ML19324C141
| ML19324C141 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 11/03/1989 |
| From: | LOUISIANA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19324C140 | List: |
| References | |
| NUDOCS 8911150062 | |
| Download: ML19324C141 (21) | |
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,;r' CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 The containment isolation valves specified in Table 3.6-2 shall be 4
OPERABLE with isolation times as shown in Table 3.6-2.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
a With one or more of the isolation valve (s) specified in Table 3.6-2 inoperable, maintain at-least one isolation valve OPERABLE in each affected penetration t
that is open and either:
Restore the inoperable valve (s) to OPERABLE status within a.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation
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position, or c.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at 4
least one closed manual valve or blind flange; or d.
Be in at least HOT STANDBY wit'dn the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.3.1 The isolation valves specified in Table 3.6-2 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.
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i-CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 - Each' isolation valve specified in Table 3.6-2 shall be ' demonstrated OPERABLE at least once per 18 months by:
a.
Verifying that on a containment isolation test signal, each isolation valve actuates to its isolation position.
b.
Verifying that on a containment Radiation-High test signal, each dontainment purge valve actuates to its isolation position.
4.6.3.3 The isolation time of each power-operated or automatic valve of Table 3.6-2 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
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'CONTAlletENT ISOLATION VALVES **
-VALVE MAXIfRM 1
NUpWER NUMBER FilNCTION ISOLATION TIME (Seconds) 4 1.
Containment Isolation (Continued).
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i 68 2SL-F604 (PSL4068)
Steas Generator 810wdown Sample 10 68 2SL-F603 (PSL4048)
Steam Generator Blowdown Sample 10 I
2.
Containment Psrge (CIAS/CPIS)
Containment Purge Inlet 5
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Containment Purge Outlet 5
Containment Purge Outlet 5
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47 2HV-F228A (CAR 20081 Containment Pressure Exhaust 5
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CARS Exhaust 5
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Safety Injection Actuation Signal (SIAS) i 26 1CH-F2501A/B(CVC103)
CVCS Letdown
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Main Steam Isolation Signal (MSIS)
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1 2MS-V602A (MS 124A)
Main Steam N.A.
1 2MS-F714 (SSL 301A)
Main Steam Sample N.A.
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2MS-V6048 (MS 1248).
Main Steam N.A.
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TABLE 3.6-2 (Continued)
CONTAINMENT ISOLATION VALVES **
PENETRATION VALVE MAXIMUM NUMBER NUM3ER FUNCTION ISOLATION TIME (Seconds) 4.
Main Steam Isolation Signal (MSIS) (Continued) 2 2MS-F715 (SSL 3018)
Main Steam Sample N.A.
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Main feedwater N.A.
Emergency Feedwater N.A.
Emergency feedwater N.A.
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Emergency Feedwater N.A.
Emergency Feedwater N.A.
Main Feedwater N.A.
Emergency Feedwater N.A.
Emergency Feedwater N.A.
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Emergency Feedwater N.A.
Emergency Feedwater M.A.
5.
Contain Spray Actuation Signal (CSAS) i' 23 2CC-F146A/B (CC 641)
CCW from RCPs and CEDM Cooler 5
CCW from RCPs and CEDM Cooler 5
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MAIN STEAM LINE ISOLATIO4 VALVES LIMITING CON 0! TION FOR OPERATION 3.7.1.5 Each main steam line isolation valve shall be OPERA 8LE.
APPLICA81LITY:
MODES 1, 2, 3, and 4.
ACTION:
MODE 1
.With one main steam line isolation valve inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status I
within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, be in at least HOT STAN08Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
' MODES 2, 3, and 4 With one main steam line isolation valve inoperable, subsequent operation in 1
MODE 2, 3, or 4 may proceed provided:
i a.
The isolation valve is maintained closed, b.
The provisions of Specification 3.0.4 are not app 1* cable.
Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS L
4.7.1.5 Each main steam line isolation valve shall be demonstrated OPERABLE l
by verifying full closure within 3.0 seconds when tested pursuant to Specification 4.0.5.
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' 3/4.7.1.4 ACTIVITY The limitations on secondery' systes specific activity ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture.
This dose also includes the effects of a coincident 1 gpa primary to secondary tube leak in the steam generator of the affected steam line and a concurrent loss-of-offsite electrical These values are consistent with the assumptions used in the safety l
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u anairs.s 3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVE The OPERAt!LITY of the main steam line isolation valves ensures that no more than one steen generator will blow down in the event of a steam line rupture. This restriction is required to (1) sinialze the positive reactivity effects of the Reactor Coolant System cooldown asso;:iated with the blowdown, and (2) limit the pressure rise within containment in the event the steam line i
i rupture occurs within containment. The OPERABILITY of the main steam isolation valves within the closure times of the Surveillance Requirements are consistent with the assumptions used in the safety analyses.
IL4.'7.2 STEAN GENERATOR PRE 550RE/ TEMPERATURE LIMITATION The limitation on steam generator secondary pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. -The limitation to 115'F and 210 psig is based on a steam generator RTNDT of 40*F and is l
sufficient to prevent trittle fracture.
Below this temperature of 115'F the system pressure must be limited to a maximum of 205 of the secondary hydro-static test pressure of 1375 psia (corrected for instrument error).
Should steam generator temperature drop below 115'F an engineering evaluation of the effects of the overpressurization is required. However, to reduce the poten-tial for brittle failure the steam generator temperature may be increased to a i
limit of 200*F while performing the evaluation. The limitations on the primary L
side of the steam generator are bounded by the restrictions on the reactor coolant systes in $pecification 3.4.6.1.
3/4.7.3 COMPONENT COOLING WATER AND AUXILIARY CC'.~QWENT COOLING WATE L
The OPERABILITY of the component cooling water systes and its corresponding auxiliary component cooling water systes ensures that sufficient coo 1Jng capacity is available for continued operation of safety-related equipment during normal and accident conditions.
The redundant cooling capacity of these systans, assuming a sin used in the safety ana'yses. gle failure, is consistent with the assumptions L
WATERFORD - UNIT 3 8 3/4 7-3 Amendment No. 6
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3/4.6.3 CONTAINMENT ISOLATION VALVES l
LIMITING CONDITION FOR OPERATION t
3.6.3 The containment isolation valves specified in Table 3.6-2 shall be
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OPERABLE with isolation times as shown in Table 3.6-2.
i, APPLICABILITY: MODES 1, 2 S and 4.
ADD ACTION:
j WitLqne 'or taore of the isolation valves ((txcept main steam and ma
\\ Te~gdwater isolation valve D specified in Table 3.6-2 inFpeYableTt5a Wfain d
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at least~bne isolation valve OPERABLE in each affected penetration that is open and either:
Restore the inoperable valve (s) to OPERABLE status within 4 a.
hours, or b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at c.
least one closed manual valve or blind flange; or d.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ADD ACTIONS for main steam and main feedwater isolation are listed under 3.7.1.5.1 and 3.7.1.5.3.
SURVEILLANCE REQUIREMENTS 4.6.3.1 The isolation valves specified in Table 3.6-2 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time.
WATERFORD - UNIT 3 3/4 6-19
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9 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each isolation valve specified in Table 3.6-2 shall be demonstrated OPERABLE at least once per 18 months by:
I Verfying that on a containment isolation test signal, each a.
isolation valve actuates to its isolation position.
b.
Verifying that on a containment Radiation-High test signal, each containment purge valve actuates to its isolation position, t
4.6.3.3 The isolation time of each power-operated or automatic valve of Table 3.6-2 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
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TABLE 3.6-2 (Continued)
CONTAINMENT ISOLATION VAL 7ES 4
MAXIMUM PENETRATION VALVE
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IS0TATION TIME (Seconds)
NUMBER NUMBER 1.
Containment Isolation (Continued) 68 2SL-F604 (PSL406B)
Steam Generator Blowdown Sample 10 68 2SL-F603 (PSL404B)
Steam Generator Blowdown Sample 10 2.
Containment Purge (CIAS/CPIS) 10 2HV-B151A (CAP 103)
Containment Purge Inlet 5
Containment Purge Inlet 5
C>ntainment Purge Outlet 5
Containment. Purge Outlet 5
Containment Pressure Exahust 5
CARS Exhaust 5
3.
Safety Injection Actuation Signal (SIAS) 26 1CH-F2501A/B (CVC103)
CVCS Letdown 10 l
4.
Main Steam Isolation Signal (MSIS)
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1 2MS-V602A (MS124A)
Main Ste N.A.
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' Main Steam Samp~e N.A.
1 2MS-F714 (SSL 301A) j Main Steamh, ADO l
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CONTAINMENT ISOLATION VALVES MAXIMUM PENETRATION VALVE NUMBER NUMBER FUNCTION ISOLATION TIME (Seconds) 4.
Main Steam Isolation Signal (MSIS) (Continued)
N.A.
2 2MS-F715-(SSL 301B)
Main Steam Sample ADD i
3 2W-V823A (W 184A)
Main Feedwater N.A.
N.A.
3 2W-V8473 (EW 229A)
Emergency Feedwater N.A.
3 2W-?848A (EFW 228A)
Emergency Feedwater N.A..
3 2FW-V851B (EW 224A)
Emergency Feedwater N.A.
3 2W-V852A (EW 223A)
4 2W-V824B (W 184B)
Main Feedwater N.A.
i N.A.
4 2W-V849A (EW 229B)
Emergency Feedwater N.A.
4 2FW-V850B (EW 228B)
Emergency-Feedvater N.A.
4 2W-V853A (EW 224B)
Emergency Feedwater N.A.
Emergency Feedwater 5.
Contain Spray Actuation Signal (CSAS) 23 2CC-F146A/B (CC 641)
CCW from RCPs and CEDM Cooler 5
CCW from RCPs and CEDM Cooler S
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TABLE 3.6-2 (Continued)
CONTAINMENT ISOLATION VALVES
~MAXIMLM PENETRATION VALVE NUMBER NUMBER FUNCTION ISOLATION TIME (Seconds) 7.
Other (Continued) 65 13401 Containment Vacuum Relief Excess Flow N.A.
Check Valve N.A.
66 2HA-E637A (HRA128A)
Hydrogen Analyzer Check Valve N.A.
67 2HA-E638B (HRA128B)
Hydrogen Analyzer Check Valve N.A.
69 ISI-V2506 (SI 510A)
SI Hot Leg Injection N.A.
70 ISI-V2508 (SI 510B)
SI Hot Leg Injection 71 2DW-V643 (CMU245)
Demineralized Water Check Valve N.A.
o May be opened en an intermittent basis under administrative control.
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- o The provisions of Specification 3.0.4 are not applicable.
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Refer to Specification 3/4.7.1.5.1 for ACTIONS and SURVEILLANCE REQUIREMENTS.
il Refer to Specification 3/4.7.1.5.3 for ACTIONS and SURVEILLANCE REQUIREMENTS.
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' MAIN STEAM LINE' ISOLATION-VALVES
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.3.7.1.5 Each main steam line isolation valve shall'be OPERABLE.
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.APPLICABILIQ: ' MODE 1, 2 SPC C f o" ~ U 't M * "o ' " 3h * 'd i E.1
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m &,we, c a, 4 s o,% etccet. J Uith one_ mnin steam line isolation-valve inoperable, but. open,(' continue)anwnseo 1.
I (POWER OPERATI0fDprovided the' inoperable valve in restored to OPERABLE within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, then procede to specification 3.7.1.5.2.
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1 SURVEILLANCE REQUIREMENTS
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' 4. 7.1.,
Each main steam line isolation valve shall he demonstrated OPERABLE byyriping full closure withim/their resysst.ive)"'"#
i Gepponse timetimiss' consistent with Table 3.3-5% hen tested so.,, pursuant to SpecifR stlosi U 0.5 '
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At least once per 18 months, each main steam isolation valve shall be demonstrated OPERABLE by verifying that each valve closes,on a MSIS test signal.
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LIMITING COND!i10N FOR OPERATION 3.7.1.5.2 Each main steam line isolation valve shall be OPERABLE.
s APPLICABILITYt.' NODES 3. an:t 4, s
The provisions of Speciffection 3.0.4 are not applicable. % v5'o 'a 55r-Losuo unae 1
' ACTION:
- d' With one main steam line isolation valve inoperable, subsequent operation maykon~tinue provide the isolation valve is maintained closed. Otherwise, be in at least COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />..
SURVEILLANCE REQUIREMENTS 4.7.1.5.2 ThemainsteamIsolationvalvesshallbedemonstrated
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=0PERABLE per the applicable'Surve111ance Requirements of 4.7.1.5.1.
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LIMITING CONDITION FOR OPERATION 3.7.1.5.3 Each main feedwater isolation valve shall be OPERABLE.
,,3 APPLICABILITY: MODE 1, 2 ACTION:
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a)
With just one main feedwater isolation valve inoperable, within 72
{y hours restore the inoperable valve to OPERABLE. Otherwise, be in at c
C least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Then, procede to specification 3.7.1.5.4.
b)
With one main feedwater isolation valve and any valve in.the associated' set of main feedwater control valves inoperable, co.sply
.with ACTION e of 3.7.1.5.5.
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With both main feedwater isolation valves inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> i
restore one inoperable valve to OPERABLE and follow ACTION a.
Otherwlse, be in at least STARTUP within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Then, procede to specification 3.7.1.5.4.
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SURVEILLANCE REQUIREMENTS i
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consistent with Table 3.3-5.
The closure response time will
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be measured when applying Specification 4.0.5 to each feedwater teolation valve.
.4.7.1.5.3.b At least once per 18 months, both feedwater isolation valves.
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shall be demonstrated OPERABLE by verifying that each valve closes on a MSIS test signal.
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3.7.1.5.4 Each main feedwater isolation valve shall be OPERABLE.
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. APPLICABILITY, MODES 3*. 4*
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The provisions of Specification 3.0.4 are not applicable..
ACTION:
With one feedwater isolation valve inoperable, subsequent operation may continue provided the isolation valve is maintrained closed. Otherwise, be i
.in COLD SHUTDOWN within the following 30 hourt.
SURVEILLANCE ~ REQUIREMENTS 1
1:
4.7.1.5.4 The feedwater' isolation valves shall be demonstrated
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.0PERABLE per the applicable Surveillance Requirements of 4.7.1.5.3.
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' FEEDWATER CONTROL VALVEE
- LIMITING CONDITION POR OPERATION 3.7.1.5.5 Each set of' main feedwater control valves shall be OPERABLE.
A' set of main feedwater control valven consists off one main feedwater regulating valve, one associated startup feedwater
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regulating valve, and an associated feedwater regulating bypass valve.
Feedwater regulating bypass valves shall be closed and its operator de-energized. Feedwater' regulating bypass valves H
may be opened on an intermittent basis within. restrictions y
listed in ACTIONS a and b below.
APPL 1CABILITY: NODES 1, 2, 3, and 4*
o The provisions of Specification 3.0.4 are not applicable.
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a)
When a feedwater regulating bypass valve does not meet its LCO in 3.7.1.5.5:and the same train's tain feedwater isolation valve is OPERABLE, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> close the feedwater regulating bypass valve
<-l' and de-energize its operator.
Or, be in at least 110T STANDilY in the p
next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in COLD SHUTI.%'N within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, f.
.b)
When a feedwater regulating bypass valve does not meet its LCO in I
3.7.1.5.5_and the same train's main feedwater isolation valve is
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inopetalile but not closed, follow ACTION e below.
c)
With either startup or regulating valve in one set of main feedwater control valves inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> either restore both the t
startup and the regulating valves to OPERABLE, or be in at least HDT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
d)
.With both feedwater regulating bypass valves open for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or more, either (1) close both feedwater regulating bypass valves, or (2) close d[
one feedwater regulating bypass valve and follow applicable ACTION a t
or b.
Otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, g
and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
e)
With one set of main feedwater control valves and the associated main feedwater isolation valve inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> execute one of i
the followingt (1) restore the affected main feedwater isolation valve to OPERABLE i
and follow ACTION a, b, or c as applicable.
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.(2) close the bypass valve and de-energite the bypass operator and restore the affected regulating and startup valves to OPERABLE.
rollow specification 3.7.1.5.3 ACTION a.
l.
(3) either close, or use block valves to isolate, the inoperable startup or inoperable regulating valve and close the bypass valve and de-energize the bypass operator.
Follow specification 3.7.1.5.3 ACTION a.
Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
f) -With some main feedwater regulating or startup valves in both trains inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> restore one set of main feedwater control valves to OPERABLE and follow ACTION c.
Otherwice, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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. 8 ANT SYSTEMS
- FEEDWATER CONTROL VALVES SURVEILIANCE RIQtt1REMENTS 4.7.1.5.5.a To be operable, a main feedwater regulating valve or startup feedwstet regulating valyn can achieve full closure within their respective recponse time limits shown~on Table 3.3-5.
v' Response time measurements for startup and regulating feedvater valves happen while applying Specification 4.0.5 to them. Compliance with this surveillance is not required for a regulating or startup feedwater valve with its upstream and downstreta block valves closed.
4.7.1.5.5 b At least once per 18 months, each main feedwater regulating.
valve and.startup feedwater regulating valve shall be demonstrated OPERABLE by verifying that each velve closes on i
a MSIS test signal.
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, o AASES 3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity, ensure that the resultant offsite radiation dose will be limited to a small fraction of 10 CFR part 100 limits in the event of a steam line rupture. This dose also includes the effects of a coincident I gpm primary to secondary tube leak in the steam generator of the affected steam line and a concurrent loss-ef-offsite electric power. These values are consistent with the assumptions used in the safety analyses.
3/4.7.1.5 MAIN STEAM ISOLATION AND MAIN FEEDWATER ISOLATION AND CONTROL VALVES TheOPERABIL_ITYoft4mainsteamisolationandmainfeedath h
l li_ sod &oii>nd control valvepensures that no more t ia~li'6ne steam generator
'will T1ow down in the event of fe M C a steam line, or feedwater line rupture.
This restriction is required to (1) minimite the positivo reactivity effeccs of the Reactor Coolcnt System cooldown associated with the blowdown, and (2) limit the pressure rise within containment in the event the steam line rupture occurs within containment. The OPERABILITY of the main steam isolation (and matFliedwater isliT tignan_d congo 1_yM within the closure timestspecT &ed by Table 3.3-5 re consistent with the assumptions used in the safety analyses.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION, The limitation on steam generator secondary pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allowable fracturt toughness stress limits. The limitation to 115'T and 210 psig is based on a steam generator RT f
NDT 40'F and is sufficient to prevent brittle fracture.
Below this temperature of 115*F the system pressure must be limited to a maximum of 20% of the secondary hydrostatic test pressure of 1375 psia (corrected for instrument error).
Should steam generator temperature drop below ll5'T an engineering evaluation of the effects of the overpressuritation is required.
- However, to reduce the potential for brittle failure the steam generator temperature may be increased to a limit of 200'F while performing the evaluation. The limitations on the primary side of the steam generator are bounded by the restrictions on the reactor coolant system in Specification 3.4.8.1.
3/4.7.3 COMPONENT COOLING WATER AND AUXILI ART COMPONENT COOLING WATER SYSTEMS The OPERABILITY of the component cooling water system and its corresponding auxiliary component cooling water system ensures that sufficient cooling capaetty is available for continued operation of safety-related equipment during normal and accident conditions. The redundant cooling capacity of these systems, assuming a single failure, is l
consistent with the assumptions used in the safety analyses.
I WATEP. FORD - UNI'i 3 B 3/4 7-3 Amendment No. 6