Text

Amends 33 & 54 to Licenses DPR-71 & DPR-62,respectively, Revising Tech Specs to Provide one-time Extension of Certain Surveillance Intervals Allowing Required Testing to Be Performed
	ML20002D598
Person / Time
Site:	Brunswick
Issue date:	12/23/1980
From:	Ippolito T; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20002D599	List: ML20002D598; ML20002D603; ML20002D607;
References
	NUDOCS 8101210539
	Download: ML20002D598 (39)
	v • d • e

.O.

/

UNITED STATES

! % '., / %

NUCLEAR REGULATORY COMMISSION

-l(

. E WASHINGTON, D. C. 20555

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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 33 License No. DPR-71 1.

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

A.

The application for amendment by Carolina Power & Light Company dated November 5,1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.

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

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

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

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

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

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 33, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

B1022105~3%

. 3.

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

FOR THE NUCLEAR REGULATORY COMISSION

& c' 0v Thomas. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: December 23, 1980 4

4 i

l 1

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ATTACHMENT TO LICENSE AMEt0 MENT NO. 33 FACILITY OPERATING LICENSE NO. OPR-71 DOCKET NO. 50-325 Remove the following pages and replace with identically numbered pages.

3/4 1-7 / 3/4 1-8 3/4 1-19 / 3/4 1-20 3/4 3-9 / 3/4 3-10 3/4 3-29 / 3/4 3-30 3/4 3-37 / 3/4 3-38 3/4 3-49 / 3/4 3-50 3/5 5-7 / 3/4 5-8 3/4 6-13 / 3/4 6-14 3/4 6-19 / 3/4 6-20 3/46-23/3/46-24

^

3/4 6-25 / 3/4 6-26 3/4 6-27 / 3/4 6-28 3/4 7-9 / 3/4 7-10 3/4 8-3 / 3/4 8-4 3/4 8-9 / 3/4 8-10 The underlined pages are overleaf pages and are provided for convenience.

/

l REACTIVITY CCNTRCL SYSTEMS FOUR CONTROL ROD GROUP SCRAM INSERTION TIMES LIMIT!NG CONDITION FOR OPERATION 3.'1.3.4 The average scram insertion time, from the fuliy withdrawn position, for the three fastest control rods in each group of four control rods arranged in a two-by-two array, based on de-energization of the. scram pilo: valve sol.enoids as time zero, shall not exceed any of the folloving:

l Position Inserted From Average Scram Fully Withdrawn Insertion Time 46 0.398 seconds i

36 0.954 seconds 25 2.120 seconds 6

3.800 seconds APP' LICABILITY: CONDITIONS 1 and 2.

ACTION:

With the average scram insertion times of the control rods exceeding the above limits, oi;eration 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, b.

The requirements of Specification 3.1.3.1 are satisfied, and c.

The Surveillance Requirements of Specification 4.l'.3.2.c are 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 REOUIREVENTS 1

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- 1 ::. r:'.

s sna'i :e s:ra

-i.s tes,ed fr:- ne fully

'- :-se ::si-i:n as re:uire: :y 5:ecification ".i.3.2.

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9 m m q9 j\\\\.

Amendment No. 33,,

a u ce o 4ir 't.unanut sr3it.93 1

CONTROL RCD SCRAM ACCUMULATORS 4

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LIMITING CONDITION FOR OPERATION

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3.1.3.5 All c:ntrol red scram ac:I=tulators shall be OPERABLI.

APPLICA5!LITY:

CONDITICNS 1, 2 and 5*.

l ACTION:

a.

In CONDITION 1 or 2 with one centrol red scram accumulator inoperable, the prevtsions of Specificatten 3.0.4 are not appli-cable and operation may continue, provide # that within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months :

1.

The incperable ac:umulater is restored to OPERABLE status, or 2.

The c:ntrol r:d assceiated with the incperable ac:u-mulater is declared inocerable, and the requirsments of Specification 3.1.3.1 are satisfied.

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

b.

In CCNDITION 3* with a withdrawn c:ntici red scram accumula :r inecerable, fully insert the affectad 'c:ntrol red and elec-trically disar n :pe directional c:ntrol valves within one hour.

Tne previsions of Specification 3.0.3 are not applicable.

SURVE!LLANCE RECUIREMENT3 4.1. 3. 5 T1e control red scram accumulators shall be deter nined CPERABLI:

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

leak detect:rs are not in the alarmed c:ndition, and b.** At least ence per 18 =enth's by performance of a:

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i.

CHANNEL FUNCTIONAL i n i c7 :ne leak detec;:rs i

( Cli -L5-123-xm ), and 2.

CHANNEL CALIER*7!0!; cf One :ressure de act:rs

("li 25-130- m x).

"A: iaas

ne ac::=ula :r ass: cia:ec witn ancn wt ndrawn c:n:r:1 c:d.

Nc: ac:licaole :D ::ntrei r:cs remcvec per 5:ecifica:icn 3.9.10.1 er l

.:.10.:.

- For the performance of this surreillance scheduled to be completed by February 10, l

1981, a onecime-only exemption is allowed to extend this surveillance until "before the completion of the Spring 1981 outage," scheduled to commence in March, 1981.

BRUNS'a'ICK - UNIT 1 3/4 1.g Amendment No. 33

REACTIVITY CONTROL SYSTEMS SURVEILLANCE REOUIREMENTS l

4.1. 5 The standby liquid control system shall be demonstrated CPERABLE:

a.

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

1.

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

~2.

The heat tracing circuit is OPERABLE.

b.

At least once per 31 days by:

1.

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

Verifying the continuity of the explosive charge, and 3.

Determining the concentration of baron in solution'by chemical analysis. This test shall a.1so be performed anytime water or baron is added to the solution er.when the solution temperature drops below the limit established in Figure 3.1.5-2.

c.

At least once per 18 mor' > during shutdown by; 1.*

Initiating one et ehe standby itquid control system l

loops,' including an explosive valve, and verifying that a flow patti frem.the pumps to the reactor pressure.

vessel is available by pumping demineralized water into the reactor vessel. The replacement charge for the explosive valve shall be frem the same manufactured batch as the one fired or.frem another batch which has been certified by having one of that batch successfully fired.

Both injection test loops shall be tested in 36 months.

2.*

Demonstrating tN t tot minimum flow reouiremene of l

41.2 gp= a: a.rr sur of 1190 psig is met.

3.

Oemor.str;-i ;,

, ne pume relief valve se:ccint is 1200 - 50 psig.

For the performance of this surveillance scheduled to be completed by February 25, 1981, a onetime-only exemption is allowed to extend this surveillance until. "before the completion of the Spring 1981 outage,"

)

scheduled to commence in March, 1981.

BRUNS'JICK - UNIT 1 3/4 1-19 Amencment No. 33

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Amendment No. 33 g

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INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERA 8LE witz their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with

!$0LATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

With an isolation actuation instrumentation channel trip set-a.

point less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable and place the inoperable channel in the tripped condition until the channel is restored to OPERABLE status witt its trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With the requirements for the minimum number of OPERABLE channels not satisfied for one trip system, place at least one inoperable

(

channel in the tripped condition within one hour.

i With the requirements for the minimum nur.ber of OPERABLE channels c.

not satisfied for both trip systems, place at least one inoper-able channel in at least one trip system

in the tripped condition within one hour and take the ACTION required by Table 3.3.2-1.

d.

The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CONDITION S.

SURVEILLANCE REQUIREMENTS 4.3. 2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECX, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2-1.

4.3. 2. 2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic ~bperation of all channels shall be performed at least once per 18 months and shall include calibration of time delay relays and timers necessary for proper functioning of the trip system.

)

1f both channels are inoperable in one trip system, select at least one inoperable channel in that trip system to place in the tripped condition, except when this would cause the Trip Function to occur.

SRUNSWICK-UNIT 1 3/4 3-9 AmendmentNo./(,33

~

JUN 11 E80

INSTRUMENTATION SURVIII. LANCE REOUIREMENTS (Continued) 4.3.2.3 The ISOLATICN SYSTEM RESPONSE TIME of each isolation function shown in Table 3.3.2-3 shall be demonstrated to be within its limit at least.once per 18 months

Each test shall include at least one logic l

train such that both logic chains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific isolation Yunction.

p.

for the performance of this surveillance on item 1-e of Table 3.3.2-3, scheduled to be completed by February 6, 1981, a onetime-only exe=otion is allowed to extend this surveillance until "before the completion of the Spring 1981 outage." scheduled to co=mence in March, 1981.

l 3RUNSWICX-UN,IT 1 3/4 3-10

-Aniendment No. 33 l

i

TABLE 4.3.2-1 (Continued) h ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5E CHANNEL OPERATIONAL Q

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WI;H TRIP FUNCTION AND INSTRlMENT NUMBER CHECK TEST CALIBRATION SURVEILLANCE REQ:ARED 5

]

5.

SiluTDOWN COOLING SYSTEM ISOLATION a.

Reactor Vessel Water - Low, Level #1 (B21-LIS-N017A,B,C,D)

D M

R 1, 2, 3 l

b.

Reactor Steam Dome Pressure -

High (832-PS-N018A,8)

NA S/U*,M R

1, 2, 3 t.'

\\*

0!

If not perfonned within the previous 31 days.

A a

I

=

N 2:

w

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INSTRUMENTATION 3/4.3.3 EMERGENCY' CORE COOLING SiSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3 The Emergency Core Cooling System (ECCS) actuation instrumentation shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the THp 5etooint column of Table 3.3.3-2 and with EMERGENCY CORE COOLING SYSTEM RESPONSE TIME as shown in Table 3.3.3-3.

APPLICABILITY: As shown in Table 3.3.3-1.

ACTION:

With an ECCS actuation in~strumentation ch'annel tMp setpoint a.

less conservative than the value shown in the Allewable Values column of Table 3.3.3-2, declare the channel inoperable and place the inoperable channel in the tripped condition until the c5annel is restored to OPERA 5LE status with its trip setpoint adjustad consistent with the Trip 5etpoint value.

b.

With one or more ICCS actuation instrumentation channels l

inoperable, take the ACTION required by Table 3.3.3-1.

c.

The provisions of Specification 3.0.3 are not applicable in OPERATIONAL CCHDITION 5.

SURVEILLANCE REOUIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the perior.tance of the CHANNEL CHECK. CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.3-1.

4.3.3.2 LOGIC SYSTEM FUNCTIONAL TE5TS and simulated automatic coeration of all channels shall be parformed at least once per 18 months and shall include calibration of time' delay relays and timers necassary for proper functioning of the trip system.

4.3.3.3 The ECCS RESP 0';5E TIME of each ECC5 f nction shown in Table 3.3.3-3*shall be demonstrated to be within the limit at lear.: once per l

18 months.

Each test shall include 1.t least one logic train such that both logic. trains are tested at least once peir 36 months and one channel per fune: ion such that all channels are tested at least once every N times 1E months where N is the total nu=cer of redundant channeis in a specific ECCS function.

For the ECCS response ti:ue test fo: Items 1 and 2 of Table 3.3.3-3 scheduled for completion by February 21, 1031, and February 19, 1981, respectively, a onecime-only exemption is allowud to extend this test until "before the com-pletion of the Spring 1981 outa ge," scheduled to commence in March,1981.

BRUNSWICK - UNIT 1 3/4 3-30 Amendment No. 33

TABLE 4.3.3-1

.:=

b N

lillitGlilCY CORE COOLING SYSTfH ACIUATION INSTRUMENTATION SURVEILl ANCE hE90'IRtHEN 9

CilANNEL OPERAT10NAL s

CllANNEL, FUNCTIONAL CllANNEL CONDITIONS IN WillCil 5

IHIP ftlllCiloft AND INSTRUNEllT NUMBER CllECK TEST cat lilitATION SUHVEILLANCE REQUIRED U

l r

1.

C0llE SPRAY SYSTEM a.

Reactor Vessel Water Level - Low,

' Level #3 (821-LIS-N031A,B,C,D)

D H

8 h.

Heactor Steam Dome. Pressure -

1,2,3,4,5 Low (ll21-PS-fl021 A,0,C,0)

HA H

Q 1,2,3,4,5 Drywell Pressure - liigh NA H

q 1, 2, 3 c.

(Ell-PS-N0llA,0 C.D) d.

lime llelay llelay NA R

R 1,2,3,4,5 e.

Bus Power Monitor (E21-KIA,B)

HA R

NA 1,2.3,4,5 2.

LPCI 11000 0F 111111 SYSTEM d,

Drywell Pressure - liigh NA H

Q 1, 2, 3 a.

( El l-PS-Ho l l A,0.C,II) h.

Iteactor Vessel ~ Water level - Low, Level #3 (021-LIS-NO3]A.D.C.D)

D H

R I, 2, 3, 4*, 5*

c.

Reactor Vessel Shroud Level NA H

Q 1, 2, 3, 4 *, 5*

Il21-LIIS-NO36and021-LITS-NO37) d.

Iteactor Steam Dome Pressure -

Low (821-PS-N021A,8,C,D) 1.

ltll11 Pump Start and LPCI Injection Valve Actuation NA H

Q 1, 2, 3, 4 *, 5*

2.

Itecirculation Loop Pump Discharge Valve Actuation HA H

Q 1, 2, 3, 4*,'5*

Illitt Pump Start-Time Delay Helay NA 11 R

1, 2, 3, 4*, 5*

e.

f.

Ilus Power Honitor (Ell-K106A DJ NA R**

NA 1, 2, 3, 4*, 5*

l 5

t f

llot appilEilile when two core spray system subsystems are OPERABLE per Specification 3.5.3.1.

- For the channel functional test scheduled to be completed by February 25, 1981, a onetime-only m"

9xemption is allowed to extend this test. until "before the completion of the Spring 1981 outage,

l scheduled to commence in March, 1981.

i

-..-......-.........t..

TABLE 4.3.3-1(Continued [

itKHr[NCY CORE COOLING SYSTEM AcluATION INSTHHH[NIATION SHHV[Itt ANCC it[quiltiH[N15

'?

I C MNNEL OPERAliONAL CilANNEL FUNCTIONAL CilANNEL CONDITIONS IN lallCH

'I IHIP_ lilNCI10N ANil INSTRUMENT InlHutR' CllECK 1L51 CALIBRAll0N SultVEILLANCE NEglillit.fi

,c:}

3.

IIPCI SYSTIM a.

Heactor Vessel Water Level - Low I.evel #2 (021-LIS-NO31A,8,C,0) 0 M

R 1, 2, 3 l

h.

lirywell Pressure-liigh NA H

q 1, 2, 3 (Ell-PS-N011A,B,C,0) c.

Condensate Storage Tank Level -

1.ow (E41-LS-N002. E41-LS-N003) NA N

Q 1, 2, 3 d.

Suppression Chamber Water Level -

Illgh (E41-LSil-N015A,8)

NA N

Q 1, 2, 3 liusPowerHonitor(E41-KS5and NA R

NA 1, 2, 3 c.

E41-KS6) s

. '.. 4-

^HE M

a.

Drywell Pressure-High NA H

Q 1, 2, 3 i

(Ell-PS-N010A,0.C,0) b.

Heactor Vessel Water Level - Low, tevel #3 (D21-LIS-NO31A B 0

11 R

1, 2, 3 l

Alis limer (821-10PU-KSA,8f,C,0) c.

NA R

R

1. I, 3 d.

Core Spray Pump Olscharge ff Pressure - liigh NA H

Q 1, 2, 3 (E21-PS-N@8A,B and E21-PS-N009A,8)

I 5

11 iiiiii (tPCi H00E3 Po g. Discharge e.

B Pressure - High NA N

Q 1, 2, 3 (Ell-PS-N016A,8,C,0 and Ell-PS-N020A.8,C,0) a 5.*

'- ""' "*""' "*"'**' ('*'-"'^

M

t l

1

^

i r

3 l

TAllLE 4.3.5.2-1 j'l It[MOIE SilulDOWN MONITORING INSTRUMENIATION SURVEILt ANCE REQlilRlHLN1S_

(5, 1

CilANNEL CilANNEL Q

l ullC110llAL UNIT Allo filSTRilMENT NUHil[R CilECK cal.lDRAll0N 25 1.

Iteactor Vessel Pressure M

]

(C32-PI-3332 and C32-PT-3332)

Q 2.

Iteactor Vessel Water Level M

Q (ll21 -L I -3331, il21 -L 1 -R604AX, H21 -LT -3331, 1121-LT-fiO26A,1121-LT-N0170-3 and fl21 -L Sil-N0170-3) 3.

Suppression Chamber Water Level M

R (CAC-l.]-3342 and CAC-LT-3342) 4.

Suppression Chamber Water Temperature M

R*

1 (CAC-Ill- / 711-/ )

Drywell' Pressure (CAC-PI-3341 and CAC-PI-3341)

M Q

I 6.

Drywell Temperature (CAC-TR-778-1,3,4)

M g.

l 7.

lirywell oxygen Concentration (CAC-AT-1259-2)

H Q

11. Itesidual lleat ite.:' oval llead Spray flow (Lll-fi-3339 and Ell-fi-3339)

H Q

9.

Ilesidual lleat Removal System flow p

,9 (Lil-fi,333fl Ellef t-333fl and Ell-fY-3338)

H Q

3 Q

10.

Residual lleat llemoval Service Water Discharge H

Q llifferenttal Pressure (Ell PDi-N002ilX and L11-PDI-3344) w

For verifying this channel calibration scheduled for completion by February 14, 1981, a onetime-only exesnption is allowed to extend this calibration until "before the completion of the Spring 1981 outage," scheduled to conunence in March, 1981.

d^'

INSTRUMENTATION POST-ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.5.3 The post-accident monitoring instrumentation channels shown in Table 3.3.5.3-1 shall be OPERABLE.

APPLICABILITY: CONDITIONS 1 and 2.

ACTION:

With the number of OPERABLE post-accident monitoring channels a.

less than required by Table 3.3.5.3-1, either restore the inoperable channels to OPERABLE status within 31 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.5.3 Each of the above required post-accident monitoring instru-mentation channels shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.5.3-1.

I BRUNSWICK-UNIT 1 3/4 3-50 Amendment No. 33

EMERGENCY CORE COOLING SYSTEMS LOW PRESSURE COOLANT INJECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.5.3.2 Two independent Low Pressure Coolant Injection (LPCI) sub-systems of the residual heat removal system shall be OPERABLE with each subsystem comprised of:

a.

Two pumps, I

b.

An OPERABLE flow path capable of taking suction from the suppression pool and transferring the water to the reactor pressure vessel.

I APPLICABILITY: CONDITIONS 1, 2, 3, 4* and 5*.

ACTION:

a.

In CONDITION 1, 2 or 3; 1.

With one LPCI subsystem or one LPCI pump inoperable.

POWER OPERATION may continue provided both CSS subsystems l

are OPERABLE; restore the inoperable LPCI subsystem or pump to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the folicwing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

With both LPCI subsystems inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.

With the LPCI system cross-tie valve open or power not removed from the valve operator, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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4.

In the event the ECCS is actuated and injects water into j

the Reactor Coolant System, a Special Report shall be

[

prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the cir-cumstances of the actuation and the total accumulated actuation cycles to date.

b.

In CONDITION 4* or 5* with one or more L?CI subsystems inoper-able, take the ACTION required by Specification 3.5.3.1.

The provisions of Specification 3.0.3 are not applicable.

J

~

Not applicable when two CSS subsystems are OPERABLE per Specification 3.5.3.1.

BRUNSWICX - UNIT l 3/45-7 Amendment No. 33

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOUIREMENTS 4.5.3.2 Each LPCI subsystem shall be demonstrated OPERABLE:

At least once per 31 days by:

a.

1.

Verif' ing that the system piping from the pump discharge y

valve to the system isolation valve is fiTled with water, 2.

Verifying)that each valve (manual, power operated or automatic in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position, and 3.

Verifying that the subsystem cross-tie valve is closed with power removed from the valve operator.

b.

At least once per 92 days by verifying each pair of LPCI pumps discharging to a com "1 header can be started from the control room and develops a tu al flow of at least 17,000 gpm against a ystem head corresponding to a reactor vessel pressure of

,> 20 psig.

At least once per 18 months *by performing a system functional l

c.

test which includes simulated automatic actuation of the system throughout its emergency operating sequence and verify-ing that each automatic valve in the flow path actuates to its correct position. Actual injection of coolant into the reactor vessel is excijded from this test.

For the performance of this system functional test scheduled to be completed by February 25, 1981, a onetime-only exemption is allowed to extend this test until "before the completion of the Spring 1981 outage," scheduled to commence in March, 1981.

1 BRUNSWICK - UNIT 1 3/4 5-8 Amendment No. 33

^

CONTAINMENT SYSTEMS SURVEILLANCE RE0VIREMENTS 4.6.3.1 Each primary containment isolation valve specified in Table 3.6.3-1 shall be demonstrated OPERABLE prior to returning the valve to service af ter maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by per-formance of the cycling test, and verification of isolation time.

4.6.3.2 Each isolation valve specified in Table 3.6.3-1 shall be demonstrated OPERABLE during COLD SHUTDOWN or REFUELING at least once per 18 months *by verifying that on a containment isolation test, signal

(

each isolation valve actuates to its isolation position.

4.6.3.3 The isolation time of each power operated or automatic valve specified in Table 3.6.3-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

4.6.3.4 Each reactor instrumentation system isolation valve shall be demonstrated OPERABLE at least once per 18 months by cycling each valve through at least one. ccmplete cycle of full travel.

For the performance of this surveillance scheduled to be complaced by February 25, 1981, a onetime-only exemption is allowed to exter.1 i

this surveillance until "before the completion of the Spring 1981 outage," scheduled to commence in March, 1981.

BRUNSWICK - UNIT I 3/4 6-13 Amen 6nent No. 33

_ o.

TABLE 3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES w

EE ISOLATION TIME gj VALVE FUNCTION VALVE GROUP 1/

(Seconds)

Main steamline isolation valves 1

3<t<5 B21-f022 A, B, C, D

~

Ej B21-f028 A, B, C, D

-i Main steamline drain isolation valves 1

30 B21-f016 B21-f019 Reactor Water sampie line isolation valves 1

5 B32-f019 832-f020 Drywell equipment drain discharge isolation valves 2

20 w

1:

G16-f019 G16-f020 o,

L" Drywell floor drain discharge isolation valves 2-20 G16-f003 G16-f004 TIP guide tube (Ball valve) 2 2

Reactor water cleanup system isolation valves 3*

35 G31-f001 9

G31-f004 E

l.

See SpecTfTcation 3.3.2.

Table 3.3.2-1 for isolation signal that operates each valve group.

w

Inboard isolation valve does not close on standby liquid control system initiation or reactor water cleanup system high temperature.

~

CONTAINMENT SYSTEMS SURVEILLANCE RECUIREMENTS 4.6.4.1 Each drywell-suppression pool vacuum breaker shall be demon-strated OPERABLE:

At least once per 31 days and after any discharge of steam to a.

the suppression pool frem any source, by exercising each vacuum breaker through one complete cycle and verifying that each vacuum breaker is closed as indicated by the position indication system.

a b.

Whenever a vacuum breaker is in the open position, as indi-cated by the position ine;fcation system, by conducting a test that verifies that the r.ifferential pressure is maintained >

l/2 the initial af for one hour without N makeup.

2 At least once per la months during shutdown by; c.

1.*

Verifying the opening setpoint, frem the closed pcsition, to be 5,0.5 psid, 2.*

Performance o' a CHANNEL CALIBRATION that each position

(

indicator indicates the vacuum breaker to be open if the vacuum breaker does not satisfy the AP test in 4.6.4.1.b, s

and 3.

Conducting a leak test at an initial differential cressure of 1 psig and verifying that the differential pressure coes not cecrease by more than 0.25 inches of water per minute for a 10 minute period.

For the verifying of the opening setpoint and the performance of the channel calibration scheduled for completion by January 31, 1981, a onetime-only exemption is allowed to extend these inspections until "before the completion of the Spring 1981 outage," scheduled to commence in March, 1981.

I E

EEUN3'.:ICK - UNIT 1 3/4 6-1g Amendment No. 33

i 1

CONTAINMENT SY3TEMS SUPPRESSION POOL - REACTOR BUILDING VACUUM BREAKERS LIMITING CONDITION FOR OPERATION All suppression pool-Reactor Building vacuum breakers shall be l

3.6.4.2 OPERABLE with an opening setpoint of 1 0.5 psid.

APPLICABILITY: CONDITIONS 1, 2 and 3.

ACTION:

With one suppression pool - Reactor Building vacuum breaker inop?rable for opening but known to be in the closed position, restore the inoperable vacuum breaker to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and. in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS Each suppression pool-Reactor Building vacuum breaker shall be 4.5.4.2 demonstrated OPERABLE:

At least once per 92 days by:

a.

1.

Manually verifying that each vacuum breaker check valve is free to open, and 2.

Cycling each vacuum breaker butterfly valve through at least one complete cycle of full travel.

b.

At least once per 18 months by:

1.

Demonstrating that the force required to c:en each vacuum f

breaker check valve does not exceed 0.5 psid.

l I

Demonstrating that tne vacuum breaker butterfly valve 2.

l opens at-0.051 0.05 : sic, crywell pressure going negative relative to Reactor Buiicing pressure.

l

'l 3.

Visual inspection.

1 Arendrient No. 76, if,33

?..;I..:0:

UNIT 1 3/4 6-20 e

i CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.5.2 Each seconda.ry containment automtic isolation damper specified in Table 3.6.5.2-1 shall be demonstrated OPERABLE:

a.

At least cnce per 92 days by cycling each automatic isolation damper testable during plant operation through at least one complete cycle of full travel.

b.

Prior to returning the damper to service after maintenance, repair or replacement work is, performed on the damper or its associated actuator, control or power circuit by performance of the cycling test and verification of isolation time.

c.

At least once per 18 months during COLD SHUTDOWN or REFUELING by:

1.

Cycling each automatic damper through at least one complete cycle of full travel and measuring the isolation time, and 2.*

Verifying that on a secondary containment isolation test signal each automatic damper actuates to its isolation position.

For this verification scheduled to be completed by February 25, 1981, a onetime-only exemption is allowed to extend this verification until "before the completion of the Spring 1981 outage," scheduled to commence in March, 1981.

BRUNSWICK - UNIT 1 3/4 6-23 Amendment No. 33

l l

TABLE 3.6.5.2-1 SECONDARY CONTAINMENT AUTOMATIC ISOLATION DAMPERS ISOLATION TIME DAMPER FUNCTION (Seconds) v 1

Reactor Building Ventilation 4

[

Supply Isolation Dampers e

2.

Reactor Building Ventilation 4

Exhaust Isolation Dampers i

I BRUNSWICK - UNIT 1 3/46-2 Amendment No. 33 l

i

g@

AJds oOkjkhQ i

CONTAINMENT SYS*EwS 3/4.6.6 CONTAIM ENT ATMOSPHERE 'ONTROI.

STANDBY GAS TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.6.6.1 Two independent Standby Gas Treatment Systan subsystems shall be OPERABL I

APPLICABILITY: CONDITIONS 1, 2, 3, 5 and *.

1 t

ACTION:

{

a.

With one standby gas treat:nent subsystem inoperable:

l.

In CONDITION 1, 2 or 3, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN i

within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

In CONDITION 5 or *, restore the inoperable subsystem to OPERABLE status within 31 days or suspend irradiated fuel handling in the secondary containment, CORE ALTERATIONS or operations that could reduce the SHUTDOWN MARGIN. The pro-visions of Specification 3.0.3 are not applicable.

b.

With both standby gas treatment subsystans inoperable; 1.

In CONDITION 1, 2 or 3 be in at least HOT SHUTDOWN within 12 '.

hours and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

In CONDITION 5 or *, suspend all irradiated fuel handling in the secondary containment, CORE ALTERATIONS or operations that I

could reduce the SHUTDOWN MARGIN. The provisions of Specifica-l tion 3.0.3 are not applicable.

SURVEILLANCE REQUIRENENTS i

h 4.S.6.1 Each standby gas treat:nent subsystem shall be de:nstrated I

OPERABLE:

1.

1: lets: Once per 31 cays by initiating, fr = the ::ntr:1 c:::, fi w thr ugh the HEPA filters and char:::: adscrbers and i

verifying :na: the systs o:erates for at leas: 10 h urs with

,e hea:ers en aut::.at c c:ntr:1.

i v en :- a: a:e: fuel is being na'iclec in the secencary centainment, v". ;

3/4 i-25 Amendment No. 33

CONTAINMENT SYSTEMS 1

SURVEILLANCE REGUIREMENTS (Continuedi b.

At least once per 18 months or (1) after any structural main-tenance on the HEFA filter or char: cal adsorber housings, or

(,2) following painting, fire or chemical release in any venti-lation zone comunicating with the system by:

1.

Verifying that the cleanuo system satisfies the in-clace testing acceptanca critaria and uses the test procedures of Regulatory Positions C.5.a., C.5.c and C.5.d of Regula-tory Guide 1.52, Revision 1, July 1975, and the system flow rata is 3000 cfm + 10"..

2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon samole obtained in accordance with Regula:crj Position C.S.b of Regulatory Guide 1.52, Revision 1, July 1975, meets the laboratory tasting criteria of Regulatory Position C.S.a of Regula-tory Guide 1.52, Revision 1, July 1975.

3.

Verifying a systam flow rata of 2000 cQ 1C% during system oceration when testad in accordanca with ANSI N510-1975.

Aftar every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorter operation by c.

verifying within~ 31 days after removal that a laforatory analysis of representative carton samcle obtained in accord-anca with Regulator / P sition C.5.b of Regulatory Guide 1.53, Revision 1, July 1975, meets the laboratory tasting crdtarit of Regulatory Position C.5.a of Regulatory Guica 1.52, Revision 1, July 1975.

d.

At least onca'per 18 months Sy:

1, Verifying that the pressure drcp across the combined HE?A filtars and charcoal adsorter banks is < 8.5 inches Water Gauge while operating the ftltar train at a flow rata of 30C0 cfm _ 10%.

2.

Verifying t5a: the filter train starts on each secondary l

containmen; isciation tes: signal.

3.

Verifying :ha: :he heaters will oissica:a a-leas: 15.2 kw when :sstad in accercance si:n ANSI.N510-1E75.

l

For the performance of this surveillance scheduled to be completed by February 25, 1981, a onetime-only exemption is allowed to extend this

. surveillance until "before the completion of the Spring 1981 outage,"

scheduled to cousnence in March, 1981.

BRUNSVICK - UNIT 1 3/4 6-26 Amendment No. 33

J l

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i e.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove > 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 3000 cfm + 10%

f.

After each complete or partial replacement of a charcoal adsorber ank by verifying that the charcoal adsorbers remove 1 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 3000 cfm + 10%.

\\

1 i

I SRUNSWICK - UNIT l 3/4 6 27 Amendment No. 33 i

4

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

a.

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

A minimum supply of 4350 gallons of liquid nitrogen.

APPLICABILITY:

CONDITION 1*.

A_CTION:

With the CAD system inoperable, restore the CAD system to OPERABLE

' status witnin 31 days or be in 'at least STGTUP within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . The provisions of Specificatier. 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS l

4.6.6.2 The CAD system shall be demonstrated to be OPERABLE; a.

At least once per 31 days by verifying that:

1.

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

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

At least once per 18 :nonths by:

1.

Cycling each power operatet 2xcluding automatic) valve in the flow path not testable during plant operation through at least one complete cycle of full travel, and 2.** Verifying that each automatic valve in the flow path l

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

xygen concentration is required to be < 4%,er Scecification

- For the performance of this surveillance scheduled to be completed by I

25, 1981, a onetime-only exemption is allowed to extend this February surveilknee until "before the completion of the Spring 1901 outage,"

scheduled to commence in March, 1981.

3RUNSWICK - UNIT 1 3/4 6 28 Amendment No. 33

PLANT SY57 EMS 3/4.7.5 HYDRAULIC SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.5 All hydraulic snubbers shown in ~able 3.7.5-1 shall be OPERABLE.

APPLICABILITY: CONDITIONS 1, 2 and 3 ACTION:

With one or more hydraulic anubbers inoperable, restore the inoperable snubber (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at las:st HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , u

SURVEILLANCE REQUIREMENTS

,,)

.p-4.7.5.1 Hydraulic snubbers shown in Table 3.7.5-1 shall be demonstrated g

OPERABLE by the performance of the following augmented inservice inspec-tion program and the requirements of Specification 4.0.5.

4.7.5.2 Each hydraulic snubber with seal material fabricated from ethylene propylene or other materials demonstrated compatible with the operating environment and approved as such by the NRC, shall be deter-mined OPERABLE at least once after not less than 4 months but within 6 months of initial criticality and in accordance with the inspection schedule of Table 4.7.5-1 thereafter, by a visual inspection of the snubber. Visual inspections of the snubbers shall include, but are not necessa, ily limited to, inspection of the hydraulic fluid reservoirs, fluid connections, and linkage connections to the piping and anchors.

Initiation of the Table 4.7.5-1 inspection schedule shall be made assuming the unit was previously at the 6 month inspecti_on interval.

~ " ~

4.7.5.3 Each hydraulic snubber with seal material not fabric 3ted from ethylene propylene or other materials demopstrated compatif sith the

)

operating environment shall be determined OPERABLE at least once per 31 days by a visual inspection of the snubber. Visual inspections of the snubbers shall include, but are not necessarily limited to, inspection i

of the hydraulic fluid reservoirs, fluid connections, and linkage connections to the piping and anchors.

BRUNSWICK - UNIT 1 3/4 7-9 Amendment No. 33 i

p PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.7.5.4 At least once ner 18 months *during shutdown, a representative sample of at least '^.nubbers or at least 10% of all snubbers listed in Table 3.7.5-1, whD.ever is less, shall be selected and functionally tested to verif;,orrect piston movement, lock up and bleed. Snubbers greater than 50,000 pound capacity may be excluded from functional test-ing requirements. Snubbers selected for functional testing shall be selected on a rotating basis except snubbers identified in Table 3.7.5-1 as either "Especially Difficult to Remove" or'in "High Radiation Zones" may be exempted from functional testing provided these snubbers were demonstrated OPERABLE during previous functional tests. Snubbers found inoperable during functional testing shall be restored to OPERABLE status price to resuming operation.

For each snubber found inoperable during these functional tests, an additional minimum of 10% of all snubbers or 10 snubbers, whichever is less, shall also be functionally tested until no more failures are found or all snubbers have been functionally tested, I

l l

For the inaccessible snubber functional inspection interval s'cheduled to end December 30, 1980, a onetime-only exe=ption is allowed to extend this inspection interval until "before the completion of the Spring 1981 outage," scheduled to commence in March, 1981.

BRUNSWICK - UNIT I 3/4 7-10 Amendment No. 33

ELECTRfCAL POWER SYSTEMS

. SURVEILLANCE REQUIREMENTS (Continued) 2.

Verifying the fuel level in the day fuel tank, 3.

Verifying the fuel transfer pump can be started and trans-fers fuel from the day tank to the engine mounted tank, 4

Verifying the diesel starts from ambient condition and accelerates to at least 514 rpm in 1 10 seconds, 5.

Verifying the generator is synchronized, loaded to L 1750 kw, and operates for 1 15 minutes, and 6.

Verifying the diesel generator is aligned to provide stanc'by cower to the associated emergency buses.

b.

At least once per 31 days by verifying the fuel leel in the plant fuel storage tank.

c.

At least once per 92 days by verifying that a sample of diesel fuel from'the fuel storage tank, obtained in* accordance with ASTM-0270-65, is within the acceptable limits specified in Table 1 of ASTM-0975-74 when checked for viscosity, water and

sediment, d.

At least once per 18 months during shutdown byi 1.

Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service, 2.* Verifying the generator capability to reject a load equal l

to one core spray pump without tripping, 3.* Simulating a loss of offsite power in conjunction with an l

emergency core cooling system test signal, and:

a)

Verifying de-energization of the emergency buses and load shedding from the emergency buses.

b)

Verifying the diesel starts from ambient condition on the auto-start signal, energizes the emergency buses with permanently connected loads, energizes the auto-connected loads through the load sequence relays and operates for 1 5 minutes while its generator is loaded with the emergency loads.

lor the verification of this iten' scheduled for completion by February 20, 1981, a onetime-only exemption is allowed to extend this inspection until "before the completion of the Spring 1981 outage," scheduled to co=mence in March, 1981.

BRUNSWICK - UNIT 1 3/4 8-3 Amendment No. 33

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4 Verifying that on the emergency core cooling system test signal, all diesel generator trips except engine over-speed, generator differential, low lube oil pressure, reverse power, loss of field and phase overcurrent with voltage restraint, are automatically bypassed.

5.

Verifying the diesel generator operates for > 60 minutes while loaded to > 3500 kw.

~

6.*

Veri fying-that tha auto-connected loads to each diesel generator do not exceed the 2000 hour0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months rating of 3850 kw.

7.*

Verifying that the automatic load Sequence relays are l

OPERABLE with each load sequence time within 10% of the required value.

l s

a

For the verification of this item scheduled for completion February 20, 1981, a onetime-only exemption is allowed to extend this inspection until "before I

the completion of the Spring 1981 outage," scheduled to commence in March, 1981.

1 BRUNSWICK - UNIT 1 3/4 8-4 Amendment No. 33

ELECTRICAL POWER SYSTEMS

~

SURVEILLANCE REOUIREMENTS (Continued) 4.8.2.3.2 Each 125-volt battery and charger shall be demonstrated OPERABLE:

i At least once per 7 days by verifying that:

a.

1.

The electrolyte level of each pilot cell is between the minimum and maximum level indication marks, 2.

The pilot cell specific gravity, corrected to 77'F, is 3.1.18, 3.

The pilot cell voltage is 3,2.0 vol'ts, and 4

The overall battery voltage is 3,120 volts.

b.

At least once per 92 days by verifying that:

1.

The voltage of each connected cell is 3,2.0 volts under ficat charge and has not decreased more than 0.3 volts from the value observed during the original acceptance

test, 2.

The specific gravity, corrected to 77'F, of each connected cell is > 1.18 and has not decreased more than 0.04 from the value observed during the previous test, and 3.

The electrolyte level of each connected cell is between the minimum and maximum level indication marks.

At least once per 18 months by verifying that:

c.

1.*

The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, 2.

The cell-to-cell and terminal connections are clean, tight, free of abnormal corrorion and coated with. anti-corrosion material, and 3.*

The battery charger will supply at seast 250 imperes at a l

minimum of 135 volts far a? least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

For the verification of this item scheduled for completion by February 23, 1981, a onetime-only exemption is allowed to extend 'this inspection until "before the completion of the Spring 1981 outage," scheduled to commence I

in March, 1981.

i l

3RUNSWICK - UNIT 1 3/4 8-9 Amendment No. 33 c-

l ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.

At least once per 18 months, during shutdown, by. verifying i

that either:

1 1.

The battery capacity is 4dequate to supply and maintain l

in OPERABLE status all of the actual emergency loads for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the battery is subjected to a battery service test, or l

2.

The battery capacity is adequate to supply a' duniny load l

l of the following profile while maintaining the battery terminal voltage > 105 volts.

a)

During the initial 60 seconds of the test; l)

Battery 1A-1 > 1042.'42 amperes, 2)

Battery lA-2 s 1211.90 amperes, 3)

Bactery 18-1 s 1089.06 amperes, and 4)

Battery 18-2 E 1028.67 amperes.

b)

During the remainder of the first 30 minutes of the test; 1)

Battery l A-1 >

amperes, Battery 1A-2 >_ 229.19 2) 159.10 amperes, 3)

Battery 18-1 > 176.79 amperes, and 4)

Battery 18-2 E 202.67 amperes.

s c)

During the remainder of the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months test; 1)

Battery lA-1 > 75.52 amperes, 2)

Battery lA-2 7 50.34 amperes, 3)

Battery 18-1 7 53.39 amperes, and 4)

Battery 18-2[6!go amperes.

3.*

At the completion of either of the above tests, the battery l

charger shall be demonstrated capable of recharging its battery at a rate of at least 200 amperes while supplying l

normal D.C. loads. The battery shall be charged to at l

least 95% capacity in < 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

At least once per 60 months during shutdown by verifying that e.

the battery capacity it least 80% of the manufac.turer's rating when subjected

, a cerformance discharge test. This performance discharge cest shall be perfonned subsequent to the satisfactory completion of the required battery service test and after normal equalizer charge.

For the verification of this item scheduled for completion by February 23, l

1981, a onetime-only exemption is allowed to extend this inspection until "before the completion of the Spring 1981 outage," scheduled to commence in March, 1981.

BRUNSWICK - UNIT 1 3/4 8-10 Amendment No. 33

'o UNITED STATES

g E $ 5.. (

g NUCLEAR REGULATORY COMMISSION 2

wasmuoTom. o. c. 20sss 4,

CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 54 License No. DPR-62 1.

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

A.

The application for amendment by Carolina Power & Light Company dated November 5,1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.

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

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

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

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

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

DPR-62 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

. 3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Thomas A. Ippolito, Chief Operating Reactors Branch 02 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: December 23, 1980 1

ATTACHMENT TO LICENSE AMENDMENT NO. 54 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Remove the following pages and replace with identically numbered pages 3/4 8-3 / 3/4 8-4 W

,w r

El.ECTRICAL POWER SYSTEMS

~"

SURVEILLANCE REQUIREMENTS (Continued) 2.

Verifying the fuel level in tfie day fuel tank.

3.

Verifying the fuel tre.ufer pump can be started and transfers fuel from the day tank to the engine mounted

tank, 4

Verifying the diesel starts from am6ient condition and accelerates to at least 514 rpm in < 10 seconds, 5.

Verifying the generator is synchronized, loaded to > 1750 kw, and operates for > 15 minutes, and 6.

Verifying the diesel generator is aligned to provide standby power to the associated emergency buses.

b.

At least once per 31 days by verifying the fuel level in the plant fuel storage tank, At least once per 92 days by verifying that a sample of diesel c.

fuel from the fuel storage tank, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM 0975-74 when checked for viscosity, water and

sediment, d.

At least once ger 18 months during shutdown by:

s 1.

Subjecting the diesel to an inspection in accordance with procedures prepared in. conjunction with its manufacturer's recommendations for this class of standby service.

2.

Verifying the generator capability to reject a load equal to one core spray pump without tripping.

3.

Simulating a loss of offsite power in conjunction with an emergency core cooling system test signal, and:

a)

Verifying de-energization of the emergency buses and load shedding from the emergency buses.

b)* Verifying the diesel starts from ambient condition l

on the auto-start signal, energizes the emergency buses with permanently connected loads, energizes the auto-connected loads through the load secuence relays and operates for > 5 minutes while its generator is loaded with the emergency loads.

For the verification of this item scheduled for completion by February 23, 1981, a onetime-only exemption is allowed to extend this inspection until "before the completion of the Spring 1981 outage," scheduled to commence in March, 1981.

BRUNSWICK - UNIT 2 3/4 8-3 Amendment No. 54

ELECTRICAL POWER SYSTEMS SURVEILLANCE' REQUIREMENTS (Continued) 4 Verifying that on the emergency core cooling system test signal, all diesel generator trips except engine over-speed, generator differential, low lube oil pressure, reverse power, loss of field and phase overcurrent with voltage restraint, are automatically bypassed.

5.

Verifying the diesel generator operates for > 60 minutes while loaded to 3,3500 kw.

' Verifying that the auto-connected loads to each diesel 6.

generator do not exceed the 2000 hour0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months ratihg of 3850 kw.

7.*

Verifying that the automatic load sequence relays are OPERABLE with each load sequence time within 10% of the required value.

For the verification of this item scheddled for completion by February 23, 1981, a onetime-only exemption is allowed to extend this inspection until "before the i

completion of the Spring 1981 outage," scheduled to commence in March, 1981.

l BRUNSWICX - UNIT 2 3/4 8-4 Amendment No. Sa

-.

ML20002D598

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