ML20085M474
| ML20085M474 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/07/1995 |
| From: | Mark Miller NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20085M476 | List: |
| References | |
| NUDOCS 9506290208 | |
| Download: ML20085M474 (18) | |
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_ UNITED STATES
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,g NUCLEAR REGULATORY COMMISSION l
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WASHINGTON, D.C. 30006 4001 i
PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-275 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE r
e Amendment No.104 License No. DPR-80 t
1.
The Nuclear Regulatory Commission (the Commission) has found that:
j A.
The application for amendment by Pacific Gas and Electric Company i
(the licensee) dated February 6, 1995, as supplemented by-letters dated March 24, and May 22, 1995, complies with the standards and i
requirements of the Atomic Energy Act of 1954, as amended.(the Act), and the Commission's regulations set forth in 10 CFR l
Chapter I; 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; l
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 j
requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment, l
and paragraph 2.C.(2) of Facility Operating License No. DPR-80 is hereby amended to % d as follows:
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9506290208 950607 PDR ADOCK 05000275
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W (2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 104, are hereby incorporated in the license.
Pacific Gas and 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 its date of issuance to be implemented within 30 days of the date of issuance.
I FOR THE NUCLEAR REGULATORY COMMISSION
}%L0.]W Melanie A. Miller, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specificetions Date of Issuance:
June 7, 1995 t
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION-2 WASHINGTON, D.C. 30666-0001
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PACIFIC GAS AND ELECTRIC COMPANY 1
DOCKET NO. 50-323 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 103 License No. DPR-82 1.
The Nuclear Regulatory Commission (the Comission) has found that:
P A.
The application for amendment by Pacific Gas and Electric Company (the licensee) dated February 6,1995, as supplemented by letters dated March 24, and May 22, 1995, 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 i
Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission-l 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 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 to read as follows:
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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. 103, are hereby incorporated in the license. Pacific Gas and 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 its date of issuance to be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 0.
Melanie A. Miller, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 7,1995 I
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_4 ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 104 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO. 103 TO FACILITY OPERATING LICENSE NO. DPR-82 DOCKET NOS. 50-275 AND 50-323 P
Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
t Overleaf pages are also provided to maintain document completeness.,
REMOVE INSERT xii xii xvii xvii 3/4 9-17 3/4 9-17 3/4 9-18 3/4 9-18 3/4 9-19 3/4 9-19 i
3/4 9-20 3/4 9-21 3/4 9-22 8 3/4 9-3 8 3/4 9-3 5-5 5-5 5-6 5-6
)
_4 I. e '
1!fDil LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION E8HE 3/4.7 PLANT SYSTEMS (continued) 3/4.7.11 AREA TEMPERATURE MONITORING.............................
3/4 7-37 i
TABLE 3.7-5 AREA TEMPERATURE M0NITORING..........................
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
3/4.8.1 A.C. SOURCES 0perating...............................................
3/4 8-1 i
TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE.......................
3/4 8-8 TABLE 4.8-2a LOAD SEQUENCING TIMERS - ESF TIMERS.................
3/4 8-9 TABLE 4.8-20 LOAD SEQUENCING TIMERS - AUTO TRANSFER TIMERS.......
3/4 8-10 Shutdown................................................
3/4 8-11 3/4.8.2 ONSITE POWER DISTRIBUTION i
0perating...............................................
3/4 8-12 Shutdown................................................
3/4 8-14 j
3/4.8.3 D.C. SOURCES 0 p e r a t i ng...............................................
3/4 8-15 TABLE 4.8-3 BATTERY SURVEILLANCE REQUIREMENTS....................
3/4 8-17 i
Shutdown................................................
3/4 8-18 1
3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Motor-Operated Valves Thermal Overload Protection and Bypass Devices......................................
3/4 8-19 Containment Penetration Conductor Overcurrent Protective Devices......................................
'3/4 8-20 DIABLO CANYON - UNITS 1 & 2 xi Amendment Nos. 66 & 66 49i & 74, 79 & 78 1
I INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PJ_G1 3/4.9 REFUELING OPERATIONS f
3/4.9.1 BORON CONCENTRATION.......................................
3/4 9-1 3/4.9.2 INSTRUMENTATION...........................................
3/4 9-2 3/4.9.3 DECAY TIME................................................
3/4 9-3 l
3/4.9.4 CONTAINMENT PENETRATIONS..................................
3/4 9-4 3/4.9.5 COMMUNICATIONS............................................
3/4 9-5
(
3/4.9.6 MANIPULATOR CRANE.........................................
3/4 9-6 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING.....................
3/4 9-7 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Level..........................................
3/4 9-8 Low Water Leve1...........................................
3/4 9-9 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM..................
3/4 9-10 3/4.9.10 WATER LEVEL - REACTOR VESSEL F u el A s s embl i e s........................................... 3/4 9-11 Control Rods..............................................
3/4 9-11a 3/4.9.11 WATER LEVEL - SPENT FUEL P00L.............................
3/4 9-12 3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM.................
3/4 9-13 3/4.9.13 SPENT FUEL SHIPPING CASK M0VEMENT.........................
3/4 9-15 FIGURE 3.9-1 UNITS 1 AND 2 SPENT FUEL P0OL LAYOUT.................
3/4 9-16 3/4.9.14 SPENT FUEL ASSEMBLY STORAGE Spent Fuel Pool Region 2..................................
3/4 9-17 FIGURE 3.9-2 MINIMUM REQUIRED ASSEMBLY DISCHARGE BURNUP AS A FUNCTION OF INITIAL ENRICHMENT AND PELLET DIAMETER TO PERMIT STORAGE IN REGION 2...............
3/4 9-18 Spent Fuel Pool Boron Concentration.......................
3/4 9-19 Spent Fuel Pool Reg i on 1..................................
3/4 9-20 FIGURE 3.9-3 MINIMUM REQUIRED ASSEM3LY DISCHARGE BURNUP AS A FUNCTION OF INITIAL ENRICHMENT (N0 IFBA) TO PERMIT STORAGE IN REGION 1...........................
3/4 9-22 3/4.10 SPECIAL TEST EXCEPTIONS l
3/4.10.1 SHUTDOWN MARGIN...........................................
3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.....
3/4 10-2 3/4.10.3 PHYSICS TESTS.............................................
3/4 10-3 l
3/4.10.4 POSITION INDICATION SYSTEM - SHUTD0WN.....................
3/4 10-4 DIABLO CANYON - UNITS 1 & 2 xii Unit 1 - Amendment 39de,104 Unit 2 - Amendment 38 d +,103
-q A.
i INDEX BASES i
SECTION g
I 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION...................................
B 3/4 9-1, 3/4.9.2 INSTRUMENTATION.......................................
B 3/4 9-1 3/4.9.3 DECAY TIME............................................
B 3/4 9 j 3/4.9.4 CONTAINMENT PENETRATIONS..............................
B 3/4 9-1 3/4.9.5 COMMUNICATIONS........................................
B 3/4 9-1 i
-3/4.9.6 MANIPULATOR CRANE.....................................
B 3/4 9-1 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING.................
B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION.........
B 3/4 9-2 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM..............
B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and SPENT FUEL P00L.............................................
B 3/4 9-2 3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM.............
B 3/4 9-3 3/4.9.13 SPENT FUEL SHIPPING CASK N0VEMENT.....................
B 3/4 9-3 3/4.9.14 SPENT FUEL ASSEMBLY ST0 RAGE...........................
B 3/4 9-3 l
i 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.......................................
B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS................................................
B 3/4 10-1 3/4.10.3 PHYSICS TESTS.........................................
B 3/4 10-1 3/4.10.4 POSITION INDICATION SYSTEM - SHUTD0WN.................
B 3/4 10-2 i
i DIABLO CANYON - UNITS 1 & 2 xvii Unit 1 - Amendment No.104 Unit 2 - Amendment No.103
.. f *, y INDEX BASES SECTION PAGE 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.........................................
B 3/4 11-1 3/4. n. 2 GASEOUS EFFLUENTS........................................
B 3/4 11-1 P
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i DIABLO CANYON - UNITS 1 & 2 xviii Amendment Nos.67 and 66
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i REFUELING OPERATIONS j
3/4.9.14 SPENT FUEL ASSEMBLY STORAGE j
SPENT FUEL POOL REGION 2 l
i LIMITING CONDITION FOR OPERATION j
3.9.14.1 The combination of initial enrichment, pellet diameter, and l
cumulative burnup for spent fuel assemblies stored in Region 2 shall be within the acceptable area of Figure 3.9-2.
APPLICABILITY: Whenever fuel assemblies are in the spent fuel pool.
ACTION:
i a.
With the requirements of the above specification not satisfied, suspend all movement of fuel assemblies and crane operations '(with loads in the fuel storage area) except to perform the following:
move the non-complying fuel assemblies to Region 1 is t.ccord:nce with TS 3.9.14.3.
Until the requirements of the above specifi-cation are satisfied, boron concentration of the spent fuel pool shall be verified to be greater than or equal to 2000 ppm at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not I
applicable.
SURVEILLANCE REQUIREMENTS 4.9.14.1 The cumulative burnup of each spent fuel assembly stored in Region 2 shall be determined by analysis of its burnup history, prior to storage in Region 2.
A complete record of initial _ enrichment, fuel pellet diameter,.and the cumulative burnup analysis shall be maintained for the time period that the spent fuel assembly remains in Region 2 of the spent fuel pool.
DIABLO CANYON - UNITS I & 2 3/4 9-17 Unit 1 - Amendment 8,104 Unit 2 - Amendment 6,103
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,I 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 initial Enrichment Wt% U-235 FIGURE 3.9-2 MINIMUM REQUIRED ASSEMBLY DISCHARGE BURNUP AS A FUNCITON OF INITIAL ENRICHMENT AND PELLET DIAMETER TO PERMIT STORAGE IN REGION 2 DIABLO CANYON - UNITS 1 & 2 3/4 9-18 Unit 1 - Amendment 8,104 Unit 2 - Amendment 6,103
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REFUELING OPERATIONS SPENT FUEL ASSEMBLY STORAGE SPENT FUEL POOL BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.14.2 The boron concentration of the spent fuel pool shall be greater than
]
or equal to 2000 ppm.
j APPLICABILITY: Whenever fuel assemblies are in the spent fuel pool.
ACTION:
a.
With the requirements of the above specification not satisfied, immediately suspend all movement of fuel assemblies in the spent fuel pool and initiate corrective actions to restore the boron concentration.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not appl icable.
SVRVEILLANCE RE0VIREMENTS 4.9.14.2 The boron. concentration of the spent fuel pool shall be determined by chemical analysis at least once per 31 days.
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i DIABLO CANYON - UNITS 1 & 2 3/4 9-19 Unit 1 - Amendment 8,104 Unit 2 - Amendment 6,103 4
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E y REFUELING OPERATIONS SPENT FUEL ASSEMBLY STORAGE SPENT FUEL POOL REGION 1 LIMITING CONDITION FOR OPERATION 3.9.14.3 The following conditions shall be met for storage of fuel assemblies in Region 1 of the spent fuel pool:
a.
The initial enrichment is 4.5 weight percent U-235 or less; or b.
The initial enrichment is from 4.5 up to a maximum of 5.0 weight percent U-235, and any of the following conditions are met:
1)
The combination of initial enrichment and cumulative burnup of the assemblies is within the acceptable area of Figure 3.9-3; or 2)
The assemblies initially contained a minimum of a nominal 36 mg/in. per assembly of the isotope B-10 integrated in the fuel rods; or 3)
The assemblies are put in a checkerboard pattern with any of the following:
a) water cells, or b) assemblies that initially contained a minimum of a nominal 72 mg/in. per assembly of the isotope B-10 integrated in the fuel rods, or c) partially irradiated fuel of at least 8000 MWD /MTU cumulative burnup; or 4)
The assemblies are put into a pattern with alternate rows of fuel assemblies and water cells.
APPLICABILITY: Whenever fuel assemblies are in Region 1 of the spent fuel pool.
ACTION:
a.
With the requirements of the above specification not satisfied, suspend all movement of fuel assemblies and crane operations (with loads in the fuel storage area) except to perform the following:
move the non-complying fuel assemblies into a pattern that complies with requirements of the above specification.
Until the requirements of the above specification are satisfied, boron concentration of the spent fuel pool shall be verified to be greater than or equal to 2000 ppm at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
DIABLO CANYON - UNITS 1 AND 2 3/4 9-20 Unit 1 - Amendment No.104 Unit 2 - Amendment No.103
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REFUELING OPERATIONS SPENT FUEL ASSEMBLY STORAGE SPENT FUEL POOL REGION 1 SURVEILLANCE REQUIREMENTS
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4.9.14.3 The cumulative burnup of each fuel assembly stored in Region 1 shall l
be determined by analysis of its burnup history, prior to storage in Region 1.
A complete record of initial enrichment, initial integral boron content, and i
the cumulative burnup analysis shall be maintained for the time period that the fuel assembly remains in Region 1 of the spent fuel pool.
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DIABLO CANYON - UNITS 1 AND 2 3/4 9-21 Unit 1 - Amendment No.104 Unit 2 - Amendment No.103
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4.5 4.6 4.7 4.8 4.9 5.0 INITIAL ENRIOf1ENT, WTs U-235 i.
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MINIMUM REQUIRED ASSEMBLY DISCHARGE BURNUP I.
AS A FUNCTION OF INITIAL ENRICHMENT (N0 IFBA) TO PERMIT STORAGE IN REGION 1 i
DIABLO CANYON - UNITS 1 AND 2 3/4 9-22 Unit I - Amendment No.104 Unit 2 - Amendment No.103 n
[J REFUELING OPERATIONS BASES 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment ventilation penetrations will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.
3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and SPENT FUEL POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the safety analysis.
The minimum water level for movement of fuel assemblies (23 feet above the vessel flange) assures that sufficient water depth is maintained above fuel elements being moved to or from the vessel. With the upper internals in place, fuel assemblies and control rods cannot be removed from the vessel.
Operations involving the unlatching of control rods with the vessel upper internals in place may proceed with less than 23 feet of water above the vessel flange provided that 23 feet of water (12 feet above the flange) is maintained above all irradiated fuel assemblies within the reactor vessel.
E4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM The limitations on the Fuel Handling Building Ventilation System ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.
The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses.
Transfer of system operation into the iodine removal mode (exhaust through HEPA filters and charcoal adsorbers) is initiated automatically by either the new fuel storage or spent fuel pool area radiation monitors required by Specification 3.3.3.
Following installation of the fuel Handling Building Ventilation exhaust radiation monitors, the automatic function of the fuel storage area monitors will be removed. Transfer of system operation into the iodine removal mode will be by either of the two Fuel Handling Building Ventilation exhaust radiation monitors required by Specification 3.3.3.
ANSI
)
N510-1980 will be used as a procedural guide for surveillance testing.
i 3/4.9.13 SPENT FUEL SHIPPING CASK MOVEMENT The restriction on spent fuel shipping cask movement ensures that no fuel assemblies will be ruptured in the event of a spent fuel shipping cask accident. The dose consequences of this accident are within the dose guideline values of 10 CFR Part 100.
3/4.9.14 SPENT FUEL ASSEMBLY STORAGE The restrictions placed on spent fuel assemblies stored in the spent fuel p
pool ensure that keff will not be greater than 0.95 under normal conditions, as discussed in TS 5.6.1.a.
The requirement for 2000 ppm boron concentration ensures that k-eff will not be greater than 0.95 under accident conditions.
The spent fuel storage has been designed and analyzed for a maximum enrichment of 5.0 weight percent U-235.
I DIABLO CANYON - UNITS 1 & 2 B 3/4 9-3 Unit 1 - Amendment 4 &-70,104 Unit 2 - Amendment 4b69,103
'S.
4 DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 Containment is designed and shall be maintained for a maximum internal pressure of 47 psig and a temperature of 271*F, coincident with a Double Design Earthquake.
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor shall contain 193 fuel assemblies.
Each assembly shall consist of a matrix of Zircaloy-4 or ZIRLO clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide as fuel material.
Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used.
Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or analysis to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core locations.
CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies. The full length control rod assemblies shall contain a nominal 142 inches of absorber material.
The nominal values of absorber material shall be 80% silver,15% indium, and 5% cadmium. All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:
In accordance with the Code requirements specified in Section 5.2 of a.
the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a temperature of 650*F, except for the pressurizer which is 680*F.
MLVE 5.4.2 The total water and steam volume of the Reactor Coolant System is 12,811 1 100 cubic feet at a nominal T'o7 Unit 2.of 576*F for Unit I and 12,903 i 100 cubic feet at a nominal T of 577'F f m
DIABLO CANYON - UNITS 1 & 2 5-5 Unit 1 - Amendment No. H,104 Unit 2 - Amendment No. M,103
tl y, DESIGN FEATURES 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE l
CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:
l equivalent to less than or equal to 0.95 when flooded with A k,,, ted water, which includes a conservative allowance for a.
unbora l
uncertainties as described in Section 9.1 of the FSAR.
b.
A nominal 10.93 inch center-to-center distance between fuel l
assemblies placed in the storage racks.
i c.
Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent.
I DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 133.
CAPACITY i
5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1324 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT l
5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
t I
l l
i DIABLO CANYON - UNITS 1 & 2 5-6 Unit 1 - Amendment 8,104 Unit 2 - Amendment 6,103
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