Text

Proposed Tech Specs Allowing Extension of 18-month Surveillances Associated W/Esf Until First Refueling Outage Scheduled for Aug 1986
	ML20214C697
Person / Time
Site:	Catawba
Issue date:	02/12/1986
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20214C695	List: ML20214C692; ML20214C697;
References
	NUDOCS 8602210238
	Download: ML20214C697 (16)
	v • d • e

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J

REACTIVITY CONTROL SYSTEMS . .

FLOW PATHS - OPERATING' LIMITING CON 0! TION FOR OPERATION 3.1.2.2 At least two* of the following three boron injection flow paths shall be OPERA 8LE:

a. The flow path from the boric acid tanks via a boric acid transfer pump and a charging pump to the Reactor Coolant System,,,and 1

b. Two flow paths from the refueling water storage tank via charging pumps to the Reactor Coolant System.

APPLICA81LITY: MODES 1, 2, 3, and 4.

ACTION:

With only one of the above required boron injection flow paths to the Reactor Coolant System OPERA 8LE, restore at least two boron injection flow paths to the Reactor Coolant System to OPERA 8LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STAN08Y and borated to a SHUTDOWN MARGIN equivalent to at least 1% Ak/k .

at 200*F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two flow paths to OPERA 8LE

9 status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .-

9 '

SURVEILLANCE REQUIREMENTS O

g g- f, n

kg 4.1.2.2 At least two of the above required flow paths shall be demonstrated OPERABLE:

mg+-

ykU a. At least once per 7 days by verifying that the temperature of the flow path from the boric acid tanks is greater than or equal to 5g 65'F when it is a required water source;

b. At least once per 31 days by verifying that each valve (manual, j 50 power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position; i

k I gE c. At least once per 18 months during shutdown by verifying that each gg automatic valve in the flow path uates to its correct position on

)

g, R aSafetyInjectiontestsignalf g@ At least once per 18 months by verifying that the flow path required E d.

j,la by Specification 3.1.2.2a. delivers at least 30 gpm to the Reactor g Coolant System.

"Only one boron injection flow p'ath is required to be OPERA 8LE whenever the temperature of one or more of the Reactor Coolant System cold legs is less than or equal to 285'F.

i CATAW8A - UNIT 1 3/4 1-8 8602210230 860212 PDR ADOCK 05000413 j

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4 TABLE 4.3-1 (Continued)

-4 REACTORTRIPSYSTEM'INSTRUMENTATIONSURVEILLANCEREQUIREMENTS E

TRIP

ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH g OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE CHANNEL CHANNEL q CALIBRATION TEST TEST LOGIC TEST _IS REQUIRED FUNCTIONAL UNIT CHECK g

M M.A. N.A. I', 2

13. Steam Generator Water Level- S R Low-Low Undervoltage - Reactor Coolant N.A. R N.A. M N.A. 1 14.

Pumps Underfrequency - Reactor N.A. R N.A. M N.A. 1 15.

Coolant Pumps M* 16. Turbine Trip

a. Low Control Valve EH S/U(1, 10) N.A. 1#

T Pressure N.A. R N.A.

Turbine Stop Valve N.A. R N.A. S/U(1, 10) N.A. 1# '

b. ,

Closure N.A. N.A. R N N.A. 1, 2

17. Safety Injection Input from N.A.

ESF

18. Reactor Trip System Interlocks

a. Intermediate Range N.A. N.A. 2##

Neutron Flux, P-6 N.A. R(4) M

b. Low Power Reactor N.A.

Trips Block, P-7 N.A. R(4) N(8) N.A. I

c. Power Range Neutron N.A.

Flux, P-8 N.A. R(4) M(8) N.A. I

d. Low Power Range Neutron N.A. R(4) N(8) - N.A. N.A. 1 Flux, P-9 NM 7his surwillance need not be performed until

. prior to entering HBF-9HtMBOIM following the {

, thit One first refueling Jrgriro7' m.

i INSTRilMENTATION ,,

SURVEILLANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuation logic and relays shall be demonstrated OPERA 8LE by performance of the Engineered Safety Features Actuation System Instrumentation Survalliance Requirements specifled in Table 4.3-2.

Y eP t

4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18. months.

Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels !

are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.* T

'this surveillance need not be performed 6 prior to entering HOF SIMDCIM following the thit One first refueling e

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l CATAWBA - UNIT 1 3/4 3-14

_ _ - . . - _ _ _ - _ _ _ _ _ _ _ . __ _ _ _ . . _ , - _ -___ _ _ ._ _ _ ___.._ _ ___ _ _.~.. _.

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of greater than or equal to 75 gallons by verifying the boron concentration of the accumulator solution;

c. At least once per 31 days when the Reactor Coolant System pressure is above 2000 psig by verifying that power is removed from the isolation valve operators on Valves NI54A, NI658, NI76A, and NI888 and that the respective circuit breakers are padlocked; and

d. At least once per 18 months by verifying that each cold leg injection accumulator isolation valve' opens automatically under each of the following conditions: M

1) When an actual or a simulated Reactor Coolant System pressure signal exceeds the P-11 (Pressurizer Pressure Block of Safety Injection) Setpoint, and Upon receipt of a Safety Injection test signal. *?

2) _

4.5.1.1.2 Each cold leg injection accumulator water level and pressure channel sh711 be demonstrated OPERABLE:

a. At least once per 31 days by the performance of an ANALOG CHANNEL OPERATIONAL TEST, and

b. At least once per 18 months by the performance of a CHANNEL CALIBRATION.

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t 3/4 5-2 CATAWBA - UNIT 1

EMERGENCY CORE COOLING SYSTEMS .

l

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l SURVEILLANCE REQUIREMENTS (Continued) '

b) With a simulated or actual Reactor Coolant System pressure ;

. signal less than or equal to 660 psig the interlocks will !i

' cause the valves to automatically close. ll

2) A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and i that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnomal corrosion.

e. Atleastonceper18. months,duringshutdown,byN

1) Verifying that each automatic valve in the flow path actuates to its correct positio'n on Safety Injection and Containment Sump Recirculation test signals, and

2) Verifying that each of the following pumps start automatically upon receipt of a Safety Injection test signal:

a) Centrifugal charging pump, .

b) Safety Injection puinp, and

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i c) Residual heat removal pump.

f. By verifying that each of the following pumps develops the indicated n differential pressure when tested pursuant to Specification 4.0.5:

$ 1) Centrifugal charging pump 1 2380 psid, 3

C 2) Safety Injection pump 1 1430 psid, and 5 3) Residual heat removal pump 1 165 psid.

g. By verifying the correct position of each electrical and/or mechanical stop for the following ECCS throttle valves:

1) Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following completion of each valve stroking i operation or maintenance on the valve when the ECCS subsystems op are required to be OPERABLE, and ok c' 2) At least once per 18 months.

Centrifugal e Charging Pu'np g g Injection Throttle Valve Number Safety Injection Throttle Valve Number 1NI-14 '

1NI-164 1NI-16 1NI-166 INI-18 1NI-168 1NI-20 1NI-170 l

CATAWBA - UNIT 1 3/4 5-7 y- . ~ . - g, ,,--_.---,.m. , , . yr.,.-_,..--%m-- , %,.m..wm_e,-,,.. - , %%._.- _ ,.,,,m_.-.m.- - , _ , .-, ,%..- , . _ . .

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.3.1 The ECCS subsystem shall be demonstrated OPERA 8LE per the applicable requirements of Specification 4.5.2.# 5 4.5.3.2. All charging pumps and Safety Injection pumps, except the above required OPERA 8LE centrifugal charging pump, shall be demonstrated inoperable by verifying that the motor circuit breakers are sociired in the open position or the discharge of each pump has been isolated from the Reactor Coolant System by at least two isolation valves with power removed from the valve' motor opera-tors at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the temperature of one or more of the Reactor Coolant System cold legs is less than or equal to 285'F.

M 'Ihis survM11arca need not k Aw e .

prior to entarirq HDT m folg h unit one first refuelirs h

I 1

CATAW8A - UNIT 1 3/4 5-10 l

CONTAINMENT SYSTEMS SURVEILLANCE REQUl#EMENTS (Continued)'

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, th&1 a laboratory analysis of a repre-sentat,ive carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2 March 1978, for a methyl iodide penetration of less than 1%;

.) d. At least once per 18 months by:

1) Verifying that the pressure drop across the combined HEPA filters, charcoal adsorber banks, and moisture separators is less than 8 inches Water Gauge while operating the system at a flow rate of 9000 cfm i 10%;

2) Verifying that the system starts automatically on any Phase "A '

Isolation test signal,189P

3) Verifying that the filter cooling electric motor-operated bypass valves can be manually opened,

4) Verifying that each system produces a negative pressure oC*

greater than or equal'to 0.5 inch Water Gauge in the annulus -

within 1 minute after a start signal, and

5) Verifying that the pre-heaters dissipate 45 t 6.7 kW when tested in accordance with ANSI N510-1980.

e. After each complete or partial replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in place penetra-

o tion and bypass leakage testing acceptance criteria of less than UE in accordance with ANSI N510-1980 for a 00P test aerosol while operating the system at a flow rate of 9000 cfm i 10%; and

f. After each complete or partial replacement of a charcoal adsorber bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than EE in accordance with ANSI N510-1980 for a halogenated hydro-carbon refrigerant test gas while operating the system at a flow rate of 9000 cfm i 10%.

N m is surveillanca need not be M a until prior to entering im SIUIDatei following the Unit one first refueling

0

. CATAWBA - UNIT 1 3/4 6-15 9- -...,,.-,...,.,-r, %.----,,-rw---.---r-+w---,-,-.-,,,-r,,,w.- - - - - - , - . --,..e- -

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CONTAINMENT SYSTEMS 3/4.6.2 OEPRESSURIZATION AND COOLING SYSTEMS CONTAI!G4ENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2 Two independent Containment Spray Systems shall be OPERA 8LE with each Spray System capable of taking suction from the refueling water storage tank and transferring suction to the containment sump.

APPLICA8ILITY: MODES 1, 2, 3, and A.

ACTION:

With one Containment Spray System inoperable, restore the inoperable Spray System to OPERA 8LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the inoperable Spray System to OPERA 8LE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

7 SURVEILLANCE REQUIREMENTS 4.6.2 Each Containment Spray System shall be demonstrated OPERABLE:

a. At least once per 31 days by 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;

b. By verifying, that on recirculation flow, each pump develops a differential pressure of greater than or equal to 185 psid when 1 tested pursuant to Specification 4.0.5;

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

1) Verifying that each automatic valve in the flow path actuates to its correct position on a Phase "B" Isolation test signal, and

2) Verifying that each spray pump starts automatically on a Phase "B" Isolation test signal.

3) Verifying that each spray pump is prevented from starting by the Containment Pressure Control System when the containment atmosphere pressure is less than or eoual to 0.25 psid, and is allowed to start at greater than or equal to 0.45 psid relative to the outside atmosphere, Ab This su m illance need not be performed until prior to entering Im sitJIDatet following the Unit One first refueling CATAW8A - UNIT 1 3/4 6-18 1

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i CONTAINMENT SYSTEMS l SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each isolation valve specified in Table 3.6-2 shall be demonstrated OPERA 8LE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 ,

months by:

a. Verifying that on a Phase "A" Isolation test signal, each Phase "A" isolation valve actuates to its isolation position;**

b. Verifying that on a Phase "B" Isolation test signal, each Phase "B" isolation valve actuates to its isolation position;4 9

c. Verifying that on a Containment Radioactivity-High test signal, each purge and exhaust valve actuates to its isolation position; and

d. Verifying that on a High Relative Humidity (>70%) isolation test signal, each upper and lower containment purge supply and exhaust valve actuates to its isolation position.

4.6.3.3 The isolation time of each power.-operated or automatic valve of ,

Table 3.6-2 shall be determined to be within its limit when tested pursuant to Specification 4.0.5. -

EN 'Ihis survai11=== need not be performed until prior to entering im SIUIDalet following the Unit One first Im6=14ng l

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CATAWBA - UNIT 1 3/4 6-21 1

o

.m CONTAINMENT SYSTEMS , ,

CONTAINMENT VALVE INJECTION WATER SYSTEM t

LIMITING CONDITION FOR OPERATION 3.6.6 Both trains of the Containment Valve Injection Water System shall be OPERA 8LE.

APPLICA8ILITY: MODES 1, 2, 3 and 4.

ACTION:

With one train of the Containment Valve Injection Water System inoperable, restore the inoperable system to OPERA 8LE status within 7 days or be in at least HOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

7 SURVEILLANCE REQUIREMENTS 4.6.6.1 Each train of the Containment Valve Infection Vater System shall be demonstrated OPERABLE at least once per 31 days by verifying that the system is pressurized to greater than or equal to 1.10 P,(16.2 psig) and has ade-quate capacity to maintain system pressure for at least 30 days.

4.6.6.2 Each train of the Containment Valve Injection Water System shall be demonstrated OPERABLE at least once per 18 months by verifying that the valve seal injection flow rate is less than 1.7 gpm for Train A and 1.4 gpm for Train 8 with a tank pressure greater than or equal to 45 psig and each auto-matic valve in the flow path actuates to its correct position on a Containment Pressure-High or a Containment Pressure-High-High test signal.'*

i M 'Ihis surveillance need not be performed until prior to entering IUr SHUIDOM4 following the thit One first refueling l

CATAW8A - UNIT 1 3/4 6-46 l

\

PLANT SYSTEMS ,

3/4.7.3 COMPONENTC00LkNGWATERSYSTEM LIMITING CONDITION FOR OPERATION 3.7.3 At least two independent component cooling water loops shall be OPERABLE.

APPLICA8ILITY: MODES 1, 2, 3, and 4. ,

ACTION:

With only one component cooling water loop OPERABLE, restore at least two loops to OPERA 8LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be'in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.3 At least two component cooling water. loops sha.11 be demonstrated OPERABtE:

a. At least once per 31 days by verifying that each valve (manual, -

power-operated, or automatic) servicing safety-relatea equipment that .

is not locked, sealed, or otherwise secured in position is in its correct position; and

b. At least once per 18 months during shutdownNy verifying that:

1) Each automatic valve servicing safety-related equipment actuates to its correct position on a Safety Injection, Phase "A" Isolation, or Phase "B" Isolatiun test signal, and

2) Each Component Cooling Water System pump starts automatically on a Safety Injection test signal.

%k This survaillance need not be performed until prior to entering IUr SIDIDCm following the thit One first refueling CATAWBA - UNIT 1 3/4 7-10

PLANT SYSTEMS 3/4.7.4 NUCLEAR SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4 At least two independent nuclear service water loops shall be OPERABLE.

APPLICA8ILITY: MODES 1, 2, 3, and 4.

ACTION:

With only one nuclear service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.4 AtleasttwonuclearservicewaterloopsshaflbedemonstratedOPERABLEI

~

a. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position is in its correct position; and

b. At least once per 18 months during shutdownf $y verifying that:

1) Each automatic valve servicing safety-related equipment actuates to its correct position on a Safety Injection, or Phase "B" Isolation test signal, and

2) Each Nuclear Service Water System pump starts automatically on a Safety Injection, or 8.oss-of-Offsite Power test signal.

M 'Ihis surveillance need not be perfonned until, prior to entering Im m f% %

Uhit One first refueling CATAW8A - UNIT 1 3/4 7-11

~ _ . ,

PLANT SYSTEMS ,

SURVEILLANCE REQUIREMENTS (Continued)* f

3) Verifying a system flow rate of 30,000 cfm + 10% during system operation when tested in accordance with AN5I N510-1980.

l

c. After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation, by verifying, i within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.S.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory, Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%;

d. At least once per 18 months by: .

1) Verifying that the pressure drop across the combined HEPA filters, charcoal adsorber banks, and moisture separators of less than 8 inches Water Gauge while operating the system at a flow rate of 30,000 cfm + 10%,

2) Verifying that the system starts on a Safety Injection .

test signal, and directs its exhaust flow through the HEPA)

filters and charcoal adsorbers,**

3) Verifying that the system maintains the ECCS pump room at a~

negative pressure relative to adjacent areas,

4) Verifying that the filter cooling bypass valves can be manually opened, and

5) Verifying that the heaters dissipate 40 1 4 kW when tested in accordance with ANSI N510-1980.

e. After each complete or partial replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in-place pene-tration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1980 for a 00P test aerosol while operating the system at a flow rate of 30,000 cfm i 10%; and

f. After each complete or partial replacement of a charcoal adsorber bank, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1980 for a halogenated hydro-carbon refrigerant test gas while operating the system at a flow rate of 30,000 cfm i 1C%.

O 'Ihis servaillance need not be ;-- '- until prior to entering HOF SIMD0005 following the Unit One first refueling CATAWBA - UNIT 1 3/4 7-17

_ __._ _._ _ _ - _ _ _ _ .._ _ . _ _ ___ _ _ _ __________i.____

I I

ELECTRICAL POWER SYSTEMS , ,

SURVEILLANCE REQUIREMENTS (Continued)

1) By verifying in accordance with the tests specified in ASTM-0975-81 prior to addition to the storage tanks that the r

sample has: !

a) An API Gravity of within 0.3 degrees at 60*F, or a specific gravity of within 0.0016 at 60/60'F, when compared to the supplier's certificate, or an absolute specific gravity at 60/60*F of greater than or equal to 0.83 but less than or e equal to 0.89, or an API gravity of greater than or equal to 27 degrees but less than or equal to 39 degrees; I

b) A kinematic viscosity at 40'C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes (alternatively, Saybolt viscosity, SUS at 100'F of greater :

than or equal to 32.6, but less than or equal to 40.1),

if gravity was not determined by comparison with the '

supplier's certification; c) A flash point equal to or greater than 125*F; and d) A clear and bright appearance with proper color when ["

tested in accordance wi'th ASTM-04176-82.

~

2) By verifying within 30 days of obtaining the sample that the other properties specified in Table 1 of ASTM-0975-81 are met .

when tested in accordance with ASTM-0975-81 except that the analysis for sulfur may be performed in accordance with ASTM-01552-79 or ASTM-D2622-82.

f. At least once every 31 days by obtaining a samplo of fuel oil in accordance with ASTM-D2276-78, and verifying that total particulate contamination is less than 10 mg/ liter when checked in accordance with ASTM-D2276-78, Method A;

g. 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 manutacturer's recommendations for this class of standby service;

2) Verifying the generator capability to reject a load of greater thar,or equal to 825 kW while maintaining voltage at 4160 1 420 volts and frequency at 60 t 1.2 Hz;

3) Verifying the generator capability to reject a load of greater than or equal to 5600 kW but less than or equal to 5750 kW without tripping. The generator speed shall not exceed 500 rpm during and following the load rejection;

4) Simulatingaloss-of-offsitepowerbyitself,*And:

a) Verifying deenergization of the emergency busses and load shedding from the emergency busses, and

'Ihis surveillance need not be perfonned until 4 prior to entering IKyr SN7IDolet following the Unit one first refueling CATAWBA - UNIT 1

y ELECTRICAL POWER SYSTEMS . .

SURVEILLANCE REQUIREMENTS (Continued)

I b) Verifying the diesel starts on the auto-start signal, energizes the emergency busses with permanently connected

loads within 11 seconds, energizes the auto-connected emergency (accident) loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. Af ter ener- ,

gization, the steady-state voltage and frequency of the j emergency busses shall be maintained at 4160 1 420 volts and 60 1 1.2 Hz during this test.

5) Verifying that on an ESF Ac,tuation test signal, without loss-of-offsite power, the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 i minutes. The generator voltage and frequency shall be at -

. 4160 2 420 volts and 60 i 1.2 Hz within 11 seconds after the auto-start signal; the steady-state generator voltage and .

frequency shall be maintained within these limits during this test;

6) Simulating a loss-of-of'fsite powe'r in conjunction with an ETF Actuation test signal, and .

a) Verifying deenergization of the esegr ency busses and load shedding from the emergency busses; b) Verifying the diesel starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 11 seconds, energizes the auto-connected emergency (accident) loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady-state voltage and frequency of the emergency busses shall be maintaine at 4160 1 420 volts and 60 1 1.2 Hz during this test; d c) Verifying that all automatic diesel generator trips, except engine overspeed, low-low lube oil pressure, generator differential, and the 2 out of 3 voltage controlled overcurrent relay scheme, are automatically bypassed upon loss of voltage on the emergency bus concurrent with a Safety Injection Actuation signal.

7) Verifying the diesel generator operates for at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The diesel generator shall be loaded to greater than or equal to 5600 kW but less than or equal to 5750 kW.. The generator voltage and frequency shall be 4160 1 420 volts and 60 1 1.2 Hz within 11 seconds after the start signal; the steady-state generator

- voltage and frequency shall be maintained within these limits

'Ihis survaillance need not be performed until prior to entering 10r SIMDatei following the N Unit one first r=^= Hag CATAWBA - UNIT 1 3/4 8-5

s ELECTRICAL POWER SYSTEMS , ,

SURVEILLANCE REQUIREMENTS (Continued) during this test. Within 5 minutes after completing this 24-hourtest,performSpecification4.8.1.1.2g.6)b)(.a4M)

8) Verifying that the auto-connected loads to each diesel generator do not exceed 5750 kW; O

9) Verifying the diesel generator's capability to:O.

a) Synchronize with the offsite power source while the generator is loaded with its emergency loads upon a simulated restoration of offsite power',

b) Transfer its loads to the offsite power source, and c) 8e restored to its standby status.

10) Verifying that with the diesel generator operating in a test ,

mode, connected to its bus, a simulated Safety Injection signal overrides the test mode by: (1) returning the diesel generator .

to standby operation, and (2) automatically energizing the emergency loads with offsite power; M -

11) Verifying that the fuel transfer valve transfers fuel from each fuel storage tank to the day tank of each diesel via the in-stalled cross-connection lines;

12) Verifying that the automatic load sequence timer is OPERABLE with the interval between each load block within the tolerances given in Table 4.8-2;

13) Verifying that the voltage and diesel speed tolerances for the accelerated sequencer permissives are 92.5 t 1% and 98 + 1%,

respectively, with a minimum time delay of 2.t 0.2 s; and

14) Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:

a) Turning gear engaged, or b) Maintenance mode.

If Specification 4.8.1.1.2g.6)b) is not satisfactorily completed, it is not necessary to repeat the preceding 24-hour test. Instead, the diesel generator may be operated at greater than or equal to 5600 kW but less than or equal to 5750 kW for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or until operatina temperature has stabilized.

44 'Ihis surveillance need not be perfomed until prior to entering HOF SEED 0Bei following the thit one first refueling CATAWBA - UNIT 1 u4 8-6

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ML20214C697

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