ML20035C463
| ML20035C463 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/01/1993 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035C464 | List: |
| References | |
| GL-91-08, GL-91-8, NUDOCS 9304080003 | |
| Download: ML20035C463 (15) | |
Text
.
f[pacacg t UNITED STATES i
4 et E
NUCLEAR REGULATORY COMMISSION E
'f WASHINGTON, D.C. 20555-0001 (s /
PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-275 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. OPR-80 i
+
1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (the licensee) dated October 27, 1992, 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 1;
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 (1) that the activiti~s authorized e
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 i
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 i
amended to read as follows:
9304080003 930401 PDR ADOCK 05000275 P
FDR
. (2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 79
, 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 is effective as of 30 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COHMISSION Ldth lll.
hQin p
q31 Theodore R. Quay, Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 1, 1993 t
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UNITED STATES 3.. U
... E NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 23555 o
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PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 78 License No. DPR-82 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (the licensee) dated October 27, 1992, 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;
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 (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 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'io read as follows:
i l
+ ;
(2)
Technical Specifications The Technical. Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 78
, 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 is effective as of 30 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION (k1ba lll'.
{rhtn L
,(pg Theodore R. Quay, Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 1, 1993 e
h h
i
ATTACHMENT TO LICENSE AMENDMENTS i
AMENDMENT NO. 70 TO FACILITY OPERATING LICENSE NO. DPR-80 i
AND AMENDMENT N0.78 TO FACILITY OPERATING LICENSE NO. DPR-82 DOCKET N05. 50-275 AND 50-323 I
t 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 INSERT 1 of 6 1 of 6 4 of 6 4 of 6 5 of 6 5 of 6 xi xi 3/4 8-19
.3/4 8-19 3/4 8-20 3/4 8-20 3/4 8-21 3/4 8-21 3/4 8-22 3/4 8-23 3/4 8-24 B 3/4 8-3 B 3/4 8-3 B
t i
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APPENDIX A TO LICENSE NOS. DPR-80 AND DPR-82 DIABLO CANYON NUCLEAR POWER PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS (NUREG-1151)
LIST OF EFFECTIVE PAGES Paae No.
Amendment No.
Pace No.
Amendment No.
Title.Page Title Page 1
Note ii 67/66 B 2-1 71/70 111 60/59 B 2-la' 71/70 iv B 2-lb 60/59 v
71/70 B 2-2 vi B 2-3 vii 75/74 B 2-4 37/36 viii 54/53 B 2-5 ix 73/72 B 2-6 x#
77/76 B 2-7 72/71 xi #
79/78 B 2-8 30/29 xii 72/71
-B 2-9 30/29 xiii 67/66 Title Page xiv 12/10 3/4.0-1 55/54 xv 54/53 3/4 0-2 57/56 xvi 75/74 3/4 0-3 xvii 3/4 1-1 72/71 xviii 67/66 3/4 1-2 xix 3/4 1-3 72/71 xx
-3/4 1-4 10/8 xxi 68/67 3/4 1-5 xxii 78/77 3/4 1-6 xxiii 67/66 3/4 1-7 72/71 Title Page 3/4 1-8 72/71' l-1 3/4 1-9 72/71 1-2 73/72 3/4 1-10 1-3 67/66 3/4 1-11 1-4 3/4 1-12 72/71 1-5 67/66 3/4 1-13 72/71 1-6 67/66 3/4 1-14 1-7 45/44 3/4'1-15 45/44 1-7a 67/66 3/4 1-16 45/44 1-8 3/4 1-17 1-9 3/4 1-18 Title Page 3/4 1-19 2-1 60-59 3/4 1-20 72/71 2-2 60/59 3/4 1-21 45/44 2-3 3/4 1-22 45/44 2-4 72/71 3/4 2-1 45/44.
2-5
-72/71 3/4 2-2 45/44 2-6 30/29 3/4 2-3 45/44-2-7 72/71 3/4 2-4 12/10 2-8 72/71 3/4 2 71/70 2-9 72/71 3/4.2-6 71/70-
.DIABLO CANYON - UNITS 1 & 2 PAGE 1 0F 6 Amendment Nos.79 & 78
APPENDIX A TO LICENSE NOS. DPR-80 AND DPR-82 DIABLO CANYON NUCLEAR POWER PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS (NUREG-ll51)
LIST OF EFFECTIVE PAGES
[
Pace No.
Amendment No.
Paae No.
Amendment No.
3/4-7-28 3/4 9-7 55/54 3/4 7-29 3/4 9-8 28/27 3/4 7-30 3/4 9-9 28/27 3/4 7-31 3/4 9-10 70/69 3/4 7-32 3/4 9-11 39/38
~ i 3/4 7-33 3/4 9-11a 39/38 3/4 7-34 3/4 9-12 55/54 3/4 7-35 3/4 9-13 55/54 3/4 7-36 3/4 9-14 3/4 7-37 3/4 9-15 8/6 3/4 7-38 3/4 9-16 8/6 3/4 7-39 3/4 9-17 8/6 3/4 7-40 55/54 3/4 9-18 8/6 3/4 8-1 74/73 3/4 9-19 8/6 3/4 8-2 76/75 3/4 10-1 72/71 3/4 8-Za 15/14 3/4 10-2 71/70 3/4 8-3 44/43 3/4 10-3 3/4 8-4 44/43 3/4 10-4 3/4 8-5 15/14 3/4 11 67/66 3/4 8-6 15/14 3/4 11-2 67/66 3/4 8-7 15/14 3/4 11-3 67/66 3/4 8-8 15/14 3/4 12-1 67/66 3/4 8-9 Title Page 3/4 8-10 Note 3/4 B-11 74/73 8 3/4 0-1 55/54 3/4 8-12 6/4 8 3/4 0-la 55/54 3/4 8-13 6/4 B 3/4 0-lb 55/54 3/4 8-14 6/4 B 3/4 0-2 57/56 **
3/4 8-15 B 3/4 0-2a 55/54 **
3/4 8-16 B 3/4 0-3 55/54 3/4 8-17 B 3/4 1-1 10/8 3/4 8-18 B 3/4 1-2 72/71 3/4 8-19 79/78 8 3/4 1-3 14/13 3/4 8-20 79/7s B 3/4 2-1 12/10
.r 3/4 8-21 79na B 3/4 2-2 12/10 3/4 8-22 Deleted B 3/4 2-3 12/10 3/4 8-23 Deleted B 3/4 2-4 71/70 3/4 8-24 Deleted B 3/4 2-5 60/59 3/4'9-1 72/71 B 3/4 2-6 37/36 3/4 9-2 46/45 B 3/4 3-1 69/68 4
3/4 9-3 B 3/4 3-la 51/50 l
3/4 9-4 46/45 B 3/4 3-2 3/4 9-5 B 3/4 3-3
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3/4 9-6 B 3/4 3-4 75/74 DIABLO CANYON - UNITS l'& 2 PAGE 4 0F 6 Amendment.Nos. 79 & 78
APPENDIX A TO LICENSE NOS. DPR-80 AND DPR-82 l
DIABLO CANYON NUCLEAR POWER PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS (NUREG-11511' l
LIST OF EFFECTIVE PAGES Paae No.
Amendment No.
Pace No.
Amendment No.
j B 3/4 3-5 67/66 B 3/4 10-1.
l B 3/4 4-1 B 3/4;10 i B 3/4 4-2 27/26 B 3/4-11-1 67/66 j
B 3/4 4-2a 27/26 B 3/4 12-1 67/66~
B 3/4 4-3 Title Page l
B 3/4 4-4 5-1 B 3/4 4-5 18/17 5-2 B 3/4 4-6 5-3 B 3/4 4-7 54/53 5-4 24/23 B 3/4 4-8 54/53.
5-5 13/11 B 3/4 4-9 54/53 5-6 8/6 B 3/4 4-10 54/53 5-7 B 3/4 4-11 54/53 6-1 75/74 B 3/4 4-12 54/53 6-2 29/28 B-3/4 4-13 54/53 6-3 29/28 i
B 3/4 4-14 6-4 59/58 B 3/4 4-15 6-5 75/74 B 3/4 4-16 6-6 59/58 B 3/4 5-1 6-7 43/42 B 3/4 5-2 65/64 ***
6-7a 41/40 t
B 3/4 5-2a 72/71 6-8 75/74-B 3/4 5-3 14/13 6-9 75/74-B 3/4 6-1 65/64 ***
6-10
~68/67 B 3/4 6-2 65/64 ***
6-11 68/67 B 3/4 6-3 14/13 6-12 68/67 B 3/4 6-4 73/72 6-13 75/74 B 3/4 7-1 6-14 41/40 B 3/4 7-2 75/74 6-15
[
B 3/4 7-2a 75/74 6-15a 67/66 t
B 3/4 7-2b 77/76 6-15b 67/66 t
B 3/4 7-2c 77/76-B 3/4 7-3 6-16 43/42 i
B 3/4 7-4 66/65 #
6-17 67/66
{
B 3/4 7-5 66/65 #
6-18 78/77 B 3/4 7-6 75/74 6-19
_71/70_
B 3/4 7-7 75/74 6-20 68/67 B 3/4 7-8 6-21 67/66 B 3/4 8-1
'44/43 6-22.
67/66-B 3/4 8-2 44/43
_6-23 67/66 B 3/4 8-3 79/78 B 3/4 8-3a 74/73 B 3/4 9-1_
46/45 B 3/4 9-2 46/45 l
B 3/4 9-3 70/69 i
DIABLO CANYON - UNITS I & 2 PAGE 5 0F 6 Amendment Nos.79 & 78.
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INDEX
't LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS I
SECTION PAGE 3/4.7 PLANT SYSTEMS (continued) 3 3/4.7.11 AREA TEMPERATURE MONITORING.............................
3/4 7-37 TABLE 3.7-5 AREA TEMPERATURE MONITORING..........................
3/4 7-38 3/4.7.12 ULTIMATE HEAT SINK......................................
3/4 7-39 3/4.7.13 FLOOD PROTECTION........................................-
3/4 7-40 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0perating...............................................
3/4 8-1 TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE.......................
3/4 8-8 i
TABLE 4.8-2a LOAD SEQUENCING TIMERS - ESF TIMERS.................
3/4 8-9
~
TABLE 4.8-2b LOAD SEQUENCING TIMERS - AUTO TRANSFER TIMERS.......
3/4 8-10 Shutdown................................................
3/4 8-11 3/4.8.2 ONSITE POWER DISTRIBUTION I
i 0perating...............................................
3/4 8-12 Shutdown........................................
3/4 8-14 3/4.8.3 D.C. SOURCES i
0perating...............................................
3/4 8-15 j
TABLE 4.8-3 BATTERY SURVEILLANCE REQUIREMENTS....................
3/4 8-17 Shutdown................................................
3/4 8-18 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES-I Motor-Operated Valves Thermal Overload Protection and Bypass Devices......................................
3/4 8-19 i
l i
Containment Penetration Conductor Overcurrent i
Protective Devices......................................
3/4 8-20 l
I i
DIABLO CANYON - UNITS 1 & 2 xi Amendment Nos. 66 & 65 i
-5 & N, 79 & 78 l
m
- +'_
i INDEX e
LIMITING CONDITIONS FOR OPERATION-AND SURVEILLANCE REQUIREMENTS l
SECTION.
LPAGE j
3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.....................................
3/4 9-l' g
- f 3/4.9.2 INSTRUMENTATION..........................................
3/4 9-2
-l 3/4.9.3 DECAY TIME..............................................
3/4. 9-3 '
-j 3/4.9.4 CO NT AINME NT PENETR ATIONS................................ -
3/4 9-4' l
3/4.9.5 CO MM U N I C AT I O N S..........................................
3/4 9-5L i
)
3/4.9.6 MANIPULATOR CRANE.......................................
3/4 9-6 3/4.9.7 CRANE TRAVEL - FUEL HANDLING ' BUILDING...................
.3/4 9 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Leve1........................................
3/4 9-8 j
Low Water Leve1.........................................
3/4 9-9 3/4.9.9 CONTAINMENT VENTILATION ISOLATION-SYSTEM................
3/4 9-10~
i r
3/4.9.10 WATER LEVEL - RE ACTOR VE55EL............................
3/4 9-11 l
Fuel Assemblies.........................................
3/4 9-11
.i Control Rods............................................
3/4 9-11a' i
- 3/4.9.11 WAT E R LEVE L - SPENT FUEL P30L...........................
3/4 9-12 3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM...............
3/4 9 l 3/4.9.13 SPENT FUEL SHIPPING CASK M0VEMENT.......................
3/4 9 i 3/4.9.14 SPENT FUEL ASSEMBLY ST0 RAGE.............................
3/4 9-17 l
.I 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...............-..........................:
3/4 10-1
' l s
3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DIbTRIBUTION LIMITS...
-3/4 10-2
}
3/4.10.3 PHYSIC 5 TESTS..............................-.............
3/4 10-3L l
3/4.10.4 POSITION' INDICATION SYSTEM
-SHUTD0WN...................
3/4 10-4
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^ DIABLO CANYON'- UNITS 1 & 2 xii DAmendment Nos. J5 & 38, 72 & -71 l I
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i ELECTRICAL POWER SYSTEMS 3/4.8.4 ELECTRICAL E0VIPMENT PROTECTIVE DEVICES MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND BYPASS DEVICES l
LIMITING CONDITION FOR OPERATION 3.8.4.1 The thermal overload protection and bypass devices, integral with the motor starter, of each valve used in safety systems shall be OPERABLE.
l APPLICABILITY: Whenever the motor-operated valve is required to be OPERABLE.
{
ACTION:
With one or more of the thermal overload protection and/or bypass devices inoperable, declare the affected valve (s) inoperable and apply the appropriate ACTION Statement (s) for the affected valves.
SURVEILLANCE REQUIREMENTS 4.8.4.1 The above required thennal overload protection and bypass devices shall be demonstrated OPERABLE:
j a.
At least once per 18 months, by the performance of a TRIP ACTUATION DEVICE OPERATIONAL TEST of the bypass circuitry for those thermal overload devices which are either:
l t
1)
Continuously bypassed and temporarily placed in-force only when i
the valve motors are undergoing periodic or maintenance testing, or i
i 2)
Normally in force during plant operation and bypassed under accident conditions.
b.
At least once per 18 months by the performance of a CHANNEL CALIBRATION of a representative sample of at least 25% of:
1)
All thermal overload devices which are not bypassed, such that each non-bypassed device is calibrated at least once per 6 years, and 2)
All thermal overload devices wnich are continuously bypassed, such that each continuously bypassed device is calibrated and l
each valve is cycled through at least one complete cycle of full travel with the motor-operator when the thermal overload device is OPERABLE and not bypassed at least once per 6 years.
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DIABLO CANYON - UNITS 1 & 2 3/4 8-19 Amendment Nos;79 & 78 4
t ELECTRICAL POWER SYSTEMS CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES i
-i LlHITING CONDITION FOR OPERATION a
3.8.4.2 For each containment penetration provided with a containment penetra-tion overcurrent protective device (s), each device shall be OPERABLE.
1 APPLICABILITY: MODES 1, 2,-3, and 4.
l ACTION:
With one or more of the above required containment penetration conductor overcurrent protective device (s) inoperable:
a.
Restore the protective device (s) to OPERABLE status or deenergize the circuit (s) by tripping the associated protective device or racking out or removing the inoperable protective device within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, declare the affected system or component inoperable, and verify the asscciated protective device to be tripped or removed, or the inoperable protective device racked out or removed at least once per 7 days thereafter; or b.
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 f
SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
t SURVEILLANCE RE0VIREMENTS 4.8.4.2 Protective devices required to be operable as containment penetration i
overcurrent protective devices shall be demonstrated OPERABLE:
i a.
At least once per 18 months:
1)
By verifying that the medium voltage 12 kV circuit' breakers.
are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers and performing the following:
a)
A CHANNEL CALIBRATION of the associated protective relays, b)
An integrated system functional test which includes-simulated automatic actuation of the system and verifying i
that each relay and associated circuit breaker and overcurrent control circuit function as. designed, and I
i l
r DIABLO CANYON - UNITS 1 & 2 3/4 8-20 Amendment Nos. 55 &_54 l-79 & 78 t
- ~.,
ELECTRICAL POWER SYSTEMS SURVETLL ANCE REOUTREMENTS (Continued) c)
For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable 6
type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
i t
2)
By selecting and functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers.
Circuit breakers selected for functional testing shall be selected on a rotating basis. Testing of "drawout" type circuit breakers shall consist of a CHANNEL CALIBRATION of the associated solid-state trip device for both the long-time delay i
trip element and the short-time delay element along with a 1
breaker functional test. Testing of molded case circuit breakers shall consist of injecting a current with a value equal to 200% (for D.C. breakers) and 300% (for. A.C. breakers) of the i
pickup of the time delay element and verifying that the circuit breaker operates within the. time delay band for that current j
specified by the manufacturer. The instantaneous element of molded case circuit breakers shall be tested by injecting a current equal to -25%, +40% of the pickup value of the element and verifying that the circuit breaker trips with no intentional-
't time delay. Circuit breakers found out-of-tolerance during functional testing shall be replaced prior to resuming opera-tion. Circuit breakers that fail to trip magnetically before the withstand capability of the penetration conductor is reached shall be declared inoperable.
Circuit breakers that fail to trip thermally before the manufacturer's maximum tolerance shall be declared inoperable. For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested; and i
3)
By verifying that the thermal overload devices integral with the motor starters, used for penetration overcurrent protection, are OPERABLE by selecting a representative sample of at least 10% of the motor overload devices and performing a CHANNEL i
CALIBRATION. Motor overloads found inoperable shall be restored to OPERABLE status prior to resuming operation.
For each motor overload device found inoperable, a CHANNEL CALIBRATION shall be performed on an additional representative sample of at least 10%
of all the motor overload devices of the inoperable type until no more failures are found or a CHANNEL CALIBRATION has been performed on all motor overload devices of that type.
l b.
At least once per 60 months by subjecting each circuit breaker to an
[
inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations.
7 l
DIABLO CANYON - UNITS 1 & 2 3/4 8-21 Amendment Nos 79 & 78 l
p ELECTRICAL POWER SYSTEMS BASES A.C. Sources. D.C. Sources, and ONSITE POWER DISTRIBUTION (Continued) will not be more than 0.040 below the manufacturer's full charge specific gravity and that the overall capability of the battery will be maintained within an acceptable limit; and (4) the allowable value for an individual cell's ficat voltage, greater than 2.07 volts, ensures the battery's capability to perform its design function.
The OPERABILITY of the A.C. electrical power sources requires maintaining a supply of fuel oil to support the operation of the emergency diesel genera-tors. The stored fuel oil supports the function of the A.C. power sources to provide power for the operation of emergency systems and engineered safety features (ESF) during and following the shutdown of the reactor in the event that offsite power sources are not available. The specified fuel oil quantity is based on the calculated fuel oil consumption necessary to support the opera-l tion of the emergency power source to power the minimum required ESF systems.
Operation of minimum ESF systems is required to mitigate a design basis acci-dent (LOCA) in one unit and those minimum required systems for a concurrent-
}
non-LOCA safe shutdown in the remaining. unit (both units initially in Mode I-operation). The fuel oil consumption is calculated for a period of 7 ' days operation of minimum ESF systems. This requirement provides a sufficient operating period within which offsite power can be restored and/or additional fuel can be delivered to the site.
The Surveillance Requirements applicable to diesel generator fuel oil storage requires cleaning the fuel oil storage tanks on a 10-year frequency.
Conducting this surveillance requires the tank to be taken out of service.
For this infrequent event, the inventory in the remaining tank is sufficient i
to support operation of the' emergency diesel generator to power the minimum required loads to maintain safe conditions for a time period of 4 days, considering one unit in Mode I through 6 operation and one unit in Mode 6 operation with at least 23 feet of water above the reactor vessel flange or
+
with the reactor defueled.
3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES The OPERABILITY of the motor operated valves thermal overload protection and bypass devices ensures that these devices will not prevent safety related valves from performing their function. The Surveillance Requirements for demonstrating the OPERABILITY of these devices are in accordance with Regulatory Guide 1.106, " Thermal Overload Protection for Electric Motors on Motor Operated Valves," Revision 1, March 1977.
A list of the TS-controlled MOV thermal overload protection and bypass devices is maintained in the Diablo Canyon plant procedures. The administra tion of the list shall be conducted in accordance with Section 50.59 of 10 CFR Part 50 and the provisions _ in the Administrative Controls Section of the TS.
Records of the changes to the valve list are maintained, and an annual report t
is made that includes a brief description of changes and a summary of the j
safety evaluation of each in accordance with 10 CFR 50.59.
Containment electrical penetrations and penetration conductors are pro-tected by either deenergizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary and backup overcurrent protec-tion circuit breakers during periodic surveillance.
DIABLO CANYON - UNITS 1 & 2 B 3/4 8-3 Amendment Nos. M & M,. 74 & 7-3, 79 & 78
t i,
1 ELECTRICAL POWER SYSTEMS 5
BASES r
ELECTRICAL EQUIPMENT PROTECTIVE DEVICES (Continued) i The Surveillance Requirements applicable to lower voltage circuit breakers provide assurance of breaker reliability by testing at least one representative sample of each manufacturer's brand of circuit breaker.
Each manufacturer's molded case and metal case circuit breakers are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers are tested.
If a wide variety exists within any manufacturer's brand of circuit breakers, it is necessary to divide that manufacturer's breakers into groups and treat each group as a separate type of breaker for surveillance purposes.
i A list of containment penetration conductor overcurrent protective devices, with information on location.and size and equipment powered by the protected circuit, is maintained and controlled at the plant site. The list is limited to those overcurrent devices installed for the purpose of keeping circuit fault current below the penetration rating.
It does not apply to other overcurrent devices associated with containment penetrations. The addition or deletion of any containment penetration conductor overcurrent protective device is governed by Section 50.59 of 10 CFR Part 50.
'i i
i i
DIABLO CANYON - UNITS 1 & 2 B 3/4 8-3a Amendment Nos. If & Z8. 74 & 73
-\\