Text

Amend 51 to License NPF-43,revising Tech Spec 3/4.7.1.5 for UHS to Better Reflect as-built Conditions of Plant & Design Basis
	ML20006E522
Person / Time
Site:	Fermi
Issue date:	02/20/1990
From:	Thoma J; Office of Nuclear Reactor Regulation
To:	;
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ML20006E523	List: ML20006E522; ML20006E526;
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	NUDOCS 9002230472
	Download: ML20006E522 (11)
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NUCLEAR REGULATORY COMMISSION g-

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i DETROIT EDISON COMPANY WOLVERINE POWER SUPPLY COOPERATIVE, INCORPORATED DOCKET NO. 50-341 FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 51 License No. NPF-43 1.

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

A.

The application for amendment by the Detroit Edison Company (the licensee) dated September 30, 1988 as supplemented December 15, 1989, 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 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 (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; L

D.

The issuance of this amendment will not be inimical to the common

- defense and security or to the 'nealth 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 Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operatiag License No. NPF-43 is hereby amended to read as follows:

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 51, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

DECO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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This license amendment is effective as of the date of its issuance with 4

full implementation within 90 days of the date of issuance.

- FOR THE NUCLEAR REGULATORY COMMISSION h

J hn 0. Thoma, Acting Director Project Directorate III-1 l

Division of Reactor Projects - III, IV, V & Special Projects Office of Nuclear Reactor Regulation j

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Attachment:

L Changes to the Technical l-Specifications l

=Date of Issuance: February 20, 1990 lL l

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c ATTACHMENT TO LICENSE AMENDMENT NO. 51 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by Amendment number and

- contain a vertical line indicating the area of change.

The corresponding L

overleaf pages are also provided to maintain document completeness.

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REMOVE INSERT xv xv 3/4 7-5*

3/4 7-5*

3/4 7-6 3/4 7-6 3/4 7-6a 3/4 7-7 3/4 7-7 3/4 7-8*

3/4 7-8*

i B3/4 7-1 B3/4 7-1 B3/4 7-la B3/4 7-2*

B3/4 7-2*

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" Overleaf pages provided to maintain document completeness.

No changes contained on these pages, i

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INDEX j

,1 BASES SECTION.

PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS...........................

B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM........

B 3/4 7-1 3/4.7.3 SHORE BARRIER PROTECTION........................

B 3/4 7-1 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM...........

B 3/4 7-la l

3/4.7.5 SNUBBERS........................................

B 3/4 7-2 3/4.7.6 SEALED SOURCE CONTAMINATION.....................

B 3/4 7-4 3/4.7.7 FIRE SUPPRESSION SYSTEMS........................

B 3/4 7-4 3/4.7.8~

FIRE RATED ASSEMBLIES...........................

B 3/4 7-4 3/4.7.9 MAIN TURBINE BYPASS SYSTEM AND MOISTURE SEPARATOR REHEATER..............................

B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, and ONSITE POWER DISTRIBUTION SYSTEMS............................

B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.........

B 3/4 8-3 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH.............................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION.................................

B 3/4 9-1 3/4.9.3 CONTROL R0D P0SITION............................

B 3/4 9-1 3/4.9.4 DECAY TIME......................................

B 3/4 9-1 3/4.9.5 COMMUNICATIONS..................................

B 3/4 9-1 3/4.9.6 REFUELING PLATF0PM..............................

B 3/4 9-2 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L............

B 3/4 9-2 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAGE P00L.......

B 3/4 9-2 3/4.9.10 CONTROL R00 REM 0 VAL.............................

B 3/4 9-2 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...

B 3/4 9-2 FERMI - UNIT 2 xv Amendment No. 51

PLANT SYSTEMS DIESEL GENERATOR COOLING WATER SYSTEM l

LIMITING CONDITION FOR OPERATION I

3.7.1.4 The diesel generator cooling water subsystem associated with each diesel generator shall be OPERABLE with each subsystem comprised of:

a.

One OPERABLE diesel generator cooling water pump, and b.

An OPERABLE flow path capable of taking suction from the associated j

ultimate heat sink and transferring cooling water through the asso-ciated diesel generator heat exchanger, 1

APPLICABILITY: When the diesel generator is required to be OPERABLE.

ACTION:

With one or more diesel generator cooling water subsystems inoperable, declare the associated diesel generator inoperable and take the ACTION required by Specification.3.8.1.1 or 3.8.1.2, as applicable.

SURVEILLANCE REQUIREMENTS 4.7.1.4 Each of the above required diesel generator cooling water subsystems shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

At least once per 18 months by verifying that each pump starts automatically upon receipt of a start signal for the associated diesel generator.

. FERMI - UNIT 2 3/4 7-5

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PLAllT SYSTEMS ULTIMATE HEAT SINK LIMITING CONDITION FOR_ OPERATION 3.7.1.5 The Ultimate Heat Sink, comprised of two one-half capacity residual heat removal (RHR) reservoirs with the capability of being cross-connected, shall be OPERABLE with:

a.

A sciniinum water voluine of 2,990,000 gallons in each reservoir (equivalent to an indicated water level of 25 feet or 580 feet elevation),

b.

A maxiinuin average water temperature of less than or equal to 80*F for each reservoir.

c.

At least one OPERABLE cooling tower with two cooling fans for each reservoir.

j d.

A minimum con.bined water volume in the two reservoirs of 5,980,000

gallons, e.

A traximum combined average water temperature for the two reservoirs of less than or equal to 80'F.

f.

A nininiun. average water temperature of greater than or equal to 41*F for each reservoir.

g.

Two reservoir cross-connect lines, each with two OPERABLE motor operated cross-connect valves.

APPLICABILITY: OPERATIONAL CONDIT10hs 1, 2, 3, 4, 5 and *.

L ACTION:

a.

With cr.e or raore of the requirenents of Specification 3.7.1.5.a. b, and c not satisfied declare the affected reservoir (s) inoperable and take the ACTION required by d. or e. below, t.

With the coir.bined water volume requirement of Specification 3.7.1.5.d cr the combined average water teopereture of Specification 3.7.1.5.e not satisfied declare both reservoirs inoperable and take the ACTION i

required by e. below, c.

With one or more reservoir cross. connect valves inoperable, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months open and de-energize both valves in at least one cross-c(nnect line and verify that these valves remain open and l-de-energized at least once per 7 days. The provisions of Specification 3.0.4 are not applicable. Otherwise, declare both reservoirs inoperable and take the ACTION of e. below.

When handling irradiated fuel in the secondary containnent.

FERMI - UNIT 2 2/4 7-6 Aniendc'ent No. 51

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LIMITING'CONDITIONFOROPERATION(Cont'ngtQ-I

' ACTION:; (Continued) d.

With one reservoir inoperable declare the associated RHRSW system

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subsystem, EESW' system. subsystem,:and diesel generator cooling water subsystem inoperable and take the ACTJON required by Specifications-3.7.1.1, 3.7.1.3~and 3.7.1.4.

e.

~With both reservoirs inoperable:

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In OPERATIONAL CONDITIONS 1, 2 or 3,: be in at least HOT -

SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .-

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'In OPERATIONAL CONDITIONS 4 or 5. declare the RHRSW system,

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ttc EESW system and the diesel generator cooling water systems m,

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inoperable and take the ACTION required by Specifications

'3.7.1.1, 3.7.1.3 and 3.7.1.4..

3.

In OPERATIONAL CONDITION *, declare the.diese'l generator l

cooling water systems inoperable and take the ACTION required by Specification 3.7.1.4.

The provisions of Specification j

3.0.3 are not applicable.

f.

With the requirements of Specification 3.7.1.5.f for one or both reservoirs not satisfied. perform a visual inspection of the-reservoir (s) st least once ner 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to verify that no ice has formed.

If ice is observed', demonstrate the OPERABILITY of each safety related pump in the reservoir (s) by running each safety.

relatt d pump at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . The provisions of Specification 3.0.4 are not applicable.

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FERNI - UNIT 2 3/4 7-6a Amendment No. 51

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PLANT SYSTEMS' p

SURVEILLANCE REQUIREMENTS

. w 4.7.1.5 The Ultimate Heat Sink shall be determined OPERABLE at least once per

a.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the individual and combined average water temperature and water volume to be within their limits.

,b.

31 days-by:'

1.

Starting each cooling tower fan from the control room and operating the fan on slow speed and on fast speed,** each'for-at least 15 minutes.

2.

For each electrical division of cross-connect valves,. verify at least one valve in the division is open, c.

92 days by cycling each reservoir cross-connect valve through at least one cycle of full travel.

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When handling irradiated fuel in the secondary containment,

- Fast speed need not be tested during icing periods.

FERMI - UNIT 2 3/4 7-7 Amendment No. 51

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' PLANT SYSTEMS

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3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM t

LIMITING CONDITION FOR OPERATION 3.7.2 ' The control: room emergency filtration system shall be OPERABLE with the-c,~

. system composed of:

a.

The passive components of the emergency makeup air filter train.

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The passive components of the emergency recirculation air filter train.

c.-

Two emergency makeup inlet air heaters.

d.

.Two recirculation fans.

e.

Two return and supply fans.

3 f.

A flowpath capable of:-

1.

Recirculating control room air.

' 2.

Supplying emergency makeup air to the control room.**

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3, 4, 5, and

ACTION:

a.

With the control room air temperature greater than 95'F but less than 105'F, restore the control room air temperature to less than or equal to 95'F within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or go to a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months operating shift. With the control room air temperature greater than or equel to 105'F, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

In OPERATIONAL CONDITION 1, 2, or 3:

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With one of the above required filter trains or flow paths in-operable, be in at leact HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

2.

.With a recirculation, return or supply fan; emergency makeup inlet air heater; damper; or other required redundant component inoperable, restore the inoperable component to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , c.

In OPERATIONAL CONDITION 4, 5 or *:

1.

With a recirculation, return or supply fan; emergency makeup in-let air heater; damper; or other required redundant component inoperable, restore the inoperable component to OPERABLE status within 7 days or initiate and maintain operation of the system in the recirculation mode of operation.

2.

With the control room emergency filtration system inoperable, suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.

d.

The provisions of Specification 3.0.3 are not applicable in Operational Condition *.

When irradiated fuel is being handled in the secondary containment.

- Not applicable in the chlorine mode of operation.

FERMI - UNIT 2 3/4 7-8

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'3/4.7 ' PLANT SYSTEMS

' BASES l

3/4.7.1 SERVICE WATER SYSTEMS The OPERABILI'Y of the service water systems ensures that sufficient cooling capacity is available for continued operation of safety-related.

equipment during normal and accident conditions. The redundant cooling capacity of these systems, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits.

.The Ultimate Heat Sink consist of two 50% capacity Residual Heat Removal (RHR) reservoirs which must be capable ~of being cross-connected.

Surveillance Requirement 4 7.1.5.b.2 assures that the ability to cross-connect the two 1

reservoirs is not compromised in the event of a failure of a single electrical power source.

3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM The OPERABILITY of the control room emergency filtration system ensures that (1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by~this system and (2) the control room will remain habitable for operations personnel during and following all design basis accident conditions.

Continuous operation of the system with heaters OPERABLE for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months during each 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying

. the control room to 5 rem or less whole body, or its equivalent.

This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A, 10 CFR Part 50.

3/4.7.3 SHORE BARRIER PROTECTION The purpose of the shore barrier is to protect the site backfill from wave erosion.

Category 1 structures are designed to withstand the impact of waves up to 5.4 feet.

So long as the backfill is in place, waves greater than 5.4 feet cannot impact Category 1 structures because of the lack of sufficient depth of water to sustain such waves.

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The shore barrier can sustain a high degree of damage and still perform L

its function, protecting the site backfill from erosion.

Thus the operability l

condition for operation of the shore barrier has been written to ensure that y

severe damage to the structure will not go undetected for a substantial period of time and provide for prompt NRC notification and corrective action.

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' FERMI - UNIT 2 B 3/4 7-1 Amendment No. 51 l

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PLANT SYSTEMS BASES 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM i

The reactor' core isolation cooling (RCIC) system is provided to assure-adequate core cooling in the event of reactor isolation from_its-primary heat sink and the loss of feedwater flow to the reactor vessel. without requiring actuation of any of the Emergency Core Cooling System equipment.

The RCIC-system is conservatively required to be OPERABLE whenever reactor pressure exceeds'150 psig.

This pressure is substantially below that~for which the low-pressure core cooling systems can provide adequate core cooling for events 1

requiring the RCIC system.

The.RCIC system specifications are applicable during OPERATIONAL-I CONDITIONS 1, 2, and 3 when reactor vessel pressure exceeds 150 psig because RCIC is the primary non-ECCS source of emergency core cooling when the reactor is pressurized.

FERMI - UNIT 2 B 3/4 7-la Amendment No. 51 l

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ML20006E522

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