Text

Forwards Tech Spec Changes Since .Tech Specs Reflect Plant Design & Operating Program Described in Fsar. Changes Considered Complete for OL Issuance
	ML20091G399
Person / Time
Site:	Callaway
Issue date:	05/31/1984
From:	Schnell D; UNION ELECTRIC CO.
To:	Harold Denton; Office of Nuclear Reactor Regulation
References
	ULNRC-835, NUDOCS 8406040258
	Download: ML20091G399 (32)
	v • d • e

-

e - . .. - - 43 U NION ELECTRIC COM PANY 1901 GRATIOT STREET ST. Louis. MISSOURI MAIUNG ADDRE. 5

"^t..:.."!"~'"

. May 31, 1984 =r.Loui.7 7.*o'JR .u..

Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

ULNRC-835 DOCKET NUMBER 50-483 CALLAWAY PLANT, UNIT 1 CALLAWAY TECHNICAL SPECIFICATIONS

References:

1) VLNRC-792 dated April 9, 1984

2) ULNRC-816 dated May 11, 1984

Attachment:

Specifications Changed Since Reference 2

. 4 In the referenced letters' Union Electric affirmed the accuracy of Callaway Technical- Specifications. The attachment to this letter contains specifications which have changed since Reference 2 and which have been resolved ' between Union Electric and the Staff. With these changes we consider the Callaway Technical Specifications complete for OL issuance.

In my judgement, the Callaway Techni:al Specifications accurately reflect the plant design and operating program at described in the FSAR and other information on our docket.

Very truly yours, Donald F. Schnell DS/nld Attachment cc: J. Holonich F. Anderson phi I

s

.\

l 8406040256 840531

, PDR ADOCK.05000483 A PM ,

l STATE OF MARYLAND )

) SS COUNTY.OF MONTG0MERY )

Donald F. Schnell, of lawful age, being first duly sworn upon oath says that he is Vice _ President-Nuclear and an officer of Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on ,

behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.

By ~~,

Donald F. Schnell Vice President -

'luclear SUBSCRIBED and sworn to before me this DIM day of ,198h

%wA' Diane Carole Kavanagh.

l My Commission Expires: 7/1/8h e

l

I

. cc: Glenn L. Koester Vice President Operations Kansas Gas & Electric P.O. Box 208 Wichita, Kansas 67201 Donald T. McPhee Vice President Kansas City Power and Light Company 1330 Baltimore Avenue Kansas City, Missouri 64141 Gerald Charnoff, Esq.

Shaw, Pittman, Potts & Trowbridge 1800 M. Street, N.W.

Washington, D.C. 20036 Nicholas A. Petrick Executive Director SNUPPS 5 Choke Cherry Road v Rockville, Maryland 20850 John H. Neisler Callaway Resident Office U.S. Nuclear Regulatory Commission RR$1 4

. Steedman, Missouri 65077 William Forney Division of Projects and Resident Programs, Chief, Section lA U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little 4

Callaway Resident Office U.S. Nuclear Regulatory Commission RR41 Steedman, Missouri 65077

. o UIRRC-835 ATTACHMENT SPECIFICATIONS CHANGED SINCE REFERENCE 2 INDEX

' Item Paga

Agree Open Issue

-1 2-2 X Typo 2 3/4 2-15 X " Actual" versus " Indicated" 3 3/4 3-49 X Remote Shutdown Instrumentation 4 3/4 3-50 X Remote Shutdown Instrumentation 5 3/4 3-51 X Remote Shutdown Instrumentation 6 3/4 3-56 X Typo 7 3/4 3-68 X Typo 8 3/4 4-2 X RCP Special Test Exception and Typo

-9 3/4 6-15 X Containment Cooling 10 3/4 6-26 X Typo

11 3/4 7-13 X Ultimate Heat Sink 12 3/4 8-9 X Battery Float Voltage 13 3/4 8-10 X Battery Float Voltage 14 3/4 8-12 X Deletion of an Action Statenent 15 3/4 8-16 X Contairynent Penetration Conductor 16 3/4 8-34 X Typo 17 3/4 B-35 X Typo 18 3/4 8-43 X Typo 19 3/4 9-7 X Refueling Spec.

20 3/4 10-4 X RCP Special Test Exception 21 B3/4 0-1 X " Actual" versus " Indicated" 22 B3/4 0-2 X Editorial 23 B3/4 0-3 X Editorial 24 B3/4 2-6 X " Actual" versus " Indicated" 25 B3/4 4-2 X Pressurizer Bases 26 B3/4 4-16 X Typo 27 B3/4 6-2 X Structural Integrity 28 6-3 X Organization Chart

Pages are attached

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1 TABLE 3.2-1 '

S.,

p DNB PARAMETERS .

y . .

A

, . LIMITS c

5' Four Loops in Three Loops in

. PARAMETER' Operation Operation w ,

Indicated Reactor Coolant System T,,g 5 592.5'F ,

l Indicated Pressurizer Pressure > 2220 psig* **

4 R.

.7 G

+

i 1.;

l~ " Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL

. POWER per minute or a THERMAL POWER step in excess of 10% of RATED THERMAL POWER. ,

- **These values left blank pending NRC approval of three loop operation. ,

)- l l'

l l8 'l-

+ 1 i

l INSTRUMENTATION l

REMOTE SHUTDOWN INSTRUMENTATION ,

\ .

LIMITING CONDITION FOR OPERATION _

3.3.3.5 The remote shutdown monitoring instrumentation channels given in Table 3.3-9 and the auxiliary shutdown panel (ASP) controls shall be OPERABLE with readouts displayed external to the control room.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With the number of OPERABLE remote shutdown monitoring channels less than the Minimum Channels CPERABLE required by Table 3.3-9, restore the inoperable channel (s) to OPERABLE status within 7 days; otherwise, 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With the ASP controls inoperable, restore the inoperable ASP controls to OPERABLE status within 7 days; otherwise, 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. The provisions of Specification 3.0.4 are not applicable.

I SURVEILLANCE REQUIREMENTS 4.3.3.5.1 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL LAL1HMA110N operations at the frequencies given in Table 4.3-6.

4.3.3.5.2 The ASP controls shall be demonstrated OPERABLE at least once per 18 months, by operating each actuated component from the ASP.

4.3.3.5.3 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 for the turbine-driven auxiliary feedwater pump or the atmospheric dump valves.

( .

CALLAWAY - UNIT 1 3/4 3-49

cs i

( -

TABLE 3.3-9 REMF]SHUTDOWNMONITORINGINSTRUMENTATION TOTAL NO. MINIMUM READOUT OF CHANNELS LOCATION CHANNELS OPERABLE INSTRUMENT RCS Pressure-Wide Range ASP

2 1 1.

2. Reactor Coolant Temperature-Cold Leg ASP

4 1 Source Range Neutron Flux ASP

2 1 3.

4. Reactor Trip Breaker Indication RTS** 1/ trip breaker 1/ trip breaker Reactor Coolant Temperature - ASP

2 1 5.

Hot Leg Reactor Coolant Pump Breakers *** 1/ pump 1/ pump 6.

1 1-

7. Pressurizer Pressure ASP

dSP" 2 1

8. Pressurizer Level

( 2/sta, gen. 1/sta. gen.

9. Steam Generator Pressure ASP

ASP

2/sta. gen. 1/stm. gen.

10. Steam Generator Level Auxiliary Feedwater Flow Rate ASP

4 1 11.

12. Auxiliary Feedwater Suction ASP

3 1 Pressure

^ Auxiliary Shutdown Panel

- Reactor Trip Switchgear

- - 13.8 kV Switchgear CALLAWAY - UNIT 1 3/4 3-50

-- - - ~,- - .-- ,. - .. . ,.

l -

TABLE 4.3-6 -

REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL CHECK CALIBRATION INSTRUMENT RCS Pressure - Wide Range M R 1.

Reactor Coolant Temperature - Cold Leg M R 2.

Source Range, Neutron Flux M R 3.

4. Reactor Trip Breaker Indication M N.A.

Reactor Coolant Temperature - Hot Leg M R 5.

6. Reactor Coolant Pump Breakers N.A. N.A.

Pressurizer Pressure M R 7.

Pressurizer Level M R

8. .

9. Steam Generator Pressure M R g

Steam Generator Level M R

10. ,

11. Auxiliary Feedwater Flow Rate M R i

12. Auxiliary Feedwater Pump Suction Pressure M R 4

4 CALLAWAY - UNIT 1 3/4 3-51

_f-TABLE 4.3-7 (Continued)

TABLE NOTATIONS

Not applicable if the associated block valve is in the closed position.

- Not applicable if the block valve is verified in the closed position and power is removed.

- - CHANNEL CALIBRATION may consist of an electronic calibration of the channel, not including the detector, for range decades above 10R/h and a one point calibration check of the detector below 10R/H with an installed y portable l gamma source. or I

4 1

1 l

i 4

CALLAWAY - UNIT 1 3/4 3-56

INSTRUMENTATION RADIOACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specifications 3.11.2.1 and 3.11.2.5 are not exceeded.

The Alarm / Trip Setpoints of these channels meeting Specification 3.11.2.1 shall be determined and adjusted in accordance with the methodology and parameters in the 00CM.

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

a. Witharadioactivegaseouseffluentmoddjoringinstrumentation l 4 channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7, why this inoperability was not corrected within the time specified. -

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous affluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequen-cies shown in Table 4.3-9.

l i

CALLAWAY - UNIT 1 3/4 3-68

. ~ . _ . - .. _ -

l REACTOR COOLANT SYSTEM HOT STAND 8Y .

LIMITING CONDITION FOR OPERATION 3.4.1.2 At least three of the reactor coolant loops listed below shall be OPERABLE and at least two of these reactor coolant loops shall be in operation:*

7

. a. Reactor Coolant Loop A and its associated steam generator and reactor coolant pump, ,

1 l b. Reactor Coolant Loop 8 and its associated steam generator and reactor coolant pump, j

i c. Reactor Coolant Loop C and its associated steam generator and I reactor coolant pump, and

d. Reactor Coolant Loop D and its associated steam generator and reactor coolant pump.

< l

! APPLICABILITY: MODE 3**. l 1

i I ACTICN: ~

i j a. With less than tre above required reactor coolant loops OPERA 8LE, i restore the required loops to OPERA 8LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be l, in HOT SHUTD0WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . ,

t i b. With only one reactor coolant loop in operation, restore at least two l

loops to operation within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

) c. With no reactor coolant loop in operation, suspend all operations j involving a reduction in baron concentration of the Reactor Coolant j System and immediately initiate corrective action to return the required reactor coolant loop to operation.

i I SURVEILLANCE REQUIREMENTS __,

a l l 4.4.1.2.1 At least the above required reactor coolant pumps, if not in l l operation, shall be determined OPERABLE once per 7 days by verifying correct t breaker alignments and indicated power availability.

4.4.1.2.2 The required steam generators shall be determined 0PERA8LE by verifying secondary side wide range water level to be greater than or equal to 105 at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l

' 4.4.1.2.3 At least two reactor coolant loopsshall be verified in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

! All reactor coc f ant pumps may be deenergized for up to I hour provided:

! (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature.

- $ee Special Test Exception Specification 3.10.4.

-CALLAWAY - UNIT 1 3/4 4-2

_. __ . . ~ _ . _ . _ _ _ _ . _ _ _ _ _.._. _ _ _ _ _ _ _ _ -

CONTAINMENT SYSTEMS 1 CONTAINMENT COOLING SYSTEM L

! LIMITING CONDITIONS FOR OPERATION l' . .

3.6.2.3' Two independent groups of containment cooling fans shall be OPERABLE with two fan systems to each group.

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

ACTION:

a. With one group of the above required containment cooling fans

} inoperable and both Containment Spray Systems OPERABLE, restore the .

4 inoperable group of cooling fans to OPERABLE status within 7 days or l 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 '

j SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

>l b. With two groups of the above required containment cooling fans

} inoperable and both Containment Spray Systems OPERABLE, restore at j least.one group of cooling fans 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 STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD I

SHU1DOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Restore both above required groups of cooling fans to OPERABLE status within 7 days of initial

, loss or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in j COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With one group of the above required containment cooling fans F

inoperable and one Containment Spray System inoperable, restore the inoperable Containment Spray System to OPERABLE status within 72 ;

hours 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 SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Restore the inoperable i

', group of containment cooling fans to OPERABLE status within 7 days j of initial loss or be in at least HOT STAND 8Y within the next i j 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 4.6.2.3 Each group of containment cooling fans shall be demonstrated OPERABLE:

{

a. At least once per 31 days by:

! 1) Starting each non-operating fan group from the conLtrol room,

{ and verifying that each fan group operates for at least 1

15 minutes, and l 2) Verifying a cooling water flow rate of greater than or equal to 2200 gpa to each cooler group.

4

! b. At least once per 18 months by verifying that on a Safety Injection )

l test signal, the fans start in slow speed or, if operating,~ shift to )

j slow speed and the cooling water flow rate increases to at least 4000

gpm to each cooler group.

! CALLAWAY - UNIT 1 3/4 6-15 l

, _~. ,_.,..,- .._ n., , , , . . . _ . , , . , . - - , . , - . . . . - _ , ,,_%.w,_,, , . . _ -e +- - , _ . - , , , , .. , , , . . ,.-

- ~

TABLE 3.6-1 (Continued}

~

CONTAINMENT ISOLATION VALVES MAXIMUM TYPE LEAK ISOLATION TIME PENETRATIONS VALVE NUMBER FUNCTION TEST REQUIRED (Seconds) 6.

Remote Manual - (Continued)

P-79 EJ HV-8701A RCS Hot Leg 1 to RHR A N.A.

Pump A Suction P-52 EJ HV-87018 RCS Hot Leg 4 to RHR A N.A.

Pump B Suction P-82 EJ HV-8809A RHR Pump A Cold Leg A N f.

Injection Iso Valve P-27 EJ HV-88098 RHR Pump B Cold Leg A N.A.

Injection Iso Valve P-15 EJ HV-8811A CTMT Recirc Sump to A N.A.

RHR Pump A Su, pion

' t P-14 EJ HV-8811B CTMT Recirc Sump to A N.A.

RHR Pump B Supton L.

P-21 EJ HV-8840 RHR Hot Leg Recirc A N.A.

Iso Valve P-87 EM HV-8802A* SI Pump A Disch Hot A N.A.

Leg Iso Valve P-48 EM HV-88028* SI Pump B Disch Hot A N.A.

Leg Iso Valve P-49 EM HV-8835 SI Pumps Disch to A N.A.

, Cold Leg Iso Valve P-89 EN HV-6 CTNT Spray Pump A A N.A.

Discharge Iso Valve P-66 EN HV-12 CTMT Spray Pump 8 A N.A.

Discharge Iso Valve

7. Active for SIS P-80 BG HV-8105 CVCS Charging Line C 10 I

CTh;se valves were assumed to be closed during the accident analysis and are normally clos:d but may be opened on an intermitcent basta uider administrative control.

t CALLAWAY - UNIT 1 3/4 6-26

'ya4 PLANT SYSTEMS

=

l 3/4.7.5 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.5 The ultimate heat sink (UHS) shall be OPERABLE with:

a. A minimum water level at or above 13.25 feet (El 831.25 feet MSL) from the bottom of the UHS,

b. An average water temperature of less than or equal to 90'F, and

c. Two UHS cooling tower trains (2 cells per train). ,

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

ACTION:

With the UHS inoperable, restore the UHS 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 STANDBY 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 .

t SURVEILLANCE REQUIREMENTS 4.7.5.1 The UHS shall be determined CPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the average water temperature and water level to be within their limits.

4.7.5.2 The UHS cooling tower trains shall be demonstrated OPERABLE at least once per 31 days by verifying that each cooling tower fan operates for at least 10 ..in ti3 ir, both ti.e slow and fast mode and at least once per 18 nonths by visually inspecting and verifying no abnormal breakage or degradation of the fill materials.

4.7.5.3 The UHS shall be determined OPERABLE at least once per 31 days by visually inspecting the UHS riprap for any abnormal degradation which might lead to blockage of the ESW pump suction. l O

CALLAWAY - UNIT 1 3/4 7-13

ELECTRICAL POWER SYSTEMS 3/4.8.2 D.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.1 As a minimum, the following D.C. electrical sources shall be OPERABLE:

a. 125-Volt Battery Bank NK11 and NK13, and its associated Full-Capacity Chargers NK21 and NK23, and

b. 125-Volt Battery Bank NK12 and NK14, and its associated Full-Capacity Chargers NK22 and NK24.

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

ACTION:

With one of the required battery banks and/or full-capacity chargers inoperable, restore the inoperable battery bank and/or full-capacity charger to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.8.2.1 Each 125-volt battery bank and charger shall be demonstrated OPERABLE:

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

1) The parameters in Table 4.8-2 meet the Category A limits, and

2) The total battery terminal voltage is greater than or equal to 130.2 volts on float charge.

1 CALLAWAY - UNIT 1 3/4 8-9 b

r; .

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. At least once per 92 days and within 7 days after a battery discharge with battery terminal voltage below 110 volts, or battery overcharge with battery terminal voltage above 150 volts, by verifying that:

1) The parameters in Table 4.8-2 meet the Category 8 limits,

2) There is no visible corrosion at either terminals or connectors, or the cell-to-cell and terminal connection resistance of these items is less than 150 x 10 s ohm, and

3) The average electrolyte temperature of at least every sixth cell is above 60*F.

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, and coated with anticorrosion material,

3) The resistance of each cell-to-cell and terminal connection is less than or equal to 150 x 10 8 ohn, and

4) The battery charger will supply at least 300 amperes at 130.2 volts for at least I hour,

d. At least once per 18 months, during shutdown, by verifying that the battery capacity is adequate to supply and maintain in OPERA 8LE status simulated emergency loads for the design duty cycle when the battery is subject to a battery service test;

e. At least once per 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. Once per 60 month interval this performance discharge test may be performed in lieu of the battery service test required by Specification 4.8. 1d. ; and

f. At least once per 18 months during shutdown, by giving performance discharge tests of battery capacity to any battery that shows signs of degradation or has reached 85% of the service life expected for the application._ Degradation is indicated when the battery capacity drops more than 10E of rated capacity from its average on previous performance tests, or_is below 905 of the manufacturer's rating.

CALLAWAY - UNIT 1 3/4 8-10

ELECTRICAL POWER SYSTEMS .

D.C. SOURCES I SHUTDOWN ".

LIMITING CONDITION FOR OPERATION 3.8.2.2 As a minimum, the following D.C. electrical sources shall be OPERABLE:

a. 125-Volt Battery Bank NK11 and NK13, and its associated Full-Capacity Chargers NK21 and NK23, or

b. 125-Volt Battery Bank NK12 and NK14, and its associated Full-Capacity Chargers NK22 and NK24.

APPLICABILITY: MODES 5 and 6.

ACTION:

With the required battery bank and/or full-capacity charger inoperable, immedi-ately suspend all operations involving CORE ALTERATIONS, positive reactivity changes or movement of irradiated fuel; initiate corrective action to restore .

the required battery bank and/or full-capacity charger to OPERABLE status as soon as possible.

SURVEILLANCE REQUIREMENTS 4.8.2.2 The t.bove required 125-volt battery banks and associated chargers shall be demr.nstrated OPERABLE in accordance with Specification 4.8.2.1.

k l

~ '

CALLAWAY - UNIT 1 ,

3/4 8-12 .

l -

l ILECTRICAL POWER SYSTEMS

, 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES

( CONTAINMENT. PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES 1

LIMITING CONDITION FOR OPERATION 3.8.4.1 All containment penetration conductor overcurrent protective devices given in Table 3.8-1 shall be OPEAABLE.

. i 1

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

ACTION:

With one or more of the above required containment penetration conductor overcurrent protective device (s) inoperable:

1

a. Restore the protective device (s) to OPERABLE status or deenergize l

l the circuit (s) by tripping the associated backup circuit breaker, or racking out or removing the inoperab's circuit breaker within ,

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , declare the affected system or component inoperable, and verify the backup circuit breaker to be tripped or the inoperable

circuit breaker racked out, or removed, at least once per 7 days

! thereafter; the provisions of Specification 3.0.4 are not applicable l

' to overcurrent devices in circuits which have their backup circuit breakers tripped, their inoperable circuit breakers racked out, or

( removed, or

! b. Be in at least NOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD t SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ql l SURVEILLANCE REQUIREMENTS j 4.8.4.1 All containment penetration conductor overcurrent protective devices i given in Table 3.8-1 shall be demonstrated OPERABLE:

1

a. At least once per 18 months:

1) Sy verifying that the 13.8 kV circuit breakers are OPERABLE by i selecting, on a rotating basis, at least 10% of the circuit i

breakers, and performing the following-i I a) A CHA.'NEL CALISRATION of the associated protective relays, b) An integrated system functional test which includes simulated i

i automatic actuation of the system and verifying that each i

relay and associated circuit breakers and control circuits function as designed and as specified in Table 3.8-1, and 4

l CALLAWAY - UNIT 1 3/4 4-16

. . n

, +wi,.m - - - - -.-+,------c-- 5 w -. -e-w -%~a-e -- -- w.+- --

+--pm,--,-e-----ig, H--e --+w.. .- *-p-

u TABLE 3.8-1 (Continued)

CONTAINMENT PENETRATION CONDUCTOR l OVERCURRENT PROTECTIVE DEVICES ,

[ ,

PROTECTIVE DEVICE POWERED NUMBER AND LOCATION EQUIPMENT Low Voltage Power and Control (Continued) i 10BK40A P-30A Fuse PZR PORY NK5108 B-30A Fuse BBPCV455A l

4BBK04B P-30A Fuse PZR PORV NK4421 B-30A Fuse BBPCV456A 5BGK04B P-3A Fuse Alternate Charging Path Isol Valv RLOO1 8-3A Fuse BGHV8147 6BGK04A P-3A Fuse Normal Charging Path Isol Valv RL001 8-3A Fuse BGHV8146 P-5LFY10A 3A Fuse Containment Cooler Drain Valve RLO23 LFLV97 B-5RLYO1H ISA Breaker PG19GCR217 P-5LFY10C 3A Fuse .

Containment Cooler Drain Valve RLO23 LFLV99

( B-5RLYO1H 15A Breaker PGI9GCR217 P-6LFY10B 3A Fuse Containment Cooler Drain Valve RLO23 LFLV98 B-6RLYO1G 15A Breaker PG20GBR217 P-6LFY100 3A Fuse -

Containment Cooler Drain Valve RLO23 LFLV100 2-69LYO1G 15A Breaker PG20GBH217 P-6LFY17A 3A Fuse Refueling Pool Stand Pipe RLO23 Discharge Valve B-6RLY01G 15A Breaker LFLV122 PG20GBR217 P-5LFY20A 15A Breaker Instrument Tunnel Susp Moisture PG19NHF224 Sensor B-5LFY20A 304 Fuse TLVF01 PG19NHF1 l

CALLAWAY - UNIT 1 3/4 B-34

. . TABLE 3.5-1 (Centinued)

CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES .

( .

PROTECTIVE DEVICE POWERED NUMBER AND LOCATION EQUIPMENT Low Voltage Power and Control (Continued)

P-6LFY208 15A Breaker Instrument Tunnel Sump Moisture PG20NBR216 Sensor B-6LFY208 30A Fuse TVLF02

. PG20NBR1 P-5SDYO6C 15A Breaker Local Radiation Monitor Power PG19NHF215 Supplies B-550YO6C 30A Fuse SPRIA39-42 PG19NHF1 P-ISJYO10 3A Fuse Press. Ctat Isol Viv RLO11 SJHV128 '

B-IRLYO1G 15A Breaker NG01ACR119 P-45JY01A 3A Fuse Press. Liq /HL 1&3 Sample Clr Viv RLO11 SJHV5 B-4RLYO1G 15A Breaker .

NG02ACR140 1GTK03C P-3A Fuse Ctat Purge Isol Viv

RLO20 B-3A Fuse GTHZ7

, P-1GSY01E 3A Fuse Hydrogen Analyzer Ctat Sample */1v RL011 G5HV14 B-1RLYO1G 15A Breaker NG01ACR119 P-1GSY01F 3A Fuse Hydrogen Anal Samp Return to Ctat Viv

RLO11 G5HV18 B-1RLYO1G 15A Breaker NG01ACR119 Hydrogen Anal Ctat Sample Viv P-4G5Y01A 3A Fuse RL011 G5HV4 B-4RLY01G NG02ACR140 15A Breaker P-4G5YO18 3A Fuse Hydrogen Anal Ctat Sample V1v RLC11 85HV5 B-4RLY01G 15A Breaker NG02ACR140 I

CALLAWAY - UNIT 1 3/4 8-35

n TABLE 3.8-1 (Continued)

CONTAINMENT PENETRATION CONDUCTOR

, OVERCURRENT PROTECTIVE DEVICES ',,

PROTECTIVE DEVICE POWERED NUMBER AND LOCATION EQUIPMENT Low Voltage Power and Control (Continued) 6GNG048 P-6A Fase Cavity Cooling Fan Discharge Damper

PG20N8F5 8-4A Fuse GNHZ48 j 1H8K03A P-3A Fuse RCDT Vapor Space CTNT Isol Viv RLO21 8-3A Fuse HBHV7126 l 6H8K04A P-3A Fuse RCDT Vapor Space CTMT Isol Viv

H8115 8-3A Fuse H8HV7127 5EPYO78 P-3A Fuse Accumulator Tank Discharge RPO43 8-15A C8-1 Valve Position Switch

! EPHV8808DA

, EPHV88088A 6EPY07A P-3A Fuse Accumulator Tank Discharge RPO44 8-15A C8-1 Valve Position Switch EFHV8808AA

. EPHV8808CA 6GTY12A P-15A Breaker CTMT Minipurge Exhaust PG20GBR134 8-20A Fuse Isolation Damper GTHZ41 6GTY12A P-15A Breaker CTMT Minipurge Exhaust PG20GBR134 8-20A Fuse Isolation Damper GTHZ42 P-55RYO9A 5A Fuse In-Core Neutron Monitoring Drive SR057 Unit Heater 8-55RYO9A 20A Breaker SROIA, 8

c!aGEr6 P-55RYO9A 5A Fuse In-Core Neutron Monitoring Drive SR057 Unit Heater 8 55RY09A 20A Breaker SR01C, D PG19GEF6 l

l CALLAWAY - UNIT 1 3/4 8-43 A

' REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) -

to removal of the reactor vessel head by performing a load test of at least 125%

, of the secondary automatic overload cutoff and demonstrating an automatic load i

cutoff when the refueling machine load exceeds the Setpoints of Specification 3.9.6a.2).

, 4.9.6.2 Each auxiliary hoist and associated load indicator used for movement of drive rods within the reactor vessel shall be demonstrated OPERA 8LE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to removal of the reactor vessel head by performing a load test !

of at least 1250 pounds.

i e

J i

)

e i

I CALLAWAY - UNIT 1 3/4 9-7 l

. SPECIAL TEST EXCEPTIONS 3/4.10.4 REACTOR COOLANT LOOPS -

f.. .

( LIMITING CONDITION FOR OPERATION

'.10.4 3 The limitations of the following requirements may be suspended:

a. Specification 3.4.1.1 - During the performance of startup and PHYSICS TESTS in MODE 1 or 2 provided:

1) The THERMAL POWER does not exceed the P-7 Interlock Setpoint, and

2) The Reactor Trip Setpoints on the OPERABLE Intermediate and Power Range channels are set less than or equal to 25% of RATED THERMAL POWER.

b. Specification 3.4.1.2 - During the performance of hot rod drop time measurements in MODE 3 provided at least three reactor coolant loops as listed in Specification 3.4.1.2 are OPERA 8LE.

APPLICABILITV: During operation below the P-7 Interlock Setpoint or performant.e of hot rod drop time measurements.

ACTION: *

( a.

,4 With the THERMAL POWER greater than the P-7 Interlock Setpoint during the performance of startup and PHYSICS TESTS, immediately open the Reactor trip breakers,

b. With less than the above required reactor coolant loops 0PERABLE during performance of hot rod drop time measurements, immediately place two reactor coolant loops in operation.

SURVEILLANCE REQUIREMENTS 4.10.4.1 The THERMAL POWER shall be determined to be less than P-7 Interlock Setp,oint at least once per hour during startup and PHYSICS TESTS.

4.10.4.2 Each Intermediate and Power Range channel, and P-7 Interlock shall be subjected to an ANALOG CHANNEL OPERATIONAL , TEST within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to initiating startup and PHYSICS TESTS.

4.10.4.3 At least the above required reactor coolant loops shall be determined

OPERA 8LE within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to initiation of the hot rod drop time measure-ments and at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during the hot rod drop time measurements by verifying correct breaker alignments and indicated power availability.

(

CALLAWAY - UN!1 1 3/4 10-4

l 3/4.0 APPLICABILITY BASES The specificatiens of this section provide the general requirements applicable to each of the Limiting Conditions for Operation and Surveillance Requirements within Section 3/4. In the event of a disagreement between the requirements stated in these Technical Specifications and that stated in an applicable Federal Regulation or Act the requirements stated in the applicable Federal Regulation or Act shall take precedence and shall be met.

3.0.1 This specification defines the applicability of each specification in terms of defined OPERATIONAL MODES or other specified conditions and is provided to delineate specifically when each specification is applicable.

3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Condition for Operation and associated ACTION requirement.

3.0.3 The specification delineates the measures to be taken for those circum-stances not directly provided for in the ACTION statements and whose occurrence would violate the intent of a specification. For example, Specification 3.5.2 requires two independent ECCS subsystems to be OPERABLE and provides explicit _

ACTION requirements if one ECCS subsystem is inoperable. Under the requirements ..

of Specification 3.0.3, if both the required ECCS subsystems are inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months measures must be initiated to place the unit 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 at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . As a further example, Specification 3.6.2.1 requires two Containment Spray Systems to be -

OPERABLE and provides explicit ACTION requirements if one Containment Spray System is inoperable. Under the requirements of Specification 3.0.3 if both the required Containment Spray Systems are inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months measures must be initiated to place the unit in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . It is acceptable to initiate and complete a reduction in OPERATIONAL MODES in a shorter time interval than required in the ACTION statement and to add the unused portion of this allowable out-of-service time to that period for opera-tion in subsequent lower OPERATIONAL MODE (S). Stated allowable out-of-service times are applicable regardless of the OPERATIONAL MODE (S) in which the inoperability is discovered but the times provided for achieving a mode reduction are not applicable if the inoperability is discovered in a mode lower than the applicable mode. For example, if the Containment Spray System was discovered to be inoperable while in STARTUP, the ACTION Statement would allow up to 156 hours0.00181 days 0.0433 hours 2.579365e-4 weeks 5.9358e-5 months to achieve COLD SHUTDOWN.

If HOT STANDBY is attained in 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months rather than the allowed 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months , 140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months would still be available before the plant would be required to be in COLD SHUTDOWN.

However, if this system was discovered to be inoperable while in HOT STANDBY, the -

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided to achieve HOT STANDBY would not be additive to the time available to achieve COLD SHUTDOWN so that the total allowable time is reduced from 156 hours0.00181 days 0.0433 hours 2.579365e-4 weeks 5.9358e-5 months to 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months .

CALLAWAY - UNIT 1 B 3/4 0-1

'APPLI'CABILITY BASES

3.0.4 This specification provides that entry into an OPERATIONAL MODE or other specified applicability condition must be made with: (1) the full cceple-ment of required systems, equipment, or components OPERABLE and (2) all other para-meters as specified in the Limiting Conditions for Operation being met without

regard for allowable deviations and out-of-service provisions contained in the

, ACTION statements.

The intent of this provision is to ensure that facility operation is not initiated with either required equipment or systems inoperable or other specified limits being exceeded.

Exceptions to this provision have been provided for a limited number of specifications when STARTUP with inoperable equipment would not affect plant safety.

These exceptions are stated in the ACTION statements of the appropriate specifications.

4.0.1 This specification provides that surveillance activities necessary to ensure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL MODES or other conditions for which the Limiting Conditions for Operation are applicable. Provisions for additional surveillance activities to be performed without regard to the applicable OPERATIONAL MODES or other conditions .

are provided in the individual Surveillance Requirements. Surveillance Requirements for Special Test Exceptions need only be performed when the Special Test Exception is being utilized as an exception to an individual specification.

4.0.2 The provisions of this specification provide allowable tolerances -

for performing surveillance activities beyond those specified in the nominal surveillance interval. These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations. The phrase "at least" associated with a surveillance frequency does not negate this

' allowable tolerance value and permits the performance of more frequent surveillance activities.

The tolerance values, taken either individually or consecutively over three tect intervals, are sufficiently restrictive to ensure that the reliaoility associated with the surveillance activity is not significantly degraded beyond that obtained from the nominal specified interval.

4.0.3 The provisions of this specification set forth the criteria for determination of compliance with the 0PERABILITY requirements _of the Limiting Conditions for Operation. Under these criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval. Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still

' meeting the Surveillance Requirements. - Items may be determined inoperable

during use, during surveillance tests or in accordance with this specification.

Therefore, ACTION statements are entered when the Surveillance Requirements 1 should have been performed rather than,at the time it is discovered that the tests were not performed.

CALLAWAY.- UNIT 1 8 3/4 0-2

_ ., , ...on.-

9- y. ----g--< -

mp.e.y -.cy-+-- -,99 --e-.-gy9-g- 1r .---ww.qy-q,.tr. w,%m gwe -w com --ywa.- 9e-*#g-T-w- --re'wv " w a'w eVF --e me N-=F-me*-et

APPLICABILITY BASES o 4.0.4 This specification ensures that the surveillance activities associated with a Limiting Condition for Operation have been performed within the specified time interval prior to entry into an OPERATIONAL MODE or other applicable. con-dition. -The intent of this provision is to ensure that surveillance activities have been satifactorily demonstrated on a current basis as required to meet the operability requirements of the Limiting Condition of operation.

Under the terms of this specification, for example, during initial plant STARTUP or following extended plant outages, the applicable surveillance activities must be performed within the stated surveillance interval prior to placing or returning the system or equipment into OPERABLE status.

4.0.5 This specification ensures that inservice inspection of ASME Code

' Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the Relief ASMEfromBoiler any and of thePressure Vessel Code above requirements has and Addenda as required by 10 CFR 50.55a.

been provided in writing by the Commission and is not a part of these Technical Specifications.

This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarification i

is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. For example, the requirements of Specification 4.0.4 to perform surveillance activities prior to entry into an OPERATIONAL MODE or other specified applicability condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps to be tested up to 1 week after return to normal operation. And for example, the Technical Specification definition of OPERABLE does not grant a grace period before a device that is not capable of performing its specified function is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

4 e

a CALLAWAY - UNIT I B 3/4 0-3

e . o _.

I

, POWER DISTRIBUTION LIMITS l BASES QUADRANT POWER TILT RATIO (Continued)

For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the movable incore detectors are used to confirm that the normalized symmetric power distribution 's consistent with the QUADRANT POWER TILT RATIO. The incore detector monitoring is done with a full incore flux map or two sets of four symmetric thimbles. The two sets of four symmetric thimbles is a unique set of eight detector locations. These locations are C-8, E-5, E-11, H-3, H-13, L-5, L-11, N-8.

3/4.2.5 DNB PARAMETERS The limits on the DNB-related parameters assure that each of the parameters is maintained within the normal steady-state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR of 1.30 throughout each analyzed transient. The in-dicated T,yg value of 592.5*F and the indicated pressurizer pressure value'of ]-

2220 psig correspond to analytical limits of 595*F and 2205 psig respectively, with allowance for measurement uncertainty.

The 12-hour periodic surveillance of these parameters through instrument -

readout is sufficient to ensure that the parameters are restored within their -

limits following load changes and other expected transient operation.

CALLAWAY -iUNIT 1 B 3/4 2-6 A

. REACTOR COOLANT SYSTEM . .

t

(

BASES .

3/4.4.2 SA'FETY VALVES The pressurizer Code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig. Each safety valve is designed to relieve 420,000 lbs per hour of saturated steam. The relief capacity of e a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown. In the event that no safety valves are OPERABLE, an operating RHR loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization. In addition, the Overpressure Protection System provides a diverse means of protection against RCS overpressurization at low temperatures.

During operation, all pressurizer Code safety valves must be OPERABLE to prevent the RCS from being pressurized above its Safety Limit of 2735 psig.

The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss-of-load assuming no Reactor trip and also assuming no operation of the power-operated relief valves or steam dump valves.

Demonstration of the safety valves' lift settings will occur only during

( shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code.

3/4.4.3 PRESSURIZER The 12-hour periodic surveillance is sufficient to ensure that the para- i meter is restored to within its limit following expected transient operation. l I

The maximum water volume also ensures that a steam bubble is formed and thus the RCS is not a hydraulically solid system. The requirement that a minimum l

m'aber of pressurizer heaters be OPERABLE enhances the capability of the plant to control Reactor Coolant System pressure and establish natural circulation.

3/4.4.4 RELIEF VALVES The power-operated relief yalves (PORVs) and steam bubble function to relieve RCS pressure during all design transients up to and including the design step load decrease with steam dump. Operation of the PORVs minimizes the undesirable opening of the spring-loaded pressurizer Code safety valves.

Each PORV has 'a remotely operated block valve to provide a positive shutoff capability should a relief valve become inoperable.

CALLAWAY -UNIT 1 8 3/4 4-2

. . . _ . - - - - - - - . =

I i

REACTOR COOLANT SYSTEM BASES )

COLD OVERPRESSURE (Continued) possible by the geometrical relationship of the RHR suction line and the RCS l wide range temperature indicator used for COMS; 3) instrument uncertainties; ]

and 4) single failure. To ensure mass and heat input transients more severe )

than those assumed cannot occur, technical specifications require. lockout of . ,

both safety injection pumps and all but one centrifugal charging pump while in '

MODES 4, 5 and 6 with the reactor vessel head installed and disallow start of an RCP if secondary temperature is more than 50*F above primary temperature.

Exceptions to these mode requirements are acceptable as described below.

Operation above 350*F but less than 375'F with only one centifugal charging pump OPERABLE and no safety injection pumps OPERABLE is allowed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

As shown by analysis LOCA's occurring at low temperature, low pressure conditions can be successfully mitigated by the operation of a single centrifugal charging pump and a single RHR pump with no credit for accumulator injection. Given the short time duration that the condition of having only one centrifugal charging i

pump OPERABLE is allowed and the probability of a LOCA occurring during this time, the failure of the single centrifugal charging pump is not assumed.

Operation below 350*F but greater than 325'F with all centrifugal charging

. and safety injection pumps OPERABLE is allowed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . During low pressure, low temperature operation all automatic safety injection actuation signals except Containment Pressure - High are blocked. In normal conditions a single failure of the ESF actuation circuitry will result in the starting of at most one train of safety injection (one centrifugal charging pump, and one safety injection pump). For temperatures above 325'F, an overpressure event occurring as a result of starting two pumps can be successfully mitigated by operation of both PORV's without exceeding Appendix G limit. Given the short time duration that

, this condition is allowed and the low probability of a single failure causing an overpressure event during this time, the single failure of a PORY is not assumed.

Initiation of both trains of safety injection during this 4-hour time frame due to

, operator error or a single failure occurring during testing of a redundant chcnnel 4

are not considered to be credible accidents.

Although COMS is required to be OPERABLE when RCS temperature is less than

' 368'F, operation with all centrifugal charging pumps and both safety injection pumps OPERABLE is acceptable when RCS temperature is greater than 350*F. Should an inadvertent safety injection occur above 350*F, a single PORV has sufficient l

l capacity to relieve the combined flow rate of all pumps. Above 350*F-eno-and all pressurizer safety valves are required to be OPERA 8LE. Operation o an be [

! RCP eliminates the possibility of a 50*F difference existing between indicated

.and actual RCS temperature as a result of heat transport effects. Considering instrument uncertainties only, an indicated RCS temperature of 350*F is suffi-ciently high to allow full RCS pressurization' in accordance with Appendix G limitations. Should an overpressure event occur in these conditions, the pres-surizer safety valves provide acceptable and redundant overpressure protection. l l

T'he Maximum Allowed PORV setpoint for the Cold Overpressure Mitigation System will be updated based on the results of examinations of reactor vessel '

material irradiation surveillance specimens performed as required by TJ CFR Part 50, Appendix H and in accordance with the' schedule in Table 4.4-5.

.CALLAWAY - UNIT 1 5 3/4 4-16

M CONTAINMENT SYSTEMS l

BASES l

3/4.6.1.4 INTERNAL PRESSURE

- The 1' imitations on containment internal pressure ensure that: (1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosphere of 3.0 psig, and (2) the

containment peak pressure does not exceed the design pressure of 60 psig ,

during steam line break conditions.

t The maximum peak pressure expected to be obtained from a steam line break i event is 48 psig. The limit of 1.5 psig for initial positive containment pressure will limit the total pressure to 49.5 psig, which is less than design pressure and is consistent with the safety analyseg.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the safety analysis for a steam line break accident. Measurements shall be made at all listed locations, whether by fixed or portable instruments, prior to determining the average air temperature.

. (

3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY i

This limitation ensures that the structural integrity of the containment vessel will be maintained in accordance with safety analysis requirements for the. life of the facility. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 50 psig in the event of a steam line break accident. The measurement of containment tendon lift-off fcece, the tensile tests of the tendon wires or strands, the visual examination of-tendons, anchorages and exposed interior and exterior surfaces of the containment, and the Type A leakage test are sufficient to demonstrate this capability. .

The Surveillance Requirements for demonstrating the containment's structural integrity are in compliance with the recommendations of proposed Regulatory i

Guide 1.35, " Inservice Surveillance of.Ungrouted Tendons in Prestressed Concrete Containment Structures," April 1979, and proposed Regulatory Guide 1.35.1,

" Determining Prestressing Forces for Inspection of Prestressed Concrete Con-tainpents," April 1979.

The required Special Reports from any engineering evaluation of containment

-abnormalties shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedure,-

the tolerances on cracking, the results of the engineering evaluation and the corrective actions taken.

1

/

CALPWAY - UNIT.1 8 3/4 6-2 Y

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ML20091G399

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Dear Mr. Denton:

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ML20091G399

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Dear Mr. Denton:

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