ML20246D213

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Proposed Tech Specs,Deleting Fire Protection & Remote Shutdown Instrumentation Requirements
ML20246D213
Person / Time
Site: Crystal River 
Issue date: 08/18/1989
From:
FLORIDA POWER CORP.
To:
Shared Package
ML20246D212 List:
References
NUDOCS 8908250294
Download: ML20246D213 (26)
v • d • e


Text

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p INDEX L

LIMITING' CONDITIONS FOR OPERATION AND SURVEILLANCE'RE0VIREMENTS l

'SECTION PAGE

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'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 -Fg-3/4 2-4' 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - FN 3/4, 2-6 l

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. 3/4.'2. 4 -

QUADRANT _ POWER TILT 3/4 2-8 j

3/4.2.5 DNB PARAMETERS 3/4 2-12 i

3/4.3 INSTRUMENTATION l

'3/4.3.1-REACTOR PROTECTION SYSTEM INSTRUMENTATION 3/4 3-1 i

3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4 3-9 3/4.3.3 MONITORING INSTRUMENTATION-I

-Radiation Monitoring Instrumentation 3/4 3-22 j

Incore Detectors 3/4 3-26 1

Seismic Instrumentation 3/4 3-28

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Meteorological Instrumentation 3/4,3-31 Post-accident Instrumentation 3/4 3-37 l

Radioactive Liquid Effluent Monitoring Instrumentation 3/4 3-42 1'l Radioactive Gaseous Effluent Monitoring Instrumentation 3/4 3-47 K

Waste Gas Decay Tank - Explosive Gas Monitoring Instrumentation 3/4 3-53 j

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i CRYSTAL RIVER - UNIT 3 IV Amendment No.

I 8908250294 890818 PDR ADCaCK 05000302

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-i INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS h

SECTION

PAGE u.

3/4.7-PLANT'SYSTEN_S 3/4l7.2' 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 R00H 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' DELET,TD "i/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 7-49 Waste Gas System 3/4 7-51 Wute Solidification System 3/4 7-53 Waste Gas Decay Tank - Explosive Gas Mixture 3/4 7-54 CRYSTAL RIVER - cilT 3 VII Amendment No.

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BASES SECTIONI PAGE 3/4.7

-PLANT SYSTEMS

- 3/4.7.1)

TURBINE CYCLE B 3/4 1-3/4.7.2~

STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION B 3/4.7-3' 3/4.7.3.

CLOSED CYCLE COOLING WATER SYSTEM B3/4L7-3

.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 FLOOD PROTECTION B3/4 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 3/4.7.11 DELETED 3/4.7.12=

DELETED 3/4.7.13.1-WASTE GAS DECAY-TANKS B 3/4.7-7 L

3/4.7.13.2-LIQUID' WASTE TREATMENT 8 3/4 7-7 1

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 3/47.13.5 EXPLOSIVE GAS MIXTURE B3/4.7-8 l

- CRYSTAL RIVER - UNIT 3 XII Amendment No.

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i CRiSTAL RIVER - UNIT 3 3/4 7-47 Amendment No.

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6.0 ADMINISTRATIVE' CONTROLS 6.1 P,ESPONSIBILIll 6.1.1 The Director, Nuclear Plant Operations shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

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 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 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.

CRYSTAL RIVER - UNIT 3 6-1 Amendment No.

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' ADMINISTRATIVE CONTROLS e.

'All, CORE ALTERATIONS after the initial fuel loading'shall'be

-directly supervised by either a: licensed Senior Reactor.0perator

or Senior Reactor. Operator limited to Fuel Handling who-has no' other concurrent responsibilities during'this operation.

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

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4 ADMINISTRATIVE ~ CONTROLS 6.3 FACILITY STAFF OVALIFICATIONS 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-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 recommendations 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 (PRC)

FUNCTION 6.5.1.1 The Plant Review Committee shall function to advise the Director, Nuclear Plant Operations on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The Plant Review ComnIttee shall be composed of the:

Chairman:

Manager, Nuclear Plant Technical Support Member:

Nuclear Operations Superintendent Member:

Nuclear Maintenance Superiritendent j

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Member:

Asst. Mgr., Nuclear Plant Technical Support Member:

Nuclear Compliance Manager Member:

Nuclear Chemistry and Radiation Protection Supt.

Member:

Mgr. Nuclear Mech./Struct. Engineering Services Member:

Mgr. Nuclear Elect./I&C Engineering Services Member:

Nuclear Safety and Reliability Superintendent Member:

At Large (Designed by Chairman)

ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the FRC Chairman to serve on a temporary basis; no more than two alternates shall l

participate as voting members in PRC activities at any one time.

MEETING FRE0VENCY-6.5.1.4 The PRC shall meet at least once per calendar month and as convened l

by the PRC Chairman or his designated alternate.

1 CRYSTAL RIVER - UNIT 3 6-5 Amendment No.

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. ADMINISTRATIVE CONTROLS 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 l

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. specified for each report.

These~ reports shall be submitted

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' 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.

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'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.

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Dose due to radioactive materials 'in liquid effluents in excess of specified limits, Specification 3.11.1.2.

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Dose due t to noble gas' in gaseous effluents in excess of specified limits, Specification 3.11.2.2.

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Total calculated dose due to release of radioactive effluents exceeding twice the limits of Specifications 3.ll.1.2.a,

3. II.1.2.b, 3. ll.2.2.a, 3.11.2.2.b, 3.II.2.3. a, or 3.11.2.3.b (required by Specification 3.11.3).

1.

Dose due to Iodine-131, Tritium, and radioactive particulate with greater than eight day half-lives, in gaseous effluents in excess of specified limits,~ Specification 3.11.2.3.

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Failure to process liquid radwaste, in excess of limits, prior to release, Specification 3.7.13.2.

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Failure to process gaseous radwaste, in excess of limits, prior to release, Specification 3.7.13.3.

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Measured levels of radioactivity in environmental samplirg 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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-3/4.3 INSTRUMENTATION' BASES 3'/4 ' 3.3 MONITORING' 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-channels and 2) the' alarm or automatic action is initiated when the radiation level' trip setpoint-is exceeded.

3/4.3.3.2 INCORE DETECTORS The OPERABILITY of the 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 ad 3-2 for examples of acceptable minimum incore detector arrangements.

3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seisnic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of t a seismic event so v. hat the response of those features important to safety may be evaluated..This capability is required to permit comparison of the measured i

response to that used in the design basis for the facility. This

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instrumentation-is consistent with the recommendations of Safety Guide'12 Instrumentation for' Earthquakes", March 1971.

j 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION q

- The OPERABILITY 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 l

radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public. This instrumentation is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs",

'l February 1972.

3/4,3.3.5 DELETED p

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

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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.

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

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PLANT SYSTEMS ILASES 3/4.7.10 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.

3/4.7.11 DELETED 3/4.7.12 DELETED l

CRYSTAL RIVER - UNIT 3 B 3/4 7-6 Amendment No.

d,;

..'2.C.'(9)

E[gg 19mBCITM Florida Tower Computation shall implement and maintain in effect idl trwisions of the approved firo ptvbid.ian powicuu as described ;in.

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the-Final Safety Analysis W for the facility and as apptwed in the Safety Evaluation %hLs dated July 27, 1979, January 22, 1981,-

January 6,

1983, and ~ Mardt 16, 1988 ' subjtet to the followingL prcnisions:

1

'Iha licensee may mke changes to the agawed fire-i.

protection etwicou without prior apprwal of the Ocruission only if those ch nges would not adversely = affect ' the -

ability to achiev6 and maintain safe stratdown in the event.

'of a fire.

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