ML17325A070

Amend 107 to License DPR-58,revising Tech Specs to Extend Period to Perform Certain Surveillances Due to Lengthened Cycle 9 Operation

ML17325A070
Person / Time
Site:	Cook
Issue date:	04/17/1987
From:	Holahan G Office of Nuclear Reactor Regulation
To:
Shared Package
ML17325A069	List: ML17325A068 ML17325A070 ML17325A071
References
NUDOCS 8704300204
Download: ML17325A070 (27)

Text

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UNITED STAlis NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.

COOK NUCLEAR PLANT UNIT NO. I N~ENDMENT TO FACILITY OPERATING LICENSE Amendment No. 107 License No.

DPR-58 1.

The Nuclear Regulatory COIIeission (the Commission) has found that A.

The application for amendment by Indiana and Michigan Electric Company (the licensee) dated January 9, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended

{the Act) and the Commission's rules and 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 rules and regulations of the Commi ss 1 on There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangerino the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Coninission'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 Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly,'he 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-58 is hereby amended to read as "follows:

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ADOCN, p~ppp3 POR

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 107, are hereby incorporated in the license.

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

3.

The Technical Specifications are to become effective within 45 days of receiot of this amendment.

4.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 17, 1987 Gary M. Hol an, Assistant Director for Region III and V Reactors Office of Nuclear Reactor Regulation

0

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT N0.107 FACILITY OPERATING LICENSE NO.

DPR-58 DOCKET ND. 50-315 Revise Appendix A as follows:

Remove Pa es 3/4 3-41*

3/4 3-42 3/4 3-56 3/4 5-1*

3/4 5-2 3/4 5-5 3/4 6-10 3/4 6-13 3/4 6-15 3/4 6-30 3/4 6-33 3/4 6-34 3/4 7-15 3/4 7-17 3/4 7-21*

3/4 7-22 3/4 7-25 3/4 7-26*

3/4 8-9 3/4 8-12 Insert Paqes 3/4 3-41 3/4 3-42 3/4 3-56 3/4 5-1

'/4 5-2 3/4 5-5 3/4 6-10 3/4 6-13 3/4 6-15 3/4 '6-30 3/4 6-33 3/4 6-34 3/4 7-15 3/4 7-17 3/4 7-21 3/4 7-22 3/4 7-25 3/4 7-26 3/4 8-9 3/4 8-12 Included for Convenience only

TABLE 3.3-7 I

SEISMIC MONITORING INSTRUMENTATION INSTRUMENTS AND SENSOR LOCATIONS 1.

STRONG MOTION TRIAXIAL ACCELEROGRAPHS a.

Reactor Pit FLoor b.

Top of Crane Hall c.

Free Field 2.

PEAK RECORDING ACCELEROGRAPHS a.

Containment Spring Line b.

Diesel Generator Room Floor c.

Spent Fuel Pool MEASUREMENT RANGE 0-1 g

0-1 g

0-1 g

0-2 g 0-2 g 0-2 g MINIMUM INSTRUMENTS OPERABLE D. C.

COOK-UNIT 1

3/4 3-41

TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REAUIREMENTS n

CD FC I

0 INSTRUMENT CHANNEL 1.

STRONG MOTION TRIAXIALACCELEROGRAPHS a.

Reactor Pit Floor 1.

Time History Recorder 2.

Seismic Trigger b.

Top of Crane lla11 1.

Time History Recorder c.

Free Field 1.

Time History Recorder 2.

Seismic Trigger 2.

PEAK RECORDING ACCELEROGRAPHS I

a.

Containment Spring Line b.

Diesel Generator Room Floor c.

Spent Fuel Pool CHANNEL CHECK NA flA NA NA CHANNEL CALIBRATION R*

R*

R CHANNEL FUNCTIONAL TEST M

NA M

NA NA NA

• The provisions of Specification 4.0.6 are applicable.

n C7 C7 7C INSTAUffENT TABLE 4.3-7 POST-ACCIDE'NT MONITORING INSTIllNCNTATIOH SURVEILLANCE AE IAEMEfITS CINflNEL CI[LCK CHARsNEL CALIOAATION D

1.

Containment Pressure 2.

Aeactor Coolant Outlet Temperature - TffOT (<<~fe Range) 3.

Reactor Coolant Inlet Temperature - TCOLO (Mfde Range) 4.

Reactor Coolant Pressure - Mide Range 5.

Pressurizer lfater Level 6.

Steam Line Pressure 7.

Steam Generator Mater Level - Narrow Range 8.

Rl/ST Mater Level 9.

BoIic Acid Tank Solution Level 10.

Auxiliary Feedwater Flow Rate ll.

Ifeactor Coolant System Subcooling Marg)n ffonitor 12.

PORV Position Indicator. - Limit Switches 13.

PORV. 01ock Valve Position Indicator - Limit Switches 14.

Safety Valve Position Indicator - Acoustic tlonftor R'*

I R*

~ The firovisions of S~iecil i+ation 4.0.G a~e ntq>lie.able.

3/4.5 EMERGENCY CORE COOLING SYSTEMS

{ECCS)

ACCUMULATORS LIMITING CONDITION FOR OPERATION 3.5.1 Each reactor coolant system accumulator shall be OPERABLE with:

a.

The isol ation valve open, b.

Between 929 and 971 cubic feet of borated water, c.

A minimum boron concentration of 1950

PPM, and d.

A nitrogen cover-pressure of between 585 and 658 psig.

APPLICABILITY:

MODES 1, 2 and 3.*

ACTION:

a.

With one accumulator inoperable, except as a result of a closed isolation valve, restore the inoperable accumulator to OPERABLE status within one hour or be in HOT SHUTDOWN within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

b.

With one accumulator inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in HOT STANDBY within one hour and be in HOT SHUTDOWN within the next 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> s.

SURVEILLANCE REQUIREMENTS 4.5.1 Each accumulator shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:

1.

Verifying the water level and nitrogen cover-pressure in the tanks, and 2.

Verifying that each accumulator isolation valve is open.

Pressurizer Pressure above 1000 psig.

3/4 5-1

EMERGENCY CORE COOLING SYSTEHS SURVEILLANCE RE UIRENENTS (Continued) b.

At 'least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution volume increase of > 1Ã of tank volume by verifying the boron concentration of the accumulator solution.

c.

At least once per 31 days when the RCS pressure is above 2000

psig, by verifying that power to the isolation valve operator is disconnected by removal of the breaker from the circuit.

d.

Verifying at least once per 18 months that each accumulator isolation valve opens automatically upon receipt of a safety injection test signal.*

• The provisions of Specification 4.0.6 are applicable.

D.C.COOK-UNIT 1

3/4 5-2 Amendment No.

107

QQGKNCY CORE COOLING SYSiEHS SURY<gl.L'AC c, REOUIR&PiTS (Continued) d.

At least once per 18 months by:

• l.

Yerifying automatic isolation and interlock ac icn of the RHR systen from the Re ctor Coolant Systen when the Reactor Coolant System pressure is above 600 psig.

2.

A visual inspec.ion oi the c"ntaicnent sump and ve. fying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks.

sere ns, etc.)

show no evidence o

s ruc:ural distress or abnormal corrosion At least once per 18 months, during shutdown, by: ~

l.

Ye. ifying t."at each automatic valve in the flow path ac~ates to i:s corre: ""siticn cn a Safety tn'ecti "n test signa 1.

2.

~ Yerifying that each cf the follcwin= cu-,.-s s+art automatically upon receipt c; a sa,etv

',n'ec=.cn

.est signal:

a)

Centr ~ugal c"zr" ng

" mo b)

Safety in~co. on pu'p c)

Residual heat r..oval pi=.,o By verifying that each of the following pumos develoos he indicated discharge pressure on re.ircula:ion flow wnen tested pursuant to Soecification 4 ~ 0 5 at least once per 31 6avs on a STAGGERED TEST BASIS.

1.

Centrifugal charging pump i 2405 psig

~

1445 psig 2.

Safety Injection pump 3.

Residual heat renoval pump 1.

Within < hours following ccmpletion of each valve stroking coeration or mainte..anco on

..".e valve when the EC."S sub-systms are required to be OPERA8LE.

• Tne provisions of Specification 4.0.6 are applicable..

107 aenment No.

19S psig g.

By verifying..'.e c"rrect posit'on of e*ch meehan',cal Stop for the the following.-.,er"ency Core Ccoling System throttle 'valves:

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CONTAItltAEHT SYSTEMS SUPVEiL'NCE RE UiR-":'l HT (Cont',nued) c.

At least once per 18 months during shutdown, by:

1.

Cyclino each power operated (excluding automatic) valve in the flow path that is not testable during plant operation, through at least one cori,piete cycle o full trave).

2.

Verifying that each automatic valve in the flow path actuates to its correct position on a Containment Pressure High-High signai.

• d.

At least once per 5 years by verifying a water flow rate of at least

'20 gpm (> 20 gpm) but not to exceed 50 gpm (< 50 gpm) from the spray additive tank test line to each containment spray 'sys'em with the spray pump operating on recirculation with a pump discharge pressure

> 255 psig.

• The provisions of Specification 4.0.6 are applicable.

0.

C.

COOK - UNiT 1

3/4 6-13 Amendment Ho. 107

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) valve or its associated

actuator, control or power circuit by performance of the cycling test,

above, and verification of isolation time.

4.6.3.1.2 Each isolation valve soecified in Table 3.6-1 shall be demon-strated OPERABLE during"the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

• a ~

b.

Verifying that on q Phase A containment isolation test each Phase A isolation valve actuates to its isolation Verifying that on a Phase B containment isolation test each Phase B isolation valve actuates to its isolation

signal, position.

signal, posltlon

~

c., Verifying that on a Containment Purge and Exhaust isolation

signal, each Purge and Exhaust valve actuates to its isolation position.

C 4.6.3.1.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

• The provisions of Specification 4.0.6 'are applicable.

r D.

C.

COOK-UNIT 1

3/4 6-15 Amendment No.

CONTAINMENT SYSTEMS ICE CONDENSER DOORS LIMITING CONDITION FOR OPERATIOH 3.6.5.3 The ice condenser inlet doors, intermediate deck doors, and top deck doors shall be closed and OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACi!ON:

Kith one or more ice condenser doors open or otherwise inoperable, POKER OPERATION may continue for up to 14 days provided the ice bed temperature

~s monitored at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the maximum ice bed temperature is maintained

~ 27'F; otherwise, restore the doors to their closed posi-tions or OPERAFLE status (as applicable) within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STAHDBY 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REOUIREMENTS 4.6.5.3.1 Inlet Doors ; Ice condenser inlet doors shall be:

a.

Continuously monitored and determined closed by the inlet door position monitoring system.

and b.

Demonstrated OPERABLE during shutdown (MODES 5 and 6) at least once per 9 months 'by+

2.

'3.

Verifying that the torque required to initially open each door is c 675 inch pounds.

Verifying that opening of each door is not impaired by ice, frost or debris.

Testing a sample of at least 50of the doors and veri-fying that the torque required to open each door is less than 195 inch-pounds when the door is 40 degrees open.

This torque is defined as the "door opening torque" and is equal to the nominal door torque plus a frictional

• The provisions of Specification 4.0.6 are applicable.

D.

C.

COOK-UNIT 1

3/4 6-30 Amendment No. 107

CONTAINMENT SYSTEMS INLET DOOR POSITION MONITORING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.5.4 The inlet door position monitoring system shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With the inlet door position monitoring system inoperable, POWER OPERATION may continue for up to 14 days, provided the ice bed temperature monitoring system is OPERABLE and the maximum ice bed temperature is < 27'F when monitored at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, restore the inlet door position monitoring system to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN 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 COLD SHUTDOWN 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 4.6.5.4 The inlet door position monitoring system shall.be determined OPERABLE by:

a

~

b.

c

~

Performing a

CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, Performing a

CHANNEL FUNCTIONAL TEST at least once per 18

months, and

• Verifying that the monitoring system correctly indicates the status of each inlet door as the door is opened and reclosed during its testing per Specification 4.6.5.3.1.*

• The provisions of Specification 4.0.6 are applicable.

D. C.

COOK-UNIT 1 3/4 6-33 Amendment No. 107

CONTAINi~iE!iT SYSTEMS DIVIDER BARRIER PERSONNEL ACCESS DOORS AND EQUIPMENT HATCHES LIMITING CONDITION FOR OPERATION 3.6.5.5 The personnel access doors and equipment hatches between the containment's upper and lower compartments shall be OPERABLE and closed.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With a pe'rsonnel access door or equipment hatch inoperable or open except for personnel transit entry and T

> 200'F, restore the door or hatch to OPERABLE status or to its clos'e3 !Iosition (as applicable) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY 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 COLD SHUTDOWN 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

'. 6.5. 5. 1 The personnel access doors and equipment hatches between the containment's upper and lower compartments shall be determined closed by a visual inspection prior to increasing the Reactor Coolant System T

above 200'F and after each personnel transit entry when the Reactor Coolant System -T, is above 200'F.

avg 4.6.5.5.2 The personnel access doors and.equipment hatches between the containment's upper and lower compartments shall be determined OPERABLE by visually inspecting the seals and sealing surfaces of these penetra-tions and verifying no detrimental misalignments, cracks or defects in the sealing surfaces, or apparent deterioration of the seal material:

a.'.

Prior to final closure of the penetration each time it has been

opened, and At least once per 10 years for penetrations containing seals fabricated from resilient materials/

• The provisions of Specification 4.0.6 are applicable.

D.

C.

COOK-UNIT 1 3/4 6-34 Amendment No. 107

PLANT SYSTBlS 3/4.7,3 COMPONENT COOLING WATER SYST~c.

LIMITING CONDITION FOR OPERATION 3.7.3.1 At least two independent component cooling water loops shall be OPERABLE.

APPLICABILITY:

MODES 1. 2, 3 and 4.

ACTION:

With only one component cooling water loop OPERABLE, restore at leas 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 STANDBY 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 SHUTDOWN within the follow-ing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REOUI REHENTS 4.7.3.1 At leas two component cooling 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 reiated equip-ment that is not locked,

sealed, or otherwise secured in position, is in its correct position.

b.

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.*

l c-At least once per 31 days on a STAGGpp~D T"-S~ pAS~S, by verifying that each pump'evelops at least 93% of the discharge pressure for the applicable flo~ rate as determined from the manufac"urerumo pe ormance Curve.

• The provisions of Specification 4.0.6 are applicable.

C.

COOK - UNIT 1

3/4 7-15 Amendmen~

No.

1p7

PLANT SYSTEMS 3/4,7.4 ASSENT?AL

""RYIC" MAT:R SYS: ":8 LIMITING CONDITION FOR OPcVTiON 3.7.4.1 At least two independent essential service water loops shall be OPERABL"-.

APPL ICAB 'T.:

MOD" S 1

2 3 and 4.

ACi:ON:

M)th only one service wate.

locp CPEVBL"", restore at least two loops

.o OP=BABLE status within 72 ho.rs cr be in 'at lees.

HOT STANDBY within the next o hours an" in COLD SHI~iDC~N within the'ol',owing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURY-L~ "C=

"".= l;".~("

4.7.4.1 At leas.

t'm essent al servic wate.

loops shall be deecnstrated OPERABLE:

a.

At least once per 31 days by verify'.rg that each valve (manual, power coer ated or auto;..atic) servic r.= safety related equip-ment that is not locked, se led,.or o.nerwise secured in

position, is in its correct posi.ion.

b.

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

c.

At leas o.".ce pe" 31 days o.". a S,A" ZB=D K5T BASZS, by verifying that ea=h pv p develops at leas 93% of the discharge press@re for the applicable flo~ rate as de-e.,ed

~-om the maze act'er's ~p perfor~ice C'-'rve.

• T¹ provis'ns of Specificatio~ 4.0.6 are.applicable.

D. C.

COOK - UNIT 1

3/4 7-17 Ameridment No.

107

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS Continued) 1.

Verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister demonstrates a removal efficiency of > 90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510 - 1975 (130'C, 95/ R.H.); or 2.

Verifying within 31 days after removal that a laboratory analysis of at least two carbon samples demonstrate a

removal efficiency of > 90/ for radioactive methyl iodide when the samples are tested in accordance with ANSI N510 - 1975 (130'C, 95/ R.H.) and the samples are prepared by either:

a)

Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or b)

Emptying a longitudinal sample from an adsorber tray, mixing, the adsorbent thoroughly, and obtaining samples at least two inches in diameter and wi th a length equal to the thickness of the bed.

Subsequent to reinstalling the adsorber tray used for obtaining the carbon

sample, the system shall be dem-onstrated OPERABLE by also:

a)

Verifying that the charcoal adsorbers remove

> 99%

of a halogenated hydrocarbon refrigerant test gas

'hen they are tested in-place in accordance with ANSI N510 - 1975 while operating the ventilation system at a flow rate of 6000 cfm + 10/, and b)

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 ventilation system at a flow rate of 6000 cfm + 10/.

D. C.

COOK-UNIT 1

3/4 7-21

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS Continued)

At least once per 18 months by:

l.

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is (

6 inches Water Gauge while operating the ventilation system at a flow rate of 6000 cfm + 10>>.

2.

Verifying that on a Safety Injection Signal from either Unit 1 or Unit 2, or on a containment phase A isolation

signal, the system automatically diverts its inlet flow through the HEPA filters and charcoal adsorber bank and that either fan can then be manually started in the re-circulation mode.

• I 3.

Verifying that the system maintains the control room at a positive pressure of > 1/16 inch W.

G. relative to the outside atmosphere at a system flow rate of 6000 cfm

+ 10'.

f.

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 ventilation system at a

flow rate of 6000 cfm + 10%.

g.

After each complete or par.tial'replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove

> 99ll of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm + 10;.

• The provisions of Specification 4.0.6 are applicable.

D. C.

COOK-UNIT 1

3/4 7-22 Amendment No. 107

PLANT SYSTEH SURVEILLANCE REOJIREt1Ef! TS (Continued) b)

Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining s8mples at least two inches in diameter and with a length equal to the thickness of the bed.

Subsequent to reinstalling the adsorber tray used for obtaining the carbon

sample, the system shall be demonstrated OPERABLE by also:

a)

Verifying that the charcoal adsorbers remove

> 99il of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 25,000 cfm + 10,'l and b)

Verifying that the HEPT.filter banks remove

> 99".of the DOP when they are tested in-place in accordance with ANSI N510 - 1975 while operating the ventilation system at a

flow rate of 25,000 cfm + 10'.

d.

At least once per 18 months by:

l.

Verifying that 'the pressure drop accross the combined HEPA filters and charcoal adsorber banks is

< 6 inches Hater Gauge while operating the ventilation system at a flow rate of 25,000 cfm + 10%.

2.

Verifying that the air flow distribution is uniform within 20ll accross HEPA filters and charcoal adsorbers when test-ed in accordance with ANSI N510 - 1975.

3.

Verifying that the standby fan starts automatically on a

Containment Pressure--High-High Signal and diverts its exhaust flow through the HEPA filters and charcoal adsorbe; banks on a Containment Pressure-High-High Signal.

• e, After each complete or partial replacement of HEPA filter band by verifying that the HEPA filter banks remove

> 99.'l of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 25,000 cfm + 10'.

f.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove

> 99 of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N51D-1975 while operat-ing the ventilation system at a flow rate of 25,008 cfm + 10'.

• The provisions of Specification 4.0.6 are applicable.

D.

C.

COOK UNIT 1

3/4 7-25 Amendment No.

107

PLANT SYSTEMS 3/4.7.7 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.7.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material, shall be free of > 0.005 microcuries of removable contamination.

APPLICABILITY: At all times.

ACTION a

~

Each sealed source with removable contamination in excess of the above limits shall be immediately withdrawn from use and:

1.

Either decontaminated and repaired, or 2.

Disposed of in accordance with Commission Regulations.

be The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4 '.7.1.1. Test Re uirements - Each sealed source shall be tested for leakage and/or contamination by:

a.

The licensee, or b.

Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.

4.7.7.1.2 Test Fre uencies - Each category of sealed sourc'es shall be tested at the frequency described below.

a.

Sources in use excludinq startu sources reviousl subjected to core flux

- At least once per six months for all sealed sources containing radioactive materials.

D.

C.

COOK-UNIT 1

3/4 7-26

ELECTBICA-'~-P SyS.

QHCE RE"U RZYZ::.6

{Continued) 0 2.

T'e p'lct ce'1 speci ic cravity, cc rected to 77 E ar.d full e'e=.rclyte level (fluid at, the bottom cf the rax'mu.-. leuc indicat'cn mark), is 1.200, 3.

The pilo= cell voltace is Z 2.10 volts, and 4.

The cveral'a:terv voltage is

~~ 250 volts.

b.

A

'east once pe" g2 days by verifying that:

The vcl"ace cf each ccnnected cell is > 2.10 volts under "ca: charge a.".d has not decreased more than 0.05 volts fr:.-. the va:ue observed during the or'ginal accep ance

test, and

.he s"ec'f " grav. ty; corrected to 77

.= and full 0

electrvly-.

level (fluid a the bcttcm of the maximum

'e;e'-."'a on.-..ark), of eac?:

connected ce is >

and has rct decreased mere than 0.03 from the va' cbser:ed cu ng

=he previous test, and

.he elec r='vte 'eve'f each ccnr.ected cell is between t.".e

=" cf =he r;.'.-.Imum level indicat'on mark and the

'""::=;.. cf "he rrax'mur. 'evel incicat'cn mark.

'least "nce "e>>

16 months by ve"'fying that:

.he ce::s, cell pla es anc batte y racks show no visual

-'nd'ca cn cf phys cal damage c"" abnormal deterioration.

.?.e cel'--c-cell ar.d te mr.nal connections are clean, t'gh

, free c: ccrrosior.

and coated with anti-corrosion mater

3.

he ba =cry cha cer will su>>plv at least 140 amperes at 250 vc'

or at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

d.

A" least once "er 16 rrcnths; dur'ng snutdown (MODES 5 or 6), b! verifying that the ba tery capac'ty is adequate to su""'

and na~ntair.

>n OpERAS' status the emercency loads for the t mes spec'f'ed xn Table 4,6-1A with the battery char"er c'scc.".nected.

The battery terminal voltage shall be rainta.ned

'" volts thrcughout the battery service test.

e.

At least ence pe 60 mcnths, du ing shutdown (MODES 5 or 6), by verifv'..c tha-the battery capacity is at least 80%

of the manufacturer's rating when subjected to a performance discharce test.

Th's performance discharge test shall be pe" crmed in p'ace of the battery service test.

V

~ The provisions of Specification 4'.6 are applicable.

D.

C.

Cook - Unit 1 3/4 8-9 Amendment No.

1Q7

ELECTRICAL POWER SYSTEMS D.C.

DISTRIBUTION -

SHUTDOWN L IMI T IN G CONDITION FOR OP ERATI ON 3.8.2.4 As a minimum, the following D.C. electrical equipment and bus shall be energized and OPERABLE:

1

-. 250-volt D.C. bus, and

~ 1 - 250-volt battery bank and charger associated with the above D.C. bus.

APPLICABILITY:

MODES 5 and 6.

ACTION

'ithless than the above. complement of D.C. equipment and bus

OPERABLE, establish CONTAINMENT INTEGRITY within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILLANCE REQUIREMENTS I

4.8.2.4.1 The above required 250-volt D.C.'us shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.

4'.8.2.4.2 The above required 250-volt battery bank and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2. *

• The provisions of Specification 4.0.6 are applicable.

0.

C.

COOK - UNIT 1

3/4 8-12 Amendment No.