ML20133D750

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Amend 84 to License DPR-72,correcting Errors & Inconsistencies & Clarifying Certain Radiological Effluent Tech Specs
ML20133D750
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 09/30/1985
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Florida Power Corp, City of Alachua, FL, City of Bushnell, FL, City of Gainesville, FL, City of Kissimmee, FL, City of Leesburg, FL, City of New Smyrna Beach, FL, Utilities Commission, City of New Smyrna Beach, FL, City of Ocala, FL, City of Orlando, FL, Orlando Utilities Commission, Sebring Utilities Commission, Seminole Electric Cooperative, City of Tallahassee, FL
Shared Package
ML20133D752 List:
References
DPR-72-A-084 NUDOCS 8510090166
Download: ML20133D750 (19)
v • d • e


Text

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UNITED STATES

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WASHINGTON, D. C. 20555

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FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEBRING UTILITIES COMMISSION SEMINGLE ELECTRIC COOPERATIVE, INC.

CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERAT!NG LICENSE Amendment No. 84 License No. OPR-72 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Florida Power Corporation, et al.

(the licensees) dated September 28, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-72 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 84 are hereby incorporated in the license.

Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

3 FOR THE NUCLEAR REGULATORY COMMISSION I' f 4

oh1 F. Stolz, Chief

{0 ating Reactors Branch #4 0

ision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: September 30, 1985 i

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l ATTACHMENT TO LICENSE AMENDMENT NO. 84 4

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FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 I

4 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness, f

Page s j

3/4 3-45 3/4 3-48 3/4 3-51 3/5 3-53 3/4 7-54 3/4 11-2 6-14b 1

6-17a 4

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TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTituMENTATION BURVEILLANCE H

6 CHANNEL CilANNEL SOURCE CilANNEL FUNCTIONAL INSTRUNENT CllECK CilECK g

CALIBRATION TEST hs 1.

GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE Auxiliary Bu!1 ding Liquid D*

P R(1)

M a-a.

Radwaste Effluent Line u,j, (NH-L2) ta b.

Secondary Drain Tank De P

Liquid Effluent Line R(1)

M (RM-L7) 2.

FLOW RATE MEASURENENT DEVICES E'

Auxiliary Building Liquid D(2)

H.A.

R K.A.

a.

Radwaste Effluent Line b.

Secondary Drain Tank Liquid D(2)

N;A.

R K.A.

Effluent Line c.

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TABLE 4.3 (Continued)

TABLE NOTATION l

  • During periods of release.

I (1)

CHANNE CALIBRATION shall be performed using:

a.

One or more standards traceable to the National Bureau of Standards, or b.

Standards obtained from suppliers that. participate in measurement assurance activities with the National Bureau of Standards, or c.

Standards related to previous calibrations performed using (a) or (b) above.

(2)

CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

A CHANNEL CHECK shall be performed at least once per day on any day that continuous, periodic or batch releases are made.

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l CRYSTAL RIVER - UNIT 3 3/4 3-46 Amendment No. 69

INSTRUMENTATICN l

RADIOACTIVE GASEOUS EFFLUENT MONITOR 1NC INSTRUMENTATION LIMITING CONDITION FOR OPERATION i

3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with the effluent release isolation alarm / trip setpoints set to ensure that tha limits of Specification 3.11.2.1 are not exceeded. The setpoints shall be dete+ed in accordancs.with. the OFFSITE DOSE CALNION MANUAL (CDCi).

APPLICABILITY:

As shown in Table 3.3-13 ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required above, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel where applicable, or change the setpoint so that it is acceptably l

conservative, or declare the channel inoperable.

5.

Tith cne or more radioactive gaseous effluent monitoring instrumentation enannels inoperable, take the ACTION. gown in Table 3.3-13.

Exert best efforts to return the inoperable instrument (s) to OPERABLE status within 30 dayr If the affected instruments cannot be returned to OPERABLE status within 30 days, provide information on reasons for inoperability and lack of I

timely corrective action in the next Effluent and Waste Disposal Semiannua!

Report.

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

c.

d.

The reporting requirements of Specification 6.9.1.9.b are not applicable.

SURVFTLLANCE REOUIREMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation enannel shall be i

demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the i

MODES and frequencies shown in Table 4.3-9.

i CRYSTAL RIVER - UNIT 3 3/4 3-47 Arnend:nent flo.

69

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l TABLE 3.3-13 9

R ADIOACTIVE G ASEOtJS EFFLUENT MONITORING INSTRUMENTATION 5

MINIMUM CilANNELS APPLICABLE OPERADLE MODES ACTION

.-.N 1.

Waste Gas Decay Tank Monitor (RM.All) a.

Noble Gas Activity Monitor

  • 1 All MODES 24 E

b.

Effluent System Flow Rate Monitor i

All MODES 26

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2.

Reactor Building Purge Exhaust Duct Monitor (RM-AI) l a.

Noble Gas Activity Monitor i

1.

Operating Range

  • 1 27 ii. Mid Ranges 29 iii. liigh Range #

1 29 b.

lodine Sampler I

25 w

c.

Particulate Sampler I

1 d.

Elfluent System Flow Rate Monitor I

25 26 w

e.

Sampler Flow Rate Monitor 26 3.

Auxiliary Building and Fuel Itandling i

Area Exhaust Duct Monitor (RM-A2) a.

Noble Gas Activity Monitor 1.

Operating Range' All MODES 28 ii. Mid Range #

I 1, 2, 3 & 4 29 iii. liigh Range #

1 1, 2, 3 & 4 29 b.

lodine Sampler All MODES 25 g

c.

Particulate Sampler I

All MODES 25

.g d.

Effluent Systern Flow Rate Monitor i

All MODES 26 e.

Sampler Flow Rate Monitor All MODES 26

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  • Provides control room alarm and automatic termination of release.
  • During periods of reactor building purge.

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  1. There is no isolation setpoint or release termination function for this monitor. Alarm setpoints are determined by the appropriate system procedures.

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TAI 5LE 4.3 9 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

7.

CHANNEL MODES IN WHICH f

Y CilANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE

_" INSTRUMENT CHECK CIIECK CALII1 RATION TEST REQUIRED l

m M 1.

WASTE GAS DECAY TANK MONITOR (RM-AI!)

a. Noble Gas Activity P

P R(1)

M All MODES E

Monitor G

b. Effluent System Flow P

N.A.

R M

All MODES w

Rate Monitor 2.

REACTOR BUILDING PURGE i

EXilAUST DUCT MONITOR (RM-AI)

a. Noble Gas Activity Monitor 1.

Operating Range D

P R(1)

M 3

g

11. Mid Range W

M R(1)

M c

iii, High Range W

M R(1)

M 5

b. Iodine Sampler W

N.A.

N.A.

N.A.

w g

c. Particulate Sampler W

N.A.

N.A.

N.A.

d. Effluent System Flow D

N.A.

R M

Rate Monitor

c. Sampler Flow Rate D

N.A.

R M

Monitor i

3.

AUXILIARY BUILDING & FUEL HANDLING AREA EXilAUST DUCT MONITOR (RM-A2) l i

a. Noble Gas Activity i

k Monitor l

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Operating Range D

N.A.

R(1)

M All MODES g

11. Mid Range W

M R(1)

M 1, 2, 3, 4 t

lii. High Range W

M R(1)

M 1, 2, 3, 4 s

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b. lodine Sampler W

N.A.

N.A.

N.A.

All MODES iEr

c. Particulate Sampler W

N.A.

N.A.

N.A.

All MODES

d. Effluent System Flow D

N.A.

R M

All MODES Rate Monitor b

e. Sampler Flow Rate D

N.A.

R M

All MODES Monitor

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i TABLE 4.3-9 (Continued's 7;3js.,+. --~.,

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  1. During periods of Reactor Building Purge.

(1)

CHANNE. CALIBRATION shall be performed using:

i a.

One or more standards traceable to the National Bureau of Standards, or b.

Standards obtained from suppliers that participate in measurement assurance activities with the National Bureau of Standards, or

  • e Standards related to previous calibrations using (a) or (b) above.

c.

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CRYSTAL RIVER - UNIT 3 3/4 F32 Amendrent flo. 69

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INSTRUMENTATION WASTE GAS DECAY TANK - EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The Waste Gas Decay Tanks shat! have one hydrogen and one oxygen monitoring channel OPERABLE.

APPLICABILITY: ALL MODES.

ACTION:

a.

With the number of OPERABLE channels less than required above, operation of this system may continue, provided grab samples are collected and analyzed (1) at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations (2) at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations b.

If the affected channel (s) cannot be returned to OPERABLE status within 14 days, submit a special report to the Commission pursuant to Specification 6.9.2 within 30 days describing the reasons for inoperability and a schedule for corrective action.

c.

The provisions of 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 The Waste Gas Decay Tank explosive gas monitoring instrumentation shall be demonstrated operable by performing the CliANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION at the frequencies shown in Table 4.3-10.

CRYSTAL RIVER UNIT 3 3/4 3-33 Amendment No. $7,84

0 M

H TABI.E 4.3-10 b

=

NASTE GAS SYSTEM EXPLOSIVE GAS MONITORING INSTRilMENTATION

'8 SURVEII.E.ANCE REQtlIREME:4TS S

1 CilA13NEL CHANNEL CHANNEL ItlNCTIONAL

, INSTRINGENT CilECE CALIBRATION TEST N

1.

Hydrogen Monitors '

D O*

Y ue 2.

Oxygen Monitors.

D

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  • The CHANNEL CALIBRATION shall include the use of standa:-d gas samples containii g a no.ainals Hydrogen Monitora

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I volume percent hydrogen, balance nitrogen.

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a.

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b.

4 volume percent hydrogen, balance nitrogen.

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Oxygen Monitors I volume percent oxygen, balance nitrogen.

c.

d.

4 volume percent oxygen, balance nitrogen.

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_ _ -. - _ _ - - _ _.. =. _

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PLANT SYSTr%

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WASTE SOLIDIFICATION SYSTEM i

N LIMITING CCNDITION POR OPERATION I

3.7.13.4 The solid radwaste system shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and burial ground requirements.

APPLICABILITY:

At all times.

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ACTICN:

With the provisions of the PROCESS CONTROL PROGRAM not I~

a.

satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site.

I b.

The provisions of Specifications 3.0.3 and 3.0.4 are i

not applicable.

1 The reporting requirements of Specification 6.9.1.9.b c.

l are not applicable.

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sunvu LLANCE REQUIR. N S l-The PROCESS CONTROL PROGRAM shall be used to verify J

4.7.13.4 the SOLIDIFICATION of at least one representative test specimen j

from at least every tenth batch of each type of wet radioactive waste (e.g., filter sludges, spent resins, evaporator bottoms, i.

and boric acid solutions).

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CRYSTAL RIVER - UNIT 3 3/4 7-53 Arnendment No. 69 i

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O PLANT SYSTEMS WASTE GAS DECAY TANK - EXPLOSIVE CAS MITERt.

LIMITING CONDITION FOR OPERATION 3.7.13.3 The concentration of oxygen in any Waste Gas occay Tank shat? h. li : i:ed to ' m than or equal to 2% by volume whenever the concent.ation of hydrov,r' r.i :'.'t ?f.cte 'I Decay Tank is greater than or equal to 4% by volume APPLICABILITY: At all times.

ACTION:

Whenever the concentration of hydrogen in any Taite fia: Decay ik is,trestet than or equal to 4% by volume, ands a.

The concentration of oxygen in that Wastu Gas Decay ' ant tter tMa P :y volume, but less than 4% by volume, without delay begin

he aru,r2 concentration to within its limit.

b.

The concentration of oxygen in that Wa.~.W.Neay Tank ' gr-u-r t-er equal to 4% by volume, immediately sus,vnd addatic..; of c:,ste ; * ' *., :t. t Waste Gas Decay Tank and without boy eegan to e ve

+e ma concentration to within its limit.

c.

The provisions of Specifications 3.0.3 and 3.; i *te no: a :r ie.

SURVEILLANCE REQUIREMENTS 4.7.13.3 The concentrations of hydrogen and $xyge, ia 'ne in sce:v ?.1s -

1 C'?.sv Tank shall be continuously monitored with th. hydrogen ver*

vvgen OPERABLE BY 5pecification 3.3.3.10 or by samptag 'n an m

c:tt...

3.3.3.10 11 the hydrogen and/or oxygen monitors a Ins, era -

CRYSTAL RIVER UNIT 3 3/47-5

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?/4.11 RADIOACTIVE EFFLUENTS..

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3/4.11.1 LIQUID EFFLUENTS CONCTNTWATTO4 i

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LIMITING CONDITION FOR OPERATION i

j 3.11.1.1 The concentration of radioactive material released to j

UNRESTRICTED AREAS (see Figure 5.1-3) shall be Less than or equal j

to the concentrations specified in 10 CFR Part 20, Appendix B, j

Table II, Column 2 for radionuclides other than dissolved or i

entrained noble gases.

For dissolved or inntrained noble gases, the concentration shall be less than or equal to 2x10-4 microcuries/al. total activity.

APPLICABILI"Y At all. times.

ACTION:

With the concentration of radioactivAmaterials j

a.

i released to UNRESTRICTED AREAS exceeding the above..

l limits, without delay restore the concentration of 1

radioactive materials being released,to UNRESTRICTED "

j 7 7,,

AREAS to within the above limits.

If the concentration of radioactive materials being released in excess of the above limito-is related to a plant operating characteristic, appropriate corrective

)

measures (e.g., power reduction, plant shutdown) shall j

be taken to restore the concentration of radioactive materials being released to UNRESTRICTED AREAS to within the above limits.

)

2 b.

The provisions of Specifications 3.0.

and 3.0.4 are not applicable.

i The reporting requirements of Specification 6.9.1.9.b c.

are not applicable.

I j i abu slI1ANCE REQUIREMENTS 4

4 4.11.1.1.1 Radioactive liquid wastes shall be sampled and i

analyzed in accordance with the sampling and analysis program of Table 4.11-1.

i 4.11.1.1.2 The results of the radioactivity analyses shall be i

used in accordance with the methods in the CFFSITE DOSE I

CALCULATION MANUAL (CDCM) to assure the concentrations of radioactive material released from the site are maintained within j

the limits of specification 3.11.1.1.

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CRYSTAL RIVER = UNIT 3 3/4 11-1 Arsendment No. 60 l

tam u 4.Al-1 RADICACTIvT LICUID WAS'"! SAMPLING Ah") ANALYSIS PRCCRAM Lower L1=it of Minimum Detection Liquid Release Sampling Analysis Type of Activity (LI.3 )

Type Frequency Frequency Analysis (uC1/ml) a A. Batch Waste P

P Releage Each Batch Zach Batch Principa} Gannaa 5x10'7 Tanks Emitters'

1. Evaporator Condensate I-131 1x10-6 Storage Tanks (2)

P M

Dissolved and 1x10-5

2. Laundry &

One Batch /M Entrained Gases Shower Sump (Gamma 2: sitters)

Tanas (2)

3. Secondary P

23 I'3 1*10" b

Drain Tank Each Batch Composite Gross Alpha 1x10~7 7

Q

'Sr-89, Sr-90 5:10~8 D

Each Batch Composite Fe-55 1x10

9

3. Continuc'js W

Principal Ga=ma 5x10~7 C

C Releases continuous Composite Emitters *

1. Seccndary
rain Tank I-131 1x1:~8

-5 M

M Dissolved and 1x10 Grab sample Entrained Gases (Gamma Emitters)

M E-3 1x10-5 Continuous' Composite C Gross Alpha 1x10~7 Q

Sr-89, St-90 5x10~8 e

C Continuous Composite Fe-55 1x10~0 CRYSTA. RIVER - UNIT 3 3/4 11-2

,.nondment flu, D, 84

ADu.IMIS""??.TIVE CON *e.0LS ina ;d, ;c;D 3z:.iI;Jnn;AL KZ70R 3 icencinued) evidence of irratersible dam;gs ar$ datactsd h*/ the monitoring, the report shall provide an analysis of the problem and a planned course of accion to alleviate the problem.

The Annual Radiological Environmental Operating Report, shall include su=marized and tabulated results in the format of Regulatory Guide 4.8, December 1975, of all radiological environmental samples taken during the report period.

In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing results shall be submitted as soon as possible in a supplementary report.

The report, shall also include the followings a

summary description of the radiological environmental

=onitoring program; a map of all sampling locations keyed to a table giving distances and directions from the reactor; the unavailability of milk or fresh leafy vegetable sa=ples required by Table 3.12-1; the results of land use censuses required by Specification 3.12.1.2r and the results of licensee participation in the Interlaboratory Comparison Program,. required by Specification 3.12.1.3.

d.

A semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.

The Semiannual Radioactive Effluent Release Report shall include a summary of the. quantities of radioactive liquid and gaseous effluents and solid waste released from the plant as outlined in Regulatory Guide 1.21, " Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants,' Revision 1, June 1974, with data summarized on a quarterly basin following the format of Appendix 3 thereof.

The Semiannual Radioactivi Effluent Release Report which is submitted 60 days af ter January 1 of nach year shall include an annual summary of hourly meteorological data collected over the previous year.

This annual summary may be either in the form of CRYSTAL RIVER - mlIT J 6-14a Amendment No. 69

ADMINISTRATIVE CONTROLS ANNUAL AND SEMIANNUAL REPORTS (Continued) an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on n.agnetic tape, or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.* This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous etfluents to MEMBERS OF THE PUBLIC, due to their activities inside the SITE BOUNDARY (Figure 5.!-3) during the report period. A!! assumptions used in making these assessments (i.e.,

specific activity, exposure time and location) shall be included in these reports.

The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

The radioactive effluent release report to be submitted 60 days af ter January 1 of each year shall also include an assessment of radiation doses to the hypothetical worst case individual from reactor releases (including doses from primtry effluent pathways and direct radiation) for the previous calendar year.

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1.

The radioactive effluent release report shall include the following information for each type of solid waste shipped of fsite during the report periods i

!)

container volume, 2) total curie quantity (specify whether determined by measurement or estimate),

3) principal radionuclides (specify whether determined by measurement or estimate),

In lieu of submittal, these meteorological data may be retained in an on-site file and provided to the NRC upon request.

CRYSTAL RIVER - UNIT 3 6-i te b Amendment No. H, 84

ADMINISTRATTVE CONTROLS l

THIRTY-DA WRITTEN REPORT 6.9.1.9 The types cf events listed h*e! w shr.!! b: thesdicc:cferit j

Dire:t:r Of the R:g!:na! Cffice within 30 days cf cec.:....sce.n se r.ter. rer~ cts.o 6he em. The un-en Information provided on the licensee event report form s i

needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

Reactor protection system or engineered safety feature instrument setting j

a.

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.

i b.

Conditions leading to operation in a degraded mode permitted h a ilmitin condition for o l

for operation. peration or plant shutdown required by a !!miting condition I

.s c.

Observed inadequacies in the implementation of administrative or i

procedural controls which threaten to cause reduction of degree of feature systems. redundancy provided in reactor protection systems or eng d.

Abnormal degradation of systems other than those specified in 6.9.1.3.c above, designed to contain radioactive material resulting from the fission process.

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1 CRYSTA1. RIVER - UNIT J pg7 j

Anendment No. 7, y;. 69 t

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1 ADMINISTR ATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement, Region !!, 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 referenced specifications a.

ECCS Actuation, Specification 3.5.2 and 3.5.3.

b.

Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

c.

Inoperable Meterorological Monitoring Instrumentation, Specification 3.3.3.4.

d.

Seismic event analysis, Specification 4.3.3.3.2.

Inoperable Fire Detection Monitoring Instrumentation, Specification 3.3.3.7 e.

l f.

Inoperable Fire Suppression System, Specifications 3.7.! !.1, 3.7.!!.2, 3.7.11.3, and 3.7.I1.4.

g.

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

h.

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

1.

Total calculated dose due to release of radioactive ef fluents exceeding twice the i

limits of Specifications 3.11.1.2.a. 3.11.1.2.b, 3.11.2.2.a. 3.11.2.2.b 3.11.2.3, or 3.II.2.3.b (required by Specification 3.!!.3).

l J.

Dose due to lodine 131. Tritium, and rad;oactive particulates with greater than 3 day half lives, in gaseous effluents in excess of specified limits, Specification 3.11.2.3.

k.

Failure to process liquid rad *aste, in excess of limits, prior to release, Specification 3.7.13.2.

1.

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

)

Specification 3.7.13.3.

Measured levels of radioactivity in environmental samp!!ng medium in excess of m.

the reportlng levels of Table 3.12 2, when averaged over any quarterly sampling

.t period, Specification 3.12.1.1.

Inoperable Mid or High Range Noble Gas Effluent Monitoring instrumentation, n.

Spect!! cation 3.3.3.9.

Inoperable euplosive gas monitoring instrumentation, Specification 3.3.3.10.

o.

CRYSTAL. RIVER UNIT 3 6 174 Amendment No.J.&, 84

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