ML20006D869

Proposed Tech Spec 3/4.9.8.1 Changing Wording & Associated Bases

ML20006D869
Person / Time
Site:	Sequoyah
Issue date:	02/09/1990
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20006D867	List: ML20006D866 ML20006D869
References
NUDOCS 9002150158
Download: ML20006D869 (7)

Text

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ENCLOSURE- .o

i PROPOSED TECHNICAL SPECIFICATION CHANGE. -;

SEQUOYAN NUCLEAR PLANT UNITS 1 AND 2.  !

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. DOCKET NOS. 50-327 AND 50-328 l u'

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. R'EFUELING OPERATIONS -

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ALL WATER LEVELS LIMITING CONDITION FOR OPERATION FP 1

3.9.8.1 At least one residual heat removal (RHR) loop shall be in operation.

APPLICABILITY: MODE 6. ,

ACTION:

a. With less than one residual heat removal loop in operation, except  :

as provided in b. below, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System. Close all containment penetrations 1 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 />.

b.. The residual heat removal loop may be removed from operation for up I to I hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

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c. The provisions of Specification 3.0.3 are not applicable. ,

SURVEILLANCE REQUIREMENTS 4.9.8.1 At least one residual heat removal loop shall be verified to be in pp operation and circulating reactor coolant at a flow rate of greater than or ,

equal to gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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_ REFUELING OPERATIONS

_ BASES . . _ . - - . . . . . . . - .

3/4.9.6 MANIPULATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that:

1) manipulator cranes will be used for movement of drive rods and fuel assemblies,

2) each crane has suf ficient load capacity to lif t a drive rod or f uel assembly, 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 PIT AREA

' ' ' The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly 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 accident analyses.

3/4.9.8 RESIOUAL' HEAT REMOVAL AND COOLANT CIRCULATION

' The requirement that at least one residual heat removal (RHR) loop be in operation ensures that; l) 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 maintained through the reactor core to mininha tha affarti of boron dilution incident and prevent boron stratification.(Kdd INSERT , ,

TP The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability. With the, reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core. -

3/4 9.9 CONTAINMENT VENTILATION SYSTEM The OPERABILITY of this system ensures that the containment vent and purge penetrations w.ill be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

SEQUOYAH - UNIT 1 B 3/4 9-2

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. . INSERT A The minimum reguired flow rale of 2twyp ensures decay heat removaI, minimizes the probohili}y af losy an RHR pump h OIr - 8D brain /7)en b lrorY) jDufnf V0k N/n ,

Ond m A M 2C5 de potenha/ for ValVC dmnage due to cavifahon or cha & r.

Losing an /fHR pomjo is a par /7cular concern durino reduce d 2C 5 in /en fory u J  ;

operabion. Thc 2000 gprn Va Iue i5 It mi+e d by the polen4iql for C4 VIAQ 41on in the confro/ Va lVc ancI Chalb ering in t he 10-inch chec k v0 Ivc.

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REFUELING OPERATIONS '

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, . %g, 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION  ;

! ALL WATER LEVELS ,

LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one residual heat removal (RHR) loop shall be in operation.

7 APPLICABILITY: MODE 6. .

I ACTION:  ;

a. With less than one residual heat removal loop in operation, except '

as provided in b. below, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System. 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 />.

b. The residual heat removal 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 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs, i

~ - c. The provisions of Specification 3.0.3 are not applicable. ,

SURVEILLANCE REQUIREMENTS _

4.9.8.1 At least one residual heat removal loop shall be verified to be in operation and circulating reactor coolant at a flow rate of greater than or equal tu 4541r gpm at least once per.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. -

2000 1

i SEQUOYAH.- UNIT 2 324 9-9 l

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REFUELING OPERATIONS ,

BASES 3/4.9.6 MANIPULATOR CRANE  :

The OPERABILITY requirements for the manipulator cranes ensure that:

1) manipulator cranes will be used for movement of drive rods and fuel assemblies,

2) each crane has sufficient load capacity to lift a drive. rod or fuel assembly, assembly, 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 PIT AREA-The restriction on movement of loads in excess.of the nominal weight of a fuel and control raJ assembly 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 accident analyses.

3/4.9.8 RESIDUAL HEAT REMOVAL !.ND COOLANT CIRCULATION

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The requirement that at least one residual heat removal (RHR) loop be in operation ensures that; 1) sufficient cooling capacity is available to remove y 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 maintained thru the reactor core to minimile the effets of a baron dilution 1 incident and prevent boron stratification, g /gsgg7~ A * -

L The requirement to have two'RHR loops' OPERABLE when there is less than 23 feet of Ut $r above the reactor pressure vessel' flange ensures that a  !

I single faile a d the operating RHR loop.will not result in a complete loss of' <,

! residual heat removal capability. With the reactor vessel head removed and  !

L 23 f eet of water above- the reactor pressure vessel' flange, a large heat sink 1- is available for core cooling. Thus, in the event of a failure of the operating q RHR loop, adequate time is provided to initiate emergency procedures to cool ~

l the core. I l;

I 3/4.9.9 CONTAINMENT VENTILATION SYSTEM 1

L ,' The OPERABILITY of this syste'm ensures that the containment vent and l- purge penetrations will be automatically isolated upon detection of high 1: radiation levels within the containment. The OPERABILITY of this system is 1

! required to restrict the release of radioactive material from the containment '

L atmosphere to the environment.

SEQUOYAH - UNIT 2 B 3/4 9-2 L

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,J JNSERT A The minimum reguired flow rale of2QX)p A ensures decay hea6 eemovaI, misenkes she probahilily of losing an 2HR pump .

b O ir - 8 0 bfY1/ n /Y)8 M b fr orY) ;Dumf V0f' bCWfn ,

An$ In 17/m 2CS the joofenfia/ for ValV6 damage due to cavik%n or chancr.

Losing an KHR pump is a parbcular .

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concern durino reduced 265 inven fory operabion. Tr c 2000 gpm vafue i3 by the polenNa I for

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Nmi+e d cayMakn in the con 4rol va Ive and Ohallering in the IO-inch chec k valyc.

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