ML17324B093

Proposed Tech Specs,Extending Certain Required Surveillances to Be Performed Beginning 861220

ML17324B093
Person / Time
Site:	Cook
Issue date:	10/01/1986
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17324B091	List: ML17324B090 ML17324B093
References
NUDOCS 8610140317
Download: ML17324B093 (31)

Text

3 4.0 APPLICABILITY SURVEILLANCE RE UIREMENTS Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Code and applicable Addenda Required frequencies for terminology for inservice performing inservice inspection ins ection and testin criteria and testin activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Yearly or annually At least once per 366 days The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.

d. Performance of the above inservice inspection and testing activities shall be in addition to other specified Surviellance Requirements.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

4.0.6 By specific reference to this section, those surveillances which must be performed on or before July 31, 1987, and are designated as 18-month surveillances (or required as outage-related surveillances) may be delayed until the end of the Cycle 9-10 refueling outage (currently scheduled to begin during the second quarter of 1987). For these specific surveillances under this section, the specified time intervals required by Specification, 4.0.2 will be determined with the new initiation date established by the surveillance date during the Unit 1 1987 refueling outage.

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D. C. COOK - UNIT 1 3/4 0-3 Amendment No.

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONOITION FOR OPERATION 3.3.1.1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.

APPLICABILITY: As shown in Table 3. 3-1.

ACTION:

As shn~n in Table 3.3-1.

SURVE I L LANCE REQUIREMENTS.

4.3.1.1.1 Each reactor trip system instrumentation channel shall be .

demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MQDEs and at the frequencies shown in Table 4.3-1.

4.3.1.1.2 The logic for the interlocks shall be demonstrated OPERABLE prior to each reactor startup unl'ess performed during the preceding 92 days. The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one logic train such that both logic trains 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 reactor trip function as shown in the "Total No. of Channels" column of Table 3.3-1.

• The provisions of Specification 4.0.6 are applicable.

0. C. COOK-UNIT 1 3/4 3-1'mendment No.

O O

REACTOR TRI P 6 YS'I'I;H 1 NSTJcc JHI'.NTATTON SIJRVEI I.LANCE RF. UI REHENTS O

00 pc CI I ANN EL HOIJES 1N Wll 1 CII

( IIANNI'.f. CI IANNl I. FUNCTIONAL SURVI ILLANCE P+

M FUNCTIONAL IJtllT ClllX K CA I. l BRAT I ()N TEST RE U I I(EI)

Hanu i 1 l(eactor Trip A. Shuiit Trip Fu>>ct ion N.h. N.A. S/U ( I ) N.A.

B. Undervol tage Trip Functioii N.h. S/U (1 ) NBA.

2. Power lcange, Neutron Flux IJ (2), H (3) 1, 2 arid gi (G)

3. Power Range, Neutron Flux, N.A. R (G) 1, 2 lligh Positive Rate Power lcange, Neutron Flux, N. A. (6) 1, 2 lligh Negative Rate

5. ?nt.ermrdiate Range, R (G) S/IJ (] ) 1, 2 and Neutron Flux

6. Source lcange, Neut ron F 1 ux R (6) H and S/ll(1) 2(7), 3(/), 4 and 5

7. Overtemperat.ure QT 2

8. Overpower LL T 1, 2

9. Pressurizer Pressure--l.ow S H 1, 2

10. Pressurizer Pressure--lligh 1, 2

11. Pressuri zc r Water Level lligh H 1 ~ 2 0 12. Loss of Flow Single loop

+ The provisions of Specification 4.0.6 are applicable.

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REACTOR TRIP .':YSI'EM INS'I'lcUMI'.NTATION SUI(VI ILI.ANCE RE UIRFHFNTS CIIANNEL HOMS IN WIIICll

('I I ANNI'.I. ('I I ANNEL FUNCTIONAL SIIRVEILLANCE FUNCTIONAI. UN ('IIIX K CA I. I III(ATI ON TFST REQU I I(ED I'I'3.

I,oss uf Flc>w - Ixcc> I.oops Ic N.A.

14 ~ Steam ('enc:rate>r Water Level-- I, 2 I.ow-l.uw

15. Steam/Feedwater Flow flismatch a>>d 1 ~ 2 law S>t.earn Ge>>c-'c at or Wat.er l.evc.l

16. Undervoltac)e Reactor Coc>lant N.h, R Pumps

17. U>>dc."r frequency Reactc>r (oul~nt. N. h. R Pumps 1(I ~ Turb i cce Tr i p N.h. I, A. I.ow I'luicl Oi 1 I'res. ure N.h. S/U (1) 2 8~ I'urLine Stop Valve Clos(>re. N.h. N.A. S/U (I) 1 ~ 2

19. Safety Injection Input frc>m LSF N.h. N. A. H(4) 1, 2 2O. Reactor Coolant Pump Breaker N.A. N.A. N.A.

g Position Trip

21. Reactor Trip Breaker A. Shunt Trip I'unction N.h. N.A. H(5) and S/U (l ) I ~ 2 B. Undervoltage Trip I'unction N.h. N.A. H(5) and S/U (1) 2

22. Automatic Trip Logic N.h. N.A. H (5) 1, 2

+ The provisions of Specification 4.0.6 are applicable.

INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumenta.

tion channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their. trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TINES as shown in Tab1e 3.3-5.

APPLICABILITY: As shown in Table 3.3-3.

ACTiON:

a. With an ESFAS instrumentation channel trip setpoint less conserva-tive than the value shown in the Allowable Values column of Table .

3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

b. With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

SURVEILLANCE RE UIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-2.

4.3.2.1.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test. The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.

4.3.2.1.3 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 logic train such that both logic 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 *

• The provisions of Specification 4.0.6 are applicable.

D. C. COOK-UNIT 1 3/4 3-15 Amendment No.

1AB LE 4. 3-2 (Con t inued)

EHGINFERED SAFFTY FEATURE ACILIATION SYSTEM INSTRUMENTATION

'5IlllllEKBttEE 8 II1HBiBII5 CHANNEL MODES IN MHICII CHANNI:L CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHFCK CAL I DRAT ION TEST RE UIRED

4. STEAM LINE ISOLATION

a. Manual N.A. M(l ) 1,2,3

h. Automatic Actuation Logic H.A. M(2) 1,2,3

c. Containment. Pressure-- M(3) 1,2,3 High-Iligh

d. Steam Flow in Two Steam 1,2,3 Lines--High Coincident. wit,h T

Low-Low Pressure--Low

5. TURBINE TRIP AND FEEDWAIEf( ISOlATION

a. Steam Generator Water S 1, 2, 3 Level--IIi gh-High

6. MOTOR DRIVEN AUXILIARY I EEDWA'IER PUMPS

a. Steam Generator Mater 1,2,3 Leve I-- Low- Low

b. 4 kv Bus 1,2,3 Loss of Voltage c; Safety Injection N.A. N.A. M(2) 1,2,3

d. Loss of Main Feed Pumps N.A. N.A. R+ 1,2,3

+- The provisions of Specification 4.0.6 are applicable.

TABLE 4.3-2 Continued EtlGItlEEREO SAFETY FEATURE ACTUATION SYSTEH ItlSTRUNENTATIOtl S RYE ILLA CE RE UIREtlEtlTS CHANtlEL %DES IN MHICH CtlANNEL ClNtlttEL FUNCTIONAL SURVE ILLANCE CAL1DBATION TEST RE UIRED FUtlCT IONAL UN IT CHECK

7. TURBINE DRIVEN AUXILIARY FEEDMATER PUHPS

a. Steam Generator Mater 1,2,3 Level--Low-Low

b. Reactor Coolant Pump Bus Undervoltage N.A. 1, 2, 3

8. LOSS OF POWER

a. 4 kv Bus Loss of Voltage 1,2,3,4

b. 4 kv Bus 1,2,3,4 Loss of Vol tage-

+

The provisions of Specification 4.0.6 are applicable.

TABLE 4.3-7 POST-ACCIOENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS CilANNEL CHANNEL INSTRUMENT CHECK CALIBRATION TAROT

1. Containment Pressure

2. Reactor Coolant Outlet Temperature - (Wide Range)

HOT

3. Reactor Coolant Inlet Temperature - TCOLO (Wide Range) 4 ~ Reactor Coolant Pressure - Wide Range

5. Pressurizer Water Level

6. Steam Line Pressure

7. Steam Generator Water Level - Narrow Range

8. RWST Hater Level

9. Boric Acid Tank Solution Level M

10. Auxiliary Feedwater Flow Rate ll. Reactor Coolant System Subcooling Margin Monitor

12. PORV Position Indicator - Limit Switches

13. PORV .Block Valve Position Indicator - Limit Switches

14. Safety Valve Position Indicator - Acoustic Monitor

• The provisions of Specification 4.0.6 are applicable.

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REACTOR COOLANT num 3/4.4.6 REACTOR COOLANT SYSTEM LEAIVAE LEhlQCE DETECTION SYSTEMS LZHZT&Q CONDITION FOR OPERATION 3,4 ~ 6 ~ 1 The follcnCx~ Reactor Coolant System leakage detactioa systems shall be OPERABLE:

a. One of the containment atmosphere particulate radioactivity monitoring channels NRS-1301 or ERS-1401),

b. The cont~ent sump level and floe monitoring system, and

c. Either the containment humidity monitor or one of tha containment atmosphere gaseous radioactivity monitoring channels.NRS-1305 or ERS-1405) ~

APPLZCABILZTT: IDES 1o 2 ~ 3 and 4 ~

hCTZOM:

arith only ceo of the above required leakage detection systaaa OPERABLE, may cont~~ue for up to 30 days provided grab samples of tha 'peration containment atmosphere are obtained and analyzed at least once per 24 bours vhea the required gaseous and/or particulate radioactivity monitoring channels are inope able; otherv'se, be in at least HOT STANDBY Wthin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the folio@!tag 30 hcasra.

SURVEILLANCE RE 4.4.6.1 The leakage detection systems shall be demonstrated OE%4$ LE bye

a. Containment atmosphere particulate and gaseous (0 being used) monitoring system-perf ormance of CHAPEL CHECK, CHANNEL CALIBRATION and QD!NNEL FUNCT ZONAL TEST at the frequenciu specified in Table 4.3-3,

b. Containment sump level and flov-monitoring systcm-performance of CKhRKL CALZ3RAXZON at least once per LS months,*

c. Containment humidity mon'tor (if being uaed) - per ounce of CHANNEL CALIBRATION as least once per 1S monsha.

• The provisions of Specification 4.0.6 are applicable.

D. C. COOK UNXT 1 3/4 4-14 Aaen4nent, No.

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1

REACTOR COOLANT SYSTEM SUgyE>LANCE RE UER&ENTS Continued) 4.4. LL.2 Each of the three block valves shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel. The block valve(s) do not have to be tested nor is a report required pursuant to Specification 6.9. L.9 when ACTiQN 3.4. Ll.a is applied.

4.4. LL.3 The emergency power suoply for the PORVs and block valves sha11 be demonstrated OPERABLE at least once per L8 months by operating the valves through a complete cycle of full travel while the emergency buses are energized by the onsite diesel generators and onsitc, plant battecies. This testing can be performed in conjunction with the requirements of Specifications 4.8.L.L.2.b and 4.8.2.3.2.c.*

• The provisions of Specification 4.0 ' are applicable.

D. C. COOK UNIT 1 3/4 4-36 Amendment No.

9IQGNCY CORE COOLING SYSTEMS SURYKILL "ACE REQUIREMENTS (Continued )

d. At 1east once per 18 months by:

1; Verifying automatic isolation and interlock action of the RHR systan from the Reactor Coolant System when the Reactor Coolant Systan pr essure is above 600 psig.

2. A visual inspection of the containment sump and verifying that the subsystan suction inlets are nct restricted by debris and that the sump components (trash racks, screens, etC.) ShOW nO eVidenCe Or StruCtural diStreSS Or abnormal corrosion

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

1. Ver ffying that each. automatic valve in the low path actuates to i:s corre"t posi ion on a Safety injection test signal.

2. Verifying that each cf the '.ollowin." oumps start automatically upon r c ipt of a safety injec:ion -. sz signal:

a ) Co ntr i fugal charg ng ump b) Safety inject.'on pump c) Residual heat removal pump By verifying that each of the following pumps develoos the indicated discharge pr essure on re irculation low wnen tested purSuant tO SOeCifiCatiOn 4.0.5 at least once per 3l daVs on a STAGGERED TEST BASXS.

1. Centrifugal charging pump > 2405 psig

2. Safety Lnjectfon pump > 1445 psig

3. Residual heat renoval pump > 195 psig

g. Sy verifying the correct position of each mechanical stop for the the following Emergency Core Cooling System throttle valves:

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenanco on the valve when the EC"S sub-systans are required to be OPERABLE.

• The provisions of Specification 4. 0.6 are applicable. Amendment No..

O..c. CQOV - UNlT 1 3/4 5-5

EMERGENCY CORE COOI ING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5.3. 1 The ECCS subsystem shall be* demonstrated OPERABLE per .the applicable Surveillance Requirements of 4. 5. 2.

4.5.3.2 All charging pumps and safety injection pumps, except the above required OPERABLE charging pump, shall be demonstrated inoperable, by verifying that the motor circuit breakers have been removed from their electrical power supply circuits, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the temperature of one or more of the RCS cold legs is less than or equal to 170'F as determined at least once per hour when any RCS cold leg temperature is between >7O F and 200 F.

• The provisions of Specification 4.0.6 are applicable.

0. C. COOK " QNIT 1 3/4 5-8 Amendment No.

I I)

CONTAINEHT SYSTB5 DIVIDER BARRIER SEAL LIMITING CONDITION FOR OPERATION 3.6.5.9 The divider barrier seal shall be OPERABLE.

APPLICABILITY: NODES 1, 2, 3 and 4.

ACilON:

Mith the divider barrier seal inoperable, restore the seal to OPERABLE status prior to increasing the Reactor Coolant System temperature above 200'F.

SURYEILLANC" REQUIREMENTS 4.5.5.9 The divider barrier seal shall be determined OPEQBLE at least once per 18 months during shutdown by: *

a. Removing two divider barrier seal test coupons and verifying that the physical properties of the test couoons are within the acceptable range of values shown in Table 3.6-2.

b. Yisually inspecting at least 95 percent of the seal's entire length and:

l. Yerifying that the seal and seal mounting bolts are pro-perly installed, and

2. Yerifying that the seal mater ial shows no visual evidence of deterioration due to holes, ruptures, chemical at.ack, abrasion,, radiation damage, or changes in physical appearances.

• The provisions of Specification 4.0.6 are applicable.

0. C. COOK-UNIT 1 3/4 6-38 Amendment No.

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued)

3. Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position.

4. Verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 10%

RATED THERMO, POWER. This requirement is not applicable or those portions of the Auxiliary Feedwater Syst: em being used intermittently to maintain steam generator level.

b. At least once per 18 months during shutdown by: *

1. Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of the appropriate engineered safety features actuation test signal required by Specification 3/4.3.2.

2. Verifying 'that each auxiliary feedwater pump starts as cesigned automatically upon receipt of the appropriate e..gineered safety features actuation test signal required by Specification 3/4 '.2.

• The provisions of Specification 4.0.6 are applicable.

D. C. COOK - UNIT 1 3/4 7 6 Amendment No-

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PLANT SYSTEMS 3/4.7.4 ESSENTIAL SERVICE MATER SYSTEM LIMITING CGNOITION FOR OPERATION 3.7.4.1 At least two independent essential service water loops shall be OPERABLE.

APPLICABILITY: MODES 1. 2, 3 and 4.

ACTION:

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

SURVEILLANCE REQUIREMENTS 4.7.4.1 At least two essential service water loops shall be demonstrated OPERABLE:

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

At least once per 18 months, during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal .*

c. At least once per 3l days on a STAGGERED TEST BASIS, bY verifying that each pump develops at least 93% of the discharge pressure for the applicable flow rate as determined from the manufacturer's Pump Performance Curve-

• The provisions of Specification 4.0.6 are applicable.

D. C. COOK - UNIT 1 3/4 7-17 Amendment No-

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~W S~ST M ZZMXTZHG CONDZTXON FOR OPERATZON 3.7.8 All snubbers Listed in Table 3,7-4 shalL be OPERABLE APKZCABZZZTYz MODES l, 2, 3 and 4. (MODES 5 and 6 for snubbers located on systems re~ed OPEIULBLE in those MODES) .

arith one or more snubbers inoperable within 72 bours replace or restore the

'inoperable snubbe (s) to OPERABLE status and perform an engineering evaluation

~

pe Specification 4.7.8.C on the supported component. or declare the supported systssL inoperable and foLLow the appropriate ACTZOS statcamnt for that, system.

4;7.8 Each snubber shaLL be demonstrated OPERABZZ by performance of the foLLowing Cugmented inservice inspection program and the requirements of Spec ifica&on 4.0.5.

a. Visxxal Znsoee mons The first inserv.'ce visuaL ~4ection of snabbers shall be per ox=aed after four months but wi~ 10 months of emnencing PNER OPERA shall include all snubbers listed in Table 3.7H. Xf less than ZOH'nd visual inspec='on shall be per onned 12 months 25h ~

two (2) snubbe s are found inoperabLe daring the first insezvice of the first inspection. Otherwise, subsepxent visuaL inspecd.ons the date shall be per ormed in accordance with the following schedule:

I No. Znoperable Snubbers Subsequent Visual e Znsoect.'on Pe 'od Znsoec 'on Pc iodr>>

0 L8 months + 25' 1 12 months 25%

2 6 months - 284 3,4 4 days 25%

5~6,7 62 days + 25' 8 or more 31 days 25m The snubbers may be categorized into two groupst Those accessible and those inaccessible dxxring reactor operation. Each group may lm "

inspected independently in accoahance with the above schedule.

The inspection intervaL shall not be Lengthened more than one step at a OThe provisions of Specification 4.0.2 are not, applicable.

• • The provisions of Specification 4.0.6 are applicable.

D C Cook 3/4 7 21 Amen~t N0.

SURVEILLANCE QyRE~~S (C

b. Ac least oace per LB mont,hs:*

l. Sy per-ormiag a syscem funct'onal cesc vhich includes simulated automacic accuatioa of tne system, aad:

a) Uerifyiag thee.che automatic valves ia the flov path actuate to c hei r co r race pasi cioas on a ces c" signal, and b) Cycliag each vaLve ia che flov path chat is not cestable duriag pLaac operacioa r,hrough ac least one complece cycle of full travel.

2. Sy inspection of deluge aad preaccion type syscem spray headers to vecify chair integrity ~

3. By iaspectioa of each open head deluge nozzLe to ver'fy no blocloL'ge.

c. At least once pe. 3 years by pe..o.='ng aa air flov east through each open head deluge header and ver'fyi."g each open head deluge nozzle is uao bscructed.

• The provisions of Specification 4.0.6 are applicable.

D C COOK - ONIT l Amendment Ho.

3/4 7 45

,II Ei.ECTRICAL POMER SYSi EILLANCc, RE lRB<HTS (Continued)

Z. Verifying the fuel level in De fue1 storage tank,

3. Verifying that a sample of diesel fue1 mm the fuel storage tank is within the acc pt ble limits specified in Table 1 of ASTH 0975-68 when checked or viscosity, waar and sediment,

4. Yerifying .he fuel transfer purip can be start d from the .

control panel and trans rs uel from the s orage system to he day .ank,

5. Verifying De diesel s arm from ambient condition,

6. Yeri ying the generator is synchroni-ed, loaded to ~ 175O kw, and operates for > 60 minutes, and

7. Yerifying the diesel generator is aligned .o provide s +ndby power .o the associated emergency busses.

At least once per 18 months during shutdown by:"

1. Subjer.ing the diesel c an inspection in accordanc wi'.h procedures pr epared ir conjunction'with its manufacturer's reccr. endations -;or this c',ass of standby service,

2. Yerifyin" .he g nerator czoabiii:y to r ject a load o

~

600 kw w', thou.:ri pping,

3. Simulat ng a loss of o-.-,si e power in conjunc ion wi4 a safety injection signal, and:

Yeri ying de-energizaticn o- tho emergency busses and load shedding from the emer g ncy busses.

Yerifying .he diesel s arts frcm ambient condition on he auto-s .": signal, nergiz s ~He emergency busses with permanen-.ly connecte" loads, energizes the auto-connected -er"ency loads &rough he load sequencer and opera;cs -or > 5 minu~ while its generator is loaded wi.h the emergency loads..

Verifying that on diesel cener tor trip, the leads are shed -;rom the emergency buses and :he diesel re-starts on the auto-s:a>>: signal following manual resettirg of the diesel trip lockout relay, Inc emergency buses are energi"ed with permanently con-nected loads, the auto-connected emergency loads are energized :hrough the load sequenc r and the diesel operates far > 5 minutes while its genera:or Is lioad d wi:h the emergency loads.

• The prove.sxons of Specification 4.0.6 are applicable.

0. C. COOK - VNlT 3/4 8-3 Anendment Ho.

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ELECTRICAL POWER SYSTEMS LIMITING CONOITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. One circuit between the offsite transmission network and the onsite Class lE dis:ribution system, and

b. One diesel generator with:

1. A day tank containing a minimum of 70 gallons of fuel,

2. A fuel storage system containing a minimum of 42,000 gallons of fuel, and A fuel transfer pump.

APPLICABILI-,Y. MOOES 5 and 6.

ACT'tOM:

With less than the above minimum required A.C. elec.rical power sources OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until the minimum reouired A.C. electrical power sources are restored to OPERABLE status.

SURYEILLANCE REOVIREMENTS 4.8.1.2 The above required A.C. ele trical oower sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for requirement 4.8.1.1.2a .6. *

• The provisions of Specification 4.0.6 are applicable.

G. C. COOK -UNIT 1 3/4 8-5 Amendment No.

ELECTRICAL POWER SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) 0

2. The pilot cell specific gravity, corrected to 77 F and full electrolyte level (fluid at the bottom of the maximum level indication mark), is Z 1. 200,

3. The pilot cell voltage is ~ 2.10 volts, and

4. The overall'attery voltage is ~ 250 volts.

b. At least once per 92 days by verifying that:

1 ~ The voltage of each connected cell is + 2.10 volts under f'oat charge and has not decreased more than 0.05 volts rom the value observed during the original acceptance test, and

2. he specific gravity, corrected to 77 F and full electrolyte level (fluid at the bottom of the maximum level ind'ation mark), of each connected cell is

'.200 and has not decreased more than 0.03 from the value observed during the previous test, and

3. The electrolyte level of each connected cell is between

-he too of the minimum level indication mark and the bottom of the maximum level indication ma k.

c. At least once per 18 months by ver'fying that:

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

2. The cell-to-cell and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.

3. The battery charger will supply at least 10 amperes at, 250 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

d. At least once pe 18 months, during shutdown (MODES 5 or 6), by ver"=ying that the battery capacity is adeauate to supply and maintain in OPERABLE status the emergency loads for the times specified in Table 4.8-2 with the battery charcer disconnected. The battery terminal voltage shall be uaintained + 210 volts throughout the battery service test e

e. At least once per 60 months, during shutdown (MODES 5 or 6), 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 per ormed in place of the battery service test.

• The provisions of Specification 4.0.6 are applicable.

D. C. COOK - UNIT 1 3/4 8-14 Amendment No.

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