ML20141F094
| ML20141F094 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 12/23/1985 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20141F100 | List: |
| References | |
| TAC-59657, TAC-59658, NUDOCS 8601080617 | |
| Download: ML20141F094 (11) | |
Text
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9 d aag y
jo UNITED STATES g
8 NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
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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.4 License No. DPR-80 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment dated August 27, 1985 (LAR 85-08) 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 (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 ",rt 51 of the Comission's regulations and all applicable requir.ents 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 amendment, and paragraph 2.C.(2) of Facility.0perating License No. DPR-80 is hereby amended to read as follows:
8601000617 851223 PDR ADOCK 05000275 P
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 4
, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license.
PG&E shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment becomes effective at the date of its issuance.
FOR THE NUCLEAR REGUL4 TORY COMMISSION
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Steven A.\\ _arga,
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V irector i
PWR Project Directorate #3 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: December 23, 1985 l
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"" " * %W'o UNITED STATES 8
N NUCLEAR REGULATORY COMMISSION
- E WASHINGTON, D. C. 20555 4,...../
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 2 DOCKET N0. 50-323 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.2 License No. DPR-8?
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment dated August 27,1985,(LAR85-08) 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 Commission'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; I
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; 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 a change to the combined Technical Specifications for Units 1 and 2 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:
. ;I (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 2, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license.
PG&E shall operate the facility in accordance with the Technical Speci.fications and the Environmental Protection Plan.
I 3.
This license amendnent becomes effective at the date of its issuance.
FOR THE NUCLEAR GULATORY COMMISSION 4
1 0%~s Stei n A. Varga frector h
PWR roject Directorate #3 Divi ion of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: December 23, 1985 o
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ATTACHMENT TO LICENSE AMENDMENT NOS. 4 AND 2 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 i
with the enclosed pages. The revised pages are identified by Amendment i
Number and contain vertical lines indiciating the area of change.
I Remove Pages Insert Pages 3/4 3-2 3/4 3-2 3/4 3-4 3/4 3-4 3/4 3-6 3/4 3-6 3/4 3-7 3/4 3-7 8 2-8 B 2-8 B 2-9 8 2-9 i
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TABLE 3.3-1 S
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E REACTOR TRIP SYSTEM INSTRUMENTATION 5
MINIMUM n
E-TOTAL NO.
CHANNELS CHANNELS APPLICABLE g
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 1.
1 2
1, 2 1
E 2
1 2
3*, 4*,
5*
11 Z
2.
Power Range, Neutron Flux a.
High Setpoint 4
2 3
1, 2 2#
i b.
Low Setpoint 4
2 3
1###,2 2#
m 3.
Power Range, Neutron Flux 4
2 3
1, 2 2#
High Positive Rate 4.
Power Range, Neutron Flux 4
2 3-1, 2 2#
High Negative Rate l
R 5.
Intermediate Range, Neutron Flux 2
1 2
1###, 2 3
l
\\
l Y
6.
Source Range, Neutron Flux N
a.
Startup 2
1 2
2##
4 l
I b.
Shutdown 2
1 2
3*, 4 *, 5
- 11 c.
Shutdown 2
0 1
3, 4, and 5 5
I 7.
Overtemperature AT 4
2 3
1, 2 6#.
8.
Overpower AT 4
2 3
1, 2 6#
5 9.
Pressurizer Pressure-Low 4
2 3
1 6#
I 10.
Pressurizer Pressure-High 4
2 3
1, 2 6#
l
[
11.
Pressurizer Water Level-High 3
2 2
1 6#
5 m
l L
l i
l l
L
TABLE 3.3-1 (Continued):
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5:
REACTOR TRIP SYSTEM INSTRUMENTATION
?
MINIMUM 52 TOTAL NO.
CHANNELS-CHANNELS APPLICABLE 25 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION E
i 18.
Safety Injection Input c-from ESF 2
1 2
1, 2 10 Nd 19.
Reactor Coolant Pump Breaker Position Trip above P-7 1/ breaker 2
1/ breaker 1
9 s.
e.
m 20.
Reactor Trip Breakers 2
1 2
1, 2 10 l
2 1
2 3*, 4 *, 5*
11 21.
Automatic Trip and Interlock 2
1 2
1, 2 10 i
Logic 2
1 2
3*, 4*, 5*
11 22.
Reactor Trip System Interlocks us 30 a.
Intermediate Range l
Neutron Flux, P-6 2
1 2
2##
8 u,
b.
Low Power Reactor Trips Block, P-7 P-10 Input 4
2 3
1 8#
P-13 Input 2
1 2
1 8#
c.
Power Range Neutron gr Flux, P-8 4
2 3
1 8#
![
d.
Power Range Neutron Flux, P-10 4
2 3
1, 2 8#
5 e.
Turbine Impulse Chamber l
l 5
Pressure, P-13 (Input to P-7) 2 1
2 1
8#
z h
23.
Seismic Trip 3 direc-2/3 loca-2/3 loca-1, 2 6#
tions (x,y,z) tions one tions all l
I in 3' locations direction directions E.
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TABLE 3.3-1 (Continued)
ACTION STATEMENTS (Continued)
ACTION 3.-
With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
a.
Below the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint, and b.
Above the P-6 Setpoint', but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.
ACTION 4 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive reactivity changes.
ACTION 5 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within I hour and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and b.
The Minimum Channels OPERABLE requirement is met; however, the i
inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.
ACTION 7 - With the number of OPERABLE channels less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel (s) is (are) placed in the tripped condition i
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />' determine by observation of the associated permissive annun-ciator window (s) that the interlock is in its required state for the existing' plant condition, or apply Specification 3.0.'3.
DIABLO CANYON.- UNITS 1 & 2 3/4 3-6 Amendment Nos, 4 and 2
e TABLE 3.3-1 (Continued)
ACTION STATEMENTS (Continued)
I j
ACTION 9 - With less than the Minimum Number of Channels OPERABLE, operation l
may continue provided the inoperable channel is placed in the tripped condition within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 10 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one' channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.
ACTION 11 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor trip breakers within the next hour.
t i
i DIABLO CANYON - UNITS 1 & 2 3/4 3-7 l
LIMITING ~ SAFETY SYSTEM SETTINGS BASES Turbine Trip A Turbine trip initiates a Reactor trip.
On decreasing power, the Turbine trip is automatically blocked by P-7 (a power level of approximately 10%
of RATED THERMAL POWER with a turbine impulse chamber at approximately 10%
of full power equivalent); and on increasing power, reinstated automatically by P-7.
Safety Injection Input from ESF If a Reactor trip has not already been generated by the Reactor Trip System instrumentation, the ESF automatic actuation logic channels will initiate a Reactor trip upon any signal which. initiates a Safety Injection.
The ESF instrumentation channels which initiate a Safety Injection signal are shown in Table 3.3-3.
Reactor Coolant Pump Breaker Position Trip The Reactor Coolant Pump Breaker Position trip is an anticipatory trip which provides score protection against DNB.
The Open/Close Position trip as-sures a reactor trip signal is generated before the Low Flow Trip Setpoint is reached.
No credit was taken in the safety analyses for operation of this trip.
The functional capability at the open/close position settings is re-quired to enhance the overall reliability of the Reactor Trip System.
Above P-7 (a power level of approximately 10% of RATED THERMAL POWER or a turbine impulse chamber pressure at approximately 10% of full power equivalent) an auto-matic reactor trip will occcur if more than one reactor coolant pump breaker is opened.
Below P-7 the trip function is automatically blocked.
l Reactor Trip System Interlocks The Reactor Trip System Interlocks perform the following functions:
P-6 On increasing power, P-6 allows the manual block of the Source Range trip and de-energizing of the high voltage to the detectors.
On de-creasing power, Source Range Level trips are automatically reacti-vated and high voltage restored.
P-7 On increasing power, P-7 automatically enables Reactor trips on low.
flow in more than one reactor coolant loop, more than one reactor coolant pump breaker open, reactor coolant pump bus undervoltage and underfrequency, Turbine trip, pressurizer low pressure and pressur-izer high level.
On decreasing power, the above listed trips are automatically blocked.
DIABLO CANYON - UNITS 1 & 2 8 2-8 Amendment Nos. 4 and 2
P LIMITING SAFETY SYSTEM SETTINGS 3
BASES (ReactorTripSystemInterlocks(Continued)
P-8 On increasing power, P-8 automatically enables a reactor trip on low flow in one or more reactor coolant loops.
On decreasing power the P-8 automatically blocks the above trip.
P-10 On increasing power, P-10 allows the manual block of the Intermediate Range reactor trip and the Low Setpoint Power Range trip; and auto-matically blocks the Source Range trip and deenergizes the Source
-Range high voltage power.
On decreasing power, the Intermediate Range
, trip and the Low Setpoint Power Range trip are automatically reacti-
/ vated.
Provides input to P-7.
P-13 Provides input to P-7.
Seismic Trip The Seismic trip is provided,to automatically shutdown the reactor in the event of a seismic occurrence which corresponds in magnitude to the Double De-sign Earthquake.
No credit was taken for operation of the Seismic trip in the safety analysis; however, its functional capability at the specified trip set-tings is required to enhance the overall reliability of the Reactor Trip System.
I' I
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DIABLO CANYON - UNITS 1 & 2 8 2-9 Amendment Nos. 4 and 2
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