Text

Proposed Changes to Tech Specs Sections 3.0 & 4.0,providing one-time Extensions for Performing Insps,Surveillances & Tests to Electrical Power Sys,Reactivity Control Sys,Eccs & Instrumentation
	ML19340C046
Person / Time
Site:	Brunswick
Issue date:	11/05/1980
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML19340C045	List: ML19340C044; ML19340C046;
References
	NUDOCS 8011130230
	Download: ML19340C046 (20)
	v • d • e

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ELECTRICAL p0WER SYSTEMS Q .

SURVEILLAf1CE REQUIREMEf1TS (Continued)

2. Verifying the fue1 level in the day fuel tank,

3. Verifying the fuel transfer pump can be started and transfers fuel from the day tank to the engine mounted tank, 4

Verifying the diesel starts from ambient condition and j 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.

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-D270-65, is within the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water and sediment,

d. At least once per 18 months during shutdown by:

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1. Subjecting the diesel to an inspection in accordance with procedures prepa_ red 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 snedding from the emergency buses.

b)* Verifying the diesel starts from ambient condition on the auto-start signal, energizes the emergency l buses with permanently connected loads, energizes the auto-connected loads through the load sequence 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, 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.

I BRUNSWICK - UNIT 2 3/4 8-3 i

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ELECTRfCAL POWER SYSTEMS ,

SURVEILLANCE REQUIREMENTS (Continued) )

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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. Verifying that the 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 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.

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i CFor the verification of this item scheduled for completion by February 23, 1981,.

Ja 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 8-4

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CONTROL ROD SCPAM ACCUMULATORS D O

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LIMITING CONDITICN FOR OPERATION .

3.1.3.5 All control red scram accumulators shall be OPERABLE.

APPLICASILITY: CONDITIONS 1, 2 and 5*. .

ACTION:

a. In CONDITION 1 or 2 witn one control red scram accumulator inocerable, the provtsions of Specification 3.0.4 are not appli-cable and operation may continue, prov,ided 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 red associated with the inoperable accu-mulator is declared inocerable, and the requirements of Specification 3.1.3.1 are satisfied.

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

b. In CONDITION 5* with a withdrawn control rod scram accumulator inoperable, fully insert the affected ' control rod and elec-trically disarm the directional control valves within one hour. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE PEC3JIREIGiTS '.

4 .1. 3 . 5 The control rod scram accumulators shall be deternined CPERABLE:

a. At least once per 7 days by verifying that the pressure and leak detectors are not in the alarmed ccndition, and b.** At least once per 18 month's by performance of a :

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1. CHANNEL FUNCTIONAL TEST of the leak detectors (C11 -LS-129-xxxx ) , a nd

2. CHANNEL CALIBRATION of tne ::ressure detectors -

( Cl l -PS-130 -xxxx ) . -

l *A: isas: tne accumulator associated witn each withdrawn control red.

Not acclicable to control rods removec per Specification 3.9.10.1 or '

.r.10.4.

- For the performance of this surveillance scheduled to be completed by February 10, 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.

BRUNSWICK -' UNIT 1 3/4 1-8

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REACTIVITY CONTROL SYSTEMS SURVEILLANCE REOUIREMENTS 4 .1. 5 The standby liquid centrol system shall be demonstrated OPERABLE:

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

1. The volume and temperature of the 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 deminerilized water to the test tank,

2. Verifying the continuity of the explosive charge, and

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

c. At least once per 18 months during shutdown by; ,

1.* Initiating one of the standby itquid control system l loops, including an explosive valve, and verifying that '

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

Both injection test loops shall be tested in 36 months.

2 .* Demonstrating that the minimum flow requirement of l 41.2 gpm at a pressure of 1190 psig is met.

3. Demor.strating tnat the pump relief valve setcoint is 1400 - 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.

i BRUNSWICK - UNIT 1 3/4 1-19

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INSTRUMENTATION SURVEILLANCE REOUIREMENTS (Continued) ..

4.3.2.3 The ISOLATION 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 35 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 ' function. '

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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 exemption is allowed to extend this surveillance until "before the completion of l

the Spripg 1981 outage," scheduled to commence in March, 1981.

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3RUNSWICK-UNIT 1 3/4 3-10 .

INSTRUMENTATXON_ .

3/A.3.3 EMERGENCY' CORE COOLING S STEM ACTUATf0N KNSTRUMENTATION 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 Trip Setooint 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:

a. With an ECCS actuation instrumentation ch'annel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3-2, declare the channel inoperable and place the inoperable channel in the tripped condition until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b. With one or more ECCS actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.3-1.

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

SURVEILLANCE RE0VIREMENTS ,

4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHAtetEL 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 TESTS and simulated automatic operation

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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.

4.3.3.3 The ECCS RESPON5E TIME of each ECCS function shown in Table i

3.3.3-3*shall be demonstrated to be within the limit at leas: once per l l 18 months. Each test shall include !.t least one logic train such that both logic . trains are tested at least once pe'r 36 months and one channel per function such that all channels are tested at least once every N times lE months where H is the total number of redundant channels in a specific ECCS function.

For the ECCS response time test for Items 1 and 2 of Table 3.3.3-3 scheduled for completion by February 21, 1981, and February 19, 1981, respectively, a onetime-only exemption is allowed to extend this test until "before the com-pletion of the Spring 1981 outage," scheduled to commence in March, 1981.

3/4 3-30 D** *D 9 i

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BRUNSWICK - UNIT 1 wo e J ; J1 a

I w TABLE 4.3.3-1 m

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s El1ERGEllCY CORE C00LiflG SYSTEM ACTUATI0fl IllSTRUMEflTATI0ff SURVEILLAflCE ItEQUIREf fElliS S

i CilAfillEL OPERAT10flAL CliANNEL, FUNCT10flAL CilAliflEL gj C0flDITIOflS Ifl WillCil TRIP fullCTI0ff AllD IllSTRUMEllT flUMBER CllECK TEST CAllBRATI0ff SURVEILLAtlCE REQUIRED 4

~ 1. CORE SPRAY SYSTEM

a. Reactor Vessel Water Level - Low. .

' Level #3 (B21-LIS-tiO31A,B,C,D) D M R 1,2,3,4,5

b. Reactor Steam Dome. Pressure -

Low (021-PS-fl021A,0,C,D) ilA M Q 1,2,3,4,5

, c. Drywell Pressure - liigh NA M Q 1, 2, 3

( El l-PS-fl011 A ,B ,C,D)

d. Time Delay Relay ilA R R 1,2,3,4,5

e. Dus Power Monitor (E21-Kl A,B) NA R ilA 1,2,3,4,5

2. LPCI MODE OF Ri!R SYSTEM

a. Drywell Pressure - liigh NA M Q 1,2,3 (Ell-PS-N0llA,0,C,0)

Reactor Vessel Water level - Low, b.

level #3 (021-LIS-i1031A,B,C.D) D M R 1, 2, 3, 4*, 5*

c. Reactor Vessel Shroud Level NA H Q 1, 2, 3, 4*, 5*

D21-LITS-NO36 and 021-LITS-N037)

d. Reactor Steam Dome Pressure - .

Low (B21-PS-N021A,0,C,D) '

1. RilR Pump Start and LPCI Injection Yalve Actuation NA M Q 1, 2, 3, 4 * , 5 * ,

2. Recirculation Loop Pump .

Discharge Valve Actuation NA M Q 1, 2, 3, 4* , 5*

e. Illin Pump Start-Time Delay Relay NA R R 1, 2, 3, 4 * , 5 *

f. Bus Power Monitor (E11-K106A,0)~ NA R** ilA 1, 2, 3, 4*, 5*

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llot applicable when two cort 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 gxemption is allowed to extend this test until "before the completion of the Spring 1981 outage,"

scheduled to commence in March, 1981. .

r o n TABLE 4.3.5.2-1 h REMOTE SiluTDOWil M0filTORIllG ItlSTRUMEllTATIOff SURVEILLAtlCE REQlllRIMEllTS a

. 'E CilAllNEL CilA!1tlEL p flillCT10llAL UillT AllD lilSTRilMEtiT flVMBER CllEC K CALIBRATI0rl 6 -

E 1. Reactor Vessel Pressure M ~~

Q

] (C32-PI-3332 and C32-PT-3332) 2 Reactor Vessel Water l'evel M Q (021-LI-3331, B21-L1-R604AX , B21-LT-3331,

. 021-LT-N026A, B21-LT-fl0170-3 and 021-LSil-fl0170-3) 3 Suppression Cliamber Water Level M R (CAC-1,1 -3342 and CAC-LT-3342) m 4. Suppression Chamber Water Temperature M R*

i (CAC-TR-778-7) .

6. Drywell' Pressure (CAC-PI-3341 and CAC-PT-3341) M

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Q

6. Drywell Temperature (CAC-TR-778-1,3,4) M g, l

7. Drywell Oxygen Concentration (CAC-AT-1259-2) M Q

8. Residual llent Removal llead Spray flow (F11-FT-3339 and Ell-FI-3339) ,

M Q

,, 9. Residual lleat Removal System flow g (Ell-fT-3338, Ell-FI-3338 and Ell-FY-3338) M Q Q 10. Residual lleat Removal Service Wa,ter Discharge M - Q Di f ferential Pressure (Ell-PDT-Il0020X

-s and Ell-PDI-3344) o - -

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

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

a. At least once per 31 days by:

1. Verifying that the system piping from the pump discharge 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 di.scharging to a common. header can be started from the control room and develops a total flow of at least 17,000 gpm against a system head corresponding to a reactor vessel pressure of

,>,20 psig. '

c. At least once per 18 months *by performing a system functional l test which includes simu'tated 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 excluded 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.

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BRUNSWICK - UNIT 1 3/4 5-8 .

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1 CONTAINMENT SYSTEMS l

SURVEILLA CE REQUIREMENTS l 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 after maintenance, repair or rcplacement 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 l 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 complete cycle of full travel.

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.

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,} BRUNSWICK - UNIT 1 3/4 6-13 1'

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.4.1 Each drywell-suppression pool vacuum breaker shall be demon- ,

strated OPEPABLE:

! a. At least once per 31 days and after any discharge of steam to the suppression pool from any source, by exercising each vacuum breaker through one complete cycle and verifying that each vacuum breaker is closed as indicated by the position I

indication system. .

b. Whenever a vacuum breaker is in the open position, as indi-cated by the position indication system, by conducting a test that verifies that the differential pressure.is maintained >

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

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c. At least once per 18 months during shutdown by; 1.* Verifying the opening setpoint, from the closed position, to be 1 0.5 psid,

2.* Performance of a CHANNEL CALIBRATION that each position (

indicator indicates the vacuum breaker to be open if the s

vacuum breaker does not satisfy the AP test in 4.6.4.1.b, j and

3. Conducting a leak test at an initial differential pressure of 1 psig and verifying that the differential pressure does not decrease 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.

. ERUf:5.-ICK - UNIT 1 3/4 6-19 t

e CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.5.2 Each seconda.ry containment automtic isciation damper specified

. in Table 3.6.5.2-1 shall be demonstrated OPERABLE:

. a. At least once 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 verificatien of isolation time,

c. At least once per 18 months during COLD SHUTOOWN or REFUELING by:

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

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

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For this verification scheduled to be completed by February 25, 1981, ij a onetime-only exemption is allowed to extend this verification until

'a "before the completion of the Spring 1981 outage," scheduled to l commence in March, 1981.

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5 BRUNSWICK - UNIT 1 3/4 6-23 i;

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CONTA!NMENT SYSTEMS SURVEILLANCE REGUIREMENTS (Continued)

b. At least once per la months or (1) after any structural main-tenance on the HEPA filter or charcoal 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-place testing acceptance criteria 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 1976, and the system flow rate is 3000 cfm 1 10%. ,

2. Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 1, July 1976, meets the laboratory testing criteria of Regulatory Position C.6.a of Regula-tory Guide 1.52, Revision 1, July 1976.

3. Verifying a system flow rate of 3000 cfm'i10% during system operation when tested in accordance with ANSI N510-1975.

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

' verifying within~ 31 days after removal that a latforatory analysis of representative carbon sample obtained in accord-ance with Regulatory Position C.6.b of Regulatory Guide 1.53, Revision 1, July 19.76, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 1, July 19.76.

d. At least once per 18 months by:

1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is < 8.5 inches Water Gauge while operating the filter train at a flow rate of 3000 cfm + 10%.

2. Verifying t5at the filter train starts on each secondary containment isolation test signal,

3. Verifying that the heaters will dissipate at least 15.2 i kw when tested in accorcance with ANSI.N510-1975.

i j *For the performance of this surveillance schedule ~d to be completed by j February 25, 1981, a onetime-only exemption is allowed to extend this surveillance until "before the completion of the Spring 1981 outage,"

scheduled to couanence in March,1901.

BRUNSWICK - L' NIT 1 3/4 6-26 h

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CONTAINMENT SYSTEMS I l

CONTAINMENT ATMOSPHERE DILUTION SYSTEM l 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*. . .

ACTION:

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

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

a. At least once per 31 days by verifying that: *

1. The system containt a minimum of 4350 gallons of liquid nitrogen, and

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

b. At least once per 18 months by:

1. Cycling each power operated (excluding automatic) valve in the flow path 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.

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

- For the performance of this surveillance scheduled to be completed by February 25i 1981, a onetime-only exemption is allowed to extend this surveillance until "before the completion ef the Spring 1931 outage,"

scheduled to cor.mence in March, 1981.

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BRUNSWICK - UNIT 1 3/4 6-28 i

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r PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) 4.7.5.4 At least once per 18 months *during shutdown, a representative sample of at least 10 snubbers or at least 10% of all snubbers listed in Table 3.7.5-1, whichever is less, shall be selected and functionally tested to verify correct 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 prior 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.

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I 0For the inaccessible snubber functional inspection interval s~cheduled to end December 30, 1980, a onetime-only exemption is allowed to extend this inspection interval until "before the completion of the Spring 1981 outage," scheduled to commence in March, 1981.

I BRUNSWICK - UNIT 1-3/4 7-10

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@p w : m .e, TABLE 4.7.5-1 .

g liVORAULIC SNUBBER INSPECTION SCHEDULE E

E NUMBER OF StalBBERS FOUND INOPERABLE NEXT REQUIRED p; INSPECTION INTERVAL **

x DURING lllSPECTION JR 9URING lilSPECTION INTERVAL

E 0 18 months + 25%

q _

12 months i 25%

I 2 6 months 125%*** l 3 or 4 124 days 4 25%

5, 6, or 7 62 days T25%

>8 31 days F 25%

Snubbers may be categorized into two groups, " accessible" and " inaccessible". This categorization shall be based upon the snubber's accessibility for inspection during reactor operation. These two groups may be inspected independently according to the above schedule.

Y ** The required inspection interval shall not be lengthened more than one step at a time and the -

S provisions of Specification 4.0.2 are not applicable.

- - For the inaccessible snubber inspection interval scheduled to end December 28, 1980, a onetime-only exemption is allowed to extend this inspection interval until "before the completion of the Spring 1981 outage," scheduled to commence in March, 1981.

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ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

2. Vtrifying the fuel level in the day fuel tank,

3. Verifying the fuel ' ransfer t 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 second ,

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.

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-D270-65, is within the acceptable limits specified in Table 1 of ASTM-D975-74 when checked for viscosity, water and sediment,

d. At least once per 18 months during shutdown by:

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 > 5 minutes while its generator is loaded

- with the emergency loads.

For the verification of this item scheduled for completion by February 20, i 1981, a onetime-only exemption is allowed to extend this inspection until 5

"before the completion of the Spring 1981 outage," scheduled to commence of '

in March, 1981.

2 y e p BRUNSWICK - UNIT 1 3/4 8-3 s

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r ELE'CTRICAL 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.* Verifying-that the 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 107 of the required value.

CFor the verification of this item scheduled for completion February 20, 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 8-4

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

a. At least once per 7 days by verifying that:

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 float charge and has not decreased more than 0.3 volts from the value cbserved 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 m.arimum level indication marks.

c. At least once per 18 months by verifying that:

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 corrosion and coated with anti-corrosion material, and 3 .* The battery charger will supply at seast 250 amperes at a l minimum of 155 volts for at 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 te commence in March, 1981.

BRUNSWICK - UNIT 1 3/4 8-9 e

e c -

ELECTRICAL POWER SYSTEMS SURVEILLAtlCE REQUIREMErlTS (Continued)

d. At least once per 18 months, during shutdown, by. verifying that either:

1. The battery capacity is qdequate to supply and maintain 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

2. The battery capaci'ty is adequate to supply a' dummy load l of the following profile while maintaining the battery terminal vol tage >_ 105 volts. ,

a) During the initial 60 seconds of the test;

1) Battery lA-1 > 1042.'42 amperes, 2 Battery lA-2 > 1211.90 amperes, 3 Battery 1B-1E1089.06 amperes, and

4) Battery 1B-2 > 1028.67 amperes.

b) During the remainder of the first 30 minutes of the test; l) Battery lA-1 > 229.19 amperes,

2) Battery lA-2 > 159.10 amperes,

3) Battery IB-1 > 176.79 amperes, and

~

s

4) Battery 1B-2 E 202.67 amperes.

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 1 A-1 > 75.52 amperes ,

2) Battery 1A-2 > 50.34 amperes,

3) Battery 1B-1 > 53.39 amperes, and

4) Battery 1B-2 > 61.09 amperes.

3.* At the completion of eitaer 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 normal D.C. loads. The battery shall be charged to at least 95% capacity in < 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

e. At least once pe~ 60 months during shutdown by verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test. This performance discharge test shall be performed subsequent to the satisfactory completion of the required battery service test and after nomal equalizer charge.

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

~381, a onetime-only exemption is allowed to extend this inspection until "uefore the completion of the Spring 1931 outage," scheduled to commence in March, 1981.

I BRUNSWICK - UNIT 1 3/4 8-10

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ML19340C046

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