Text

Amend 224 to License NPF-03,revises TS Section 1.0, Definitions, to Clarify Meaning of Core Alteration, Relocates TS Section 3/4.9.5 & Associated Bases to Technical Requirements Manual
	ML20236K423
Person / Time
Site:	Davis Besse
Issue date:	06/30/1998
From:	Hansen A; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20236K426	List: ML20236K423; ML20236K432;
References
	NUDOCS 9807090313
	Download: ML20236K423 (10)
	v • d • e

_ - - _ - _ _ _ ___ - _ ___ _ ___-_ -_________

- aeoug g,

t UNITED STATES i

i l

u 8

NUCLEAR REGULATORY COMMISSION I

f

(

WASHINGTON D.C. 30666 4 001

\\...../

l TOLEDO EDIS0N COMPANY CENTERIOR SERVICE COMPANY 8E THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. l AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No.224 License No. NPF-3 1.

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

A.

The application for amendment by the Toledo Edison Company, Centerior Service Company, and The Cleveland Electric Illuminating Company (the licensees) dated December 23, 1997, as supplemented by letter dated June 11, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

l 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; 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 to approve the relocation of certain Technical Specification requirements to licensee-controlled documents, as described in the licensees.' application dated December 23, 1997, as supplemented by letter dated June 11, 1998, and evaluated in the staff's safety evaluation dated June

, 1998. This license is also hereby 9807090313 900630 DR ADOCK O 3j6

(. 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. NPF-3 is hereby amended to read as follows:

(2)

Te_chnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 224, are hereby incorporated in the license.

The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications, i

l 3.

This license amendment is effective as of its date of issuance and shall L

be implemented not later than 120 days after issuance.

Implementation shall include the relocation of Technical Specification requirements to the appropriate licensee-controlled documents as identified in the licensees' submittal dated December 23, 1997, as supplemented by letter dated June 11, 1998, and reviewed in the staff's safety evaluation dated June 30, 1998.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION N

Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications l

Date of ' issuance: June 30, 1998 l

l l

l r

4 1

-_ -. ~ -__ _ -_- - -_-_-___..____.__ - _ - - - _ _- -.____ _ __ _ _ - - -

~ _ _

l ATTACHMENT TO LICENSE AMENQMENT NO 224 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 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 area of change.

Remove Insert TS Index VIII TS Index VIII TS Index XII TS Index XII TS 1-3 TS 1-3 TS 3/4 0-1 TS 3/4 0-1 TS 3/4 9-5 TS 3/4 9-5 TS B 3/4 0-lb TS B 3/4 0-lb TS B 3/4 9-la TS B 3/4 9-la l

l l

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION PME l

3/4.9 REFUELING OPERATIONS

{

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 3/4.9.4 CONTAINMENT PENETRATIONS................

3/4 9-4 3/4.9.5 DELETED.........................

3/4 9-5 l

3/4.9.6 FUEL HANDLING BRIDGC OPERABILITY.............

3/4 9-6 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING 3/4 9-7 3/4.9.8 DECAY HEAT REMOVAL AND COOLANT CIRCULATION All Water Level s.....................

3/4 9-8 Low Water Level s.....................

3/4 9-8a 3/4.9.9 DELETED

. 3/4 9-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL................ 3/4 9-10 3/4.9.11 STORAGE P0OL WATER LEVEL.................

3/4 9-11 3/4.9.12 STORAGE P00L VENTILATION.................

3/4 9-12 3/4.9.13 SPENT FUEL P00L FUEL ASSEMBLY STORAGE..........

3/4 9-13 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS.................

3/4 10-1 3/4.10.2 PHYSICS TESTS,.....................

3/4 10-2 l

3/4.10.3 REACTOR COOLANT LOOPS..................

3/4 10-3 l

3/4.10.4 SHUTDOWN. MARGIN.....................

3/4 10-4 l

DAVIS-BESSE, UNIT 1 VIII Amendment No. 33,130,185, 224 l

l

INDEX t

BASES SECTION EAGE 3/4,7 PLANT SYSTEMS 3/4.7.1 TUR$lNE CYCLE...................... B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..... B 3/4 7-4 3/4.7.3 COMPONENT COOLING WATER SYSTEM.............. B 3/4 7-4 3/4.7.4 SERVICE WATER SYSTEM................... B 3/4 7-4 1

l 3/4.7.5 ULTIMATE HEAT SINK.................... B 3/4 7-4 l

3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM........ B 3/4 7-4 3/4.7.7 SNUBBERS......................... B 3/4 7-5 3/4.7.8 SEALED SOURCE CONTAMINATION............... B 3/4 7-6 3/4.7.9 Deleted l

3/4.7.10 Deleted 3/4.8 ELECTRICAL POWER SYSTEMS.................... B 3/4 8-1 l

.3/4.9 REFUELING 0PERATIONS 3/4.9.1 BORON CONCENTRATION................... B 3/4 9-1 3f4.9.2 INSTRUMENTATION..................... B 3/4 9-1 3/4.9.3 DECAY TIME........................ B 3/4 9-1 3/4.9.4 CONTAINMENT PENETRATIONS................. B 3/4 9-1 3/4.9.5

. Deleted l

l DAVIS-BESSE, UNIT 1 XII Amendment No. 30,105,135,174, 224 l

DEFINITIONS CHANNEL FUNCTIONAL TEST 1.11 A CHANNEL FUNCTIONAL TEST shall be:

a.

Analog channels - the injection of a simulated signal into the i

channel as close to the primary sensor as practicable to verify 0PERABILITY including alarm and/or trip functions.

b.

Bistable channels - the injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip functions.

CORE ALTERATION 1.12 CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATIONS shall not preclude ccmpletion of movement of a component to a safe position.

l SHUTD04N MARGIN 1.13 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

a.

No change in axial power shaping rod position, and b.

All control rod assemblies (safety and regulating) are fully inserted except for the single rod assembly of highest reactivity worth which is assumed to be fully withdrawn.

IDENTIFIED LEAKAGE 1.14 IDENTIFIED LEAKAGE shall be:

a.

Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b.

Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDAP.Y LEAKAGE, or CAVIS-BESSE, UNIT 1 1-3 Amendment No. 224

3/4 LIMITING CONDITIONS FOR OPERATION AND SURV2ILLANCE RE0VIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Limiting Conditions for Operation and ACTION requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for each specification.

l 3.0.2 Adherence to the requirements of the Limiting Condition for Operation l

and/or associated ACTION within the specified time interval shall constitute i

L compliance with the specification.

In the event the Limiting Condition for i

Operation is restored prior to expiration of the specified time interval, completion of the ACTION statement is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, action shall be initiated within I hour to place the unit in a MODE in which the Specification does not apply Ay.

I placing it, as applicable, in:

1.'

At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 2.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and 3.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time l

limits as measured from the time of failure to meet the Limiting Condition for l

Operation.

Exceptions to these requirements are stated in the individual Specifications.

3,0.4-Entry into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the ccnditions of the Limit,ing Condition for Operation are met without reliance on provisions contained in the ACTION I

statements unless otherwise excepted. This provision shall not prevent passage through OPERATIONAL MODES as required to comply with ACTION statements.

3.0.5 When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided: (1) its corresponding normal or emergency power source is OPr.RABLE; and (2) all of its redundant system (s),

I subsystem (s), train (s), component (s) and device (s) are OPERABLE, or likewise satisfy the requirements of this specification.

Unless both conditions (1) and-(2) are satisfied, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months action shall be initiated to place the unit in a MODE in which the applicable Limiting Condition for Operation does l

not apply by placing it as applicable in:

l.

-1..

At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l 2.

At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and l

3.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l This Specification is not applicable in MODES 5 or 6.

1 3.0.6 Equipment removed from service or declared inoperable to comply with

. ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to Specification 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

DAVIS-BESSE, UNIT 1 3/4 0-1 Amendment No. 71,135,153, 4 4

)*

l 1

i j

\\

t DELETED I

DAVIS-BESSE, UNIT I 3/4 9-5 Amendment No. 224

\\

APPLICABILITY BASES other specified conditions are. satisfied.

In this case, this would mean that for one division the emergency power source must be OPERABLE (as must be the components supplied by the emergency power source) and all redundant systems, subsystems, trains, components and devices in the other division must be l

OPERABLE, or likewise satisfy Specification 3.0.5 (i.e., be capable of performing their design functions and have an emergency power source OPERABLE).

In other words, both emergency power sources must be 0PERABLE and j

all redundant systems, subsystems, trains, components and devices in both divisions must-also be OPERABLE.

If these: conditions are not satisfied, action is required in accordance with this specification.

In MODES 5 or 6, Specification 3.0.5.is not applicable, and thus the individual ACTION statements for each applicable Limiting Condition for

- Operation in these MODES must be adhered to.

3.0.6 Specification 3.0.6 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or der'ared inoperable to comply with ACTIONS.

The sole purpose of this Specification is to provide an exception to Specification 3.0.2 (e.g.,

to not comply with the applicable Required Action (s)) to allow the performance of. required testing to demonstrate:

a.

The OPERABILITY of the equipment' being returned to service; or b.

The OPERABILITY of-other equipment.

The administrative controls ensure the time the equipment is returned to

!~

- service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the required testing to demonstrate OPERABILITY. 'This Specification does not provide time to perform any other i

preventive or corrective maintenance.

l An example of demonstrating the OPERABILITY of the equipment being returned to j

service is reopening a containment isolation valve that has been closed to comply with Required Actions, and must be reopened to perform the required testing.

l An example of demonstrating the OPERABILITY of other equipment being returned to service is taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance 1

of required testing on another channel in the other trip system. A similar j

example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the l

logic to function and indicate the appropriate response during the performance j

i of required testing on another channel in the same trip system.

l l

l DAVIS-BESSE, UNIT 1 B 3/4 0-lb Amendment No 71,135, 224 1

l l

4 l

3/4.9 REFUELING OPERATIONS BASES 3/4.9.4 CONTAINMENT PENETRATIONS (Continued)

Regarding LCO 3.9.4.c, the phrase " atmosphere outside containment" refers to anywhere outside the containment vessel, including (but not limited to) the containment annulus and the auxiliary building.

For penetrations that are closed by a method equivalent to a manual or automatic isolation valve, or a blind flange, the isolation technique must be approved by an engineering evaluation. The isolation technique may include the use of a material that can provide a temporary seal capable of maintaining the integrity of the penetration to restrict the release of radioactive material from a fuel handling accident.

With the containment purge and exhaust system in operation, a high radiation signal received from the containment purge and exhaust system noble gas monitor will effectively automatically contain the release by shutting down the containment purge system supply and exhaust fans and closing their inlet and outlet dampers. On a valid signal, the control room operator will then mar.ually close the containment purge and exhaust isolation valves.

Therefore, the uncontrolled release of radioactive material from the containment to the environment will be restricted.

With the containment purge and exhaust system not in operation, there would be no flow to the containment purge and exhaust system noble gas monitor, hence the requirements of Specification 3.9.4.c.2 would not be satisfied.

In this situation, unless Specification 3.9.4.c.1 is satisfied, entry into the Action statement would be required.

With a containment purge penetration not capable of being closed from the control room by an OPERABLE containment purge and exhaust isolation valve upon receipt of a high radiation signal from the containment purge and exhaust system noble gas monitor, closure of the containment purge and exhaust penetrations with at least one isolation valve ensures that the uncontrolled release of radioactive material from the containment to the environment will be restricted.

IL4,d. 5 COMMUNICATIQMi Deleted i

i DAVIS-StSSE, UNIT 1 B 3/4 9-la Amendment No. 185,202,221, 224 L

L j

_ _ _ _ _ _

ML20236K423

Text

Attachment:

Navigation menu

Search