ML19308D567

Tech Spec Change Request 4 Re Tech Specs 3.4.2 Through 3.4. 9,revising Power Distribution Limits,Instrumentation,Rcs, Plant & Electrical Power Sys & Refueling Operations

ML19308D567
Person / Time
Site:	Crystal River
Issue date:	07/11/1977
From:	FLORIDA POWER CORP.
To:
Shared Package
ML19308D566	List: ML19308D565 ML19308D567
References
NUDOCS 8003030741
Download: ML19308D567 (26)

Text

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. . Technical Sp"cification Change Request No. 4 O The following discussion of changes to the sample Fire Protection Technical Specifications are limited to the specifications where a sample Specification was changed or where an item was added. These changes and additions are consistent with the Fire Protection Program Review, Crystal River 3, June 1977. Housekeeping changes and " fill-in-the-blanks" are not addressed.

a) Crystal River 3 Technical Specification 3.7.ll.1.b - Separate water supplies are not required at CR3. The fire protection water supply system criterion are met with the use of only one fire water storage tank (Fire Protection Program Review, Section 6.E.2).

b) CR3 Technical Specification 3.7.11.1, Action d - This action statement was added because the Fire Suppression Water System is not directly related to nuclear safety and the other Action statements provide time and reporting requirements so that adequate fire suppression capability for the protection of the nuclear plant is continued.

c) CR3 Technical Specification 4.7.ll.l.c - The Post Indicator Valves were deleted from this Specification because of the high failure rate of the linkage between the. valve and the indicator due to excessive surveillance. When the linkage fails, the indicator will cycle but the valve won't. .The cycling of these valves is covered by CR3 Technical Specification 4.7.ll.l .d on a 6 month surveillance interval.

d) CR3 Technical Specification 3.7.11.2, Action a - The establishment of frequent fire watch patrols in the fire zone with the inoperable equipment in conjunction with the fire detection instrumentation is adequate to provide the necessary fire suppression capability for the continued protection of the nuclear plant until the inoperable j equipment is returned to service.

l e) CR3 Technical Specification 3.7.11.2, Action c - This action statement was added because the Fire Suppression Water System is not directly related to nuclear safety and the other Action statements provide time and reporting requirements so that adequate fire suppression capability for 1.he protection of the nuclear plant is continued.

f) CR3 Technical Specification 4.7.ll.2.c - The option of a water flow test was added to give flexibility in the flow testing. The require-ment to verify that only the normally open nozzles are free of obstructions was added. No obstructions should develop in a normally closed nozzle and to inspect the sprinkler nozzles would entail destroying them, g) Sample Technical Specification 3/4.7.11.3 - This Specification was deleted from our proposed Technical Specificatica changes as there is no safety related equipment protected by the CO2 system at CR3.

8 0 08 0 3 0 ]L/ ('

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.h) CR3 Technical Specificatitn 3.7.11.3 - The requirement to verify tha weight of the halon storage tanks was deleted. Halon is a gas so its weight is dependent on the pressure and temperature in the storage tanks. Since the temperature in the Cable Spreading Room is constant and the pressure of the storage tanks will be verified, the verification of the weight of the storage tank is not essential in determining that the halon system is operable.

1) CR3 Technical Specification 3.7.11.3, Action a - The establishment of frequent fire watch patrols in the fire zone with the inoperable equipment in conjunction with the fire detection instrumentation is adequate to provide the necessary fire suppression capability for the continued protection of the nuclear plant until the inoperable equipment is returned to service.

j) CR3 Technical Specification 3.7.11.3, Action c - This action statement was added because the Fire Suppression Water System is not directly related to nuclear safety and the other Action statements provide time and reporting requirements so that adequate fire suppression capability for the protection of the nuclear plant is continued.

k) CR3 Technical Specification 4.7.11.3.b.1 - The requirement to verify that the system actuates on a simulated test signal would empty our halon storage tanks each time the surveillance was performed.

Therefore, we will verify that the system would actuate on a simulated test signal.

1) Sample Technical Specification 4.7.ll.3.b.2 - This surveillance was deleted because CR3 does not have a halon system with a certral storage tank and headers and nozzles.to distribute the halon. CR3 does have storage tanks distributed throughout the Cable Spreading Room and each tank discharges its halon directly from the tank.

m) Sample Technical Specification 3/4.7.11.5 - This Specification was deleted from our proposed Technical Specification changes because there is no safety-related equipment protected by the fire hose stations at CR3.

n) CR3 Technical Specification 3.7.12, Action a - The establishment of frequent fire watch patrols in the fire zone with the inoperable equipment in conjunction with the fire detection instrumentation is adequate to provide the necessary fire suppression capability for the continued protection of the nuclear plant until the inoparable equipment is returned to service.

o) CR3 Technical Specification 4.7.12.2 - The surveillance requirement for a local leakage test to be performed prior to declaring a fire barrier penetration fire seal functional has been changed to a visual inspection. The fire barrier penetration fire seals used at CR3 and shown in the Fire Protection Program Review (Figure 5-10) can be verified to be functional by performance of a visual inspection.

e

.p) Sample Technical Specification 6.5.2.8.i - There is no Fire Protection Program and implementing procedures at CR3. See item s) for further discussion, q) Sample Technical Specification 6.5.2.8.j - The responsibility for the inspection was assigned to the Nuclear Plant Manager (CR3 Technical Specification 6.1.2). The audit of the inspection was retained by the NGRC (CR3 Technical Specification 6.5.2.9.g). The inspection will include fire protection activities but not loss prevention activities. There are no requirements for a loss prevention program so it is inconsistent to require an inspection of a nonrequired program.

r) Sample Technical Specification 6.5.2.8.k - This Specification was deleted from our proposed Technical Specification changes. It should not be a Technical Specification requirement to use outside personnel without the option of using qualified offsite licensee personnel as in Sample Technical Specification 6.5.2.8.J.

s) Sample Technical Specification 6.8.1.f - This Specification was deleted from our proposed Technical Specificati.on changes. CR3 has integrated the fire protection procedures into the applicable parts of the plant procedures manual (Fire Protection Progam Review, Section3.3). In addition, the necessary procedures are already required by CR3 Technical Specification 6.8.1.a: Appendix "A" of Regulatory Guide 1.33, November,1972. The applicable parts of this Regulatory Guide are items C.17, D.22, F.16, F.23, and H.2.a.8.

The other activities specifically referenced by CR3 Technical Specifications 6.8.1.b, c, d, and e are also covered by Regulatory Guide 1.33 but are specifically called out in FSAR, Section 12.4 as having their own set of separate procedures. Fire Protection is not singled out as such so the procedures were incorporated into the plant procedures manual where applicable.

. Technical Sp'ecification Change Request No. 4 Remove the pages listed below and insert the replacement pagss.

Pages to be Removed Replacement Pages I I& IA IV IV VII VII XII XII 1-6 1-6 3/4 3-40 3/4 3-41 3/4 7-38 3/4 7-39 3/4 7-40 i 3/4 7-41 3/4 7-42 3/4 7-43 B 3/4 3-3 B 3/4 3-3 B 3/4 7-6 B 3/4 7-6 6-1 6-1 6-2 6-2 6-3 6-3 6-5 6-5 6-10 6-10 6-13 6-13 1

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'INDEX DEFINZTIONS SECTION PAGE 1.0 DEFINITIONS DEFINED TERMS . . . . . . . . . . . . . . . . . . . . 1 -1 THERMAL POWER . . . . . . . . . . . . . . . . . . . . 1 -1 RATED THERMAL POWER . . . . . . . . . . . . . . . . . 1 -1 OPERATIONAL MODE. . . . . . . . . . . . . . . . . . . 1 -1 ACTION . . . . . . . . . . . . . . . . . . . . . . . 1 -1 OPERABLE - OPERABILITY. . . . . . . . . . . . . . . . 1-1 1 REPORTABLE OCCURENCE. . . . . . . . . . . . . . . . . 1-2 CONTAINMENT INTEGRITY . . . . . . . . . . . . . . . . 1-2 CHANNEL CALIBRATION . . . . . . . . . . . . . . . . . 1-2 CHANNEL CHECK . . . . . . . . . . . . . . . . . . . . 1-2 CHANNEL FUNCTIONAL TEST . . . . . . . . . . . . . . . 1-3 CORE ALTERATION . . . . . . . . . . . . ....... 1-3 SHUTDOWN MARGIN . . . . . . . . . . . . . . . . . . . 1-3 IDENTIFIED LEAKAGE. . . . . . . . . . . . . . . . . . 1-3 i

UNIDENTIFIED LEAKAGE. . . . . . . . . . . . . . . . . 1-4 PRESSURE BOUNDARY LEAKAGE . . . . . . . . . . . . . . 1-4 CONTROLLED LEAKAGE. . . . . . . . . . . . . . . . . . 1-4 QUADRANT POWER TILT . . . . . . . . . . . . . . . . . 1-4 00SE EQUIVALENT I-131 . . . . . . . . . . . . . . . . 1-4 5-AVERAGE DISINTEGRATION ENERGY . . . . . . . . . . . 1-4 STAGGERED TEST BASIS. . . . . . . . . . . . . . . . . 1-5 FREQUENCY NOTATION. . . . . . . . . . . . . . . . . . 1-5 AXIAL POWER IMBALANCE . . . . . . . . . . . . . . . . 1-5 CRYSTAL RIVER - UNIT 3 I

y SHIELD BUILDING INTEGRITY . . . . . . . . . . . . . . 1-5 REACTOR PROTECTION SYSTEM RESPONSE TIME . . . . . . . 1-5

- ENGINEERED SAFETY FEATURE RESPONSE TIME . . . . . . . 1-6 PHYSICS' TESTS.. . . . . . . . . . . . . . . . . . . . 1-6 FIRE SUPPRESSION WATER SYSTEM . . . . . . . . . . . 1-6 OPERATIONAL MODES (TABLE l.1) . . . . . . . . . . . . 1-7 FREQUENCY NOTATION (TABLE 1.2). . . . . . . . . . . . 1-8 CRYSTAL RIVER - UNIT 3 IA

)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS 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 g -F.............. 3/4 2-4 3/4.2.3 NUCLEAR ENTHALPY RISE ,

HOT CHANNEL FACTOR - Fds . . . . . . . . . . 3/4 2-6 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 Seismic Instrumentation. . . . . . . . . . . . . 3/4 3-28 Meteorological Instrumentation . . . . . . . . . 3/4 3-31 Remote Shutdown Instrumentation. . . . . . . . . 3/4 3-34 Post-accident Instrumenta cion. . . . . . . . . . 3/4 3-37 Fire Detection Instrumentation . . . . . . . . . 3/4 3-40 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS. . . . . . . . . . . . . . 3/4 4-1 3/4.4.2 SAFETY VALVES - SHUTDOWN . . . . . . . . . . . . 3/4 4-3 3/4.4.3 SAFETY VALVES - OPERATING. . . . . . . . . . . . 3/4 4-4 CRYSTAL RIVER - UNIT 3 IV

l LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 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 7-13 Decay Heat Closed Cycle Cooling Water System . 3/4 7-15 3/4.7.4 SEA WATER SYSTEM Nuclear Services Sea Water System. . . . . . . 3/4 7-16 Decay Heat Sea Water System. . . . . . . . . . 3/4 7-17 3/4.7.5 ULTIMATE HEAT SINK . . . . . . . . . . . . . . 3/4 7-18 3/4.7.6 FLOOD PROTECTION . . . . . . . . . . . . . . . 3/4 7-19 3/4.7.7 CONTROL ROOM EMERGENCY VENTILATION SYSTEM . . 3/4 7-20 3/4.7.8 AUXILIARY BUILDING VENTILATICN EXHAUST SYSTEM. 3/4 7-23 3/4.7.9 HYDRAULIC SNUBBERS . . . . . . . . . . . . . . 3/4 7-25 3/4.7.10 SEALED SOURCE CONTAMINATICN. . . . . . . . . . 3/4 7-35 3/4.7.11 FIRE SUPPRESSION SYSTEMS Water System . . . . . . . . . . . . . . . . 3/4 7-38 Deluge and Sprinkler Systems . . . . . . . . . 3/4 7-40 l Halon System . . . . . . . . . . . . . . . . . 3/4/7-42 3/4.7.12 FIRE BARRIER PENETRATION FIRE SEALS. . . . . . 3/4 7-43 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating. . . . . . . . . . . . . . . . . . . 3/4 8-1 Shutdown . . . . . . . . . . . . . . . . . . . 3/4 8-6 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribtuion - Operating. . . . . . . . . 3/4 8-7 A.C. Distribution - Shutdown . . . . . . . . . 3/4 8-9 D.C. Distribution - Operating . . . . . . . . . 3/4 8-10 D.C. Distribution - Shutdown . . . . . . . . . 3/4 8-12 1

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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 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 ULTIMATE HEAT SINK. . . . . . . . . . . . . . . . B 3/4 7-4 3/4.7.6 F000 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 BUILDING VENTILATION EXHAUST SYSTEM . . B 3/4 7-5 3/4.7.9 HYDRAULIC SNUBBERS. . . . . . . . . . . . . . . . B 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION . . . . . . . . . . . B 3/4 7-6

D 3/4.7.11 FIRE SUPPRESSION SYSTEMS. . . . . . . . . . . . . B 3/4 7-6 3/4.7.12 FIRE BARRIER PENETRATION FIRE SEALS . . . . . . . B 3/4 7-6 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES . . . . . . . . . . . . . . . . . . B 3/4 8-1 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEM. . . . . . . . . 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 CCMMUNICATIONS. . . . . . . . . . . . . . . . . . B 3/4 9-1 CRYSTAL RIVER - UNIT 3 XII I

DEFINITIONS' ENGINEERED SAFETY FEATURE RESPONSE TIME 1.25 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump dis-charge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

PHYSICS TESTS 1.26 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and

1) described in Chapter 13 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

FIRE SUPPRESSION WATER SYSTEM 1.27 A FIRE SUPPRESSION WATER SYSTEM shall consist of: a water source; pumps;and distribution piping with associated sectionalizing control or isolation valves. Such valves shall include yard hydrant curb valves, and the first valve ahead of the water flow alarm device on each sprinkler, hose standpipe or spray system riser.

CRYSTAL RIVER - UNIT 3 1-6

INSTRUMENTATION-FIRE-DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION l 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. <

l APPLICABILITY: At all times when safety related equipment in that fire detection zone is required to be OPERABLE.

ACTION: )

I With the number of OPERABLE fire detection instruments less than required ,

by Table 3.3.11:

a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, establish a fire watch patrol to inspect the zone with the inoperable instrument (s) at least once per hour, and

b. Restore the inoperable instrument (s) to OPERABLE status within 14 days or prepare and submit a special report to the Commission pursuant to Specification 6.9.2 within the next 10 days out-lining the cause of the malfunction and the plans 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:

a. At least once per 6 months by a CHANNEL FUNCTIONAL TEST, and

b. At least once per 12 months by performance of a Channel Calibration.

4.3.3.7.2 The circuitry associated with the detector alarms listed in Table 3.3-11 shall be demonstrated OPERABLE at least once per 62 days for all National Fire Protection Association (NFPA) Code 72D Class B supervised circuits.

CRYSTAL RIVER - UNIT 3 3/4 3-40

TABLE 3.3-11 FIRE DETECTION INSTRUMENTS MINIMUM DETECTORS OPERABLE DETECTOR LOCATION HEAT / SMOKE

1. Control Complex

a. Elevation 108'0"

1. Zone.4 (Plant Battery Room 38) NA/l

2. Zone 5 -(Plant Battery Room 3A) NA/1

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/1

6. Zone 9 (4160V Switchgear Bus Room 3A) NA/l ,

7. Zone 10 (Inverter Room 3B) NA/l

8. Zone 11 (Inverter Room 3A) NA/l 1

b. Elevation 124'0" i

1. Zone 5 (Control Rod Drive Equipment Room) NA/2

2. Zone 7 (480V Switchgear Bus Room 3B) 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 38 (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.Equicment Room) NA/S I

2. Zone 4 (HVAC Emergency Equipment 38) NA/l l

3. Zone 5 (HVAC Emergency Equipment 3A) NA/l

2. Auxiliary Building

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/NA

3. Zone 27 (Emergency Diesel Generator Room 38) 5/NA

4. Zone 28 (Emergency Diesel Generator. Room 3A) 5/NA CRYSTAL RIVER - UNIT 3 3/4 3-41

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~ . - - - - - - - - - - - - - - - - -

4 PLANT SYSTEMS 3/4.7.11 FIRE SUPPRESSION SYSTEMS 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 gpm. with their discharge aligned to the fire suppression header.

b. A water supply with a minin..im contained water volume of 345,000 gallons.

c. ' Automatic initiation logic for each fire pump.

APPLICABILITY: At all times.

ACTION:

a. With less than the above required equipment, restore the in-operable equipment to OPERABLE status within 7 days or prepare and submit a Special Report to the Ccmmission pursuant to Specification 6.9.2 within the next 10 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system.

b. With no FIRE SUPPRESSICN WATER SYSTEM OPERABLE, within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:

1. Establish a backup FIRE SUPPRESSION WATER SYSTEM.

2. Notify the Commission pursuant to Specification 6.9.2 outlining the actions taken and the plans and schedule for restoring the system to OPERABLE status,

c. Restore the FIRE SUPPRESSION WATER SYSTEM to OPERABLE status within 14 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the system to OPERABLE status.

d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

CRYSTAL RIVER - UNIT 3 3/4 7-38 m >

1 .

' PLANT SYSTEMS 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 water supply contained water 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 recircu-lation flow.

c. At least once per 92 days by cycling each testable valve except Post Indicator Valves through one complete cycle.

d. At least once per 6 months by cycling each Post Indicator Valve through one complete cycle.

e. At least once per 18 months:

1. By performing a system functional test which includes simulated automatic actuation of the system throughout its operating sequence and verifying that each auto-matic valve in the flow path actuates to its correct position. ,

2. By verifying that each pump develops at least 2000 gpm at a discharge pressure of > 115 psig.

f. At least once per 3 years by performing flow tests of the system in accordance with Chapter 5, Section 11 of Fire Protection l Handbook,14th Edition (January,1976) published by National i Fire Protection Association.

T 1

CRYSTAL RIVER - UNIT 3 3/4 7-39 l

1

' 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: At all times when safety related equipment in the respective fire zone is required to be OPERABLE.

ACTION:

a. With a deluge or sprinkler system inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone with the inoperable system at least once per hour.

b. Restore the system to OPERABLE status within 14 days or prepare and submit a Special Report to the Comission pursuant to Specification 6.9.2 within the next ten days outlining the cause of inoperability and the plans for restoring the system to OPERABLE status,

c. The provisions of Specifications 3.0.3 and 3.0.4 are not j applicable.

SURVEILLANCE REOUIREMENTS 4.7.11.2 The deluge and sprinkler systems shall be demonstrated to be OPERABLE:

a. At least once per 92 days by cycling each testable valve ,

through one complete cycle.

b. At least once per 18 months:

1. By performing a system functional test which includes simulated automatic actuaton of the system and verifying that the automatic valves in the flow path actuate to their correct positions.

2. By inspection of spray headers to verify their integrity.

3. By inspection of each nozzle to verify no blockage.

c. At least once per 3 years by performing an air flow test or a water flow test through each deluge / sprinkler header and verifying each deluge / sprinkler nozzle that is normally open is' unobstructed.

CRYSTAL RIVER - UNIT 3 3/4 7 :

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_ TABLE 3.7-4 DELUGE AND SPRINKLER SYSTEMS y SYSTEM LOCATION r-g 1. AliFL-1 Deluge System Auxiliary Building, Elevation 143'0", Zone 11 (Main Filter Exhaust Room)

~

h 2. AllFL-2A Deluge System Auxil'iary Building, Elevation 143'0", Zone 11 (Main Filter Exhaust Room) '

g

3. AliFL-2B Deluge System Auxiliary Building, Elevation 143'0", Zone 11 (Main Filter Exhaust Room)

[. 4. AllFL-2C Deluge System Auxiliary Building, Elevation 143'0", Zone 11 (Main Filter Exhaust' Room)

5. AliFL-20 Deluge System Auxiliary Building, Elevation 164'0", Zone 5 (Main Filter Exhaust Room)

6. AllFL-4A Deluge System Control Complex, Elevation 164'0", Zone 5 (HVAC Emergency Equipment 3A)

7. 'AllFL-4B Deluge System Control Complex, Elevation 164'0", Zone 4. (llVAC Emergency Equipment 38)

8. AliFL-15 Deluge System Auxiliary Building, Elevation 95'0", Zone 34 (Nuclear Sampling Room)

9. Emergency Diesels Deluge Auxiliary Building, Elevation 119'0", Zones 27 and 28

. 7' t

s PLANT ~ SYSTEMS j

I HALON SYSTEM LIMITING CONDITION FOR OPERATION 3.7.11.3 The Halen system in the Cable Spreading Room (Control Complex, Elevation 134'0") shall be OPERABLE with the storage tanks having at least 90% of full charge pressure.

APPLICABILITY: At all times ACTION:

a. With the Halon system inoperable within I hour establish a ,

fire watch patrol to inspect the Cable Spreading Room at least  !

once per hour.

b. Restore the system to OPERABLE status within 14 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of inoperability and the plans for restoring the system to OPERABLE status.

c. 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 92 days by verifying each Halon storage tank pressure, l

b. At least once per 18 months by

1. ' Verifying the system, including associated ventilation dampers, would actuate automatically to a simulated test signal.

2. Verifying the OPERABILITY of the manual initiating system.

CRYSTAL RIVER - UNIT 3 3/4 7-42

PLANT SYSTEMS 3/4.7.12 FIRE BARRIER PENETRATION FIRE SEALS LIMITING CONDITIONS FOR OPERATION 3.7.12 All fire barrier penetration fire seals protecting safety related areas shall be functional.

APPLICABILITY: At all times.

ACTION:

a. With a fire-barrier penetration fire seal non-functional, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect at least one side of the affected penetration at least once per hour.

b. The provisions of 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.12.1 Fire barrier penetration fire seals shall be verified to be

=

functional by a visual inspection;

a. At least once per 18 months, and

b. Prior to declaring a fire barrier penetration fire seal functional following repairs or maintenance.

4.7.12.2 Fire barrier penetration fire seals that perform a pressure sealing function shall be verified to be functional by performance of a visual inspection prior to declaring a fire barrier penetration fire seal functional following repairs or maintenance.

CRYSTAL RIVER - UNIT 3 3/4 7-43

n -. -

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 CFR 50.

3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with -the recommendations of Regulatory Guide 1.97, " Instrumentation 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 instrumentaion 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 RIVFP - UNIT 3 B 3/4 3-3

o, 'd.

PLANT-SYSTEMS BASES .

3/4.7.10 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requirin leak testing, including alpha emitters, is based on 10 CFR 70.39(c) g 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 confine 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, and Halon. The collective capability of the fire supression 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 to 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.

3/4.7.12 FIRE BARRIER PENETRATION FIRE SEALS l

The functional integrity of the fire barrier penetration fire seals ensures that fires "ill be confined or adequately retarded frcm spreading to adjacent portic..s of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The fire barrier penetration fire seals are a passive element in the facility fire protection program and are subject to periodic inspection.

During periods of time when the seals are not functional, a fire watch patrol is required to be maintained in the vicinity of the affected seal until the seal is restored to functional status.

CRYSTAL RIVER - UNIT 3 8 3/4 7-6

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 sa 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.

6.2 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 shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b. At least one licens'ed Operator shall be in the control rocm when fuel is in the reactor,

c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

d. An 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 1 member shall be maintained onsite at all times. This excludes 5 members of the minimum shift crew necessary for safe shutdown of the plant.

CRYSTAL RIVER - UNIT 3 6-1

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ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 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 replacement 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 reccmmendations of Section 5.5 of ANSI N18.1-1971 and Apper. dix "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.

6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRCl FUNCTION 6.5.1.1 The Plant Review Committee shall function to advise the Nuclear Plant Manager on all matters related to nuclear safety.

I COMPOSITION 6.5.1.2 The Plant Review Committee shall be composed of the:

Chairman: Assistant Nuclear Plant Manager Member: Operations Supervisor Member: Technical Support Engineer Memoer: 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.

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

CRYSTAL RIVER - UNIT 3 6-5 i

ADMINISTRATIVE CONTROLS REVIEW (Continued)

g. Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Ccmmission.

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 minutes 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 Facf'.ity Emergency Plan and implementing proced,;res at .

least once per 24 months. i

f. The Facility Security Plan and implementing procedures at least once per 24 months.

g. The facility fire protection program and procedures at least once per 12 months l

h. Any other area of facility operation considered appropriate by the NRCC or the Senior Vice President Engineering and Construction.

AUTHORITY 6.5.2.10 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 6-10

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ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a. The intent of the original procedure is not altered.

b. The change is approved by two members of the plant management j staff, at-least one of whom holds a Senior Reactor Operator's License on the unit affected.

c. The change is documented, reviewed by the PRC and approved by the Nuclear Plant Manager within 14 days of implementation.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCE REPORTS 6.9.1 Information to be reported to the Commission, in addition to the reports required by Title 10, Code of Federal Regulations, shall be in accordance with the Regulatory Position in Revision 4 of Regulatory Guide 1.16, " Reporting of Operating Information - Appendix "A" Technical Specifications."

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 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.

b. Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

c. Inoperable Meteorological Monitoring Instrumentation, Specifi-cation 3.3.3.4.

d. Seismic event analysis, Specification 4.3.3.3.2.

e. Inoperable Fire Detection Monitoring Instrumentation, Specification 3.3.3.7.

f. Inoperable Fire Suppression System, Specifications 3.7.11.1, 3.7.11.2 and 3.7.11.3.

CRYSTAL RIVER - UNIT 3 6-13