ML20076A882
| ML20076A882 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/27/1991 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076A886 | List: |
| References | |
| NUDOCS 9107090078 | |
| Download: ML20076A882 (9) | |
Text
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j#je nigk UNITED STATES ~
NUCLEAR REGULATORY COMMISSION a
f-WASHWGTON, D. C. 20555
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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-275 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No. OPR-80 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Pacific Gas & illectric Company (the licensee) dated February 28, 1990, 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; 8.
The facility will operate. in conformity with the application, the provisions-of.- the Act, and. the regulations of the Commission, C.
There is reasonable assurance (i) the activities authorized by this amendment can be conducted >
endangering the health and safety.of-the public, and (ii) i activities will be conducted.in compliance with th, sion'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.
Accordingl), the license is amended by chaiges 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 cmended to read as follows:
9107090078 910627 DR ADOCK OSO 5
2 (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 64, 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 becomes effective at the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION d
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,M'd, k.s/ /Mfh ames E. Dyer, Director Project Directorate V Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 27,1991
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UNITED STATES
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s, m PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT N0. 2 DOCKET NO. 50-323 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 63 License No. OPR-82 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (the licensee) dated February 28, 1990, complies with the standards and s
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 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 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 o' the Comission'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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l (2). Technical Specifications The Technical Specifications contained in Appendix A and the l
Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 63, 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 becomes effective at the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
]j
( M>-,M
/m James E. Dyer, Director
- Project Directorate V l
Division of Reactor Projects ll!/IV/V l
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 27,1991 l
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ATTACHMENT TO LICENSE AMENDHENT NOS. 64 AND 61 FACILITY OPERATING LICENSE N05. DPR-80 AND 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 PAGE INSERT PAGE X
X 3/4 7-Da B 3/4 7-2a B 3/4 7-2b t
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INDEX J
LIMITINc CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS 3/4.1.1 TURBINE CYCLE Safety Valves...........................................
3/4 7-1 TABI C 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SE1 POINT WITH INOPERABLE STEAM LINE SAFETY VALVES.......
3/4 7-2 FABLE 3.7-2 STEAM LINE SAFETY VALVES PER L,3P....................
3/4 7-3 Auxiliary Feedwater System..............................
3/4 7-4 Ccndensato Storage Tank.................................
3/4 7-6 Specific Activity.......................................
3/4 7-7 TAGLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAFPLE AND ANALYSIS PR0 GRAM.............................
3/4 7-8 Main Ste-Line Isolation Valves........................
3/4 7-9 Steem G ator 10% Atmospheric Dump Valves............
3/4 7-9a
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S/4.7.2 STEAM GEL nTOR PRESSURE / TEMPERATURE LIMITATION.........
3/4 7-10 3/4.7.3 VITAL COMPONENT COOLING WATER SYSTEM....................
3/4 7-11 3/4.7.4 AUXILIARY SALTWATER 55 STEM..............................
3/4 7-12 3/4.7.5 CONTROL ROOM VENTI LATION SYSTEM.........................
3/4 7-13 3/4.7.6 AUXILIARY BUILDING SAFEGUARDS AIR FILTRATION SYSTEM.....
3/4 7-16 3/4.7.7 SNUB 8ERS................................................
3/4 7-18 FIGURE 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST..........
3/4 7-23 3/4.7.8 SEALED SOURCE CONTAMINATION............................
3/4 7-24 3/4.7.9 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System...........................
3/4 7-26 Spray and/or Sprinkler Sys tems.........................
3/4 7-28 C0 System..............................................
3/4 7-30 2
TABLE 3.7-3 CO SYSTEM............................................
3/4 7-31 2
dalon System............................................
3/4 7-32 Fire Hose Stations................
3/4 7-33 l
TABLE 3.7-4 FIRE HOSE STATIONS...................................
3/4 7-34 Amendment Nos.64 and 63 DIABLO CANYON - UNITS 1 & 2 x
l PLANT SYSTEMS S1EAM GENERATOR 10% ATHOSPHERIC DUMP VALVES LIMITING CONDITION FOR OPERATION l
3.7.1.6 Four steam cenerator 10% atmospheric dump valves (ADVs) with the associated block valves open and associated remote manual controls, including the backup air bottles, shall be OPERABLE.
APPLICABILIH:
H0 DES 1, 2, and 3.
(Cycle 5 and after)
ACTION:
a.
With one less than the required number of 10% ADVs OPERABLE, restore the inoperable steam generator 10% ADV to OPERABLE status within 7 j
days; or be in at least HOT SiANDBY 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With two less than the required numbered of 10% ADVs OPERABLE, restore at least one of the inoperable steam generator 10% ADVs 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 i
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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQdIREMENTS i
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- 4. 7.1. 6 Each steam generator 10% ADV, associated block valve and associated l
remote manual controls including the backup air bottles shall be demonstrated OPERABLE:
1 a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that the backup air bottle I
for each steam generator 10% ADV has a pressure grs!ater than or equal to 260 psig, and b.
At least once per 31 days by verifying that the steam generator 10%
ADV block valves are open, and l
c.
At least once per 18 months by verifying that all steam generator 10% ADVs Will operate using the remote manual controls and the backup air bottles.
DIArLO CANYON - UNITS 1 & 2 3/4 7-9a Amendment Nos, 64 and 63 y
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PLANT SYSTEMS BASES 3/4.7.1.4 SPECIFIC ACTIVITY The limitations on Secondary Coolant System specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of 10 CFR Part 100 dose guideline values in the event of a steam line rupture.
This dose also includes the effects of a coincident 1 gpm reactor-to-secondary tube leak in the stern generator of the affected steam line.
These values are consistent with the assumptions used in the safety analyses.
3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture.
This restriction is required to:
(1) minimize the positive reactivity ef fects of the Reactor Coolant Syste,n cooldown associated with the blowdown, and (2) limit the pressure rise within containment in the event the steam line rupture occurs within containment.
The OPERABILITY of the main steam isolation valves within the closure times of the Surveillance Requirements is consistent with the assumptions used in the safety analyses.
t 3/4.7.1.6 STEAM GENERATOR 10% ATMOSPHERIC DUMP VALVES The Limiting Condition for Operation requirement of four steam generator 10% atmospheric dump valves (ADVs) (PCV-19, PCV-20, PCV-21, and PCV-22) ensures that following a ste-generator tube rupture accident subcooling can be achieved, consistent with assumptions used in the steam generator tube rupture analysis, to facilitate equalizing pressures between the Reactor Coolant System and the faulted steam generator.
This eliminates further primary to secondary leakage and potential subsequent overfill of the affected steam generator.
The analysis assumo that the 10% ADV on the ruptureti steam generator is not used, and that the other three 10% ADVs are used for heat removal.
The surveillance requirement for the 10% ADVs backup air bottles ensures that the 10% ADVs will be available to mitigate the consequences of a steam generator tube ruptu u accident concurrent with loss of offsite power.
A backup air bottle pressure of 260 psig provides adequate air to operate as assumed in the analysis.
This provides sufficient margin to allow cooldown consistent with the cnalysis assumptions.
Concurrent with the requirement that a specific number of 10% ADVs be OPERABLE is the requirement that the associated 10% ADV block valves upstream be open.
Should an associated 10% ADV block valve be closed, the 10% ADV downstream of that block valve should also be considered inoperable and the applicable ACTION statement shall be entered until such time that the block valve is opened.
DIABLO CANiON - UNITS 1 & 2 B 3/4 7-2a Amendment Nos. 64 and 63
PLANT SYSTEMS BASES 3/4.7.1.6 STEAM GENERATOR 10% ATHOSPHERIC DUMP VALVES (continued)
Additionally, the requirements of Technical Specification 3.G.3, Containment Isolation Valves, apply to the 10% ADVs.
The Technical Specification is applicable in plant operational Modes 1, 2, and 3 because the 10% ADVs are required to provide the subcooling as necessary to permit primary system depressurization for SGTR accident mitigation, j
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DIABLO CANYON - UNITS 1 & 2 B 3/4 7-2b Amendment Nos. 64 and 63
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