ML20058N173

Updated Tech Specs Permitting Removal of Rod Sequence Control Sys & Reducing Rod Worth Minimizer Cutoff Setpoints to 10%-rated Thermal Power

ML20058N173
Person / Time
Site:	Brunswick
Issue date:	08/09/1990
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20058N170	List: ML20058N167 ML20058N173
References
NUDOCS 9008130275
Download: ML20058N173 (38)

Text

i i INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PACE 3/4.0 A P P LI C A B I L I TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 0-1

• r 3/4.1 REACTIVITY COVrROL SYSTEMS 3/4.1.1 SHUTDOWN MARCIN.......................................... 3/4 1-1 3/4.1.2 R EA CT I V I T Y AN 0H AL I E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-2 3/4.1.3 CONTROL RODS Control Rod Operability.................................. 3/4 1-3 ,

Cont rol Rod Max imum Sc ram Ins er t i on Times . . . . . . . . . . . . . . . . 3/4 1-5 Control Rod Average Scram insertion Times................ 3/4 1-6 Four Cont rol- Rod Croup Sc ram In se rt ion Time s. . . . . . . . . . . . . 3/4 1-7 Con t r ol Rod S c r am Ac c umul a t or s . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-8 Con t rol Rod Dri ve Cou pl ing. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-9 Control Rod Position Indication.......................... 3/4 1-11 Control Rod Drive Housing Support........................ 3/4 1-13 3/4.1.4 CONTROL ROD PROGRAM CONTROLS Rod Worth Minimizer...................................... 3/4 1-14 Rod Sequence Control System (DELETED).................... 3/4 1-15 l

Rod Block Monitor................c....................... 3/4 1-17 i/4.1.$ STANDBY LIQUI D CONTROL SY ST EM. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-18 .

J/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERACE PLANAR LI NEAR HEAT CENERATION RATE. . . . . . . . . . . . . . . 3/4 2-1 3/4.2.2 APRM SETP0!NTS........................................... 3/4 2-2 3/4.2.2 M I N I M UM C R I TI CAL POWE R RATI 0. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 2-3 t

BRUNSWICK - UNIT 1 IV Amendment No.

l 9008130275 900809 PDR P

ADOCK 05000324 '

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e INDEX ,

LIMITINC CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS I

SECTION PACE [

3/4.9 REFUELING OPERATIONS (Continued) 3/4.9.3 CON TROL ROD POS I T 10N. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . :3/4 9-5_

3/4.9.4 DECAY TIME............................................ 3/4 9-6 3/4.9.5 ~ COMMUNICATIONS.......................... ............. 3/4 9-7 N 3/4.9.6 CRANE AND HOI ST OPERABI LI TY . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-8

• 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORACE P00L. . . . . . . . . . . . . .... 3/4 9-9' 'I 3/4.9.8 W ATER L EV EL-R EA CTOR V ES S E L. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-10' f 3/4.9.9 W ATER LEVEL-S PENT FUEL STOR ACE IN>3L. . . . . . . . . . . . . . . . . . . 3/4 9  !

l 3/4.9.10 CONTROL ROD REMOVAL {,

Single Control Rod Removal............................ 3/4 9-12  ;

Multiple Control Rod Removal.......................... 3/4 9-14 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRI MARY CONTAI NMENT I NTECRI TY . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-1

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3/4.10.2 ROD S EQUENCE CONTROL SYSTEM ( DELETED) . . . . . . . . . . . . . . . . . 3/4 10-2 l ,

3/4.10.3 SilVTDOWN HARC 1 N DEMONSTRATI ONS. . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-3 ')

3/4.10.4 R EC I R CU LATI ON L00 PS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10 3/4.10.5

'f P LA NT S ER VI C E W AT ER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4'10-5 .

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BRUNSWICK - UNIT-1 IX Amendment No. , .I; e

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. e INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS (Cont inued) 3/4.7.3 F LOOD P RO TE CT 10 N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-1 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM.................. B 3/4 7-1 3/4.7.5 SNUBBERS............................................... B 3/4 7-2 3/4.7.6 SEALED dOURCE CONTAMINATION............................ B 3/4 7-3 3/4.7.7 FIRE SUPPRESSION SYSTEMS............................... B 3/4 7-3 3/4.7.8 FIRE BARRIER PENETRATIONS.............................. B 3/4 7-3 3/4.8 ELECTRICAL POWER SYSTEMS................................... B 3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH.................................... B 3/4 9-1 3/4.9.2 INSTRUMENTATION........................................ B 3/4 9-1 3/4.9.3 CONTROL ROD POSIT 10N.................................. B 3/4 9-1 3/4.9.4 DECAY TIME............................................ B 3/4 9-1 3/4.9.5 COMMUNICATIONS........................................ B 3/4 9-1 3/4.9.6 C RAN E AND 110l S T O PE RA B I LI TY . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORACE P00L. . . . . . . . . . . . . . . . . . B 3/4 9-2  ;

3/4.9.8 WATER LEVEL-REACTOR VESSEL, and 3/4.9.9 WATER LEVEL-REACTOR FUEL STORAC E P00L. . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.10 CON TRO L R OD R EM0V AL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS.

3/4.10.1 PRIKARY CONTAINHENT JNTECRITY......................... B 3/4 10-1 1

3/4.10.2 ROD SEQUENCE CONTROL SYSTEM (DELETED)................. B 3/4 10-2 l 3/4.10.3 S HUTDOWN MARCIN DEMON STRATION S . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10-3 3/4.10.4 R EC I R CU LATI ON L00 P S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10-4 3/4.10.5 P LA NT S ERV I CE W AT ER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10-5 l t

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BRUNSWICK - UNIT 1 XII Amendment No.

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i REACTIVITY CONTROL SYSTEMS LIMIT!NC , CONDITION FOR OPERATION (Continued) I ACTION! (Continued)

2. If the inoperable control rod (s) is inserted  ;

a) Within one hour disarm the associated directional control valves ,

either!  !

1) Electrically, or

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

b) Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c. With more than 8 control rods inoperable, be in at. least HOT SHUTDOWN ,

within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. ,

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE at least once per 31 days byt*

a. Verifying each valve to be open.

b. Cycling each valve at least one complete cycle of full travel.

4.1.3.1.2 All withdrawn control rods not required to have their directional control valves disarmed electrically or hydraulically shall be demonstrated '

OPERABLE by moving each cont rol rod at least one notch

a. At least once per 7 days when above the preset power level of the RWH l and y

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b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when above the preset power level of the. i RWH and any control rod is immovable as a result of excessive I friction or mechanical interference.

4.1.3.1.3 All withdrawn control rods shall be determined OPERABLE by

• demonstratiag the scram discharge volume drain and vent valves OPERABLE, when i the reactor protection system logic is tested per Specification 4.3.1.2, by ,

l verifying that the drain and vent valvest l

a. Close within 30 seconds after receipt of a signal for control rods to scram, and

• l b. Open when the scram signal is reset or the scram discharge volume trip is bypassed.

• These valves may be closed intermittently for testing under administrative control. .

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

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REACTIVITY CONTROL SYSTEMS f

CONTROL ROD MAXIMUM SCRAM INSERTION TIMES LIMITING CONDITION FOR OPERATION 3.1.3.2 The maximum scram insertion time of each cont rol rod f rom the f ully withdrawn position to notch position 6, based on de-energitation of the scram pilot valve solenoids as time zero, shall not exceed 7.0 seconds. .

APPLICABILITY OPERATIONAL CONDITIONS 1 and 2.

ACTIONt With the maximum scram insertion time of one or more control rods exceeding 7.0 seconds, operation may continue and the provisions of Specification 3.0.4 are not applicable provided that t

a. The control rod with the slow insertion time is declared inoperable,

b. The requirements of Specification 3.1.3.1 are satisfied, and

c. If within the preset power level of the RWH, the requirements of Specification 3.1.4.1.d are also satisfied, and

d. The Surveillance Requirements of Spccification 4.1.3.2.c are l performed at least once per 92 days when operation is continued with three or more control rods with slow scram insertion timest Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l l SURVEILLANCE REQUIREMENTS 4.1.3.2 The maximum scram insertion time of the control rods shall be demonstrated through measurement

a. For all control rods -prior to TilERMAL POWER exceeding 40% of RATED THERMAL POWER following CORE ALTERATIONS or af ter a reactor shutdown that is greater than 120 days, i

b. For specifically af fected individual control rods following maintenance on or modification to the control rod or rod drive system which could affect the scram insertion time of those specific control L rods, and

c. For 10% of the control rods, on a rotating basis, at least once per 120 days of operation. ,

BRUNSWICK - UNIT 1 3/4 1-5 Amendment No.

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REACTIVITY CONTROL SYSTEMS ~

FOUR CONTROL F.0D CROUP SCRAM INSERTION ' TIMES QTING CONblTION FOR OPERATION 3.1.3.4 The average scram insertion time, f rom the fully withdrawn position,-

for the three fastest cont rol rods in each group of four control rods arranged in a two-by-two array, based on deenergitation of the scram pilot valve solenoids as time zero, shall not exceed any of the followingt Position Inserted from Average Scram inser-Fully Wit hdrawn tion Time (Seconds) ,

46 0.33

-36 1.12

26. 1.93 i 6 3.58 APPLICABILITYI OPERATIONAL CONDITIONS 1 and 2.

ACTIONI With the average scram insertion times of control- rods exceeding the above limits, operation may continue and the provisions of Specification 3.0.4 are not appilcable providedt

a. The control rods with the slower than average scram insertion times are declared inoperable,

b. The ' requirements of Specification 3.1.3.1 are satisfied, and

c. If within the preset power level of ~ the RWM,- the requirements of Specification 3.1.4.1.d are also satisfied, and

d. The Surveillance Requirements of Specification 4.1.3.2.c are l-performed at least once per 92 days whtn operation is continued with three or more control rods with slow scram insertion times.

' Otherwise, be in at least il0T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.1.3.4 All control rods shall be demonstrated OPERABLE by scram time testing from the fully withdrawn position as' required by Surveillance Requirement 4.1.3.2.

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BRUNSWICK - UNIT 1 3/4 1-7 Amendment No.

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REACTIVITY CONTROL SYSTEMS l CONTROL ROD SCRAM ACCUMULATORS

LIMITING CONDITION FOR OPERATION 3.1.3.5 All control rod scram accumulators shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and $*. .

ACTION:

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a. In OPERATIONAL CONDITION 1 or 2 with one cont rol rod scram i accumulator inoperable, the provisions of Specification 3.0.4 are not- 1 applicable and operation may continue, provided that within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> t r

1. The inoperable accumulator is restored to OPERABLE status, or ,

2. The control rod associated with the inoperable accumulator is declared inoperable, and the requirements of Specification.

3.1.3.1 are satisfied.

3. And, if within the preset power level of the RWM, the requirements of Specification 3.1.4.1.d are also satisfied.

Otherwise, be in at least HOT SHUTDOWN within the next-12 hours.

b. In OPERATIONAL CONDITION $* with a withdrawn control rod scram accumulator inoperable, fully insert the affected control rod and electrically disarm the directional control valves within one hour.

The provisions of Specification 3.0.3 are not applicable.  ;

SURVEILLANCE REQUIREMENTS a 4.1.3.5 The control rod scram accumulators shall be determined OPERABLE:

a. At least once per 7 days by verifying that the pressure and leak [

detectors are not in the alarmed condition, and i

b. At least once per 18 months by performance of at

1. CHANNEL FUNCTIONAL TEST of the leak' detectors, and

2. CHANNEL CALIBRATION of the pressure detectors.

• At least the accumulator associated with each withdrawn control rod. Not applicable to cont rol rods removed per Specification 3.9.10.1 or 3.9.10.2.

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

REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE COUPLINC LIMITING CONDITION FOR OPERATION 3.1.3.6 All control rods shall be coupled to their drive mechanisms.

APPLICABILITY CONDITIONS 1, 2, and 5*.

ACTIONI

a. In CONDITION 1 or 2 with one control rod not coupled to its associated drive mechanism, the provisions of Specification 3.0.4 are 4 not applicable and operation may continue providedt i

1. Within the preset power level of the idei, the cont rol rod is  !

declared inoperable and fully inserted until recoupling can be attempted with TilERMAL POWER above the preset power level of the RWM and the requirements of Specification 3.1.4.1.d are 1 satisfied. g

2. Above the preset power level of the RWM, the control rod drive l 1s inserted to accomplish recoupling. If recoupling is not accomplished on the first attempt, declare the control rod inoperable, fully insert the control rod, and electrically disarm the directional control valves.

3. The requirements of Specification 3.1.3.1 are satisfied.

b. In CONDITION 5*, with a withdrawn control rod not coupled to its associated drive mechanism, insert the control rod to' accomplish recoupling. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.1.3.6 The coupling integrity of a control rod shall be demonstrat ed by withdrawing the control rod to the fully withdrawn position and verif ying that the rod does not go to the overt ravel positiont I

a. Prior to reactor criticality after completing CORE ALTERATIONS that could have af fected the control rod drive coupling integrity,

• At least each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

J BRUNSWICK - UNIT 1 3/4 1-9 Amendment No.

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• e REACTIVITY CONTROL SYSTEMS CONTROL ROD POSIT!ON INDICATION LlHITINC CONDITION FOR OPERATION 3.1. 3' 7 All control rod reed switch position indicators shall be OPERABLE.

i APPLICABILITY: CONDITIONS 1. 2, and 5*.

ACTION:

a. In CONDITION 1 or 21 With one or more control rod reed switch position indicators inoperable, including " Full-in" or " Full-out" i indication, the provisions of Specification 3.0.4 are not applicable and operation may continue, provided that within one hours' '

1) The position of the control rod is determined by an  !

alternate method, or

2) The control rod is moved to a position with an OPERABLE  !

reed switch posi; ion indicator, or

3) The control rod with the inoperable reed _ switch position  ;

indicator is declared inoperable and the requirements of Specification 3.1.3.1 are satis fied t

4) And, if within the preset power level of the RWH, the requirements of Specification 3.1.4.1.d are satisfiedt  ;

Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. ,

b. In CONDITION 5* with a withdrawn control. rod reed switch position i indicator inoperable, fully insert the withdrawn control rod. The l

provisions of Specification 3.0.3 are not appilcable.

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• At least each withdrawn control rod. Not applicable to control rode removed per Specification 3.9.10.1 or 3.9.10.2.

BRUNSWICK - Utii t . 3/4 1-11 Amendment No. +

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REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.3.7 The cont-al rod reed switch position indicators shall be determined OPERABLE by verifyingt

a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, that the position of the control rod is indicated,

b. That the indicated control rod position changes during the movement of the control rod when performing Surveillance Requirement l 4.1.3.1.2, and  !

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c. That the control rod reed switch position indicator corresponds to the control rod position indicated by the " Full-out" reed switches when performing Surveillance Requirement 4.1.3.6.b.

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BRUNSWICK UNIT 1 3/4 1-12 Amend ment No.

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L REACTIVITY CONTROL SYSTEMS 1

3/4 1.4 CONTROL-ROD PROGRAM CONTROLS ROD WORTH MINIMIZER-LIMITING CONDITION FOR OPERATION 1 3.1.4.1- The Rod Worth Minimirer,(RWM) shall'be OPERABLE when THERMAL POWER.is l~ei than 10% of RATED THERMAL POWER.:

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APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2*.

ACTIONt i

a. .With the RWM inoperable after the-first 12 control rods have been' d f ully withdrawn on-a -startup,-. operation _ may continue provided that control rod movement and compliance lwith the prescribed BPWS control; p rod pattern are verified by a_second licensed operator or qualified  ;

member of the plant technical staff.

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b. With the RWM inoperable before the first 12 control: rods are l '

withdrawn on a startup, one startup'per calender year may be performed provided that . control rod movement'and compliance with the

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j prescribed BPWS control rod pattern are verified by a'second li ensed, operator or qualified m' ember of the plant technical staff.

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c. .With RWM inoperable on'a shutdown, shutdown may continu'e provided 1' that control rod movement 'and compliance with the prescribed BPWS control rod pattern are verified by a second licensed operator-or-

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A qualified member-of,the plant technical-staff.  !

d.

b With RWM' operable but individual controlL rod (s) declared inoperable,' e operation and control rod movement:below the. pres *nt pwer level of : '

',}'

the RWM may continnefprovidedi' i

1. No more. than three '(3) control rods _are _ declared inoperablec in' any one BWS group, and, -

2. The inoperable control rod (s) is bypassed on the RWM and control  !

rod movement of the_ bypassed rod (s) is: verified 1by'a second '

licensed operator or qualified member of the plant J t echnical, j staff. t i

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With RWM l'aperable,.the provisions of Specification 3.0.4 are not applicable.

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• Entry into OPERATIONAL CONDITION 2 and withdrawal of sel'ected control, rods is

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permitted for the' purpose of determining the OPERABILITY of-the RWM prior to withdrawal of control rods for.the purpose of bringing the reactor to -

-criticality.

1 BRUNSWICK - UNIT 1 3/4 1-14 Amendment No-.

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REACTIVITY CONTROL SYSTEMS 't SURVEILLANCE REQUIREMENTS _, ., _,

4.1.4.1.1 The RWM shall te demonstra*e< .

.RABLE in OPERATIONAL CONDITION 2, a prior to withdrawat of control rods for tne purpose of making the reactor -

critical and in OPERATIONAL CONDITION 1 when the RWM is initiated during .;

control rod inrsrtion when reducing THERMAL POWER by

[

a. Verifying proper annunciation. of the select' ion error of at least one out-of-sequence' control rod, and i

b. Verifying the rod block function of the RWM by moving an out-of- I sequence control rod.

'l 4.1~.4.1.2 The RWM shall- be demonstrated OPERABLE by verifying the control rod Banked Position Withdrawal Sequence. input to the RWM computer is correct -

following any-loading of the sequence program into the computer.

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BRUNSWICK - UNIT 1 3/4 1-14a Amendment No.

, -e o: i REACTIVITY CONTROL SYSTEMS ROD SEQUENCE CONTROL SYSTEM-LIMITING CONDITION FOR OPERATION ,

3.1.4.2 (DELETED)-

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SURVEILLANCE REQUIREMENTS:

4.1.4.2 (DELETED) "

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BRUNSWICK - UNIT 1 3/4 1-15 Amendment No.

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Page 3/4 1-16.

Intentionally Left Blank I

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l BRUNSWICK - UNIT 1 3/4 1-16 Amendment $No.

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n SPECIAL-TEST EXCEPTIONS 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM' LIMITING CONDITION FOR OPERATION 3.10.2 (DELETED)

SURVEILLANCE REQUIREMENTS 4.10.2- (DELETED) 1.

t BRUNSWICK'- UNIT 1 3,4 10-2 Amendmer.t No.

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n REACTIVITY CONTROL SYSTEM

. i BASES CONTROL RODS (Continued)  !

on a scram than has been a* 'lped even chough control rods with inoperable i accumulators may still be errod wit h normal drive water pressure.

Operability of the accumulatu

- 'A at there is a means available to j insert the control rods. even uader the n.o:: unfavorable depressurization of:

the= reactors.

Control rod coupling integrity is required to ensure compliance with .the j analysis of the rod drop accident in the PSAR. The overtravel position j feature provides the only positive means of determining that a rod is properly - '

coupled and, therefore, this check must be performed prior to achieving criticality after each refueling. The subse'quent check is performed as a  !

backup to the initial demonstration. j

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In order to ensure that the control rod patterns can be followed and therefore that other parameters are within-their limits, the control rod position indication system must be OPERABLE.

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The control rod housing support restricts the outward movement of a i

-control rod to less than 3 inches in the event of a' housing failure. The  ;

amount of rod reactivity which could be-added by.this small amount of rod withdrawal is less than a normal *ithdrawal increment'and will not contribute i to any damage to the primary coolant-system. The support is not required when j there is no pressure to act as a driving force to rapidly eject a drive :i housing.

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The required surveillance intervals,are adequate to determine that.the [

rods are OPERABLE and not so frequent as to cause excessive wear on the system j components. b 3/4.1.4 CONTROL ROD PROCRAM CONTROLS 1

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Control rod withdrawal and insertion sequences are established to assure

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that the maximum in sequence individual control rod or control rod segments which are withdrawn at any time during the fuel cycle could not be worth i enough to result in a peak fuel enthalpy greater than 280 cal /gm in the event  ;

of a control rod drop accident. . The specified sequences are characterized hv

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l homogeneous, scattered patterns of controlcrod withdrawal. When= THERMAL PC

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i is greater than or equal to.10% of RATED THERMAL POWER, there<is no possible ,;

rod worth which, if dropped at the design rate of the velocity limiter,.could '

result in a peak enthalpy of 280 cal /gm. Thus, requiring the RWM'to be ,

OPERABLE when THERMAL POWER is less than 10% of RATED THERMAL POWER provides:  !

adequate control.

Use of the Banked Position Withdrawal Sequence (BPWS) ensures that in:the event of a control rod drop accident the peak fuel enthalpy will not be greater than 280 cal /gm (Reference 4).

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

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REACTIVITY CONTROL SYSTEM BASES

, - CONTROL ROD PROGRAM CONTROLS (Continued) 1 -

The RWM as.a backup to procedural control, pr xides an automatic cont rol l rod pattern monitoring f unction to ensure adherence to the BPWS control movement sequences f rom 100% control- rod densi ty to 10% ' RATED THERHAL POWER D and, thus, eliminates the postulated <: control rod drop accident from resulting in a peak fuel' enthalpy greater than 280- cal /gm .(Ref erence 5).

lc l The requirement that RWM. be operable for the withdrawal of the first 12 ,

E control rods on a startup is to ensure that the RWM systen, maintains a high '

degree of availability.

Deviation from the BPWS control rod pattern may be allowed for thel '

. perf ormance of c Shutdown Martin Demonstration tests.

The' analysis of the rod drop accident . is presented -in Section.15.4.6 of the Updated FSAR and the techniques cf the analysis are presented in.a topical report (Reference.1) and two supplements -(References 2 and 3).

-The RBM is designed to automatically prevent fuel damage in the event of erroneous-rod withdrawal from locations of-high power density during high power operation. Two channels are provided. Tripping one of the channels l will block erroneous rod withdrawal soon enough to prevent fuel-damage. . This L system backs up the written sequence used by the operator for withdrawal of control rods.  ;

I i' I

3/4.1.5 STANDBY LIQUID CONTROL SYSTEM 1

1 The standby liquid control ' system provides a backup capability for maintaining the reactor suberitical in the event that insufficient rods are-  !

inserted in the core when a scram is called-for. The volume;and weight

. percent of poison material in solution is based on being able to bring the l reactor -to the suberitical condition as the plant cools to ambient condition. The temperature requirement is necessary to keep the sodium

- pentaborate in solution. Checking the volume and temperature once each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> assures ~that the solution is available for use.

With redundant pumps and a highly reliable control rod scram system, operation of the reactor is permitted to continue for short: periods of time with the system inoperable or for longer periods of' time with one of the l redundant components inoperable.

Surveillance requirements are established on a f requency that assures a high reliability of the system. Once the solution is established, boron i concentration wtll not vary unless more boron or water is-added, thus a: check on the temperature and volume once each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> assures that the solution:is available for use.  !

Replaceme.nt 'of the explosive charges in the valves at regular intervals  ;

will assure that these valves will not fail because of-deterioration of the charges.

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

REACTIVITY CONTROL SYSTEM

-BASES Referencest

1. C. J. Paone, R. C. Stirn, and J. A. Woodley, " Rod Drop Accident Analysis for Large BWRs " C. E. Topical Report NEDO-10527, March 1512.

2. C. J~. Paone, R. C. Sti rn, and R. M. Yound, Supplement I to NEDO-10527,

' July 1972.

I

3. .J. A. Haum, C. J. - Paone, .and R. C. Stirn, addendum 2 " Exposed Cores" 'l supplement 2 to NEDO-10527, January 1973. j

4. NEDE-240ll-P-A, " General . Elect ric Standard Application f or Reactor Fuel," l Revision 6, Amendment 12. '

5. NEDE-20411-P-A, " General Electric Standard Application f or Reactor Fuel,"

Revision 8,1 Amendment 17.

-)

i BRUNSWICK - UNIT 1 B 3/4 1-5 Amendment No.

I p:.. ..

3/4.10 SPECIAL TEST EXCEPTIONS-BASES

• 3/4.10.1- PRIMARY CONTAIRMENT INTECRITY.

The requirement for PRIHARY. CONTAINMENT INTEGRITY is removed during the period when- open vessel tests are being performed during low power PHYSICS TESTS.

3/4.10.2 ROD SEQUENCE CONTROL SYSTEM (DELETED)

~

'3/4.10.3' SHUTDOWN' M ARCIN DEMONSTRATIONS Performance of shutdown margin demonstrations with the vessel head

removed requires additional restrictions in orderf to ensure _ that criticality l does not occur. These additional restrictions are- specified in this LCO.

3/4.10.4- RECIRCULATION: LOOPS i This special: test exception permits reactor criticality under no flow conditions and is~ required to perform certain start-up and PHYSICS TESTS while .j

. at low. THERMAL POWER levels.. i 3/4.10.5 -PLANT SERVICE WATER '

This Special Test Exception permits securing the Service Water System conventional-header when the nuclear' header =is out of service and is required to permit flange-installation in-service' water system header cross-connect piping.

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-f BRUNSWICK - UNIT 1 B 3/4 10-1 Amendment No.

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q. .

INDEX LIMITINC CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS -

SECTION PACE.

3/4.0 A P P L I C A B I L I TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARCIN.......................................... L3/4 1-1 3 / 4 .1. 2 . R EA CTI V I TY AN0M AL I E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1 3/4.1.3 ' CONTROL RODS-Con t rol Rod O pe ra bi l i t y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1 1 Cont rol Rod Max imum Scram Ins er t i on Times . . . . . . . . . . . . . . . . . 3/4 1-5 H Control Rod Average Scram Insertion Times................ 3/4 1 l Four Control Rod Group Scram Insertion Times.............. 3/4 1-7 Con t rol Rod S c ram Acc umul at or s . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.1-8 Con t r ol Rod Dri ve Cou pl ing . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-9 Control Rod Position Indication........................... 3/4 1-11 Control Rod Drive Housing Support........................ 3/4'l 3/4.1.4 CONTROL ROD PROGRAM CONTROLS -l Rod Worth Minimizer...................................... 3/4'l-14 -l Rod Sequence Control System (SdLETED)....................- 3/4 1-15 l Rod Block Monitor........ ......... ...................... 3/4 1-17 3/4.1.5 STANDBY LIQUI D CONTROL SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . . . . -3/4 1-18 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERACE PLANAR LI NE AR HEAT CENERATION RATE. . . . . . . . . . . . . . . 3/4 2-1 3/4.2.2 MINIMUM CR'TICAL POWER RATI0............................. 3/4 2-3 BRUNSWICK - UNIT 2 IV Amendment No.

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. _ _ _ . _ _ _ _ _ _ _ _ . _ I

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PACE 3/4.9 REFUELINC OPERATIONS (Continued) .

3/4.9.3 CONTROL-ROD POSITION................. ........... .... 3/4 9-5 3/4,9.4 DECAY TIME............................................ 3/4 9-6 l

-3/4.9.5 COMMUNICATIONS........................................ 3/4 9-7 3/4.9.6' ' CRANE AND HOI ST OPERABI LI TY . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-8 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORACE POOL. . . . . . . . . . . . . . . . . . 3/4 9-9 3/4.9.8 WATER LEVEL-REACTOR VESSEL............................ 3/4 9-10.

L 3/4.9.9 WATER LEVEL-SPENT FUEL STORACE P00L................... 3/4 9-11.  ;

3/4.9.10 CONTROL ROD REMOVAL r Single Control' Rod Removal............................ 3/4 9-12.

Mul t i pl e Cont ro l Rod Remo val . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-14 3/4.10 SPECIAL' TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINHENT INTECRITY......................... 3/4 10-l' 3/4.10.2 ROD' SEQUENCE CONTROL SYSTEM (DELETED)................. 3/4110-2 l 3/4.10.3 SHUTDOWN HARCIN DEMONSTRATIONS........................ 3/4 10-3 3/4.10.4. R EC I R CU LATI ON L00 PS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-4

_,9 3/4.10.5 P LA NT S ER VI C E W AT ER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-5 i

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BRUNSWICK - UNIT 2 IX Amendment No.

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INDEX BASES SECTION PACE

'3/4.7 PLANT SYSTEMS (,ontinued) 3/4.7.3- F LOO D P RO T E CT I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-1 3/4.7.4 R EACTOR CORE ISOLATION COOLI NG SYSTEM . . . . . . . . . . . . . . . . . . B 3/4 7-1 3/4.7.5 SNUBBERS................................................ B 3/4 7-2 3/4.7.6 S EALED SOURCE CONTAMI NATI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-4 i

3/4.7.7 FI RE SUPPRESS ION SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-4 i 3/4.7.8 FIRE BARRIER PENETRATIONS.............................. B 3/4 7-5 t i

3/4.8 E LE CT R I C A L POW E R S Y ST EM S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

B-3/4 8-1

, l 3/4.9 REFUELING OPERATIONS j 3/4.9.1 R EA CTOR MOD E SW 1 TCH . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 I 3/4.9.2 I N S T R UM EN TAT I O N . . . . . . . . . . . . . . . . . '. . . . . . . . . . . . . . . . . . . . . . B 3/4-9-1 3/4.9.3 CONTROL ROD P0SITICN.................................. B 3/4-9-1 3/4.9.4 DEC AY TIME. . . . . . . . ................................. B 3/4 9-1 3/4.9.5 COMMUNICATIONS........................................ B'3/4 9-1 I 3/4.9.6 CRANE AND E10lST OPERABILITY........................... B 3/4 9-2 3/4.9.7 C' ME TRAVEL-SPENT FUEL STORACE- P00L.' . . . . . . . . . . . . . . . . . B'3/4 9-2 R 3/4.9.8 WATER LEVEL-REACTOR VESSEL, and 3/4.9.9 W ATER LEVEL-R EACTOR FUEL STOR ACE P00L. . . . . . . . . . . . . . . . . B 3/4 9-2 ,

3/4.9.10 CONTROL ROD REM 0 VAL.........,.......................... B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIO[S  !

3/4.10.1 P R I MARY CONTAi h ME NT I NT EC R I TY . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10  ;

3/4.10.2 ROD SEQUENCE CONTROL SYSTEM ( DELETED) . . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.3 SHUTDOWN MARC IN DEMON STRATION S. . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.4 R EC I R CU LATI ON L00 PS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - B 3/4 10-1 -

-3/4.10.5 P LANT S ERV I CE ' W ATER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 10-1 l I

BRUNSWICK - UNIT 2 XII Amendment No.

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Cont inued)

ACTION: (Continued)

'2. -If the inoperable control rod (s) is inserted:  !

a) Within one hour' disarm the associated directional control? valves either:

1) Electrically, or  !

2)- . Hydraulically by closing the drive water and ' exhaust water -

isolation valves.

~

b) Otherwise, be in at least HOT SHUTDOWW within the- next .12 hout s,

c. With more than 8 control rods inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. ,

SURVEILLANCE REQUIREMENTS

'4.1.3.1.1 'The scram discharge volume drain'and vent valves shall be k demonstrated OPERABLE at least once per 31 days byt*

a. ' Verifying each valve to be open.  !

b. Cycling each valve at least one complete cycle of full tr; vel.

4.1.3.1.2 All withdrawn control rods not requiredLto have their directional control valves disarmed electrically' or hydraulically shall. be demonstrated OPERABLE by moving each control. rod at least'one notch:- .

a. At least once per 7 days when above the preset power level'of the RWM and l .

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b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when above the preset power level of the  !

RWM and any control rod is immovable as a result'of excessive

~ l' friction or mechanical interference. l 4.1.3.1.3 All withdrawn control rods shall be determined OPERABLE by demonstrating the scram discharge volume. drain and vent < valves OPERABLE, when the reactor protection system logic is. tested per Specification 4.3.1.2, by verifying that the drain and vent valves q

a. Close within 30 seconds after receipt of a signal for. cont-ol rods to I scram, and b.- Open when the scram signal is reset or the scram discharge volume trip is bypassed.

• These valves say be closed intermittently for testing under administrative i control.

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

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s' .-

REACTIVITY CONTROL SYSTEMS

]

CONTROL ROD MAXIMUM SCRAM INSERTION TIMES ' I LIMITING CONDITION FOR OPERATION 3.1.3.2 The maximum scram insertion t'ime of esch: cont rol rod _ f rom the f ully-withdrawn-position to notch position 6, based on =de-energization of the scram!  !

time zero,' shall'not exceed 7.0 seconds.--

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pilot valve solenoids , I APPLICABILITY: -OPERATIONAL CONDITIONS l and 2. [

ACTION:

With the maximum scram insertion time of one'or more, control rods. exceeding 7.0 seconds, operation may continue and the provisions of Specification l 3.0.4 are not applicable provided thatt

a. The control rod with the- slow insertion time is declared inoperable,

b. The requi rement s of Specificatio'n '3'.l.3.1 are sat isfied' and-

c. If within the preset power l'evel of f the: RWM,, the1 requirements ' of Speci fication 3.1.4.1.d' a re al so sati sfied, and L d.

f .i The Surveillance Requirements of Specification '4.1;3.2.c are l performed at least once per 92' days when'operationtis continued with three or more control rods"with slow scram insertion timesi Otherwise,'be in at leas t il0T . SilUTDOV. althin the next 12: hours.-

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SURVEILLANCE REQUIREMENTS 2

+

4.1.3.2 The maximum scram insertion time of~the control" rods'shall be demonstrated through measurement:

a. For all control rods prior to TilERMAL POWER exceeding 40%' of RATED THERMAL POWER f ollowing CORE ALTERATIONS 4 or af ter a ' reactor. shutdown that is greater than 120 days,

b. For specifically af fected individual control rods following

~

maintenance on or modification to-the control rod or_ rod drive-system which could affect the scram insertion time of ~ those specific control-rods, and

c. For 10% of the control rods, on a rotating basis,~at least once per 120 days of operation.

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BRUNSWICK - UNIT 2 3/4 1-5 Amendment No.-

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o REACTIVITY CONTROL SYSTEMS 1

' FOUR CONTROL ROD' CROUP SCRAM INSERTION TIMES LIMITINC- CONDITION FOR OPERATION 3.1.3.4 TheLaverage. scram insertion time,_from the1 fully withdrawn position, I for the three fastest control' rods in each' group of four control rods arranged in a two-by-two array', based' on deenergitation of the scram pilot valve-  !

solenoids as time zero, shall not exceed any of the following Position Inserted From- Average Scram Inser-Fully Withdrawn . tion Time (Seconds) 46 0.33-36 1.12 26 1.93 .i 6 3.58 N

-APPLYCABILITY: OPERATIONAL CONDITIONS 1 and.2. - t ACTION:

With the average scram insertion times of control rods exceeding the above ,

limits, operation may continue and the provisions of Specification 3.0.4 are ,

not applicable provided:  ?

a. The control rods with the slower than -average scram insertion times are declared inoperable, i

b. The requirements of Specification 3.1.3.I'are satisfied, and

c. If'within the_ preset power level of the RWH, the requirements of Specification 3.1.4.1.d are:also satisfied.:and i

d. The Surveillance Requirements.of. Specification 4.1.3.2.c are _

l  !

I performed at least once per.92 days-when operation is continued with

• three or more control rods with slow' scram insertion time's.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.1.3.4 All control rods shall be demonstrated OPERABLE by scram time testing ~

from the fully withdrawn positist as required by Surveillance Requirementi 4.1.3.2.

i BRUNSWICK. - UNIT 2 3/4 1-7 Amendment No.

O - m e .e - .,, p

4E+ 4 REACTIVITY CONTROL-SYSTEMS'

. CONTROL ROD SCRAM ACCUMULATORS .

LIMITING CONDITION FOR OPERATION i 3.1.3.5 All control rod scram accumulators shall-be OPERABLE.

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1 APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 5*.

' ACTION:

a. In OPERATIONAL CONDITION 1 or-2 with one control rod scram accumulator inoperable, the provisions of. Specification,3.0.4 are not applicable'and operation may continue,- provided' that within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

1. The inoperable accumulator is restored to OPERABLE status, or

2. 'The control rod associated with the inoperable accumulator is  ;

declared 'inopetable, and- the requirements of Specification 3.1.3.1 are satisfied. ,

3. And, if within the preset power level of the RWM, the

~

requirements of Specification 3.1.4.1.d are also satisfied =. l i

Otherwise, be in at least HOT SHUTDOWN within the next.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

~

b. In OPERATIONAL CONDITION $* with a withdrawn control rod scram-accumulator inoperable, fully insert. the af fected control rod and 1 electrically disarm the directional control valves within one hour.

The provisions'of Specification 3.0.3 areLnot applicable.

SURVEILLANCE REQUIREMENTS

}j 4.1.3.5 The control- rod scram accumulators shallL be ' determined'0PERABLE: '

a. At least once per 7 days by verifying.that the. pressure and leak detectors are not in the alarmed condition,and t

b. At least once per 18 months by perf ormance of a n-  ;

1. CHANNEL FUNCTIONAL TEST of the -leak detectors, and j

2. CHANNEL CALIBRATION of the. pressure detectors.

• At least the accumulator associated with each withdrawn control . rod. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

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l BRUNSWICK - UNIT '2 3/4.1-8 Amendment No.

w a[ + %

REACTIVITY CONTROL SYSTEMS

- 3;ilTROL ROD DRIVE COUPLING

.QMITINC CONDITION FOR OPERATION 3.1.3.6 All control rods shall be coupled- to their drive -mechanisms.

APPLICABILITY: CONDITIONS 1, 2, and $*.

ACTIONt-

a. .In CONDITION 1 or:2 with one control rod _not coupled to its associated drive mechanism, the provisions of Specification 3.0.4 are-not applicable and operation may continue providedt

1. Within the preset- power level of the RWM, the _ cont rol rod is I declared inoperable and fully inserted until recoupling can- be attempted with TilERMAL POWER above the preset power level of;the' RWM and the-requirements of Specification'3.1.4.1.d are satisfied. 1l

2. Above the preset power level of the RWM, the control _ rod drive l is inserted'to accomplish recoupling. If recoupling is not accomplished on the first attempt, declare the control ~ rod-

. inoperable, fully insert the control rod, and. electrically disarm-the directional control valves.

3.- The requirements of Specification 3.1.3.1 are satisfied.

b. In CONDITION 5*, with a withdrawn control rod not coupled _ to its associated drive mechanism, insert the control rod to accomplish recoupling. The provisions of Specification ~3.0,3 are not' applicable.

SURVEILLANCE REQUIREMENTS 4.1.3.6 The coupling integrity of a control rod shall be demonstrated by withdrawing the control rod to the fully withdrawn position and verifying that the rod does not-go to the overtravel positiont l

• At least each withdrawn control rod. Not applicable to control rods' removed per Specification 3.9.10.1 or 3.9.10.2.

BRUNSWICK - UNIT 2 3/4 1-9 Amendment No.

REACTIVITY CONTROL SYSTEMS -

' CONTROL ROD POSITION INDICATION +

LIMITING CONDITION FOR OPERA

• ION- -

P 3.1.3.7 All control' rod rerd switch position indicators ~shall be OPERABLE.

APPLICABILITY: CONDITIONS 4 2, and 5*..

?

ACTION:

a. In CONDITION 1 or 2: With one or more control rod reed' switch position indicators inoperable, including " Full-in" or- " Full-out'! ,

indication, the provisions of Specification 3.0.4 are not applicable.

and operation may continue, provided that within one hour:

1) The position of the control rod is determined ~by an. l alternate method, or

2) The control rod.is moved to a position with an OPERABLE l j reed switch position indicator, or

3) The. control rod with the inoperable reed switch position: l indicator is declared inoperable and the requirements of Specification 3.1.3.1 are satisfied;.

4) And, if within the preset power level of the RWM, the requirements of Specification 3.1.4.1.d are'also Jatisfied; ,

Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, -

b. 'In CONDITION 5* with a withdrawn control rod reediswitch position indicator inoperable, ' fully insert the withdrawn: control rod. The provisions of Specification 3.0.3 are not aPflicable.

r i

• At least each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

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l BRUNSWICK - UNIT 2 3/4 1-11 Amendment No.

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REACTIVITY CONTROL SYSTEMS >

l SURVElLLANCE REQUIREMENTS 4.1.3.i The control rod reed switch position indicators shall be determined OPERABLE by verifyingt - l-

a. Ac least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, that the position of the control rod is indicated,.

b. That the indicated control' rod position changes during the movement of the control rod when performing Surveillance Requirement 4.1.3.1.2, and ,

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c. That the control rod reed switch position. indicator corresponds to the control rod position ' indicated by the " Full-out" reed switches when performing Surveillance Requirement 4.1.3.6.b.  ;

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l BRUNSWICK '- UNIT 2 3/4-1-12 Amendment No.

L4 + *:

REACTIVITY CONTROL SYSTEMS . {

3/4' l'.4 - CONTROL ROD 1PROCRAM CONTROLS i

,P WORTH MINIMIZER' a MITING CONDITION FOR OPERATION 3.1.4.1 The Rod Worth Minimizer .(RWM) shall' be OPERABLE when> THERHAL -POWER is ,

less than 10% of RATED THERMAL POWER.

' APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2*. i ACTION: ,

a.' With the RWM' inoperable after the first 12 control' rods have beenf l fully withdrawn on a startup,= operation may continue provided that control rod movement and compliance with the prescribed' BPWS control'  !

' rod pattern are verified by a_second licensed operator _or.qualifieds

member of the plant technical staff.

b. With the RWM inoperable before the first 12' control rods are withdrawn on a startup, one startup per calender year may be . .

performed provided that control rod movement and compliance.withithe prescribed BPWS control rod pattern are verified by a second licensed operator or qualified member of the' plant" technical'staf f. '

c. With RWM inoperable on a. shutdown,? shutdown may continue provided - ~,

that control rod movement land compliance with the prescribed BPWS control rod pattern are verified by a second licensed operator or qualified member of the plant' technical staff.

d. -With-RWM-operable but individual control 1 rod (s) declared inoperable, operation and control rod ~ movement-below the preset power = level of the RWM may continue providedt_

=1. No more than. three-(3) control rods are declared' inoperable in t any one BWS group, and, r

2. The inoperable control rod (s),is bypassedfon the EG41 and-' control rod movement of the' bypassed rod (s) is verified by a second.

licensed _ operator or qualified member of the'plantLtechnical

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staff. i

e. With RWM-inoperable, the provisions of Specification 3.0.4 are not applicable.

)

• Entry into OPERATIONAL CONDITION 2 and withdrawal of selected control rods is permitted for the purpose of determining the OPERABILITY of the RWM prior to withdrawal- of control rods for the purpose of bt'inging the reactor to criticality.  ;

i BRUNSWICK - UNIT 2 3/4 1-14 Amendment No.

wv d 4

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REACTIVITY' CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4 .1. 4 .1.1 - The RWM shall.ta demonstrated OPERABLE. in OPERATIONAL CONDITION 2, prior to withdrawal of controljrods for the purpose of making the reactor critical and in OPERATIONAL CONDITION 1 when the RWM is initiated during control rod insertion when reducingzTilERMAL POWER by

a. Verifying proper annunciation of the selection error of'at least one out-of-sequence cont rol rod , and I

b. Verifying the' rod block function of the RWM by moving an out-of- i sequence control rod.

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4.1.4.1.2 The RWM shall4 be demonstrated-OPERABLE by verif ying the controlf rod .

Banked Position Withdrawal Sequence-input to the RWH computer is correct following any loading of the sequence program into the computer..

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BRUNSWICK - UNIT 2 3/4 1-14a Amendment No. l

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.. . .. ;  ?; s N(

l REACTIVITY. CONTROL' SYSTEMS t

ROD' SEQUENCE CONTROL SYSTEM ,o i

L1HITING CONDITION FOR OPERATION

-3.1.4.2 (DELETED) .t

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4 SURVEILLANCE REQUIREHENTS 4.1.4.2 (DELETED)'

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BRUNSWICK - UNIT 2 3/4 1-15 Amendment No.

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i ' BRUNSWICK - UNIT 2 3/4-1-16 Amendment Noa l.

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I SPECIAL TEST EXCEPTIONS 3/4.10.2-~ ROD SEQUENCE CONTROL SYSTEM LIMITING CONDITION FOR OPERATION  :

1 3.10.2 (DELETED)

SURVEILLANCE REQUIREMENTS 4.10.2 (DELETED) l

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BRUNSWICK - UNIT 2~ 3/4 10-2 Amendment No.

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1 REACTIVITY CONTROL SYSTEM  !

BASES

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CONTROL RODS (Continued) on a scram tha'n has been analyzed even though control rods with inoperable accumulators may still be ir.serted with normal drive water pressure. ,

Operability of the accumulator ensures that-there'is a means available to insert the ~ control rods even under the most' unfavorable depressurization of -j the reactors. i Control rod coupling integrity is required to ensure compli'ance with' the q analysis of the rod drop accident in'the PSAR. The overtravel position '

feature provides the only positive means of determining that a rod-is properly  ;

coupled and therefore this check must be performed prior to achieving-criticality af ter each refueling. . The subsequent-check is-performed'as a.

backup to the initial demonstration.

In order to ensure that'the-control rod patterns can be followed and I therefore that other parameters are within their limits, the control. rod position indication system-must be OPERABLE.

The control rod housing support rest ricts the outward movement of a control rud to less than 3 inches in the event of a housing failure. . The- 1 amount of rod'Eeactivity which could be added by this small amount of rod withdrawal is less than a normal withdrawal increment and will not contribute to any damage to the primary coolant' system. The support is not required.when  !

there-is no pressere to set as a driving force to rapidly eject a drive housing.-

The required surveillance intervals are adequate to determine.thatsthe j rods are OPERABLE and not so frequent as to cause excessive wear on:thefsystem

• components.

3/4.1.4 CONTROL ROD PROGRAM CONTROLS +

Control rod withdrawal and insertion sequences are established to assure that the maximum in sequence individual control rod or control rod segments which are withdrawn at any time during the fuel cycle could not be worth L enough to result in a peak fuel enthalpy greater than 280 cal /gm in-the event. -i l

of a control rod drop accident. The specified sequences are characterized by homogeneous, scattered patterns of control rod withdrawal. When THERMAL POWER is greater than or equal to 10% of RATED THERMAL POWER, there is no possible l-  ;

rod worth which, if dropped at the design rate of the velocity limiter, could result in a peak enthalpy of 280 cal /gm. <Thus, requiring the RWH to be l ,

OPERABLE when THERHAL POWER is less than 10% of RATED TiiERHAL POWER provides L

adequate control.

Use of the Banked Position Withdrawal Sequence (BPWS) ensures that in the '

event of a control rod drop accident the peak fuel enthalpy will not be greater than 280 cal /gm (Reference 4).

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

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• O REACTIVITY CONTROL SYSTEM BASES CONTROL ROD PROCRAM CONTROLS (Continued)

The RWM as a backup to procedural cont rol provides an automatic control rod pattern monitoring function to ensure adherence to the BPWS control movement sequences f rom 100% control rod density to 10% RATED THERHAL POWER and, thus, eliminates the postulated control rod drop accident f rom resulting in a peak fuel enthalpy greater than 280 cal /gm (Reference 5).

The requirement-that RWM be operable for the withdrawal of the 'first- 12 control rods on a startup is to ensure that the RWM system maintains a high degree of availability.

Deviation f rom the BPWS control' rod pattern may be allowed for the-performance of Shutdown Martit Demonstration tests.

The analysis of the rod drop accident is pre < ted in Section 15.4.6 of-the Updated FSAR and the -techniques of the anal) .s are presented in a topical report (Reference 1) and two supplements (References 2 and 3).

The RBM is designed to automatically prevent f uel damage in the event of erroneous rod withdrawal from locations of high power density during high power operation. The RBM is only required to be operable when the limiting condition described in Specification 3.1.4.3 exists. Two channels are provided. Tripping one of the channels will block erroneous rod withdrawal soon enough to prevent f uel damage. This system backs up the written sequence used by the operator for withdrawal of control rods. Further discussion of the RBM system is provided in Reference 5.

3/4.1.5 STANDBY LIQUID CONTROL SYSTEM The standby liquid control system provides a backup capability for=

maintaining the reactor suberitical in the event that insufficient rods are inserted in the core when a scram is called for. The volume and weight percent of poison material in solution is based on being able to bring the reactor to the suberitical condition as the plant cools to anbient condition. The temperature requirement'is necessary to keep the sodium pentaborate in solution.- Checking the volume and temperature once each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> assures that the solution is available for use.

With redundant pumps and a highly reliable control rod scram system, operation of the reactor is permitted to continue for short periods of time with the system inoperable or for longer periods aof time with one of the redundant components inoperable.

Surveillance requirements are established on a f requency that assures a high reliability of the system. Once. the solution is established, boron concentration will not vary unless more boron or water is added, thus a' check on the temperature and volume once each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> assures that the solution is .)'

avai'able for use.

Replacement of the explosive charges in the valves at regular intervals will assure that these valves will not fail because of deterioration of the charges. i I

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

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mP REACTIVITY CONTROL SYSTEM

' BASES'

References:

1. C. J. Paone, R. C. Stirn and J. A. Woodley,'" Rod Drop Accident Analysis for Large BWRs " C. E. Topical Report NEDO-10527, March 1972.

2. 1C. J. ' Paone, R. C. Sti rn, and R. M._ Yound, Supplement 1 to NED0-10527,

_ July 1972.

3. J. A. Haum, C. J. Paone, and R. C. Stirn, addendum 2_" Exposed Cores" supplement 2 to NED0-10527,fJanuary 1973.

4.. NEDE-240ll-P-A, " General Electric Standard Application f or Reactor Fuel,"

Revision 6, Amendment 12.

5. NEDC-31654P, " Maximum Extended Operating Domain Analysis for Brunswick Steam Electric Plant, " February-1989.

6. NEDE-20411-P-A, " General Electric Standard Application for Reactor Fuel,"

Revision 8, Amendment 17.

c BRUNSWICK - UNIT 2 B 3/4 1-5 Amendment No.

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3 o f .1 o' 3/4.10 SPECI AL TEST EXCEPTIONS BASES 3/4.10.1 PRIMARY CONTAINMENT INTECRITY ,

The requirement for PRIMARY CONTAINMENT INTECRITY is removed during the [

period when open vessel tests are being perf ormed during low power PHYSICS TESTS.

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3/4.10.2 ROD SEQUENCE CONTROL SYSTEM (DELETED) 3/4.10.3 SHUTDOWN MARCIN DEMONSTRATIONS Performance of shutdown margin demonstrations with the vessel head removed requires additional' restrictions in order to ensure that criticality '

does not occur. These additional restrictions are specified in this LCO. '

3/4.10.4 RECIRCULATION IDOPS 1

This special test exception permits reactor criticalit'y under no' flow conditions and is requireo te perform certain start-up and PHYSICS TESTS while -l at low THERMAL POWER levels. '

3/4.10.5 PLANT SERVICE WATER-This Special Test Exception permits securing the Service Water System conventional header when the nuclear header is out of service and is required

, to permit flange installation in service water system header cross-connect l Pi ping.

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l BRUNSWICK - UNIT 2 B 3/4.10-1 AmendmentiNo.

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