ML19319C864

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{{#Wiki_filter:_. / L/ INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL. POWER IMBALANCE................................ 3/4 2-1 3/4.2.2 NUCLEAR HEAT FLUX HOT CHANNEL FACTOR - F...,............................. 3/4 2-4 9 3/4.2.3 NUCLEAR ENTHALPY RISE N 3M 2-6 HOT CHANNEL FACTOR - F3gm........o............... 3/4.2.4 QUADRANT POWER TILT.................................. 3/4 2-8 3/4.2.5 DNB PARAMETERS....................................... 3/4 2-12 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............ 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.................................... 3/4 3-9 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation................. 3/4 3-22 Incore Detectors.......................... .......... 3/4 3-26 S e i smi c I ns t rumen ta ti on.............................. 3/4 3-28 Meteorological Ins trumenta tion....................... 3/4 3-31 Remote Shutdown Instrumentation...................... 3/4 3-34 Post-accident Instrumentation........................ 3/4 3-37 Fi re Dectection Ins trumenta tion...................... 3/4 3-40 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT L00PS................................ 3/44-1 3/4.4.2 SAFETY VALVES - SHUTD0WN............................. 3/4 4-3 3/4.4.3 SA FETY VALV ES - 0 PERAT ING............................ 3/4 4-4 CRYSTAL RIVER - UNIT 3 IV eees040 92Y.

i,* 3 A . r. INDEX T .IMITING CONDITIONS FOR OPERATION AND SURVEILLANCE-REOUIREMEN S SECTION _PAGE 3/4.7' PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...... 3/4 7-13 3/4.7.3 CLOSED CYCLE COOLING WATER SYSTEM Nuclear Services Closed Cycle Cooling System......... 3/4 7-14 Decay Heat Closed Cycle Cooling Water System......... 3/4 7-15 3/4.7.4 SEA WATER SYSTEM Nuclear Services Sea Water lSys tem.................... 3/4 7-16 Decay Hea t Sea Wa ter Sys tem.......................... 3/4 7-17 3/4.7.5 ULTIMATE HEAT SINK................................... 3/4 7-18 3/4.7.6 FL000' PROTECTION..................................... 3/4 7-19 3/4.7.7 CJNTROL ROOM EMERGENCY VENTILATION SYSTEM............ 3/4 7-20 3/4.7.8 AUXILI ARY BUILDING VENTILATION EXHAUST SYSTEM........ 1/4 7-71 3/4.7.9 HYDRAULIC SNUBBERS................................... 3/4 /-25 3/4.7.15 SEALED SOURCE CONTAMINATION.......................... 3/4 7-3S 3/4.7.11 FIRE SUPPRESSION SYSTEMS Water System.........................................;3/4 7-38 Del uge a nd Spri nkl er Sys tems........................ 3/4 7-41 Ha l o n S ys t em........................................ 3/ 4 7-4 4 Fi re Hos e S ta ti on s.................................. 3/ 4 ' 7-4 S 3/4.7.12 PENETRATION FIRE BARRIERS........................... 3/4 7-47 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES O p e ra t i n g........................................... 3 / 4 8-1 S h u t d ow n............................................. 3 / 4 8-6 3/4.8.2. DNSITE POWER DISTRIBUTION SYSTEMS A.C. Di s tribution - Opera ting........................ 3/4 8-7 A.C. Distribution - Shutdown......... 3/4 8-9 D.C. Distribution - Operating... 3/4'8-10 0.C. Distribution - Shutdown.. 3/4 8-12 CRYSTAL RIVER - UNIT 3 VII' y l r -

INDEX ~ BASES PAGE SECTION 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 CLOSED CYCLE COOLING WATER SYSTEM................ B.3/4 7-3 3/4.7.4 SEA WATER SYSTEM...<....,........................ B 3/4 7-3 3/4.7.5 ULT IMAT E H EAT S I N K............................... B 3/4 7-4 3/4.7.6 FLOOD PROTECTION................................. B 3/4 7-4 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM........ B 3/4 7-4 3/4.7.8 AUXILIARY BUILD 7NG VENTILATION-EXHAUST SYSTEM.... B 3/4 7-5 3/4.7.9 HYDRAULIC SNUBBERS............................... B 3/4 7-5 3/4.7.lb SEALED SOURCE CONTAMINATION...................... B 3/4 7-6 3/4.7.11 FIRE SUPPRESSION SYSTEMS......................... B 3/4 7-7 3/4.7.12 PENETRATION FIRE BARRIERS........................ B 3/4 7-6 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SCORCES..................................... B 3/4 8-1 3/4.8.2 ONSITE POWER DISTRIBUTION 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

RYSTAL RIVER - UNIT 3 XII

,8 INSTRUME'NTATION FIRE ~0ETECTION INSTRUMENTATION LIMITING CONDITION'FOR OPERATION 3.3.3.7 As a minimum, the' fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE. APPLICABILITY: Whenever-equipment in that fire detection zone is required to be OPERABLE. ACTION: With one or more of the fire detection instrument (s) shown in Table 3.3.11, inoperable: a. Within 1 hour, establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per. hour, and .b. Restore the inoperable instrument (s) to OPERABLE status within 14 days or in lieu of any other report required by Specification '6.9.1, prepare and submit a Special Report to the. Commission pursuant to Specification 6.9.2 within the next 30 days out-lining the action taken, the cause of-the malfunction and the plans and schedule for restoring the instrument (s) to OPERABLE status. c. The provisions of Specifications 3.0.3 and 3.0.4 are not. applicable. SURVEILLANCE REQUIREMENTS 4.3.3.7.1 Each of the above fire detection instruments shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. l 4.3.3.7.2 ThL circuitry associated with the detector alarms listed in l-Table 3.3-11 shall be demonstrated OPERABLE at least once'per 6 months for all National Fire Protection Association (NFPA) Code 72D Class B I supervised circuits. l 4.3.3.7.3 THE non-supervised circuits between the local panels and the control room for the detectors listed in Table 3.3-11 shall be denonstrated j OPERABLE at least once per 31 dyas. i CPYSTAL RIVER - UNIT 3 3/4 3-40 v ,s

2/ ' TABLE 3.3-11 FIRE DETECTION INSTRUMENTS MINIMUM DETECTORS OPERABLE ~ DETECTOR LOCATION HEAT /SM0KE 1. Conte Complex ~a. i.levation 108'0" 1. Zone 4 (Plant Battery Room 38) -NA/l 2. - Zone 5 (Plant Battery Room 3A) NA/l 3. Zone 6 (Battery Charger Room.38) NA/l 4 , Zone 7 (Battery Charger Room 3A) NA/l 5.. Zone 8 (4160V Switchgear Bus Room'3B) NA/l 6. Zone 9.(4160V Switchgear Bus Room 3A) flA/l 7. Zone-10 (Inverter Room 38) NA/l 8. Zone 11. (Inverter Room 3A) NA/l b. Elevation 120'0" 1. Zone 5 (Control Rod Drive Equipment Room) NA/2 2. Zone 7 (480V Switchgear. Bus Room 38) NA/l 3. Zone 8 (480V Switchgear Bus Room 3A) NA/l c. Elevation 134'0' 1. Zone 3A (Cable Spreading Room) NA/S or 2. Zone 3B (Cable Spreading Room) NA/3 d. Elevation 145'0" 1. Zone 4 (Satellite Instrument Shop and Office)NA/2 2. Zone 5 (Control Room) 1/6 e. Elevation 164'0" 1. Zone 3 (HVAC Equipment Room) NA/S 2. Zone 4 (HVAC Emergency Equipment 3B) NA/l 3. Zone 5 (HVAC Emergency Equipment 3A) NA/l l 1 2. Auxiliary Building i a. . Elevation 119'0" 1. ' Zone 20 (Emergency Diesel' Generator 3B Controls Room) 1/NA 2. Zone 21 (Emergency Diesel Generator 3A Controls Room) 1/MA 3. Zone 27 (Emergency Diesel Generator Room 38) 5/MA CRYSTAL RI'f!R OOIT $ "9h f

n PLANT SYSTEMS 3/4.7.11 FIRE SUPPRESSION' SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.11.1 The fire suppression water system shall be OPERABLE with: a. At least two high pressure pumps each with a capacity of 2000 gpn, with their discharge aligned to the fire suppression header, b. Separate water. supplies, each with a minimum contained water volume of 345,000 gallons. c. An OPERABLE flow path capable of taking suction from the water supply and transferring the water through distribution piping with OPERABLE sectronalizing control or isolation valves to the yard hydrant curb valves and the front valve ahead of the water flow alarm device on each sprinkler, hose standpipe and spray system riser required to be OPERABLE per Specifications 3.7.11.2 and 3.7.11.4. APPLICABILITY: At all times. ACTION: a. With one pump and/or one water supply inoperable, restore the in-operable equipment to OPERABLE status within 7 days or, in lieu of any other report required by Specification 6.9.1, prepare and'sub-mit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system. The provisions of Specification 3.0.3 and 3.0.4 are not applicable. b. With the fire suppression water system otherwise inoperable: 1. Establish a backup fire suppression water system within 24 hours, and 2. Submit a Special Report in accordance with Specification 6.9.2; a) By telephone within 24 hours, b) Confirm by telegraph, mailgram, or facsimile transmission no later than the first working day following the event, and CRYSTAL RIVER - UNIT 3 3/4 7-38

n PLANT SYSTEMS LIMITING CONDITION FOR OPERATION (Cont'd)- c) In writing within 14 days-following the event, out- -lining the action taken, the-cause of the inoperability and the plans and schedule for-restoring the system - -to OPERABLE status. SURVEILLANCE REQUIREMENTS 4.7.11.1 The fire' suppression water system.shall be demonstrated OPERABLE: a. At least once per 7 days by verifying the' contained water supply volume. b. At least once per 31 days on a STAGGERED TEST BASIS by starting each pump and operating it for at least 15 minutes on recircula-tion flow. c. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position. d. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel. e. At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system throughout its operating sequence, and: 1. Verifying that each automatic valve in the flow path actuates to its correct position, i 2. Verifying that each pump develops at least 2000 gpm at a discharge pressure of > 115 psig. 3. Cycling each valve in the flow path that is not testable luring plant operation through at least one complete cycle of fulI travel, and 4 Verifying that each high pressure pump starts (sequentially) to maintain the fire suppression water system pressure > 70 psig. f. At least once per 3 years by performing flow tests of the system in accordance with Chapter 5, Sectiun 11 of Fire Prnter. tion llandbook, lath Edition (January 1976) published by National Fire Protection Association. CRYSTAL RIVER - UNIT 3 3/4 7-39

m PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Cont.) q. By ' demonstrating the fire pump. diesel engines OPERABLE: 1. At least once per 31. days by verifying: (a) The fuel storage tank contains at least 175 gallons of fuel, and (b) The diesel stacts from ambient conditions and operates for_ at least 20 minutes. 2. At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained in accordance with ASTM-D270-65, is within the acceptable limits specified in Table 1 of ASTM-D975-74 with respect to viscosity, water content and sediment for the type of fuel specified for use in the diesels. 3. At least once per 18 months, during shutdown, by: (a) Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service, and (b) Verifying the diesel starts from ambient conditions on the auto-start signal and operates for > 20 minutes while loaded with the fire pump. ~ h. By demonstrating the fire pump diesel starting 24-volt battery banks and chargers OPERABLE: 1. At least once per 7 days by verifying that: (a) The electrolyte level of each battery is above the plates, and (b) The overall battery voltage is 1 24 volts. 2. At least once per 92 days by verifying that the specific gravity is appropriate for continued service of the battery. 3. At least once per 18 months by verifying that: (a) The batteries, cell plates and battery racks show no visual indication of physical damage or abnonnal deterioration, and (b) The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material. CRYSTAL RIVER - UNIT 3 3/4 7-40 l

j PLANT SYSTEMS DELUGE AND SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.11.2 The deluge and sprinkler systems shown in Table 3.7-4 shall be OPERABLE. APPLICABILITY: Whenever equipnent in the deluge / sprinkler protected areas' ts required to be OPERABLE. ACTION: a. With one or more of the above required deluge and sprinkler systems inoperable, establish a continuous fire watch with backup fire suppression equipment for the unprotected area (s) within I hour; restore the system to OPERABLE status within.14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Soecial Report to the. Commission pursuant to Specification 6.5.2 within the next 30 days out-lining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status, b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable. SURVEILLAtCE REQJtREMENTS J 4.7.11.2 Each of the above required deluge and sprinkler systems shall be demonstrated OPERABLE: -a. At least or e per 12 months-by cycling each testable valve in the flow path through at least one complete cycle of full travel. b. At least once per 18 months: 1 By performing a system functional test which includes simulated automatic actuation of the system, and: a) Verifying that the automatic valves in the flow path actuate to their correct positions. CRYSTAL RIVER - UNIT 3' 3/4 7-41

t SURVEILLANCE REQUIREMENTS (Continued) b) Cycling each valve in the flow path.that is not testable during plant operation through at least one complete cycle of full. travel. 2. By inspection of the spray headers to verify their integrity,'and 3. By inspection of each nozzle to verify no blockage. c. At least once per 3 ~ years by performing. an _ air flow test through each 'open head spray / sprinkler header and verifying each open head spray / sprinkler nozzle is unobstructed. CRYSTAL RIVER - UtlIT 3 3/4 7-42

'I ? I TABLE'3.7 4 E!d CFLUGE AND SPRINKLER SYSTEMS. . i2 P SYSTEM LOCATION 25 y 1 AllFL-1. Deluge System Auxiliary: Building, Elevation 143'0", Zone 11 (Main Filter Exhaust Room) 2. AllFL-2A Deluge System Auxiliary Building, Elevation 143'0", Zone 11 - (Main Filter. Exhaust Room)- E

q 3.

AHFL-2B Deluge System Auxiliary Building, Elevation 143')", Zone ll. (Main; Filter Exhaust Roo. { . #1 ^ 4. AllFL-2C Deluge System . Auxiliary Building, Elevation 143'0", Zone.11. (Main Filter Exhaust Room), u, 5. AHFL-2D Deluge System Auxiliary Building, Elevation 164'0", Zone.5 (Main Filter Exhaust. Room). 6. AHFL-4A Deluge System Control Complex, Elevation 164'0", Zone 5 (llVAC. Emergency ' Equipment 3A)- 7. AllFL-4B Deluge System Control Complex, Elevation 164'0", Zohe 4 (HVAC Emergency EquipmentL38) u,. 1: 8 AllFL-15 Deluge System Auxiliary Building, Elevation 95'0", Zone 34 (Nuclear Sampling Room). y I. 9. Emergency Diesels Deluge Auxiliary Building, Elevation 119'0", Zones 27 and 28 n

~ PLANT SYSTEMS HALON SYSTEM LIMITING CONDITION FOR OPERATION 3.7.11.3 - The Halon system in the Cable Spreading room (Control Complex, Elevation 134'0") shall be OPERABLE w.ith the stoiage tanks having at least 95% of full charge weight and 90". of full charge pressure. APPLICABILITY: At all times ACTION: a. With one or more of the above required Halon systems inoperable, establish a continuous fire' watch with backup fire suppression equipment for the unprotected area (s) within 1 hour; restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to. the Commission pursuant to Specification 6.9.7 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.7.11.3 The Halon system shall be demonstrated OPERABLE: a. At least once per 6 months by verifying each Halon storage tank weight and pressure. b. At least once per 18 months by 1 Verifying the s, stem, including associated ventilation dampers, would actuate automatically to a simulated test signal. 2 Verifyir.g the OPERABILITY of the manual initiating 1 system. 3. Performance of a flow test through headers and nozzles to assure no blockage. CP,YSTAL RIVER - UNIT 3 3/4 7-44

. /. m PLANT SYSTEMS-F, IRE HOSE STATIONS LIMITING CONDITIONS FOR OPERATION 3.7.11.4 The fire hose stations shown in Table 3.7-5 shall be'0PERABLE. APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations.is required to be OPERABLE. ACTION: a. With one.or more the fire hose stations shown in Table 3.7-5 inoperable, route an. additional equivalent capacity fire hose to the unprotected area (s) from an OPERABLE hose station within 1 hour. b. .The provisions of Specifications 3.'0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.7.11.4 Each of the fire hose stations shown in Table 3.7 5 shall be deconstrated OPERABLE: a. At least once per 31 days by: l. Visual inspection of the station to assure all required equipaent is at the station, and 5. At least once per 18 months by: 1. Removing the hose for inspection and re-racking, and 1 2. Replacement of all degraded gaskets in couplings. c. At least once per 3 years by: 1. Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage. 2. Conducting a hose hydrostatic test at a pressure at least 50 psig greater than the maximum pressure available at that hose station. CRYSTAL! RIVER UNIT 3 3/4 7-45 +

n.,

..73 ( g. w ~ TABLE 3.7-5 . FIRE HOSE STATIONS

Hose Reel.

Hose Reel-Location Valve flo. 1. Control Complex - a. Elevation 134' l. Zone 4.(Entrance to Cable Spreading Room) FSV-253-2. . Turbine Building Elevation 145' a. l. Entrance to Control Complex ' FSV-155'- 3. Intermediate Building a. Elevation 95' l. - Zone 3 (Steam Driven Emergency Feedwater FSV-170 Pump) .b. Elevation 119' l. Zone 2 (Reactor Building Industrial Cooler FSV-169 Circulating Pumps) 2. Zone 5 (Containment Personnel Airlock) FSV-134 4 Auxiliary Building a. Elevation 95' 1. Zone 1. (corridor outside Chem-Rad Area) FSV-135 2. Zone 5 (ES MCC 3A1) FSV-143 3. Zone 13 (Elevator) FSV-138 4 Zone 17 (fluclear Services Sea Water Pumps) FSV-139 b. Elevation 119' ~1 Zone 18 (Elevator) FSV-137 2. Zone 23 (Es MCC 3 A B) FSV-142 3. Zone 26 (Waste Compactor) FSV-140 -e. Elevation 143' 1 Zone 9 (Entrance to Charcoal Filter Room) FSV-131 d. Elevation 162' 'l. Zone 1 (florth of Spent Fuel Pools) FSV-136 2. ~ Zone 3-(Elevator)- FSV-133

n.; PLANT SYSTEMS 3/4.7.12 PENETRATION FIRE BARRIERS LIMITING CONDITIONS FOR OPERATION ~3.7.12 ~ All penetrat: 1n fire -barriers protecting safety related areas shall be functional. AP_PLICABILITY: At all times. ACTION: a. With one or more of the above required penetration fire barriers non-functional, establish a continuous fire watch on at least one side of the affected penetration within 1

hour, b.

The provisions of Specifications 3.0.3 and 3.'0.4 are not applicable. SURVEILLANCE RE0VIREMENTS 4.7.12 Each of the above required penetration fire barriers shall be verified to be functional by a visual inspection; a. At least once per 18 months, and b. Prior to declaring a penetration fire barrier functional following repairs or maintenance. u i

RYSTA8. RIVER - UNIT 3 3/4 7-47 i

3 -3. ~~s. 3/4 3 ' INSTRUMENTATION BASES REMOTE SHUTDOWN INSTRUMENTATION (Continued) HOT STANDBY of the facility from locations. Outside of the control room. This capability =is required in the event control room habitability is lost and is consistent with General: Design Criterion 19 of Appendix "A", 10 CF9 50. 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that suf-ficient in#ormation is available on selected plant parameters to monitor and assess these variables following an accident. This capability. is consistent with the recammendations of Regulatory Guide 1.97, "Instru-mentation -for Light-Water Cooled Nuclear Power Plants to assess Plant Conditions During and Following an Accident", December 1975. 3/4.3.3.7 FIRE DETECTION INSTRUMENTATION The OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program. In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is returned to service. . CRYSTAL RIVER - UNIT 3' B 3/4 3-3

p h-h q l ~ PLANT SYSTEMS-BASES 3/4.7.I0 SEALED' SOURCE CONTAMINATION The limitations on removable contamination for.ources requirinq leak testing', including alpha emitters,-is based on 10 CFR 70.19(c) limits for plutonium'. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values. 3.4.7.11-FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that ade-quate fire suppression capability is available to can'ine and extinguish fires occurring in any portion of the, facility where safety related equipment is located. The fire suppression system consists of the water system, deluge and sprinklers, hose stations and Halon. 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 inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the affected equipment can be restored to service. In the event that the fire suppression water system becomes in-operable, immediate 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 ot the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant. j l l 3/4.7.12 PENETRATION FIRE BARRIERS t l The functional integirty of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishmen+.. The penetration fire barriers are a passive element in the facility fire protection program and are subjec+' -o periodic inspection. During periods of time when the barriers are not functional, a fire watch patrol is required to be maintained in the vicinity of the affected barrier until the barrier is restored to functional status.

  • CRYSTALRIVER - UNIT 3 8 3/4 7-6 Amendment No.

L.--

.S ) / 6.0' ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Nuclear Plant Manager shall be responsible for overall facility operation and shall-delegate in writing the succession-to this responsibility during his absence. 6.1.2 The Nuclear Plant Manager shall be responsible for an annual fire protection inspection which shall be performed utilizing either qualified offsite licensee personnel or an outside fire protection firm. The inspection shall consist of: a) an inspection of safety-related areas of the Plant to verify that they are in conformance with the fire hazards analysis; and b) a review of the Fire Brigade organization, training, and drills to verify their conformance with the requirements of Section 27 of the NFPA Code-1976. 6.1.3 The Nuclear Plant Manager shali De' responsible for an inspection nf the fire protection program to be performed by a qualified outside fire consultant at least once per 36 months. 6.2 ORGANIZATION OFFSITE

6. 2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on figure 6.2-2 and: a. Each on duty shif t shall be composed of at least the minimum shift crew composition shown in Table 6.2-1. b. At least one. licensed Operator shall be in the control room when fuel is in the reactor. c. At least two licensed Operators shall be present. in the control rnom during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips. d. Aa individual qualified in radiation protection procedures shall be on site when fuel is in the reactor. e. All CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation, f. A Fire Brigade of at least 5 membersshall be maintained onsite at all times. This excludes 5 members of the minimum shif t crew necessary for safe shutdown of the plant and personnel required for other essential functions. CRYSTAL RIVER - UNIT.3 6-1 AmendmentNo.)I,

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  • T ltANAGER SUPERVISOR r-PROT ECTION ENGINEER SDL

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7 e. II ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 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 the Radiation Protection Engineer.who shall meet or exceed the qualifications of Regulatory Guide 1.8, September,1975. 6.4 TRAINING 6.4.1 A retraining and replacemen't training program for the facility staff shall be maintained under the direction of the Assistant Nuclear Plant Manager 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 Plant Manager and shall meet or exceed the requirements of Section 27 of the NFPA Code-1976. I 6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC) FUNCTION 6. 5.1.1 The Plant Review Committee shall function to advise the Nuclear Plant Manager on all matters related to nuclear safety. COMPOSITION 6.5.1.2 The Plant Review Committee shall be composed of the: Chairman: Assistant Nuclear Flant Manager Member: Operations Supervisor Member: Technical Support Engineer Member: Maintenance Engineer Member: Chemistry and Radiation Protection Engineer ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PRC Chairman to serve on a temporary basis; no more than two alternates shall_ participate as voting members in PRC activities at any one time. MEETTNG FREQUENCY 1 6.5.1.4 The PRC shall meet at least once per calendar month and as convened by the PRC Chariman or his designated alternate. j CRYSTAL RIVER - UNIT 3 6-5 AmendmentNo./,

y x l ADMINISTRATIVE CONTROLS REVIEW (Continued) 9 Events requiring 24 hour written notification to the Commission. h. All recognized indications of an unanticipated-deficiency in some aspect of design or operation of safety related structures, systems, or components. i. Reports and meetings minytes of.the Plant Review Committee. AUDITS 6.5.2.9 Audits of facility activities shall be performed under the cognizance of the NGRC. These audits shall encompass: a. The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months. b. The performance, training and qualifications of the entire facility staff at least once per 12 months. c. The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months. d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months. e. The Facility Emergency Plan and implementing procedures at least once per 24 months. f. The Facility Security Plan and implementing procedures at least once per 24 months. .g. The facility fire protection program and implementing procedures at least once per' 24 months. h. Any other area of facility operation considered appropriate by the NRCC or the Senior Vice President Engineering and Construction. AUTHORITY 6.5.2.lb The NGRC shall report to and advise the Senior Vice President- ~ Engineering and-Construction on those areas of responsibility specified in Sections 6.5.2.8 and 6.5.2.9. . CRYSTAL RIVER - UNIT 3 6-lb' AmendmentNo.I,

4 m s ADMINISTRATIVE CONTROLS-6.7' SAFETY LIMIT VIOLATION 6.7.1. The following actions shall.be taken in the event a Safety' Limit is violated: The facility shall be placed in at 'least H0T STAtlDBY within a. one hour. b. The Safety ' Limit violation shall'. be reported to the Commission, the Director-Power Produttion and to the flGRC within.24 hours, c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PRC. This. report shall describe (1) applicable circumstances preceding the violation, (2) effects-of the violation upon facility components, systems. or structures, and (3) corrective action taken to prevent recurrence. d. The Safety Limit Violation Report shall be submitted to the Commission, the flRGC and the Director-Power Production within 14 days-of the violation. 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below: a'. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, flovember,1972. b. Refueling operations. l c. Surveillance and test activities of safety related equipment. d. Security Plan implementation. e. Emergency Plan implementation, f. Fire Protection Program implementation. l 6.8.2 Each procedure and administrative policy of 6.8.1 above, and j changes thereto, shall.be reviewed by the PRC'and approved by the fluclear Plant Manager prior to implementation and reviewed periodically as set _ forth in administrative procedures. CRYSTAL RIVER - UtlIT 3 6-12 Amendment flo. jif,

~ ADMINISTRATIVE CONTROLS occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete. explanation of the circumstances surrounding the event. a. . Reactor protection. system or engineered safety feature instru-ment settings which are found to-be less conservative than those established by the, technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems. b. Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation. c. 0bserved inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems. d. Abnormal degradation of systems other than those specified in 6.9.1.8.c above, designed to contain radioactive material resulting from the fission process. SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement, Region II, within the time period spec-ified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applic-able reference specification: ~ a. ECCS Actuation, Specification 3.5.2 and 3.5.3. b. Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3. c. Inoperable Meteorological Monitoring Instrumentation, Spec- -i fication 3.3.3.4. d. Seismic event analysis, Specification 4.3.3.3.2. e. Inoperable Fire Detection l',onitoring Instrumentation. Specification 3.3.3.7. f. Inoperable Fire Suppression System, Specifications 3.7.11.1, 3.7.11.2, 3.7.11. 3, and 3.7.11.4. CRYSTAL RIVER - UNIT 3 6-17 Amendment No.}}

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