ML20072N537

Amends 93 & 92 to Licenses DPR-80 & DPR-82,respectively, Revising TS 3/4.8.1, AC Sources by Increasing Required Quantity of EDG Fuel Stored in Day Tank to 250 Gallons

ML20072N537
Person / Time
Site:	Diablo Canyon
Issue date:	08/23/1994
From:	Quay T Office of Nuclear Reactor Regulation
To:
Shared Package
ML20072N545	List: ML20072N537
References
NUDOCS 9409060177
Download: ML20072N537 (20)

Text

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UNITED STATES

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N> 'OLEAR REGULATORY COMMISSION WASHINGTON, O C. 205$5-0001 PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-275 DIABLO CANYON NVCLEAR POWER PLANT. Ull]T NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No. DPR-80 1.

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

A.

The application for amendment by Pacific Gas & Electric Company (the licensee) dated December 8, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission; 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 Commission'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, the 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 Opeiating License No. DPR-80 is hereby amended to read as follows:

9409060177 940823 PDR ADOCK 05000275 P

PDR

~ (2)

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.

93, are hereby incorporated in the license.

Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.

3.

This license amendment is effective as of 30 days from the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

~

m Theodore R. Quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 23, 1994

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• l9 sq UNITED STATES

, '*{s j g j N ' CLEAR REGULATORY COMMISSION

-*g WASHINGTON, D.C. 20555-0001 s

PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 DIABLO CANYON NUCLEAR POWER PLANT. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 92 License No. DPR-82 1.

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

A.

The application for amendment by Pacific Gas & Electric Company (the licensee) dated December 8, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission; i

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 i

conducted in compliance with the Commission'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, the 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-82 is hereby amended to read as follows:

' (2)

Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 92

, are hereby incorporated in the license. Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.

3.

This license amendment is effective as of 30 days from the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 3 ~b Theodore R. Quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 23, 1994

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 9 3 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMFNDMENT NO. 92 TO FACILITY OPERATING LICENSE NO. DPR-82 DOCKET NOS. 50-275 AND 50-323 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

Overleaf pages are also included, as appropriate.

REMOVE INSERT 3/4 7-38 3/4 7-38 3/4 8-1 3/4 8-1 3/4 8-2 3/4 8-2 3/4 8-3 3/4 8-3 3/4 8-4 3/4 8-4 3/4 8-11 3/4 8-11 B 3/4 3-la B 3/4 3-la B 3/4 8-1 B 3/4 8-1 B 3/4 8-2 B 3/4 8-2 B 3/4 8-3 B 3/4 8-3 B 3/4 8-3a B 3/4 8-3a B 3/4 9-3b 1

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PLANT SYSTEMS 3/4.7.11 AREA TEMPERATURE MONITORING t

LIMITING CONDITION F00 OPERATION 3.7.11 The temperature of each area shown in Table 3.7-5 shall not be exceeded for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or by more than 30 F.

APPLICABILITY:

Whenever the equipment in an af fected area is required to be OPERABLE.

ACTION:

a.

With one or more areas exceeding the temperature limit (s) shown in Table 3.7-5 for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, prepare and submit to the Com-mission within 30 days, pursuant to Specification 6.9.2, a Special Report that provides a record of the cumulative time and the amount by which the temperature in the affected area (s) exceeded the limit (s) and an analysis to demonstrate the continued OPERABILITY of the affected equipment.

The provisions of Specifications 3.0.3 and 3.0.4 l

are not applicable.

l b.

With one or more areas exceeding the temperature lin.it(s) shown in Table 3.7-5 by more than 30 F, prepare and submit a Special Report as required by ACTION a. above and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either restore the area (s) to within the temperature limit (s) or declare the equip-ment in the affected area (s) inoperable.

SURVEILLANCE REQUIREMENTS 4.7.11 The temperature in each of the areas shown in Table 3.7-5 shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, f

I l

DIABLO CANYON - UNITS 1 & 2 3/4 7-37

TABLE 3.7-5 AREA TEMPERATURE MONITORING AREA TEMPERATURE LIMIT ( F) 1.

4 kV Vital Bus F Area 5 103 2.

4 kV Vital Bus G Area s 103 3.

4 kV Vital Bus H Area s 103 4.

480 V Bus F Area 5 103 5.

480 V Bus G Area 5 103 6.

480 V Bus H Area s 103 7.

Battery No. 1 Room s 89 8.

Battery No. 2 Room 5 89 9.

Battery No. 3 Room s 89 10.

Instrument Inverter No. 1 Room s 103 11.

Instrument Inverter No. 2 Room s 103 12.

Instrument Inverters No. 3 & 4 Room 5 103

13. Diesel Generator No. 1 Room s 129 14 Diesel Generator No. 2 Room u 129

15. Diesel Generator No. 3 Room 5 129 l

16. Cable 5preading Room s 103 17.

Safety Injection Pump No. 1 Room s 103 18.

Safety Injection Pump No. 2 Room s 103

19. Centrifugal Charging Pump No.1 Room s 103

20. Centrifugal Charging Pump No. 2 Room s 103 21.

Reciprocating Charging Pump No. 3 Room s 103 22.

Residual Heat Removal Pump No.1 Room s 103

23. Residual Heat Removal Pump No. 2 Room 5 103

24. Contain:ent Spray Pumps Nos. 1 & 2 Area s 103

25. Motor Auxiliary Feedwater Pump No. 2 Room s 103

26. Motor Auxiliary Feedwater Pump No. 3 Room s 103

27. Auxiliary Feedwater Valves LCV-113 & 115 Area 5 103

28. Component Cooling Water Pump No. 1 Room s 111 29.

Component Cooling Water Pump No. 2 Room s 111

30. Component Cooling Water Pump No. 3 Room s 111 i

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DIABLO CANYON - UNIT 1 & 2 3/4 7-38 Amendment Nos. 93 & 92 l

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a.

Two independent circuits (one with delayed access) between the offsite transmission network and the Onsite Class IE Distribution System, and b.

Three separate and independent diesel generators, each with:

1.

For Unit 1 Cycle 6 and Unit 2 Cycle 6:

A separate engine-mounted fuel tank containing a minimum volume of 200 gallons of fuel, and f

for Unit 1 Cycle 7 and after, Unit 2 Cycle 7 and after:

A separate engine-mounted fuel tank containing a minimum volume of 250 gallons of fuel, and 2.

Two supply trains of the Diesel Fuel Oil Storage and Transfer Sys-tem contai..ng a minimum combined storage of 33,000 gallons of fuel for one unit operation

• and 65,000 gallons of fuel for two unit operation.

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

ACTION:

a.

With one offsite circuit of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C.

sources by performing Specification 4.8.1.1.la within I hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.

If each of the diesel generators have not been successfully tested within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> demonstrate its OPERABILITY by performing Specification 4.8.1.1.2a.2) separately for each such diesel generator within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restore the offsite circuit 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 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 />.

b.

With a diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the A.C. offsite sources by performing Specification 4.8.1.1.la within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; and if the diesel generator became inoperable due to any cause other than preventive maintenance or I

• The performance of Technical Specification Surveillance Requirement 4.8.1.1.3.e l

requires one fuel oil storage tank to be removed from service to be drained and cleaned. During this surveillance, the diesel generator fuel oil storage requirement for ele unit operation in Modes 1 through 4 and one unit operation in Mode 6 with at least 23 feet of water above the reactor vessel flange or with l

the reactor vessel defueled is 35,000 gallons. The tank being cleaned may be f

inoperable for up to 10 days. For the duration of tank cleaning, temporary onsite fuel oil storage of 24,000 gallons will be maintained.

Prior to removal of a tank from service, the offsite circuits required by Technical Specification 1

3.8.1.1.a will be verified to be OPERABLE.

DIABLO CANYON - UNITS 1 & 2 3/4 8-1 Amendment Nos.-44 & 43, 74 & 7h 93 & 92

~-

ELECTRICAL POWER SYSTEMS LIMITING CONDIT' ION FOR OPERATION ACTION (Continued) testir.g, demonstrate the OPERABILITY of the remaining OPERABLE diesel generators by performing Specification 4.8.1.1.2a.2) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> *; restore the diesel generator to OPERABLE status within l

7 days 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 />.

c.

With one offsite circuit and one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. scurces by performing Specifica-tion 4.8.1.1.la. within I hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> there-after; and if the diesel generator became inoperable due to any cause other than preventive maintenance or testing, demonstrate the OPER-ABILITY of the remaining OPERABLE diesel generators by performing Specification 4.8.1.1.2a.2) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; restore at least one of the inoperable sources to OPERABLE status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or be in at least HOT STAN0BY 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 />. Restore the other A.C. power source (offsite circuit or diesel generav.'r) to OPERABLE status in accordance with ACTION a. or b., as approp: fate with the time requirement of that ACTION statement based on the time of initial loss of the remaining inoperable A.C. power source. A successful test of diesel OPERABIL-ITY per Specification 4.8.1.1.2a.2) performed under this ACTION statement for OPERABLE diesels or a restored to OPERABLE diesel satisfies the dies 91 generator test requirement of ACTION a. or b.

d.

With one diesel generator inoperable in addition to ACTION b. or c.

above verify that:

1.

All required systems, subsystems, trains, components and devices that <: pend on the remaining OPERABLE diesel generators as a source of emergency power are also OPERABLE, and 2.

When in MODE 1, 2, or 3 that at least two auxiliary feedwater pumps are OPERABLE.

If these conditions are not satisfied within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 />.

• This test is required to be completed regardless of when the inoperable diesel generator is restored to operability.

DIABLO CANYON - UNITS 1 & 2 3/4 8-2 A-endment Nos. 44 1 13,-76 1 75. 93 & 92 2

m

F ELECTRICAL POWER SYSTEMS SURVEILLANCE RE0VIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the Onsite Class lE Distribution System shall be:

Determined OPERABLE at least once per 7 days by verifying correct a.

breaker alignments, indicated power availability, and b.

Demonstrated OPERABLE at least once per 18 months during shutdown by:

1)

Transferring 4 kV vital bus power supply from the normal circuit to the alternate circuit (manually and automatically) and to the delayed access circuit (manually), and 2)

Verifying that on a Safety Injection test signal, without loss of offsite power, the preferred, immediate access offsite power source energizes the emergency busses with permanently connected loads and energizes the auto-connected emergency (accident) loads through sequencing timers.

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

l a.

In accordance with the frequency specified in Table 4.8-1 nn a STAGGERED TEST BASIS by:*

l 1)

Verifying the fuel level in the engine-mounted fuel tank, 2)

Verifying the diesel starts from ambient condition and accela-rates to at least 900 rpm in less than or equal to 10 seconds.

The generator voltage and frequency shall be 4160 + 240/-375 volts and 60 1.2 Hz within 13 seconds after the start signal.

The diesel generator shall be started for this test by using one of the following signals:

a)

Manual, or b)

Simulated loss of offsite power by itself (Startup bus undervoltage),or c)

A Safety Injection actuation test signal by itself.

• All diesel generator starts for the purpose of this surveillance test ma be preceded by an engine prelube period.

Further, all surveillance tests, with j

the exception of once per 184 days, may also be preceded by warmup procedures j

(e.g., gradual acceleration and/or gradual loading > 150 sec) as recommended by the manufacturer so that the mechanical stress and wear on the diesel engine is minimized.

DIABLO CANYON - UNITS 1 & 2 3/4 8-3 Amendment Nos. 44 & 43, 85 & 85,93 E 92

4

[LECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continoed) 3)

Verifying the generator is synchronized, loaded to greater than or equal to 2484 kW in less than or equal to 60 seconds, and operates for greater than or equal to 60 minutes, 4)

Verifying the diesel generator is aligned to provide standby power to the associated emergency busses, and 5)

Verifying the diesel engine protective relay trip cutout switch is returned to the cutout position following each diesel generator test, b.

At least once per 18 months during shutdown, by:

1)

Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service; 2)

Verifying that the load sequence timers are OPERABLE with each load sequence timer within the limits specified in Table 4.8-2; 3)

Verifying the generator capability to reject a load of greater than or equal to 508 kW while maintaining voltage at 4160 +

240/-375 volts and frequency at 60 3 Hz; 4)

Verifying the generator capability to reject a load of greater than or equal to 2484 kW without tripping.

The generator voltage shall not exceed 4580 volts during and following the load rejection; 5)

Simulating a loss of offsite power by itself, and:

a)

Verifying de-energization 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 10 seconds, energizes the required auto-connected loads through sequencing timers and operates for greater than or equal to 5 minutes while its generator is loaded with the permanent and auto-connected loads. After energization of these loads, the steady state voltage and frequency of the emergency busses shall be maintained at 4160 + 240/-375 volts and 60 1 1.2 Hz during this test.

DIABLO CANYON - UNITS 1 & 2 3/4 8-4 Amendment Nos. 44-8r437 00 a 05, 93 & 92

ELECTRICAL POWER SYSTEMS A.C. SOURCES 1

SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a.

One circuit between the offsite transmission network and the Onsite Class IE Distribution System, and b.

One diesel generator with:

1.

For Unit 1 Cycle 6 and Unit 2 Cycle 6:

An separate engine-mounted fuel tank containing a minimum volume of 200 gallons of fuel, for Unit 1 Cycle 7 and after, Unit 2 Cycle 7 and after:

An separate engine-mounted fuel tank containing a minimum volume of 250 gallons of fuel, 2.

One supply train of the Diesel Fuel Oil Storage and Transfer system containing a minimum storage of 26,000 gallons

• of fuel in addition to the fuel required for the other unit.

ePPLICABILITY: MODES 5 and 6.

ACTION:

With less than the above minimum required A.C. electrical power sources OPERABLE, immediately suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel or crane operations with loads over the fuel storage pool.

In addition, when in MODE 5 with the reactor coolant loops not filled, or in MODE 6 with the water level less than 23 feet above the reactor vessel flange, immediately initiate corrective action to restore the required sources to OPERABLE status as soon as possible.

SURVEILLANCE REQUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the requirements of Specifications 4.8.1.1.1, 4.8.1.1.2, 4.8.1.1.3, and 4.8.1.1.4, except for Speci fications 4.8.1.1.1.b.2) and 4.8.1.1.2.a.2)c), b.2) for ESF timers, b.6), b.7), b.10),

and b.ll).

• The performance of Technical Specification Surveillance Requirement 4.8.1.1.3.e requires one fuel oil storage tank to be removed from service to be drained and cleaned. During this surveillance, the diesel generator fuel oil storage requirement for one unit operation in Modes 5 or 6 and one unit oparation in Mode 6 with at least 23 feet of water above the reactor vessel flange or with the reactor vessel defueled is 35,000 gallons. The tank being cleaned may be inoperable for up to 10 days.

For the duration of tank clean-ing, temporary onsite fuel oil storage of 24,000 gallons will be maintained.

Prior to removal of a tank from service, the offsite circuits required by Technical Specification 3.8.1.2.a will be verified to be OPERABLE.

DIABLO CANYON - UNITS 1 & 2 3/4 8-11 Amendment Nos. 74 1 73, 93 & 92

ELECTRICALPOWERSYS$M 3/4.8.2 ONSITE POWER DISTRIBUTION OPEPATING LIMITING CON 0iTION FOR OPEPATION 3.8.2.1 The following electrical busses shall be energized in the specified manner:

For Units 1 and 2 Cycle 6:

a.

4160 volt Vital Bus F.

b.

480 volt Vital Bus F, c.

4160 volt Vital Bus G, d.

480 volt Vital Bus G, e.

4160 volt Vital Bus H, f.

480 volt Vital Bus H.

120 volt Vital Instrument A.C. Bus 1 energized from its associated inverter g.

connected to D.C. Bus 1*,

h.

120 volt Supplemental Vital Instrument A.C. Bus 1A energized from its associated inverter connected to D.C. Bus 1*.

i.

120 volt Vital Instrument A.C. Bus 2 energized from its associated inverter connected to D.C. Bus 2*,

J.

120 volt Vital Instrument A.C. Bus 3 energized from its associated inverter connected to D.C. Bus 3*,

k.

120 volt Supplemental Vital Instrument A.C. Bus 3A energized from its associated inverter connected to D.C. Bus 3*,

1.

120 volt vital Instrument A.C. Bus 4 energized from its associated inverter connected to D.C. Bus 2*,

125 volt D.C. Bus 1 energized from Battery Bank 1, and its associated full-m.

capacity charger, 125 volt D.C. Bus 2 energized from Battery Bank 2, and its associated full-n.

capacity charger, and 125 volt D.C. Bus 3 energized from Battery Bank 3 and its associated full-o.

capacity charger.

• Two vital instrument A.C. inverters or one vital and one supplemental vital instrument A.C.

l l

inverter may be disconnected from their D.C. busses for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the purpose of performing an equalizing charge on their associated battery bank provided: (1) their vital busses are energized, and (2) the vital busses associated with the other battery banks are energized from their associated inverters and connected to their associated D.C. busses.

DIABLO CANYDN UNITS 1 & 2 3/4 8 12 Amendment Not, 83 and 82

3/4 3 INSTRlFENTATION BASES

/d 1.and 3/4 3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATLRES As UA JON Sv5 TEM INSTRirENTATION The OPERABILITY of the Reactor Trip System and Engineered Safety Features Actuation System instrumentation and interlocks ensure that: (1) the associated ACTION and/or Reactor trip will be initiated when the parameter monitored by each channel or cceina-tion thereof reaches its Setpoint. (2) the specified coincidence logic and sufficient redundancy is maintained to permit a channel to be out of service for testing or main-tenance consistent with maintaining an appropriate level of reliability of the Reactor Protection and Engineered Safety Features instrumentation, and (3) sufficient redundancy is maintained to permit a channel to be oJt of service for testing or maintenance, and (4) sufficient system functional capability is available from diverse paramet<#rs.

The OPERABILITY of these systems is required to provide the overall reliability.

redundancy. and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operatic.i of each of tnese systems is consistent with the assumptions used in the accident analyses. Tne Surveillance Requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to cemonstrate this capability. Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP 10271.

• Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instru-mentation System.' and saplements to that report. Surveillance intervals and out of-service times were determined based on maintaining an appropriate level of reliability of tne Reatter Protection System.

The Process Protection System is designed to permit any one channel to be tested and maintained at power in a bypassed mode. If a channel has been bypassed for any purpose. the bypass is continuously indicated in the control room as required by applicable coces and standards. As an alternative to testing in the bypass mode, testing in tne trip mode is also possible and permitted.

The Erg'neered Safety Features Actuation System senses selected plant parameters and determines whether or not predetermined limits are being exceeded. If they are, the signals are comcined into logic matrices sensitive to combinations indicative of various acc1 cents, events, and transients. Once the required logic combination is completed.

the syste" sects actuation signals to those engineered safety features components whose ag;*egate function best serves the requirements of the condition. As an example, the follo.ing actions may be initiated by the Engineered Safety Features Actuation System to 2111; ate the consequences of a steam line break or loss of coolant accident: (1) safety injection cumps start and automatic valves position. (2) Reactor trip. (3) feedwater isolation. (4) startup of the emergency diesel generators. (5) containment spray pumps start and automatic valves position. (6) containment isolation. (7) steam line isola-tion. (8) Turbine trip. (9) auxiliary feedwater pumps start and automatic valve posi-tion. (10) containment fan cooler units start, and (11) component cooling water pu@s l

start and automatic valves position.

The Engineered Safety Feature Actuation Systes Instrumentation Trip Setpoints speci-fied in Table 3.3 4 are the nominal values at wtiich the trips are set for each func-tional unit. If the functional unit is based on analog hardware, the retpoint is con-sidered to be adjusted consistent with the nominal value when the *as left* setpoint is within the band allowed for calibration accuracy. For all setpoints in digital hardware, the setpoints are set at the nominal values.

DIABLO CANTON - UNITS 1 & 2 B 3/4 3 1 Arendment Nos. -H and 69-6: & 83

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=

INSTRUMENTATION BASES REACTOR PROTECTION SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)

To accommodate the instrument drift that may occur between operational tests and the accuracy to which setpoints can be measured and calibrated, Allowable Values for the setpoints have been specified in Table 3.3-4.

Operation with setpoints less conservative than the Trip Setpoint, but within the Allowable Value, is acceptable.

The methodology to derive the Trip Setpoints is based upon combining all of the uncertainties in the channel.

Inherent to the determination of the Trip Setpoints are the magnitudes of these channel uncertainties. Sensor and rack instrumentation utilized in these channels are expected to be capable of operating within the allowances of these uncertainty magnitudes.

ESF response times specified in Table 3.3-5, which include sequential operation of the RWST and VCT valves (Table Notations 4 and 5), are based on values assumed in the on-LOCA safety analyses. These analyses take credit for injection of borated water from the RWST.

Injection of borated water is assumed not to occur until the VCT charging pump suction isolation valves are closed following opening of the RWST charging pump suction isolation valves.

When the sequential operation of the RWST and VCT valves is not included in the response times (Table Notation 7), the values specified are based on the LOCA analyses.

The LOCA analyses takes credit for injection flow regardless of the source. Verification of the response times specified in Table 3.3-5 will assure that the assumptions used for the LOCA and non-LOCA analyses with respect to the operation of the VCT and RWST valves are valid.

Undervoltage protection will generate a loss of power diesel generator start in the event a loss of voltage or degraded voltage condition occurs.

The diesel generators provide a source of emergency power when offsite power is either unavailable or is insufficiently stable to allow safe unit operation. The first level undervoltage relays (FLURs) detect the loss of bus voltage (less than 69% bus voltage). The second level undervoltage relays (SLURS) provide a second level of undervoltage protection which protects all Class lE loads from short or long term degradation in the offsite power system. The SLUR allowable value is the minimum steady state voltage needed on the 4160 volt vital bus to ensure adequate voltage is available for safety related equipment at the 4160 volt, 480 volt, and 120 volt levels.

DIABLO CANYON - UNITS 1 & 2 B 3/4 3-la Amendment Nos. SS '. C5, 93 & 92 I

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l 3/4.8 ELECTRICAL POWER SYSTEMS BASES 3/4.8.1. 3/4.8.2. and 3/4.8.3 A.C. SOURCES. D.C. 50.jRCES. and DNSITE POWER DISTRIBUTION The OPERABILITY of the A.C. and D.C power sources and associated distri-bution systems during operation ensures that sufficient power will be available to supply the safety-related equipment required for:

(1) the safe shutdown of the facility, and (2) the mitigation and control of accident conditions within the facility. The minimum specified independent and redundant A.C. and D.C.

power sources and distribution systems satisfy the requirements of General Design Criterion 17 of Appendix A to 10 CFR Part 50.

The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensur-ate with the level of degradation. The OPERABILITY of the power sources is consistent with the initial condition assumptions of the safety analyses and is based upon maintaining sufficient redundancy of the onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss-of-offsite power and single failure of one onsite A.C. source. The A.C. and D.C. source allowable out-of-service times are based on Regulatory Guide 1.93, " Availability of Electrical Power Sources,"

December 1974 except for the allowed outage time associated with Action State-ment b. of Specification 3.8.1.1.

This allowed outage time was changed to be consistent with the recommendation of Diablo Canyon Power Plant Diesel Genera-i tor Allowed Outage Time Study, May 1989. When one diesel generator is inoper-able, there is an additional ACTION requirement to verify that all required systems, subsystems, trains, components and devices, that depend on the remain-l ing OPERABLE diesel generators as a source of emergency power, are also OPERABLE, and that at least two auxiliary feedwater pumps are OPERABLE. This requirement is intended to provide assurance that a loss-of-offsite power event j

will not result in a complete loss of safety function of critical systems dur-ing the period one of the diesel generators is inoperable. The term, verify, as used in this context means to administrative 1y check by examining logs or

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other information to determine if certain components are out-of-service for maintenance or other reasons.

It does not mean to perform the surveillance requirements needed to demonstrate the OPERABILITY of the component.

The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that:

(1) the facility can be maintained in the shutdown or refueling condition for extended time periods, and (2) sufficient instrumentation and centrol l

capability is available for monitoring and maintaining the facility status.

The design of the 125-volt D.C. distribution system is such that a battery can have associated with it a full capacity charger powered from it associated j

480-volt vital bus or an alternate full capacity charger powered from another 480-volt vital bus.

Technical Specification 3.8.2.1 ACTION c. limits operation in the latter configuration to 14 days. Technical Specification 3.8.3.1 re-quires either charger be OPERABLE.

The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are in accordance with the recommendations of Regulatory DIABLO CANYON - UNIIS 1 & 2 8 3/4 8-1 Amendment Nos. '.

'3, 93 & 92

ELECTRICAL POWER SYSTEMS BASES A.C. SOURCES. D.C. SOURCES. and ONSITE POWER DISTRIBUTION (Continued)

Guides 1.9, " Selection of Diesel Generator Set Capacity for Standby Power Sup-plies," March 10,1971,1.108, " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977, where applicable.

The steady state voltage and frequency Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are consistent with the second level undervoltage relay allowable values. This is the minimum steady state voltage needed on the 4160 volt vital buses to ensure adequate 4160 volt, 480 volt and 120 volt levels. The maximum steady state output voltage of 4400 V is the maximum operating voltage for 4000 V motors specified in ANSI C84.1. The maximum steady state output voltage of 4440 V ensures that, for a lightly loaded distribution system, the voltage at the terminals of 4000 V motors is no more than the maximum rated operating voltages. The specified minimum and maximum frequencies of the DG are 58.8 Hz and 61.2 Hz, respectively. These values are equal to i 20% of the 60 Hz nominal frequency and are derived from the recommendations given in Regulatory Guide 1.9.

The Surveillance Requirements for demonstrating the OPERABILITY of the batteries are based on the recommendations of Regulatory Guide 1.129, "Mainte-nance Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants," February 1978, and IEEE Std 450-1980, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations."

Verifying average electrolyte temperature above the minimum for which the battery was sized, total battery terminal voltage onfloat charge, connection resistance values and the performance of battery service and discharge tests ensures the effectiveness of the chargiag system, the ability to handle high discharge rates and compares the battery capacity at that time with the rated capacity.

Table 4.8-3 specifies the normal limits for each designated pilot cell and each connected cell for electrolyte level, float voltage and specific gravity.

The limits for the designated pilot cells float voltage and specific gravity, greater than 2.13 volts and 0.015 below the manufacturer's full charge specific gravity or a battery charger current that had stabilized at a low value, is characteristic of a charged cell with adequate capacity. The normal limits for each connected cell for float voltage and specific gravity, greater than 2.13 volts and not more than 0.020 below the manufacturer's full charge specific gravity with an average specific gravity of all the connected cells not more than 0.010 below the manufacturer's full charge specific gravity, ensures the OPERABILITY and capability of the battery.

Operation with a battery cell's parameter outside the normal limit but within the allowable value specified in Table 4.8-3 is permitted for up to 7 days. During this 7-day period:

(1) the allowable values for electrolyte level ensures no physical damage to the plates with an adequate electron trans-fer capability; (2) the allowable value for the average specific gravity of all the cells, not more than 0.020 below the manufacturer's recommended full charge specific gravity ensures that the decrease in rating will be less than the safety margin provided in sizing; (3) the allowable value for an individual cell's specific gravity ensures that an individual cell's specific gravity DIABLO CANYON - UNITS 1 & 2 B 3/4 8-2 Amendment Nos. it & 42, SS & 85 93 & 92

ELECTRICAL POWER SYSTEMS f

1 BASES A.C. Sources. D.C. Sources. and ONSITE POWER DISTRIBUTION (Continued) will not be more than 0.040 below the manufacturer's full charge specific gravity and that the overall capability of the battery will be maintained within an acceptable limit; and (4) the allowable value for an individual cell's float voltage, greater than 2.07 volts, ensures the battery's capability to perform its design function.

The OPERABILIT'I of the A.C. electrical power sources requires maintaining a supply of fuel oil to support the operation of the emergency diesel genera-tors. The stored fuel oil supports the function of the A.C. power sources to provide power for the operation of emergency systems and engineered safety fea-tures (ESF) during and following the shutdown of the reactor in the event that offsite power sources are not available. The specified fuel oil quantity is based on the calculated fuel oil consumption necessary to support the operation of the emergency power source to power the minimum required ESF systems.

Operation of minimum ESF systems is required to mitigate a design basis acci-dent (LOCA) in one unit and those minimum required systems for a concurrent non-LOCA safe shutdown in the remaining unit (both units initially in Mode 1 operation). The fuel oil consumption is calculated for a period of 7 days operation of minimum ESF systems. This requirement provides a sufficient operating period within which offsite power can be restored and/or additional fuel can be delivered to the site.

The diesel fuel oil storage system consists of two common tanks with a nominal capacity of 40,000 gallons each and six emergency diesel generator (EDG) fuel oil day tanks with a nominal capacity of 550 gallons each. The fuel oil maintained in each day tank is used for the start and the initial operation of the associated EDG. Additional fuel oil is transferred from the storage tanks via the diesel fuel oil storage and transfer system to replenish the day tanks as required. The design incorporates sufficient redundancy so that a malfunction of either an active or a passive component will not impair the l

ability of the system to supply fuel oil.

Two redundant fuel oil transfer pumps supply fuel oil to EDG day tanks from either storage tank. One pump is adequate to supply the six EDGs operat-ing at full load.

Each EDG day tank has two separate, redundant transfer pump start-stop level switches. Each level switch automatically starts a transfer pump and opens the supply header solenoid valve corresponding to the respective transfer pump, 0-1 or 0-2.

In addition, high and low level alarms are provided on each day tank and activate alarms both locally and in the control room.

i DIABLO CANYON - UNITS 1 & 2 B 3/4 8-3 Amendment Nos. O 1 10, 44 S 'O, 74 u 70 79 o 78, CC & 05, 93 & 92

ELECTRICAL POWER SYSTEMS BASES A.C. Sources. D.C. Sources. and ONSITE POWER DISTRIBUTION (Continued)

The Technical Specifications required minimum fuel oil in each EDG day tank is a contained quantity sufficient for EDG operation at full load for a nominal one-hour period. One hour is adequate time for an operator to take corrective action to restore the fuel oil supply to the affected day tank. The EDG day tank 31-day surveillance frequency is adequate to assure that a suf-ficient supply of fuel oil is available, since the transfer pumps auto-starts are at a level above the Technical Specification's minimum contained volume.

Therefore, normal EDG operation will not result in day tank levels below the

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Technical Specifications minimum required volume. Additional assurance of sufficient day tank contained volume is provided by a low level alarm.

For proper operation of the EDGs, it is necessary to ensure the proper quality of the fuel oil. Regulatory Cuide 1.137, " Fuel Oil Systems for Standby Diesel Generators," Revision 1, October 1979, as supplemented by ANSI N195-1976, addresses the recommended fuel oil practices. The surveillance frequen-cies of Technical Specifications 4.8.1.1.2d. and 4.8.1.1.3b. for checking and removing accumulated water from the day tank and main storage tank, respec-tively, are established by Regulatory Guide 1.137, Revision 1.

The Surveil-lance Requirements of Technical Specification 4.8.1.1.3e.1) for draining the fuel stored in the fuel oil storage tanks, removing accumulated sediment, and tank cleaning are in accordance with the recommendations of Regulatory Guide 1.137, Revision 1.

Surveillance Requirements for the assurance of fuel oil quality are in accordance with the ASTM Standards specified in Technical Specification 4.8.1.1.3.

The Surveillance Requirements applicable to diesel generator fuel oil storage requires cleaning the fuel oil storage tanks on a 10-year frequency.

Conducting this surveillance requires the tank to be taken out of service.

For this infrequent event, the inventory in the remaining tank is sufficient to support operatien of the emergency diesel generator to power the minimum required loads to maintain safe conditions for a time period of 4 days, consid-ering one unit in Mode I through 6 operation and one unit in Mode 6 operation

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with at least 23 feet of water above the reactor vessel flange or with the reactor defueled.

3/4.8.4 ELECTRICAL E0UIPMENT PROTECTIVE DEVICES The OPERABILITY of the motor operated valves thermal overload protection and bypass devices ensures that these devices will not prevent safety related valves from performing their function. The Surveillance Requirements for demonstrating the OPERABILITY of these devices are in accordance with Regulato-ry Guide 1.106, " Thermal Overload Protection for Electric Motors on Motor Operated Valves," Revision 1, March 1977.

A list of the TS-controlled M0V thermal overload protection and bypass devices is maintained in the Diablo Canyon plant procedures. The administra-tion of the list shall be conducted in accordance with Section 50.59 of 10 CFR Part 50 and the provisions in the Administrative Controls Section of the TS.

DIABLO CANYON - UNITS 1 & 2 B 3/4 8-3a Amendment Nos. 10 & 18, 74 & 73, 0; ; 0;, 93 & 92

ELECTRICAL POWER SYSTEMS BASES l

ELECTRICAL E0VIPMENT PROTECTIVE DEVICES (Continued)

Records of the changt.

o the valve list are maintained, and an annual report is made that includes a brief description of changes and a summary of the safety evaluation of each in accordance with 10 CFR 50.59.

Containment electrical penetrations and penetration conductors are pro-tected by either deenergizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers during periodic surveillance.

The Surveillance Requirements applicable to lower voltage circuit breakers provide assurance of breaker reliability by testing at least one representative sample of each manufacturer's brand of circuit breaker.

Each manufacturer's molded case and metal case circuit breakers are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers are tested.

If a wide variety exists within any manufacturer's brand of cir-cuit breakers, it is necessary to divide that manufacturer's breakers into groups and treat each group as a separate type of breaker for surveillance purposes.

A list of containment penetration conductor overcurrent protective devices, with information on location and size and equipment powered by the protected circuit, is maintained and controlled at the plant site. The list is limited to those overcurrent devicas installed for the purpose of keeping cir-cuit fault current below the penetration rating.

It does not apply to other overturrent devices associated with containment penetrations.

The addition or deletion of any containment penetration conductor overcurrent protective device is governed by Section 50.59 of 10 CFR Part 50.

DIABLO CANYON - UNITS 1 & 2 B 3/4 8-3b Amendment Nos. 49-&-M, 74-& CG & C5,93 & 92