ML20082H908
| ML20082H908 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/11/1995 |
| From: | Mark Miller NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20082H910 | List: |
| References | |
| NUDOCS 9504170419 | |
| Download: ML20082H908 (9) | |
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UNITED STATES
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PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-275 DIABLO CANYON NUCLEAR POWER PLANTA UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 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 February 16, 1994, 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 (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 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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(2) Technical Specification 1 The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Apper. dix B, as revised.~
through Amendment No.
99,- 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.
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3.
This license amendment is effective 30 days after the date of its
. issuancs.
FOR THE NUCLEAR REGULATORY COMMISSION t
s Melanie A. Miller, Senior 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: April 11, 1995
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Jh UNITED STATES B-NUCLEAR REGULATORY COMMISSION m-5 4f WASHINGTON, D.C. 2066Ek 0001 l
EA.CIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 98 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 16, 1994, complies with the standards s
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 "ommission; 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 Operating License No. DPR-82 is hereby amended to read as follows:
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(2)' Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained.in Appendix B, as revised -
through Amendment No.
98,- 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 30 days after the date of its issuance.
P FOR THE NUCLEAR REGULATORY COMMISSION :
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Melanie~ A. Miller, Senior 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:
April 11, 1995 i
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 99 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO. 98 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 Amendment number and contain marginal lines indicating the area of. change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMQYE INSERT 3/4 6-3 3/4 6-3 B 3/4 6-1 B 3/4 6-1 4
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, CONTAllMENT SYSTEMS SURVEILLANCE REQUIREMENTS i
4.6.1.2 The containment leakage rates shall be demonstrated at the following 1
test schedule and shall be determined in conformance with the criteria'speci-fled in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-1972:
a.
Three Type A ' tests (Overall Integrated Containment Leakage Rate) shall be conducted at approximately equal intervals during shutdown at greater than or equal to P, 47 psig, or, as applicable, at greater than or equal to P,, f5 psig, during each 10-year service period; b.
If any >eriodic Type A test fails to meet 0.75 L or 0.75 L as applica)1e, the test schedule for subsequent Typ,e A tests sh,all be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet either 0.75 L, or 0.75 L,, as applicable, a Type A test shall be performed at least every 18 months until two consecu-tive Type A tests meet either 0.75 L or 0.75 L, as applicable, at which time the above test schedule m,ay be resum,ed;
.I c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1)
Confirms the accuracy of the test by verifying that the supple-mental test result, L,, minus the sum of the Type A and the superimposed leak, L, is equal to or less than 0.7.5 L, or 0.25 L,, as - applicable; 1
2)
Has a duration sufficient to establish accurately the change in leakage between the Type A test and the supplemental test; and 3)
Requires that the rate at which gas is injected into the con-tainment or bled from the containment during the supplemental i
test is between 0.75 L, and 1.25 L, or 0.75 L, and 1.25 L,, as applicable.
1 DIABLO CANYON - UNITS 1 & 2 3/4 6-3 Unit 1 - Amendment No. 99 Unit 2 - Amendment No. 98
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~ CONTAINMENT' SYSTEMS' J
14 SURVEILLANCE REQUIREMENTS (Continued) d.
Type B and C tests'shall-be conducted with gas at P,, 47 psig,'at-intervals no greater.than 24 months ~except for tests involving:
1 1)
Air. locks, and 2)
Penetrations using continuous Leakage Monitoring Systems, Air locks shall be' tested and demonstrated OPERABLE by. the require-e.
ments of Specification 4.6.1.3; f.
Type B tests for penetrations employing a' continuous Leakage Monitoring System shall be conducted at greater than or equal to P,, 47. psig, at intervals no greater than once per'3 years;.
3 g.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall.be performed to select a balanced integrated Leakage Measurement System; and h.
The provisions of Specification 4.0.2 are not applicable.
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DIABLO CANYON - UNITS 1 & 2 3/4 6-4
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3/4.6 CONTAIMENT SYSTEMS BASES 3/4.6.1 CONTAIMENT 3/4.6.1.1 - CONTAIMENT 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 1
conjunction with the leakage rate limitation, will limit the SITE BOUNDARY l
radiation doses to within the dose guideline values of 10 CFR Part 100 during accident conditions.
.3/4.6.1.2 CONTAIMENT LEAKAGE
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The limitations on containment leakage rates ensure that the total j
containment leakage volume will.not exceed the value assumed in the safety analyses at the peak accident pressure, P i
measured overall integrated leakage rate l. As an added conservatism, the s further limited to less than or l
equal to 0.75 L or less than or equal to 0.75 L, as' applicable, during I
performanceoftheperiodictesttoaccountfor,possibledegradationofthe 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.
An exemption has been granted from the requirements of 10 CFR Part 50, 1
Appendix J, Section.III.D.I.(a). The exemption removes the requirement that i
the third Type A test for each 10-year period be conducted when the plant is i
shut down for the 10-year plant inservice inspection (Reference License Amendment Nos. 99 and 98). The interval between Type A containment tests will i
be.no greater than three 18-month fuel cycles, or 4.5 years.
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 3
containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosphere of 3.5 psig, and (2) the j
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 1 - Amendment No. 66,99 Unit 2 - Amendment No. 64,98
b Reissued SGptember 19,1991 CONTAINMENT SYSTEMS
. BASES 3/4.6.1.5 AIR TEMPERATURE The limitations on containment everage air temperature ensure that the overall containment everage air temperature does not exceed the initial temperature condition assumed in the safety analysis for a LOCA.
3/4.6.1.6 CONTAllMENT 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 l.
1 examination of the concrete liner, and the Type A leakage test are sufficient todemonstratethiscapabi1Ity.
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 ine,(2 an exhaust line of the purge system, and (3) the vacuum / pressure relief line)to 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 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.
Operetion 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 chall 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.
i DIABLD CANYON - UNITS I & 2 8 3/4 6-2 Amendment Nos. 65 and 64 l
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