Text

Amends 39 & 38 to Licenses DPR-80 & DPR-82,respectively, Revising Combined Tech Specs to Require That at Least 23 Ft of Water Maintained Above Top of Irradiated Fuel Assemblies within Vessel During Movement of Rod Cluster
	ML20244C846
Person / Time
Site:	Diablo Canyon
Issue date:	06/07/1989
From:	Knighton G; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20244C848	List: ML20244C846; ML20244C855;
References
	NUDOCS 8906150170
	Download: ML20244C846 (10)
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UNITED STATES.

f8 NUCLEAR REGULATORY COMMISSION o

p WASHINGTON. D. C. 20555 PACIFIC GAS ~AND ELECTRIC COMPANY' DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-275 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.- 39 License No.-DPR-80 1.

The Nuclear Regulatory Commission (the Commission) has found that:

l A.

The application for amendment by Pacific Gas & Electric Company -

(the licensee), dated March 29, 1989 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 regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized l

by this amendment can be conducted without endangering.the health l

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 Commission's regulations and all applicable requirements have been satisfied.

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P ADOCM 05000275 PNu l

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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 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. 39, 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 licer.se conditions.

3.

This license amendment becomes effective at the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMIS; ION M

M 7

George W,

'nighton,41 rector Project irectorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 7, 1989

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UNITED STATES

- 8 NUCLEAR REGULATORY COMMISSION-o y,

,E WASHWGTON, D. C. 20655

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PACIFIC GAS AND ELECTRIC COMPANY D_IABLO CANYON NUCLEAR POWER PLANT, UNIT 2 i

DOCKET NO. 50-323 j

i AMENDMENT TO FACILITY OPERATING LICENSE' Amendment No. 38 License No. DPR-82 1.

The Nuclear Regulatory Comission' (the Commission) has found that:

l A.

The application for amendment by Pacific Gas & Electric Company j

(thelicensee),datedMarch 29, 1989 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 ap)11 cation, the provisions of the Act, and the regulations of tie Commissien; 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 i

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 l

of the Commission's regulations and all applicable requirements have I

been satisfied.

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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:

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment-No. 38, 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.

FOR THE NUCLEAR REGULATORY COMMISSION p fff/

George W,/ Knighton, rector Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 7, 1989

l ATTACHMENT TO LICENSE AMENDMENT NOS. 39 AND 38 FACILITY OPERATING LICENSE NOS. DPR-80 and DPR-82 DOCKET NOS. 50-275 AND 50-323 i

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 areas of change. Overleaf pages are also included, as appropriate.

Remove Page Insert Page xii xii 3/4 9-11 3/4 9-11 3/4 9-11a B 3/4 9-2 B 3/4 9-2 B 3/4 9-3 B 3/4 9-3 l

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS-SECTION PAGE 3/4.7 PLANT SYSTEMS (continued) l

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3/4.7.10 FIRE BARRIER PENETRATIONS...............................

-3/4 7-36 i

i 3/4.7.11 AREA TEMPERATURE MONITORING.............................

3/4.7-37

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i TABLE'3.7-5 AREA TEMPERATURE MONITORING..........................

3/4 7-38 I

1 4

3/4.7.12 ULTIMATE HEAT SINK......................................

3/4 7-39

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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

)

TABLE 4.8-2a LOAD SEQUENCING TIMERS - ESF TIMERS.................

3/4.8-9 i

TABLE 4.8-2b LOAD SEQUENCING TIMERS - AUTO TRANSFER TIMERS.......

3/4 8-10 l

Shutdown................................................

3/4 8-11 3/4.8.2 ONSITE POWER DISTRIBUTION Operating...............................................

3/4 8-12 Shutdown.................................................

3/4 8-14

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3/4.8.3 D.C. SOURCES 0perating...............................................-

3/4 8-15 TABLE 4.8-3 BATTERY SURVEILLANCE REQUIREMENTS....................

3/4 8~17 Shutdown................................................

3/4 8-18 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Motor-Operated Valves Thermal Overload Protection and Bypass Devices......................................

3/4 8-19 TABLE 3.8-1 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND BYPASS DEVICES......................................

3/4 8-20 Containment Penetration Conductor Overcurrent Protective Devices......................................

3/4 8-23 DIABLO CANYON - UNITS 1 & 2 x1

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS.

SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.....................................

3/4 S-1 3/4.9.2 INSTRUMENTATION.........................................

3/4 9-2 3/4.9.3 DECAY TIME..............................................

3/4 9-3 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 L ow Wa te r Le v e 1......................................... 3/4 9-9 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM................

3/4 9-10 3/4.9.10 WATER LEVEL - REACTOR VESSEL............................

3/4 9-11 Fuel Assemblies.........................................

3/4 9-11 Control Rods....................................'........

3/4 9-11a l

3/4.9.11 WATER LEVEL - SPENT FUEL P00L...........................

3/4 9-12 1

i 3/4.9.12 FUEL HANDLING BUILDING VENT 3 LATION SYSTEM...............

3/4 9-13 3/4.9.13 SPENT FUEL SHIPPING CASK M0VEMENT.......................

3/4 9-15 3/4.10 SPECIAL TEST EXCEPTIONS 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 3/4.10.4 POSITION INDICATION SYSTEM - SHUTDOWN...................

3/4 10-4 DIABLO CANYON - UNITS 1 & 2 xii Amendment Nos.39 and 38

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REFUELING OPERATIONS l

3/4.9.10 - WATER LEVEL - REACTOR VESSEL l

FUEL ASSEMBLIES LIMITING CONDITION FOR OPERATION i

3.9.10.1 At least 23 feet of water shall be maintained over the top of the reactor pressure vessel flange.

i APPLICABILITY:

During movement of fuel assemblies within containment when the I

reactor pressure vessel pressure contains irradiated fuel assemblies.

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ACTION:

With the requirements of the above specification not satisfied, suspend all operations involving movement of fuel assemblies within the reactor pressure i

vessel.

The provisions of Specification 3.0.3 are not applicable.

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SURVEILLANCE REQUIREMENTS 4.9.10.1 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to the start of and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter during movement of irradiated fuel assemblies within containment.

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l DIABLO CANYON - UNITS 1 & 2 3/4 9-11 Amendment Nos.39 and 38 L _ _-_ _

REFUELING OPERATIONS WATER LEVEL - REACTOR VESSEL CONTROL RODS LIMITING CONDITION FOR OPERATION 3.9.10.2 At least 23 feet of water shall be maintained over the top of the irradiated fuel assemblies within the reactor pressure vessel.

APPLICABILITY; During movement of control rods within the reactor pressure vessel whiTF in MODE 6.

ACTION:

With the requirements of the above specification not satisfied, suspend all operations involving movement of control rods within the pressure vessel.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.10.2 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to the start of and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter during movement of control rods within the reactor pressure vessel.

DIABLO CANYON - UilITS 1 & 2 3/4 9-11a Amendment Nos.39 and 38

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REFUELING OPERATIONS' 3/4.'9.11' WATER LEVEL - SPENT FUEL POOL LIMITING CONDITION FOR OPERATION-3.9.11 At least 23 feet of water shall'be maintained over the top of irradiated fuel assemblies seated in the storage racks.-

l APPLICABILITY: Whenever irradiated fuel assemblies are..in the spent' fuel pool.

1 ACTION:

l a.

With the requirements of the above specification n.ot. satisfied, suspend all movement of fuel assemblies and crane operations with-loads in the fuel storage areas and restore the water level to within its limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b.

The provisions of Specifications'3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.11 The water level in the spent fuel pool shall be determined to be at-least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in the spent fuel pool.

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DIABLO CANYON - UNITS 1 & 2 3/4 9-12

l 3/4.9" REFUELING OPERAT10NS' BASES

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u 3/4.9.11 BORON CONCENTRATION:

' lThe. limitations on' reactivity conditions-.during REFUELING' ensure that:-

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.(1) the' reactor will remain subcritical during CORE ALTERATIONS,.and'(2) ai-

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" uniform boron concentration'is' maintained for reactivity control in the water:

volume.having. direct access'.to'the? reactor vessel. These limitations.'are con-

.sisten.t.with the initial conditions assumed for the boron dilutioniincident/

'in-the safety analysis..,

1 3/4.9.~2-INSTRUMENTATION'

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.The OPERABILITY of the Source Ran Neutron Flux Monitors ensure's that-l redundant monitoring capability is'ava able to' detect changes in:the reactivity. condition of the core.

3/4.9.3 DECAY TIME The minimum requirement for reactor suberiticality prior to movement off i

irradiated fuel assemblies in the reactor' vessel ensures that sufficient time has elapsed to allow the_ radioactive decay of the short lived fission products.

'This decay time is consistent with the assumptions used in"the safety: analyses.

3/4.9.4 CONTAINMENT P' PENETRATIONS

k The requirements on containment penetration. closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted i

from leakage to the environment.' The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potentia 1'while in the REFUELING MODE.

3/4.9.5 COMMUNICATIONS l.

The requirement for communications' capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity conditions during CORE ALTERATIONS.

1 3/4.9.6 MANIPULATOR CRANE j

'l The OPERABILITY requirements for the manipulator cranes ensure that:

j (1) manipulator cranes will be used for movement of control rods and fuel

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assemblies, '(2) each crane has sufficient load capacity to lift a control rod or fuel assembly, and (3) the core internals and reactor vessel are protected 3

from excessive lifting force'in the event they are inadvertently engaged

.i during lifting operations.

i DIABLO CANYON - UNITS 1 & 2 B 3/4 9-1 1

REFUELING OPERATIONS BASES 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel and control assembly and associated handling tool, except the movable fuel hand pool ensu. ling building walls, over other fuel assemblies in the spent fuel res that in the event this load is dropped:

(1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of the fuel in the storage racks will not result in a critical array.

This assumption is consistent with the activity release assumed in the safety analyses.

The movable fuel handling building walls travel on rollers over the spent fuel pool and have been designed to remain in place during postulated seismic events.

3/4.9.8 RESIDUAL ~ HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal'(RHR) train be'in operation ensures that:

(1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140 F as required during the REFUELING MODE and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.

The requirement to maintain a 3000 gpm flowrate with the reactor subcritical less than 57 hours6.597222e-4 days 0.0158 hours 9.424603e-5 weeks 2.16885e-5 months ensures that there is adequate decay heat removal capability. After the reactor is subcritical for 57 hours6.597222e-4 days 0.0158 hours 9.424603e-5 weeks 2.16885e-5 months , the flowrate can be reduced to 1300 gpm and meet the decay heat removal requirements.

The reduced flowrate provides additional margin to vortexing at the RHR pump suction while in partial drain operation.

The requirement to have two RHR trains OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR train will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and 23 feet of water above the reactor vessel flange, a large heat sink is available for core cooling.

Thus, in the event of a failure of the operating RHR train, adequate time is provided to initiate emergency procedures to cool the core.

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.

i 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 DIABLO CANYON - UNITS 1 & 2 B 3/4 9-2 Amendment Nos.39 and 38

REFUELING OPERATIONS BASES WATER LEVEL - REACTOR VESSEL and SPENT FUEL POOL (Continued) 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..

3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM The limitations on the Fuel Handling Building Ventilation System enstie 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 1'

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.

ANSI N510-1980 will be used as a procedural guide for surveillance testing.

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 Region 2 of the spent fuel pool and the requirement for 2000 ppm boron concentration ensure that keff will not be greater than 0.95.

The spent fuel storage has been designed and analyzed for a maximum enrichment of 4.5 weight percent U-235.

DIABLO CANYON - UNITS 1 & 2 B 3/4 9-3 Amendment Nos.39 and 38 l

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ML20244C846

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