Text

Amend 40 to License DPR-22,incorporating Administrative Changes & Changing Radiation Monitoring Requirements Due to Installation of Reactor Bldg Vent wide-range Gas Monitors
	ML20140B980
Person / Time
Site:	Monticello
Issue date:	03/18/1986
From:	Zwolinski J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20140B986	List: ML20140B980; ML20140B990;
References
	NUDOCS 8603250059
	Download: ML20140B980 (19)
	v • d • e

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'o, UNITED STATES E'

'g NUCLEAR REGULATORY COMMISSION 3 #.

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WASHINGTON, D. C. 20555

%,.....f NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 1

MONTICELLO NUCLEAR GENERATING PLANT l

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.40 4

i License No. DPR-??

l 1.

The Nuclear Regulatorv Comission (the Commission) has found that:

A.

The application for amendment by Northern States Power Company (the licensee) dated Aucust 30, 1984, as revised on November 8, 1984, j

and August 29, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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; I

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endancering the health and safety of the public and (ii) that such activities will be conducted in compliance with the Commission'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 Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and naranraph 2.C.2 of Facility Operating License No. DPR-22 is hereby amended to read as follows:

8603250059 860318 DR ADOCK O 23

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2 Technical Specifications I

The Technical Specifications contained in Appendix A as revised through Amendment No. 40, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This licensa amendment is effective as of the date of its issuance.

4

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FORTHENUCLEARREGULAT0pC ISSION 1

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John A. Zwolinski, Director BWR P 0,4ect Directorate #1 Divislon of BWR Licensing

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Attachment:

Changes to the Technical Specifications 3

Date of Issuance:

March 18, 1986 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 40 t

i FACILITY OPERATING LICENSE NO. DPR-22

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l DOCKET NO. 50-263 i

i Revise Appendix "A" Technical Specifications by removing the pages I

identified below and insertina the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

J REMOVE INSERT i

l 47 47 l

50 59 62 62 68 68 J

70 70 192 192 193 193 197 197

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198d 198d i

1481 1981 i

198k 198k 1981 1981 1

198m 198m 198n 198n i

1980 1980 l

198y 198y i

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i 3.0 LIMITING C005)ITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS E.

Reactor Bes11 ding Vent 11ation Isolation and Standby Ces Treatment System Initiation Whenever secondary containment integrity is required as specified in 3.7.C.

the I.initing Conditions for Operation

~

for the instrumentation listed in Table 3.2.4 shall be met.

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1 3

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Tchle 3.2.4 Instrumentation That Initiates Rzecter Building Vzntilotien Isolcticn And Standby Gas Treatment System Initiation Min. No. of Operable Total No. of Instru-or Operating Instrument ment Channels Per Trip Channels Per Trip Required Function Trip Settings System System (Notes 1,2)

Conditions *

1. Low Reactor Water 210'6" above 2

2 A. or B.

Level (Note 3) the top of the active fuel

2. High Drywell Pres-

!s2 psig 2

2 A. or B.

sure (Note 3)

3. Reactor Building 3s100 mR/hr 1

1 (Note 4)

A. or B.

Plenum Radiation Monitors

4. Refueling Floor 3;100 mR/hr 1

1 (Note 4)

A. or B.

Radiation Monitors

5. Reactor Building calculated per 1

1 (Note 4)

A. or B.

Vent Wide Range 3.8.B Cas Monitors l

Notes:

l (1) There shall be two operable or tripped trip systems for each function with two instrument channels per trip system and there shall be one operable or tripped trip system for each function with one instrument channel per trip system.

(2) Upon discovery that minimum requirements for the number of operable or operating trip systems or instrument channels are not satisfied action shall be initiated to:

Ng (a) Satisfy the requirements by placing appropriate channels or systems in the tripped condition, or cp (b) Place the plant under the specified required conditions using normal operating procedures.

S (3) Need not be operable when primary containment integrity is not required-y I

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(4) One of the two monitors may be bypassed for maintenance and/or testing.

Required Conditions when minimum conditions for operation are not satisfied, i

A. The reactor building ventilation system isolated and the standby gas treatment system operating.

l B. Establish conditions where secondary containment is not required, t

3.2/4.2 59

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4

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.2 l

l Table 4.2.1 - Continued Minimum Test and Calibration Frequency For Core Cooling Rod Block and Isolation Instrumentation Instrument Channel Test (3)

Ca!!bration (3)

Sensor Check (3) 3.

Steam Line Low Pressure Note !

Once/3 months None 4.

Steam Line High Radiation once/ week (5)

Note 6 Once/ shift l

HPCI ISOLATION 1.

Steam Line !!1gh Flow Once/ month once/3 months None 2.

Steam Line High Temperature Once/ month once/3 months None RCIC ISOLATION 1.

Steam Line High Flow Once/ month Or.ne/3 months None 2.

Steam Line High Temperature Note 1 Once/3 months None REACTOR BUILDING VERTILATION 1.

Radiation Monitors (Plenum)

.Once/ month once/3 months Once/ day 2.

Radiation Monitors (Refueling Floor)

Note i Once/3 months (4) 3.

Wide Range cas Monitors See Table 4.8.2 RECIRCULATION PUMP TRIP 1.

Reactor High Pressure Note 1 Once/ Operating Cycle-Once/ Day g

Transmitter Once/3 Months-Trip Unit ma et 2.

Reactor Low Low Water Level (Note 7)

Once/ month once/ Operating Cycle-Once/ shift l

Transmitter Once/3 Months-Trip Unit 2

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SHUTDOWN COOLING SUFPLY ISOLATION

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1.

Reactor Pressure Interlock Note 1 Once/3 Months None y*

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3.2/4.2 62 1

- - _ _ _ _ _ _ _ = _ = _ _ _ _

= _

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Brass Continued:

3.2 The RBM bypass time delay is set low enough to assure minimum rod movement while upscale trips are i

bypassed.

l The IRM rod block function provides local as well as gross core protection. The scaling arrangement is such that trip setting is less than a factor of 10 above the indicated level.. Analysis of the worst case accident results in rod block action before MCPR approaches the Safety Limit (T.S.2.1.A).

4 A downscale indication of an APRM or IRM is an indication the instrument has failed or the instrument is not sensitive enough.

In either case the instrument will not respond to changes in control rod

(

motion and thus control rod motion is prevented. The downscale trips are set at 3/125 of full scale.

l For effective emergency core cooling for the small pipe break the HPCI or Automatic Pressure Relief system must function since for these breaks, reactor pressure does not decrease rapidly enough to allow either core spray or LPCI to operate in time. The arrangement of the tripping contacts is such as to provide this function when necessary and minimize spurious operation. The trip settings given in the specification are adequate to assure the above criteria is met.

Reference Section 6.2.4 and 6.2.6 FSAR. The specification preserves the effectiveness of the system during periods of maintenance, testing, or calibration, and also minimizes the risk of inadvertent operation; i.e., only one instrument channel out of service.

Six radiation monitors (two reactor building vent plenum, two reactor building vent wide range gas and two refueling floor) are provided which initiate isolation of the reactor building and operation'of the standby gas treatment system following a refueling accident. The monitors measure radioactivity in the reactor building ventilation exhaust and on the refueling floor. One upscale trip signal or two downscale/ inoperable trip signals, from a pair of monitors performing the same function, will cause the desired action. Trip i

settings of 100 mR/hr for the reactor building vent plenum monitors and the refueling floor monitors are based upon initiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident leaves the reactor building via the normal ventilation lf stack but that all the activity is processed by the standby gas treatment system. The reactor building vent j

g wide range gas monitors trip settings will be calculated in accorda,nce with NRC approved methods in the ODCM g

to ensure that the alarm / trip will occur prior to exceeding the -limits of 10CFR Part 20.

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The recirculation pump trip description and performance analysis is discussed in Topical Report NEDO-25016,' September 1976, " Evaluation of Anticipated Transients Without Scram for the Monticello o

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Nuclear Generating Plant".

(See September 15, 1976 letter from Mr L 0 Mayer, NSP, to Mr D L Ziemann, ma USNRC.) The pump trip is provided to minimize reactor pressure in the highly unlikely event of a 1.

plant transient coincident with the failure of all control rods to scram. The rapid flow reduction o

i 3.2 BASES 68 4

Trip Function Deviation Reactor Building Ventilation Isolation and Reactor Building Vent

+5 mR/hr Standby Gas Treatment System Initiation Plenum Monitors Specification 3.2.E.3 and Table 3.2.4-Refueling Floor

+5 mR/hr Radiation Monitors Low Reactor Water Level

-6 inches High Drywell Pressure

+1 psi Primary Containment Isolation Functions tow Low Water Level

-3 inches Table 3.2.1 High Flow in Main Steam Line

+2%

High Temp. In Main Steam

+10*F Line Tunnel Low Pressure in Main Steam

-10 psi Line High Drywell Pressure

+1 psi Low Reactor Water Level

-6 inches HPCI High Steam Flow

+7,500 lb/hr HPCI Steam Line Area High

+2*F Temp.

RCIC High Steam Flow

+2250 lb/hr R

RCIC Steam Line Area High Temp

+2*F N

5 Shutdown Cooling Supply ISO

+7 psi 5

70 3.2 BASES

.4*

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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEII. LANCE REQUIREMENTS 3.8 RADI0 ACTIVE EFFLUEKfS 4.8. RADI0 ACTIVE EFFLUEWrS Applicability:

Applicability:

Applies at all times to the liquid and gaseous Applies to the sampling monitoring, and recording radioactive effluents from the plant and the of liquid and gaseous radioactive ef fluents, solidification and packaging for shipment of verification of solidification, and solid radioactive waste, verification of equipment operability.

Objective:

To implement the requirements of 10CFR20, 10CFR71 To implement the requirments of 10CFR20, 10CFR50 Section 50.36a, Appendix A and 10CFR71,10CFR50 Section 50.36a, Appendix A and Appendix I to 10CFR50, 40CFR141, and 40CFR190 pertaining Appendix I to 10CFR50, 40CFR141, and 40CFR190 pertain-to radioactive effluents.

ing to radioactive effluents.

Specification:

Specification: -

A. Liquid Effluents A. Liquid Effluents

1. Concentration

a. The concentration of liquid radioactive

a. Surveillance of Liquid effluent monitoring material released from the site instrumentation shall be performed as (Figure 3.8.1) shall be limited to the required by Table 4.8.1.

concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for radio-hf -

nuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble g[

gases, Jhe concentration shall be limited to g

2x 10, uci/ml total activity.

o"

b. When the concentration of radioactive material in Ei Liquid released from the site exceeds the limits in (a) above, immediately restore concentration

$2 within acceptable limits.

3.8/4.8 192

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILI.ANCE REQUIREMENTS b.

Radioactive liquid wastes shall be sampled

c. Radioactive material in liquid effluent and analyzed according to the sampling and released from the site shall be con-analysis program of Table 4.8.3, tinuously monitored in accordance with Table 3.8.1.

c.

The results of radioactive analysis shall be l

used in accordance with the methods of the

d. The 11guld effluent monitors having ODCM to assure that the concentrations at the provisions for automatic alarming, as listed point of release are maintained within the in Table 3.8.1, shall be used to limit the limits of Specification 3.8.A.1.a.

concentration of radioactive material released at any time from the site to the values given in 3.8.A.I.a.

Setpoints aball be determined in accordance with the methods in the Of f-site Dose Calculation Manual (ODCM).

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c) 3.8/4.8 193

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t 3.01.IMITING CONDITIONS FOR OPERATION 4.0 SURVEILI.ANCE REQUIREMENTS B. Gaseous Effluents B. Caseous Effluents t

1. Dose Ra te

1. Dose Ra te i

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a. The dose rate at any time due.to radioactive

a. Surveillance of gaseous effluent monitoring materials released in gaseous effluents from instruments shall be performed as required the site (Figure 3.8.2) shall be limited by Table 4.8.2.

to the following:

b. The release rate of I-131, tritium and radioactive l

1. For noble gases to 1500 mrem / year particulates with half-lives greater than eight to the total body and $3000 mren/ year to days shall be determined by obtaining representa-the skin, and tive samples and performing analyses in accordance with the sampling and analysis program specified

2. For I-131, tritium, and radioactive par-in Table 4.8.4.

Following each analysis ticulates, with half-lives greater than the dose rate due to I-131, tritium, and radio-eight days to 11500 mres/ year to any active particulates with half-lives greater than organ.

eight days shall be determined to be less than the 11mit in Specification 3.8.B.I.a.2 in accordance with the ODCN.

4 b.

With the dose rate (s) exceeding the limits in (a) above, immediately decrease the re-lease rate within acceptable limits.

ac. Radioactive material in gaseous effluents released from the site shall be continuously l 37 monitored in accordance with Table 3.8.2.

d.

The noble gas effluent monitors having provisions for the automatic termination 3

' of gaseous releases, as listed in Table 3.8.2 jy shall be used to limit of fsite dose rates to 4

the values established in Specification 3.8.B.I.a.l.

Setpoints shall be determined 4

3, in accordance with the ODCM.

o 3.8/4.8 197

l 3.0 1.IMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

'5. Main Condenser Offgas Activity

5. Main Condensor Offgas Activity a.

The gross gamma radioactivity release The gross gamma radioactivity of noble gases from rate measured at the stegm jet air ejector shall the main condenser air ejector shall be determined 16x 10 uci/sec following to be within the limit specified in 3.8.B.5.a at 2

be limited to a.30-minute decay, the following times by perfording an isotopic analysis of a representative sample of gases:

b.

When the limit in (a) above is exceeded, restore the gross gamma radioactivity release

1. Once every month, rate to within the 11mit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or

2. Within.24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months follwoing an increase be in at least hot shutdown within the next in the continuous monitor reading of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

50% after factoring out increases due j

to power level.

c.

The activity of radioactive material in gaseous form removed from the main condenser shall be continuously monitored by the steam jet air ejector monitors in accordance with Table 3.8.2.

d.

The steam jet air ejector monitors shall be set to automatically terminate offgas flow within 30 minutes at the limit established in Specification 3.8.B.5.a.

6. Containment Venting and Purging

6. Containment Venting and Purging 1

a.

Except for inerting operations following

a. Except for inerting operations following startup startup and deinerting prior to shutdown, and deinerting prior to shutdown, the containment

!I containment venting and purging above cold shall be determined to be' aligned for venting or

] $

shutdown shall be via the 2-inch bypass purging through the Standby Cas Treatment System

! SI flow path using the Standby Cas Trea tment within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to start of and at least once System.

per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during venting or purging of the r*

containment above cold shutdown.

2 x

b. Containment inerting following startup and

b. Prior to containment venting or purging, the (2

deinerting prior to shutdown shall be via sampling and analysis requirements of Table 4.8.4

},

the Reactor Building plenum and vent.

shall be met.

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-3.8/4.8 198d I

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TABLE'3.8'k - RADI0 ACTIVE LIQUID EFFLUEIR HONITORING INSTRUME!EATION (Page 1 of 2)

Minimum Chan6ela Instrument Operable Applicability

.Ac tion if Minimum Channels not Operable Liquid Radwaste Ef fluent Line i

During release of Liquid radwaste releases may continue for up to 14 days l Cross Radioactivity Monitor *

""T1 quid radwaste provided that. prior to initiating a release a.

At least two independent samples are analyzed in accordance with Specification 4.8.1.d b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; otherwise, suspend release of radioactive effluents l

via this pathway.

Liquid Radwaste Effluent Line 1

During release of Liquid radwaste releases via this pathway may continue l

~

Flow Instrument liquid radwase for up to 30 days provided the flow rate is estimated at least once every four hours during actual releases.

Pump curves may be used to estimate flow.

. Ditcharge Canal Flow Effluent releases via this pathway may continue for up He2surement to 30 days provided the flow rate is estimated at least Open Cycle Mode 1

During release of once every four hours during actual releases. Pump i

Closed / Helper Cycle Mode 1

liquid radwaste curves may he used to estimate flow.

Dircharge Canal Cross

- -1 At all times Effluent releases may continue for up to 30 days l

e Rrdioactivity Honitor provided that at least once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months a grab sample a

((

shall be collected and analyzed for gyoss beta and gamma radioactivity at an LLD of 10 uCi/ml.

Service Water Discharge Pipe I

At all times Service water discharge may continue for up to 30 days g

Cress Radioactivity Monitor

provided that at least once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months a grab o

sample is collected and analyzed for gross beta and 7

ya gamma radioactivity at an LLD of 10 uC1/ml.

s a

o 3.8/4.8 1981 t

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TABLE 3.8.2

- RADI0 ACTIVE CASEQUS EFFLUENT HONITORING INSTRIMENTATION (Page 1 of 2)

Minimum Channels Instrument Operable Applicability Action if Minimum Channels not Operable Main Condenser Air Ejector 2

During air ejector From and after the date that one of the two steam jet Noble Gas Activity Honitor opera t ion air ejector off-gas radiation monitors is made or found to be inoperable, continued reactor power operation is permissible provided the inoperable radiation monitor instrument channel is tripped. Upon loss of both steam jet air ejector off-gas radiation monitors, he'in Hot Standby within six hours.

Main Condenser Offgas Treatment 2f During air ejector Operation may continue for up to 14 days with one Operable Sys tem flydrogen Monitors operation channel per operating recombiner train. With all channels inoperable, be in Hot Standby within six hours.

I Plant Stack Wide Ra'nge Noble Gas Activity 1

At all times Releases via this pathway may continue for up to 30 days l

Monitors

provided grab samples are taken and analyzed at least once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Iodine Sampler Cartridge 1

At all times '

Releases via this pathway may continue for up to 30 days provided within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months samples are continuously collected with auxiliary sampling equipment as required by Table 4.8.4.

Particulate Sampler Filter 1

At all times Releases via this pathway may continue for up to 30 days provided within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months samples are continuously collected with auxiliary sampling equipment as required by Table 4.8.4.

m 1

. g, Stack Flow Honitor i

At all times Releases via the pathway may continue for up to 30 days pro-g vided the flow rate is estimated at least once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

o Sample Flow Instrument 1

At all times Releases via the pathway may continue for up to 30 days pro-Ei vided the flow rate is estimated at least once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b4 n.

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3.8/4.8 198k

TABLE 3.8.2

- RADI0 ACTIVE CASEQUS EFFI.UENT MONITORING INSTRUMEffrATION (Page 2 of 2)

Minimum Channets' Instrument Operable Applicability Action if Minimum Channels not Operable Reactor Building Vent (includes Turbine Building

& Radwaste Building releases)

Wide Range Noble Gas Activity 1

At all times Releases via this pathway may continue for up Monitor **

to 30 days provided grab samples are taken and analyzed at least once every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Iodine Sampler Cartridge 1

At all times Releases via the pathway may continue for up to 30 days provided within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months samples are continuously collected with auxiliary sampling equipment as required by Table 4.8.4.

Particulate Sampler Cartridge 1

At all times Releases via the pathway may continue for up to 30 days provided within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months samples are continuously collected with auxiliary sampling equipment as required by Table 4.8.4.

Duct Flow Monitors 1

At all times Releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Sample Flow Instruments At all times Releases via this pathway may continue for up to 30 days provided the flow rate is fI estimated at least once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , o

EI Notes:

- Indicates number of channels required per. operating recombiner train.

??

- Provides automatic termination of offgas treatment system releases.

U is

- - Provides automatic isolation of reactor building releases, o

3.8/4.8 198-1

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TABLE 4.8.1

- RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

~

SURVEILLANCE REQUIREMENTS Source Sensor Check Check Functional Test Instrument Frequency Frequency Frequency Calibration Frequency Liquid Radwaste Effluent Daily during Immediately Within 3 months prior Within 12 months prior to Lins Gross Radioactivity release Prior to to making a release making a release.*

Monitor Each Release Within 3 months prior Within 12 months prior to Liquid Radwaste Effluent Daily during Line Flow Instrument release to making a release making a release.

Within 3 months prior Within 18 months prior to Instruments used in Daily during Dstermination of Discharge release to making a release making a release.

Canal Flow Service Water Discharge Daily Monthly Quarterly Each Operating Cycle

Pips Gross Radioactivity Monitor Di: charge Canal Gross Daily Monthly Quarterly Each Operating Cycle **

'l Radioactivity Monitor Turbine Building Daily Monthly Quarterly Each Operating Cycle Normal Drain Sump Monitor Quarterly when Each Operating Cycle Leval Monitors for Daily when Tecporary Outdoor Tanks in use in use when in use Holding Radioactive Liquid

- The initial Instrument Calibration shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using sources traceable to NBS. standards. These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent calibration sources that have been related to the initial calibration shall be used.

- - An initial Instrument Calibration was. performed using a liquid reference standard over the systems intended range of energy and measurement range. Solid calibration sources traceable to NBS Standards currently being applied for instru-ment calibrations were related to the initial calibration.

If, in the future, the canal radioactivity monitor is replaced, the following conditions shall apply:

Detector response and system efficiency shall be equal to or better than the present system.

a.

f b.

Footnote (*) shall apply.

198m 3.8/4.8 Amendment No. IS,40

/

TABLE 4.8.2

- RADI0 ACTIVE GASEOUS EFFLUENT. HONITORING INSTRUMENTATION SURVEILLANCE REQUIREHElfrS (Page 1 of 2)

Source Sensor Check Check Functional Test Instrument

~ Frequency Frequency Frequency Calibration Frequency Main Condenser Air Ejector

' Daily during

~

Quarterly Once each Operating Cycle Noble Gas Activity Monitors air ejector operation Hain Condenser Of fgas Trea t-Daily during Monthly Quarterly #

ment System Hydrogen Honitors air ejector operation Plant Stack Wide Range Noble Daily Monthly Quarterly Once each Operating Cycle

Cas Activity Honitors Plant Stack Iodine and Weekly Particulate Samplers Plant Stack Flow Honitor Daily Once each Operating Cycle a

Plant Stack Sample Flow Daily' Once each Operating Cycle Instruments N

a

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8 3.8/4.8 198n

TABLE 4.8.2

- RADI0 ACTIVE CASEOUS EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE REQUIREHEffrS (Page 2 of 2)

Source Sensor Check Check Functional Test Instrument Frequency Frequency Frequency Calibration Frequency Reactor Building Vent Wide Da ily Monthly Quarterly Once each Operating Cycle

Range Noble Cas Activity Honitors Reactor Building Vent Weekly Iodine and Particulate Samplers 1

Reactor Building Vent Duct Daily Once each Operating Cycle Flow Monitors Reactor Building Vent Daily Once each Operating Cycle Sample Flow Instruments

- The initial Instrument Calibration shall be performed using ene or more of the reference standards certified by the National Bureau of Standards (NBS) or using sources traceable to NBS standards. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent calibration sources that have been related to the initial calibration shaLL be used.

- The Calibration shall include the use of standard gas samples containing a nominal four volume percent

!g(

hydrogen.

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3.8/4.8 198o

3.8 and 4.8 Bases: (continaed)

Specification 3.8.B.4.c is provided to ensure that the concentration of potentia!!y explosive gas mixtures contained in the waste gas treatment system is maintained below the flammability limits of hydrogen and oxygen.

Automatic control features are included in the system to prevent the hydrogen and oxygen concentrations from reaching these flammability limits. Maintaining the concentration of hydrogen below the flammability limit provides assurance that the releases of radioactive materials will be controlled in conformance with the require-ments of General Design Criterion 60 of Appendix A to 10 CFR Part 50 Specifica tion 3.8.B.4.e is provided to limit the radioactivity which can be stored in one decay tank. Restricting t

the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an j

uncontrolled release of the tanks contents, the resulting total body exposure to an individual at the site i

i restricted area boundary will not exceed 20 mrem. A flow restrictor in the discharge line of the decay tanks

[

I prevents a tank from being discharged at an uncontrolled rate.

In addition, interlocks prevent the contents of a j

tank from being released with less than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of holdup.

i Specification 3.8.B.5 establishes a maximum activity at the steam jet air ejector. Restricting the gross radio-activity rate of noble gases from the main condenser provides reasonable assurance that the total body exposure l

to an individual at the restricted area boundary will not exceed the limits of.10 CFR Part 20 in the event this effluent is inadvertently discharged directly to the environment with minimal treatment. This specification j

implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.

Specification 3.8.B.6 requires the containment to twt purged and vented through the standby gas treatment system except during inerting and deinerting operations. This provides for lodine and particulate removal from the containment atmosphere. During outages when the containment is opened for maintenance, the containment ventilation exhaust is directed to the monitored reactor building vent.

Use of the 2-inch flow path prevents damage to the l

standby gas treatment system in the event of a loss of coolant accident during, purging or venting. Use of the reactor building plenum and vent flow path for inerting and deinerting operations permits the reactor building vent wide range gas monitors to automatically terminate releases in the event that release rate limits are exceeded.

l[ C.

Solid Radioactive Waste a

$I Specification 3.8.C.1 provides assurance that the solid radwaste system will be used whenever solid radwastes require processing and packaging prior to being shipped of fsite. This specification implements the

((

requirements of 10 CFR Part 50.36a and General Design Criteria 60 of Appendix A to 10 CFR Part 50.

o.

D 3.8/4.8 BASES 198y-

.

ML20140B980

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