ML20236X859

Proposed Tech Specs Re Fire Protection

ML20236X859
Person / Time
Site:	Davis Besse
Issue date:	12/07/1987
From:	TOLEDO EDISON CO.
To:
Shared Package
ML20236X823	List: ML20236X822 ML20236X833 ML20236X859
References
TAC-65361, NUDOCS 8712100318
Download: ML20236X859 (7)

Text

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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 SFU2BERS . .... . . . . . . . . . . . 3/4 7-20 3/4.7.8 SEALED SOURCE CONTAMINATION . . . . . . . . . . . . 3/4 7-36 3/4.7.9 FIRE SUPPRESSION SYSTEMS Fire Suppression Water 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 1 l

3/4.8 ELECTRICAL POWER 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 8-10 8712100318 871207 PDR ADOCK 05000346 VII AmendmentNo.//, 103 i P PDR l

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l ADDilt0NAl CHMGS PREVIOUSLY

! PROPO$!D fn LtHlR N

$ctial No._ }_'{0] D3te //.p-F7 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 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM. . . . . . ..... B 3/4 7-3 4 3/4.7.4 SFRVICE 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 3/4 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 TIME. . . . . . . . . . . . . . . . ..... 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. 38

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L l -PLANT SYSTEMS

! I 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 of the above fire barriers inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, either:

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

a. Performing a visual inspection of the exposed surfaces of anch fire-rated wall *, floor and ceiling, electrical race-way 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 lesst once per 18 months.

• Barrier 102 West /210 East and a portion of barrict s 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.

DAVIS-EESSE, UNIT 1 3/4 7-47 Amendment No. 9,55,93

SURVEILLANCE REQUIREMENTS

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 scaled 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 that is unlocked is closed or 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,

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

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i DAVIS-BESSE, UNIT 1 3/4 7-48 Amendment No. 9,65,93 l

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l I PLANT' SYSTEMS BASES l

3/4.7.8 SEALED SOURCE CONTAMINATION I

The limitations on removable conte.mination 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.

4 3/4.7.9 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is arra11able 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, and fire hose stations. The collective capability of the fire suppression systems is adequate to minimi e 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, alternate 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 provideo for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppres-sion capability for the continued protection of the nuclear plant. i 3/4.7.10 FIRE BARRIERS The OPERABILITY of the fira barrier ensures that fires will be confined i i

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 minimizes 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 j dampers, are considered OPERABLE when the visually observed condition is  !

the same as the as-designed condition. The as-designed condition of each i fire barrier is based on a tested configuration or a configuration  !

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

DAVIS-BESSE, UNIT 1 B 3/4 7-6 Amendment No. 9

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F-ADDITIONAL CHANGES PREVIOUSLY PROPOSED BY LETTER Scrial flo. l'/ / / Date F-3/-F7 l

ADMINISTRATIVE CONTROLS 1

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum i 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 Shift 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 Erigade shall be maintained under the direction of the Nuclear Training Director.

6.5 REVIEW AND AUDIT 6.5.1 STATION REVIEW BOARD (SRB)

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

DAVIS-BESSE, UNIT 1 6-5 Amendment No. 9,37,89,98

ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of 7nspection 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 requirements of the applicable reference specification:

a. ECCS Actuation, Specifications 3.5.2 and 3.5.3.

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b. Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

c. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

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 HEMBER OF THE PUBLIC  !

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

h. The discharge of radioactive liquid waste without treatment acd I in excess of the limits in Specification 3.11.1.3.

1. The calculated air dose from radioactive gases exceeding the l

limits in Specification 3.11.2.2.

j. The calculated dose from the release of iodine-131, tritium, and l radionuclides in particulate form w1th 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

and in excess of the limits in Specification 3.11.2.4.

1. The calculated doses from the release of radioactive materials l 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  ;

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

DAVIS-BESSE, UNIT 1 6- 18 Amendment No. 5,12,55,86 l

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