ML20095G896
| ML20095G896 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/17/1992 |
| From: | Gagliardo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20095G898 | List: |
| References | |
| NUDOCS 9204290170 | |
| Download: ML20095G896 (9) | |
Text
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'n NUCLEAR REGULATORY COMMISSION 3 4 WASHINGTON. D, C. 20555 l;
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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. 69 License No. DPR-80 1.
TN Kuclear Regulatory Commission (the Consission) has found that:
A.
The application for amendment by Pacific gas & Electric Company (the licensee) dated March 18, 1991, as supplemented by letters dated May 3 and November 22, 1991, complies with the standards and requirements of the Atumic Energy Act of 1954, as amended (the Act),
and the Coumission's regulations set forth in 10 CFR Chapter I; B.
The facilitj will operate in conformity with the application, the provisions of the Act, and the regulations of the Commissior.;
C.
There is reasonable assurance (i) that the-activities authorized by this amendment can be conducted without endangering the health and saf ety of the public, and (ii) that such~ activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this onendment 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 1 4 mended by changes to the Technical Specifications as indicateo.n the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operatino License No. DPR-80 is hereby amended to read as follows:
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-2 (2) [echnical Specifications The Technical Specifications containcd in Appendix A and the Environnental Protection Plan contained in Appendix B, as revised through Amendar.t No. 69, are hereby incorporatea in the license.
Facific Gas & Electric Company shall operate the f acility in accordance with the Technical Sperifications and the Environmental Protectior. Plan, except where otherwise stated in specific license cor.ditions.
3.
This license arnenount becomes effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0FNISSION r&/
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'h James E. Gagliardo, acting Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Reguletion
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 17, 1992
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NUCLEAR REGULATORY COMMISSION s,
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D0CKET,NO. 50-323 AMENDMENTTOFACILITYOFEQLI,NGLICENSE Amendment tio. 68 License No. DPR-82 1.
The f;uclear Regulatory Conmission (the Commission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (the licensee) dated March 18, 1991, as supplemented by letters dated Fay 3 and November 22, 1991, complies with the standards and requirerents of the Atomic Energy Act of 1954, as atended (the Act),
and the Commission's regulations set forth in 10 CFR Chapter I; B.
The f acility will operate in conformit3 with the application, the provisior,s of the Act, and the regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment con be conducted without endangering the. health and safety of the public, and (ii) that such activities will be conducted in compliarse with the Curmission'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, end paragraph 2.C.(2) of Facility Operating License No. DPP.-82 is hereby agended to read as follows:
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i l (2) _ Technical Specifications The Technical Specifications containea in Appendix A &nd the Environn4 ental Protection Plan niitoined in Appendix B, as revised through Amendment No.
68, are hereby incorporated in the license.
Fecific Gas & Electric Con.pany shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conaitions.
3.
This license amendr9nt becomes effective as of the date of its issuance.
FOR THE NUCLEAR REGULA7vRY COMMISSION f
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Jan.es E. Gagliardo, Acting Director Project Directorate V Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specificaticns Date of Issuance:
April 17, 1992
ATTACHMEN1 TO LICENSE AMENDPENT NOS. 64 AfC 68 FACILITY OPERATING LICENSE N05. DPR-80 AND DPR-82 DOCKET N05. '0-275 AND 50-323 Revise Appendix A Terhoical Specifit.ations by renoving the pages identified below and inserting the enclosed pages.
The revised pages are ider.tified by the captioned arrenar.ent nur.ber end contain marginal lines indicating the area of change. Overleaf pages are also included, as appropriate.
REFj0VE PAGE INSERT PAGE a/4 6-14 3/4 6-14 5 3/4 3-1 B 3/4 3-1 n
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a 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 cooler units with a minimum of one unit in each group, or At least two electrically independent groups of containment fan cooler a.
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.
3 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 withi.i 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 />, 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 ir 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 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-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 hrurs.
Restore the inoperable group of containmant cooling fans to OPERABLE status within 7 days of initial loss or be in at least HOT 5TANDBY 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 deraonstrated OPERABLE:
At least once per 31 days by:
p.
1)
Starting each containment fan cooler unit acd verifying that each containment fan cooler unit operates for at least 15 minutes, DIABLO CANYON - UNITS 1 & 2 3/4 6-13 A.Tendment Nos.ll and 9
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2)
Verifying a cooling water flow rate of greater than or equal to 2000 gpm to each cooler, and 3)
For Units 1 and 2, Cycle 5:
Verifying that each containment fan cooler unit starts on low speed and the dampers transfer to the accident position.
For Units 1 and 2, Cycle 6 and after:
Verifying that each containment fan cooler unit starts on low t
speed.
b.
At least once per 18 mont5s by verifying that each containment fan cooler unit starts automatically on a Safety Injsetion test signal.
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DIABLO CANYON - UNITS 1 & 2 3/4 6-14 Amendment Nos. 69 and 68 s
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3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION The OPERABILITY of the Reactor Trip System and Engineered Safety Features Actuation System instrumentation and interlocks ensure that:
(1) the associated ACTION and/or Reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic and sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance consistent with maintaining an appropriate level of reliability of the Reactor Protection and Engineered Safety Features instrumentation, and (3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and (4) sufficient system functional capability is available from diverse parameters.
The OPERABILITY of these systems is required to provide the overall re-liability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions.
The integrated operation of each of these systems is consistent with the assump-tions used in the accident analyses.
The Surveillance Requirements specified for these systems ensure that the overall system functional capability is main-tained comparable to the original design standards.
The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.
Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271, " Evaluation of Surveillance Frequencies and Det of Service Times for the Reactor Protection Instrumentation System," ano n g lements to that report.
Surveillance intervals and out of-service times were determined based on maintaining an appropriate level of reliability of the Reactor Protection Systein.
The Engineered Safety Features Actuation System senses selected plant parameters and determines whether or nui, preaetermined limits are being exceeded.
If they are, the signals are combined into logic matrices sensitive to combinations indicative ef various accidents, events, and transients.
Once i
I the required logic combination is completed, the system sends actuation signals to those engineered safety features components whose aggregate function best serves the requirements of the condition.
As an example, the following a.ctions may be initiated by the Engineered Safety Features Actuation System to mitigate the consequences of a P.eam line creak or loss of coolant accident:
(1) safety injection pumps start and automatic valves position, (2) Reactor trip, (3) feed-water isolation, (4) startup of the emergency diesel generators, (5) containment spray pumps start and automatic valves position, (6) containment isolation, (7) steam line isolation, (8) Turbine trip, (9) auxiliary feedwater pumps start and automatic valve posi'. ion, (10) containment fan cooler units start, and (11) component cooling vater pumps start and automatic valves position.
l ESF response times specified in Table 3.3-5, which includa sequential operation of the RWST and VCT valves (Table Notations 4 and 5), are based on values assumed in the ncn-LOCA safety analyses.
These analyses take credit for injection of boratec weter from the RWST.
Injection of borated water is DIABLO CANYON - UNITS 1 & 2 B 3/4 3-1 Amendment Nos. 5I and 50 '
69 and 68
1NSTRlMENTAT10N BASES REACTOR PROTECTION SY!, TEM and ENGINEERED SAFETY FEATURES ACTUATION _SYS1FM M]iiUMENTAT10N (Continued) assumed not to occur until the VCT charging pump suction isolation valves are closed following opening cf the RW5T charging pump suction isolation valves.
When the sequential operation of the Rt!ST and VCT valves is not included in the response times (Table Notation 7), the values specifCed are based on the LOCA analyses. The LOCA analyses takes credit for injection flow regardless of the source. Verification of the response times specified in Table-3.3-5 will assure that the assumptions used for the LOCA and non-LOCA analyses with respect to the operation of the VCT and RWST valves are valid.
T DIAB!.0 CANYON - UNITS 1&2 8 3/4 3-la
'mendmerit No:. 51 and 50
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