Text

Amend 221 to License NPF-3,adding Valve Position Requirements & Deleting Certain Containment Radiation Monitor Requirements & Valve Isolation Verification Requirements
	ML20216B898
Person / Time
Site:	Davis Besse
Issue date:	04/15/1998
From:	Hansen A; NRC (Affiliation Not Assigned)
To:	;
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ML20216B904	List: ML20216B898; ML20216B940;
References
	NUDOCS 9805180508
	Download: ML20216B898 (19)
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TOLEDO EDISON COMPANY QiNTERIOR SERVICE COMPANY 8!iD THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 221 License No. NPF-3

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1.

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

A.

The application for amendment by the Toledo Edison Company, Centerior Service Company, and The Cleveland Electric Ililuminat;nj Company (the licensees) dated June 24, 1997, 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 l

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, l

and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:

I ENCLOSURE 1 78A!8882 58M346

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P PDR s

.. (2)

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 221, are hereby incorporated in the license.

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

3.

This license amendment is effective as of its date of issuance and shall be inplemented not later than 120 days after issuance.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION j

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 Date of issuance: April l!', 1998 J

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ATTACHMENT TO LICENSE AMENDMENT NO. 221 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 3/4 3-10 TS 3/4 3-10 TS 3/4 3-11 TS 3/4 3-11 TS 3/4 3-12 TS 3/4 3-12 TS 3/4 3-13 TS 3/4 3-13 TS 3/4 3-14 TS 3/4 3-14 TS 3/4 3-16 TS 3/4 3-16 TS 3/4 3-18 TS 3/4 3-18 TS 3 4 3-20 TS 3/4 3-20 f

TS '3/4 3-21 TS 3/4 3-21 TS 3/4 3-22 TS 3/4 3-22 TS 3/4 6-10 TS 3/4 6-10 TS 3/4 6-15 TS 3/4 6-15 TS 3/4 9-4 TS 3/4 9-4 TS B 3/4 6-2 TS B 3/4 6-2 TS B 3/4 6-3 TS B 3/4 6-3 TS B 3/4 9-la TS B 3/4 9-la

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TABLE 3.3-3 (Continued)

TABLE NOTATION Trip function may be bypassed in this MODE with RCS pressure below 1800 psig. Bypass shall be automatically removed with RCS pressure exceeds 1800 psig.

Trip function may be bypassed in this MODE with RCS pressure below 660 psig.

Bypass shall be automatically removed when RCS pressure exceeds 660 psig.

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DELETED l

DELETED All functional units may be bypassed for up to one minute when starting each Reactor Coolant Pump or Circulating Water Pump.

i When either Decay Heat Isolation Valve is open.

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The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 10 - With the number of OPERABLE functional units one less than the Total Number of 'Jn'ts, STARTUP and/or POWER OPERATION may proceed l

provided both of t'.ie following conditions are satisfied:

a.

The inoperable functional unit-is placed in the tripped condition within one hour.

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b.

The Minimum Units OPERABLE requirement is met; however, one l

additional functional unit may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.1.

i ACTION 11 - With any component in the Output Logic inoperable, trip the associated components within one hour or be in at least HOT STANDBY 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 .

1 DAVIS-BESSE, UNIT 1 3/4 3-12 Amendment No. 20,37,52,102, 135,150,100,211,210,221

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i TABLE 3.3-5 SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS l

1.

Manual a.

Fans 1.

Emergency Vent Fan NA 2.

Containment Cooler Fan NA l

b.

HV & AC Isolation Valves 1.

ECCS Room NA 2.

Emergency Ventilation NA 3.

Containment Air Sample NA 4.

DELETED l

5.

Pentration Room Purge NA c.

Control Room HV & AC Units NA d.

High Pressure Injection 1.

High Pressure Injection Pumps NA 2.

High Pressure Injection Valves NA

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Component Cooling Water 1.

Component Cooling Water Pumps NA 2.

Component Cooling Aux. Equip. Inlet Valves NA 3.

Component Cooling to Air Compressor Valves NA f.

Service Water System 1.

Service Water Pumps NA 2.

Service Water From Component Cooling Heat Exchanger Isolation Valves NA i

g.

Containment Spray Isolation Valves NA l

h.

Emergency Diesel Generator NA 1.

Containment Isolation Valves j

1.

Vacuum Relief NA 2.

Normal Sump NA 3.

RCS Letdown Delay Coil Outlet NA 4.

RCS Letdown High Temperature NA l

DAVIS-BESSE, UNIT 1 3/4 3-14 Amendment No.221 l

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TABLE 3.3-5 (Continued)

SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 2.

Containment Pressure - High a.

Fans 1.

Emergency Vent Fans s 25*

2.

Containment Cooler Fans s 45*

b.

HV & AC Isolation Valves 1.

ECCS Room s 75*

2.

Emergency Ventilation s 75*

3.

Containment Air Sample s 30*

4.

DELETED l

5.

Penetration Room Purge s 75*

c.

Control Room HV & AC Units s 10*

d.

High Pressure Injection

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High Pressure Injection Pumps s 30*

2.

High Pressure Injection Valves s 30*

e.

Component Cooling Water 1.

Component Cooling Water Pumps s 180*

2.

Component Cooling Aux. Equip. Inlet Valves s 180*

3.

Component Cooling to Air Compressor Valves s 180*

f.

Service Water System 1.

Service Water Pumps s 45*

2.

Service Water From Component Cooling Heat Exchanger Isolation Valves s NA*

g.

Containment Spray Isolation Valves s 80*

h.

Emergency Diesel Generator s 15*

DAVIS-BESSE, UNIT 1 3/4 3-16 Amendment No. M4r 221 l

1 TABLE 3.3-5 fContinued).

SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS b.

Component Cooling Isolation Valves (Continued) 3.

Inlet to CRDM's s 35*

4.

CRDM Booster Pump SJCtion s 35*

5.

Component Cooling from Decay Heat Cooler s NA*

4.

RCS Pressure-Low a.

Fans 1.

Emergency Vent Fans s 25*

2.

Containment Cooler Fans s 45*

b.

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ECCS Room s 75*

2.

Emergency Ventilation s 75*

3.

Containment Air Sample

$ 30*

4.

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5.

Penetration Room Purge s 75*

c.

Control Room HV & AC Units 5 10*

d.

High Pressure Injection 1.

High Pressure Injection Pumps s 30*

2.

High Pressure Injection Valves s 30*

e.

Component Cooling Water 1.

Component Cooling Water Pumps s 180*

2.

Component Cooling Aux. Equipment Inlet Valves s 180*

3.

Component Cooling to Air Compressor Valves s 180*

f.

Service Water System 1.

Service Water Pumps s 45*

2.

Service Water from Component Cooling Heat Exchanger Isolation Valves s NA*

g.

Containment Spray Isolation Valves s 80*

h.

Emergency Diesel Generator 5 15*

DAVIS-BESSE, UNIT 1 3/4 3-18 Amendment No. 444r 221

TABLE 3.3-5 (Continued)

SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 6.

DELETED TABLE NOTATION Diesel generator starting and sequence loading delays included when applicable.

Response time limit includes movement of valves and attainment of pump or blower discharge pressure.

DAVIS-BESSE, UNIT 1 3/4 3-20 Amendment No. 40r 221

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CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 The containnent purge supply and exhaust isolation valves shall be closed with control power removed.

l APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one isolation valve open in a containment purge supply and/or exhaust penetration, or with its control power not removed, verify that the remaining containment purge supply and exhaust isolation valves are closed with control power removed by perfoming Surveillance Requirement 4.6.1.7 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Close the open containment purge supply and/or exhaust isolation ulve and verify control power is removed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY 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 .

SURVEILLANCE REOUIREMENTS 4.6.1.7 At least once per 31 days verify that each containment purge supply j

and exhaust isolation valve is closed with control power removed.

l DAVIS-BESSE, UNIT 1' 3/4 6-10 Amendment No. 445r221

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CONTAINMENT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) 4.6.3.1.2 Each isolation valve shall be demonstrated OPERABLE at least once each REFUELING INTERVAL, by:

a.

Verifying that on a containment isolation test signal, each 5

automatic isolation valve actuates to its isolation position.

b.

DELETED l

4.6.3.1.3 The isolation time of each power operated or automatic valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

DAVIS-BESSE, UNIT 1 3/4 6-15 Amendment No. I'7,213, 221 N6

. ELEVELING OPERATIONS CONTAINMENT PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment penetrations shall be in the following status:

a. The equipment door closed and held in place by a minimum of four bolts,

b. A minimum of one door in each airlock closed, but both doors of the

'4 containment personnel air lock may be open provided that at least one personnel air lock door is capable of being closed and a designated individual is available immediately outside the personnel air lock to close the door, and

{

c.

Each penetration providing direct access from the containment atmosphere to the atmosphere outside containment shall be either:

1.

Closed by a manual or automatic isolation valve, blind flange, or equivalent, or 2.

Be capable of being closed from the control room by an OPERABLE containment purge and exhaust valve upon receipt of a high radiation signal from the containment purge and exhaust system noble gas monitor.

1 APPLICABILITY:

During CORE ALTERATIONS or movement of irradiated fuel within the

)

containment.

ACTION:

a.

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment.

b. With the requirements of Specification 3.9.4.c not satisfied for the containment purge and exhaust system, close at least one of the isolation valves for each of the purge and exhaust penetrations providing direct access from the containment atmosphere to the outside atmosphere within one hour.

c. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REOUIREMENTS 4

4.9.4 Each of the above required containment penetrations shall be determined to be either in its required condition or capable of being closed by an OPERABLE containment purge and exhaust valve, within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment, by:

a. Verifying the penetrations are in their required condition, or b.- Verifying that with the containment purge and exhaust system in operation, and the containment purge and exhaust system noble gas monitor capable of providing a high radiation signal to the control room, that after initiation of the~high radiation signal, the containment purge and exhaust isolation valves can be closed from the control room.

DAVIS-BESSE, UNIT 1 3/4 9-4 Amendment No. 105,202,221

CONTAINMENT SYSTEMS BASES 3 /4. 6.1. 4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the annulus atmosphere of 0.5 psi and 2) the containment peak pressure does not exceed the design pressure of 40 psig during LOCA conditions.

The maximum peak pressure obtained from a LOCA event is 37 psig. The limit of 1 psig for initial positive containment pressure will limit the total pressure to 38 psig which is less than the design pressure and is consistent with the safety analyses.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a LOCA.

3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY Deleted 3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM Maintaining the containment purge supply and exhaust isolation valves closed with control power removed at all times during MODES 1, 2, 3 and 4 provides assurance that the safety function of containment isolation is maintained in the event of a LOCA.

The ACTION statement assures that at least one containment purge supply and exhaust isolation valve is closed in each containment penetration and provides reasonable time to permit closure of an open valve.

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that containment depressurization and cooling capability will be available in the event of a LOCA. The pressure reduction and resultant lower containment DAVIS-BESSE, UNIT 1 B 3/4 6-2 Amendment No. 135,005, 221 l

CONTAINMENT SYSTEMS BASES leakage rate are consistent with the assumptions used in the safety analyses.

Borated Water Storage Tank (BWST) outlet isolation valves DH-7A and DH-7B are de-energized during MODES 1 2, 3, and 4 to preclude postulated inadvertent closure of the valves in the event of a fire, which could result in a loss of the availability of the BWST. Re-energization of valves DH-7A and DH-7B is permitted on an intermittent basis during MODES 1, 2, 3 and 4 under administrative controls. Station procedures identify the precautions which must be taken when re-energizing these valves under such cc:trols.

Containment Emergency Sump Recirculation Valves DH-9A and DH-9B are de-energized during MODES 1, t, 3, and 4 to preclude postulated inadvertent opening of the valves in the event of a fire, which could result in draining the Borated Water Storage Tank to the Containment Emergency Sump and the loss of this water source for normal plant shutdown. Re-energization of valves DH-9A and DH-98 is permitted on an intermittent basis during MODES 1, 2, 3,.and 4 under administrative controls. Station procedures identify the precautions which must be taken when re-energizing these valves under such controls.

3/4.6.2.2 CONTAINMENT COOLING SYSTEM The OPERABILITY of the containment cooling system ensures that 1) the containment air temperature will be maintained within limits during normal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions.

i 3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation within the required time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

Containment isclation valves and their required isolation times are addressed in the USAR. The opening of a closed inoperable containment isolation valve on an intermittent basis during plant operation is permitted under administrative control. Operating procedures identify those valves which may be opened under administrative control as well as the safety precautions which must be taken when opening valves under such controls.

The conta3nment purge supply and exhaust system isolation valves are considered OPERABLE with respect to containment isolation when they meet the requirements of Specification 3.6.1.7.

DAVIS-BESSE, UNIT 1 B 3/4 6-3 Amendment No. 225,10,1"2,105,221

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 manually 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.

3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling.

station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during CORE ALTERATIONS.

DAVIS-BESSE, UNIT 1 B 3/4 9-la Amendment No.1"S,2^2,221

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ML20216B898

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