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Corrected Tech Spec Pages 3/4 2-8,3/4 4-19,3/4 7-66,3/4 8-9, 3/4 8-23 & B3/4 9-2
	ML20038C409
Person / Time
Site:	Farley
Issue date:	11/10/1981
From:	; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20038C410	List: ML20038C409;
References
	NUDOCS 8112100597
	Download: ML20038C409 (6)
	v • d • e

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POWER DISTRIBUTION LIMITS 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR - F g LIMITING CONDITION FOR OPERATION 3.2.3 F

shall be limited by the following relationship:

H F

$ l.55 [1 + 0.2 (1-P)] [1-RBP(BU)]

H where P = THERMAL POWER

' and RATED THERMAL POWER R8P(BU) = Rod Bow Penalty as a function of region average burnup as shown in Figure 3.2-3, where a region is defined as those assemblies with the same loading date (reloads) or enrichment (first cores).

APPLICABILITY:

MODE 1 ACTION:

With F exceeding its limit:

l a.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Tr.ip Setpoints to 1 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , b.

Demonstrate through in-core mapping that F is within its limit l

N within24hoursafterexceedingthelimithrreduceTHERMALPOWERto less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and Icentify and correct the cause of the out of limit condition prior c.

to increasing THERMAL PCWER above the reduced limit required by q or b, above; subsequer.: PCWER OPERATION may proceed provided that F' isdemonstratedthrcagnin-coremappingtobewithinitslimitakHa nominal 50% of RATEC T."ERMAL POWER prior to exceeding this THERMAL POWER, at a nominal 75% :f :ATED THERMAL POWER prior to exceeding this THERMAL power -

.itnin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after attaining 95% or greater RATED THEr 7aER.

8112100597 e1iiio DR ADOCK 05000364 p

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REACTOR COOLANT SYSTEM TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES Q2E11V016A Q2E11V001A Q2E11V016A Q2E11V001B Q2E11V051A Q2E11V051B Q2E11V051C Q2E11V021A Q2E11V021B Q2E11V021C Q2E11V042A Q2E11V042B Q2E21V077A*

Q2E21V0778*

Q2E21V076A*

Q2E21V076B*

I Q2E21V062A s

Q2E21V062B Q2E21V062C Q2E21V066A 02E21V066B C2E21V066C j

C2E21V077C 02E21V078A 02E21V078B C::21V078C 12E21V079A

E21V079B

'T_21V079C

- e*

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i TABLE 3.7-d AREA TEMPERATURE MONITORING AREA TEMPERATURE LIMIT (*F) 1.

ESF Pump Room:

a.

RHR Pump 2A 150*F b.

RHR Pump 2B 150*F c.

AFW Pump 2A 150*F d.

AFW Pump 2B 150*F e.

CCW Pump Room 150*F f.

Containment Spray Pump 2A 150*F g.

Containmant Spray Pump 2B 150*F h.

Charging Pump Room 2A 150*F j

i.

Charging Pump Room 2B 150*F j.

Charging Pump Room 2C 150 F 2.

Electrical Areas:

a.

MCC 2A Room 150 F b.

MCC 28 Room 150*F c.

600 Volt Load Center 20 Room 150*F d.

600 Volt Load Cente-IE Room 150 F e.

Battery Charger F 150*F f.

Battery Charger F 150*F g.

Battery Room A 120*F h.

Battery Room B 120*F i.

Diesel Generator 150*F j.

Diesel Generator 150 F 1

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ELECTRICAL POWER SYSTEMS i

J/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. DISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.1 The following A.C. electrical busses and inverters shall be OPERABLE and energized.

4160 volt Emergency Bus #

F, H and K 4160 volt Emergency Bus #

G, J and L 600 volt load Centers #

D, H, K and R 600 volt Load Centers #

E, J, L and S 120 volt A.C. Vital Bus # A energized from irverter #A connected to D.C.

Bus Train A* and 600 volt Load Center 0 tnrough 600 volt Motor Control Center A.

120 volt A.C. Vital Bus # B energized from inverter #8 connected to D.C.

Bus Train A* and 600 volt Load Center D through 600 volt Motor Control Center A.

120 volt A.C. Vital Bus # C energized from inverter #C connected to D.C.

Bus Train B* and 600 volt Load Center E through 600 volt Motor Control Center B.

120 volt A.C. Vital Bus # 0 energized from inverter #D connected to D.C.

Bus Train B* ano 600 volt Load Center E through 600 volt Motor Control Center B.

APPLICABILITY:

MODES 1, 2, 3 and 4 ACTION:

With less than the above corolement of A.C. busses OPERABLE and a.

energized, restore the incoerable busses to OPERABLE and energized status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least WOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the.ilo.ing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With one inverter inope

=. energize the associated A.C. Vital Bus within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; restore the i-

o CPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY with following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

- t 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the SURVEILLANCE REOUIREMENTS 4.8.2.1 The specified A.C.

and energized at least once

.ers shall be determined 0FERABLE and indicated power availab-

'fying correct breaker alignment

=

Two inverters may be discor ource for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for the purpose of performing a provided (1) their vital bu; their associated ba ttery bank busses associated witn the u-

ergized, and (2) the vital ERABLE and energize'.

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t I

i TABLE 3.8-1 (Continued)

CONTAINMENT PENETRATION CONOUCTOR OVERCURRENT PROTECTIVE CEVICES I

Device Numcer Trip Setpoint Response Time System and Location (Ascere)

(Secords)

Powered 6.

600VAC Pressuri:er Distr. Pn1 2S SKA #1 750-1600

.01.-016 Pressuri:er Htr Group IS SKR 82 750-1600

.01.-016 Terminal Box N2T3011 BKR #3 750-1600

.01.-016 SKR 84 750-1600

.01.-016 BKR 85 750-1600

.01.-016 7.

600VA0 Pressurt:er Htr. Distr. Pn1 2C Cir:uit Skrs.

SKR *1 750-1600

.01.013 Pressuri:er Mtr Group 20 SKR *2 750-1600

.31.016 Terminal Sex NOT3008 BKR 83 750-1600

.01.016 BKR #4 75C-1600

.01.016 SKR #5 750-16C0

.01.016 SKR *6 750-1600

.01.016 i

SKR #7 750-1600

.01.016 8.

600VAC Pressuri:er Htr. Diste. Pn1 20 Cir:uit Skrs.

SKR *1 750-15--

.01.016 Pressuri:er Htt Group 20 SKR e2 750-l'

.01.016 Terminal Sex N2T3007 BKR 83 750-1

.01.016 3KR #4 750 '

.31.016 9.

60CVAC 8ressuri:er nTR. Diste. Pn1 2E Cir:uit 3krs.

3KR *1 750-

'16 Pressuri:er htr Group ZE SKR *2 750-Termi al Sex N2T30C9 SKR #3 750 '

BKR 84 750 '.

SKR #5 750.

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REFUELING OPERATIONS BASES l

MANIPULATOR CRANE (Continued) or fuel 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 SPENT FUEL STORAGE BUILDING - BRIDGE CRANE and SPENT FUEL CASK CRANE i

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 l

result in a critical array.

This assumption is consistent with the activity release assumed in the accident analyses.

The outdoor overhead gantry crane does not meet the design requirements for wire rope strength and fleet angle safety margins of reeving systems, therefore the ropes must be inspected to assure that they meet the require-ments of the standard specified in the surveillance.

Cold proof tests of the crane will be performed to demonstrate OPERABILITY.

It is permissible to operate the crane at temperatures less than the temperature at which it was proof tested, provided these operations take place at derated loads as stated in the action statement.

3/4.9.8 RESIDUAL HEAT REMOVA'. l'O COOLANT CIRCULATION The requirement that at 1+sst one residual heat removal loop be in operation ensures that 1) suft cient cooling capacity is available to remove decay heat and maintain the wata-in the reactor pressure vessel below 140 F as required during the REFUELING MODE, and 2) sufficient coolant circulation l

is maintained thru the react - : ore to minimize the effects of a boron dilution incident and preve-cron stratification.

The requirement to ha W loops OPERABLE when there is less than i

23 feet of water above the cressure vessel flange ensures that a l

single failure of the oper

'coe will not result in a complete loss of l

residual heat removal cac:

tne reactor vessel head removed and 23 feet of water above the

~ vessel flange, a large heat sink is available for core coo' event of a failure of the a

operating RHR loop, adecus 1 to initiate emergency procedures to cool the core.

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ML20038C409

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