ML20147C329

Amend 106 to License NPF-3,revising Tech Specs 3/4.7.10,6.4 & 6.9 & Bases 3/4.7.10 to Reflect Current Plant Design, Testing & Compensatory Measures

ML20147C329
Person / Time
Site:	Davis Besse
Issue date:	02/25/1988
From:	Perkins K Office of Nuclear Reactor Regulation
To:
Shared Package
ML20147C333	List: ML20147C329
References
NUDOCS 8803030053
Download: ML20147C329 (13)

Text

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UNITED STATES y

g NUCLEAR REGULATORY COMMISSION 5

"j WASHINGTON, D C 20555

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TOLEDO EDIS0N COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.106 License No. NPF-3 1.

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

The application for amendment by the Toledo Edison Company)and A.

The Cleveland Electric Illuminating Company (the licensees dated December 7, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confcmity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the puolic; and 3

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. hPF-3 is hereby amended to read as follows:

8803030053 080225 PDR ADOCK 05000346.

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2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.106 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 implemented not later than March 26, 1988 FOR TiiE NUCLEAR REGULATORY COMMISSION

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Kenneth E. Perkins Director Project Directorate III-3 Division of Reactor Projects - III, IV, Y and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 25, 1988

ATTACHMENT TO LICENSE AMEN 0 MENT NO.106 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Repla e the following pages of the Appendix "A" Technical Specifications with the attdched pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change. Corresponding overleaf pages are provided to maintain document completeness.

REMOVE INSERT VII VII XII XII 3/4 7-47 3/4 7-47 3/4 7-48 8 3/4 7-6 B 3/4 7-6 6-5 6-5 6-18 6-18 1

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7 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves.

3/4 7-1 Auxiliary Feedwater System 3/4 7-4 Condensate Storage Tank..............

3/4 7-6 Activity 3/4 7-7 Main Steam Line Isolation Valves 3/4 7-9 Secondary Water Chemistry..

3/4 7-10 Motor Driven Feedwater Pump System.

3/4 7-12a 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.

3/4 7-13 3/4.7.3 COMPONENT COOLING WATER SYSTEM 3/4 7-14 3/4.7.4 SERVICE WATER SYSTEM 3/4 7-15 3/4.7.5 ULTIMATE HEAT SINK 3/4 7-16 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM.

3/4 7-17 3/4.7.7 HYDRAULIC SNUBBERS 3/4 7-20 3/4.7.8 SEALED SOURCE CONTAMINATION.

3/4 7-36 3/4.7.9 FIRE SUPPRESSION SYSTEMS Fire Suppression Vater System.

3/4 7-38 Spray and/or Sprinkler System.

3/4 7-42 Fire Hose Stations 3/4 7-44 3/4.7.10 FIRE BARRIERS.

3/4 7-47 l

3/4.8 ELECTRICAL POVER SYSTEMS 3/4.8.1 A.C. SOURCES Operating.

3/4 8-1 Shutdown 3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating.

3/4 8-6 A.C. Distribution - Shutdown 3/4 8-7 D.C. Distribution - Operating.

3/4 8-8 D.C. Distribution - Shutdown 3/4 8-11 DAVIS-BESSE, UNIT 1 VII Amendment No. 55,15), 106

O INDEX BASES SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAIh7ENT...

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS...

B 3/4 6-2 3/4.6.3 CONTAIhMENT ISOLATION VALVES..

B 3/4 6-3 3/4.6.4 COMBUSTIBLE GAS CONTROL...

B 3/4 6-4 3/4.6.5 SHIELD BUILDING.

B 3/4 6-4 DAVIS-BESSE UNIT 1 XI

INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE 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 3/4.7.5 ULTIMATE HEAT SINK.

B 3/4 7-4 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM.....

B 3/4 7-4 3/4.7.7 HYDRAULIC SNUBBERS.

B 3/4 7-5 3/4.7.8 SEALED SOURCE CONTAMINATION...

B 3/4 7-6 3/4.7.9 FIRE SUPPRESSION SYSTEMS.

B 3/6 7-6 3/4.7.10 FIRE BARRIERS..

B 3/4 7-6 l

3/4.8 ELECTRICAL POWER SYSTEMS.

B 3/4 8-1 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 TIMI.

B 3/4 9-1 3/4.9.4 CONTAINMENT PENETRATIONS.

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

B 3/4 9-1 DAVIS-BESSE, UNIT 1 XII Amendment No. AA 106

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PLANT SYSTEMS 3/4.7.10 FIRE BARRIERS LIMITING CONDITION FOR OPERATION 3.7.10 All fire barriers separating portions of redundant safe shutdown systems required in the event of a fire shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a.

With one or more c f the above fire barriers inoperable, within I hour, ei';her:

1.

Establish a continuous fire watch on at least one side of the affected fire barrier, or 2.

Verify the OPERABILITY of the fire detectors on at least one side of the affected fire barrier and establish an hourly fire watch patrol, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUIREMENTS 4.7.10 Each of the above required fire barriers, including sealing devices, shall be verified OPERABLE by:

a.

Perforring a visual inspection of the exposed surfaces of each fire-rated vall*, floor and ceiling, electrical race-vay fire enclosure and structural steel fire-proofing at least once per 18 months, b.

Performing a visual inspection of each fire door, fire damper and associated hardware at least once per 18 months.

f

• Barrier 102 West /210 East and a portion of barriers 206 East /210 West and 205 North /206 South behind the filter bank are not subject to the requirements for visual inspection due to ALARA considerations.

1 DAVIS-BESSE, UNIT 1 3/4 7-47 Amendment No. I,di gg, 106

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I SURVEILLANCE REQUIREMENTS i

c.

Performing a visual inspection of at least ten percent of each type of sealed penetration at least once per 18 months. If the penetration (s) is determined to be inoperable, declare the affected penetration (s) inoperable and perform a visual inspection of an additional ten percent of the degraded type of sealed penetration. This inspection process shall continue until a ten percent sample with no visually apparent adverse changes in appearance or changes from the as-built condition are found or until all required sealed penetrations of the degraded type have been inspected.

Samples shall be selected such that each penetration seal vill be inspected at least once per 15 years.

d.

Verifying at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> each fire door (1) that is unlocked is closed or (ii) that is equipped with an automatic hold-open and release mechanism is free from obstructions.

e.

Verifying at least once per 7 days each locked fire door is closed and locked.

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f.

Performing a functional test that verifies the operation of automatic hold-open and release mechanisms upon full openings, and latch and closing mechanisms upon full and partial openings, at least once per 18 months.

1 DAVIS-BESSE, UNIT 1 3/4 7-48 Amendment No. I,df.df, 106

9 PLANT SYSTEMS BASES 3/4.7.8 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from by product, source, and special nuclear material souces will not exceed allowable intake values.

3/4.7.9 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occuring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, rnd fire hose stations. The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program.

In the event that portions of the fire suppression systems are inoper-able, altsrnate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.

In the event the fire suppression water system becomes inoperable, immedi-ate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppres-sion espability for the continued protection of the nuclear plant.

3/4.7.10 FIRE BARRIERS The OPERABILITY of the fire barrier ensures that fires will be confined or adequately retarded from spreading to adjacent fire areas or to portions of redundant safe shutdown systems required in the event of a fire within the fire area. This design feature minimites the possibility of a single fire rapidly involving several fire areas of the facility prior to detection and extinguishment. The fire barriers are passive elements in the facility fire protection program.

Fire barriers, including cable penetration barriers, fire doors and dampers, are considered OPERABLE when the visually observed ' condition is the same as the as-designed condition. The as-designed condition of each fire barrier is based on a tested configuration or a configura*.fon

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analyzed to withstand the fire hazards associated with the fire area.

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i DAVIS-BESSE, UNIT 1 B 3/4 7-6 Amendment No. 1, 106

ADMINISTPATIVE CONTROLS 6.3 FACILITY STA}F QUALIFICATION i

6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1)- the Chemistry and Health Physics General Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8 September 1975 and (2) the Shif t Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Training Director and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Nuclear Training Director.

6.5 REVIEW AND AUDIT 6.5.1 STATION REVIEW BOARD (SRB)

FUNCTION

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gw 6.5.1.1 The Station Review Board (SRB) shall function to advise the Plant Manager on all matters related to nuclear safety.

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DAVIS-BESSE, UNIT 1 6-5 Amendment No i,11,gy,ff, 106

ADMINIS h TIVE CONTROLS COMPOSITION 6.5.1.2 The Station Review Board shall be composed of the:

Chairman:

Station Review Board Chairman

• Member:

Assistant Plant Manager, Operations Member:

Assistant Plant Hanager, Maintenance Member:

Technical Support Manager Member:

Chemistry and Health Physics General Superintendent Member:

Operations Engineering Supervisor (Plant)

Member:

An Engineering Director or Performance Engineering Manager Member:

Operations Quality Assurance Manager Member:

Operations Superintendent (Plant)

• Designated in writing by the Plant Manager. The Chairman will be drawn from SRB members.

ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the SRB Chairman to serve on r temporary basis; however, no more than two alter-nates shall participate as voting acabers in SRB activities st any one time.

MEETING FREQUENCY 6.5.1.4 The SRB shall meet at least once per calendar month and as convened by the SRB Chairman or his designated alternste.

QUORUM 6.5.1.5 A quorum of the SRB shall consist of the Chairman or his desig-nated alternate and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The Station Review Board shall be responsible for:

a.

Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Plant Manager to affect nuclear l

safety.

b.

Review of all proposed tests and experiments that affect nuclear safety.

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DAVIS-BESSE, UNIT 1 6-6 Amendment No. 14/, 74/,98 a

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l ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requireeents of the applicable reference specifications a.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

b.

Inoperable Seismic Monitoring Instrumentation Specification L

3.3.3.3.

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c.

Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

l d.

Seismic event analysis, Specification 4.3.3.3.2.

e.

Fire Detection Instrumentation, Specification 3.3.3.8.

f.

Fire Suppression Systems, Specifications 3.7.9.1 and 3.7.9.2.

g.

Dose or dose commitment exceedences to a MEMBER OF THE PUBLIC l

from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (Specification 3.11.1.2).

h.

The discharge of radioactive liquid vaste without treatment and l

in excess of the limits in Specification 3.11.1.3.

i.

The calculated air dose from radioactive gases exceeding the l

f limits in Specification 3.11.2.2.

j.

The calculated dose from the release of iodine-131, tritium, and l

radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding the limits in Specification 3.11.2.3.

k.

The discharge of radioactive gaseous vaste without treatment l

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and in excess of the limits in Specification 3.11.2.4.

1.

The calculated doses from the release of radioactive materials l

1 in liquid or gaseous effluents exceeding the limits in Specification 3.11.4.

m.

The level of radioactivity as the result of plant' effluents in l

an environmental saepling medium exceeding the reporting levels of Table 3.12-2 (Specification 3.12.1).

DAVIS-BESSE, UNIT 1 6-18 Amendment No. I,If,$I,gd, 106 j

ADMiNj9U?!IVECCNTROLS 6.10 RECORD RETEhTION 6.10.1 The following records shall be retained for at least five yearst a.

Records and logs of facility operatien covering time interval at each power level.

b.

Records and logs of principal maintenance activities.

inspections, repair and replacement of prfncipal items of equipment related to nuclear safety.

c.

ALL REPORTABLE EVENTS.

d.

Records of surveillance accivit(es, inspections and calibrations required by these Technical Specifications.

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DAVIS-BESSE UNIT 1 6-18a Amendment No. 86.93 (Next page is 6-19)

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