Text

Amend 8 to License NPF-30,changing Tech Specs to Extend 18-month Surveillance Interval for Various Tests Until Prior to Startup
	ML20133F895
Person / Time
Site:	Callaway
Issue date:	10/03/1985
From:	Oconnor P; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20133F898	List: ML20133F895; ML20133F900;
References
	NUDOCS 8510150024
	Download: ML20133F895 (15)
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'

o UNITED STATES y

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NUCLEAR REGULATORY COMMISSION y

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WASHINGTON, D. C. 20555 t

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UNION ELECTRIC COMPANY DOCKET NO. 50-483 CALLAWAY PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 8 License No. NPF-30 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment by Union Electric Company (the licensee), dated July 10, 1985, as supplemented by letter dated August 9, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Comission's regulations;

d. The issuance of this amendment will not be inimical to the comor 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 Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and i

Paragraph 2.C.(2) of Operating License No. NPF-30 is hereby amended to read as follows:

i (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 8, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. UE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

8510150024 851003 PDR ADOCK 05000483 P

PDR

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3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

(

Paul W. O'Connor, Acting Branch Chief Licensing Branch No. 1 Division of Licensing

Attachment:

Change to the Technical Specifications Date of Issuance:

OCT 3 1985

SEE PREVIOUS CONCURRENCES LB#1:DL LB#1:DL LB#1:DL OELD LB#1:DL

TAlexion:kab

MRushbrook

P0'Connor 09/25/85 (vtBJYoungblood

RPerlis l

09/16/85 09/18/85 09/19/85

[0 / l /85

ATTACHMENT TO LICENSE AMENDMENT NO. 8 OPERATING LICENSE NO. NPF-30 DOCKET NO. STN 50-483 Revise Appendix A, as follows:

REMOVE INSERT 3/4 3-10 3/4 3-10 3/4 3-12 3/4 3-12 3/4 3-33 3/4 3-33 3/4 3-34 3/4 3-34 3/4 3-37 3/4 3-37 3/4 5-5 3/4 5-5 3/4 6-13 3/4 6-13 3/4 6-17 3/4 6-17 3/4 7-11 3/4 7-11 3/4 7-12 3/4 7-12 3/4 8-4 3/4 8-4 3/4 8-10 3/4 8-10 O

TABLE 4.3-1 (Continued) n REACTOR TRIP'SY' TEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

?!

S E

Si TRIP

~'

ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH EE CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE El FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED r,

13. Steam Generator Water Level-S R

M N.A.

N.A.

1, 2 1

Low-Low i

14.

Undervoltage - Reactor Coolant N.A.

R N.A.

M N.A.

1 Pumps i

15. Underfrequency - Reactor N.A.

R N.A.

M N.A.

1 4

Coolant Pumps j'

16. Turbine Trip g>

a.

Low Fluid Oil Pressure N.A.

R N.A.

S/U(1,10)

N.A.

1 E$

b.

Turbine Stop Valve N.A.

R N.A.

S/U(1,10)

N.A.

1 i

Closure

17. Safety Injection Input from N.A.

N.A.

R#

N.A.

1, 2 1

ESF l

18. Reactor Trip System Interlocks a.

Intermediate Range Neutron Flux, P-6 N.A.

R(4)

M N.A.

N.A.

2##

b.

Low Power Reactor 37 Trips Block, P-7 N.A.

R(4)

M(8)

N.A.

1 m

R c.

Power Range Neutron j

Flux, P-8 N.A.

R(4)

M(8)

N.A.

1 i

d.

Power Range Neutron

!?

Flux, P-9 N.A.

R(4)

M(8)

N.A.

I c2 t

TABLE 4.3-1 (Continued)

TABLE NOTATIONS a

0nly if the Reactor Trip System breakers happen to be closed and the Con-trol Rod Drive System is capable of rod withdrawal.

The specified 18 month frequency may be waived for Cycle I provlded the surveillance is performed prior to restart following the first refueling The provisions of outage or June 1, 1986, whichever occurs first.

Specification 4.0.2 are reset from performance of this surveillance.

1. Below P-6 (Intermediate Range Neutron Flux interlock) Setpoint.

1. 1. Below P-10 (Low Setpoint Power Range Neutron Flux interlock) Setpoint.

(1) If not performed in previous 7 days.

Comparison of calorimetric to excore power indication above 15% of RATED (2)

THERMAL POWER. Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15%

(3)

Recalibrate if the absolute difference is greater of RATED THERMAL POWER.

than or equal to 3%. The provisions of Specification 4.0.4 are not appli-cable for entry into MODE 2 or 1.

(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

Detector plateau curves shall be obtained, evaluated and compared to manu-(5)

For the Intermediate Range and Power Range Neutron Flux facturer's data.

channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

Incore - Excore Calibration, above 75% of RATED THERMAL POWER. The provi-(6) sions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(7)

With power greater than or equal to the interlock Setpoint the required

-(8)

ANALOG CHANNEL OPERATIONAL TEST shall consist of verifying that the inter-lock is in the required state by observing the permissive annunciator window.

Monthly surveillance in MODES 3*, 4*, and 5* shall also include verification (9) that permissives P-6 and P-10 are in their required state for existing plant Monthly conditions by observation of the permissive annunciator window.

surveillance shall include verification of the Baron Dilution Alarm Setpoint of less than or equal to an increase of twice the count rate within a 10-minute period.

(10) Setpoint verification is not required.

(11) At least once per 18 months and following maintenance or adjustment of the Reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verification of the Undervoltage and Shunt trips.

(12) At least once per 18 months during shutdown, verify that on a simulated Boron Dilution Doubling test signal the normal CVCS discharge valves will close and the centrifugal charging pumps suction valves from the RWST will cpen within 30 seconds.

(13) CHANNEL CALIBRATION shall include the RTO bypass loops flow rate.

/nendnent No. O CALLAWAY - UNIT 1 3/4 3-12

_ =

44 TABLE 4.3-2 h

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION h

SURVEILLANCE REQUIREMENTS 4

TRIP ANALOG ACTUATING MODES e5 CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE

' FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST' IS REQUIRED 1.

Safety Injection (Reactor Trip, Phase "A" Isolation, Feedwater Isolation Turbine Trip, Component Cooling Water, Auxiliary Feedwater-Motor-Driven Pump Emergency Diesel Generator Operation, Containment Cooling, and Essential Service Water Operation) 1,2,3,4l l

1 a.

Manual Initiation N.A.

N.A.

R#

N.A.

T b.

Automatic Actuation M.A.

N.A.

N(1)

M(1)

Q(3) 1, 2, 3, 4 ti Logic and Actuation Relays (SSPS) c.

Containment Pressure-S R

M N.A.

N.A.

1,2,3 High-1 d.

Pressurizer Pressure-S R

M N.A.

N.A.

1, 2, 3 Low I

e.

Steam Line Pressure-S R

M N.A.

N.A.

1,2,3 Low 2.

Containment Spray 1, 2, 3, 4 l a.

Manual Initiation N.A.

N.A.

R#

N.A.

b.

Automatic Actuation N.A.

N.A.

M(1)

Q(3) 1, 2, 3, 4 Logic and Actuation y

Relays (SSPS) l c.

Containment Pressure-S R

M N.A.

N.A.

1, 2, 3

[

High-3 A

.O

9.

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION E

SURVEILLANCE REQUIREMENTS

~

1 RIP ANALOG ACTUATING MODES E

CHANNEL DEVICE MASTER STAVE FOR WHICH U

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE

FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED 3.

Containment Isolation a.

Phase "A" Isolation

1) Manual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4

2) Automatic Actuation N.A N.A.

N.A.

M(1)

Q(3) 1, 2, 3, 4 Logic and Actuation Relays (SSPS)

3) Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

y b.

Phase "B" Isolation

1) Manual Initiation N.A.

N.A.

R#

N.A.

1, 2, 3, 4 l

2) Automatic Actuation N.A.

N.A.

M(1)

Q 1,2,3,4 Logic and Actuation Relays (SSPS)

3) Containment 5

R M

N.A.

1, 2, 3 Pressure-High-3 c.

Containment Purge Isolation

1) Manual Initiation N.A.

N.A.

R N.A.

N.A.

1,2,3,4 1

2) Automatic Actuation N.A.

N.A.

M(1)

Q(3) 1, 2, 3, 4 l

Logic and Actuation Relays (SSPS)

{

g g

3) Automatic Actuation

)

R Logic and Actuation g

Relays (BOP ESFAS)

N.A.

M(1)(2)

N.A.

1, 2, 3, 4 h

4) Phase "A" See Item 3.a. above for all Phase "A" Isolation Surveillance Requirements.

I P

Isolation i

l 1

TABLE 4.3-2 (Continued)

[

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5;

SURVEILLANCE REQUIREMENTS E

TRIP ANALOG ACTUATING MODES si CHANNEL DEVICE MASTER SLAVE FOR WHICH

q CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE wFUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED 9.

Control Room Isolation a.

Manual Initiation N.A.

N.A.

R N.A.

N.A.

All b.

Automatic Actuation N.A.

N.A.

M(1)

Q(3) 1, 2, 3, 4 Logic and Actuation Relays (SSPS) c.

Automatic Actuation t*

Logic and Actuation Relays (BOP ESFAS)

N.A.

M(1)(2)

N.A.

All Y

t' d.

Phase "A" Isolation See Item 3.a. above for all Phase "A" Isolation Surveillance Requirements.

10.

Solid-State Load Sequencer N.A.

N.A.

M(1)(2)

N.A.

1, 2, 3, 4 11.

Engineered Safety Features Actuation System Interlocks a.

Pressurizer Pressure, N.A.

R M

N.A.

1,2,3 P-11 27 b.

Reactor Trip, P-4 N.A.

N.A.

R N.A.

N.A.

1, 2, 3 5ft TABLE NOTATIONS R

5 (1) fach train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

^

==

(2) Continuity check may be excluded from the ACTUATION LOGIC TEST.

?

(3) Except Relays K602, K620, K622, K624. K630, K740, and K741, which shall be tested at least once per 18 months during refueling and during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless they have been tested within the es previous 90 days.

The specified 18 month frequency may be waived for Cycle I provided the surveillance is performed prior to restart following the first refueling outage or June 1,1986, whichever occurs first. The provisions of Specification 4.0.2 are reset from performance of this surveillance.

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2)

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

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

e.

1)

Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal and/or on Automatic Switchover to Containment Sump from RWST Level-Low-Low coincident with Safety Injection test signal; and 2)# Verifying that each of the following pumps start automatically l

upon receipt of a Safety Injection actuation test signal:

a)

Centrifugal charging pump, b)

Safety Injection pump, and c)

RHR pump.

f.

By verifying that each of the following pumps develops the required differential pressure on recirculation flow when tested pursuant to Specification 4.0.5:

1)

Centrifugal charging pump 1 2400 psid, 2)

Safety Injection pump

> 1445 psid, and 3)

RHR pump 1 165 psid.

g.

By verifying the correct position of each mechanical position stop for the following ECCS throttle valves:

1)

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and

{

2)

At least once per 18 months.

i HPSI System CVCS System Valve Numbers Valve Numbers EMV095 EMV109 BGV-198 EMV096 EMV110 BGV-199 EMV097 ENV089 BGV-200 EMV098 ENV090 BGV-201 ENV107 EMV091 BGV-202 EMV108 EMV092

The specified 18 month frequency may be waived for Cycle I provided the surveillance is performed prior to restart following the first refueling outage or June 1, 1986, whichever occurs first. The provisions of Specification 4.0.2 are reset from performance of this surveillance.

CALLAWAY - UNIT 1 3/4 5-5 Amendment flo. 8

CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent Containment Spray Systems shall be OPERABLE with each Containment Spray System capable of taking suction from the RWST and transferring suction to the containment sump.

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

ACTION:

With one Containment Spray System inopeaable, restore the inoperable Containment Spray System 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 ; restore the inoperable Containment Spray System to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.2.1 Each Containment Spray System shall be demonstrated OPERABLE:

a.

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

By verifying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to 250 psig when tested pursuant to Specification 4.0.5; c.

At least once per 18 months during shutdown, by:

1)

Verifying that each automatic valve in the flow path actuates to its correct position on a Containment Pressure-High-3 (CSAS) test signal, and 2)# Verifying that each spray pump starts automatically on a l

Containment Pressure-High-3 (CSAS) test signal.

d.

At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

The specified 18 month frequency may be waived for Cycle I provided the surveillance is performed prior to restart following the first refueling outage or June 1,1986, whichever occurs first. The provisions of Specification 4.0.2 are reset from performance of this surveillance.

l CALLAWAY - UNIT 1 3/4 6-13 Amendment No. 8 l

1

)

CONTAINMENT SYSTEMS

(

SURVEILLANCE REQUIREMENTS (Continued) 1 4.6.3.2 Each containment isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least j

once per 18 months by:

a.# Verifying that on a Phase "A" Isolation test signal, each l

Phase "A" isolation valve actuates to its isolation position, 1

I b.# Verifying that on a Phase "B" Isolation test signal, each l

Phase "B" isolation valve actuates to its isolation position, and c.

Verifying that on a Containment Purge Isolation test signal, i

each purge supply and exhaust isolation valve actuates to its isolation position.

4.6.3.3 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 i

i Specification 4.0.5.

4 i

The specified 18 month frequency may be waived for Cycle I provided the i

surveillance is performed prior to restart following the first refueling outage or June 1,1986, whichever occurs first. The provisions of Specification 4.0.2 are reset from performance of this surveillance.

l I

i, l

l i

1 I

i l

l i

i i

I l

CALLAWAY - UNIT 1 3/4 6-17 Arendment No. 8 l

PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3 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 least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.3 At least two component cooling water loops shall be demonstrated OPERABLE:

a.

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

In addition, an ANALOG CHANNEL OPERATIONAL TEST of the surge tank level and flow instrumentation which provide automatic isolation of the non-nuclear safety related portion of the system shall be performed at least once per 31 days; b.

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

8 1)

Each automatic valve servicing safety-related equipment or isolating the non-nuclear safety-related portion of the systerg actuates to its correct position on a Safety Injection and on a simulated High Flow and Low Surge Tank Level test signal, and 2)# Each OPERABLE Component Cooling Water System pump starts auto-l matica11y on a Safety Injection and Loss-of-Power test signal.

c.

At least once per 18 months during shutdown, by performing a CHANNEL CALIBRATION of the surge tank level and flow instrumentation which provide automatic isolation of the non-nuclear safety-related portion of the system.

The specified 18 month frequency may be waived for Cycle I provided the survelliance is performed prior to restart following the first refueling outage or June 1,1986, whichever occurs first. The provisions of Specification 4.0.2 are reset from performance of this surveillance.

CALLAWAY - UNIT 1 3/4 7-11 Amendment No. 0 b

_ = _ _ - _ _

PLANT SYSTEMS 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM l

LIMITING CONDITION FOR OPERATION 3.7.4 At least two independent essential service water (ESW) loops shall be OPERABLE.

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

l ACTION:

With only one ESW loop OPERABLE, restore at least two ESW loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT 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 .

1 SURVEILLANCE REQUIREMENTS

(

1 l

4.7.4 At least two ESW 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 equipment i

that is not locked, sealed, or otherwise secured in position, is in l

its correct position.

In addition, at least once per 31 days, an j

ANALOG CHANNEL OPERATIONAL TEST of the differential pressure instru-mentation for automatic isolation of the ESW to the air compressors shall be performed; b.

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

i i

1)

Each automatic valve servicing safety-related equipment or i

isolating the non-nuclear safety-related portion of the system actuates to its correct position on a Loss-of-Power or Safety-Injection test signal and on a simulated High Differential j

Pressure test signal; and 2)# Each ESW System pump starts automatically on a Safety Injection, l

Low Suction Pressure (AFW pumps) and Loss-of-Power test signal.

c.

At leart once per 18 months during shutdown, by performing a CHANNEL CALIBRATION of the differential pressure instrumentation for automatic isolation of the ESW to the air compressors.

i

The specified 18 month frequency may be waived for Cycle I provided the surveillance is performed prior to restart following the first refueling i

outage or June 1,1986, whichever occurs first. The provisions of l

Specification 4.0.2 are reset from performance of this surveillance.

i l

CALLAWAY - UNIT 1 3/4 7-12 Anendment No. 8

E_LECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) a)

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

A kinematic viscosity at 40'C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes, if gravity was not determined by comparison with the supplier's certification; c)

A flash point equal to or greater than 125'F; and d)

A clear and bright appearance with proper color when tested in accordance with ASTM-04176-82.

2)

By verifying within 30 days of obtaining the sample that the other properties specified in Table 1 of ASTM-0975-81 are met when tested in accordance with ASTM-0975-81 except that the analysis for sulfur may be performed in accordance with ASTM-D1552-79 or ASTM-D2622-82.

At least once every 31 days by obtaining a sample of fuel oil in e.

4 accordance with ASTM D2276-78, and verifying that total particulate contamination is less than 10 mg/ liter when checked in accordance with ASTM-02276-78, Method A;

]

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

l 1)

Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service;

~

2)

Verifying the diesel generator capability to reject a load of greater than or equal to 1352 kW (ESW pump) while maintaining voltage at 4000 t 320 volts and frequency at 60 1 5.4 Hz; 3)

Verifying the diesel generator capability to reject a load of 6201 kW without tripping. The generator voltage shall not exceed 4784 volts during and following the load rejection; 4) 3fmulating a loss-of-offsite power by itself, and:

a)

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

Verifying the diesel starts on the auto-start signal, energizes the emergency busses with permanently connected loads within 12 seconds, energizes the auto-connected shutdown loads through the shutdown sequencer and operates for greater than or equal to 5 minutes while its generator I

The specified 18 month frequency may be waived for Cycle I provided the surveillance is performed prior to restart following the first refueling l

outage or June 1, 1986, whichever occurs first. The provisions of i

Specification 4.0.2 are reset from performance of this surveillance.

CALLAWAY - UNIT 1 3/4 8 4 Amendment No. 8

~

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 veriffing that:

1)

The parameters in Table 4.8-2 meet the Category B Ilmits, 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 9 ohm, and 3)

The average electrolyte temperature of at least every sixth cell is abova 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 anti-corrosion material, 3)

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

battery capacity is adequate to supply and maintain in OPERABLE status simulated emergency loads for the design duty cycle when the battery is subject to a battery service test; af.'

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 4.8.2.1d.; 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 10% of rated capacity from its average on previous performance tests, or is below 90% of the manufacturer's rating.

The specified 18 month frequency may be waived for Cycle I provided the surveillance is performed prior to restart following the first refueling outage or June 1, 1986, whichever occurs first. The provisions of Specification 4.0.2 are reset from performance of this surveillance.

CALLAWAY - UNIT 1 3/4 8-10 Mendment No. 8 L

ML20133F895

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