ML20066K034

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Proposed Tech Specs Deleting Fire Protection Requirements
ML20066K034
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 02/22/1991
From:
FLORIDA POWER CORP.
To:
Shared Package
ML20066K029 List:
References
NUDOCS 9102270068
Download: ML20066K034 (25)
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Text

TECHNICAL SPECIFICATION REPLACEMENT PAGES I

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l 180H 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 ,

3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR -F" 3/4 2 6 AH 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 J3/4.3.2- 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 Instrumentation 3/4 3-37 Radioactive Liquid Effluent Monitoring Instrumentation 3/4 3-42'-

Radioactive Gaseous Effluent Monitoring Instrumentation 3/4 3-47 Waste Gas Decay Tank - Explosive Gas Monitoring ,

Instrumentation 3/4 3-53 Toxic Gas System

- Chloride Detection 3/4 3-55

- Sulfur Dioxide Detection 3/4 3-56 CRYSTAL RIVER - UNIT 3 IV Amendment No.

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1E0.11 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS c

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 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 VENTILATION EXHAUST SYSTEM 3/4 7-23.

-3/4.7.9 ' HYDRAULIC SNUBBERS 3/4 7-25' 3/4.7.10' SEALED SOURCE CONTAMINATION 3/4 7-35 3/4.7.11- -DELETED 3/4.7 12- DELETED 3/4;7.13' =RADI0 ACTIVE WASTE SYSTEMS-Waste Gas Decay: Tanks 3/4 7-48 Liquid Radwaste Treatment System 3/4 7 Waste Gas System 3/4:7-51 Waste Solidification System 3/4 7-53 Waste Gas Decay Tank - Explosive Gas Mixture 3/4 7-54 g  : CRYSTAL RIVER - UNIT 3 VII Amendment No.

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ma BASES-SECTION PAGE 3.4.6- PLANT SYSTEMS 3/4.7.1 TURBINE CYlLE 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 3/4.7.6 ULTIMATE HEAT SINK B 3/4 7-4 3/4.7.6 FLOOD PROTECTION- B 3/4 7-4 14 - 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 3/4.7 11 DELETED 3/4.7.12- DELETEDE 3/4.7.13.1- WASTE GAS DECAY TANKS B 3/4 7-7 3/4.7.13.2c LIQUID WASTE TREATMENT B 3/4 7-7 3/4.7.13.3' WASTE GAS SYSTEM B 3/4 7-8 3/4.7.13.4- SOLID RADI0 ACTIVE WASTE B 3/4 7-8 13/4.7.13.5 EXPLOSIVE GAS MIXTURE B 3/4 7-8 i

CRYSTAL RIVER -' UNIT 3 XII Amendment No.

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TASLE 3.3-9-- . -

[ ' REMOTE SHUTDOWN M0 ITilING' INSTRUMENTATION MINIMUM.-

LREADOUT- ' MEASUREMENT. T'",NNELS ~

INSTRUMENT . LOCATION , l RANGE' UPERABLE_

1. - Reactor Trip Breaker *

.CRD switchgear room open-clase. 11per trip. breaker and -

Indication' 124 foot' elevation.

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-1 per secondary trip breaker .

2. Reactor Coolant: Remote' shutdown panel 120-920*F-- 1.per loop. -;
Temperature ~ Th '
3. Reactor CoolantLPressure- ' Remote shutdown' panel 2500 psig 1

-4. Pressurizer Level " Remote shutdown panel 320" H 2O 1 ,

5. Steam Generator Pressure' ' Remote. shutdown panel' 0-1200 psig 1 per steam generator
6. Steam Generator Level 1 Remote shutdown panel 0-150" H 2O 1 per steam generator j
7. Decay Heat Removal' . Remote shutdown panel ' '

0-300*F 1 per cooler

  • Temperature i
8. Mctor Driven Emergency  ? Intermediate' Building 0-2000 psig 1.per pump  :

Feedwater Pressure 95' foot' elevation ,

9. Nuclear Services Closed Auxiliary Building 0-300 psig 1

. Cycle Cooling Pumps ^95: foot elevation ,

Discharge Pressure

10. Nuclear. Services Closed l Auxiliary Building 0-250*F 1 per cooler -
Cycle Cooling Cooler' 95 foot 1 elevation '?
Outlet
Temperature #

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! I a-CRYSTAL' RIVER-- UNIT.3 3/4 3-35~ Amendment No.

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CRYSTAL RIVER UNIT 3 3/4 3 41 Amendment No.

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CRYSTAL RIVER.- UNIT 3 3/4 7-45 Amendment No.

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-CRYSTAL RIVER.- UNIT 3 3/4 7-46' Amendment'No.-

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CRYSTAL RIVER ~- UNIT 3.. 3/4 7 47 Amendment No.

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6.0 ADMINISTRATIVE CONTR0' S f.1 RESPONSIBillTY 6.1.1- The Director, Nuclear Plant Operations shall be responsible for overall facility operation and shall delegate in writing the succession to this I responsibility during his absence. l 6 , 2 . . .. . . ORGANIZAT10N OFFSITE i 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall i,e established for facility operation and

- corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant,

a. Lines of authority, responsibility, and communications shall be established and defined from the highest management levels through '

intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as Appropriate, in the form of organiztlion charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the final Safety Analysis Report,

b. The Director, Nuclear Plant Operations shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operatioa and maintenance of the plant. l
c. The Vice President, Nuclear Operations shall have -corporate responsibility for. overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure-nuclear safety,
d. The individuals who train the operating staff and those who carry out health physics _ and quality assurance functions may report to the appropriate o M ite manager; however, they shall have sufficient organi;ational freedom to ensure their independence from operating pressures.

CRYSTAL RIVER - UNIT-3 61 Amendment No.

6.0 ADMINISTRATIVE CONTROLS 6.2.2 FACILITY staff

a. Each on duty shift shall be composed of at least the minimum shif t 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, i

s 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 af ter 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. DELETED
g. The shift supervisors shall hold a senior reactor operator Itcense.

The operators required to have a license shall hold at least a reactor-operator-license.

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. CRYSTAL RIVER'- UNIT 3 6 la Amendment No.

s ADMINISTRATIVE CONTROLS 623 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANS1 N18.1-1971 for comparable positions, except for the Chemistry and Radiation Protection Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the Operations Technical Advisor, who shall have a Bachelor's degree, or the 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 Vice President, Nuclear Operations and shall meet or exceed the requirements and recommer.dations of Section 5.5 of ANSI N18.1 1971 and 10 CFR Part 55.

6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC1 IEll.0ff 6.5.1.1 The Plant Review Committee shall function to advise the Director, Nuclear Plant Operations (DNP0) on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Plant Review Committee. shall be composed of nine members and one chairman from Nuc1 car Operations Supervisory Personnel responsible for the !

following areas: operations, health physics, security, maintenance, '

modifications, engineering,' nuclear safety, and quality. These positions will be designated by the DNP0 in Administrative Procedures.

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.

EETING FRE0MDiCl 6.5.1.4 The PRC shall meet at least once per calendar month and as convened by the PRC Chairman or his designated alternate. ,

I CRYSTAL. RIVER UNIT 3 65 Amendment No.

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ADMINISTRATIVE CONTROLS i SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement, Region 11, within the time period specified for each report. These reports shall be submitted covering the activities identified below. A separate Licensee Event Report, when required by 10 CFR 50.73(a), need not be submitted if the Special Report meets the requirements of 10 CFR 50.73(b) in addition to the requirements of the applicable referenced 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 Specification 3.3.3.4.
d. Seismic event analysis, Specification 4.3.3.3.2.
e. Deleted.
f. Specific Activity, Specification 3.4.8.
g. Results of Steam Generator _ Tube Inspection. Specification 4.4.5.5.b.
h. Deleted, t
i. Dose due to radioactive materials in liquid effluents in excess of specified limits, Specification 3.11.1.2.

J. Dose' due to noble gas in gaseous effluents in excess of specified limits, Specification 3.11.2.2.

k. Total calculated dose due to release of radioactive effluents exceeding twice the limits of Specifications 3.ll.1.2.a, 3 ll.l.2.b, 3.ll.2.2.a, 3.ll.2.2.b, 3.ll.2.3.a, or 3.ll.2.3.b (required by Specification 3.11.3).
1. Oose due to lodine 131, Tritium, and radioactive particulates with greater than eight day half lives, in gaseous effluents in excess of specified limits, Specification 3.11.2.3.
m. Failure to process liquid radwaste, in excess of limits, prior to-release, Specification 3.7.13.2.

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n. Failure. to process gaseous radwaste, in excess of limits, prior to release, Specification _3.7.13.3.
o. Measured levels of radioactivity in environmental sampling medium in

- excess of the reporting levels of Table 3.12-2, when averaged over any quarterly sampling period, Specification 3.12.1.1.

CRYSTAL-RIVER - UNIT 3' 6-17 Amendment No.

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"ASES  :

3/4.3.3 MON 110 RING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION.

The OPERABILITY of the radiation monitoring channels ensures that 1) the  !

radiation levels are continually measured in the areas served by the individual

-chanrkls and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded. .i The CHANNEL CAllBRATION of the Reactor Building High Radiation Monitor is performed la illy for at least one decade below 10 rad /hr. 10 iltu calibration by electronic signal substi_tution is used for all range decades above 10 rad /hr.

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}/4.3.3.2 INCORE DETECTORS The OPERABILITY of th'e incore detectors ensures that the measurements obtained- from use of .this system accurately represent the spatial neutron flux distribution of the reactor core. See Bases Figures 3-1 and 3-2 for examples of acceptable minimum incore detector arrangements.

3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient '

capability -is available to promptly determine the magnitude of a seismic event so that .the response of those features important to safety may be evaluated. This capability is required to permit comparison of the measured response to that used in the desi n basis for the facility. This instrumentation is consistent with-the recommen ations of Safety Guide 12 " Instrumentation for Earthquakes", March 1971.

3/_f.3.3.4 METEOROLOGICAL INSTRUMENTATION -

. Thu OPERABillTY 'of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses

-to the public as'a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the needs for initiating protective measures to protect the health and safety. of the - public. This s instrumentation is consistent with the recommendations of Regulatory Guide 1.23 "0nsite Meteorological- Programs", February 1972.

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTAllQH The OPERABILITY of- the remote shutdown ..mu a.entation ensures that sufficient capability.is availefole to permit shutdown and ..aintenance of HOT STANDBY.

of the' facility from locations outside of the control room.

This capability is-required in the event control room capability is lost and is consistent with General '

Design Criterion 19 of Appendix "A", 10 CFR 50.

CRYSTAL RIVER - UNIT 3 B 3/4 3-2 Amendment.No'._

3/4.3 INSTRUMENTATION ,

BASES  :

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 DELETED c

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CRYSTAL RIVER - UNIT 3- fi3/4 3-3 -Amendment No.

EL6!il_11SIDiS BASES 3/4.7.10 SEALED SOURCE CONTAMINATION The lir.itations on removable contamination for sources requiring leak testing, includirg alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.

This limitation till ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.

3/4.7.11 DELETED 3/4.7.12 DELETED CRYSTAL RIVER - UNIT 3 8 3/4 76 Amendment No.

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LICENSE CONDITION f

2.C (9) FIRE PROTECTION Florida Power Corporation shall implement and maintain in effect all provisions of the approved fire protection program as described in the final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979, January 22, 1981, January 6,1983, July 18,1985 and March 16, 1988, subject to the following provisions:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achiave and maintain safe shutdown in the event of a fire.

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