ML20207N846
| ML20207N846 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 01/07/1987 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207N848 | List: |
| References | |
| TAC-60833, TAC-60834, NUDOCS 8701140461 | |
| Download: ML20207N846 (9) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION a
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WASMNGTON, D. C. 20655
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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 "
DOCKET NO. 50-275 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.11 License No. DPR-80 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment dated February 14,1986,(LAR86-03) by Pacific Gas & Electric Company (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized
' I-by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by a change to the combined Technical Specifications for Units 1 and 2 as indicated in the attachment to this license amer.dment, and paragraph 2.C.(2) of Facility Operating License No. DPR-80 is hereby amended to read as follows:
8701140461 870107 PDR ADOCK 05000275 ]
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_2 (2) Technical Specifications The Technical Specifications contained in Appendix A,as revised through Amendment No. 11, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license.
PG8E shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment becomes effective on the date of its issuance.
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FOR THE NUCL R F GULATORY COMMISSION
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PWR Project Direr'or
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Attachment:
Changes to the Technical Specifications Date of Issuance: January 7, 1987 6
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NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D. C. 20555
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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 2 -
DOCKET NO. 50-323 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 License No. DPR-82 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment dated February 14,1986,(LAR96-03) by Pacific Gas & Electric Company (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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;
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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.
i 2.
Accordingly, the license is amended by a change to the combined Technical Specifications for Units 1 and 2 as indicated in the attachment to this license amendment, and paragraph ?.C.(2) of Facility Operating License No DPR-82 is hereby amended to read as follows:
i
. (2) Technical Specifications The Technical Specifications contained in Appendix A..as revised through Amendment No. 9, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license.
PGAE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment becomes effective on the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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f 7ts rh, or PWR Proiect Dire te #3 Division of PWR sing-A, NRR
Attachment:
Changes to the Technical Specifications Date of Issuance: January 7, 1987 S
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UNITED STATES P
NUCLEAR REGULATORY COMMISSION o
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ATTACHMENT TO LICENSE AMENDMENT NOS. 11 AND g FACILITY OPERATING LICENSE NOS. DPR-80 AND DPR-82 DOCKET NOS. 50-275 AND 50-323 Revise the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment Number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 3/4 6-7 3/4 6-7 3/4 6-13 3/4 6-13 B 3/4 6-1 B 3/4 6-1 8 3/4 6-2 B 3/4 6-2 l
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CONTAINMENT SYSTEMS INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION
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- 3. 6.1. 4 Containment internal pressure shall be maintained between -1.0 and
+1.2 psig.
l APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
I' With the containment internal pressure outside of the limits above, restore the internal pressure to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 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 />.
t SURVEILLANCE REQUIREMENTS 4.6.1.4 The containment internal pressure shall be determined to be within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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DIABLO CANYON - UNITS 1 & 2 3/4 6-7 Amendment Nos. II and 9
CONTAINMENT SYSTEMS CONTAINMENT COOLING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.3 The Containment Cooling System shall be OPERABLE with either:
At least three electrically independent groups of containment fan a.
cooler units with a minimum of one unit in each group, or b.
At least two electrically independent groups of containment fan cooler units with a minimum of two units in each group.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With one group of the above required containment cooling fans a.
s inoperable and both Containment Spray Systems OPERABLE, restore the inoperable group of cooling fans to OPERABLE status within 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 SHUT-D0WN 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 two groups of the above required containment cooling fans inoper-able, and both Containment Spray Systems OPERABLE, restore at least one group of cooling fans 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 />.
Restore both above required groups of cooling fans to OPERABLE status within 7 days of initial loss 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 SHUT-DOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
With one group of the above required containment cooling fans c.
inoperable and one Containment Spray System inoperable, restore the inoperable Spray System 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 />.
Restore the inoperable group of containment l
cooling fans to OPERABLE status within 7 days of initial loss 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 />.
SURVEILLANCE REQUIREMENTS 4.6.2.3 Each containment fan cooler unit shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1)
Starting each containment fan cooler unit and verifying that each containment fan cooler unit operates for at least 15 minutes, DIABLO CANYON - UNITS 1 & 2 3/4 6-13 Amendment Nos.ll and 9 l
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 associated leak rates assumed in the safety analyses.
This restriction, in conjunction with the leakage rate limitation, will limit the SITE B0UNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions.
3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total contain-ment leakage volume 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, or less than or equal to 0.75 L, as applicable, during perfomance of t
the periodic test to account for possible degradation of the containment leakage barriers between leakage tests.
'the surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J of 10 CFR Part 50.
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l 3/4.6.1.3 CONTAINMENT AIR LOCKS l
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 46.65 psig. This includes the limit of 1.2 psig for initial positive contain-ment pressure.
The total pressure is less than design pressure and is con-sistent with the safety analyses.
DIABLO CANYON - UNITS 1 & 2 B 3/4 6-1 Amendment NosJI and 9 l
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 CONTAINMENT 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 of 46.65 psig in the event of a LOCA.
The l
visual examination of the concrete, liner, and the Type A leakage test are sufficient to demonstrate this capability.
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 to ensure that the SITE BOUNDARY dose guidelines of 10 CFR Part 100 would not be exceeded in the event of a loss-of-coolant accident during containment purging operations. The vacuum / 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 <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> 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, ear is a function of anticipated need and operating experience.
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DIABLO CANYON - UNITS 1 & 2 B 3/4 6-2 Amendment Nos.lland 9
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