Text

Proposed Tech Specs Change Re Removal of Rod Sequence Control Sys
	ML20059G768
Person / Time
Site:	Brunswick
Issue date:	08/29/1990
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML20059G752	List: ML20059G749; ML20059G768;
References
	TAC-76164, TAC-76165, NUDOCS 9009130138
	Download: ML20059G768 (38)
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<:' BRUNSWICK STEAM ELECTRIC PLANT,. UNITS 1 AND 2 NRC DOCKETS 50 325 & 50-324'-

cy,T a - OPERATING LICENSES DPR 71'& DPR h 'M ~ REQUEST FOR LICENSE AMENDMENT

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ROD-SEQUENCE CONTROL' SYSTEM / ROD WORTH MINIMIZER-(NRC TAC NOS'.,76164.AND.76165).

, y a h;; TECHNICAL SPECIFICATION PAGES - UNIT 1.

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9009130138 900029 PDR ADOCK 05000324 ~;,,f ,

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INDEX'

- .. i LIMITING CONDITIONS F0k OPERATION AND SURVEILLANCE REQUIREMENTS

.SECTION PACE

>L3/4.0 A P P L I CA B I LI TY . . . . i . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .3/4 0 3/4.1 REACTIVITY CONTROL SYSTEMS 3 / 4 .1.1 S HUTDOWN MARC I N . . t. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . : 3/4il-1'

,J" 13 / 4.1. 2 > R EACTI V ITY ' ANOMAL I ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '3/4-1-2 a

3/4.1.3 CONTROL RODS Con t r ol _ Rod O pe ra bi l i t y . . . . . . . . . . . . . . . . . . . . . . . . . . '. . . . . . . . 3/4 1-3 Control' Rod'Haximum Scram Insertion Times................ 3/4 1-5 q., . Control Rod Average. Scram Insertion Times................ 3/4;1-6 s

Four- Cont rol ' Rod Group Scram Inse rt ion Time s. . . . . . . . . . . . . 3/4 1-7 Control Rod Scram Accumulators.............'.............. 3/4 1-8.

1 Con t rol Rod D ri ve Cou pl ing. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1 . Control Rod ~ Position. Indication........................'... 3/4.4-11 e ' 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'l-15 l Rod Block Monitor............,............................ 3/4 1-17'

., - 3 / 4.1. 5 . STANDBY LIQUID _ CONTROL SYSTEM . . . . . . . . . . . . . . . . . . . . . . .' . . . . . 3/4 1-18 3/4.2 POWER DISTRIBUTION' LIMITS

(

s ' 3/4. 2 ~. 1 L AVERACE PLANAR LI NE AR H EAT CENERATION R ATE. . . . . . . . . . . . . . . 3/4 2-1 3/4'.2.2 A PRM :: S ETP 0 I NT S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 3/4 2-2 3 / 4'. 2. 3 - MINIhUM CRITI CAL POWER RATI 0. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4,2 W:- u , ,

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9 a ib INDEX!

LIMITING CONDITIONS'FOR OPERATION AND SURVEILLAN G REQUIREMENTS- _

L SECTION P AC E .-

g; ai 3/4.9 REFUELINC 0PERATIONS (Continued) ,

'/4.9.3' CONTROL ROD POSIT 10N.................................. -.3/4 9-5' 3/4.9.k: DECAY TIME........4................................... 3/4 9-6;

, 3/4.9.5 COMMUNICATIONS........................................ 3/4 9-7 3/4.9.6 C RANE ' AND 110l ST O PE RABI LI TY . . . . . . . . . . . . . . . . . .~. . . . . . . . . 3/4 9-8 3 / 4. 9 '. 7 l- . CRANE TRAVEL-SPENT FUEL STORACE P00L.................. 3/4 9-9 3/4.9.8- WATER LEVEL-REACTOR VESSEL;........................... -3/4 9-10 3/4.9.9' WATEli LEVEL-SPENT FUEL STORACE P00L...................' 3/4 9-11 3/4.9.10 CONTROL ROD REMOVAL Single Control Rod Removal..........................'... 3/4 9 Mut t i ple Cont rol Rod .Remova l . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4-9-14

.3/4.10 SPECIAL TEST EXCEPTIONS .1 .

3/4.10.1- PRIMARY CONTAINMENT INTEGRITY......................... 3/4 10-1 3/4.10.2- - ROD S EQUENCE CONTROL ' 4 v. EM ( DELETED) . . . . . . . . . . . . . . . . . - 3/4'10-2' ll ,

3 / 4.10. 3 - ' S!!UTDOWN MARCIN. 00r10N STRATION S . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-3 3/4.10.4- RECIRCULATION L00PS;..................................- 3/4 10-4 3/4.10.5 P LANT S ERV I CE W AT ER . . . . . . . . . . . . . . . . . . . '. . . . . . . . . . . . . . . . - 3/4 10-5 s

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BRUNSWICK - UNIT 1 IX Amendment No.

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'INDEX

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[, 3/4.7: PLANT SYSTEMS (Continued) 3/4.7.3 FLOOD PROTECT 10N.......................................- B 3/4 7-1 3/4.7.4. REACTOR CORE-ISOLATION COOLING SYSTEM.................. B 3/4 7-l'-

, . 3/4.7.5 SNUBBERS............................................... B 3/4 7-2

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3 / 4.'7. 6 :. S EA LE D SOUR CE CONTAMI N ATI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-3/4 7-3

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3 / 4.- 7. 7 FIRE SUPPRESSION SYSTEMS............................... B 3/4 7-3" '

3/4.7.8- FIRE BARRIER PENETRATIONS.............................. .

B 3/4 7-3' i

3/4.8 ELECTRICAL POWER SYSTEMS.................................... B 3/4 8-1 '

. :3/4.9 J REFUELINC OPERATIONS

- 3/4.9.1 REACTOR MODE SWITCH.................................... B 3/4-9-1

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B 3/4 9-1 3 / 4'. 9. 2 INSTRUMENTATION........................................

<3/4.9.3 CONTROL ROD POSIT!0N.................................. B 3/4 9-1 3/4.9.4- ' DECAY TIME............................................. B 3/4 9 3/4.9.5 COMMUNICATIONS........................................ B 3/4 9 * '3/4;9.6- - CRANE AND HOI ST OPERABI LI TY . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9 "

1. M- 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORACE P00L. . . . . . . . . . . . . . . . . . - B 3/4'9-2 m

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3/4.9.8 WATER LEVEL-REACTOR VESSELi and

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-3/4.9.9- . W ATER LEVEL-REACTOR FUEL STOR ACE P00L. . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.10 CONTROL ROD REM 0 VAL.................................... B 3/4 9-2 13/4.10- SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY......................... B 3/4:10-1

(,, . h <3/4.10.2 ROD SEQUENCE CONTROL SYSTEM (DELETED)................. B 3/4 10-2 l

> 3/4.'10.3 SHUTDOWN'HARCIN DEMONSTRATIONS........................ B 3/4 10-3

3/4.10.4 RECIRCULATION-L00PS................................... B 3/4'10-4 3/4.10.5 PLANT SERVICE WATER................................... B 3/4 10 ;{

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BRUNSWICK - UNIT 1 XII Amendment No.

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i . . s REACTIVITY CONTROL SYSTEMS-

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LIMITING CONDITION FOR OPERATION (Continued)

~ A'CTION : = (Continued)'

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

' a); Within ~one hour disarm the associated ' directional control valves

'either:

Elect rically,_ or

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Hydraul cally-by closing the drive-water and exhaust water,

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2) isolation valves.

_b)' _0therwise,Jbe in at least HOT; SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

-within 12, hours. n

, SURVEILLANCE REQUIREMENTS 4.1.3.'l'.1'=The scram discharge volume drain and vent valves shall be

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demonstrated OPERABLE 'at .least once_ per 31 days byt* ,

e a.- Verifying,each valve-to be open.

, (b.- Cycling each: valve at 'least one complete cycle of f ul'1 travel.

4'.l'.3'.l.2^ All: withdrawn control rods not required to have their directional

' control valve's' disarmed electrically or hydraulically shall be demonstrated

[ ' OPERABLE by moving 3each control rod at'least 'one notch:.

a. LAt_least.once per 7 days when above the preset power level of the RWM iand t l.

'b. At least once-per 24-hours when above the preset power level of the l

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

friction or_ mechanical interference.

g 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:

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g, a. Close within 30 seconds af ter receipt of a signal for control rods to .

q scram,'and.

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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. l l

iBRUNSWICK , UNIT 1 3/4 1-4 Amendment No.

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[(. qq REACTIVITY CONTROL SYSTEMS I CONTROL ROD HAXIMUM SCRAM ' INSERTION TIMES

- LIMITING CONDITION FOR OPERATION D <

~ 3.1.3.2 'The maximum scram insertion time of each control rod from-the fully r withdrawn position .to' notch position 6,' based on de-energization of the scram

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4 pilot valve solenoids as time zero, shall not exceed-7.0 seconds.

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- APPLICABILITY: .CGNDITIONS 1 and 2. '

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ACTION:

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With the maximum scram insertion time of oneoor more control rods exceeding 9

' 7.0 seconds, operation may continue and the provisions of Specification 3.0.4 dj, .

are. not applicable provided that:

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

b.- The requirenwnts of Specification 3.1.3.1 are satisfied, and

c. If within the preset power level of the RWM, the1 requirements of Specification 3.1.4.1.d are also-satisfied. and ,

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

' SURVEILLANCE REQUIREMENTS 2

4.1.3.2J The maximum scram insertion time of the: control rods shall be j demonstrated through measurement:

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a. For all control rods prior to THERMAL POWER; exceeding 40% of RATED-THERMAL' POWER following CORE ALTERATIONS or af ter.a reactor shutdown ;

that is greater than 120 days, 4"

b .' Forcspecifically affected individual control rods following i maintenance on or modification to the control rod or' rod drive system "

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, which could affect the scram insertion time of those specific control ,

D rods, and ;

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

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

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/ tf5 REACTIVITY CONTROL SYSTEMS

. f g ..FOUR CONTR0tt ROD CROUP SCRAM INSERTION TIMES 7-LLIMITINC CONDITION FOR OPERATION q^. 3.l'.3.4 Th'e" average; scram' insertion time, from the fully withdrawn position, for. the three fastest cont rol rods in each group of four cont. ol rods arranged w( -

.in a two-by-two array, based on.-deenergitation of the scram pilot valve g" solenoids as time zero, shall not exceed any of the following v Position Inserted From Average Scram Inser-

," Ful ly ' W i t hd rawn - tion Time (Seconds)

, ,. 46 0.33-V* ' 3 6 --

26 1.12 1.93 6 3.58 APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

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, cb. .The requirements of Specification 3.1.3.1 are satisfied. and

.!f within the preset power level'of the RWM,1the requirements of

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c.

+ ' Specification 3.1.4.1.d are also satisfied,.and

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d. The Surveillance Requirements of Specification 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' times.

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 .

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SURVEILLANCE' REQUIREMENTS 4 '.'l . 3. 4 All' control rods shall,be demonstrated OPIRABLE 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. j y -

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REASTIVITY CONTROL SYSTEMS

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' CONTROL ROD SCRAM - ACCUMULATORS i lLIMITINC' CONDITION FOR OPERATION -- (

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4 3.1.3.5' - All control rod scram accumulators shall' be OPERABLE. j L

APPLICABILITYt. OPERATIONAL CONDITIONS 1, 2, and $*,

' ACTION:

~ 1

a. In 0PERATIONAL CONDITION 1 or J2 with one cont rol rod scram .

accumulator: inoperable, the' provisions of Specification- 3.0.4 are- not i 7; . applicable and operation may continue, provided that within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

-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. .,

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

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

i

b. '

In'GPERATIONAL CONDITION 5* with a withdrawn control rod scram accumulator inoperable,c 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 3

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4.1.3.5 The control rod scram accumulators shall be determined OPERABLE::

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

b. At least once' per- 18 months by performance of a s

1. ; CHANNEL FUNCTIONAL TEST of the leak detectors, and Ols , ;

[ 2. CHANNEL CALIBRATION of the pressure detectors. j

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n , -*At least the accumulator associated with each withdrawn control rod. Not

,, cpplicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2. -

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

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.o REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE COUPLINC

, L1HITING CONDITION FOR OPERATION 3.1.3.6 All control rods shall be coupled to their drive mechanisms.

APPLICABILITY: CONDITIONS 1, 2, and 5*.

ACTION:

a. In CONDITION 1 or 2 wit h one control rod not- coupled to its -

.associa*ed drive mechanism, the provisions of Specitication 3.0.4 are not app.icable and operation may continue provided =

1. Within the preset power level' of the RWM, the cont rol rodL si l declared inoperable and fully inserted until 'recoupling can be attempted with THERHAL POWER above the preset power level of'the-

-RWH-and;the requirements of Specification 3.1.4.1.d are l satisfied.

2. Above the preset power level ot the RWH, the control rod drive =l' is-inserted to accomplish recoupling. If recoupling istnot accomplished on the first attempt, declare the control rod inoperable, fully insert the control rod, and electrically disarm the directional control valves.

3. The requireme s of Specification 3.1.3.1 are satisfied.-

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

SURVEILLANCE REQUIREMENTS is , ..

4.' l . 3. 6 The coupling, integrity of a control rod shall be demonstrated by

'E 1 ~ withdrawingcthe control rod to the fully withdrawn position and verifying that

, y .the rod ~does not go to the. overtravel positions g,' a. Prior to reactor. criticality after completing CORE ALTERATIONS chat could have af fected the control rod drive coupling integrity,;

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

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

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. REACTIVITY -CONTROL SYSTEMS -

CONTROL ROD POSITION INDICATION LIMITING CONDITION FOR OPERATION

- 3.1.3.7,"All control rod' reed switch position indicators shall be'0PERABLE.-

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

S ACTION '

a. In CONDITION 1 or 2 With one or more control rod reed switchL l

, position indicators inoperable, including " Full-in" or " Full-out" indication, the provisions of Specification 3.0.4 are -not ' applicable r 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' reed' switch-position indicator, or

3) The control rod with the inoperable reed switch position 1l-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 satisfied;

=0therwise, be in at least HOT SHUTDOWN within 12-hours.

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.In CONDITION 5* with a withdrawn control rod reed switchL position

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b.

indicator inoperable, fully insert the withdrawn controtirod.'- The

. provisions of Specification 3.0.3'are.not applicable.

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

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

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- . REACTIVI1T CONTROL SYSTEMS ;

, , SURVEILLANCE REQUIREhdNTS !

!4.1.3.1, - The ' control rod reed switch position indicators shall be determined l' -;

OPERABLE by verifying.

as At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , that the position of the cont'rcl rod is c indicated,

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b. That the indicated control rod position changes doring ths movement of: the control rod when' performing Surveillance Requirement

>:4.1.3.1.2, and-s

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

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, 11' hI BRUNSWICK - UNIT 1 3/4 1-12 Amendment No.

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' REACTIVITY CONTROL SYSTEMS

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3/4 1.41 CONTROL ROD PROGRAM CONTROIS ROD WORTil MINIMlZER LIMITING CONDITION' FOR OPERATION t __

3.1.4.1 -The Rod Worth Minimizer: (RWM) shall be OPERABLE when TilERMAL POWER-is less than 10% of RATED TilERMAL POWER. -[

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2*.

ACTIONt-

a. With the RWM. inoperable af ter the first 12 control-rods.hsve been.

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' qualified 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 u performed provided that control rod movement'and compilance with the-prescribed BPWS control rod pattern are verified by a second licensed

, operatoroor qualified member of the plant technical staff.

c' . WithLRWH inoperable on a shutdown, shutdown may continue provided that control rod movement and 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 rod (s) declared inoperable, y operation and' control rod movement below the present power level of the RWM may continue provided:

-1.

No more than three (3) control rods are declared inoperable in any one BWS group, and, m 2. The inoperable control rod (s) is bypassed on the RWM and control rod movement of the bypassed rod (s) .is ' verified by a second licensed operator or qualified member of the plant technical staff.

e. With RWM inoperat 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 bringing the reactor to criticality.

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

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-REACTIVITY CONTROL SYSTEMS 4

SURVEILLANCE REQUIREMENTS 1.

4.1.4.1.1 _The RWM shall be demonstrated OPERABLE in OPERATIONAL ~ CONDITION 2 -

prior to withdrawal of control rods for the purpose of_ making the reactor-1 ' critical and in OPERATIONAL CONDITION I when the RWM is initiated during

control rod insertion when reducing THERHAL POWER byt-

a. : Verifying proper annunciation of.the selection error of:at least-one

<out-of-sequence control rod, and-

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

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. l

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.i I ROD SEQUENCE CONTROL' SYSTEM ,

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

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BRUNSWICK - UNIT l' 3/4 10-2 Amendment No.

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4 REACTIVITY CONTROL SYSTEM BASES _

CONTROL RODC (C .t inued) on a scram than has been analyzed even thougi control rods with inoperable accumulators may still be inserted with cormal drive water pressure.

Operability of the accumulator ensures the t there is a means available to insert the control rods even under the most unf avorable depressurization of the reactors.

Control rod coupling integrity is raquired to ensure compliance with the analysis of the rod drop accident in the FSAR. 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 after 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 follnwed and therefore that other parameters are within their limits, the control rod position indication system must be OPERABLE.

The control rod housing suppcrt rest rict s the outward movement of a 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 withdrawal increment and will not contribute to any damage to the primary coolant system. The support is not required when there is no pressure to act as a driving f orce to rapidly eject a drive housing.

The required surveillance intervals are adequate to determine that he rods are OPERABLE and not so frequent as to cause excessive wear on the system components.

3/4.1.4 CONTROL ROD PROGRAM CONTROLS Control rod withdrawal and insertion sequences are established to assure trat 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 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 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 OPERABLE when THERHAL POWER is less than 10% of RATED THERHAL 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.

J. : p...

" b; ,

h REACTIVITY CONTROL SYSTEM BASES CONTROL ROD PROCRAM CONTROLS (Continued)

The 'RWH as a backup to procedural control provioes 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 TiiERMAL POWER-and, thus,. eliminates the postulated control rod drop accident from 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 -15 to ensure that the RWM system maintains a high degree of-availability.

Deviation f rom the- BPWS control rod pattern may be allowed f or the

. performance of Shutdown Margin Demonstration tests.

=The analysis of the rod drop accident is presented in-Section 15.4.6 of

.the Updated FSAR and the techniques of the analysis are presented in a topical .l report:(Reference 1) and two' supplements (References 2 and 3).

The RBM isLdesigned to automatically prevent f uel damage in the event of

, erroneous rod withdrawal from locations of high_ power = density during high p power operation. Two channels are provided. Trapping 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.

3/4.1.5 STANDBY LIQUID- CONTROL SYSTEM Thel atandby . liquid ' control system provides a backup capability f or

-maintaining;the reactor suberitical in the event that insufficient rods are inserted:in the core when a scram isLcalled for. The volume and weight '

Lpercentiof poison material in~ solution is based on being able to bring the

'reartor to the subcritical conditico 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 241 hours0.00279 days 0.0669 hours 3.984788e-4 weeks 9.17005e-5 months ' 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-b with 'the ; system . inoperable or for longer periods of time with. one of the ,

c , redundant-components inoperable.

- Surveillance requirements are established on a frequency that assuresLa 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months assures that the solution is-m Javailable 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.

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

(f } .

h #; 1

.., m. .

E 'L f_)

o,.

- REACTIVITY CONTROL SYSTEM -

BASES f-2 '

Referencest.

1. C. J. - Paone, R. C.- Stirn, . and J. A. Woodley, " Rod Drop Accident Analysis' for Large BWRs' " C. - E. Topical Report NED0-10527; March' 1972.

2. C. J. : Paone, - R. C. Sti rn,. and R. M. Yound, ' Supplement .1 t o NEDo-10527, July 1972.

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

4. NEDE-240ll-P-A, ,"Ceneral > Electric Standard Application ~ for Reactor Fuel,"

, Revision 6, Amendment 12.

-n: .

5. NEDE-20411-P-A, "Ceneral Electric Standard Application for Reactor Fuel,"

4 Revision 8, Amendment 17.

6

.Y G ,

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

i .

',' *i

' ,7 P- -

"3/4.10 SPECIAL TEST EXCEPTIONS BASES 3/4.10.1 PPIMARY CONTAINMENT INTECRITY The requi rement - f or _ PRIMARY CONTAINMENT INTECRITY -i s removed during, the .

period ~ when _open vessel tests are being performed during low power PilYSICS TESTS.-

3/4.10.2 ROD SEQUENCE CONTROL SYSTEM (DELETED) 3/4.10.3 - SilVTDOWN M ARCIN DEMONSTRATIONS '

-Performance of shutdown margin demonstrations with the vessel head removed requires additional restrictions in order to ensure that criticalit'y:

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

3/4.10.'4 RECIRCULATION LOOPS-This special~ test exception permits reactor criticality under no _ flow

. conditions and' is- required to perform certain start-up and PilYSICS TESTS while

-at. Low THERMAL POWER levels.

-3/4.10.5 ' PLANT SERVICE WATER s

i 'This Spe'c ial 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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i BRUNSWICK - UNIT 1 B 3/4 10-1 Amendment No.

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9. : +

ENC 14SURE 3

, BRUNSWICK STEAM ELECTRIC PLANT,. UNITS 1 AND'2 NRC DOCKETS 50 325'& 50 324- 4 OPERATINC LICENSES DPR-71 & DPR.62 REQUEST. FOR LICENSE AMENDMENT ROD. SEQUENCE CONTROL SYSTEM / ROD WORTH MINIMIZER .

(NRC TAC NOS. 76164 = Ai4D 76165)-

TECHNICAL SPECIFICATION PAGES - UNIT 2 s o.

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LIMITINC' CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS :

m.

SECTION- PACE:

3/4.0 A P P L I CA B I L I TY . . . . . . . . , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . : 3/4 0-1

13/4.1 REACTIVITY CONTROL SYSTEMS-

' 3/ 4.1."1 SHUTDOWN MARCIN..................'.......................

. 3/4 1 '3/4;1.2 R EACT I V I T Y ~ AN OM AL I_E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1 L 3/4.1.3 CONTROL RODS-l'

!? Control Rod Operability.................................. 3/4.1 a Control' Rod' Maximum Scram Insertion Times................

, 1 3/4 1-5 L 7" , Control Rod Average Scram Insertion. Times................ 3/4 1-6 1

n.

Iye _ Four' Cont rol Rod Group Sc ram Inse rtion Times. . . . . . . . . . . . . 3/4 1-7 L Con t rol Rod S c ram . Ac c umul at or s . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4'l-8 l

Con t r ol Rod' D ri ve Cou pl ing. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - - 3 / 4 ' l-9

' Control Rod Position Indication..........................' 3/4 1-11 i, 1

Control Rod Drive Housing Support........................, 3/4 1-13 1!

23 / 4.~ 1. 4 CONTROL ROD PROGRAM CONTROLS , ,

i. ,

Rod Worth-Minimizer....................... ...........p.. 3/4 1-14

. Rod Sequence Control System (DELETED).................... 3/4l 1-15 '

.l g Rod Block Monitor......................................~.. 3/4 1-17 l L3/4.1.5- STANDBY LIQUID CONTROL SYST EM ; . . . . .' . . . . . . . . . . . . . . . . . . . . . . . 3/4 1 ,

3/4.2 L POWER DISTRIBUTION LIMITS '4t 3/4.2.1 AVERACE PLANAR LINEAR HEAT CENERATION RATE. . . . . . . . . . . . . . . 3/4 2-1 g ..

L 3/4.2.2 M I N I M UM C R I TI CAL POWE R ' RATI 0. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 2-2 ,j 1

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BRUNSWICK - UNIT 2 IV Amendment No. l

)

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$l 4 INDEX ;

,. LIMITINC CONDITIONS FOR OPERA" ION AND SURVEILLANCE REQUIREMENTS __

l!

l '

I.

SECT g % ACE 3/4.9 REFUELINC OPERATIONS (Continued) >

r 3/4.9.3 CONTROL ROD P0tITION............... .................. 3/4 9-5

[ 3/4.9.4 DECAY TIME............................................ 3/4 9-6 3/4.9.5 COMMUNICATIONS........................................ 3/4 9-7 -

3/4.9.6 CRANE AND !!OI ST OPE RABI LI TY . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-8 f 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORACE P00L. . . . . . . . . . . . . . . . . . 3/4 9-9 3/4.9.8 W AT ER L EV EL-R EACTot V ES S E L. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-10 3/4.9.9 WATER LEVEL-SPENT FUEL STORACE P00L................... 3/4 9-11 3/4.9.10 CONTROL' ROD REMOVAL- ,

S in gl e Cont rol Rod Re mo va l . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-12 Mul t i pl e Co nt rol Ro d Remova 1. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9 l 3/4.10 SPECIAL TEST EXCEPTIONS L e 3/4.10.1 PRIKARY CONTAINMENT li,*TECRITV......................... 3/4: 10-1 '

l 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM (DELETED)................. 3/4 10-2 3/4.10.3 S HUTDOWN MARCIN D EMONSTRATI ON S. . . . . . . . . . . . . . . . . . . . . . . . - 3/4 10-3 3/4.10.4 R EC I R CU LATI ON L00 PS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-4 3/4.10.5 P LA NT S ERV I C E W AT ER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 3/4 10-5 1>

j r

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5 BRUNSWICK - UNIT 2 IX Amendment No.

t 1..

INDEX

~ BASES

~

SECTION PACE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.3 FLOOD PROTECT 10N....................................... B 3/4.7-1 3/4. 7.4 - REACTOR COR E ISOLATION COOLING SYSTEM. . . . . . . . . . . . . . . . . . B 3/4 7-1 3/4.7.5 SNL'SRERS....... u...................................... B 3/4 7-2 3/4.7.6 S EALED SOURCE CONTAMI NATI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7 .

3/4.7.7 FIRE SUPPRESSION SYSTEJS............................... B 3/4 7-4 3/4.7 8 FIRE BARRIER PENETRATIONS.............................. B 3/4 7-5 3 / 4. 8 E LE CT RI C AL POWER S Y ST EM S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR HODE SWITCH.................................... B 3/4 9-1 3/4.9.2 I N S TR UM EN T AT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-1 3/4.9.3 CONTROL ROD P0SITION.................................. B'3/4 9.l 3/4.9.4 DECAY TlHE...... ..................................... B 3/4 9-1 3/4.9.5 COMMUNICATIONS........................................ B 3/4 9-1

-3/4.9.6 C RAN E AND HOI ST O P E RABI LI TY . . . . . . . . . . . . '. . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.7 CRANE TRAVEL-Sp?NT FUEL STORACE POOL. . . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.9.8 WATER LEVEL-REACTO. V. EL. and 3/4.9.9 UATER LEVEL-REACT 01 FUEL STORACE P00L................. B 3/4 9-2 3/4.9eiQ CON TR OL R OD R EM OV Al . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 9-2 3/4.10 VPECIAL TEST EXCEPTIONS 3/4.10.1 FRl HARY CONTAlWNENT INTEGRI TY . 2 4. . . . . . . . . . . . . . . . . . . . . . B 3/4 10-1 3/4.10.2 ROD S EQU1NCR CONTROL SICTEM ( DELETED) . . . e . . . . . . . . . . . . . B 3/4 10-1 l

-3/4.10.3 S HOTDOWN MARC IN D EMON ST RAT 10N h . . . . . . . . . . . . e . 4 . . . . . . . . B 3/4 10-1 3/4.10.? RECISCULATION LO0PS.............................u..... B 3/4 10-1 3/4.10.5 P LANT S ERVI CE W AT ER . . . . . . . . . . . e . . . . . e r . . . . . . . . . . . . . . . . 0 3/4 10-1 BRUNSWICK - UNIT 2 X11 Amendment No.

y-

' 4 2 # q4 P

o j REACTIVITY CONTROL SYSTEMS L

IdMITING CONDITIO FOR OPERATION (Cont inued)

ACTIONI (Continued) ~

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

a) Within one hour disarm the associated directional control valves L either -

1) Electrically, or i

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . 'I

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

within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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 t'ull travel, i 4.1.3.1.2 All withdrawn control rods not required to have their d'irectional control vahes disarmed'electrir ally or hydraulically shall be demonstrated OPERABLE by n.oving each control rod at least one notcht At least once per 7 days when above the preset power level of the RWH a.

and l l

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when above the preset power level of the RWM and any centrol rod is immovable as a result of ' excessive l friction or mechanical interference.

4.1.3.1.3 All withdrawn control rods shall be determined OPERABLE by demonstrating the scam 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 valvest l- a. Close within 30 seconds af ter receipt of a signal for control ro.is to L scram, and

b. Open when the scram signal is reset or the scram discharge volume I t rip is bypassed.

. , *These valves may be closed intermittintly for testing under administrative l

control.

l l

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

H. t f

. 'k ,.

'O

,t

.A

~

REACTIVITY CONTROL S) STEMS CONTROL ROD KAXIMUM SCRAM INSERTION TIMES !

LIMITINC CONDITION FOR OPERATION 3.1.3.2 The maximum scram insertion time of each control rod'from the ful Y withdrawn position to notch position 6, based on de-energization of the seraic pilot valve solenoids as time zero, shall not exceed 7.0 seconds.

-APPLICABILITY OPERATIONAL CONDITIONS 1 and 2.

ACTION: ,

m With the maximum scram insertion time of one or more control rods exceeding i

7. 0 seconds, operation may continue and the provisions of Specification 3.0.4 a.e not applicable provided thatt '

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

b. The .equirements of Specification 3,1.3.1 are satisfied, and r

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 cf Specification 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . ,

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

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

b. For specifically af fected individual cont rol rods following maintenance on or modification to the control rod or rod drive system l which could affect the scram insertion time of those specific control L rods, and l c. For 10% of the ccntrol rods, on a rotating basis, at least once per

120 days of operation.

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

s

{. ,

- i

!g.

REACTIVITY CONTROL SYSTEMS j FOUR COWTROL ROD CROUP SCRAM INSERTION TIMES ;

LIMITICC_ CONDITION FOR OPERATION t'

3.1.3.4 The average scram insertion time, f rom the fully withdrawn position, for _the tiree f astest control rods in each group of four control rods arranged in a two-hy-two array, based on deenergization of the scram pilot valve ;

, solenoids as time zero, shall not exceed any of tne followings t Positici inserted From

~

Average Scram Inser- l Ful l t Withd.a . _ tion Time (Seconds) l j~ 46 0.33-36 1.12 ,

26 1.93 6 3.58 i APPLICABILITY OPERATIONAL CONDITIONS I and 2. ,

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 a'rerage 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 when operation is continued with three or more control rods with slow scram incertion times.

t 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 .

. SURVEILLANCE REQUIREMENTS L 4.1.3.4 All. control rods shall be demonst rated OPERABLE by scram time testing .

~

from the fully withdrawn position as required by Surveillance Requirement l 4.1.3.2.

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

m.

I

,,. 4 . !

e REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS i

LIMITING CONDITION FOR OPERATION 3.l.3.$ All control rod scram accumulators shall be OPERABLE.

APPLICABi',lTY OPERATIONAL JONDIY10NS 1, 2, and $*.

ACTIOWs

a. In OPERATIONAL. CORDITION 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 Lourst- ;

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. l 4

3. And, if within the preset power level of the RWH, the requirements of Specification 3.1.4.1.d are also sa.isfied.

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

b. In OPERATIONAL CONDITION 5* 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 4.1.3.5 The control rod scram accumulators shall be determined OPERABLE l

a. At least once per 7 days by verifying that the pressure and leak detectors are noe in the alarmed condition, and ,

T

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

1. CHANNEL FUNCTIONAL TEST of the leak detectors, ano

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. !

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

QW( I' - . . . . . . . ' ' ' '.

' ~ '

(i l

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

APPLICABILITY: CONDITIONS 1, 2, and $*.

ACTION:

a. In CONDITION 1 or.2 with one control rod not coupled to its associated drive rechanism, 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 control rod is l declared. inoperable and fully inserted until recoupling can be attempted with THERMAL POWER _above the preset power level of the RWM and the requirements of Specification 3.1.4.1.d are .l satisfied.:

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 f ully withdrawn position and verifying that the rod does not 6 to the overtravel positiont 3 *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.

y y, ,

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REACTIVITY CONTROL SYSTEMS CONTROL ROD POSITION INDICATION LIMITING CONDITION FOR OPERATION

'3.1.3.7 All control rod reed switch position indicators shall be OPERABLE. ;

AP PLIC AB I LI,TY: CONDITIONS 1, 2, and 5*.

ACTION h

a. In CONDITION 1 or.): With one or more control . rod reed switch l 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 hourt !

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 reed switch position indicator, or !

3) The control rod with the inoperable reed switch position l-indicator is ceclared inoperable and the requirements of Specification 3.1.3.1 are satisfiedi

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

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

I

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

provisions of Specification 3.0.3 are not applicable.

f r

t 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 1-11 Amendment No. ,

l

p.

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i REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.3.7 The control rod reed switch position indicators shall be determined. l OPERABLE by verif yingt

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

b. That the indicated control rod position changes during the movement of the cont rol rod. when performing Surveillance Requirement 4....'.l.2, and '-

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

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BRUNSWICK - UNIT 2 3/4 1-12 Amendment No. t w :1L ' s >

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j REACTIVITY CONTROL SYSTEMS 3/4 1.4 CONTROL ROD PROCRAM CONTROLS ROD WORTH MINIM!ZER LIMITING CONDITION FOR OPERATION !

L 3.1.4.1 The Rod Worth Minimizer (RWM) shall bc OPERABLE when THERMAL POWER is less than 10% of RATED THERMAL POWER.

APPLICABILITY: OPERATIONAL CONDITIONS I and 2*.

V ~

ACTION 7 a. With the RWH -inoperable af ter the first 12 control rods have been l fully withdrawn on a startup, operation may continue provided that j control rod movement and compliance with the prescribed BPWS control L rod pattern are verified by a second licensed operator or qualified member of the plant technical staff.

b. With the RWH inoperable before the first 12 control rods are ,

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

prescribed BPWS control rod pattern are verified by a second licensed operator or qualified member of the plant technical staff.

c.-

~

With RWH inoperable on a shutdown, shutdown may continue provided that control rod movement and compliance with the prescribed BPWS p

control rod pattern are verified by a second licensed operator or ;

qualified member of the plant' technical staf f.

d. With RWH operable but individual control rod (s) declared inopnrable,

, operation and control rod movement below the preset power level of l the RWM may continue providedt

1. No more than thrce (3) control rods are declared inoperable in any one BWS group, and,

2. The inoperable control rod (s) is bypassed on the RWH and control ;

rod movement of the bypassed rod (s) is verified by a second licensed operator or qualified member of the plant technical staff.

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

Entry into O'PERATIONAL CONDITION 2 and withdrawal of selected control rods is '

permitted for the purpose of determining the OPERABILITY of the RWH prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.

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

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SURVEILLANCE REQUIREMENTS t 4.1.4.1.1 .The RWM shall. be demonstrated OPERABLE in OPERATIONAL CONDITION 2, prior to withdrawal of control rods for the purpose of making the reactor critical and in OPERATIONAL CONDITION 1 when the RWM is initiated during '

control rod insertion when reducing THERMAL POWER by .

-a. Verifying proper annunciation of the selection error of at least ons ,

[- out-of-sequence control rod, and ;

b. Verifying the rod _ block function of the RWM by moving an out-of- >

sequence control rod.

r 4.1.4.1.2 The RWM shall be demonstrated OPERABLE by veritying 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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h BRUNSWICK - UNIT 2 3/4 1-14a Amendment No. l

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Amendment No.

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REACTIVITY CONTROL SYSTEM BASES CONTROL RODS (Continued) on a scram than has been analyzed even though cont rol rods with inoperable accumulators may still be inserted with normal drive water pressure.

Operability, of the accumulator ensures that there is- a means available to insert the cont rol rods even under the most unfavorable depressurization of the reactors.

Control rod coupling integrity is required to ensure compliance with the analysis of the rod drop accident in the FSAR. 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 after 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 therefore that other parameters are within their limits, the control rod c position indication system must be OPERABLE.

The control rod housing support restricts the outward movement of a

- 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 withdrawal increment and will not contribute to any damage to the primary coolant system. The support is not required when there is no pressure to act as a driving force to rapidly eject a drive housing.

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 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 red or centrol rod segments which are withdrawn at any time during the f uel cycle could not be worth 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 by I homogeneous, scattered patterns of control rod withdrawal. When THERMAL POWER l 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 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 i greater than 280 cal /gm (Reference 4).

BRUNSWICK - UNIT 2 B 3/4 1-3 Amend ment No.

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REACTIVITY CONTROL SYSTEM, BASES _

CONTROLROD PROCitAM CONTROLS (Continued)

The RWM as a backup to procedural control provides an automatic control rod pattern monitoring function to ensure adherence to the BpWS control movement sequences from 100% control rod density to 10% RATED THERMAL p0WER and, thus, eliminates the postulated control rod drop accident from resulting in a peak fuel enthalpy greater than 280 cal /gm (Reference 5).'

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

Deviation from the BPWS control rod pattern may be allowed for the performance of Shutdown Margin Demonstration tests.

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

The RBH is desigr.ed to automatically nrevent fuel damage in the event of4 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 fuel 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.

h l.5 STANDBY LI(UID CONTROL SYSTEM The standby liquia control system provides a backup capability for mair.taining the reactor subcritical 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 tc bring the reactor to the suberitical condition as the plant cools to ambient condition. The temperatu e requirement is necessary to keep the sodium pentaborate in solution. Checking the volume and temperature on e each 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 redundant components inoperable.

Surveillance requirements are established on a frequency 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months assures that the solution is available for use.

Replacement of the explosive charges in the valves at regular intervals will assure that these valves will not fa!1 because of detertoration of the charges.

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

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4 REACTIVITY CONTROL SYSTEM BASES Re f e renc es t

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

July 1972.

l:

'3. J. A. Haum, C. J. Paone, and R. C. Stirn, addendum 2 " Exposed Cc ces"

supplement '2 to NED0-10527, January 1973.

(

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

Revision 6, Amendment 12. '!

5. NEDC-31654P, " Maximum Ex 'nded Operating Domain Analysis for Brunswick ,

Steam Electric Plant. " t.'ruary.1989. i

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

Revision 8, Amendment 17. I r

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

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o 3/4.10 SPECIAL' TEST EXCEPTIONS BAijS 3/4.10.1 PRIMARY CONTAIMMENT INTECRITY The requirement for PRIMARY CONTAINMENT INTECRITY is removed during the period when open vessel tests are being parformed during low power PHYSICS

~ TESTS.

3/4.10.2 ROD SEQUCNCE CONTROL SYSTEM (DELETED) 3/4.10.3 SiluTDOWN MARCIN DEMONSTT.ATIONS Performance of shutdown margin demonstrations with the vessel head removed requires additional restrictions in order to ensure that criticality does not occur. Toese additional restrictions are specified in this LCO.

3/4.10.4 RECIRCULATION LOOPS This special test exception permits reactor criticality under no flow-conditions and is required to perf orm certain start-up and PilYSICS TESTS while at low TilERMAL POWER levels.

3/4.10.5 Pl. ANT SERVICT. 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.

BRUNSWICK - UNIT 2 B 3/4 10-1 Amendment No.

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v t e Letter Sequence Other
TAC:76164, (Open) TAC:76165, (Open)
Initiation Request, Request Acceptance... Administration Questions Answers Results Approval... Other: ML20059G768
MONTHYEAR1990-08-29 [Table View]

ML20059G768

Text

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