Text

Amends 110 & 109 to Licenses DPR-80 & DPR-82,respectively, Revising TSs 3/4.6.1.1,3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.3 & Adding Spec 6.8.4.j
	ML20100Q444
Person / Time
Site:	Diablo Canyon
Issue date:	03/01/1996
From:	Steven Bloom; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20100Q448	List: ML20100Q444; ML20100Q449;
References
	NUDOCS 9603110641
	Download: ML20100Q444 (18)
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NUCLEAR REGULATORY COMMISSION f

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WASHINGTON, D.C. 30668 0001 PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-275 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.110 License No. DPR-80 1.

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

A.

The application for amendment by Pacific Gas and Electric Company (the licensee) dated December 27, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 (11) that such activities will to conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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-80 is hereby amended to read as follows:

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9603110641 960301 DR ADOCK 0500 5

.. (2) Technical Snecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix 8, as revised through Amendment No. 110, 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 conditions.

3.

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

FOR THE NUCLEAR REGULATORY C0ft1ISSION

' v h' i

teven 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:

March 1, 1996

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y UNITED STATEE 3

S NUCLEAR REGULATORY COMMISSION E

WASHINGTON, D.C. 3088H001 PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 fiSRLD CANYON NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 109 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 December 27, 1995, 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 1

Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and

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safety of the public, and (ii) that.such activities will be conducted in compliance with the Commission's regulations; 0.

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 awnded to read as follows:

.. (2) Technical Snecifications The Technical Specificatiens contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.

109, 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 conditions.

3.

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

FOR THE NUCLEAR REGULATORY Com ISSION

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Q yn Steven 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:

March 1, 1996

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ATTACHMENT TO LICEhSE AMENDMENTS AMENDMENT NO. 110TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO. ino TO FACILITY OPERATING LICENSE NO. DPR-82 DOCKET NOS. 50-275 AND 50-323

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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 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 3/4 6-4 3/4 6-5 3/4 6-5 3/4 6-6 3/4 6-6 l

3/4 6-9 3/4 6-9 3/4 6-16 3/4 6-16 8 3/4 6-1 S 3/4 6-1 6-15c 6-15c

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3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION l

3.6.1.1 CONTAINMENT INTEGRITY shall be maintained.

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

ACTION:

Without CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within I hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REOUIREMENTS 4.6.1.1 CONTAINMENT INTEGRITY shall be demonstrated:

a.

At least once per 31 days by verifying that all penetrations

not capable of being closed by OPEMBLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under administrative control as permitted by Specification 3.6.3.

b.

By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.

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Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed,.or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except such verification need not be performed more often I

than once per 92 days.

DIABLO CANYON UNITS 1 & 2 3/4 6-1 Unit 1 - Amendment No. M,110 Unit 2 - Amendment No. M,109 1

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a CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited in accordance with the Containment Leakage Rate Testing Program.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the measured overall integrated containment leakage rate exceeding hours., within I hour initiate action to be in HOT STANDBY within the next 6 1.0 L and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Restore the overall integrated leakage rate to less than or equal to 0.75 L and the combined leakage rate for all penetrations subject to Type B and,,C tests to less than or equal to 0.60 L, prior to increasing the Reactor Coolant System temperature above 200*F.

DIABLO CANYON - UNITS I & 2 3/4 6-2 Unit 1 - Amendment No.110 Unit 2 - Arundment No.109

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9 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the test schedule and shall be determined in conformance with the criteria specified in the Containment Leakage Rate Testing Program.

i DIABLO CANYON - UNITS 1 & 2 3/4 6-3 Unit I - Amendment No. 99,110 (Next page is 3/4 6-5) Unit 2 - Amendment No. 98,109 l

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CONTAIMENT SYSTEMS l

CONTAINMENT AIR LOCKS 4

LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed.

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

ACTION:

l a.

With one containment air lock door inoperable:

1.

Maintain at least the OPERABLE air lock door closed and either restore tha inoperable air lock door to OPERABLE status within 3j 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed, l

2.

Operation may then continue until performance of the next i

required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least 4

once per 31 days, t

j 3.

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

The provisions of Specification 3.0.4 are not applicable.

i b.

With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed, restore the inoperable air lock to OPERABLE status within 24 i

hours or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in 4

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

1 DIABLO CANYON - UNITS 1 & 2 3/4 6-5 Unit 1 - Amendment No. 110 Unit 2 - Amendment No. 109

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

l a.

By verifying leakage rates in accordance with the Containment Leakage Rate Testing Program.

b.

At least once per 6 months by verifying that only one door in each air lock can be opened at a time.

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DIABLO CANYON - UNITS 1 & 2 3/4 6-6 Unit 1 - Amendment No. 110 Unit 2 - Amendment No. 109

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CONTAINMENT SYSTEMS j-CONTAIMENT STRUCTURAL INTEGRITY t

LIMITING CONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

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

ACTION:

1 i

With the structural integrity of the containment not conforming to the above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-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 i

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

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SURVEILLANCE REQUIREMENTS i

4.6.1.6.1 Containment Surfaces The structural integrity of the exposed j

accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined during shutdown by a visual inspection of i

these surfaces. This inspection shall be performed in accordance with the Containment Leakage Rate Testing Program to verify no apparent changes in appearance or other abnormal degradation.

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4.6.1.6.2 Recorts Any abnormal degradation of the containment structure detected during the above required inspections shall be reported to the i

Commission in a Special Report pursuant to Specification 6.9.2 within 15 days.

i This report shall include a description of the condition of the concrete, the J

inspection procedure, the tolerances on cracking, and the corrective actions i

taken.

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DIABLO CANYON - UNITS 1 & 2 3/4 6-9 Unit 1 - Amendment No.110 Unit 2 - Amendment No.109

CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 One purge supply line and/or one purge exhaust line of the Containment Purge System may be open or the vacuum / pressure relief line may be open.

The vacuum / pressure relief line may be open provided the vacuua/ pressure relief isolation valves are blocked to prevent opening beyond 50' (90* is fully open).

Operation with any two of these three lines open is permitted.

Operation with the purge supply and/or exhaust isolation valves open or with the vacuum / pressure relief isolation valves open up to 50' shall be limited to less than or equal to 200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months during a calendar year.

APPLICABILITY:

MODES 1, 2, 3, and 4.

, ACTION:

With a containment purge supply and/or exhaust isolation valve open-or the vacuum / pressure relief isolation valves open up to 50' for more than 200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months during a calendar year or the Containment Purge System open and the vacuum / pressure relief lines open, or with the vacuum / pressure relief isolation valves open beyond 50', close the open isolation valve (s) or isolate the penetration (s) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and. in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.7.1 The position of the containment purge supply and exhaust isolation valves and the vacuum / pressure relief isolation valves shall be determined closed at, least once per 31 days.

4.6.1.7.2 The cumulative time that the purge supply and/or exhaust isolation valves or the vacuum / pressure relief isolation valves have been open du:ing a calendar year shall be determined at least once per 7 days.

4.6.1.7.3 The vacuum / pressure relief isolation valves shall be verified to be blocked to prevent opening beyond 50' at least once per 18 months.

DIABLO CANYON - UNITS 1 & 2 3/4 6-10

CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 Each containment isolation valve shall be OPERABLE.*

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With one or more of the isolation valve (s) inoperable, maintain at least one l

isolation valve OPERABLE in each affected penetration that is open and:

a.

Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or b.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the isolation position, or c.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange; or d.

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 .

Locked or sealed closed valves may be opened on an intermittent basis under administrative control.

SURVEILLANCE REQUIREMENTS 4.6.3.1 Each containment isolation valve shall be demonstrated OPERABLE prior I

to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test, and verification of isolation time.

4.6.3.2 Each containment isolation valve shall be demonstrated OPERABLE at l

1 east once per 18 months by:

a.

Verifying that on a Phase "A" Isolation test signal, each Phase "A" isolation valve actuates to its isolation position; b.

Verifying that on a Phase "B" Isolation test signal, each Phase "B" isolation valve actuates to its isolation position; and c.

Verifying that on a Containment Ventilation Isolation test signal, each containment ventilation isolation valve actuates to its isola-tion position.

DIf3LO CANYON - UNITS 1 & 2 3/4 6-15 Amendment Nos. 73 8 72

CONTAIMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.3 The isolation time of each testable power-operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

4.6.3.4 Each containment ventilation isolation valve, except the air sample supply and return valves, shall be demonstrated OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after eac5 closing of the valve, except when the valve is being used for multiple cycling, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months by verifying leakage rates in accordance with the Containment Leakage Rate Testing Program.

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DIABLO CANYON - UNITS 1 & 2 3/4 6-16 Unit 1 - Amendment No. M,110 Unit 2 - Amendment No. M,109 5

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3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and

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associated leak rates assumed in the safety analyses. This restriction, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE l

i The limitations on containment leakage rates specified in the Containment Leakage Rate Testing Program ensure that the total containment leakage volume I

will not exceed the value assumed in the safety analyses at the peak accident pressure, P. As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L during i

performance of the periodic test to account for possible degradation of the containment leakage barriers between leakage tests.

l The surveillance testing for measuring leakage rates as specified in the Containment Leakage Rate Testing Program is consistent with Regulatory Guide

-1.163 dated September 1995, and the requirements of Option B of 10 CFR Part 50 Appendix J.

3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that:

(1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosphere of 3.5 psig, and (2) the containment peak pressure does not exceed the design pressure of 47 psig during LOCA conditions.

The maximum peak pressure expected to be obtained from a LOCA event is less than 47 psig, which is the maximum design pressure of containment. This includes the limit of 1.2 psig for initial positive containment pressure. The total pressure is less than design pressure and is consistent with the safety analyses.

DIABLO CANYON - UNITS 1 & 2 B 3/4 6-1 Unit I - Amendment No. Er99,110 Unit 2 - Amendment No. Hy98,109

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Reissued September 19, 1991 CONTAINMENT SYSTEMS BASES 3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the safety analysis for a LOCA.

3/4.6.1. 6 CONTAll#4ENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment will withstand the maximum pressure in the event of a LOCA. The visual examination of the concrete todemonstratethiscapabi1Ity.Ifner, and the Type A leakage test are sufficient 3/4. 6.1.7 CONTAINMENT VENTILATION SYSTEM-Use of the containment purge lines is restricted to two of the three following lines:

(1) a supply line (2 an exhaust line of the purge system, and (3) the vacuum / pressure relief line)tu ensure that the SITE SOUNDA guidelines of 10 CFR Part 100 would not be exceeded in the event of a loss-of-coolant accident during conteinment purging operations. The vacum/ pressure relief valves must be. blocked to open no more than 50' because these valves have not yet been qualified to close under accident conditions.

Operation will be limited to 200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months during a calendar year. The 200-hour limit shall not become effective until after initial criticality. The total time the Containment Purge (vent) System isolation valves may be open during MODES 1, 2, 3, and 4 in a calendar year is a function of anticipated need and operating experience.

DIABLD CANYDN - UNITS 1 & 2 B 3/4 6-2 Amendment Nos. 65 and 64

ADMINISTRAT_IVE CONTROLS PRDCEDURES AND PRDGRAMS (Continued)

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5)

Limitations on the operability and use of the liquid and l

gaseous effluent treatment systers to ensure that the appro-priate portions of these systems are used to reduce releases 4

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of radioactivity when the projected doses in a 31 -day period would exceed 2 percent of the guidelines for the l

annual dose or dose comettaent conforming to Appendix I to I

10 CFR Part 50, i

7)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at er beyond the 51TE SOUNDARY shall be limited to the j

following:

a.

For noble gases: Less than or equal to a dose rate of i

500 ares /yr to the whole body and less than or equal to a dose rate of 3000 ares /yr to the skin, and

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b.

For Iodine-131, for Iodine-133, for tritium, and for j

all radionuclides in greater than 8 days: particulate form with half-lives Less than or equal to a dose rate of 1500 area /yr to any organ.

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8)

Limitations on the annual and quarterly air doses resulting i

from noble gases released in gaseous effluents from each unit to areas beyond the 5!TE B0UNDARY conforming to j

Appendix I to 10 CFR part 50, I

g)

Limitations on the annual and quarterly doses to MEMBERS OF l

THE PUBLIC from lodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the $1TE B0UNDARY conforming to Appendix ! to 10 CFR Part 50, and 10)

Limitations on the annual dose or dose comitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation free uranium fuel cycle sources conforming to 40

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CFR Part 190.

l h.

Radiolocical Environmental Monitorine Procram A program shall be provided to monitor the radiation and radio-nuclides in the environs of the plant. The program shall provide i

(1) representative sensurements of radioactivity in the highest potential exposure pathways, and of the effluent monitoring program (2) verification of the accuracy and modeling of environmental exposure pathways. The program shall (1 be contained in the RMCP, (2) confors to the gu' dance of Appe)ndix I to 10 CFR Part 50 and (3) include the following:

1)

Ronitoring, sampilng, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ERMP, DIAll0 CANYON - UNITS 1 & 2 5-15b Amendment Nos. 85 8 84 l

l ADMINISTRATIVE CONTROLS

,4 PROCEDURES AND PROGRAMS (Continued) h.

Radioloaical Environmental Monitorina Proaram 2)

A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3)

Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in the environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

i.

Reactor Coolant Puma Flywheel Inroection Inspect each reactor coolant pump flywheel in accordance with the recommendations of Regulatory Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

j.

Containment Leakaae Rate Testina Proaram j

A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program, dated September 1995".

The peak calculated containment internal pressure for the design basis loss of coolant accident, P,, is 47 psig.

The maximum allowable containment leakage rate, L,, at P,, shall be 0.10% of containment air weight per day.

Leakage rate acceptance criteria are:

a.

Containment overall leakage rate acceptance criterion is s 1.0 L,.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are s 0.60 L for the Type B and Type C tests and s0.75L,forTypeAfests; b.

Air lock testing acceptance criteria are:

1)

Overall air lock leakage rate is s 0.05 L, when tested at 2 P,.

2)

For each door, leakage rate is s 0.01 L, when pressurized to 2 10 psig.

The provisions of Specification 4.0.2 do-not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

The provisions of Specification 4.0.3 are applicable to the Containment Leakage Rate Testing Program.

DIABLO CANYON - UNITS 1 & 2 6-15c Unit 1 - Amendment No. 86 98,110 7

Unit 2 - Amendment No. 84 W,109 7

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ML20100Q444

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