~
~
Recirculation Loops Operating Jet Pumps Safety/Relief Valves (SRVs) a 25%
RTP Safety/Relief Valves SRVs) < 25% 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 3.4-14 3.4-16 3.4-18 3.4-21 3.4-23 3.4-31 3.5-1 3.5-1 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.
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 limits.
24 months on a
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 <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 /> 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 FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS CONDITIONS REFERENCED REQUIRED FROM CHANNELS PER REQUIRED FUNCTION ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE 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
b.
Drywall Pressure High 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) 1,2,3, 4(a) 5(a) 1 ~ 2I3 1,2,3, 4(a) 5(a) 1,2,3, 4(a) 5(a) 1,2,3, 4(a) 5(a) 1,2,3 2(b) 2(b) 1 per valve SR 3.3 '.1.1 SR 3.3.5.1.2 SR 3.3.5.1 '
SR 3.3.5.1.6 SR 3.3.5 '.2 SR 3.3.5.'I.4 SR 3.3.5.1.6 SR 3.3 '.1.5 SR 3.3 '.1.6 SR 3.3.5 '.5 SR 3.3.5.1.6 SR 3.3 ' '-2 SR 3.3 '.1.3 SR 3.3.5.1.6 SR 3.3.F 1.2 SR 3.3 '.1.4 SR 3.3.5.1.6 h -148 inches S 1.88 psig.
h 8.53 seconds and
< 10.64 seconds 2 17.24 seconds and
< 21.53 seconds 2 3'4 seconds and 5 6.00 seconds 2 448 psig and
< 492 psig g.
LPCS Pump Discharge Flow Low (Minimun Flow) h.
LPCI Pump A Discharge Flow-Low (Minimun Flow) i.
Manual Initiation 4(a),5(a) 1 per valve 8
Ie2e3i 4(a) 5(a) 1,2,3, 4(a) 5(a) 1,2,3, 4(a) 5(a)
SR 3.3.5 ~ 1.2 SR 3.3.5.1.4 SR 3.3.5 '.6 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5 '.6 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3 '.1.6 2 448 psig and S 492 psig
> 668 gpll and 5 1067 gpm
? 605 gpm and
< 984 gpm SR 3.3 '.1.6 HA (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 FUNCTION APPLICABLE MODES OR OTHER SPECIFIED COND IT IOHS CONDITION S REFERENCED REQUIRED FROM CHANNELS PER, REQUIRED FUNCTION ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOMABLE VALUE 2.
Subsystems a.
Reactor Vessel Mater Level Low Low Low, Level 1
b.
Drywall Pressure - High c.
LPCI Pump B Start LOCA Time Delay Relay d.
LPCI Punp C Start - LOCA Time Delay Relay e.
LPCI Pump 8 Start - LOCA/LOOP Time Delay Relay f.
Reactor Vessel Pressure - Low (Injection Permissive)
Ii2I3I 4(a) 5(a) 1 ~ 2i3 g2/ 3@
I(a) 5(a) 1 g2$ 3g 4(a) 5(a) 1,2,3, 4(a) 5(a) 1,2,3 2(b) 2(b) 1 per valve C
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 SR 3.3.5.1.2 SR 3.3 '.1.4 SR 3.3.5.1.6 SR 3.3.5.1.5 SR 3.3.F 1.6 SR 3.3.5.1.5 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 '.1.2 SR 3.3.5.1.4 SR 3.3.5.1-6 2 -148 inches S 1.88 psig 2 17.24 seconds and
< 2'1.53 seconds 2 8.53 secoAds aAd S 10.64 secoAds 2 3.04 secoAds aAd S 6.00 seconds 2 448 psig SAd
< 492 psig g.
LPCI Pumps 8 8 C
Discharge Flow Low (Minilmia Flow) h.
Manual Initiation 1,2,3, 4(a) 5(a) 1 ~ 2I3I 4(a) 5(a) 1 per pump 4,5 1 per valve 8
SR 3.3.5.1.2 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 '.1.6 2 448 psig aAd
< 492 psig 2 605 gpm SAd
< 984 gpm HA 3.
High Pressure Core Spray (MPCS) System a.
Reactor Vessel Mater Level Low Low, Level 2 1,2,3, 4(a) 5(a) 4(b)
SR 3.3.5.1.1 SR 3.3 '.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 2 -58 inches (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 FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS CONDITIONS REFERENCED REQUIRED FROM CHANNELS PER REQUIRED FUNCTION ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 3.
HPCS System (continued) b.
Drywall Pressure High c.
Reactor Vessel Water Level High, Level 8 1 ~ 2/3 1,2,3, 4(a) 5(a) 4(b)
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 5 1>>88 pslg 5 56.0 inches d.
Condensate Storage Tank Level Low e.
Suppression Pool Water Level - High f.
HPCS System Flow Rate Low (Miniaam Flow) g.
Manual Initiation 1,2,3, 4(c) 5(c) 1,2,3 1I2I3I 4(a) 5(a) 4(a) 5(a)
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3 '.1.6 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 SR 3.3 '.1.2 SR 3.3.5.1.4 SR 3.3 '.1.6
> 448 ft 1 inch elevation
< 466 ft 11 inches elevation
> 1200 gpm and S 1512 gpm SR 3.3 ~5.1.6 NA 4.
Automatic Depressurization System (ADS) Trip System A a.
Reactor Vessel Water Level Low Low Low, Level 1
b.
ADS Initiation Timer c.
Reactor Vessel Water Level - Low, Level 3 (Permissive) d.
LPCS Pump Discharge Pressure - High 1 2(d) 3(d)
(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 '.1.4 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 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 SR 3.3.5.1 '
SR 3.3.5.1.4 SR 3.3.F 1.6
> -148 inches 5 115.0 seconds
> 9.5 inches k 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)
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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 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 is within limits.
24 months on a
STAGGERED TEST BASIS WNP-2 3.3-54 Amendment No.
150
ECCS Operating 3.5.1 SURVEILLANCE RE UIREMENTS 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 a 6350 gpm a 7450 gpm a 6350 gpm a 128 psid 26 psid a 200 psid SR 3.5.1.5 NOTE Vessel injection/spray may be excluded.
Verify each ECCS injection/spray 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 WNP-2 3.5-5 (continued)
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 injection/spray subsystem is within limits.
24 months 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 injection/spray subsystem inoperable.
A. 1 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.
Bil Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).
Immediately C.
Two required ECCS injection/spray subsystems inoperable.
Ci I Initiate action to suspend OPDRVs.
AND Immediately 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.
150
(
Iy
a>
~ A 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 Immediately 0.2 AND 0.3 Initiate action to restore one standby gas treatment subsystem to OPERABLE status.
Initiate action to restore isolation capability in each required secondary containment penetration flow path not isolated.
Immediately 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 a 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.
150 i
ECCS Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY
'R 3.5.2.2 Verify, for the required High Pressure Core 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.
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 required ECCS injection/
spray subsystem, the piping is filled with 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.
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 specified flow rate with the specified developed head.
In accordance with the Inservice Testing Program SYSTEM LPCS LPCI HPCS FLOW RATE a 6350 gpm a 7450 gpm a 6350 gpm TOTAL DEVELOPED HEAD a 128 psid 26 psid a 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.
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 inoperable.
A.l AND Verify by administrative means High Pressure Core Spray System is OPERABLE.
Immediately A.2 Restore RCIC System to OPERABLE status.
14 days B.
Required Action and associated Completion Time not met.
B.l AND B.2 Be in MODE 3.
Reduce reactor steam dome pressure to x 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.
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 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 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, with reactor pressure c 1035 psig and a 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 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 x 165 psig, the RCIC pump can develop a flow rate a 600 gpm against a system head corresponding to reactor pressure.
24 months
{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 actual or simulated automatic initiation signal.
24 months MNP-2 3.5-13 Amendment Ne.
150
[
a
~c4
~ t l
REQUEST FOR AME vfENT TO OPERATING LICENSE GARDING TECHNICAL SPECIFICATION RESPONSE TIMETESTING Page 1 of 3 I NIFICANTHAZARD 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
'-'r,
-.'EQUEST FOR AMEN
~ ENT TO OPERATING LICENSE GARDING TECHNICAL v"
SPECIFICATION RESPONSE TIMETESTING 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 fullyfunctional and willnot create the possibility of a new or different kind of accident from any accident previously evaluated.
REQUEST FOR AMENDMENTTO OPERATING LICENSE LARDINGTECHNICAL SPECIFICATION RESPONSE TIMETESTING Page 3 of 3 Operation of WNP-2 in accordance with the proposed amendment change willnot 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 withinthe applicable analyses which enable qualitative assessment of the proper performance of these devices.
Plant and system response to an initiating event willremain 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 ofSelected 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 eligibilitycriteria 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.