Text

Amends 127 & 125 to Licenses DPR-80 & DPR-82,respectively, Revising Combined TSs for Plant to Change TS 3/4.8.1.1, AC Source - Operating
	ML20249B593
Person / Time
Site:	Diablo Canyon
Issue date:	06/05/1998
From:	Steven Bloom; NRC (Affiliation Not Assigned)
To:	;
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ML20249B594	List: ML20249B593; ML20249B596;
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	NUDOCS 9806230352
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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3o66641001 l

PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-275 I

DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.127 License No. DPR-80 1.

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

A.

The application for amendment by Pacific Gas and Electric Company (the licensee) dated February 27, 1997, as supplemented by letter dated December 4. 1997, complies with the standards and requirements of the Atomic Energy Act of 1954. as amended (the Act). anc 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:

There is reasonable assurance (1) that the activities authorized by j

C.

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:

The issuance of this amendment will not be inimical to the common D.

defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 E.

of the Commission's regulations and all applicable requirements have been satisfied.

Accordingly, the license is amended by changes to the Technical 2.

Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-80 is hereby amended to read as follows:

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l 9006230352 900605 l

PDR ADOCK 05000275 l

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.127. are hereby incorporated in the license.

Pacific Gas and Electric Company shall operate the facility in

,..', " ^

accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license 9

conditions.

3.

.This license amendment is effective as of its date of issuance to be -

implemented within 30 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION ven D. Bloom, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 5, 1998

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

$(p. 4 WASHINGTON. D.C. 20066-0001

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PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 QJABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 125 License No. DPR-82 1.

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

A.

The application for amendment by Pacific Gas and Electric Company (the licensee) dated February 27. 1997, as supplemented by letter dated December 4.1997 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), anc the Commission's regulations set forth in 10 CFR Chapter I:

l B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules 6nd 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 l

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 Specifications The-Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix'B. as revised through Amendment No. 125, are hereby incorporated in the license.

~ Pacific Gas and Electric Company shall operate the-facility in I

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 its date of issuance to be implemented within 30 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION BD &

gevenD. Bloom,ProjectManager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications

'Date of Issuance:

June 5, 1998 u_..A____

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-ATTACHMENT TO LICENSE-AMENDMENTS AMENDMENT NO.127 TO FACILITY OPERATING LICENSE NO. DPR-80

. AND' AMENDMENT NO.125-TO FACILITY OPERATING LICENSE NO. DPR-82

~

DOCKET NOS. 50-275 AND 50-323 Revise Appendix A-Technical' Specifications by removing the pages identified

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below and inserting the enclosed pages. The revised pages are identified by-Amendment number and contain marginal lines indicating the areas of change.

The corresponding overleaf pages are also provided to maintain document-completeness.

REMOVE INSERT 3/4 3-20 3/4 3-20 3/4 3-21 3/4 3-21 3/4 8-3 3/4 8-3 B 3/4 8-2 8 3/4 8-2 I

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TABLE 3.3-3 (Continued)

TABLE NOTATIONS

Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) Setpoint.

1. Trip function automatically blocked above P-11 (Pressurizer Pressure Interlock) Setpoint and is automatically blocked below P-11 when Safety Injection on Steam Line Pressure-Low is not blocked.

1. 1. For Mode 3. the Trip Time Delay associated with the Steam Generator Water Level-Low-Low channel must be less than or equal to 464.1 seconds.

ACTION STATEMENTS ACTION 14 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 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 SHUTD0WN within the following 30 hour3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months s: however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months l

for surveillance testing per Specification 4.3.2.1, orovided the other channel is OPERABLE.

ACTION 15 - With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirement. declare the affected Emergency Diesel Generator (s) inoperable and comply with the ACTION statements of Specification 3.8.1.1: however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.

-ACTION 16 - With the number of OPERABLE Channels one less than the. Total Number of Channels, declare the affected Emergency Diesel Generator (s) inoperable and comply with the ACTION statements of Specification 3.8.1.1: however one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.

ACTION 17 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met.

One additional channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.

ACTION 18 - With less than the Minimum Channels OPERABLE requirement.

operation may continue provided the containment purge supply and exhaust valves (RCV-11, 12. FCV 660. 661. 662. 663. 664) are maintained closed.

ACTION 19 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-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 .

ACTION 20 - With the number of OPERABLE channels one less than the Total Number of Channels. STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

The Minimum Channels OPERABLE requirement is met: however, the inoperable channel or one additional channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification

'4;3.2.1.

DIABLO' CANYON - UNITS 1 & 2 3/4 3-21 Unit 1 - Amendment No. M-84-1W.127 Unit 2 - Amendment No. 50.83,102.125

TABLE 3.3-3 (Continued)

' ACTION STATEMENTS (Continued)

ACTION 21 - With less than the Minimum Number of Channels OPERABLE, within I hour determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 22 - With ?ise number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least H0T SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channal is OPERABLE.

ACT!0N 23 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 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 .

ACTION 24 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated pump or valve inoperable and take the ACTION required by Specification 3.7.1.5 or 3.7.1.2 as applicable.

ACTION 25 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 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 ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 29 - With the number of OPERABLE cht.nnels less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided that within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , for the affected RCS Loop Delta-T channel (s),

either:

a.

The Trip Time Delay threshold power level for zero seconds time delay is adjusted to 05 RTP, or b.

With the number of OPERABLE channels one less than the Total Number of Channels, the affected Steam Generator Water Level-Low-Low channels are placed in the tripped condition.

ACTION 35 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the trip condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and I

b.

The Minimum Channels OPERABLE requirement is met; however, the l

inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.2.1.

DIABLO CANYON - UNITS 1.& 2 3/4 3-22 Unit 1 - Amendment No. 6h44,103 Unit 2 - Amendment No. 69 43,102 7

1 l

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the Onsite Class 1E Distribution System shall be:

a.

Determined OPERABLE at least once per 7 days by verifying correct breaker alignments indicated power availability, and b.

Demonstrated OPERABLE at least once per REFUELING INTERVAL 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:

a.

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

1)

Verifying the fuel level in the engine-mounted fuel tank.

2)

Verifying the diesel starts from standby condition and l

accelerates 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 1.2 Hz within 13 seconds after the start signal. The diesel generator shall be started for this test by I

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 may be ) receded by an engine prelube period.

Further, all surveillance tests, wit 1 the exception of once per 184 days. may also be preceded by warmup) as procedures (e.g.. gradual acceleration and/or gradual loading > 150 sec 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 Unit 1 - Amendment H.83.93.12? '.27 Unit 2 - Amendment 43.85.92.124.125 j

l

1 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3)

Verifying the generator is synchronized, loaded to greater than or equal to 2484 kW in less than or equal to 60 seconds, and l

operates for greater than or equal to 60 minutes.

l 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 REFUELING INTERVAL 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 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 t 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 wrmanently connected loads within 10 seconds, energizes tie 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 t 1.2 Hz during this test.

DIABLO CANYON - UNITS 1 & 2 3/4 8-4 Unit 1 - Amendment 4'.95.93 124 126 Unit 2 - Amendment 43.95.92.

e i

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. SOURCES. 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 l

Design Criterion 17 of Appendix A to 10 CFR Part 50.

The ACTION requirements specified for the levels of degradation of the l

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.g3, " 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-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 will not result in a complete loss of safety function of critical systems der-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 other information to determine if certain components are out-of-service for maintenance or othe-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 snsures that:

(1) the facility can be maintained in the shutdown or refueling condition for extended time periods, and (2) sufficient instrumentation and contrc1 capability is available for monitoring and maintaining the facility status.

The design of the 125-volt D.C. distribution system is cuch that a battery can have associated with it a full capacity charger powered from it associated 1

1 480-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 - UNITS 1 & 2 B 3/4 8-1 Amendment Nos. it i ", 93 8 92 I

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

Guides 1.9. " Selection of Diesel Gene:ator Set Capacity for Standby Power Supplies." 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.

" Standby condition" stated in surveillance requirement 4.8.1.1.2a.2 means the lubricating oil and jacket water temperatures are between 90 F and 175 F.

The lube oil and jacket water temperatures must be maintained at or above 90*F for EDG operability.

The steady state voMage 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 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 4400 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 o)erating voltages. The specified minimum and maximum frequencies of the Xi are 58.8 Hz and 61.2 Hz.

respectively.

These values are ecual to 2% 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 I

batteries are based on the recommendations of Regulatory Guide 1.129.

" Maintenance 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." One exception to Regulatory Guide 1.129. Section C.1, applies to the battery service test. The service test should be performed during an outage, with the interval between tests not to exceed 30 months.

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 charging 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 connocted cells not more than 0.010 below the manufacturer's full charge specific gravity, ensures-the OPERABILITY and capability of the battery.

DIABLO. CANYON - UNITS 1 & 2 B 3/4 8-2 Unit 1 - Amendment H.85.93.126.127 Unit 2 - Amendment 43.85.92.124.125 Revised by NRC letter dated 9/15/94

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