ML20236H373
| ML20236H373 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 07/27/1987 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236H377 | List: |
| References | |
| TAC-60829, TAC-60830, NUDOCS 8708050162 | |
| Download: ML20236H373 (8) | |
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UNITED STATES j
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- t NUCLEAR REGULATORY COMMISSION j
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- WASHINGTON, D C. 20555 e
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l PACIFlc GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1
' DOCKET NO. 50-275 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 15 License No. DPR-80
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The Nuclear Regulatory Comission (the Comission) has found that:
1.
A.
The application for amendment by Pacific Gas & Electric Company (the licensee), dated February 13, 1936, complies with the standcrds 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; l
I B.
The facility will o>erate in conformity with the ap)11 cation, the provisions of tie Act, and the regulations of t,e Comission; C.
There is reasonable assurance (i) that the activities cuthorized 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 comon defense and security or to the health and safety of the public; and l
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.
l 870B050162 870727 PDR ADOCK 05000275 P
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 follcws:
1 (2) Technical Specification _s_
The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
16, 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.
j FOR THE NUCLEAR REGULATORY COMMISSION eorgeK. Knight irector Project Director V
Division of Reactor Projects - III, 1
IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 27, 1987 f
/psMooq'o, UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
W ASHINGTON, D. C. 20555
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5 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 2 DOCKET NO. 50-323 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 15 License No. DPR-82 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company i
(the licensee), dated February 13, 1986, complies with the standards and f
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 ap)11 cation, the provisions of the Act, and the regulations of t1e Comission; 1
i 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 of the Comission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical l
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.
15, are hereby incorporated in the license.
Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental l
Protection Plan, except where otherwise stated in specific license i
conditions.
3.
This license amendment becomes effective at the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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eorge W Knightow, Director Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects i
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Attachment:
I Changes to the, Technical Specifications s
Date of Issuance:
July 27, 1987 I
1
July 27e 1987 J
ATTACHMENT TO LICENSE AMENDMENT NOS.16 AND 15 l
FACILITY OPERATING LICENSE NOS. DPR-80 AND DPR-82
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l DOCKET NOS. 50-275 AND 50-323
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Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change, j
f Remove Insert I
3/4 4-19 3/4 4-19 3/4 4-20 3/4 4-20
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3/4 4-21 3/4 4-21
REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:
7 a.
No PRESSURE BOUNDARY LEAKAGE, b.
1 gpm UNIDENTIFIED. LEAKAGE, 1 gpm total reactor-to-secondary leakage through all steam c.
generators and 500 gallons per day through any one steam generator, d.
10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System,
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40 gpm CONTROLLED. LEAKAGE at a Reactor Coolant System pressure of e.
2235 1 20 psig, and
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1 gpm leakage at a Reactor Coolant System pressure of 2235 1 20 psig for Reactor Coolant System Pressure Isolation Valves as specified l
1 in Table 3.4-1, APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
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a.
With any PRESSURE B0UNDARY LEAKAGE, be in at least HOT STANDBY l
within 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 />.
b.
With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE B0UNDARY LEAKAGE and leakage from Reactor Coolant System pressure isolation valves, reduce the leakage rate to within 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 />.
With any Reactor Coolant System ' pressure isolation valve leakage c.
greater than the above limit, isolate the high, pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed manual and/or deactivated automatic valves, 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 />.
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i DIABLO CANYON - UNITS 1 & 2 3/4 4-19 Amendment Nos.16 and 15
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS Reactor Coolant System leakages shall be demonstrated toIbe within 4.4.6.2.1 each of the above limits by:
Monitoring the containment atmosphere particulate or gaseous a.
radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; b.
Monitoring the containment structure sump inventory and discharge at least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s-
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Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump c.
seals at least once per 31 days when the Reactor Coolant System pressure is 2235 1 20 psig with the modulating valve fully open.
The provisions of Specification 4.0.4 are not applicable for. entry into MODE 3 or 4; i
d.
Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, except when T,yg is being changed by greater than 5 F/ hour or when diverting reactor coolant to the liquid holdup tank, in which cases the required inventory balance shall be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of the excepted 1
operation; and
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Monitoring the Reactor Head Flange Leakoff System at least once per e.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.4.6.2.2 As specified in Table 3.4-1, Reactor Coolant System pressure isola-tion valves shall be demonstrated OPERABLE pursuant to Specification 4.0.5, except that in lieu of any leakage testing required by Specification 4.0.5,.
each valve shall be deinonstrated OPERABLE by verifying leakage to be within its limit:
J a.
Every refueling outage during startup, b.
Prior to returning the valve to service following maintenance, repair or replacement work on the valve, and j
I Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve actuation due to automatic or manual c.
action or flow through the valve. After each disturbance of the valve, in lieu of measuring leak rate, leak-tight integrity may be verified by absence of pressure buildup in the test line downstream of the valve.
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.
DIABLO CANYON - UNITS'1 & 2 3/4 4-20 Amendment Nos. 16 and 15
J TABLE 3.4-1, REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NUMBER FUNCTION Accumulator,fRHRandSIS 1.
8948 A, B, C, and D first off check valves from RCS cold legs 2.
8819 A, B, C, and 0 SIS:second off check valves from RCS cold legs 1
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3.
8818 A, B, C, and D RHR second off check valves from RCS cold legs 4.
- 8956 A, B, C, and D-Accumulator second off check. valves from RCS cold legs 5.
8701* and 8702*
RHR suction isolation valves 6.
8949# A, B, C, and D LSR and SIS first off
-l check valves from RCS' i
hot legs-1 7.
8905# A, B, C, and D SIS second off check valves from RCS hot legs 0
8.
8740# A and B RHR.second off check valves from RCS hot legs 9.
8802*# A and B SIS to RCS hot legs-isolation valves 10.
8703*#
RHR to RCS hot legs isolation valve-1 I
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- Testing per Specification 4.4.S.2.2c. not required.
- For flowpaths with 3 pressure. isolation valves in series, at least 2 of the 3 valves shall meet the requirements of Specification.3.4.6.2f.
i DIABLO CANYON - UNITS 1 & 2 3/4'4-21 An:endment Nos.16 and 15 l
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