ML20012D449
| ML20012D449 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/15/1990 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20012D448 | List: |
| References | |
| NUDOCS 9003270340 | |
| Download: ML20012D449 (40) | |
Text
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7 LIMITING CONDITION FOR OPERATION SURVEILLANCE RE0VIREMENT 3.5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING 4
SYSTEMS SYSTEMS Aeolicability Apolicability.
Applies to the operational status of Applies to the Surveillance the core and suppression pool cooling Requirements of the core and suppression pool cooling systems which-l
- l. systems..
are required when the corresponding Limiting Condi_ tion for operation is in effect.
i
- 0biective' Obiective j
To assure the operability of the core To verify the operability of the core l and suppression pool cooling systems and suppression pool cooling systems l
4 under all conditions for which this under all conditions for which this l
cooling capability is a'n essential cooling capability is an essential response to station abnormalities, response to station abnormalities.
- ]
f Soecification Soecification l A.
Core Sorav and LPCI Systems l
A.
Core Sorav and LPCI Systems l~
l
]
.1.
Both core spray systems shall be l.
operable whenever irradiated fuel 1.
Core Spray System Testing.
R is in the vessel and prior to
- reactor startup from a Cold LtRG Freauency Condition, except as specified in 3.5.A.2 below, a.
Simulated Once/ Operating Automatic Cycle Actuation test, b.
Pump Operability-Once/ month c.
Motor Operated Once/ month Valve Operability j
d.
Pump flow rate Once/3 months Each pump shall deliver at least 3600 gpm against a system head corresponding to a reactor vessel
{
pressure of 104 psig.
e.
Core Spray Header 6 p Instrumentation Revision 177 Amendment No.'42, 62, Ild 103
^
LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT
-3.5.A Core Sorav and LPCI Systems-4.5.A. Core Sorav and LPCI Systems (cont'd)
(cont'd)
Check Once/ day Calibrate.
Once/3 months i
Test Step Once/3 months 2.
From and after the date that one 2.
This section intentionally left l-
.of the core spray systems is made blank or found to be inoperable for any reason, continued reactor 3.
LPCI system Testing shall be as operation is permissible during follows:
the succeeding seven days, provided that during such seven
- a. Simulated Once/ Operating days all active components of the Automatic Cycle other core spray system and active Actuation components of the LPCI system and Test the diesel generators are operable.
- b. Pump Once/ month 3.
The LPCI system shall be operable Operability whenever irradiated fuel is in the reactor-vessel, and prior to
- c. Motor Operated Once/ Month reactor startup from a Cold valve
' Condition, except as specified in operability l
'3.5 A.4 and 3.5.F.5.
- d. Pump Flow Once/3 months
- 4. -From and after the date-that the 4
'l LPCI-system is made or found to be Each LPCI pump'shall pump 4800 inoperable for any reason, gpm at a head across the pump continued reactor operation is of at least 380 ft.
permissible only during the succeeding seven days unless it is sooner made operable, provided l
that during such seven days the
~j containment cooling system (including 2 LPCI pumps) and active components of both core
.l-spray systems, and the diesel generators required'for operation of such components if no external source of power were available shall be operable.
l 5.
If the requirements of 3.5.A cannot be met, an orderly shutdown of the reactor shall be initiated and the reactor shall be in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Revision Amendment No.
104
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This Page Intentionally Left Blank 1;
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Revision Amendment No.
105 a.
(
LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT
'[3.5.B.ContainmentCoolinaSystem 4.5.B Containment Coolina System l.
1.
Except as specified in 3.5.B.2 1.
Containment Cooling system
'l '
and 3.5.F.3 below, both Testing shall be as follows:
containment cooling. system loops shall be operable whenever Ltam Freauency irradiated fuel is in the reactor vessel and reactor coolant a.
Pump & Valve Once/3 months.
temperature is greater than Operability 212'F, and prior to reactor-startup from a Cold Condition, b.
Pump Capacity After pump Test Each RBCCH maintenance
'2. - From and-after the date that one pump shall and every 3 containment cooling system loop deliver 1700 gpm months is made or found to be inoperable at 70 ft. TDH.
for any reason, continued reactor Each SSHS pump operation is permissible only shall deliver 2700 during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> gpm at 55 ft. TOH.
unless such system. loop is sooner made operable, provided_ that the c.
Air test on
-Once/5 years l
other containment cooling system drywell and loop, including its associated torus headers l:-
diesel generator, is operable, and nozzles
- 3. -If the requirements of 3.5.B cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a Cold l
Shutdown Condition within 24 L
hours ~.
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Revision l
Amendment No.
106 l
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- LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT C.
-1.
The HPCI system shall be operable 1.
HPCI system testing shall be l~
- whenever there is irradiated fuel-performed as follows
- in the reactor vessel, reactor-pressure is greater than 150
- a. Simulated Once/ operating L
psig, and reactor coolant Automatic cycle temperature is greater than Actuation-
-365'F; except as specified in Test 3.5.C.2 below.
- b. Pump Oper-Once/ month
- 2.. From and after the date that the ability HPCI-system is made or foundlto be inoperable for any reason,
- c. Motor Operated Once/ month continued reactor operation is Valve Oper-permissible only during the.
ability c
succeeding seven days unless such system is sooner made operable,
- d. Flow Rate at Once/3 months providing that during such seven 1000 psig days all active components of the-ADS system, the RCIC system, the
- e. Flow Rate at.
Once/ operating LPCI system and both core spray 150 psig cycle systems are operable.
The HPCI pump shall deliver at least 3.
If the requirements of 3.5.C 4250 gpm for a system head cannot be met, an orderly corresponding to a reactor pressure of shutdown shall be initiated and 1000 to 150 psig.
the-reactor pressure shall be reduced to or below 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Revision Amendment No.
107
g,2 LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT
. - 3.5.D t ! Reactor' Core Isolation Coolina
- 4. 5. D.
Reactor Core Isolation Coolina S 111m (RCIC) System
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(RCIC)
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The RCIC system shall be oper'able 1.
RCIC system testing shall be k
whenever.there is irradiated fuel performed as follows:
in the reactor vessel, reactor 6
pressure is greater than 150 a.
Simulated Once/ operating.
psig, and-reactor coolant Automatic cycle temperature is greater than Actuation'
'365'F; except as specified in Test
.3.5 D.2 below,
~ Once/ month-b.
Pump 2.
From and after the date that the Operability RCICS is made or found to be
. inoperable for any reason, c.
Motor Once/ month continued reactor power operation Operated is permissible only,during the Valve
. succeeding seven days provided Operability.
1that during such.seven days the HPCIS is operable, d.
Flow Rate at Once/3 months 1000 psig 3.
If the requirements of 3.5.D
'cannot be met, an orderly e '.
Flow Rate at Once/ operating
- shutdown:shall'be initiated and 150 psig-cycle the reactor pressure shall be reduced to or-below=150 psig The RCIC pump shall deliver at
.within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.-
'least 400 gpm for a. system head corresponding to a reactor pressure of 1000 to 150 psig..
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Revision
' Amendment No.
108
s LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT 3.5; E R Automati c - Deores surization -
-4.5.E Automatic: Deoressurization System (ADS)~
System (ADS) 1.
During each operating cycle the l
l=
The Automatic Depressurization-System shall'be operable whenever following tests shall be performed there is irradiated fuel in the on the ADS:
reactor vessel'and the' reactor pressure is greater than 104 psig a.
A simulated automatic actuation and prior to a startup from a-test shall be performed prior Cold Condition,.except as to startup after each refueling specified in 3.5.E.2 below.
outage.
The ADS manual inhibit switch will be included in this 2.
From and after the date that one test.
, c.
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valve in the Automatic l
Depressurization System is made b.
With the reactor at pressure, or found to be inoperable for any each relief valve shall be reason, continued reactor.
manually opened until a.
operation is permissible only corresponding change in reactor during the succeeding seven days pressure or main turbine bypass unless such valve is sooner made valve positions indicate that operable, provided that during steam is-flowing from the valve.
l-such seven days the HPCI system is operable.
3.
If the requirements of 3.5.E cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall be reduced to at least 104 psig-within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Revision
. Amendment No.
109
LIMITING CONDITION FOR OPERATION' SURVEILLANCE REOUIREMENT 3.5.F Minimum Low' Pressure Coolin'a and Diesel Generator Availability 1.
_During any period when one diesel
- generator is inoperable,
-continued reactor operation is permissible only during the
- l succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless such diesel generator is sooner made operable, provided that all of-the low pressure core and
_l containment cooling systems and the remaining diesel generator shall be operable.
If this requirement cannot be met, an orderly shutdown shall be i
initiated and the reactor shall l
be placed in'the Cold Shutdown
,j Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
-2.
Any combination of inoperable components in the core and containment cooling systems shall not defeat'the capability of the H
remaining operable, components to fulfill the. cooling functions.
l 3,
When irradiated fuel is in the re-l actor vessel and the reactor is in -
the Cold Shutdown condition, both core spray systems, the'LPCI and containment cooling systems may be. inoperable, provided no work is being done which has the potential-for draining the reactor vessel.
4.
During a refueling outage, for a-period of-30 days,-refueling oper-ation'may continue provided that one core spray system or the LPCI
-system is operable or Specification 3.5.F.5'is met.
5.
When irradiated fuel is in the reactor vessel and the reactor is in the Refueling Condition with the torus drained, a single control rod drive mechanism may be removed, if both of the following conditions are p
satisfied:
Revision l
Amendment No.
110
9 LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT
' m 3.5.F-Minimum-Low Pressure Coolina and Diesel Generator Availability a)' No work on the reactor'ves-
"sel, in addition to CRD re-moval, will be performed which has the potential for i
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exceededing the maximum 1eak rate from a single control. blade seal if it became unseated, b) -1) the core spray systems are operable and aligned
.with a suction path from the-condensate storage tanks.
i i ).the condensate storage tanks shall contain at least 200,000 gallons of usable water and the refueling cavity and dryer /
separator pool shall be flooded to a least L
elevation 114'-0" 3.5.G (Intentionally left blank) 3.5.H Maintenance'of Filled Discharae 4.5.H Maintenance of Filled Disch,argg EiDA EiDA Whenever core spray systems, LPCI The following. surveillance requirements system, HPCI or RCIC are required to shall be adhered to to assure that the be operable, the discharge piping from discharge piping of the-core spray L
the' pump discharge of these systems to systems, LPCI system, HPCI and RCIC-are
.l
'the last block valve shall be filled, filled:
1.
Every month prior to the-testing of the LPCI system and core spray l:
systems, the discharge piping of these systems shall be vented from i.
the high point and water flow observed.
2.
Following any period where the LPCI system or core spray systems have l
not been required to be operable, l
s the discharge piping of the inoperable system shall be vented from the high point prior to the return of the system to service.
Revision Amendment No.
111 h
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' LIMITING CONDITION'FOR OPERATION SURVEILLANCE REOUIREMENT
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4.5.HL
' Maintenance of Filled -
i Discharae Pine-(Cont'd) 3.
Hhenever the HPCI or RCIC system is. lined up to_take suction.from the torus, the discharge piping of' the HPCI-and RCIC-shall be vented
-from the high' point-of the' system
-and water flow observed on a-monthly basis.
4.
The pressure switches'which-monitor the discharge lines to-ensure that they are full shall-be functionally tested every month
.and calibrated every three months.
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' Revision Amendment No.
112
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O; 3.5.A Core Sorav and LPCI System
'This specifibation assures that adequate emergency cooling capability is available whenever irradiated fuel is in the reactor vessel.
Based on the loss of coolant analysis performed by General Electric in 1
accordance with Section 50.46 and Appendix K of 10CFR50, the Pilgrim I Emergency Core Cooling Systems are adequate to provide sufficient cooling to the core to dissipate the energy associated with the loss of coolant accident,.
.I to limit calculated fuel clad temperature to less than.2200*F, to limit calculated local metal water reaction to less than or equal to 17%, and to limit calculated core wide metal water reaction to less than or equal to 1%.
Core spray distribution has been shown, in full-scale tests of systems similar in design to that of Pilgrim, to exceed the minimum requirements by at least 25%.
In addition, cooling effectiveness has been demonstrated at less than half the rated flow in simulhted fuel assemblies with heater rods to duplicate the decay heat characteristics of irradiated fuel.
The accident analysis takes credit for core spray flow into the core at vessel pressure below 205 psig.
However, the analysis is conservative in that no credit is taken for spray cooling heat transfer in the hottest fuel bundle until the pressure at rated flow for the core spray (104 psig vessel pressure) is reached.
The LPCI system is designed to provide emergency cooling to the core by flooding in the event of a loss-of-coolant accident. This system functions in combination with the core spray system to prevent excessive fuel clad temperature. -The LPCI system and the core spray system provide adequate l
cooling for break areas of approximately 0.2 square feet up to and including the double-ended recirculation line break without assistance from the high pressure emergency core cooling systems.
The combination of the core spray systems and the LPCI system assures that
-adequate core cooling is achieved assuming any coincident single failure of an active safety-related component. Core Standby Cooling System (CSCS) performance evaluations consider only the most severe single failure for each break size range.
These single failures include the LPCI injection valve, one diesel generator, the HPCI system or one ADS valve. With these single failures, the combinations of analyzed low pressure CSCS capacity include two core spray pumps, one core spray pump and two LPCI pumps, or two core spray and four LPCI pumps.
Each core spray system consists of one pump and associated piping and valves with all active components required to be operable.
The LPCI system consists of four LPCI pumps and associated piping and valves with all active components required to be operable.
l Revision Amendment No.
113
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A&SES:
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3.5 A Core Sorav-and LPCI-Systemse (Cont'd) 4 l
s Should one_ core spray system become inoperable, the remaining core spray and i
W; ne the,LPCIcsystem are available should the need for core cooling arise.
Based.
on judgments of the reliability of the remaining systems; i.e., the core spray j
'and LPCI, a seven-day repair period was obtained.
l If the LPCI system is not available, at least 2 LPCI pumps must be available to fulfill the containment cooling function.
Based on judgments of the reliability. of the remaining core spray systems, a 7-day repair period was set.
The.LPCI system is not considered inoperable when the RHR System is. operating i
in the shutdown cooling mode.
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Revision Amendment No.
114 I
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BASES:
3.5.8 Containment Coolina System The containment cooling system for Pilgrim I consists of two independent loops-each of which to be an operable loop requires one LPCI pump, two RBCCH pumps.
and two SSH pumps to be operable. There are installed spares for margin above the _ design conditions. - Each sysgem has the capability to perform its function; i.e., removing 64 x 10 Btu /hr (Ref. Amendment 18). even with some l
system degradation.
If one loop is out-of-service, reactor operation is permitted for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
With-components or systems out-of-service, overall core and containment cooling reliability is maintained by the operability of the remaining cooling equipment.
Since some of the SSH and RBCCH pumps are required for normal operation, l
capacity testing of individual pumps by direct flow measurement is impractical. _The pump capacity test is a comparison of measured pump performance parameters to shop performance _ tests combined with a comparison to the performance of the previously tested pump. These pumps are rotated during operation and performance testing will be integrated with this or performed during refueling when pumps can be flow tested individually.
Tests during normal operation will be performed by measuring the shutoff head.
Then the pump under test will be placed in service and one of the previously operating pumps secured.- Total flow indication for the system will be compared for the two cases. Where this is not feasible due to changing system conditions, the pump discharge pressure will be measured and its power requirement will.be used to establish flow at that pressure.
Revision Amendment No.
115
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3.5.C lEl
'The: limiting conditions for operating the HPCI System are derived from the
-l Station. Nuclear. Safety Operational Analysis -(Appendix G) and a detailed functional-analysis of the HPCI System (Section 6).
h The HPCIS is provided to assure that the reactor core is adequately cooled to limit fuel clad temperature in the event of a small break in the nuclear system and loss-of-coolant which does not result in rapid depressurization of
-the reactor vessel'. The HPCIS permits the reactor to be shut down while maintaining sufficient reactor vessel water level inventory until the vessel is depressurized.
The HPCIS continues to operate until reactor vessel F
' pressure is-below the pressure at which LPCI operation or Core Spray System operation maintains core cooling, y
The capacity of the system is selected to provide this required core cooling.
The HPCI pump is designed to pump 4250 gpm at reactor pressures between 1100 and 150 psig.
Two sources of water are available.
Initially.-demineralized.
water from the condensate storage tank is used instead of injecting water from the suppression pool into the reactor.
When the NPCI-System begins operation, the reactor depressurizes more rapidly
~
than would occur if HPCI was not initiated due to the condensation of steam by B.
the: cold fluid pumped into the reactor vessel by the HPCI System. As the reactor vessel pressure continues to decrease, the HPCI flow momentarily reached equilibrium with the flow through the break.
Continued depressurization causes the break flow >to decrease below the HPCI flow and the-
' liquid inventory.begins-to rise.
This type of response is-typical of.the small breaks.
The core never uncovers and is continuously cooled throughout the transient.so that no core damage of any kind occurs for breaks that lie within the capacity range of the HPCI.
LThe analysis in the FSAR,' Appendix G, shows that the AD'S provides a single
' failure proof path for depressurization for postulated transients and accidents.
The RCIC-is required as an alternate source of makeup to the HPCI only:in the case of loss of all offsite A-C power.
Considering the HPCI and the ADS.plus RCIC as redundant paths, and considering' judgments of the reliability of the ADS and RCIC systems, a 7-day allowable repair time is specified.
1The requirement that HPCI be operable when reactor coolant-temperature is greater that 365'F is included in Specification 3.5.C.1 to clarify that HPCI ineed.not be operable during certain testing (e.g., reactor vessel hydro testing at high reactor pressure and low reactor coolant temperature).
365'F is approximately equal to the-saturation steam temperature at 150 psig.
Revision Amendment No.
116
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l BASES:.
o 3.5.D RCIC System
' The'RCIC is designed to provide makeup to-the nuclear system as part of the (planned operation-for-periods when the normal heat sink is unavailable.
The nuclear safety analysis,-FSAR Appendix G, shows-that RCIC also serves as redundant makeup system on total-loss of all offsite-power in the event that
~ HPCI is unavailable.
In all other postulated accidents and' transients, the ADS provides redundancy for the HPCI.
Based on this and judgments on the I
reliability.of the HPCI system, an allowable repair time of seven days is specified.
The requirement that RCIC be operable when reactor coolant temperature is greater than 365'F is included in Specification 3.5.D.1 to clarify that RCIC need not be operable during certain testing (e.g., reactor vessel. hydro testing at high reactor pressure and low-reactor coolant temperature).
365'F is-approximately equal to the saturation steam temperature at 150 psig.
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h Revision 1
Amendment No.
117
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BASES:
C 3.5.E Automatic Deoressurization System (ADS)
'The limiting conditions for operating the ADS are derived from the Station Nuclear Operational Analysis (Appendix G) and a detailed functional analysis-
- of the ADS (Section 6).
This specification ensures the operability of the ADS under all conditions for
-which the automatic or manual depressurization of the nuclear system is.an r
essential-response to station-abnormalities.
The nuclear system pressure relief system provides automatic nuclear system depressurization for small breaks _in the nuclear system so that the low pressure coolant injection (LPCI) and the core spray systems can operate to l
protect the fuel barrier.
Because the Automatic Depressurization System,does not. provide makeup to the reactor _ primary vessel, no credit is taken for the steam cooling of the core caused-by the system actuation to provide further conservatism to the CSCS.
Performance analysis of-the Automatic Depressurization System is considered only with _ respect to its depressurizing effect in conjunction with LPCI or Core Spray. There are four valves provided and each has a capacity of 800,000 lb/hr at a reactor pressure of 1125 psig.
The allowable out of service time for one ADS valve is determined as seven days because of the redundancy and because of HPCIS operability; therefore, redundant protection for_the core with a small break in the nuclear system is still available~.
-The ADS test circuit permits continued surveillance on the operable relief valves to assure that they will be available if required.
Revision Amendment No.
118
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BASESr 3.5;H.
Maintenance of' Filled Discharae Pine.
- If the discharge piping of the core spray, LPCI system, HPCI, and RCIC are'not-
~
filled,1a water hammer can develop in this piping when the pump and/or pumps-E x
4-r are started.: - An analysis has been-done.which shows that if a water. hammer
- werecto occur:at;the~ time at which the system were required, the system would still_ perform its design function.- However, to minimize damage to the discharge piping and to ensure'added margin in the operation of these systems,
- this: Technical Specification requires the discharge lines to be filled whenever the system is in an operable condition.
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'4.5 Core an'd Con'tainment Coolina Systems Surveillance Frecuencies
~ The testing interval for the core and containment cooling systems is based on industry practice, quantitative reliability analysis, judgment and
-practicality.1 The-core cooling systems have not been designed to be fully.
> testable during operation.
For example, in the' case of the HPCI,-automatic
. initiation during power operation would result in pumping cold water into the-reactor vessel which is not desirable.
Complete ADS testing during power operation causes.an' undesirable loss-of-coolant inventory.
To increase the availability of_the core:and containment cooling systems, the' components which make up the-system;; i.e., instrumentation, pumps, valves, etc., are tested L
frequently.. The pumps and motor operated injection valves 'are also tested each month'to~ assure their operability. A simulated automatic actuation test-once each cycle combined with monthly tests of the pumps and injection valves zis-deemed to be adequate testing of these systems.
The surveillance requirements provide adequate assurance that the core and containment cooling systems will be operable when required.
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l Revision L
Amendment No.
122 1
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BASES:- (Cont'd) 4,g The diesel fuel oil quality must be checked to ensure proper operation of the diesel generators. Hater. content should be minimized because water in the
. fuel could contribute to excessive damage to the-diesel engine.
The Electrical Protection' Assemblies (EPAs) on the RPS inservice power supplies (either two motor generator sets or one motor generator and the.
alternate _ supply), consist of protective relays that trip their-incorporated circuit breakers on overvoltage, undervoltage or underfrequency. conditions.
.There are-2-EPAs in series per. power source.
It'is_necessary to periodically test.the relays to ensure the sensor is operating correctly and to ensure the trip unit _is operable.
Based on experience at conventional-and nuclear power =
1
- plants, a six. month frequency for the channel functional test is established.
This frequency is consistent with the Standard Technical Specifications.
LThe EPAs of the power sources to the RPS>shall be determined.to be operable by performance of a channel calibration of the' relays once per operating cycle.
During calibration, a transfer to the alternate power source is required;-
- however,-prior to switching to alternate feed, de-energiration of the applicable MG set power source must;be accomplished. This results in a
-half-scram on.the< channel being calibrated until the alternate power source is
- t-
' connected and the half scram is cleared.
Based on operating experience, drift -
of.the EPA protective relays is not significant. -Therefore, to avoid possible spurious scrams, a calibration frequency-of once per' cycle is established.
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' Amendment No. 127 201
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- >', mlHNG CONDITIONS FOR OPERATION SURVEILLANCE REOUJREMENT
=3.5 CQRLAND_ CONTAINMENT C00LlNG 4.5 - C.QRLAND_CQNTAINMENT CQ2mG SYSTEMS SYSTEMS
.ernlica.hilityt Aeolicabilitv Applies to-the operational status of Applies to the Surveillance thg. core and suppression pool cooling Requirements of the core a_nd g ystems.
Suppression pool cooling systems which are required when t@he corresponding Limiting Condition for.
operation is in effect.
Objective Obiettive To assure the operability of the-core To verify the operability of t e core suppression pool cooling and suppression pool cooling ystems ystems under all conditions for under all conditions for which this.
w ich this cooling capability is an cooling capability is,an essential essential response to station response to station abnormalities.
n
. abnormalities.
P Sktcification Speci fication
' A.. Core, Satay and LPCIhJitems A.
Con _jpny_3rd LPCI Sbystems
'l.
Bothcoresprayhsystemsshall 1.CoreSprayhystemTesting.
_ be operable whenever irradlated fuel is in the vessel and prior to Hitn f.LtQutaty reactor startup from a Cold Condition, except as specified in a.
Simulated Once/ Operating 3.5.A.2-below.
Automatic
. Cycle Actuation test.
b.. Pump' Operability Once/ month
[
c.
Motor Operated Once/ month p
Valve Operability j
j j d.
Pump flow rate e.
e vr i st 3600 gpm against e
P a system head corresponding to i
a reactor vessel ja pressure of 104 psig.
e.
Core Spray Header ap Instrumentation E.
A Revision
. Amendment-o,d2,62,g>pymf[]
0 103 i
F i
_l
o
[-
D j
(MITING CMQITION FOR OPERATION SURVEILLANCE REQUIREMENT Core _ Soray _ and LPCI hsyllem 3.5.A Core Spray and LPCQyligma 4.5.A (cont'd)
(cont'd)
Check Once/ day Calibrate Once/3 months t
4 A ~est Once/3 months 2.
From and after the da,te_that on
>'f 2. ['htr it i; d of the core spray stem 5
) core :pr:y tub;y te- !:
4 made or found to be nopera e for heprob!:, the Op t:51 : c o e-(
any reason, continued reactor
-tprey-545yste=, the LNI 1
operation is permissible during
+ 45y44 m :nd the dit::1
)
the succeeding seven days, 9 p paters the!! be der.6trated-provided that during such seven g t: b; ;;r:b!: 8
- dictely. The days all active components of the Operab!: :cre :; :y ::b;y: tem other core spray subsystem and 15:1 b: dern:tnted to b:
active components of the LPCI
+ pre); d:ily th:re;fter,
.,w M ubsy'ste89and the diesel W Wrs are operable.
3.
LPCI D ) Testing shall be A'$4' as follows: '*
3.
The LPCI ste hall be operable wienever tradiated fuel
- a. Simulated Once/ Operating is in the reactor vessel, and Automatic Cycle prior to reactor startup from a Actuation Cold Condition, except a,s Test
. specified in 3.5. A.4, and y,
3.5.F.5.
- d
- b. Pump Once/ month Operability ggg g.
c.
Operated Once/Nonth g
gQ operabili ty y
- d. Pump Flow Once/3 months m k, u goQU
/06 D; Each LPCI pump shall pump 4800
~'
gpm at a head across the pump of at least 380 ft.
-n
- w_
Tk M % WN L
.h /.W/e l
l l
N Amendmentflo.I 104 L
1
7
[
y i
n LIMITING CONDITIONS FOR OTERATION SUR's'EILIANCE REOUTRD!ENT ffrrD~n., -,
7.5.A Cere Sprav and LPCI Subsystems ;' '.5.A Core Sprav and LPCI Subsystems (Cont'd)
% (Cont'd),,
s-4fW t
14r-From-and-e f t er-the -6 ate-that~one 4 j W,eef t-is-det+rn4aed-that en:- 3f-(
-o f-t he - R tih-0.FG)-tuete-le-eed e
) 4.he RFt (LFCI)- pen ps-i+-4neperable
(
j er-f ound--to4e-4neperabl+-for--any--
.st-+-t4= " hen it 1: : quind-4+
\\
s eesern-continued-reac tor -opere-
+e-epet* bier-th; ;r ;t;in ;nt ;;;1ird f
Lion-is-pern.issible-+nly--during
- ub yst
- :, th: :nzining ::t4*e-een.-
t he-succeed in g-t h i r t y-d a y s,- pr+--
pre ts of A ' m 0 9 ystes, both-I
' c.or s-spray--syst -- 2nd th: dh;;l -
vided-that-during-such-thirt-y-days k tenee*t+7; ;h;11 b; d;.;;;;;;;;;d tc the-containn,ent-cooling subsystem 1 p
<-he - r ema in in g-ac t i vedemponen t s-o f be-eperabl "
'ie<+1y =d th: ;;-
/
('
t he-L pC I-Gubs ys tem r-and-e l l-aotiv e.
j;;;b1;-LPCI;~2p;dailythe.esI;er.
-eemponent s--of bo th -ecr.e--spray--sub-systems-and-the stes+1-g+nwat+r-s-
)
- o p e-aM*,-
s
- 5. / Meen i; u dat+reiwed-thet-the-From andAr the date that the
- 4rPG-eubeyetc; i; ir.;p;r:bh, both-f#
OPCI subsystem)s made or f ound to
/ -eor +-spray-subsyst :=, th: :;r tein--
.a.ent--e++14*g-owboyet = =d ;-he-N gag e inopera e for any rcason, ro / cf continued reactor operation is per-( -etesel-generatet; : ;,;1r;d f er missible only during the succeed-
/ +pe te t4en-o f-seeh-componen t s-i f-5 ing seven days unless it is sooner ee-exterr. 1 e;.;; cf, _.....
made operable, provided that during
- ihbh
- h:11 b; dun:tr;;;d' OMA such seven davs the containment
- S: :p uble i m fistely cr'
/yj coolinr/s'$s'ystD(including 2 LPCI acily th::=fi::.
/ pumps) 'and~ active components of of both core spray subs)it'ei's;7 siid N
M the diesel generator eliGired for Ab operation of such components if no external source of power were avail-able shall be operable.
6 If the require: tents of 3.5. A can-not be net, an orderlv shutdown 5
of the reactor shall be initiated and the reactor shr.ll be in the gogp Cold Shutdown Condition within g fogI 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
) &wf
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I 4
-11MITING CONDITI(LN FOR OPERATION SURVEILLANCE REOUIREMENT i."' r h.5.8 Containe.ent Coolitio yv gh 1
~w~
4.5.B.
Containment Cooling g
Containment Cooling" b ows.mS'ubs Q
}b l
- 1. ' Ex e >t as specified in.3.5.B.2, 1.
PA and 3.5.F.3 belgw both Testing shall be as o
y containment cooling {ble vrieirever-bsysteRy,q m, loops shall be opera ltim Frecuency
. 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 maintenance Each RBCCW pump and every 3 shall deliver months hb A *d3 1700-gpm at g Q./ w 70 ft. TDH.
Each O
SSHS pump shall f C"bL / OF deliver 2700 gpm at 55 ft. TDH.
c.
Air test on Once/5 years drywell and torus headers and nozzles i
.T a:.. ah s r..a se...,
..,s.:
T E";: "'2:" 1: ;:; E h :.a: ; ', "'", i n '
l
!!" 'll, n,,'2,,X,_,'."; "t. A.s.X'. ' " ' ' ' "
ou vy
_=-___
Revision Amendment
- o. 42, 44, 106
T LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENT v
l
.,. i. 0 het a4*mmt-C*14 ng Su b t y t em,
4.0.0 Cent:i ::nt C001'n: Seb ys4n-i 4fearW K+nt4b 2.
From and after the date Qa Lone 2.
When ent :catair::nt-cee449 containment coolingd T6sys p pgh tubtyttee 100; be:: :: inep;r:ble, t
loop is made or founNe th: :p;r:ble ;;b:y:t:: 1;;; :nd its---
inoperable for any reason, L -4;;0ciated die::1 ;:ntr:ter-;h:44-i continued reactor operation is
' be d: n n:4+:t:d to b; ;;;r: bis permissible pnly_during the 3- :dictely :nd th: Op::: bit C
M WCA succeeding Hn dty4 ynless such
-tent:t ::nt :: ling :;b:y; tem icop TO /0(,
1 onTr mad
\\
-daily 'hert:f t:
m containment cooling Q
3 h02 h
loop, including its associated M A diesel generator, is operable.
3.
If the requirements of 3.5.B cannot be met, an orderly Mv6 shutdown shall be initiated and TO /06 the reactor 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 />.
r m.
p~
IlECI(uhyg.+,
C.
HPCIISubsgtiLn hh C.
w m w HPC1 4Rb q Qom} testing shall be 1.
The HPCI ubsyst Jer. shall be 1.
t t
operable w Tr there is performed as follow!.:
irradiated fuel in the reactor
-i vessel, reactor pressure is
- a. Simulated Once/ operating greater than 150 psig, and Automatic cycle V
reactor coolant temperature is Actuation i
greater than 365'F; ex e t as Test specified in 3.5.C.2 below y
- b. Pump Oper-0$ce/ month
?
r ability q
- c. Motor Operated Once/ month bbw A w N 3 t
- d. Flow Rate at Once/3 months ga
/08 1000 psig
- e. Flow Rate at Once/ operating 150 psig cycle
.Aa/d/ &
4.5.c.I w d ha.
?]s,onathna4-nsf-grsn<nfm-tm t{0-for--the-pered-setobe r 31. 1980-v OaI ng tw m p m. ember 7, :;ee..~'/s w
Revisionh N
Amendment No, d-fef-H+)
107
C l.
LIMITING CONMTION FOR OPERATION SURVEILLANCE RE0' IREMENT J
HPCI-$tstylter (Cont'd)
- HPCI %b;;/ste:
The HPCI pump shall deliver at Wv6 A corresponding to a reactor pressure %
least 4250 gpm for a system head of 1000 to 150 psig.
2.
a the date that the 2.
Men-44 i; d;terbin:d that the "PCI h
,g CI syst is made or found Ogbayete;a is inop;r:51; the RCIC, to be inoperable for any reason, th: LPCI ;;b;y;t;;, 50th cer; ; prey MNf3 continued reactor operation is sub;y;teet, and the ADS sub:ytte-To o? permissible only during the
+c4uat40n logic- :hel' be r
sut geding seven days unless such de=n:tn ted to be :; r:ble ubsysterii is sooner made 4amediately. The *CIC ;I;b
" ter :nd y "
opera TE')providing that during
^DS ;ub;ystte 10;4< ;h:!
g such seven days all act t 4eeenttuted t0 be Oper:b!: d:ily components of the ADS 8Pb thereafter.
the RCIC system, the LPC W
- iuRy~steRQandbothcorespray
,q C,/,,% g r geare operable.
m%
3.
If the requirements of 3.5.C cannot be met, an orderly
^M "O shutdown shall be initiated and ro /rf the reactor pressure shall be reduced to or below 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.5.0 Reatter core Isolation Conjing 4.5.0 Reactor Cor_e Isolation Coolina n
(RCICKSubs ys teniV g (RCIC)[Sutftystemyg 3h
~~
% f/
N_~-r: m.D 1.
The RCIC yste hall be 1.
RCI s ste testing'shall be t
operable whene there is performed ollows:
irradiated fuel in the reactor vessel, resctor pressure is a.
Simulated Once/ operating greater L.:a 150 psig, and Automatic cycle reactor coolant temperature is Actuation greater than 365'F; except as Test specified in 3.5.D.2 below.
t Operability e"*"
c.
Motor Once/ month Operated f@
p rability R t.i d / A t f4.5.D.i a d lM r pwp 10 9 Revision h C l
w Amendment No, f4 r4M. '"-)
108
9 LIMITING CONDITION FOR OPERAVION SURVEILLANCE REOUIREMENT C
ttWore helat4M<+W%
^5.D'Estt67C'er:M iicrCoch$p G=&vM 4RCIC) ! @ M ee-Mont'd) 2.
From and after the date that the d.
Flow Rate at Once/3 months RCICS is made or found to be 1000 psig gg inoperable for any reason, M O vfD continued reactor power operation e.
Flow Rate at Once/operatin0 4
-ro is permissible only during the 150 psig cycle jog succeeding seven days provided that during such seven days the The RCIC pump shall deliver at HPCIS is operable, least 400 gpm for a system head corresponding to a reactor 3.
If the requirements of 3.5.D pressure of 1000 to 150 psig.
cannot be met, an orderly h.&.
/vmvfD shutdown shall be initiated and Fher it-t; det+ mined th:t-te-70 the reactor pressure shall be AC4C-subsyster i; i operable, the n
jpg reduced to or below 150 psig
"?CIS :h:11 be d:=r.;tt ted to be within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
+p07:b10 '
- diately :nd :::Ely
-the+4&t+F.
3.5.E 6.ui.omatic Deoressurization 4.5.E Automatic Decre11grization System (ADS) ly11talADS) 1.
T g_
tomatic Depressurizat Wn 1.
During tach operating cycle the
.ubsys shall be operable following tests shall be performed w
here is irradiated fuel on the ADS:
b n the reactor vessel and the irector pressure is greater than a.
A simulated automatic actuation l
104 psig and prior to a startup test shall be performed prior
?
a from a Cold Condition, except as to startup after each refueling specified in 3.5.E.2 below, outage. The ADS manuai inhibit switch will be included in this test.
l pM e2 c cb b.
With the reactor at piessure, each relief valve shall be g g[ dgA4 manually opened untti a p
corresponding change in reactor scf, // O pressure or main turbine bypass v
U valve positions indicate that steam is flowing from the valve.
b l
1 l
l Revision h
-~ -
Amendment No.(R-42. JE-4N-109
t t!M!T:"*, CCND*T!CM 70p. 0?D.A7!i:
MVI:1'A ::E REUI;r?:7
- -, p
- w. -,
LS.! Aute--ti: O^=r+s =ri ;t t i =
.5.: tc;;;c.;ti:M:::u-i=ti;..
4vster l'23) Jc-t'd)
Cy: :: (!OS }
'C:n,'d) 2.
Tro and after the date that one "n= it 1: dete-
- ed that tre valv:
'44~ vr.1ve in the auto:stic cepressur-
-f the #5 i; in:F 7di. ^ h; !Z 1:stion [ 'yste: is made er found
- h^7;;
M *C!i'" 1^2 : IO: 00 1
f 22 0;-
I ;O
- O ^ ; #
.M 0pgf) to be inopert.t e for any reason,-
-eye:= :bl. b:
!-- = :r:: ! :: b;
/p continued reactor operation,.s per-
_____t,,
,___,,,,_3..
3.,
~
/
/g7 e.issible er.ly during the succeeding
.' G..'.1... _ _. _ _'C. T..'... W. '.... _7. ', _ /
i
^
,7 seven days ur.less suen ve.1ve is i.
--2 i
sooner rade cperatie, provided tha'.
durin. suth seven, t.ays the KPC:
subsystem is operable.
3.
If the requirements of 3.5.I can-not be met, an orderly shutdown p ppg shall be initiated and the reac-70 tor pressure shall be reduced to
/09 at least 104 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c 3.3.T P.inL== Imr Pressure Coolint k.5.T "ini g 1,= S;;;ur: *coline-c.nd Diesel Generator Avail-_
end-F----
"-4',
3 ability ebiMey-
-t._~-
s gw.
g % -~ %%,
1.
During any pericd when one diesel y
ha-14-4e-det:.- ' :d tM t ;;; di;=
generator is inoperable, centinued
- ---- t-- i p.es, p.s 1-.; 7, reactor operation is permissible
- m. __ _ s 4.s _
.a enly during the succeeding eewe]e
.t..
.t.3
- s.,____
unless such diesel genera or 1
'; Z; Z__;,
3< i
'f?. b00es is sooner made operable, provided
' ' " ',.. u__ r - ---
__2 2
_m_
,_u,.,__
that all of the low pressure core andcontainmentcooling(gystems 01: ;p: ;51: dd;::'. gemee:t r c'-"-
and the ree.aining diesel generator b^ f r --trt* d te 5: :;. 21: i: -
shall be operable. If this re-tr'*st dy --' '-*'" +2r--ifte- "-+43 quirement cannot be met, an order-th: i;.;p;;;ti: 2.1:::1 i: ;;g;i, lyshutdownshallheinitiated and the reactor shall be placed in the Cold Shutdown Condition
]
vithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1 2.
A :y co:bination of inoperable com-ponents in tne cere and conte.in-
=ent co: ling syste:s shal.1 not de-feat the capability of the recatn-
- .ng operatie :omp:nents to fulfill the co: ling ^.m:tions.
10
,u un
, a cd C A acS
/w hu jacs4 - / //
V Amendment No.
j tj
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l
E
- ~
. LIMITINO CONDITION FOR-OPTFJ720N grRVI:LLANet nor2RLvtg7 3.5.T Mininen Lev Pressure Coolint and Diesel Generator Avail-ability (Cont'd) 3.
When irradiated fuel is in the re-actor vessel and the reactor is in the Cold Shutdown Conlition, both b
' core spray systems, @tv LPCI and containment cooling ystems may 3,4 fgd be inoperable, provided no work is being done which has the potential g pg for draining the reactor vassel.
g 4.
During a refueling outage, for a E
/
period of 30 days, refueling oper-ation may continue provided that p
p one core spray system or the LPCI
~
/,
systen is operable or Specification
/
3.5.T.5 is met.
i s
.q5.
When irradiated fuel is in the
('/
reactor-vessel and the reactor is in the '.1tefueling Condition vith the torus drained, a single j
/
control rod drive methe.nism may
/
be removed,' if both of the foi-i>
i loving conditions art i.atistieu
/
'k-
'a)
No vod. on the reartt.t ves-sel, in addition to CRD re-V aovel, will.be performed which has the potential for ex:end-
[
ing the maximum leak rate from v
a single control blade seal
/
if'it became unsested.
l-/
J b)
- 1) the cure spray systans are
/
operable and aligned with a suction path f rom the conden-sate. storage tanks.
ii) the 7
condensate storage tanks shall contain at least 200,000 gal-lons of usable water and'the ref ueling cavity and dryer /
I' separater pool shall be flooded f.
to at least elevation 114'-0".
3.5.G M Y, f // 9'{ N,/, N (Intentionally left blank)
/
N.EYA &
.k. & 3,,f, }.{ 4
//c2 111 Amendment No.
t
}IMITING CONDITION FOR OPERATION gURVE1LIANCE REQUIREMENT 3.5.H Maintenance of Filled Dis-
- 4. 5. H Maintenance of Filled Discherme charge Pipe Pipe (gt g)
MOVfb MOV(O 7b lti L
7p///
Whenever_ core spray subsystems, LPCI The following surveillance requirements Lubsysty HPCI, or RCIC are required shall be adhered to to assure that the t
/to be 6perable, the discharge piping discharge Pipin of the' core spray sub-
@ from the pump discharge of these sys-systems, LPCI ubsys HPCI and RCIC tems to the last block valve shall be are fillsd m qh i
filled.
,A 1.
Every month to to the testing of the LPCI u systes and core spray y cj subsystem, t e scharge piping of these systems shall be vented from the high point and water flow ob-
///
served.
2.
Pollowing any period where the_LPCI e@ or core spray @
haiTe not been required to be oper p9 M M able, the discharge piping of the 79 inoperable system shall be vented g/
frot the high point prior to the return of thw system to service, 3.
Whenever the HPCI or RCIC system tii lined up to take suuion from the f
torus, the disc'tarte piping ei the HPCI and RCIC shall te wt.ted from the high point of the syn.tes and vater flow otserved on a monthly basis.
4.
Thk pressure switches which monitor the discharge lines to ensure chat they are full s. hall be functier. ally tested every nonth and (:aliststed every three n.onths.
AmendmentNo.h 112 / /
i
MM5 :
s Con _SpuLarJM7($gbly11m>,,#h 3.5.A This specification assures that adequate emergency Cooling capability is available whenever irradiated fuel is in the reactor vessel.
Based on the loss of coolant analysis performed by General Electric in accordance with Section 50.46 and Apperdit K of 10CFR50, the Pilgrim I Emergency Core Cooling Systems are adeauate to provide sufficient cooling to tne core to dissipate t.1e energy associated with the loss of coolant accident, to limit calculated fuel clad temperature to less than 2200*F, to lirnit calculated local metal water reaction to less than or equal to 171, and to limit calculated core wide metal water reaction to less than or equal to 1%.
[
f,
m.- -..
L
,N ' H t4ag :on d i 14o%-M--wm44*MpM444u(4+n&--M A4-through 3. 5. *. 6
' +pM44y -t he ccmbination+-oLoper4tde-wt+yst+ms40-aswre-the.-wa444t4444-y-+f-we--m494wo-<+M4n9-Sy&t e a not+4-4tm e 4 -44494 4444vre of CSCS e;eipment-ouvr4449-49r449-a -Jo&&-of--too44nt-4 H44e4tWAder-thew-44444n940n4444Ms-+f --
oper-at4onwt44-4+wlt 4A-4n44Muate-too44ng4Lth-r4ntor-4on,
-n x..~_._
--x_
x w._
- x.. - x._.-
~
E
- ore spray distribution has been shown, in full-scale tests of systems similar in design to that of Pilgrim, to exceed the minimum requirements by at least 25%.
In addition. tooling effectiveness has been demonstrated at less than half the rsted flow in simulated f uel assembl'.es with heater rods tc duplicate
[
the decay heat thurar,teristics of irradiated fuel.
The accident ar.alysis Q
takes credit fos core spray flow i'ito the core et vessel pressure belcw 205 I
psig.
Howettr, the analysis is cor.servative in thSt no credit is taken for G
L spray sooling beat transfer
'.fi the bottest feel turd'.e until the pressure at d
rated flow for the core so n y (104 rsig sessti pressures is reathert.
'y The LPCI htpLtoDis dhsLuigned to provide emergehty tooling to the ere by f
,, 3,,, g-w r
[
flooding GWevent of a loss-of-coolant acticent. This system " unctions in ccgrbination with the cor, spr_q@ system to prevent enessive fuel clad so
~he LPCI dsykt-and the core spray subsystem provicie adequate F
ga tempt'a+ure.
- f Co f p or DreaK areEs o. approximately 0.2 square feet up to ant,, 'ncluding the f.subte-ended retinuiacion line t,reak without assistance from the high 0
4 pressure errergency core ccMing subsystems.
f~.-~
/ Me-eMowab4--r+patM4 mes -e re-- >6 t a bl4 stW -+o-tt'ai-the.-+wrags-r4 sk-ri W for-3
' r+pa4 r--wo444e no gr+ ster -than-tM4ni4-444t.-rate. The met h and toMept
}
I
- -e++-deser41.e4-4#--r+W+nt+-+4b-444ng-4he r4wh-dev44opH'-4n-y
.. _ ~ -
y g, __
m._ m _ a u_.
m __ s..
The combinati:9 c' the core spray systems and the LPCI system assures that acel ate ~ ore coc'i^; 's acties e assuming sny cointicen't sinale failure of an
- ntreent
- pre Star,JLy Cooling System'(CSCS)
't e safety-relate:
Cerf:"*ar:e e.a'.3
- "s :;-t3 ' t
'y t r e n;.s t severe single fai'Ure for eaCh iye range, ng;p :ir gg e,,
r
- re3t t
- . i '"
R the LP[1 injecti C '1 salve, one s
'iesel gere"3tDr, e 0 :
yst(? rr.- p t.;3 valve.
W ih tnese sinale t
"res s Jre [S;S Capaci ty ibC IJ00 two (3'
res, the
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%is-r+$wec+1-W+-r4Mir p^ried iMead -te be 1:s: th= 1/O-%e-tut--im 4eevab--.7hi&-uwn+: thtt the tre sprty r_b&ytter! = d LMI tenst5tet: :. -
,1 e t cf 0 :y:U;n;.svev:r, th: 00-bind-+# ret Of th: W: syst :: tr 16e-4--
' twee*stv: ltd tv 7:rature r;*i 1140 b cetri h r:d.
"'t. : ttet inter /1 : ;
ified-in--Greerf t:: 1er b. ) v : 3 : nth:.
%+r efer, = embl^ r ep_u p:rhd "tiet witt a.'.n: t!.e bui: -ith consikrin; cir.r,1: feil rt: he.de -
t: 10:: Q.L:. ";0 hy: =d thi: i;; ificatier i; eithin ihn perici. To:
ruitiple f 4hret, : th:r ter-inte..u.1.e ape;.ifie n w
. m &...
Surante that the retainin; syste.:.411 6: tion, e i:.11y t::t--i; ::.11 :. -
feer-A. %eogh-44-i? re :; sin +G--Sit the 14erration ;iven in : eferes. e ('.)
pr e fi S! t quentitative n:0.H t ::ti-e.te :.1.he_bl
- r.ir time:, t..: hs-
+f Oper:.tig htt t support t?.e L aly+ies1 S;;ren:h prevent: 22-'aete it--
- pt=:: et this--e+the'. st t'i tire nerefert, u, tire: :u.t:d in th:
Op-:ific iter: "ere ::ttllished vith d; re;ird te lud; :nt.
Should one core sprayh, s -- esorae inoperabic, the retaininf, core sprey and the LMI system are availatic shodd the need for core co.lin; e. rise.
.s..._. u - N...--....,- - -
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e 4 wig stie ef th p;. 7: =i :.::: n:2 Thi: h o r,&At a ti e-i n c h 44-e -
- "' a g p w4;-),1 M _E Q T v -IcF Ni os judsbe5ts 'Ef the rent @llity of *.he re:r.aininf. systens t i.e., the core sprSy r.nd LMI, a seven. day repair peHo:1 VVS obthit'ed.
Ehest-14-%e-1+++-eP-**e-LM: ;cr; err _r, 6.-r.etrly _^ ee.p'a e.' re:4 sadvs corrt e.ineeta-ter &4 rc-e qu i ;; = t-- -1 tv-11 bit
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tw:: ;f 'a:-rai :.bility :f th: =tjer!;.: er th' :::: :::'.h; r;;i ese+,-
t whfeh-vG,i-heet.= t. :ted i b: Op:riti:, a 30-46y-::r.1 p ri.:4 i: j : t _._r.
(4+4s]Tf,the LWI--
_"/ *p,pis nor availativi nT-Est 2 LK! pumps if.ist be j
pvaihble to it.lfill tr.e containment coolinE functien.
7-day repa.ir
, g M period set Q g t
operating iW;.c%is not cotaidered inoperabic enca the RIG. Sy8te't The LPC is shutdown cooling raode.
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3.5.b centaineent Cooling
--~v The containment cooling subsystem for Pilgrim 1 consists of two independent loops each of which to be an operable loop requires one 1.CP1 pump, two RBCCW i
pumps, and two SSW pumps to be operable. There are installed spares for mar-gin above the design conditions. Esch system has the capability to perform 6 Btu /hr (Ref. Aundment 16), even with 38 its f unction;; i. e., re:noving 64 x 10 some system degradation. If one loop is out-of-service, reactor operation is p
permitted f orffeven 'daysgt emy tie !1ng-of--the-+per-*Me-[cep RN.e ip l
Q N ' W el JEtjtk P M d
& w M^- G A, )
With components or
'bsystgems out-6f-s tvice, overall core and containment
[-
^ cooling r* liability is ma'intained by b e " M -the operability of the L
remaining cooling equipment.,(Wf d gf;; ci cperet+nty : L: d::::::::: 5
{J
(-depenc e-en-the-na t-ure-Mw*t-r+asen-(c : th: ::t-ci :::vi;; : quip;.;..t.
Ter
-r++t4ne-out-of-++rvic e p e ri ed: :-aus:d by p :uent:14*e-eeintenanee -etti,
r
-t h puer-end--va3*-oper4b414+y--chec44--v111 he per4+r::d to demonstret; ep; -
i
~ ' " " +,-deeign-def t-d'
.ebilit*-of--the-res.a4ntw; corpenents. Mcueur,
. -e4encyr-* toes-46u8+d--the-out-of-+ervice-periodr-then-the-dwm ivu v!
-operabni-tt-ehevid ' e--thorough ::::gh : ;;;;;; thet+sie44et-trebles doi e
tuomP +r-14-en-eet-of-::r:1;;-
l net--ew is tw>n-the-+easinlet,.-4eemenoats. F:
p;-ind sete- :::: d b;. ful-un-of-4-tu p te deliver rat:d 0: pant?,--th: c'.h:: -
7 pus.ps,. cL.this-.typa-might-b e cubpot+d-to-+-especity-tc t.
Is. y eventr N-s'orveillanet-tem edwt-es, :: required by Se: tier L ! th::: +eelfaesttensi j
-deteil-the-ret:eired-e st e s.t of t;nettip
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-n
.Since some of th SV s.nd RBCOV pumps are required for nor.nal operttion, casacity testing o individud pumps by dir ect flow measuM:.ent is imprac-i tical. The pu'cp capacity test is a coanarison of measured pump performance parpmiters to shop perferrance usts combined with a comparison to the per-formance of tc.e previously tested pcmp. Tnera pu.ps are rotated during op-erat"ca and perf ormance testing vill be integnted with this cr performed during rafueling when custps can be flov tected individually. Tests during ncrmal cperathn will be performed by ricasurirg 1.he shutcff head. Then tha r
pump tender test will be placed in service ard ene of the previous.'\\y opera-ting pumps secared. Total flow indication for the system vill be compared f or the two cases. Where this is not #easible due to chang'ng system con -
ditions, the pw.p discharge pressure vill be m. Sured and its power require-ment will be used to establish flow at that pressare.
115 i
n i
ILA1ES:
6 3.5.C EP11 t
The limiting conditions for operating the HPCI System are derived from the Station Nuclear Safety Operational Analysis (Appendix G) and a detailed 4
functional analysis of the HPCI System (Section 6).
The HPCIS is provided to assure that the reactor core is adequately cooled to limit fuel clad temperature in the event of a small break in the nuclear system and loss-of-coolant which does not result in rapid depressurization of the reactor vessel. The HPCIS permits the reactor to be shut down while maintaining sufficient reactor vessel water level inventory until the vessel is depressurized.
The HPCIS continues to operate until reactor vessel pressure is below the pressure at which LPCI operation or Core Spray System operation maintains core cooling.
The capacity of the system is selected to provide this required core cooling.
The HPCI pump is designed to pump 4250 gpm at reactor pressures between 1100 and 150 psig. Two sources of water are available. Initially, demineralized water from the condensate storage tank is used ine.tead of injecting water from the suppression pool into the reactor.
When the HPCI System begins operation, the reactor depressurizes more rapidly than would occur if HPCI was not initiated due to the condensation of steam by the cold fluid pumped into the reactor vessel by the HPCI System. As the reactor vessel pressure continues to decrease, the HPCI flow momentarily reaches equilib' lum with the flow through the break. Continued depressurization causes the break flow to decrease below the HPCI flow and the liquid inventory begins to rise. This type of response is typical of the small breaks. The core never uncovers and is continuously cooled throughout the transient so that no core dam,ge of any kind occurs for breaks that lie within the capacity range of the PPCI, The analysis in.the FSAR, Appendix G, shows that the ADS provides a single failure proof path for depressurization for postulated transients and accidents. The RCIC is required as an alternate source of makeup to the HPCI I
only in the case of. loss of all offsite A-C power. Considering the HPC1 and M n m M '!~feeM-gg44:E (KADS_plus RCIC as redundant 96ths.f* crc?:ays based on Se one a.th :eit'd ett u atc3 M 'owaD f % % % ee-ef-Vdpents af '.he'reliobility oFfhe 7.05 CN *dg d t (fftqupey. _ Comider%
3 y% wpm.
8 s s ecified and F.CIC systems, a 7 day
, p u, The requirement that HPCI be operable when reactor coolant temperature is
/
greater than 365'F is included in Specification 3.5.C.) to clarify that HPCI need not be operable during certain testing (e.g., reactor vessel hydro M(
testing at high reactor pressure and low reactor coolant temperature). 365'F
/
is approximately equal to the saturation steam temperature at 150 psig.
Q 116 Revision
p x
1
.'O f
BASES:
3.5.0 R_CIC System The,RCIC is designed to provide makeup to the nu: lear system as part of the planned operation for periods when the normal heat sink is unavailable. The nuclear safety analysis, FSAR Appendix G, shows that RCIC also serves as redundant makeup system on total loss of all offsite power in the event that i
HPCI is unavailable. In all other postulated accidents and transients, the ADS provides redundancy for the HPCI.
Based on this and judgments'on the reliability M the__HPCI sys_ tem, an allowable repair time. of s da is saecified f!?:dter and reegr7ceefty3tgmcer tgemstre;37:5, ay ;75ng.
i f: pc0tigi is cor,sid: d d:; cite bered en jud;-?at and practicality.t te:t'ng reeld ca IC "O r e -
~
~~
cycl'n; tn
~
The requirement that RCIC be operable when reactor coolant temperature is j,
greater than 365'F is included in Specification 3.5.0.1 to clarify that RCIC-need not be operable during certain testing (e.g., reactor vessel hydro A,
testing at high reactor pressure and low reactor coolant temperature). 365'F is approximately equal to the saturation steam temperature at 150 psig.
k f
5 IJ 9
4 l
Revisionh 117
e-f o
4 y
?>.SES :
o 3 5,I Aute:ati Deprestri:rtien Sysee: ICS)
The 11=iting conditiens fer eperating the CS are derived frc: the Statics Nucle s.: operational Analysis (A;;endix G) a:d a detailed Pas:tional ar. sly.
sis of the ALS (Section 6).
n.is specification ensures the cpert.bility of the CS = der a.11 ceniiticas for which the automatic er casual depresseitt. tion cf the :::ler; system is as essentir.1 response _ tc static: abscr-*" ties.
':he nuclear syste pressee relief syste: provides anc:atie :ncles.: sys e:
depress =izatien for s-*' treahs in the nuclear s ste so that the lov pres-t se e ceciant injectic (1?OI) and the core spray
< systess can c;ers.te to protect the fuel tr.rrier.
3ecause the Aute:atic Depress =1:r. tion Systes does not provide makeup to the reacter print.ry vessel, ne credit is taken for the s,es: cooling cf the cere caused by the system actuation to provide farther conservatis: to the OSOS.
perferts.n=e a r. lysis of the Aute=atic Depressurizatica Syste is cc sidered only with respect to its depresseizing effect in conjunctica vi.h 1;;; c C re Spray, Onere are fer valves provided and each has a capacity of 500,000 lb/tr at a reaeter pressure: of n25 psis.
p dla w if HPc/Sopw~L~Ad 5f The al.1 cable out ef service tird fo_r ene ADS vr.1ve is determined a.s seven it.yy tecausc;Lthe red =dr.nc,w(a7.2.'~::: =: tt.: :'c W L: denenet h t:t. :: g hr_sh-sur4r.g.-tM: PM~ Jherefore, red =da:T yrotectics fer the c re E T s rc. or M t= the nucles.r system is still available.
Ite cs test =ircuit percits censinued surv2111r:ce on the operktle relief va.1ves to ass =e that tsey vill be availabit if required.
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4.$ Core end Containw nt Coolint Syster.t Surveill ance Trcquencies The.testint interval fer the core and containment cooling systems is based on industry riectice, quantitative reliability On:1ycic, judptent and prac-ticality. The core. cooling systems have not been designed to be fully test-
?
cbic during operation, for exc.ple, in the case of the HP 1, autoratic initiatinn durinr. rover operction vould result in pumping cold water into the. rcteter vessel which is not desirt.ble. Cemplete ADS testing during
)
power. operation carts on undesirebic loss of coolant inventory. To in-cresce the availability of the core and conicirment cooling cystems the cortponents which enhe up the cystem; i.e., ins trumentat ion, pu :ps, valve s,
etc., are tected frequently. The pu ps and inster operated injection valves ere t.1so tested each month to assure their operability. A simulated auto.
{.
static actuation test once each cycle combined vith conthly tests of the ptere and injection valves is deemed to be ecce,unte testing of there syster-s.
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The diesel fuel oli quality must be checked to ensure proper operation of the diesel generators. Water content should be minimited because water in the fuel could contribute to excessive damage to the diesel engine.
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The Electrical Protection Assemblies (EPAs) on the RPS inservice power l
supplies (either two motor generator sets or one motor generator and the i
alternate supply), consist of protective relays that trip their incorporated
/
circuit breakers on overvoltage, undervoltage or underfrequency conditions.
1 There are 2 EPAs in series per power source. It is necessary to periodically
/
test the relays to ensure the sensor is operating correctly and to ensure the trip unit is operable. Based on experience at conventional and nuclear power
/
plants, a six month frequency for the channel functional test is established.
/
This frequency is consistent with the Standard Technical Specifications.
The EPAs of the power sources to the RPS shall be determined to be operable by performance of a channel calibration of the relays once per operating cycle.
During calibration, a transfer to the alternate power source is required; P
l however, prior to switching to alternate feed, de-energitation of the I
applicable MG set power source must be accoepitshed. This results in a half-scram on the channel being calibrated until the alternate power source is j
connected and the half scram is clesred. Based on operating experience, drift of the EPA protective relays is not significant. Therefore, to avoid possible spurious scra'as, a calibration frequency of once per cycle is establisted.
F
?
Revision 36o.h Amendment
,, _ _ _,,