ML20072M703
| ML20072M703 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 07/11/1983 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20072M702 | List: |
| References | |
| NUDOCS 8307150070 | |
| Download: ML20072M703 (9) | |
Text
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING SYSTEMS SYSTEMS Applicability Applicability Applies to the operational status of Applies to the Surveillance Require-the core and suppression pool cooling ment of the core and suppression pool subsystems.
cooling subsystems which are required when the corresponding limiting Condi-tion for operation is in effect.
Objective Objective To assure the operability of the core To verify the operability of the core and suppression pool cooling subsystems and suppression pool cooling subsystems under all conditions for which this under all conditions for which this cooling capability is an essential re-cooling capability is an essential re-sponse to station abnormalities.
sponse to station abnormalities.
Specification Specification A.
Core Spray and LPCI Subsystems A.
Core Spray and LPCI Subsystems 1.
Both core spray subsystems shall 1.
Core Spray Subsystem Testing.
be operable whenever irradiated fuel is in the vessel and prior Item Frequency to reactor startup from a Cold Condition, except as specified a.
Simulated Once/ Operating in 3.5.A.2 below.
Automatic Cycle Actuation test.
b.
Pump Once/ month Operability c.
Motor Operated Once/ month Valve ?pera-bility d.
Pump flow rate.Each pump shall deliver at least 3600 gpm against a system head corres-ponding to a reactor ves-(
sel pressure l
at 104 psig.
e.
Header ap 8307150070 830711 Instrumen-PDR ADOCK 05000293 tation p
PDR l
AmendmentNo.g 103
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.5.A Core Spray and LPCI Subsystems 4.5.A Core Spray and LPCI Subsystems (Cont'd)
(Cont'd)
Check Once/ Day Calibrate Once/3 months Test once/3 months 2.
From and after the date that one 2.
When it is determined that one core of the core spray subsystems is spray subsystem is inoperable, made or found to be inoperable the operable core spray subsystem, for any reason, continued reactor the LPCI subsystem and the diesel operation is permissible during generators shall be demonstrated to the succeeding seven days, pro-be operable immediately. The vided that during such seven days operable core spray subsystem all active components of the shall be demonstrated to be other core spray subsystem and operable daily thereafter.
active components of the LPCI subsystem and the diesel gen-erators are operable.
3.
The LPCI Subystems shall be 3.
LPCI Subsystem Testing shall be operable whenever irradiated as follows:
fuel is in the reactor vessel, and prior to reactor startup a.
Simulated Automa-Once/Oper-from a Cold Condition, except tic Actuation ating as specified in 3.5.A.4, Test Cycle 3.5.A.5 and 3.5.F.5.
b.
Pump Operability Once/ month c.
Motor Operated Once/ month Valve Operability l
l l
d.
Pump Flow Once/3 months Three LPCI pumps shall deliver 14,400 gpm against a system head corresponding to a ves-sel pressure of 20 psig.
AmendmentNo.$
104
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT
- 3.5.B Containment Cooling Subsystem 4.5.B Containment Cooling Subsystem 1.
Except as specified in 3.5.B.2, 1.
Containment Cooling Subsystem Test-3.5.B.3, and 3.5.F.3 below, ing shall be as follows:
both containment cooling subsys-tem loops shall be operable when-Item Frequency ever irradiated fuel is in the reactor vessel and reactor coolant a.
Pump & Valve Once/3 months temperature is greater than 212'F, Operability and prior to reactor startup from a Cold Condition.
b.
Pump Capacity After pump Test.Each RBCCW maintenance pump shall deli-and every 3 ver 1700 gpm months at 70 Ft. TDH.
Each SSWS pump shall deliver 2700 gpm at 55 ft. TDH.
c.
Air test on Once/5 years drywell and torus headers and nozzles l
- Conditional relief granted from this LCO for the period October 31, 1980 through November 7, 1980.
l Amendment No. %
106
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT
- 3.5.B Containment Cooling Subsystem 4.5.B Containment Cooling Subsystem (Cont'd) 2.
From and after the date that one 2.
When one containment cooling sub-containment cooling subsystem loop system loop becomes inoperable, the is made or found to be inoperable operable subsystem loop and its for any reason, continued reactor associated diesel generator shall operation is permissible only dur-be demonstrated to be operable im-ing the succeeding seven days mediately and the operable contain-unless such subsystem loop is ment cooling subsystem loop daily sooner made operable, provided thereafter.
that the other containment cooling subsystem loop, in-cluding its associated diesel generator, is operable.
3.
If the requirements of 3.5.B can-not be met, an orderly shutdown shall be initiated and the reac-tor shall be in a Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C.
HPCI Subystem C.
HPCI Subsystem 1.
The HPCI Subsystem shall be oper-1.
HPCI Subsystem testing shall be able whenever there is irradiated performed as follows:
fuel in the reactor vessel, reactor pressure is greater than 104 psig, a.
Simulated Once/ operating and prior to reactor startup from Automatic cycle a Cold Condition, except as speci-Actuation fied in 3.5.C.2 and 3.5.C.3 below.
Test b.
Pump Opera-Once/ month bility c.
Motor Opera-Once/ month ted Valve Operability d.
Flow Rate Once/3 months at 1000 Psig e.
Flow Rate Once/ operating at 150 psig cycle
- Conditional relief granted from this LCO for the period October 31, 1980 through November 7, 1980.
Amend. ment No. $
107
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT i
3.5.C HPCI Subsystem (Cont'd) 4.5.C HPCI Subsystem (Cont'd)
The HPCI pump shall deliver at least 4250 sps for a system head corresponding to a reactor pres-sure of 1000 to 150 psig.
2.
From and after the date that the 2.
When it is determined that the HPCI HPCI Subsystem is made or found to Subsystem is inoperable the RCIC, be inoperable for any reason, con-the LPCI subsystem, both core spray tinued reactor operation is per-subsystems, and the ADS subsystem missible only during the succeed-actuation logic shall be demon-ing seven days unless such subsys-strated to be operable immediate-tem is sooner made operable, pro-ly. The RCIC system and ADS sub-viding that during such seven days system logic shall be demonstrated all active components of the ADS to be operable daily thereafter.
subsystem, the RCIC system, the LPCI subsystem and both core spray subsystems are operable.
3.
If the requirements of 3.5.C can-not be met, an orderly shutdown shall be initiated and the reac-tor pressure shall be reduced to or below 104 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.5.D Reactor Core Isolation Coolina 4.5.D Reactor Core Isolation Cooling (RCIC) Subsystem (RCIC) Subsystem 1.
The RCIC Subsystem shall be oper-1.
The RCIC Subsystem testing shall able whenever there is irradiated be performed as follows:
fuel in the reactor vessel, the reactor pressure is greater than a.
Simulated Once/ operating 104 psig, and prior to reactor Automatic cycle startup from a Cold Condition, Actuation except as specified in 3.5.D.2 Test below.
b.
Pump Opera-Once/ month bility i
l l
c.
Motor Opera-Once/ month ted Valve j
Operability l
1 l
Amendment No. $
108
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT f
<3.5.D R: actor Cora Isolation Cooling 4.5.D Reactor Cara Isoletion Cooling (RCIC) Subsystcn (C:nt'd)
(RCIC) Subsysten (Cont'd) d.
Flow Rate once/3 months at 1000 Psig e.
Flow Rate Once/ operating at 150 cycle Psig The RCIC pump shall deliver at least 400 gpm for a system head corresponding to a reac-tor pressure of 1000 to 150 psig.
2.
From and after the date that the 2.
When it is determined that the RCIC RCICS is made or found to be inop-subsystem is inoperable, the HPCIS able for any reason, continued shall be demonstrated to be oper-reactor power operation is permis-able immediately and weekly there-sible only during the succeeding after.
seven days provided that during such seven days the HPCIS is oper-able.
3.
If the requirements of 3.5.D cannot be met, an orderly shutdown shall be initiated and the reactor pres-sure shall be reduced to or below 104 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.5.E Automatic Depressurization 4.5.E Automatic Depressurization System (ADS)
System (ADS) 1.
The Automatic Depressurization Sub-1.
During each operating cycle the system shall be operable whenever following tests shall be performed there is irradieted fuel in the on the ADS:
reactor vessel and the reactor a.
A simulated automatic actua-pressure is greater than 104 psig and prior to a startup from a tion test shall be performed Cold Condition, except as speci-prior to startup after each fied n 3.5.E.2 below.
refueling outage.
b.
With the reactor at pressure, each relief valve shall be manually opened until a cor-responding change in reactor pressure or main turbine by-pass valve positions indicate that steam is flowing from the valve.
i 109 AmendmentNo.Q l
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,3. 9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM Applicability:
Applicability:
Applies to the auxiliary electrical Applies to the periodic testing re-power system.
quirements of the auxiliary elec-trical systems.
l Objective:
Objective:
i To assure an adequate supply of elec-Verify the operability of the trical power for operation of those auxiliary electrical system.
systems required for safety.
Specification:
Specification:
A.
Auxiliary Electrical Equipment A.
Auxiliary Electrical Equipment Surveillance The reactor shall not be made criti-1.
Diesel Generators cal unless all of the following con-ditions are satisfied.
a.
Each diesel generator shall be manually started and loaded once 1.
At least one offsite transmission each month to demonstrate opera-line and the startup transformer tional readiness. The test shall are available and capable of auto-continue for at least a one hour natically supplying auxiliary power period at rated load.
to the emergency buses.
i During the monthly generator test 2.
An additional source of offsite power the diesel generator starting air consisting of one of the following:
compressor shall be checked for operation and its ability to re-a.
A transmission line and shutdown trans-charge air receivers. The opera-former capable of supplying power to tion of the diesel fuel oil trans-the emergency 4160 volt buses.
fer pumps shall be demonstrated, and the diesel starting time b.
The main transformer and unit auxiliary to reach rated voltage and fre-transformer available and capable of quency shall be logged.
supplying power to the emergency 4160 volt buses.
3.
Both diesel generators shall be oper-able. Each diesel generator shall have a minimum of 19,800 gallons of diesel fuel on site.
I b.
Once per operating cycle the con-dition under which the diesel gen-erator is required will be simu-lated and a test conducted to dem-onstrate that it will start and accept the emergency load within the specified time sequence. The results shall be logged.
Amendment No. $
194
4.12G Alternate Shutdown Panels
'3.12G Alternate Shutdown Pan 21s 1.
Alternate shutdown panels for the 1.
Components listed below shall be ocerated systems listed below shall be OPER-from the alternate shutdown panels once/
ABLE at all times that the system cycle.
is required to be operable except as specified in 3.12G.2.
Core Spray Mot r operated valves.
a.
Core Spray b.
RHR RHR c.
RBCCW j
i d.
Salt Service Water Motor operated valves utilizing the MCC t
e.
HPCI B-17 alternate power source.
f.
RCIC g.
Automatic Depressurization SSWS h.
Diesel Generators pg,p3, 2.
With any of the alternate shutdown RBCCWS panels inoperable, imediately verify that fire detection with Pumps and motor operated valves.
l automatic fire suppression for the Cable Spreading Room is OPERABLE.
2.
Alternate shutdown panel capability for the If fire detection with automatic systems listed below shall be verified to fire supression cannot be deter-be operable once/ cycle.
mined operable, take appropriate action as described in Section RCIC 3.12.D of the Tech. Specs.
l HPCI i
3.
The systems listed below shall be tested as follows:
AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) l Perform a test from the alternate shutdown I
panel to verify that the relief valve solenoids actuate. Test shall be perfomed after each refueling outage prior to startup DIESEL GENERATORS Once/ refueling outage the diesel generator control circuits shall be isolated from the Cable Spreading Room and the diesel generator started.and loaded.
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BASES ITM Alternate Shutdown Panals t
l The alternate shutdown system, independent of cabling and equipment in the j
Cable Spreading Room is provided to effect safe shutdown of Pflgrim in the event of a fire in the Cable Spreading Room. This is accomplished by in-i stalling isolation switches for safety-related equipment that will provide the capability for the plant operators to reach a safe shutdown condition.
1 These switches will isolate their associated equipment from the CSR cables.
l thus transfer control from the Control Room to the local emergency shut-j down stations outside the CSR. These isolation switches are located in alternate shutdown panels and are located as close as practical to the I
j j
equipment or switchgear they serve.
The operability of the fire suppression and detection system in the Cable Spreading Room in conjunction with the passive element of cable coating ensures that adequate fire protection / detection / suppression capability is 4
i available to quickly detect, confine and extinguish fires occurring in any portion of the room where safety-related equipment is located. The fire detection / suppression system consists of an independent smoke detection system, an automatic Halon 1301 Fire Suppression system and fire hose stations available outside the doorways to the Cable Spreading Room. The i
collective capability of passive protection and detection with either manual or automatic suppression is adequate to minimize potential damage to safety-related equipment and is a major element in the facility fire protection program.
An emergency shutdown procedure, which is etapatible with the design modifi-cations and plant operator availability, provides step-by-step actions to i
initiate safe shutdown operation.
Operator actions to isolate safety-related j
cables passing through the CSR is initiated as soon as a fire which is not immediately extinguishable is detected and confimed in the CSR.
l Alternate shutdown panels are provided for the following systems:
1 i
a.
b.
RHR c.
RBCCW f
d.
Salt Service Water 4
e.
HPCI i
f.
RCIC g.
Automa. tic Depressurization System h.
Diesel Generators Inoperability of the above listed systems does not require entry into LCO action statements for the alternate shutdown panels.
A surveillance frequency of once per cycle is considered prudent and more frequent testing not warranted. The frequency of once per refueling outage for ' testing the diesel generators prevents unnecessarily rendering them inoperable during nomal power operation. The frequency of once per refuel-ing outage for the Automatic Depressurization System is consistant with the existing surveillance frequency for this system.
Requiring this surveillance to be perfomed during a refueling outage will also assure that plant condi-tions will allow for safe access to the ADS solenoids.
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