Text

Amends 59 & 85 to Licenses DPR-71 & DPR-62,respectively, Modifying Tech Specs to Clarify Certain Requirements,Making Changes to Provide Consistency W/Actual Plant Design & Editorially Correcting Certain Requirements
	ML20082P248
Person / Time
Site:	Brunswick
Issue date:	12/02/1983
From:	Vassallo D; Office of Nuclear Reactor Regulation
To:	; Carolina Power & Light Co
Shared Package
ML20082P252	List: ML20082P248; ML20082P258;
References
	DPR-62-A-085, DPR-71-A-059 NUDOCS 8312080156
	Download: ML20082P248 (21)
	v • d • e

'

a ttoo

'o UNITED STATES e[gc NUCLEAR REGULATORY COMMISSION c

WASHINGTON, D. C. 20555

'i %.3"Qh[; j

-c-s: p CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. DPR-71 1.

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

A.

The application for amendment by Carolina Power & Light Company (the licensee) Jated December 6, 1982, 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 Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:

8312080156 832202

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qDR ADOCK 05000324 g

PDR

2.

Technical Specifications The Technical Specifications contained in Aprendices A and B, as revised through Amendment No. 59, are hereby incorporated in the license.

The licensee shall operate the facility in accordance

.with the Technical Specifications.

3.

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

FORTHENplEARREULATORYCOMMISSION

/

fw Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: December 2,1983 G

e b

ATTACHMENT TO LICENSE AMENDPENT N0. 59 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Revise the Appendix A Technical Specifications as follows:

Remove Insert 3/4 1-19 3/4 1-19 3/4 6-28 3/4 6-28 3/4 1-3 3/4 1-3 3/4.3-40 3/4 3-40 3/4 3-41 3/4 3-41 3/4 3-42 3/4 3-42 3/4 3-43 3/4 3-43 3/4 3-43a 3/4 3-43a l

l 1

~

A REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS

~

4.1.5 The standby liquid control system shall'be demonstrated OPERABLE:

a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying that:

1.

The volume and temperature of the soditan pentaborate solution are within the limits of Figures 3.1.5-1 and 3.1.5-2, and 2.

The heat tracing circuit is OPERABLE.

b.

At least once per.31 days by:

'1.

Starting each pump and recirculating demineralized water to the test tank, 2.

Verifying the continuity of the explosive charge, and 3.

Determining the concentration of boron in solution by chemical analysis. This test shall also be performed anytime water or boron is added to the solution or when the solution temperature drops below the limit established in Figure 3.1.5-2.

At least once per-18 months during shutdown by:

c.

1.

_ Initiating one of the standby liquid control system loops, l

including an explosive valve, and verifying that a flow path from the pumps to the reactor pressure vessel is available by pumping demineralized water into the reactor vessel. The replacemene. charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has been certified by having one of that batch successfully fired.

Both injection test loops shall be tested in 36 months.

2.

Demonstrating that the minimum flow requirement of 41.2 gpm at a

{'

pressure of greater than or equal to 1190 psig is met.

l-3.

Demonstrating that the pump relief valve setpoint is 1400 t 50 psig.

i i

' BRUNSWICK - UNIT 1 3/4 1-19 Amendment No. 59

CONTAINMENT SYSTEMS CONTAIMiENT ATMOSPHERE DILUTION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.6.2 The containment atmosphere dilution (CAD) system shall be OPERABLE with:

An OPERABLE flow path capable of supplying nitrogen to the drywell, a.

and b.

A minimum supply of 4350 gallons of liquid nitrogen.

APPLICABILITY:

CONDITION 1*.

ACTION:

With the CAD system inoperable, restore the CAD system to.0PERABLE status within 31 days or be in at least STARTUP within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . The 4

provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.6.6.2 The CAD system shall be demonstrated to be OPERABLE:

a.

At least once per 31 days by verifying that:

-1.

The system contains a minimum of 4350 gallons of liquid nitrogen, and 2.

. Each valve (manual, power-operated, or automatic) in the ficw 5

path not locked, sealed, or otherwise secured in position, is in its correct position.

b.

At least once per 18 months by:

1.

Cycling each power operated (excluding automatic) valve in the flow path through at least one complete cycle of full travel, l

and i

2.

Verifying that each automatic valve in the flow path actuates to l

!its correct position on a Group 2 and 6 isolation test signal.

4 i

When oxygen concentration is required to be < 4% per Specification 3.6.6.3.

BRUNSWICK - UNIT 1 3/4 6-2.8 Amendment No. 59

REACTIVITY CONTROL SYSTEMS 3/4.1.3 CONTROL RODS CONTROL' ROD OPERABILITY 4

LIMITING CONDITION FOR OPERATION 3.1.3.1 All control rods shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

s With one control rod inoperable due to being immovable, as a result of

p a.

j excessive friction or mechanical interference, or known to be untrippable:

1.

Within one hour:

a)

Verify that the inoperable control rod, if withdrawn, is separated from all other inoperable control rods by at least two control cells in all directions.

b)

Disarm the associated directional control valves hydraulically by closing the insert and withdraw isolation valves.

2.

Otherwise, 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 .

3.

Restore the inoperable control rod to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least H0r SHUTDOWN within the next 12 ho.urs,

b..

With one or more control rods inoperable for causes other than addressed in ACIION a, above:

i 1.

If the inoperable control rod (s) is withdrawn, within one hour:

a)

Verify that the inoperable withdrawn control rod (s) is separated from all other inoperable control rods by at least two control cells in all directions, and b)

Demonstrate the insertion capability of the inoperable l

withdrawn control rod (s) by inserting the control rod (s) at

{

least one notch by drive water pressure within the normal operating range *, or 1

c)

Fully insert the inoperable withdrawn control rod (s) and disarm the associated directional control valves either:

'1)

Electrically, or 2)

Hydraulically by closing the drive water and exhaust water isolation valves.

i '

The inoperable control rod may then be withdrawn to a position no further

~

withdrawn than its position when found to be inoperable.

i BRUNSWICK - UNIT 1 3/4 l-3 Amendment No. 59

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- - - - - - - - - - - -, _,, - - - =, -, + - -, - - -,

TABLE 3.3.4-1 m

CONEROL R0D WITilDRAWAL BIDCK INSTRUMENTATION s

.Q MINIMUM MJMBER OF APPLICABLE OPERABIn CHANNELS OPERATIONAL TRIP FUNCTION AND INSTRUMENT NUMBER PER TRIP SYSTEM (a)

CONDITIONS U

1.

APRM ( C51-APRM-CH. A, B, C, D, E,F) i a.

Upscale (Flow Biased) 2 1

b.

Inoperative 2

1, 2, 5 c.

Downscale 2

1 d.

Upscale (Fixed) 2 2, 5 4

2.

ROD BLOCK MONITOR (C51-RBM-CH. A,B) a.

Upscale 1

1*

g b.

Inoperative

.1 1*

I e

c.

Downscale 1

1*

Yg 3.

SOURCE RANGE MONITORS (C51-SRM-K600A,B.C D) a.

Detecto ot full in (b) 1 2, 5 b.

Upscale 1

2, 5 Inoperatig c.

i 2, 5 d.

Downscale 1

2, 5 4.

INTERMEDIATE RANCE MONITORS (d) ( C51-IRM-K601A, B, C, D, E, F,G,II) a.

Detector not full in (*)

2 2, 5 b.

Upscale 2

2, 5 g

Inoperabl{8) 2 2, 5 c.

g d.

Downscale 2

2, 5 l

g 5.

SCRAM DISQIARGE V0wME (C11-LSil-N013E) 1 n

a.

Water level - liigh 1#

1, 2, 5**

i i

. ~.

TABLE 3.3.4-1 ( Continued)

CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION NOTE (a) The minimum number of OPERABLE CHANNELS may be reduced by one for up to 2 l

hours in one of the trip systems for maintenance and/or testing except for Rod Block Monitor function.

(b) This function is bypassed if detector is reading >100 cps or the IRM l

channels are on range 3 or higher.

(c)

This function is bypassed when the associated IRM channels are on range 8 l

or higher.

(d)

A total of 6 IRM instruments must be OPERABLE.

(e) This function is bypassed when the IRM channels are on range 1.

When THERMAL POWER exceeds the preset power level of the RWM and RSCS.

With any control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

This signal is contained in the Qannel A logic only.

i l

BRUNSWICK UNIT 1

'3/4 3-41 Amendment No.

59

TABLE 3.3.4-2 CONTROL ROD WITHDRAWAL BIDCK INSTRUMENTATION SETPOINES TRIP FUNCTION AND INSTRUMENT NUMBER TRIF S'ETPOINr ALIDWABLE VAIDE 1.

APRM ( C51-APRM-QI. A, B, C, D, E, F)

Q a.

Upscale (Flow Biased)

< (0.66W + 42%)

T*

< (0.66W + 42%)

T*

MTPF MrPF s.

b.

Inoperative NA NA

- g g

c.

Downscale

> 3/125 of full scale

> 3/125 of full scale H

d.

Upscale (Fixed)

< 12% of RATED THERMAL POWER

< 12% of RATED THERMAL POWER H

2.

ROD BLOCK MONITOR ( CS I-RBM-Cil. A,B) a.

Upscale 1 (0.66W + 41%)

T*

< (0.66W + 41%)

T*

MrPF MrPF b.

Inoperative NA NA c.

Downscale

> 3/125 of full scale

> 3/125 of full scale 3.

SOURCE RANGE MONITORS ( C51-SRM-K600A, B, C, D) a.

Detector not full in NA NA 5

5 t'

b.

Upscale

<1x 10 cps

< 1 x 10 c p, c.

Inoperative NA NA d.

Downscale

> 3 cps

__3 cps 4.

INTERMEDIATE RANGE MONITORS ( C51-IRM-K601 A, B, C, D, E, F,G, H) a.

Detector not full in NA NA b.

Upscale

< 108/125 of full scale

< 108/125 ef full scale c.

Inoperative NA NA d.

Downscale

> 3/125 of full scale

> 3/125 of full scale 5.

SCRAM DISCllARGE VOIBME (Cll-LSil-N013E) a.

Water Invel liigh

< 73 gallons 1 73 gallons N

T=2.43 for 8x8 fuel T=2.48 for 8x8R fuel B-T=2.48 for P8x8R fuel I

$n 1

~

TABLE 4.3.4-1

o CONTROL R0D WITilDRAWAL BIDCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS si:

5 g

QlANNEL OPERATIONAL l

GIANNEL FUNCTIONAL OIANNEL CONDITIONS IN WilIQi TRIP FUNCTION AND INSTRUMENT NUMBER GlECK TEST CALIBRATION SURVEILLAWCE REQUIRED

+

4 1.

APRM ( C51-APRM-Ql. A, B, C, D, E,F) w a.

Upscale.(Flow Biased)

NA S/U(c)

,M R(b)(a) l S/U(I ),M

")

)

b.

Inoperative NA Q

NA 1, 2, 5 c.

Downscale NA S/U(")',

NA(*

1 d.

Upscale (Fixed)

NA S/U

,Q R

2, 5 2.

ROD BLOCK MONITOR ( CS I-RBM-QI. A, B)

S/U(c)

,M R(a) g, a.

Upscale NA S/0(,c) c b.

Inoperative NA c.

Downscale NA S/U( )

NA(*)

,Q 1*

,M R

1*

3.

SOURCE RANGE MONITORS ( C51-SRM-K600A, B, C, D) a.

Detector not full in NA S/U(c)

,W NA 2, 5 S/U(c) b.

Upscale NA S/U(c)

,W NA 2, 5 c.

Inoperative NA

,W NA 2, 5 S/U(c),W NA 2, 5 d.

Downscale NA 4.

INTERMEDIATE RANGE MONITORS ( C51-IRM-K601 A, B, C, D, E, F,G,H) a.

Detector not full in NA S/U(c),g(d)

NA 2

NA W

NA 5

b.

Upscale NA S/U(c),g(d)

NA 2

h NA W

NA 5

S/U(C),W(d) c.

Inoperative NA NA 2

NA W

NA 5

S/U(

,W NA 2

d.

Downscale NA m

)

NA W

NA 5

l

~

g TABLE 4.3.4-1 ( Cont'd)

E CONTROL ROD WITilDRAWAL BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS un d

S CHANNEL OPERATIONAL i

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH g

TRIP FUNCTION AND INSTRUMENT NUMBER CilECK TEST CALIBRATION (*

SURVEILLANCE REQUIRED 01 5.

SCRAM DISCllARGE V0WME ( Cll-LSil-N013E) g a.

Water Level - liigh NA Q

R 1, 2, 5**

(a) CilANNEL CALIBRATIONS are electronic.

(b) This calibration shall consist of the adjustment of the APRM flow biased setpoint to conform to a calibrated flow signal.

(c) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to startup, if not performed within the previous 7 days.

(d) When changing from CONDITION 1 to CONDITION 2, perform the required surveillance Ed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months af ter entering CONDITION 2.

When TilERMAL POWER is greater than the preset power level of the RWM and RSCS.

Y

- With any control rod withdrawn.

Not applicable to control rods removed per hi Specification 3.9.10.1 or 3.9.10.2.

1 y

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d Cg

c

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UNITED STATES

[ f ;.% lj NUCLEAE PEGULATORY COMMISSION of E _1 R

MSHING T ON. O. C. 20555

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j CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENTTOFACILITYOPERATIN'GdICENSE Amendment No. 85 License No. DPR-62 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Carolina Power & Light Company (the licensee) dated December 6, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as emended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the ' activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is hereby amended to read as follows:

n_

. 2.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 85, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date-of Issuance:

December 2,1933

ATTACHMENT TO LICENSE AMENDMENT N0. 85 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Revise the' Appendix A Technical Specifications as follows:

Remove Insert 3/4 3-62 3/4 3-62 3/4 1-19 3/4 1-19 3/4 6-28 3/4 6-28 3/4 3-40 3/4 3-40 3/4 3-41 3/4 3-41 3/4 3-42 3/4 3-42 3/4 3-43a 3/4 3-43a 4

e f

s.

INSTRUMENTATION

.3/4.3.6 RECIROJIATION PUMP TRIP ACTUATION INSTRUMENTATION ATW3 RECIROJIATION PUMP TRIP SYSTEM INSTRUMENIATION LIMITING CONDITION FOR OPERATION 3.3.6.1 The Anticipated Transient Without Scram recirculation pump trip l

(ATWS-RPT) system instrumentation trip systems shown in Table 3.3.6.1-1 shall be OPERABLE with their trip setpoints set consistent with the v'alues shown in the Trip Setpoint column of Table 3.3.6.1-2.

APPLICABILITY:

CONDITION 1.

ACTION:

With an ATWS recirculation ptanp trip system instrumentation trip a.

satpoint less conservative than the value-shown in the Allowable Values column of Table 3.3.6.1-2, declare the trip system inoperable until the trip system is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With the requirements for the Minimum Number of OPERABLE Trip Systems per Operating Pump not satisfied for one Trip Function, restore the inoperable trip system to OPERABLE status within 14 days or be in at least STARTUP within the.next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE REQUIREMENIS 4.3.6.1.1 Each ATWS recirculation pump trip system instrumentation trip system shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CFANNEL CALIBRATIOS operations at the frequencies shown in Table 4.3.6.1.1-1.

4.3.6.1.2 IDGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.

BRUNSWICK - UNIT 2 3/4 3-62 Amendment No. 85

c.

REACTIVITY CONTROL SYSTEMS

' SURVEILLANCE REQUIREMENTS 4.1.5 The standby liquid control system shall be demonstrated OPERABLE:

' At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying that:

a.

1.-

The volume and temperature of the sodium pentaborate solution are within the limits of Figures 3.1.5-1 and 3.1.5-2, and 2.

The heating tracing circuit is OPERABIE.

b.

' At least once per 31 days by:

1.

- Starting each ' pump and recirculating demineralized water to the test tank, 2.

Verifying the continuity of the explosive charge, and 3.

Determining the concentration of boron in solution by chemical analysis. This test shall also be ' performed anytime water or boron is added to the solution or when the solution temperature drops below the limit established in Figure 3.1.5-2.

At least once per 18 months during shutdown by:

c.

-1.

Initiating one of the standby liquid control system loops, including an explosive valve, and verifying that a flow path from the pumps to the reactor pressure vessel is available by pumping demineralized water into the reacor vessel. The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has been certified by having one of that batch successfully fired.

Both injection test loops shall be tested in 36 months.

2.

Demonstrating that the minimum flow requirement of 41.2 gpm at a pressure of greater than or equal to 1190 psig is met.

l 3.

Demonstrating that the pump relief valve setpoint is 1400 t 50 psig.

4 l

e-BRUNSWICK - UNIT-2 3/4 1-19 Amendment No.

85

CONTAINMENT SYSTEMS CONTAINMENT ATMOSPHERE DIIIITION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.6.2 The containment atmosphere dilution (CAD) system shall be OPERABLE with:

An OPERABLE flow path capable of supplying nitrogen to the drywell, a.-

and b.

A minimu:a supply of 4350 gallons of liquid nitrogen.

APPLICABILITY:

CONDITION 1*.

ACTION:

With the CAD system inoperable, restore the CAD system to OPERABLE status within 31 days or be in at least STARTUP within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.6.6.2 The CAD system shall be denonstrated to be OPERABLE:

a.

At least once per 31 days by verifying that:

1.

The system contains a minimum of 4350 gallons of liquid nitrogen, and 2.

Each valve (manual, power-operated, or automatic) in the flow path not locked, sealed, or otherwise secured in position, is in its correct position.

b.

At least once per 18 months by:

1.

Cycling each power-operated (excluding automatic) valve in the flow path through at least one complete cycle of full travel, l

and 2.

Verifying that each automatic valve in the flow path actuates to its correct position on a Group 2 and 6 isolation test signal.

When oxygen concentration is required to be < 4% per Specification 3.6.6.3.

BRUNSWICK - UNIT 2 3/4 6-28 Amendment No. 85

.~

N TABLE 3.3.4-1

.E CONTROL ROD WITHDRAWAL BIDCK INSTRUMENTATION N

MINIMUM NUMBER OF-APPLICABLE OPERABIE QlANNE OPERATIONAL h

TRIP FUNCTION AND INSTRUMENT NUMBER '

PER TRIP SYSTEM CONDITIONS H

N 1.

APRM ( CSI-APRM-Qi. A, B, C, D, E ' F) a..

Upscale (Flow Biased) 2 1

.b.

Inoperative 2-1,2,5 c.

Downscale..,

2 1

d.'

Upscale (Fixdd) 2 2, 5 2.

ROD BLOCK MONITOR (C51-PLci-CH. A,B) a.

Upscale 1

1*

R b.

Inoperative 1

1*

c.

Downscale 1

1*

Y

.g 3.

SOURCE RANGE MONITORS. (C51-SRM-K600A,B,C,D)

Detectogot f ull in a.

1 2, 5

.b.

Upscale 1

2, 5 c) c.

Inoperati 1

2, 5 d.

Downscale 1

2, 5 4.

INTERMEDIATE RANTE MONITORS (d)

( C51-IRM-K601A, B, C D. E. F,G,il)

Detector not full in(*)

a.

2 2, 5 b.

Upscale 2

2, 5 Inoperably c.

2-

,, 5 k

Downscale *}

d.

2-2, 5 s.

g 5.

SCRAM DISQIARGE V0WME ( Cl2-LSil-N013E)

?,

a.

Water Invel - liigh lf 1, 2, 5**-

n.

TABLE 3.3.4-1 (Continued)

' CONTROL ROD WITHDRAWAL BIDCK INSTRUMENTATION N0frE i

(a) The minimum nsaber of OPERABLE CHANNELS may be reduced by one for up to 2 l

-hours in one of the trip systems for maintenance and/or testing except for Rod Block Monitor function.

(b)

This function is. bypassed if detector is reading >100 cps or the IRM.

l channels are on range 3 or higher.

'ke) This function is ' bypassed when the associated IRM channels are on range 8 l

or higher.

(d)

A total of 6 IRM instruments must be OPERABLE.

(e) This function is bypassed when the IRM channels are on range 1.

When THERMAL POWER exceeds the preset power level of the RWM and RSCS.

- . With any control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

This signal is contained in the Channel A logic only.

BRUNSWICK - UNIT 2 3/4 3-41 Amendment No.

85

TABLE 3.3.4-2 CONTROL ROD WITHDRAVAL BIDCK INSTRUMENTATION SETPOINTS E

TRIP FUNCTION AND INST'UMENT NUMBER TRIP SETPOINE ALIDWABIE VAIDE b

1.

APRM (C51-APRM-01. A,B,C, D,E F) b a.

Upscale (Flow Biased)

< (0.66W + 42%)

T*

1 (0.66W.+ 42%)

T*

8 MIPF MIPF g

b.

Inoperative NA NA y

c.

Downscale

> 3/125 of full sca'Le

> 3/125 of full scale d.

Upscale (Fixed)

< 12% of RATED THERMAL POWER

< 12% of RATED THERMAL POWER g

2.-

ROD BLOCK MONITOR ( CS I-RBM-CH. A, B) a.

Upscale f (0.66W + 39%)

T*

< (0.66W + 39%)

T*-

b.

Inoperative NA MIPF NA MIPF c.

Downscale

> 3/125 of full scale

> 3/125 of full scale 3.

SOURCE RANGE MONITORS ( C51-SRM-K600A,B, C, D) a.

Detector not full in NA NA' 5

5 b.

Upscale

< 1 x 10 cps i 1 x 10 cps Q

c.

. Inoperative NA NA d.

Downscale

> 3 cps

> 3 cps Y

4.

INTERMEDIATE RANGE MONITORS ( C51-IRM-K6 01 A, B, C, D, E, F,G, H) a.

Detector not full in NA NA b.

Upscale

< 108/125 of full scale

< 108/125 of full scale c.

Inoperative NA NA d.

Downscale

> 3/125 of full scale

> 3/125 of full scale 5.

SCRAM DISQlARGE VOIBME (Cl2-LSH-N013E) a.

Water Invel liigh

< 73 gallons 1 73 gallons

T=2.60 for 7 x 7 fuel.

k T=2.43 for 8 x 8 fuel.

g, T=2.39 for 8 x 8R fuel.

g T=2.39 for P8 x 8R fuel.

E

.if

(.Il I

c.

.,. j TABLE 4.3.4-1 (Cont'd)

E CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS un N

CHANNEL OPERATIONAL 8

OlANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHIQi TRIP FUNCTION 'AND INSTRUMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE RE(glIRED W

g n

5.

SCRAM DISCHARGE V0WME ( C12-LSH-N013E)

I a.

Water Invel - High NA Q

R 1, 2, 5**-

(a)

QIANNEL CALIBRATIONS are electronic.

(b) This calibration shall consist of the. adjustment of the APRM flow biased setpoint to conform to a calibrated flow signal..

(c) Within 24 houre prior to startup, if not perf> taed within. the previous 7 days.

(d) When changing from CONDITION 1 to CONDITION 2, perform the required surveillance M

within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months af ter entering CONDITION 2.

L' hen THERMAL POWER is grecter than the preset power ' level of the RIM and RSCS..

Y With any control rod withdrawn.

Not applicable to control rods removed per

-h Specification 3.9.10.1 or 3.9.10.2.

y a

an

.

ML20082P248

Text

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