Text

Amend 80 to License NPF-3,modifying Tech Specs to Permit Operation for Cycle 5
	ML20101L377
Person / Time
Site:	Davis Besse
Issue date:	12/13/1984
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Toledo Edison Co, Cleveland Electric Illuminating Co
Shared Package
ML20101L381	List: ML20101L377; ML20101L404;
References
	NPF-03-A-080 NUDOCS 8501020209
	Download: ML20101L377 (54)
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UNITED STATES f

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NUCLEAR REGULATORY COMMISSION E

WASHINGTON, D. C. 20555

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s TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 80 License No. NPF-3 1.

The Nuclear Regulatory Comission (the Cocinission) has found that:

The application for amendment by the Toledo Edison Company)and A.

The Cleveland Electric Illuminating Company (the licensees dated July 20, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and i

safety of the public, and (ii) that such activities will be conducted l

in compliance with the Comission's regulations; l

D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 i

of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical i

Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:

l 8501020209 841213 PDR ADOCK 05000346 P

PDR

s 2-Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 80, are hereby incorporated in the license. The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGUL TORY COMMISSION e

l

+

ohn F. Stolz, Chief J

Op ating Reactors Branch #4 lvision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: December 13, 1984 i

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_ ATTACHMENT TO LICENSE AMENDMENT NO. 80 FACILITY-0PERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Insert Page Remove Page 2-3 2-3 2-5 2-5 2-7 2-7 B 2-2 B27 B 2-5 8 2-5 3/4 1-26 3/4 1-26 3/4 1-28 3/4 1-28 3/4 1-28a 3/4 1-28a 3/4 1-28b 3/4 1-78b 3/4 1-28c 3/4 1-28c 3/4 1-28d 3/4 1-28d 3/4 1-29 3/4 1-29 3/4 1-29a 3/4 1-29a 3/4 1-29b 3/4 1-29b 3/4 1-29:

3/4 1-29c 3/4 1-29d 3/4 1-29d 3/4 1-31 3/4 1-31 3/4 1-34 3/4 1-34 3/4 1-35 3/4 1-35 3/4 1-36 3/4 1-36 3/4 1-37 3/4 1-37 3/4 1-38 3/4 1-38 3/4 1-39 3/4 1-39 3/4 1-40 3/4 1-40 3/4 1-41 3/4 1-41 3/4 1-42 3/4 1-42 3/4 1-43 3/4 1-43 3/4 2-1 3/4 2-1 l

3/4 2-2 3/4 2-2 3/4 ?-2a 3/4 2-2a 3/4 2-2b 3/4 2-2b 3/4 2-2c 3/4 2-2c 3/4 2-2d 3/4 2-2d j

3/4 2-3 3/4 2-3 3/4 2-3a 3/4 2-3a 3/4 2-3b 3/4 2-3b 3/4 2-3c 3/4 2-3c 3/4 2-3d 3/4 2-3d 3/4 2-12 3/4 2-12 3/4 4-1 3/4 4-1 e

L

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6 Figure 2.1-2 Reactor Core Safety Limit,

% RATED THERMAL POWER

- 120

(-48,112.0)

(44,112)

~~

- 100 (49,100)

(-49,100.0)

(-48,89.1) r (44,89.1)

P 3 PUMP LIMIT

- 80

(-49,77.1)- (

)(49,77.1)

ACCEPTABLE

- 60 OPERATION UNACCEPTABLE FOR SPECIFIED UNACCEPTABLE OPERATION RC PUFiP OPERATION COMBINATION 40

- 20 1

1 1

1 I

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I

-60 40

-20 0

20 40 60 Axial Power Imbalance, %

PUMPS OPERATING REACTOR COOLANT FLOW, GPM 4

387,200 3

290,100 DAVIS-CESSE, UNIT 1 2-3 Ar.endm::nt No. 77, JE, 73, FE, Ey.

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SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS e

REACTOR PROTECTION SYSTEM SETPOINTS 2.2.1 The Reactor Protection System instrumentation setpoints shall be set consistent with tne Trip Setpoint values shown in Table 2.2-1.

APPLICABILITY: As shown for each channel in Table 3. *-1.

ACTION:

With a Reactor Protection System instrumentation setpoint less conserv-ative than the value shown in the Allowable values column of Table 2.2-1, declare the channel inoperable and apply the aopif cable ACTION statenent requirement of Specification 3.3.1.1 until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

DAVIS-BESSE, UNIT 1 2-4

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_ Table 2.2-1 Reactor Protection System Instrumentation Trip Setpoints En C

w" Functional unit Trip setpoint Allowable values 4

1.

Manual reactor trip Not applicable.

Hot applicable.

2.

liigh flux

<104.94% of RATED THERMAL POWER with

<104.94% of RATED TilERMAL POWF.R wi th Tour pumps operating Tour pumps operatingI

<79.7% of RATED THERMAL POWER with

<79.7% of RATED TilERMAL POWER with l

Ihree pumps operating Three pumps operatingI 3.

RC high temperature

<618*F

<618*FI 4.

Flux -- aflux/ flow (II Trip setpoint not to exceed the lim-Allowable values not to exceed tlie it line of Figure 2.2-1 limit line of Figure 2.2-18

{

5.

RC low pressureIII

>1983.4 psig

>1983.4 psig*

>1983.4 psig**

6.

RC high pressure

<2300 psig

<2300.0 psig*

<2300.0 psig**

7.

RC pressure-temperature (l)

>(12.60 Tout F - 5662.2) psig

>(12.60 T ut *F - 5662.2) psigI o

pumps oni{ number of RC liigh flux

<55.1% of RATED TilERMAL POWER with

<55.1% of RATED THERMAL POWER with 8.

)

one pump operating in each loop one pump operating in each loopI

<0.0% of RATED THERMAL POWER with

<0.0% of RATED THERMAL POWER with Two pumps operating in one loop,aiid Two pumps operating.in one loop and no pumps operating in the other loop

.no pumps operating in the other loopI

<0.0 of RATED THERMAL POWER with no

<0.0% of RATED THERMAL POWER with no l

f Fumps operating or only one pump op-liumps 00erating or only one pump op-erating erating'

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$5

=

9.

Containment pressure high

<4 psig

<4 psigI U

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5 T'

h Table 2.2-1.

(Cont'd) m Trip may be manually b"ypassed when'RCS pressure $1820 psig by actuating shutdown bypass provided that:

Q a.

The high flux trip setpoint is 55% of RATED TilERMAL POWER.

b.

The shutdown bypass high pressure trip setpoint of s1820 psig la imposed.

c.

The shutdown bypass is removed when RCS pressure >l820 psig, o

Allowable value for CilANNEL FUNCTIONAL. TEST.

r

- Allowable value for CllANNEL cal.IBRATION.

Allowable value for CIIANNEL FUNCTIONAL TEST and CilANNEL CALIBRATION.

+

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Figure 2.2-1 Trip Setpoint for Flux -- AFlux/ Flow Curve shows trip setpoint for a 25% flow reduction for three pump operation (290,100 cpm).

The actual setpoint will be directly procortional to tha actual flow with three pumps.

% RATED THERMAL POWER

- 120 UNACCEPTABLE OPERATION UNACCEPTABLE OPERATION

(-18.2,106.8)

(18.2,106.8)

M =1.000 M =-1.000 1

I LIMIT

(-34.0,91.0) 34.0,91.0) i I

i 1

80 (18.2,l79.7)

(-18.2,j 79.7) l 3iPUMP l

(-34.0,63.9) l LIfIT l

34.0,63'.9)

- 60 l

I l

1 l

ACCE ABLE OPERATION F@

l SPECI IED RC PUMP COMBIgNATION.I I

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- 40 l

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- 20 l

l I

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-60

-40

-20 0

20 40 60 l

i Axial Power Imbalance, %

4 l

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i DAVIS-BESSE, UNIT 1 2-7 Amendment No. 77, 7:1, D, #

61, 80 g,. x

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Figure. 2.2. 2 Allowable value for Mu-a Fla/now DLW l

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Amendment ?!o. p,Xr,g,45 DAVIS-BESSE, UNIT 1 P

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2.1 SAFETY LIMITS BASES 2.1.1 and 2.1.2 REACTOR CORE The restrictions of this safety limit prevent overheating of the fuel cladding and possible cladding perforation wnich would result in the release of fission products to the reactor coolant. Overneating of the fuel cladding is prevented by restricting fuel operation to within the nucleate boiling regime wnere the heat transfer coefficient is large and the cladding surface temperature is sligntly above the coolant saturation temperature.

Ooeration above the upper boundary of the nucleate boiling regime would result in excessive cladding temperatures because of the onset of departure from nucleate boiling (DNB) and :ne resultant sharp reduction in heat transfer coefficient. DNB is not a directly measurable parameter during operation and therefore THERMAL POWER and Reactor Coolant Temper-ature and Pressure have been related to DNB through the B&W-2 DNB correlation. The DNS correlation has been develcoed to predict ne DNB flux and tne location of DNS for axially unifom and non-uniform neat flux distributions. The local DNB neat flux ratio. DNBR, defined as the ratio of the neat flux that would cause DNB at a carticular core location to tne local heat flux, is indicative of the margin to DNB.

The minimum value of the DNBR during steady state operation, normal operational transients, and anticipated transients is limited to 1.30.

This value corresponds to a 95 percent probability at a 95 percent conficence level that DNB will not occur and is cnosen as an acptcoriate margin to DNB for all operating conditions.

The curve presented in Figure 2.1-1 represents the conditions at wnien a minimum DNBR of 1.30 is predicted for the maximu ; possible thermal power 112: wnen :ne reactor coolant flow is 387, 200 GPM, which is 110% of design flow rate for four operating reactor coolant cumos. This curve is based on the following hot enannel factors with potential fuel densifi-cation and fuel rod bowing effects:

FN = 1.50 Fg = 2.55; Fh = 1.71; The design limit power peaking factors are the most restrictive calculated at full power for the range frem all control rods fully witndrawn to minimum allowable control rod withorawal, and for n the core DNBR design basis.

Amendment No.11I3 3 DAVI5-BESSE, UNIT I B2-1

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d SAFETY LIMITS BASES The reactor trip envelope appears to approach the safety limits more close-ly than it actually does because the reactor trip pressures are measured at a location where the indicated pressure is about 30 psi less than core out-let pressure, providing a more conservative margin to the safety limit.

The curves of Figure 2.1-2 are based on the more restrictive of two thermal limits and account for the effects of potential fuel densification and po-tential fuel rod bow.

1.

The 1.30 DNBR limit produced by a nuclear power peaking factor of FO*

2.56 or the combination of the radial peak, axial peak, and position of the axial peak that yields no less than a 1.30 DNBR.

1 2.

The combination of radial and axial peak that causes central fuel melt-ing at the hot spot. The limits are 20.4 kW/f t for batches IE, 48, and 5A and 20.5 kW/ft for batches 5B, 6, and 7.

Power peaking is not a directly observable quantity and therefore limits have been established on the basis of the reactor power imbalance produced by the power peaking.

The specified flow rates for curves 1 and 2 of Figure 2.1-2 correspond to the expected minimum flow rates with four pumps and three pumps, respective-ly.

The curve of Figure 2.1-1 is the most restrictive of all possible reactor coolant pump-maximum thermal power combinations shown in BASES Figure 2.1.

The curves of BASES Figure 2.1 represent the conditions at which a minimum

+

DNBR of 1.30 is predicted at the maximum possible thermal power for the num-ber of reactor coolant pumps in operation or the local quality at the point of minimum DNBR is equal to +22%, whichever condition is more restrictive.

These curves include the potential effects of fuel rod bow and fuel densiff-cation.

The DNBR as calculated by the B&W-2 DNB correlation continually increases from point of minimum DNBR, so that the exit DNBR is always higher.

Extrap-olation of the correlation beyond its published quality range of +22% is justified.on the basis of experimental data.

8 2-2 Amendment No. 77, 73, AE, E7, 30 DAVIS-BESSE, VI'IT 1 1

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LIMITING SAFETY SYSTEM SETTINGS BASES Y

RC High Temoerature The RC high temperature trip <618'F prevents the reactor outlet temperature from exceeding the design limT'ts and acts as a backup trip for all power ex-cursion transients.

Flux -- aFlux/ Flow The power level trip setpoint produced by the reactor coolant system flow is based on a flux-to-flow ratio which has been established to accommodate flow decreasing transients from high power where protection is not provided by the high flux / number of reactor coolant pumps on trips.

The power level trip setpoint produced by the power-to-flow ratio provides both high power level and low flow protection in the event the reactor power level increases or the reactor coolant flow rate decreases.

The power level setpoint produced by the power-to-flow ratio provides overpower DNB protection for all modes of pump operation.

For every flow rate there is a maximum permissible power level, and for every power level there is a minimum permissible low flow rate.

Examples of typical power level and low flow rate combinations for the pump situations of Table 2.2-1 that would result in a trip are as follows:

1.

Trip would occur when four reactor coolant pumps are operating if power is 106.8% and reactor coolant flow rate is 100% of full flow rate, or flow rate is 93.63% of full flow rate and power level is 100%.

2.

Trip would occur when three reactor coolant pumps are operating if power is 79.7% and reactor coolant. flow rate is 74.7% of full flow rate, or flow rate is 70.22% of full flow rate and power is 75%.

For safety calculations the instrumentation errors for the power level were used. Full flow rate in the above two examples is defined as the flow cal-culated by the heat balance at 100% power.

1 DAVIS-BESSI, 'JNIT 1 B 2-5 Amendment Ho. JE, 73, f), sJ,00

LIMITING SAFETY SYSTEM SETTINGS BASES The AXIAL POWER IMBALANCE boundaries are established in order to prevent reac-tor thermal limits from being exceeded. These thermal limits are either power peaking kW/ft limits or Df8R limits.

The AXIAL POWER IMBALANCE reduces the power level trip produced by a flux-to-flow ratio such that the bounda-ries of Figure 2.2-1 are produced.

RC Pressure - Low, High, and Pressure Temoerature The high and low trips are provided to limit the press ~ure range in which reac-tor operation 1.s permitted.

During a slow reactivity insertion startup accident from low power or a slow reactivity insertion from high power, the RC high pressure setpoint is reached before the high flux trip setpoint.

The trip setpoint for RC high pressure, 2300 psig, has been established to maintain the systen pressure be-low the safety limit, 2750 psig, for any design transient.

The RC high pres-sure trip is backed up by the pressurizer code safety valves for RCS over pressure protection, and is therefore set lower than the set pressure for these valves,1 2525 psig. The RC high pressure trip also backs up the high flux trip.

The RC low p essure,1983.4 psig, and RC pressure-temperature (12.60 tout -

5662.2) psig, trip setpoints have been established to maintain the ONB ratio greater than or equal to 1.30 for those design accidents that result in a cressure reduction.

It also prevents reactor coeration at pressures below the valid range of DNB correlation limits, protectino against DNB.

Hioh Flux / Number of Reactor Coolant Pumos On In conjunction with the flux -

aflux/ flow trip the high flux / number of reac-tor coolant pumps on trio prevents tne minimum core DNBR from decreasing

', below 1.30 by tripping the reactor due to the loss of reactor coolant pump (s).

The pump monitors also restrict the power level for the nuccer of pumos in operation.

l B 2-6 DAVIS-BESSE, UNIT 1 Amendment Mo. 33, AE, $3, 61 r---

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REACTIVITY CONTROL SYSTEMS SAFETY R0D INSERTION LIMIT.

LIMITING CONDITION FOR OPERATION 3.1.3.5 All safety rods shall be fully withdrawn.

~

APPLICABILITY:

1* and 2*#.

ACTION:

With a maximum of one safety rod not fully withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, within one hour either:

a.

Fully withdraw the rod or b.

Declare the rod to be inoperable and apply Specification 3.1.3.1.

SURVEILLANCE REQUIREMENTS 4.1.3.5 Each safety rod shall be determined to be fully withdrawn:

a.

Within 15 minutes prior to withdrawal of any regulating rod during an approach to reactor criticality, b.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

See Special Test Exception 3.10.1 and 3.10.2.

With Keff > 1.0.

i DAVIS-BESSE, UNIT 1 3/4 1-25

' REACTIVITY CONTROL SYSTEMS i

REGULATING ROD INSERTION LIMITS

' LIMITING CONDITICN FOR OPERATION 3.1.3.6 The regulating rod groups shall be limited in physical insertion as shown on Figures 3.1-2a, -2b, -2c, and -2d and 3.1-3a, -3b, -3c and -3d. l A rod group overlap of 25.

5*. shall be maintained between sequential with-drawn groups 5, 6 and 7.

APPLICABILITY: MODES 1* and 2*#.

ACTION With the regulating rod groups inserted beyond the above insertion limits (in a region other than acceptable operation), or with any group sequence or overlap outside the specified limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, either:

a.

Restore the regulating groups to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or b.

Reduce THERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the_ rod group position using the above figures within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or c.

Be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

NOTE:

If in unacceptable region, also see Section 3/4.1.1.1.

4

See Special Test Exception 3.10.1 and 3.10.2.

With keff 1 1.0.

f DAVIS-BESSE, UNIT 1 3/4 1-25 Amendment No. 77, 33, /J, #E, EJ, l

$7,20 l.

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W REAC*iVI*Y C M CL SYSTE"5 t!GULATING RCC INSERTION UMIT3 SURVEILLANCi RECUIRE"EN'S 4.1. 3. 5 The position of esca regulating grous shall be detemined to be witnin the insertien, sequenca and overlag limits at least onca every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months exces: when:

a.

The regulating md insertion limit alam is incoerable, then verify tae gmuss :s he witain tae insertion Ifmits at less:

onca per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; I

3.

De ::ntml ed drive secuence alam is incoersble, then verify tae smu:s :s be within :na sequenca anc overlas limits a: least onca per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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Figure 3.1-2a Regulating Group Position Limits, O to 25+10/-0 E,F,P0, Four RC Pumps -- Davis-Besse 1, Cycle 5 (275,102)

(229,102) 100 Power Level Cutoff = 100%

(300,102)

(270,92)

=

W SHUTDOWN 80 2

MARGIN (250,80)

LIMIT a

i f

e M

UNACCEPTABLE RESTRICTED 60 OPERATION OPERATION Pa j

(1

, 0)

(225,50) e 40 E

E 20 b

ACCEPTABLE

[

86,15)

OPERATION (0,7.6) 0 8

8 0

100 200 300 Rod Index (% Withdrawn)

GR 5' I

O 75 100 GR 61 1

1 0

25 75 100 GR 7' I

0 25 100 DAVIS-BESSE, UNIT 1 3/4 1-20 Amendment !!c. 77, 33, /E, 37, 80 6

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Figure 3.1-2b Regulating Group Position Limits, 25+10/-0 to 200t10 EFPD, Four RC Pumps -- Davis-Besse 1, Cycle 5 (229,102)

(275102{

100 -

Power Level (200,102)

Cutoff = 100%

(270,92) 2 u

SHUTDOWN (225,80) 5 80 MARGIN g

, LIMIT 0

p[4 UNACCEPTABLE P

OPERATION 60 S

A y

(159,50)

['

(200,50)

T 40 a

5 E

S ACCEPTABLE OPERATION

[

(8A,15)

'(0,7.5) lb0

200, 300 0

Rod Index (% Withdrawn)

GR5b 75 100 i

GR 6 0 5

75 100 i

e s

GR 7,0 25 100 I

i

!-i i

DAVIS-BESSE, UNIT 1 3/4 1-20a Amendment Ho, JJ, 33, /2, AE, i7,80 O

Figure 3.1-2c Regulating Group Position Limits, 200 10 to 330 t10 EFPD, Four RC Pumps -- Davis-Besse 1, Cycle 5 (275,102)

(267,102)

=

2 100 Power Level (300,102)

Cutoff = 100%

OPERATION RESTRICTED (270,92)

_m 80

(

9,80)

SHUTDOWN MARGIN a

g LIMIT wA 60 e

UNACCEPTABLE OPERATION (200,50) o 40 5

E ACCEPTABLE OPERATION g

20 j

(126,15)

' (0,5.7) 00 100 200 300 Rod Index (% Withdrawn)

GR 5 3

7S 100 0

25 75 100 GR 7 0

25 100 DAVI5-BESSE, UNIT T 3/4 1-20b Amendment flo. 47, AE, $J, $7,80

o Figure 3.1-2d Regulating Group Position Limits, 330 110 to 390 t10 l

EFPD, Four RC Pumps, APSRs Withdrawn -- Davis-Besse 1, Cycle 5 (271,102)-

100 -

Power Level (300,102)

Cutoff = 100%

SHUTDOWN MARGIN 3

8C -

LIMIT c-a f

sP 60 S

Q UNACCEPTABLE (206'50)

OPERATION o

4C -

,=

8 ACCEPTABLE OPERATION t

20 (134,15) 1 0 (0,4.6) 0 100 200 300 Rod Index (% Withdrawn)*

I C-R 5 O

75 100 i

f I

t GR 6 0 25 75 100 GR 7 0

25 100 I

i I

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DAVZS-BESSE, Ui;IT 1 3/4 1-2Cc Amendment l'o. /E, 37, D, 80 l

o Figure 3.1-2e Deleted I

DAVIS-BESSE, UNIT 1 3/4 1-28d Amendment flo. (J, $7, 67, go

Figure 3.1-3a Regulating Group Position Limits, O to 25+10/-0 EFPD, Three RC Pumps -- Davis-Besse 1, Cycle 5 100 -

(275,77) 5 (229,'77) 80

?

(300,77) l (270,69.5)

SHUTDOWN a:

MARGIN (250,60.5)

N 60 LIMIT S

PERATION UNACCEPTABLE OPERATION 40 (109,38)

(225,38) 5 0

f 5

20 ACCEPTABLE OPERATION g

(86,11.75)

, (0,6.2) i i

b 100 200 300 Rod Index (*. Withdrawn)

GR 5 0 75 100 I

I I

I GR 6 0

25 75 100 l

i i

I GR 7 25 100 0

I DAVIS-BESSE, UNIT 1

.3/4 1-20 Amendment No. 77, 33, /7, f3 01,80

Figure 3.1-3b Regulating Group Position Limits, 25+10/-0 to 200 010 EFPD, Three RC Pumps -- Davis-Besse 1, Cycle 5 100 -

2 (275,77) 80 (229,77)

(300,77) a.

aI 8

(270,69.5) 5 h (225.60.5)

SHUTOOWN iE 60 MARGIN

[4 e

LIMIT i

?

I UNACCEPTABLt OPERATION 40 (159,38)

(200,38) 8 t

S:.

ACCEPTABLE c

20 -

OPERATION g

86,11.75)

~-

I 0

O 100 200 300 Rod Index (*. Withdrawn)

GR 5 O

75 100 GR 6 25 75 100 0

i t

1 OR 7 0 25 100 1

3 AVIS-DESSE, UillT 1 3/4 1 2ga Amandaant to. 11, pp, pg, pp, py, 80 l

Figure 3.1-3c Regulating Group Position Limits, 200 !10 to 330 !10

)

EFPD, Three RC Pumps -- Davis-Besse 1, Cycle 5 100 o

2 w

(275,77) 3 80 (267,77)

(300,77) h OPERATION RESTRICTED -

270,69.5)

A 60 (239,60.5) 9 E

=

SHUTDOWN MARGIN LIMIT 40 g

UNACCEPTABLE (200,38) t OPERATION E

ACCEPTABLE b

20 j

OPERATION (126,11.75) g (0,4.7) i 0

100 200 300 Rod In,dex (". Withdrawn) 0 75 100 GR 6 O

25 75 100 0

25 100 l

l l

{

l DAVIS-CESSE, UNIT 1 3/41-29b Amendment No. 77, JA, /2, /E, H,19, 03 i

Figure 3.1-3d Regulating Group Position Limits, 330 10 to 390 10 EFPD, Three RC Pumps, APSRs Withdrawn -- Davis-Besse

1. Cycle 5 100 -

2sg 80

.(271,77)-

S (300,77) f i:

SHWDOWN 60 MARGIN c

W LIMIT I

UNACCEPTABLE g

OPERATION 40 j

(206,38)

E b

20 ACCEPTABLE 3

OPERATION (134,11.75)

(0,4.0) t f

I O O 100 200 300 RodIndex(". Withdrawn}

GR 5 0

75 100 0 0 0

23 75 100 l

f l

GR 7 0 25 100 DA"IS-DISSE, UllIT 1 3/4 1-20c Amendment !!o. JJ, 33, /J,57, /s, 80 e

PL.

P

Figure 3.1-3e Deleted DAVIS-BESSE, UNIT 1 3/4 1-29d Amendment No. A5, $7, 87, l

80 I

i i

1 l

l i

l REACTIVI*Y CONTROL SYSTEMS R00 PROGRAM LIMITING CON 0! TION FOR OPERATION J.1.3.7 Each control rod (safety, regulating and APSA) shall be pro-granmed to operate in the core position and rod group specified in Figure 3.1 4.

I APPLICABILITY: MODES l' and 2*.

AC TON:

With any control rod not programed to coerate as specified above, he in HOT STANOSY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

SURVEILLANCE RECUIREw!NTS 4.1.3.7 a.

Each control rod shall be demonstrated to be prograned to operate in the specified core position and rod gr up by:

1.

Selection and actuation fran the centrol room and verifi-cation of movement of the proper rod as indicated by both the assolute and relattve position indicators:

i a)

For all control rods, after the control red drive patenes are locked subsecuent to test, reprograming or maintenanca within the panels.

b)

For specifically affected individual rods, following i

maintenance, test, reconnection or modification of power or instrumentation canles from the control rod i

drive control system to the control rod drive.

2.

Verifying that eacn cable that has been disconnected has I

been properly matened and reconnected to the specified control rod drive.

I b.

At least once esca 7 days, verify that the control red drive paten panels are locked.

'see 5pecial Test uceptions 3.10.1 and 3.10.2.

OAV!S-BESSE. UNIT 'l 3/4 1-30 knendment No.11

~

Figure 3.1-4 Control Rod Core Locations and Group Assionments -- Davis-Besse 1, Cycle 5 X

l-A B

3 7

3 C

2 6

6 2

1 0

7 8

.5 8

7 E

2 5

5 2

i F

3 8

1 7

1 8

3 G

6 4

4 6

W-7 5

7 1

7 5

7

-Y H

K 6

4 4

6 L

3 8

1 7

1 8

3 j

M 2

5 5

2 N

7 8

5 8

7 0

2 6

6 2

P 3

7 3

i R

l Z

1 2

3 4

5, 6

7 8

9 10 11 12 13 14 15 l

No, of l

Grouc rods Functions 1

5 Safety 2

8 Safety

'X Group Number 3

8 Safety l

l 4

4 Safety i

5 8

Control 6

8 Control 7

12 Control 8

8 ApSRs Total #

61 j

DAVIS-BESSE, UtlIT 1

, /,4 1 - 31 Amendment flo. 77, 33, f), 7t 3

80

LMTDTiCMLLY LST $1.ANg

...I........ e-::.us:.,,,N.,

3p ; ~"..

knenc: ment Ma,11 e

REACTIVITY CONTROL SYSTEMS XENCN REACTIVITY LIMITING CCNDITION FOR OPERATION 3.1.3.8 THERMAL POWER shall not be increased above the power level cutoff specified in Figure 3.1-2 unless one of the following conditions is sa tisfied:

a.

Xenon reac*.ivity is witnin 10 percent of the equilibrium value for RATED THERMAL PCWER and is approaching stability, or b.

THERNAL PCWER has been within a range of 87 to 92 percent of RA ED THERFAL PCWER for a period exceeding 2 nours in the soluole poison control soce, excluding xenon free start-ups.

APDLICA31LI*Y: MCOE 1.

AC* ION:

Witn tne recuirements of the above soecification not :atisfied, recuce THE?JiAL PCWER to less taan or ecual to t.ie power level cutoff witnin 15 minutes.

I SURVI:LLANCE RECUIREMENTS 4.1.3.3 Xenon reactivity shall be datemined to be within 10% of the ecutlierium value for RATED TMEFF.AL PChER and to be a: reacning stability cr it sna11 te detamined tnat the THERFAL PCiiER has :een in tne aange :f 37 to 92% of RATED THERMAL PCWER for 1 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , prior to increasing THEAMAL PCWER acove the power levt1 cutoff, i

CAVIS-BEISE, UNIT 1 3/4 l-33 e

REACTIVITY CONTROL SYSTEMS AXIAL POWER SHAPING R0D INSERTION LIMITS LIMITING CONDITION FOR OPERATION

'f 3.1.3.9 The axial power shaping rod group shall be limited in physical in-sertion as shown on Figures 3.1-Sa, -5b, -5c, -5d, -Se, -5f, and -5g.

l APPLICABILITY: MODES 1 and 2*.

ACTION With the axial power shaping rod group outside the above insertion limits, either:

a.

Restore the axial power shaping rod group to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or b.

Reduce THERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the rod group position using the above figures within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or c.

Be in at least HOT STAND 8Y within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REOUIREMENTS 4.1.3.9 The position of the axial power shaping rod group shall be deter-mined to be within the insertion limits at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except l

when the axial power shaping rod insertion limit alarm is inoperable, then verify the group to be within the insertion limit at least once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

With Keff2,1.0.

l DAVIS-BESSE, UNIT 1 3/4 1-34 Amendment i:o. 33, AE, /5, $7, $)

80 e

Figure 3.1-Sa APSR Position Limits, 0 to 25+10/-0 EFPD, Four RC Pumps -- Davis-Besse 1, Cycle 5

( 9,1_02 )

(38,102)

' ' ~

100

'I9'92)

(38,92)'

RESTRICTED g

REGION w

80<

g (0,80)

(50,80) a f

awA 60 od E

(100,50) e PERMISSIBLE 40 g

OPERATING REG:0N 8

t S.

g 20 5

0 f

I I

i f

f 0

10 20 30 40 50 60 70 80 90 100 APSR Position (". Withdrawn) l l

l i

DAVIS-BESSE, UNIT 1 3/4 1-35 Amendment t'o EE, /E, El,80 6

\\

Figure 3.1-5b APSR Position Limits, 25+10/-0 to 200 10 EFPD, Four RC Pumps -- Davis-Besse 1, Cycle 5 (9,102)

(42,102)

C 100 RESTRICTED (9,92)

(42'92)

REGION p

5 80s c

(0,80)

I (50,80) 1 m

"=*

60 8

2 (100,50)

PERMISSIBLE 40 OPERATING REGION a

5 E

E b

20 E

~'

0O 10 20 30 40 50 60

, 70 80 90 100 APSR Position (% Withdrawn) l l

i e

l i

5 1

DAVIS ~-BESSE, UNIT 1 3/4 1-36 Amendment ?!o. p, pg, 33, y,

80 4

a

Figure 3.1-Sc APSR Position Limits, 200 t10 to 330 t10 EFPD,

-Four RC Pumps -- Davis-Besse 1, Cycle 5 1

( 9,C102)

(42,102) 100 (9,92)

RESTRICTED (42,92)

REGION 5

80i l

(0,80)

(50,80) c.

N z

s (100,70) 60 O

E PERMISSIBLE

[

OPERATINr, REGION 40 E

g 20 3

c 0O 10 20 30 40 50 6,0 70 80 90 100 APSR Position (% Withdrawn)

DAVIS-BESSE, U IT 1 3/4 1-37

__g Ancndment :!o. 33, /3, 37, 77, 80

-, - - ~

-,-r t.--

a p.

,y

-g-

p sw w-g p-

..,n

_-_g-

.-v*m-r

Figure 3.1-5d APSR Position Limits, 330 10 to 390 210 EFPO, Three or Four RC Pumps, APSRs Withdrawn --

Davis-Besse 1, Cycle 5 100 2

w 2

80 a

h w

C W

60 APSR INSERTION NOT ALLOWED IN THIS TIME INTERVAL t

40

~

Eg s.

g 20 o.

i' 0

0 10 20 30 40 50 60 70 80 90 100 APSR Position (% Withdrawn)

DAVIS-BESSE, UNIT I 3/4 1-08 Amendment t!o. 33, pg, Ay, gy, gg, 80

Figure 3.1.h APSR Position Limits, O to 25+10/-0 EFPD, Three RC Pumps -- Davis-Besse 1, Cycle 5 100 5

5 c.

80 5

(38,77)

(9,77)

RESTRICTED

=

.(,69.5)

(38,69.5)\\

REGICN (0,60.5)

(50,60.5) o l

40 I

100,38)

PERMISSIBLE OPERATING REGION u

20 2

I 0

O 10 20 3,0 40 50 40 70 80 90 100 APSR Position (". Withdrawn)

DAVIS-BESSE, UNIT 1

~3/t,1-39 Amendment !'o. /7, /E, JJ, gg, 80

o Figure 3.1-5f APSR Position Limits, 25+10/-0 to 200 10 EFPD, Three RC Pumps -- Davis-Besse 1, Cycle 5 100 8

o.

(9 77)

(42,77\\

80 t

RESTRICTED REGION

'(9,69.5)

(42,69.5) g

{j (0,60.5)

(50,60.5)

~

o Y

40 (100,38)

,5 PERMISSIBLE g

OPERATING REGION 3

20 c.

0 O

10 20 30 40 50 60 70 80 90 100 APSR Position (% Withdrawn)

DAVIS-BESSE, UNIT 1 3/4 1-40 Amendment No. Jg, gy, g7, 80

- W e & =

er ;a

=***-y

_ese,=*

A ps waamam =

--+.e-=e=

+e e*

===,=.===w e

~

Figure 3.1-5g APSR Position Limits, 200 t10 to 330 t10 EFPD, Three RC Pumps -- Davis-Besse 1, Cycle 5 100 5

8 c-a (9,77)

(42,77)

E 80 5

RESTRICTED 5

.i(9,69.5)

REGION (42,69.5) ew j

60 (0,60.5)

(50,60.5)

(100,53) o "c

8 40 PERMISSIBLE OPERATING REGION ua j

20 0

O 10 20 30 40 50 60 70 80 90 100 APSR Position (% Withdrawn) l l

l l

j DAVIS-BESSE, UilIT 1 3/4 1-41 Amendment f!o. f), EJ, 77, 80 i

,-e e-

-,cew v

=, +, - -

---m-4.

w-.#

-ee.,

g--

Figure 3.1-Sh Deleted DAVIS-BESSE, UNIT 1 3/4 1-42 Amendment No. AE, $7, 59, 80 l

Figure 3.1-51 Deleted DAVIS-BESSE, UNIT 1 3/4 1-43 Amendment tio. M, EJ, M,

80

3/4.2. POWER DISTRIBUTION LIMITS AXIAL POWER IMBALANCE LIMITING CONDITION FCR OPERATION 3.2.1 AXIAL POWER IMBALANCE shall be maintained within the limits shown on Figures 3.2-la, -lb, -ic, and -id and 3.2-2a, -2b, -2c and -2d.

l APPLICABILITY:

MODE 1 above 40". of RATED THERMAL POWER.*

ACTION With AXIAL POWER IMBALANCE exceeding the limits specified above, either:

a.

Restore the AXIAL POWER IMBALANCE to within i ts limits within 15 minutes, or b.

Within one hour reduce power until imbalance limits are met or to 407, of RATED THERMAL POWER or 1-ss.

SURVEILLANCE REOUIREMENTS The AXIAL POWER IMBALANCE shall be determined to be within limits 4.2.1.

at least once ever/ 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when above 407, of RATED THERMAL POWER except when the AXIAL POWER IMBALANCE alam is inoperable, then calculate the AXIAL POWER IMBALANCE at least once per hour.

i l

l

(

t

See Special Test exception 3.10.1.

DAVIS-BESSE, UNIT 1 3/4 2-1 Arendar.t ::o. 33, /2, /E, p,

Mi 80

.m..

_e-

,,...,.9%.-,,..w

,m,

.p.+c,g,

-3 y

M +a

Figure 3.2-la Axial Power Imbalance Limits, O to 25+10/-0 EFPD, Four RC Pumps -- Davis-Besse 1, Cycle 5

(-23,102)-

_'-100

(

(-25,92)

(

-90 5

(-30,80)r

!--80 i(30,80) a h--70 W

i:

-60 o#<

."O RESTRICTED PERMISSIBLE

[

REGION OPERATING o

REGION y

- 40 8

5

-30 S

5

-20 3

s

-10 t

I f

f f

-40

-30

-20

-10 0

10 20 30 40 Axial Power Imbalance (".)

l DAVIS-BESSE, UNIT 1 3[42-2 Amendment !!o. JJ, 33, /E, JJ,

80 i

h y __

m

Figura 3.2-lb Axial Power Imbaiance Limits, 25+10/-0 to 200 t10 EFPD, Four RC Pumps -- Davis-Besse 1, Cycle 5

(-23,102) -

(23,102) -

__ gg

(-30,92)

'(30,92)

E-- 90 1

Yo c.

- 80 b

$-- 70 E

S-- 60

E

- 50 RESTRICTED PERMISSIBLE a

REGION OPERATING 5-- 40 REGION E

$-- 30 bg-- 20 c.

- 10 t

f f

f 30

-20

-10 0

10 -

20 30 40

-40 Axial Power Imbalance (*.')

DAVIS-BESSE, UtlIT 1 3/4 2-2a Amendment t!o, JJ, 33, fa, AE,$7, 80 m-m

-e.

Figure 3.2-lc Axial Power Imbalance Limits, 200 210 to 330 !10 EFPD, Four RC Pumps -- Davis-Besse 1, Cycle 5

(-23,102) --

100 i(30,92)

(-30,92)"

E

-90

-80 a

f5

-70 iE S

-60 2

a:

-50 g

RESTRICTED PERMISSIBLE e

-40 REGION OPERATING 8

REGION 5S

-30 t

-20 g

c.

-10 t

I f

1

-40

-30

-20

-10 0

10 20 30 40 Axial Power Imbalance (%)

J T

l DAVIS-BESSE, UNIT 1 3/4 2-2b Amendment !:o. /,7, /E, 77, E7, 80

---,4

,y er...,...,,,,

e+,m- - -

eremw-u-,---eim e.e__.,_m,_eamy rar + + u

,______sas.eesma2. _ _ _ - -"a_ am m eh m---

o "oure 3.2-Id Axial Power Imbalance Limits, 330 !10 to 390 t10 EFPD, Four RC Pumps, APSRs Withdrawn --

Davis-Besse 1, Cycle 5

(-23,102)

- (23,102)

- 100

(-30,92)r.

g-- 90

'(30,92)

$oc-

- 80 a

f

$-- 70 i5 S-- 60 3

[-- 50 RESTRICTED PERMISSIBLE REGION OPERATING T-- 40 REGION 8

i L.

f-- 30 l

s.

j

- 20 c.

- 10 I

I I

t t

t

-40

-30

-20

-10 0

10 20 30 40 Axial Power Imbalance (".)

l DAVIS-BESSE, UNIT I 3/4 2-2c Amendment.'o. A3, 37, 39, 80

+1 N

I Figure 3.2-le Deleted DAVIS-BESSE, UllIT 1 3/4 2-2d knendment fio. #, $7, $7, 80

.=m--

---.a m.m.

,e..++-

.s

mw

Figure 3.2-2a Axial Power Imbalance Limits, O to 25+10/-0 EFPD, Three RC Pumps -- Davis-Besse 1, Cycle 5

- - 100

^m

- 80

(-17.25,77)-

'(17.25,77) a

(-18.75,69.5) 2 (18.75,69.5) 5

(-22.5,60.5) if -

(22.5,60.5)

- 60 O

E M

w

- 40 z=

a 5

~

w RESTRICTED se E

REGION Ge f

$5

- 20 EG 5

e5 3

5 i

i

.i i

i i l t

1

-40

-30

~-20

-10 0

10 20' 30 40 Axial Power Imbalance (".)

l l

l DAVIS-CESSE, UtlIT'l 3/4 2-3

.anendment !!o, 77, 73, gE, 37, 80 t

'w t

-+M%9MW 'm e svo-,

-v--

&OV VM'vf '4W

' = &

M t*%

w f'

Figure 3.2-2b A'xial Power Imbalance Limits, 25+10/-0 to 200 t10 EFPD, Three RC Pumps -- Davis-Besse 1, Cycle 5 100 Es 80 o

(-17.25,77 -

17.25,77) a

(-22.5,69.5)i (22.5,69.5)

!c!A 60 8e x

w 40 z

o S

a RESTRICTED $$

5

e. REGION S=

0 E

g 20 55 5

C E

O f

I f

f f.==-

t 1

40

-30 20 10 0

10 20 30 40 Axial Power ~ Imbalance (".)

DAVIS-BESSE, ViIT 1 3/4 2-3a fnendment !!o. 77, 77, JE, D, 37, 80 e

wN-C*

--*g*M--g--*

.e

,--e y

e e----+et 4

--+--ev'*

w d-ee.,

-e

-ee f my 'e - 4 e

>b+-=ed

'-eet 94db eh*es>aq

o Figure 3.2-2c Axial Power Imbalance Limits, 200 10 to 330 !10 EFPD, Three RC Pumps -- Davis-Besse 1, Cycle 5

- - 100 2s

(-li.25,77'_

- 80

,17.25,77)

I (22.5,59.5)

(-22.5,69.5)

=

="

- 60 S2 z2 o

we

- 40 RESTRICTED dE j

REGION gg g

2; E

- 20 3

c.

I t

t t

i le t

1 40

-30

-20

-10 0

10 20 30 40 Axial Power Imbalance (%)

JAVfS-BESSE, 'JflIT 1 3/4 2-3b Ancr.dment !!o. 47, JE, 37, 39, 00

.,..,m.

e..-

a.,

, o e-

Figure 3.2-2d Axial Power Imbalance Limits, 330 10 to 390 t10 EFPD, Three RC Pumps, APSRs Withdrawn --

Davis-Besse 1, Cycle 5

- - 100 2sos - 80

(-17.25,77),

(17.25,77)

(-22.5,69.5) (

h h(22.5,69.5)

W

- 60

=5

=o

$5

- - 40 5"

T RESTRICTED y y

REGION gg g

E5

~

- 20 8

b B

L 1

f f

a

-30

-20

-10 0

10 20 30 40 Axial Power Imbalance (".)

MVIS4 ESSE, Vi!IT 1 3/4 2-3c Amendment !!o, 6, U, M, 80

.--s' M--..-

---u

'an-*--------.-----.-. u--.M -..

n :---.-----

e o

Figure 3.2-2e Deleted DAVIS-BESSE, UNIT 1 3/4 2-3d Amendment No. #, M, D,

C0

PCWER DISTRIBUTION LIMITS LIMIT!NG CONDITION FOR OPERATION (Continued)

AC* ION:

(Continued) d.

With the QUADRANT PCWER TILT detemined to exceed the Maximum Limit of Table 3.2-2, reduce THERMAL POWER to < 15 of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SURVEILLANCE REQUIREMENTS 4.2.4 The OUADRANT PCWER TILT shall be detamined to be within the limits at least once every 7 days during oceration aoove 15% of RATED WERMAL PCWER excect wnen the CUACRANT PCWER TILT alam is inocerable, Onen the CUADRANT PCWER TILT saall ce calculated at least once per 12 hcurs.

l i

l DAVIS-BESSE, UNIT 1 3/4 2-11 l

.r-w,-

.w c,-

9-

--i,-,--r.,.p-w.

w rq-m-w.-e-g-

pgryg, m mm,,% e w.

w - pgy3-e.-

yg y=

he e- - @ :- 9-Dt y --,. -,

= # 4 d i aF- - -*4 e E 4

h-"---e8--

"-'k--*-

9 ew"-

Table 3.2-2 Quadrant Power Tilt Limits

~

l Steady state Transient Maximum limit limit limit Measurement independent 4.92 11.07 20.0 QUADRANT POWER TILT QUADRANT POWER TILT is.

measured by:

Symmetrical incore detector 3.37 8.52 20.0 system, 0-50 t10 EFPD Symmetrical incore detector 3.02 8.52 20.0 system, after 50 10 EFPD Power range channels 1.96 6.96 20.0 Minimum incore detector system 1.90 4.40 20.0 DAVIS-D SSE, Ui!IT 1 3/4 2-12 Amendment' t!o. 77,33,/7,27, 80

,w--

3/4.4. REACTOR COOLANT SYSTEM 3/4.4.1.

COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION LIMITING CONDITION FOR OPERATION 3.4.1.1 Both reactor coolant loops and both reactor coolant pumps in each loop shall be in operation.

APPLICABILITY:

MODES 1 and 2*.

ACTION:

With one reactor coolant pump not in operation, STARTUP and POWER OPERA-a.

TION may be initiated and may proceed provided THERMAL POWER is re-stricted to less than 79.7% of RATED THERMAL POWER and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months l

the setpoints for the following trips have been reduced to the values specified in Specification 2.2.1 for operation with three reactor cool-ant pumps operating:

1.

High Flux 2.

Flux-aFlux-Fl ow SURVEILLANCE REOUIREMENTS 4.4.1.1 The above required reactor coolant loops shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.2 The reactor protective instrumentation channels specified in the applicable ACTION statement above shall be verified to have had their trip setpoints changed to the values specified in Specification 2.2.1 for the ao-plicable number of reactor coolant pumps operating either:

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after switching to a different pump combination if the l

a.

switch is made while operating, or l

b.

Prior to reactor criticality if the switch is made while shutdown.

l l

l 1

See Special Test Exception 3.10.3.

Amendment !!o J$. 33,AZ, #3, DAVIS-8 ESSE, UNIT 1 3/44-1 80 l

l l

t

e 3/4.4 REACTOR COOLANT SYSTEM.

SHUTDOWN AND HOI STANDBY LIMITING CONDITION FOR OPERATION 3.4.1.2 a.

At least two of the coolant loops listed below shall be l

OPERA 3LE:

1.

Reactor Coolant loop 1 and its associated steam' generator, 2.

Reactor Coolant Loop 2 and its associated steam generator, 3.

Decay Heat Removal Imop 1,*

4.

Decay Heat Removal Loop 2.*

b.

At least one of the above coolant loops shall be in operation.**

c.

Not more than one decay. heat removal pump may be operated with the sole suction path through DH-11 and DH-12 unless the control power has been removed from the DE-11 and DH-12 valve operator, or manual valves DE-21 and DH-23 are opened.

d.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

APPLICABILITY: MODES 3, 4 an.! 5 ACTION:

s.

With less than the above required coolant loops OPERABLE, immediately initiate corrective action to return the required coolant loops to OPERA 3LE status as soon as possible, or be in COLD SHUTDOWN within 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months , b.

With none of the above required coolant loops in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.

j

Iba normal or emergency power source may be inoperable in )CDE 5.

- The decay heat removal pumps may be de-energized for up to I hour provided (1) no operations are permitted that would cause dilution of i

the reactor _ coolant system baron concentration, and (2) core outlet temperature is maintained at least 10 F below saturation temperature.

DAVIS-3 ESSE UNIT 1 3/4 4 Amendment No. };#,25, 38 i

m.-

,_m._m.._. _ - _. _. -

..._,#4

... a.

.4 fA.___,

...h

?,.-.~.-..,,--s.%.

" Y't '( * '

ML20101L377

Text

Attachment:

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