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| document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS & TEST REPORTS | | document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS & TEST REPORTS | ||
| page count = 9 | | page count = 9 | ||
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{{#Wiki_filter:4 St. Lucie Unit 2 Docket No. 50-389 Proposed License Amendment SDCS Minimum Flow Rate Re uirements ATTACHMENT 3 ST. LUCIE UNIT 2 hGQUCED-UP TECHNICAL SPECIFICATION PAGES Page 3/4 9-8 Page 3/4 9-9 Page B 3/4 9-2 Insert A 9503080425 950227 PDR ADOCK 05000389 . | |||
P PDR | |||
REFUELING OPERATIONS 3/4.9..8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8. l At least one shutdown cooling loop shall be OPERABLE and in operation." | |||
APPLICABILITY: NODE 6 when the water level above the top of the reactor pressure vessel flange is greater than or equal to 23 feet. | |||
ACTION: | |||
With no shutdown cooling loop OPERABLE and in operation, suspend all operations involving an incr ease in the reacto~ decay heat load or a reduction in boron concentration of the Reactor Coolant System and within 1 hour initiate corrective action to return the required shutdown cooling loop to OPERABLE and operating status as soon as possible. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours. | |||
~ | |||
4.9.8.1 At least once per 12 hours: | |||
j a. At least one shutdown cooling loop shall be verified to be in operation.I | |||
: b. The total flow rate of reactor coolant to the reactor pressure vessel shall be verified to be greater than or equal to 3000 gpm.** | |||
SURVEILLANCE RE UIREMENTS A | |||
operation-and-ci-rcu &ting-reactor-coo-l~nt~~Hewma~~ | |||
uA-4o-3600-g m-at AaM-once-pe~hR-houm. | |||
,,',*" The reactor coolant flow rate requirement may be reduced to 1850 gpm if the following conditions are satisfied before the reduced requirement is | |||
'mplemented: the reactor has been determined to have been subcritical for at I least 125 hours, the maximum RCS temperature is s 117 'F, and the temperature | |||
~ of CCW to the shutdown cooling heat exchanger is s 87 'F. | |||
The shutdown cooling loop may be removed from operation for up to 1 hour per 8-hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs. | |||
ST. LUCIE - UNIT dy. 3/4 9-8 ~emir I" Ibm | |||
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'h R FUELING OPERATIONS LOW WATER V LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent shutdown c'ooling loops shall be OPERABLE and at least one shutdown cooling loop shall be in operation. | |||
A~P AM 1: MIIAE'E h th I I h th t P I th pressure vessel flange is less than 23 feet. | |||
ACTION: | |||
: a. With less than the required shutdown cooling loops OPERABLE, within 1 hour initiate corrective action to return the required loops to OPERABLE status, or to establish greater than or equal to 23 feet of water above the reactor pressure vessel flange, as soon as possible. | |||
: b. With no shutdown cooling loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and within 1 hour initiate corrective action to return the required shutdown cooling loop to operation. Close al,l containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours. | |||
SURVEILLANCE RE UIREHENTS W~~~~~n~utdow~ co ~erH+eM~)~ | |||
Moperation-and-ci-rcu3 ating-r eactov-coolant-at~fkow-ate-of-greater-than-oi.- | |||
~ ual-to<000-gpm-.at-.leastmnc~er-I&hou 4.9.8.2 At least once per 12 hours: | |||
: a. At least one shutdown cooling loop shall be verified to be in operation. i i | |||
: b. The total flow rate of react:or coolant to the reactor pressure vessel shall be verified to be greater than or equal to 3000 gpm.* | |||
* Th r~~~t~~ coolant flow rate requ r re uirement may be reduced to 1850 gpm if the, are satisfie d before the tore h uce re I following conditions en determined ave b een subcritical for at | |||
~ | |||
implemented: the reactor has been erature is 117 'P I and the temperature least 125 hours,shutdown the maximum RC S tern pexchanger aner s | |||
)oof CCW to o the cooling heat ST. LUCIE - UNIT 2 3/4 9-9 Amendment No. pd, pd' | |||
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REFUELING OPERATIONS BASES 3/4.9.6 MANIPULATOR CRANE The OPERABILITY requirements for the refuel1ng machine ensure that: | |||
(Q manipulator cranes will be used for movement of fuel assemblies, with or without CEAs, (2) each crane has sufficient load capacity to lift a fuel assembly, with or without CEAs, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations. | |||
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly, CEA and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the safety analyses. | |||
3/4. 9. 8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is main-tained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification. | |||
The requirement to have two shutdown cooling loops OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange with irradiated fuel in the core ensures that a single fai lure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability. With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange with irradiated fuel in the core, a large heat sink is available for core cooling, thus in the event of a fai lure of the operating shutdown cooling loop, adequate time is provided to initiate emergency rocedures to cool the core. | |||
happ 4/ 3/4. 9. 9 CONTAINMENT ISOLATION SYSTEM pgjggAP~ | |||
84' The OPERABILITY of this system ensures that the containment isolation gag'$ valves will be automatically isolated upon detection of high radiation leve 1 s restrict within the containment. The OpERABILITY of this system is required to the r elease of radioactive mater ial from the containment atmosphere to the environment. | |||
ST. LUCIE - UNIT 2 B 3/4 9-2 A~a~&lr Klo. | |||
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St. Lucie Unit 2 Docket No. 50-389 Proposed License Amendment SDCS Minimum Flow Rate Re uirements WP 9 I' PW I INSERT A The footnote providing for a minimum reactor coolant flow rate of a 1850 gpm considers one of the two RCS injection points for a SDCS train to be isolated. The specified parameters include 50 gpm for flow measurement uncertainty, and 3 'F uncertainty for RCS and CCW temperature measurements. The conditions of minimum shutdown time, maximum RCS temperature, and maximum temperature of CCW to the shutdown cooling heat exchanger are initial conditions specified to assure that a reduction in flow rate from 3000 gpm to 1800 gpm will not result in a temperature transient exceeding 140 'F during conditions when the RCS water level is at an elevation a 29.5 feet. | |||
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Latest revision as of 12:32, 4 February 2020
ML17228B059 | |
Person / Time | |
---|---|
Site: | Saint Lucie |
Issue date: | 02/27/1995 |
From: | FLORIDA POWER & LIGHT CO. |
To: | |
Shared Package | |
ML17228B058 | List: |
References | |
NUDOCS 9503080425 | |
Download: ML17228B059 (9) | |
Text
4 St. Lucie Unit 2 Docket No. 50-389 Proposed License Amendment SDCS Minimum Flow Rate Re uirements ATTACHMENT 3 ST. LUCIE UNIT 2 hGQUCED-UP TECHNICAL SPECIFICATION PAGES Page 3/4 9-8 Page 3/4 9-9 Page B 3/4 9-2 Insert A 9503080425 950227 PDR ADOCK 05000389 .
P PDR
REFUELING OPERATIONS 3/4.9..8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8. l At least one shutdown cooling loop shall be OPERABLE and in operation."
APPLICABILITY: NODE 6 when the water level above the top of the reactor pressure vessel flange is greater than or equal to 23 feet.
ACTION:
With no shutdown cooling loop OPERABLE and in operation, suspend all operations involving an incr ease in the reacto~ decay heat load or a reduction in boron concentration of the Reactor Coolant System and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to return the required shutdown cooling loop to OPERABLE and operating status as soon as possible. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
~
4.9.8.1 At least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
j a. At least one shutdown cooling loop shall be verified to be in operation.I
- b. The total flow rate of reactor coolant to the reactor pressure vessel shall be verified to be greater than or equal to 3000 gpm.**
SURVEILLANCE RE UIREMENTS A
operation-and-ci-rcu &ting-reactor-coo-l~nt~~Hewma~~
uA-4o-3600-g m-at AaM-once-pe~hR-houm.
,,',*" The reactor coolant flow rate requirement may be reduced to 1850 gpm if the following conditions are satisfied before the reduced requirement is
'mplemented: the reactor has been determined to have been subcritical for at I least 125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br />, the maximum RCS temperature is s 117 'F, and the temperature
~ of CCW to the shutdown cooling heat exchanger is s 87 'F.
The shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8-hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.
ST. LUCIE - UNIT dy. 3/4 9-8 ~emir I" Ibm
p
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~ w P p p,S 0
<+a Q a~ ~
4pf t S 4e ~.
ea r . J 4
~ M A
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~ ~h f AILS,},J(c
'h R FUELING OPERATIONS LOW WATER V LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent shutdown c'ooling loops shall be OPERABLE and at least one shutdown cooling loop shall be in operation.
A~P AM 1: MIIAE'E h th I I h th t P I th pressure vessel flange is less than 23 feet.
ACTION:
- a. With less than the required shutdown cooling loops OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to return the required loops to OPERABLE status, or to establish greater than or equal to 23 feet of water above the reactor pressure vessel flange, as soon as possible.
- b. With no shutdown cooling loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate corrective action to return the required shutdown cooling loop to operation. Close al,l containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE RE UIREHENTS W~~~~~n~utdow~ co ~erH+eM~)~
Moperation-and-ci-rcu3 ating-r eactov-coolant-at~fkow-ate-of-greater-than-oi.-
~ ual-to<000-gpm-.at-.leastmnc~er-I&hou 4.9.8.2 At least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
- a. At least one shutdown cooling loop shall be verified to be in operation. i i
- b. The total flow rate of react:or coolant to the reactor pressure vessel shall be verified to be greater than or equal to 3000 gpm.*
- Th r~~~t~~ coolant flow rate requ r re uirement may be reduced to 1850 gpm if the, are satisfie d before the tore h uce re I following conditions en determined ave b een subcritical for at
~
implemented: the reactor has been erature is 117 'P I and the temperature least 125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br />,shutdown the maximum RC S tern pexchanger aner s
)oof CCW to o the cooling heat ST. LUCIE - UNIT 2 3/4 9-9 Amendment No. pd, pd'
~1 q ~
Op
~ OO ~
~e k
tj
~
.1
)
gl P m
o
REFUELING OPERATIONS BASES 3/4.9.6 MANIPULATOR CRANE The OPERABILITY requirements for the refuel1ng machine ensure that:
(Q manipulator cranes will be used for movement of fuel assemblies, with or without CEAs, (2) each crane has sufficient load capacity to lift a fuel assembly, with or without CEAs, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly, CEA and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the safety analyses.
3/4. 9. 8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140'F as required during the REFUELING MODE, and (2) sufficient coolant circulation is main-tained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.
The requirement to have two shutdown cooling loops OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange with irradiated fuel in the core ensures that a single fai lure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability. With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange with irradiated fuel in the core, a large heat sink is available for core cooling, thus in the event of a fai lure of the operating shutdown cooling loop, adequate time is provided to initiate emergency rocedures to cool the core.
happ 4/ 3/4. 9. 9 CONTAINMENT ISOLATION SYSTEM pgjggAP~
84' The OPERABILITY of this system ensures that the containment isolation gag'$ valves will be automatically isolated upon detection of high radiation leve 1 s restrict within the containment. The OpERABILITY of this system is required to the r elease of radioactive mater ial from the containment atmosphere to the environment.
ST. LUCIE - UNIT 2 B 3/4 9-2 A~a~&lr Klo.
il e
~a.
r
/ 1'+~
~
an
~
~
~ ~~ ~ <1 (ki:~3pg(" '
<Ygg y )g. 'p <p~A~h";Q
St. Lucie Unit 2 Docket No. 50-389 Proposed License Amendment SDCS Minimum Flow Rate Re uirements WP 9 I' PW I INSERT A The footnote providing for a minimum reactor coolant flow rate of a 1850 gpm considers one of the two RCS injection points for a SDCS train to be isolated. The specified parameters include 50 gpm for flow measurement uncertainty, and 3 'F uncertainty for RCS and CCW temperature measurements. The conditions of minimum shutdown time, maximum RCS temperature, and maximum temperature of CCW to the shutdown cooling heat exchanger are initial conditions specified to assure that a reduction in flow rate from 3000 gpm to 1800 gpm will not result in a temperature transient exceeding 140 'F during conditions when the RCS water level is at an elevation a 29.5 feet.
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