Text

Revised Tech Specs 3/4.2 Re Power Distribution Limits. Handwritten Draft Safety Evaluation Encl
	ML20126G015
Person / Time
Site:	Brunswick
Issue date:	03/06/1981
From:	; Office of Nuclear Reactor Regulation
To:	;
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ML20126G013	List: ML20126G011; ML20126G015;
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3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION r

3.2.1' ALL AVERAGE PLANAR LINEAR HEAT GENERATION RATES (APLHGR's)' for each type of fuel as a function.of AVERAGE PLANAR EXPOSURE shall not exceed the limits shown in Figures 3.2.1 -1, 3.2.1 -2, 3.2.1-3, 3.2.1 -4, 3.2.1 -5 or l

3,2.1-6.*

APPLICABILITY:

LONDITION i, when THERMAL POWER > 25% of PATED THERMAL POWER.

ACTION:

With an APLHGR exceeding the limits of Figure 3.2.1-1, 3.2.1-2, 3.2.1-3, r

3.2.1-4, 3,2.1-5 or 3.2.1-6, initiate corrective action within 15 minutes and continue corrective action so that APLHGR is within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER l

within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

S*JRVEILLANCE REQUIREMENTS 4.2.1 All APLHGR's shall be verified to be equal to or less than the appli-cable lirdt determined from Figure 3.2.1 -1, 3. 2.1-2,. 3. 2.1 -3, 3. 2.1-4, 3.2.1-5 or 3.2.1-6:

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and I

Initially and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the reactor is c.

operating with a LIMITING CONTROL ROD PATTERN for APLHGR.

"In single reactor recirculation loop operation, the APLHGR limit shall be reduced to.65 of the values specified in the above tables.

This portion of the Specification expires on March 15, 1981.

e ERL*NSWICX-UNIT 1 3/4 2-1 Amendment No.

SS

3/4.2.2 APRM SETPOINTS LIMITING CONDITION FOR OPERATION 3.2.2 The flow biased APRM scram trip setpoint (5) and rod block trip set point (Sgg) shall be established according to the following relationship:

S 2 (.0.66W + 54%) T S < (0.66W + 50.7%) (Single Loop)*

l S

1 (0.66W + 42%) T S 1 (0.66U + 38.M) W ngle Loop)*

RB RB where:

5 and sob are in percent of RATED THERMAL POWER.

W = Loop recirculation flow in percentor of rated flow, T = Lowest value of the ratio of design TPF divided by the HTPF -

obtained for any class of fuel in the core (T 1 1.0),and Design TPF for: 8 x 8 fuel = 2.45.

8 x 8R fuel = 2.48.

PS x 8R fuel = 2.48.

APPLICABILITY:

CONDITION 1, when THERMAL POWER > 25% of RATED THERMAL POWER.

ACTION:

With 5 or SRB exceeding the allowable value, initiate corrective action within 15 minutes and continue corrective action so that S and SRB are within the required limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or reduce THERMAL POWER to less than 25% of RATED THERf%L POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REQUIREMENTS 4.2.2 The MTPF for each class of fuel shall be determined, the value of T calculated, and the flow biased APRM trip setpoint adjusted, as required:

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and c.

Initially and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the reactor is operating with a LIMITING CONTROL R00 PATTERN for MTPF.

This portion of the specification expires on March 15, 1981.

BRUNSWICK-UNIT 1 3/4 2-8 Amendment No.

TRIP FUllCTION AND INSTRUMENT NUMBER TRIP SETPOINT ALLOWALLE VALUE i

!S

[-j 1.

APRM (CSI-APRM-Cll. A,B,C,D,E,F) x

- (0.66 W + 42%)NT W '

T* **

~(0.66W + 42%)

T*

i M

a.

Upscale (Flow Biased) j 7

MIPF j

E,-

b.

Inoperative NA NA t

-i c.

Downscale

> 3/125 of full scale

> 3/125 of full scale d.

Upscale (Fixed)

< 12% of RATED TilERMAL POWER

< 12% of RATED TilERMAL POWER i

l 2.

ROD BLOCK MONITOR (CSI-RBM-CH.A,B) 4 i

a.

Upslcale

~~< (0.66W + 41%)

T* ***

<(0.66W + 41%)

T* ***

MTPF MTPF b.

Inoperative NA NA c.

Downscale

> 3/125 of full scale

> 3/125 of full scale j

3.

SOURCE RAllGE MONITORS (C51-SRM-K600A,B,C,D) g a

a.

Detector not full in NA NA 5

5 y

n b.

Upscale

< 1 x 10 cps

< 1 x 10 cps l

c.

Inoperative tiA RA d.

Downscale

> 3 cps

> 3 cps I

4.

INTERMEDIATE RANGE MONITORS (C51-IRM-K601A,B,C,D,E,F,G,ll) a.

Detector not full in NA NA l

b.

Upscale s 108/125 of full scale 5 108/125 of full scale c.

Inopei itive NA NA i

d.

Downscale

> 3/125 of full scale

> 3/125 of full scale IT'=2.43 for 8x8 fuel w

S T=2.48 for 8x8R fuel y

T=2.48 for P8x8R fuel

- When in single loop, trip setpoint and allowable value shall be reduced to < (.66W + 38.7%) W T

within 24 l

[

hours in single recirculation loop operation. This Specification expires oii March :15,1981.

P

- - When in single Inop, trip setpoint and allowable value shall be reduced to < (.66W + 35.7%) T

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in single recirculation loop operation.

MTPF This Specification expires on March 15, 1981.

3'/ 4. 4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM RECIRCULATION LOOPS LIMITING CONDITION FOR OPERATION 3.4.1.1 Two reactor coolant recirculation loops shall be in operation with the cross-tie valve closed, the pump discharge valves OPERABLE and the pump discharge bypass valves OPERASLE or closed.

APPLICABILITY:

CONDITIONS 1* and 2*.

ACTION:

With one or both recirculation loops not in operation, operation may continue; restore both loops to operation within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least H0T SHllTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .**

l SURVEILLANCE REOUIREMENTS 4.4.1.1 Each pump discharge valve and bypass valve shall be demonstrated OPERABLE by cycling each valve through at least one complete cycle of full travel during each COLD SHUTCOWN which exceeds 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , if not performed in the previous 31 days.

4.4.1.2 Each pump discharge bypass valve, if not OPERABLE, shall be verified to be closed at least once per 31 days.

See Special Test Exception 3.10.4.

- Until March 15, 1981, with one recirculation pump not in operation, reduce power to less than 50% and reduce the setpoints as specified in Table 2.2.1-1, Table 3.3.4-2, Section 3.2.1, and Section 3.2.2, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . With both recirculation loops, not in operation, operation may continue; restore at least one loop to operation within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

BRUNSWICK-UNIT 1 3/4 4-1 Amendment No.

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