ML20141H431

Amend 128 to License DPR-49,incorporating Corrections to Radiological Effluent Tech Specs to Reflect Actual Design & Operating Conditions

ML20141H431
Person / Time
Site:	Duane Arnold
Issue date:	01/04/1986
From:	Muller D Office of Nuclear Reactor Regulation
To:	Central Iowa Power Cooperative, Iowa Electric Light & Power Co
Shared Package
ML20141H435	List: ML20141H431 ML20141H438
References
DPR-49-A-128 NUDOCS 8601130650
Download: ML20141H431 (37)

Text

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[. UNITED STATES

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' NUCLEAR REGULATORY COMMISSION

• f i WASHINGTON, D. C. 20555 f

IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE M

DOCKET NO. 50-331 u-

-DUANE ARNOLD ENERGY CENTER-AMEN 0 MENT TO FACILITY OPERATING LICENSE r

Amendment No.128.

License No. DPR-49 1.

The Nuclear. Regulatory Commission (the Commission) has found that:

A.

.The application for amendment by Iowa Electric Light and Power Company, et al, dated November 13, 1985, compiles 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 Commission;

-C.

There is reasonable assurance (1) 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 Commission's regulations; l

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

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E..

The issuance of this amendment is in accordance with 10 CFR Part i

51 of the Commission's regulations and all applicable requirements have been satisfied.

2.-

Accordingly, the license is amended by changes to-the Technical Specifi-cations as indicated in the attachment to this license amendment and

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paragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby amended to read as follows:

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- * (2)- Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 128, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license amendment is effective as of the date of issuance.

FOR THE NUCLEAR REGULATORY C0tWISSION N

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Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: January 4, 1986

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ATTACHMENT TO LICENSE AMENDMENT NO.128 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines.

Pages 1.0-6 3.14-5 3.15-10 1.0-7 3.14-6 3.15-13 3.2-2a 3.14-7 3.15-14 3.2-3 3.14-8 3.16-2 3.2-27 3.14-9 3.16-5 3.2-29 3.14-12 3.16-12 3.2-33 3.15-1 6.8-2 3.2-43 3.15-8 6.10-3 3.2-44 3.15-2 6.11-6 3.14-1 3.15-4 6.11-7 3.14-2 3.15-5 3.14-3 3.15-7

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22._ INSTRUMENTATION 4

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Instrument Calibration or Channel Calibration - An Instrument Calibration means the verif*ication or adjustment of an instrument sigral output so that it corresponds, within acceptable range and accuracy, to a known value(s) of the parameter which the instrument monitors.

The acceptable range and accuracy of an instrunent and its setpoint are given in the system design control document and its setpoint is used in the Technical Specifications.

Instrunent calibration may be performed by any series of sequential, overlapping, or total channel steps such that the entire instrument is calibrated.

Instrument calibration includes the.~ Instrument or Channel Functional Test, as appropriate.

b.

Channel - A channel is an arrangement of a senior and associated components used to evaluate plant variables 'a'1d produce discrete outputs used in logic. A channel terminates and loses its identity where individual channel outputs are" combined in logic.

c.

Instrunent or Channel Functional Test - An Instrument or Channel Functional Test fdr

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(1) Analog channels means the injection of a simulated signal into the channel as close to the sensor as practicable to verify N'

the proper response, alarm, and/or initiating action.

(2) Bistable channels mean's the injection of a simulated signal into the sensor to verify the proper response, alarm and/or initiating action.

d.

Instrument or Channel Check - An instrument or channel check is a qualit'ative determination of acceptable operability by observation of instrunent behavior during operation.

This determination shall x

l Include, where possible, comparison of the instrument or channel with another indtpendent instrument measuring the same variable, e.

Logic' System Functional Test - A logic system functional test means a test of all relays and contacts of a logic circuit to insure all components are operable per design intent. Where practicable, action will go. to completion; i.e., pumps will be started and valves operated, f.

Trip System - A trip system means an arrangement of instrument channel trip signals and auxiliary equipment required to initiate e.ction to accomplish a protective trip function. A trip system nay require one or more instrument channel trip signals related to one or more plant parameters in order to initiate trip system action.

Initiation of protective action May require the tripping s

of a single trip system or the coincident tripping of two trip systems.

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Protection Action

'An action initiated by the protection system when a limit is reached. (t ' protective action can be at a channel or system level.

,s, Amendment No. Jpp,JJA,128 1.0-6

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22.

Instrumentation - Continued h.

Protective Function - A system protective action which results from the protective action of the channels monitoring a particular plant condition.

1.

Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit in question, j.

Logic - A logic is an arrangement of relays, contacts, and other components that produces a decision output.

1)

Initiating - A logic that receives signals from channels and produces decision outputs to the actuation logic.

2) Actuation - A logic that receives signals (either from initiating logic or channels) and produces decision outputs to accomplish a protective action, k.

Primary Source Signal - The first signal, which by plant design, should initiate a reactor scram for the subject abnonnal occurrence (see Updated FSAR Chapters 7 and 15).

l 1.

Source Check - A Source Check is the assessment of channel response when the channel sensor is exposed to a source of radiation.

23. FUNCTIONAL TESTS A functional test is the manual operation or initiation of a system, subsystem, or component to verify. that it functions within design tolerances (e.g., the manual start of a core spray pump to verify that it runs and that it pumps the required volume of water).

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24. SHUT 00WN The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.

25. ENGINEERED SAFEGUARD An engineered safeguard is a safety system, the actions of which are essential to a safety action required in response to accidents.

26. SURVEILLANCE FREQUENCY Periodic surveillance tests, checks, calibrations and exaninations shall be performed within the specified surveillance intervals. These intervals may be adjusted plus or minus 25%. The operating cycle interval as pertaining to instrument and electrical surveillance shall never exceed 15 months.

In cases where the elapsed interval has exceeded 100% of the specified interval, the next surveillance interval shall commence at the end of the original specified interval.

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Anendment No.10$,128 1.0-7 L

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LIMITkNGCONDITIONFOROPERATION/

-SURVEILLANCE < REQUIREMENT-)

(b) TheRBMcontroYrodblockset-i points are given in Table i

3.2-C.

The upscale High Powtr l

Trip Setpoint shall be aaplied when the core thermal power is greater than or e ual to 85%

of rated (P > 85%. The up-scale InternfFdiate Power Trip Setpoint shall be applied when t

the core thermal power is

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greater than or equal to 65%

of rated and less than 85% of rated (65% < P < 85%). The upscale Low" Tower Trip Setpoint shall be applied when the. core thermal power is greater than or equal to 30%

of rated and less than 65% of rated (30% < P < 65%.

The

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RBM can be trypassed hen core thermal power is less than 30%

of rated. The RBM bypass time delay (t shall be less thanorN.2q al to 2.0 seconds.

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D.-

Radiation Monitoring Systems-D.

Radiation Monitoring # Systems-isoiation e initiation Isolation & Initiation tunct uns i

Functions 1.

Steam Air Ejector Offgas

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Steam Air Ejector Offgas 3YSI 8" system

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a)~Atleastonepost-Instrumentation shall be treatment steam air ejector offgas -system functionally te'sted, calibrated I'

and. checked as indicated in radiation monitor shall be i Table 4.2.D.

. operable during reactor 4j a

power operation.

The System lo ic shall be monitors shall be set to functiona 1 tested as initiate immediate closure indicated i Table 4.2-D.

,of the charcoal bed bypass valve and the air elector off as isolation valve at a i

set ing quivalent to or es abelow th dose rate limits

'in Specification.3.15.2.1.

b) In the event.no post-treatment monitor is operable, gases from the e

. steam air;es ector offgas-system may e released to.

the environment for up to 4

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided-(l) the 1

charcoal bed of the offgas s stem is not bypassed, and

( ) the offgas stack noble gas activity monitor is operable.

Otherwise be in at least HOTSTANDEYwithinthe

.following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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Amendment No. JP),J7p.128 t

DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT

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c) At least one pre-treatment steam air ejector offgas system radiation monitor shall be operable during reactor power operation.

The monitors shall be set to initiate an alarm if the monitor exceeds a trip setting equivalent to 1.0 Ci/sec of noble gases after 30 minutes delay in the offgas holdup line.

In the event the noble gas flow in the air ejector offgas exceeds the equivalent of 1.0 Ci/sec after 30 minutes delay in the offgas holdup line restore the rate to les,s than this limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least hot standby within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, d) In the event no pre-treatment monitor is operable, gases from the steam air e.iector offgas system may be released for up to 30 days provided the charcoal bed of the(1) l offgas system is not bypassed, (2) Grab samples are collected and analyzed weekly, and (3) the offgas stack noble gas activity monitor is operable, or at least 1 post-treatment monitor is operable.

Otherwise$Y within the be in at least HOT STAND following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

Reactor Building Isolation 2.

Reactor Building Isolation and Standby Gas Treatment and Standby Gas Treatment System System The limiting conditions for Instrunentation shall be operation are given in functionally tested, calibrated Specification 3.7.B.

and checked as indicated in Table 4.2-0.

System logic shall be functionally tested as indicated in Table 4.2-0.

Amendment No. JS$,128 3.2-3

.E TABLE 4.2-8 (Continued) g B

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' MINIMlM TEST AND CALIBRATION. FREQUENCY FOR CSCS Logic System Functional-Test (4) (6)

Calibrction Frequency (9) b 1)

Core Spray Sihsystem Onee/6 months

2) Low Pressure Coolant Injection Once/6 months Subsystem 3)

Containment Spray Subsystem Once/6 months

4) HPCI Subsystem Once/6 months y

5). HPCI Subsystem Auto Isolation Once/6 months

6) ADS Subsystem (11)

Once/6 months l

7) RCIC Subsystem Auto Isolation Once/6 months

8) Area Cooling for Safeguard Systen (Mce/6 months

9) Low-Low Set Function Once/6 months

@g TABLE 4.2-D 2

MINIMUM TEST AND CALIBRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS r+

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ro Instrunent Functional Instrunent -

Instrument Channels Test (9)

Calibration (9) Source Check Check

1) Refall Area Exhaust Monitors Once/3 months Once/ Refueling Once/ month Once/ day

2) Reactor Builcing Area Exhaust Monitors Once/3 months Once/ Refueling Once/ month Once/ day

3) Offgas Post-treatment Radiation Monitors Once/3 months (10)

Once/ Refueling Once/ month Once/ day

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4) Offgas Pre-treatment Radiation Monitors Once/3 months (10)

Once/ Refueling Once/ month Once/ day i

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Logic System Functional Test (4) (6)

Frequency (9)

1) Reactor Building Isolation Once/ Refueling

2) Standby Gas Treatment System Actuation Once/ Refueling 3)

Steam Jet Air Ejector Offgas Line Isolation Once/ Refueling 4)

Steam Jet Air Ejector Charcoal Bed Bypass Once/ Refueling 4

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DAEC-1 These instrument channels will be calibrated using simulated electrical signals.

4.

Simulated automatic actuation shall be performed once each operating cycle. Where possible, all logic system functional tests will be performed using the test jacks.

5.

Reactor low water level, high drywell pressure and high radiation main steam line tunnel are also included on Table 4.1-2.

6.

The logic system functional tests shall include a calibration of time delay relays and timers necessary for proper functioning of the trip systems.

7.

These signals are not PCIS trip signals but isolate the Reactor Water Cleanup system only.

8.

This instrumentation is excepted from the functional test definition.

The functional test will consist of comparing the analog signal of the active thermocouple element feeding the isolation logic to a redundant thermocouple element.

9.

Functional tests and calibrations are not required on the part of the system that is not required to be operable or is tripped. Functional tests shall be performed prior to returning the system to an operable status with a frequency not less than once per month. Calibrations shall be performed prior to returning the system to an operable status with a frequency not less than those defined in the applicable table.

However, if maintenance has been performed on those components, functional tests and calibration shall be performed prior to returning to service.

10. The Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Instrument indicates a downscale failure.

3.

Instrument controls not set in operate mode.

11. A functional test shall be performed for the ADS manual inhibit.

switches as part of the ADS subsystem tests.

Amendment No. f99, JJp,128 3.2-33

DAEC-1 o

o The r< fueling interlocks also operate one logic channel, and are required for safety only when the mode switch is in the refueling posi; ion.

For effective emergency core cooling for small pipe breaks, the

.HPCI system must function since reactor pressure does not decrease rapid enough to allow either core spray or LPCI to operate in t i:ne. The automatic pressure relief function is provided as a sackup to the HPCI in the event the HPCI does not operate..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 are met.

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.

Two air ejector offgas post-treatment monitors are provided.

They are designed so that an instrument failure gives a downscal.e trip or an inoperative trip. When both instruments reach an upscale trip, point, or when one reaches an upscale trip point and the other reaches a downscale trip point or an inoperative trip, a trip is actuated. The post-treatment monitors have three upscale trip setpoints, one (HI) to initiate charcoal bed bypass valve Amendment J09,128 3.2-43 J

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DAEC-1 closure (valve CV-4134A open and CV-4134B closing to route offgas

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through the charcoal) and another (Hi Hi Hi) to initiate offgas system isolation valve (valve CV-4108) closure. The third trip point (Hi Hi) is for alarm initiation, and will initiate prior to the offgas isolation trip.

Customarily, the trip setting for bypass valve closure is lower than the trip setting for offgas system isolation valve closure.

Two sets of two radiation monitors are provided which initiate the

-Reactor Building Isolation function and operation of the standby gas treatment system. Two instrument channels monitor the radiation from the refueling area ventilation exhaust ducts and two instrument channels monitor the building ventilation below the refueling floor.

Trip settings of < 9 mr/hr for the monitors in the' refueling area ventilation exhaust ducts 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 path but rather all the activity is processed by the standby gas

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treatment system.

Flow integrators are used to record the integrated flow of liquid from the drywell sumps. The alarm unit in each

' Amendment J07,128 3.2-44

DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT l

,3.14 RADI0 ACTIVE LIQUID EFFLUENT 3.14.1~ The radioactive liquid

4.14.1.1 Each radioactive liquid l

effluent monitoring-effluent monitoring instrumentation instrumentation channels shown in

. channel shall be demonstrated l

Table 3.14-1 shall be OPERABLE-OPERABLE by performance of the with-their alarm and trip.

CHANNEL CHECK, SOURCE CHECK, CHANNEL setpoints set to ensure that the CALIBRATION, and CHANNEL FUNCTIONAL limits of Specification 3.14.2 are TEST operations during the modes and not exceeded.

at the frequencies shown in Table 4.14-1.

APPLICABILITY: As shown in Table 3.14-1.

4.14.1.2 The setpoints shall be determined in accordance with the ACTION:

method described in the ODAM.

a. When a radicactive liquid effluent monitoring instrumentation channel alarm and trip setpoint is less conservative than a value which will ensure that the limits of 3.14.2 are met, adjust without delay to meet l

Specification 3.14.2, or suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable,

b. When less than the minimum required liquid effluent monitoring instrument channel is OPERABLE, take

the ACTION stated in Table 3

14-1 and make every reason 8bleseffort to restore the iRstr,ument to operable status.

In the event the minimum required instrumentation is not p

returned to OPERABLE status within 30 days,

. explain in the next Semiannual Radioactive Material Release Report, in lieu of any other -

report,-. why the instrument was-not made OPERABLE in a timely manner.

3.14-1 Amendment J99,128 o

DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCEREQUIRENENT 3.14.2 The concentration of 4.14.2.1 Each radioactive liquid radioactive material in liquid waste batch shall be sampled and effluent released from the site to analyzed in accordance with Table the unrestricted area (see UFSAR 4.14-2 before release.

Figure 1.2-1) shall not' exceed the concentrations specified in 10CFR Alternatively, pre-release analysis Part 20, Appendix B, Table II, of batch (es) of radioactive liquid Column 2.for radionuclides other waste may be by gross 8 or y than dissolved or entrained noble counting provided the maximum gases.. For dissolved or entrained permissible concentration, 1 x 10-7 noble gases, the concentration uCi/ml, is. applied at the shall not exceed 2 x 10-" uCi/ml unrestricted area bo'undary, total activity.

4.14.2.2. The results of pre-release APPLICABILITY: At all times.

analyses shall be used with the calculational methods in the ODAM to ACTION:

establish trip setpoints for batch releases to assure that the

a. With the concentration of concentration at the restricted area radioactive material boundary does not exceed the limit released from the site to in Specification 3.14.2.

unrestricted areas exceeding the limit, 4.14.2.3 In any week during which without delay restore the Service Water is released to the concentration within the unrestricted area, a grab sample of limit.

water shall be collected from that Service Water System and analyzed as specified in Table 4.14-2, Item B.1 -

or B.2, and It em B.4.

In the event the radioactivity concentration in the service water exceeds the LLD stated in Table.

4.14-2 for the analytical method used, the activity concentration shall be determined by sampling and post-release analyses specified in Table 4.14-2, Items B.2 through B.S.

I Amendment J99, 128 3.14-2 i

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DAEC-1 LIMITING CONDITIONS FOR OPERATION

' SURVEILLANCE REQUIREMENT 3.14.3 The dose or dose commitment 4.14.3 Dose Calculations.

In any to a member-of the Public from quarter in which radioactive liquid radioactive materials in liquid effluent is discharged, an effluents released to the assessment shall be performed in l unrestricted area (see UFSAR Figure accordance with the ODAM at least 1.2-1) shall not exceed:

once per 30 days in order to verify that the cumulative dose commitment 1.5 mrem to the total body during does not exceed the limits in any calendar quarter, Specification 3.14.3.

5.0 mrem to any organ during any calendar gaarter, 3.0 mrem to the total body during

- any calendar year, or 10.0 mrem to any organ during any calendar year.

APPLICABILITY:. At all times.

ACTION:

a. With the calculated dose from the release of_

radioactive materials in liquid effluents exceeding the above limit, prepare and' submit to the Commission within 30 days from the end of the quarter during which the release occurred, pursuant to Specification 6.11.3, and in lieu of any other report, a Special -Report which identifies the cause(s) for -_ exceeding the limit and defines the corrective actions to be taken.

Amendment J09, 128 3.14-3

TABLE 3.14-l'

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RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY #

ACTION 1.

Gross Radioactivity Monitors Providing Automatic Termination of. Release a.

Liquid.Radwaste Effluent Line (1)

During releases 18

.2.

Gross Radioactivity Monitors Not Providing Automatic Termination of Release a.

RHR Service Water System Effluent Line (1)

During releases 20

b. ~ General Service Water System (1)

During releases 20 c.

RHR Rupture Disc Effluent (1)

During releases 20 Line 3.

Flow Rate Measurement Devices l

a.

Liquid Radwaste Effluent Line**

(1)

At. all times 21 b.

Liquid Radwaste Dilution Line (1)

During releases 22 l

1. Channel (s) shall be OPERABLE and in service except that channels out of service are permitted for preventive maintenance and required tests, l

checks, or calibrations.

• • Pump curves may be utilized to estimate flow in lieu of flow measurement devices.

Amendment J M, 128

TABLE 3.14-1

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(Continued) i TABLE NOTATION ACTION 18 With no channel 0PERABLE, effluent may be released provided that prior to initiating a release:

1.

At least two samples are analyzed in accordance with Specification 4.14.2.1, and; 2.

A technically qualified member of the Facility Staff verifies the release rate calculations and discharge valving determined by another technically qualified Facility Staff member.

Otherwise, suspend releace of radioactive effluents via this pathway.

ACTION 20 With no channel OPERABLE, effluent releases via the affected pathway may continue provided the effluent is sampled and analyzed for gross radioactivity at least once per eight hours during actual release. The analysis shall be capable of detecting 10-7 pCi/ml.

ACTION 21 With no channel OPERABLE, effluent releases via this pathway may continue provided the flow rate is estimated with pump curves at least once per batch during actual releases.

ACTION 22 With no channel OPERABLE, suspend release of ecdioactive effluents via this pathway.

Amendment JOS,128 3.14-6 L. _

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TABLE 4.14-1 a

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.RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

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CHANNEL gj CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 1.

Gross Beta or Gamma Radioactivity Monitors.Providing Alarm and Automatic Isolation a.

Liquid Radwaste Effluent Line D*

D(6)

R(3)

Q(1)(2) l 2.

Gross Beta or Gamma Radioactivity Monitors Providing Alarm But Not p)

Providing Automatic Isolation

-i' a.

RHR Service Water System Effluent Line D*

M R(3)

Q(2) b.

General Service Water D*

M R(3)

Q(2)

System Effluent Line c.

RHR Rupture Disc Effluent D*

M' R(3)

Q(2)

Line 3.

Flow Rate Measurement Devices a.

Liquid Radwaste Effluent Line D(5)*

N.A.

R Q

b.

Liquid Radwaste Dilution Line D(5)*

N.A.

R Q

r-l TABLE 4.14-1 m.

(Continued)

TABLE NOTATION

• During releases via this pathway.

• • During liquid additions to the tank.

(1) 'The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway if the following condition exists:

l 1.

Instrument indicates measured levels above the alarm / trip setpoint.

(2)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation-occurs if any of the following conditions exist:

1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

3.

. Instrument indicates a downscale failure.

4.

Instrument controls not set in operate mode.

(3)

The CHANNEL CALIBRATION shall include the use of a known radioactive source (traceable to the National Bureau of Standards radiation measurement systen or acceptable non-NBS standards) positioned in a reproducible geometry with respect to the sensor and emitting beta or gan:ma radiation in the range measured by the channel. CHANNEL 4

CALIBRATION may normally be done during refueling outages.

(4)

Not used l

-(5)

CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.

(6) On any day on which a release is made, a SOURCE CHECK shall be made at least once, prior to. the first release.

Amendment]$9,128 3.14-8

TABLE 4.14-2 g

RADI0 ACTIVE LIQUID WASTE SA> FLING AND ANALYSIS PROGRAM Lower Limit S

Minimtsn of Detection Samp1ing Analysis Type of.Acttvity (LLD)a

[

Liquid Release Type Frequency Frequency Analysis (uCi/ml) 3 P

P A. Batch Waste Each Batch Each Batch Principal Gamma Emitters' 5 x 10-7 C

E!

Release Tanks 8

I-131 1 x 10-6 i

i P

I One Batch /M M

Dissolved and 1 x 10-5 Entrained Gases P

Each Batch H-3 1 x 10-5 f

M b

Composite Gross alpha 1 x 10-7 w

P

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Each Batch Sr-89, Sr-90 5 x 10-8 f

e g

b Composite Fe-55 1 x 10-6 f

B. Continuous 1.

W W

Gross beta / gamma 1 x 10-7 Service Water Grab Sample d

Release f

2.

W W

Principal Gamma Emitters 5 x 10-7 Sample Points:

Grab Sample o General Service I-131 1 x 10-6 Water f

e RHR Service Water 3.

M M

Dissolved and System A Grab Sample Entrained Gases 1 x 10-5 e RHR Service Water I

System B 4.

W M

H-3 1 x 10-5 Grab Sample Composite Gross alpha 1 x 10-7 f

5.

W Q

Sr-89, Sr-90 5 x 10-8 Grab Sample Composite Fe-55 1 x 10-6

1 DAEC-1 O

3.14.1 and 4.14.1 BASES 1.

Radioactive Liquid Effluent Instrumentation The radioactive liquid effluent instrun'entation is provided to monitor and control as applicable the release of radioactive material in liquid efflu,ents.

The OPEdABILITY and use of these instruments implements the requirements of 10CFR Part 50, Appendix A, General Design Criteria 60, 63, and 64. The alarm and/or trip setpoints for these instruments are calculated in the manner described in the 00AM to

. assure that the alarm and/or trip will occur before the limit specified in 10CFR Part 20.106 is exceeded.

Instrumentation is expected to be OPERABLE and in service when required by Specification. An instrument may be removed from service voluntarily for the purpose of tests checks, calibration, or preventative maintenance without declaring the channel inoperable.

3.14.2 and 4.14.2 BASES 1.

Liquid Effluent Concentration Specification 3/4.14.2 is provided to satisfy the regulation governing the maximum concentration of radioactive material in liquid effluent that may be released to an unrestricted area as stated in 10CFR Part 20.106 and the regulation requiring surveys needed to determine compliance stated in Part 20.201.

Conformance to Specifit, cion 3.14.2 when applied to the activity concentration in the river at the site boundary due to liquid effluent, would assure that the average activity concentration in liquid effluent released to the unrestricted area is a small fraction of the limit specified in Part 20.106.

The sample points noted in Table 4.14-2 are adequate to ensure sampling of potential liquid radioactive effluents from the service water systems. The sample points include the General Service Water System and the RHR Service Water Systems A and B.

The sample point for the RHR Service Water Systems h at a location downstream of the point where Emergency Service Watcr discharge joins with the RHR Service Water System, and upstream of the point where the RHR Rupture Disc Line branches off of the RHR Service Water System. This sample point will therefore provide for sampling effluents from the RHR Service Water System, Emergency Service Water System and/or RHR Rupture Disc line.

3.14.3 and 4.14.3 BASES 1.

Dose Due to Radioactive Effluents Specifications 3.14.3, 3.15.3, and 3.15.4 implement the requirements of 10CFR Part 50.36a and of 10 Cf.T Part 50, Appendix I,Section IV. These specifications state Limiting Conditions of Operation (LCO)isto keep levels of radioactive materials in LWR effluents as low as reasonably achievable.

Compliance with these specifications will also keep average releases of radioacthe material in effluents at small percentages of the limits specified in 10CFR Part 20.106. Surveillance requirements provide for the measurement of releases and calculation of doses to verify compliance with the Specifications. Action statements in these Specifications implement the requirements of 10CFR Part LCO is(c)(2) and 10CFR Part 50, Appendix I, 5.% tion IV.A in the event a 50.36 not met.

3.14-12 AmendmentJpp,128

DAEC -

1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.15.1' The radioactive gaseous 4.15.1.1-Each radioactive gaseous effluent monitoring instrumentation effluent monitoring instrumentation channels shown in Table 3.15-1 channel shall be demonstrated -

shall be OPERABLE.

Their OPERABLE by performance of the radioactive noble gas monitor alarm CHANNEL CHECK, SOURCE CHECK, CHANNEL setpoint shall be set to cause CALIBRATION, AND. CHANNEL FUNCTIONAL automatic alarm when the limits of TEST operations during the MODES and Specification 3.15.2.1 are at the frequencies shown in Table

. exceeded..

4.15-1.

APPLICABILITY: As shown in Table 4.15.1.2 The setpoints shall be

.15-1.

determined according to the method 3

described in the ODAM.

ACTION:

a. With radioactive gaseous effluent monitoring instrumentation channel alarm setpoint less conservative than a value which will ensure that the limits of 3.15.2 are met, adjust without delay to meet. Specification 3.15.1, declare the channel inoperable, or immediately suspend any release via the instrumented pathway,

b. When less than the minimum required gaseous effluent monitoring instrument i:

channels OPERABLE, take the action. stated in Table 3.15-1 and make every-reasonable effort to restore the instrument to operable status.

In the event the minimum required instrumentation is not returned to OPERABLE status within 30 days, explain in the next Semiannual Radioactive Material Release Report, in lieu of any other report, why the instrument was not made OPERABLE in a timely manner.

Amendment Jpp, 128 3.15-1

E DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 4.15.2 Compliance with 3.15.2 shall be assessed on the basis of results of measurements specified in Table 4.15-2 and according to methodology stated in the ODAM.

-3.15.2.1-The dose rate in the unrestricted area (see UFSAR Figure 1.2-1) due to radioactive noble gas released in effluents shall not

' exceed 500 mrem / year to the total body or 3000 mrem / year to skin.

3.15.2.2 The dose rate in the unrestricted area due to I-131, I-133, H-3, and to radioactive particulates having half-lives of 8 days or more that are released in effluents shall not exceed 1500 mrem / year to any organ.

APPLICABILITY: Whenever monitoring or sampling is required.

ACTION: When the dose rate exceeds a limit in 3.15.2, decrease the release rate without delay to comply with the limit.

3.15-2 Amendment J09, 128

r DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.15.4 The dose to a member of the 4.15.4.1 Dose. Assessment An public from iodine-131, I-133, H-3, assessment shall be performed in and from radionuclides in accordance with the ODAM at least

_ particulate form having half-lives once every 31 days to verify that greater than eight-days in gaseous the cumulative' dose commitment due effluents released from the site to to I-131, I-133, H-3, and the unrestricted area (see UFSAR radioactive particulates having Figure 1.2-1) shall not exceed:

half-lives greater than eight days in gaseous effluents does not exceed 7.5 mrem to any organ during any the limits in Specification 3.15.4.

calendar quarter, or, 15.0 mrem to any organ during any calendar year.

APPLICABILITY:

At all times when monitors are required.

ACTION:

a. With the calculated dose from the release of I-131, I-133, H-3, and radionuclides in particulate form ha'ving half-lives greater than eight days in gaseous effluents exceeding the above limit, prepare and submit a Special Report.to the Commission within 30 days fcilowing the end of the calendar. quarter during which the release occurred.

The Special Report shall be made pursuant to Specification 6.11.3, shall be in lieu of any other report, and shall identify the cause(s) for exceeding the limit and define the corrective actions taken.

l 3.15-4 Amendment JSP,128

TTO DAEC-1

+

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.15.5 Every reasonable effort 4.15.5 The gaseous effluent shall be madeLto maintain at-least monitoring systems of Specification one train of the Offgas System-3.2.D shall be used to verify the

-0PERABLE.

operation of the offgas system.

~

Within four hours af ter commencing operation of the main condenser air ejector, at.least one train of charcoal beds in the Offgas System shall be placed in operation to treat radioactive gases from the main condenser air ejector.

Duri ng continuing reactor operation, at least one train of charcoal beds in the Offgas System shall be used to treat the gases before discharge.

APPLICABILITY: When the main condenser air ejector is operating.

ACTION:

a. If-gaseous wastes are discharged for more than 7 days without treatment, prepare and submit a Special Report to the Commission within 30 days pursuant to Specification 6.11.3, in lieu of any other report, including the

'following information:

1. Identification of the inoperable equipment or subsysten and reason for inoperability.

2. Action (s) taken to restore the inoperable equipment to OPERABLE status.

3. Summary description of action (s) taken to prevent a recurrence.

Amendment 199,128 3.15-5 uz-

TABLE 3.15-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION k

Minimum g

Channels m.,

Instrument @

Operable Applicability #

Function Action 1.

Deleted g

2.

Offgas Hydrogen Monitor (R2) 2 Monitor hydrogen 29 oo concentration 3.

Offgas Stack Monitoring System (R3) a.

Noble Gas Activity Monitor 1

Monitor activity 27 concentration, alarm b.

Iodine Sampler Cartridge 1

Collect iodine sample 31 c.

Particulate Sampler Filter 1

Collect particulate 31 sample d.

Effluent Flow Measuring Device-1 Measure air flow 26 e.

Sample Flow Measuring Device 1

Measure air flow 26 y

Y 4.

Reactor Building Exhaust Vent Monitoring System (R4) a.

Noble Gas Activity Monitor 1

Monitor activity 27 concentration, alarm b.

Iodine Sampler Cartridge 1

Collect iodine sample 31 c.

Particulate Sampler Filter 1

Collect particulate 31 sample d.

Effluent Flow Measuring Device 1

Measure air flow 26 e.

Sample Flow Measuring Device 1

Measure air flow 26 5.

Turbine Building Exhaust Vent Monitoring System (RS) a.

Noble Gas Activity Monitor 1

Monitor radioactivity 27 concentration, alarm b.

Iodine Sampler Cartridge 1

Collect iooine sample 32 c.

Particulate Sampler Filter 1-Collect particulate sample 32 d.

Effluent Flow Measuring Device 1

Measure air flow 26 e.

Sample Flow Measuring Device 1

Measure air flow 26

TABLE 3.15-1 (Continued)

TABLE NOTATION

@ Refer to 0 DAM Figure 3-1 for location of effluent monitoring points R1 thru R6.

1. Ch'annels shall be OPERABLE and in service except that channels out of service are permitted for.the purpose of required tests, checks, calibration, and preventative maintenance without declaring the channel to be inoperable.

• During releases via this pathway.

• • During offgas system operation.

ACTION 25 Deleted ACTION 26 With no channel OPERABLE, effluent releases via this pathway may continue provided the flow rate is estimated whenever operation of a main exhaust fan combination is changed in the system.

ACTION 27 With no channel 0PERABLE, effluent releases via this pathway may continue if grab samples are taken at least once per eight hours and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l

or if an alternate monitoring system is utilized. Drywell purge is permitted whenever the offgas itack monitor.or' its alternate monitor is operating.

ACTION 28 Deleted ACTION 29 With one channel 0PERABLE, operation of the offgas system may la continue provided the recombiner temperature sensor is operable.

When only one of the preceding methods is operable, the offgas system may be operated provided gas samples are collected at least once per day and analyzed for hydrogen within the ensuing four hours.

ACTION 31 With no channel OPERABLE, effluent releases via this pathway may l

continue, provided samples required in Table 4.15-2 are continuously collected with auxiliary sampling equipment.

ACTION 32 With no channel OPERABLE, effluent releases via this pathway may continue if grab samples are taken at least once per eight hours and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l

or if an alternate monitoring system is utilized.

Amendment 199,128 3.15-8

TABLE 4.15-1 (Continued)

TABLE NOTATION Instrumentation shall be OPERABLE and in service except that channels out of service are permitted for the purpose of required tests, checks, calibrations, _and preventative maintenance without declaring the channel to be inoperable..

During releases via this pathway.

l ** During offgas system operation.

• • • During operation of the stean jet air ejector.

(1)'Not used.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

1.

Instrument indicates measured levels above the alarm setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

l 4.

Deleted (3) The CHANNEL CALIBRATION shall include the use of a known radioactive source (traceable to the National Bureau of Standards radiation measurement system or other acceptable non-NBS standards) positioned.in a reproducible geometry with respect to the sensor and enitting beta and/or gamma radiation in the range measured by the channel in accord with established station calibration procedures. Alternately, after the initial calibration, noble gas activity monitors may be calibrated by laboratory analyzed gas samples collected and analyzed per Table 4.15-2, item A.

(4) The CHANNEL CALIBRATION shall include the use of at least two standard gas samples, each containing a known volume percent hydrogen in the range of the instrument, balance nitrogen.

I Amendment J09, 128 3.15-10

l DAEC-1

~

3.15.1 and 4.15.1 BASES 1.

Radioactive Gaseous Effluent Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor the release of radioactive materials in gaseous effluents and, as appropriate, to control potential releases.

Instrumentation for monitoring the concentration of potentially explosive gas mixtures in the main condenser offgas treatment system is also provided. The presence of instruments for monitoring both radioactive and explosive gaseous effluents is depicted in ODAM Figure 3-1.

The OPERABILITY and use of these instruments implements the requirements of 10CFR Part 50, Appendix A, General Design Criteria 60, 63, and 64.

Reactor building exhaust ventilation shaft radiation monitors initiate isolation of the reactor building normal ventilation and start standby gas treatment when a high trip point is reached.

DAEC is equipped with a radioactive gaseous effluent monitoring system which includes detectors at the offgas stack (R3), the reactor building vent (R4), and the turbine building vent (RS). A remote indication and control unit located near each etector displays the detector reading and, whenever the setpoint is exceeded, an indicator light. The data are also routed to a control computer and a control room display but do not cause a trip to isolate the ventilated area.

In the event the control computer and/or control room display fall to function or are voluntarily taken out of service, each remote indication and control unit is designed to acquire data for up to 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

It is intended that each affected remote indication and control unit display be observed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (in which case the affected channel remains OPERABLE).

If an alarm trip setpoint is exceeded at the same time the control computer and/or control room display are neither functioning nor in service, alarm annunciation will still occur in the control room.

In the event the detector reading and the indication of exceeding the monitor setpoint are not provided at either the control room or the remote indication and control unit, then the affected channel is not l

OPERABLE and DAEC will either perform the appropriate ACTION or will provide an alternate monitoring system. This permits DAEC to retain the GE gaseous monitoring system as an alternate system for normal effluent monitoring when the Kaman system is temporarily inoperable.

When used as an alternate monitoring system, the GE system is subject to the requirements stated in Specifications 3.15.1 and 4.15.1 and to LLD requirements stated in Table 4.15-2, Item C.

Amendment # 9, 128 3.15-13

T.

DAEC-1 2.

Not used l

3.

Gaseous Effluents Assessments of dose required by Specifireions 4.15.3 and 4.15.4 to verify compliance with Appendix I,Section IV are based on measured radioactivity in gaseous effluent and on calculational methods stated in the ODAM.

Pathways of exposure and location of individuals are selected such that the dose to a nearby resident is unlikely to be underestimated.

Dose assessment methodology described in the ODAM for gaseous effluent will be consistent with the methodology in Regulatory Guides 1.109 and 1.111.

Cumulative and projected assessments of dose made during a quarter are based on historical average meteorological conditions measured at DAEC. Assessment made for the annual radiological environmental report will be based on annual averages of atmospheric conditions during the period of release.

3.15.2 and 4.15.2 BASES Gaseous Effluent Concentration This specification is intended to ensure that the concentration of radioactive material in the unrestricted area beyond the site boundary due to gaseous effluents from DAEC will maintain doses within the annual dose limits to unrestricted area provided in-10 CFR Part 20.

Compliance with these limits also reasonably assures that radioactive material in gaseous effluents will not result in exposure of a member of the public in an unrestricted area to annual averaged concentrations exceeding the limit in 10 CFR Part 20.106.

The occupancy time of members of the public who may occasionally be on the site is expected to be low enough to compensate for any less atmospheric dispersion on site than to the environs offsite.

Assessment of compliance is based upon an effluents measuremer.t program defined in Table 4.15-2 and methodology stated in the ODAM. The resolving time of the measurements, ie., the sample integration time, bounds the minimum averaging time of the effluent measurements. waste streams.

The StandDy Gas Treatment System is considered an Engineered Safety Feature and not an exhaust ventilation treatment system.

Thus the exhaust ventilation system discharges via the reactor building vent.

3.15.3 and 4.15.3 BASES Doses due to Noble Gases These specifications implement the requirements of 10 CFR Part 50, Appendix I.

Amendment 109, 128 3.15-14

DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT

'3.16.2 A radiological 4.16.2.1 Sampling and analyses environmental monitoring program required in Table 3.16-1 shall De shall be conducted as specified in performed such that the detection Table 3.16-1.

capabilities specified in Tat 4 3.16-2 are achieved under rou;ine APPLICABILITY: At all times.

conditions.

If a sample ana:ysis does not meet the LLD specifved,

. ACTION:

report the reason attributed in the next Annual Radiological

a. In the event the Environmental Report.

radiological environmental monitoring program is not 4.16.2.2 Land Use Census DAEC conducted as specified in shall conduct annually a land use the Table 3.16-1, prepare census within three miles cf the and submit to the Station to identify radioicgically Commission in the Annual important changes in land use.

Radiological Environmental Report the reasons for not conducting the program in accord with the Table 3.16-

'I and the plans for preventing a recurrence.

b. In the event radioactivity in a sampled environmental medium, averaged over a calendar quarter, is attributable to DAEC and exceeds an appropriate value listed in Table 3.16-3 or, if not listed, causes a potential annual dose exceeding two times the quarterly dose limit in Specification 3.14.3 or 3.15.4, prepare and submit to the Commission within 30 days after discovery a Special Report which includes an evaluation of any relea:e conditions, environmental factors or other conditions which chused the value(s) of Table 3.16-3 or two times the quarterly dose limit to be exceeded and which defines the corrective actions to be taken.

If the radioactivity in environmental sample (s) is not attributable to releases from the Station, the. Special Report is not Amendment 109,128 3.16-2

T f

' DAEC-1 7,.

. LIMITING' CONDITIONS FOR'0PERATION SURVEILLANCE REQUIREMENT 3.16.4 Appropeiate equipment shall 4.16.4.1 The. Process Control-

'be' operated in accordance with a Program shall. state the essential c

Process' Control Progran to process.

operating parameters of the wet radioactive. waste-solids process (es), the essential destined for disposal to a form characteristics of the waste form to

.e:

that meetsJppropriate requirements be shipped, and the' essential

'of 10 CFR Part 61.561before the product verification requirements.

wastesis shipped frwi the DAEC site.

'e w

(,

APPL'ICABILITY:

During Processing of radioactive waste solids for disposal.

ACTION:-

O~

s 1.

Suspend delivery to a ' transport carrier of any container of radioactive waste riot complying with 10 CFR Part 61.56.

A

_s E,

s s

?.

s t

3

%c 2

'3.16-5 Amendment JDS, J28

\\

\\

\\ \\,'

\\

(

t

environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

3.16.4 and 4.16.4 BASES 1.

Radioactive Waste Solids This specification implements the requirements of 10 CFR Part 50.36a(a), the General Design Criterion 60 of 10 CFR Part 50 Appendix A, and of 10 CFR Part-61.56 on characteristics of low-level radioactive wastes destined for disposal by burial. Applicable requirements on packaging and delivery of packages of radioactive material to a carrier for transport stated in 10 CFR Part 71 and on transportation of hazardous materials in 49 CFR 171-179 are not' restated in the technical specifications.

Processing waste to meet characteris. tics permitted under 10 CFR Part 61.56 may include solidification, preparation for deposit in a high integrity container, or any form acceptable under Part 61 for shipment to and receipt by a licensed disposal facility or licensed radioactive waste processor.

It is intended that a Contractor may perform the waste processing provided he operates according to a Process Control Program approved in accordance with Technical Specification 6.15.

Amendment JS9, 128 3.16-12

t DAEC-1 i

r

~

8.

Procedures required by the pl, ant Security Plar.

t t

j 9.

Operation of radioactive waste systems.

1

10. Fire Protection Prog' am ihplanentation.

r t

(

,11.4 A preventive maintenance and periodic visual exanination program to reduce leakage from systems jutside containment that would or could contain highly radioactive ' fluids during a serious transient to as f ow as practical levels.' This progran shall also include l

provisions for performance of periodic systems leakdests of each

.)

system no less frequently than at refueling cycle intervals.

12. Program to ensure the capability to accurately determine the airborne iodine concentrationgin vital areas under accident conditions, including training of personnel, procedures for monitoring and. provisions for maintenance of sampling and analysis j

(

equipment.

/

3.' Administrative procedures for shift overtime for Operations

'/ ' Cpersonnel to be consistent with the Commission's June 15,1982,-

/

policy statement.

.)

14. Offsite Dose Assessment Manual.

-l 1

15. Process Control P1ani j

16. - Quality Control Progran, for effluents.

6.8.2 Procedures described in 6.8.1 above, and changes thereto, shall be

./

reviewed by the Operations Committee and approved by the Plant h"

Superintendent-Nuclear prior to implementation, except as provided in 6.8.3 below.

6.8.3 Temporary minor changes to procedures described in 6.8.1 above which do not change the intent of the. original procedure may be made with the concurrence of two members of the plant management staff, at least one of whom shall hold a senior operator license.

Such changes shall be i

doctsnented and promptly reviewed by'the Operations Committee and by the Plant Superintendent-Nuclear.

Subsequent incorporation, if necessary, as a permanent change, shall be in accord with 6,.8.2 above.

t

- 7 Anendment fic. J M J26, 128 6.8-2

DAEC-1

.s.

7.

Records of training and qualification for current members of the plant staff.

'8.

Records of in-service inspections performed pursuant to these Technical Specifications.

-9.

. Records of. Quality Assurance activities required by the QA Manual.

10.

' Records of. reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

11.

Records of meetings of the Operations Committee and the Safety Committee.

12.

Records for Environmental -Qualification which are covered under the provisions of-paragraph 6.13.

13.

Records of the service lives of all safety-related hydraulic and mechanical snubbers including the date at which the service life commences and

' associated installation and raintenance records.

14.

Records of results of analyses required by the radiological environmental monitoring - program.

. Amendment-No. 19$ JJ3, 128 6.10-3

DAEC-1

-6.11.3 UNIQUE REPORTING REQUIREMENTS

.Special reports shall be submitted to the Director of

' Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be p

l submitted covering the activities identified below pursuant to the requirements of the applicable reference specification.-

a.

Reactor vessel base, weld and heat'affected zone metal testspecimens(Specification 4.6.A.2).

b.

1-131 dose equivalent exceeding 50% of equilibrium value (Specification 4.6.B.1.h).

c.

Inservice inspection (Specification 4.6.G).-

d..

Reactor Containment Integrated Leakage Rate Test (Specification 4.7.A.2.f).

e.. deleted f.

Fire Protection Systems (Specifications 3.13. A.3, 3.13.B.2, 3.13.B.3, 3.13.C.3, and 3.13.D.3),

g.

deleted l Amendment 109,128 6.11-6

p

~+gg.

DAEC-1 x

.h.

Radioactive Liquid or Gaseous Eff! cent.- calculated dose exceeding specified limit-(Specifications 3.14.3, 3.15.3 and 3.15.4).

(effective date 1/1/86) s,

i. _ Off-Gas System inoperable (Specification 3.15.5)..

l (effective date-1/1/86)

j. Measured levels of radioactivity in an environmental sampling

. medium determined to exceed the reporting level values _of Table 3.16-3 when averaged over ary calendar quarter sampling period,

~(specification 3.16.2.b).

(effective date 1/1/86) k.

Annual dose to a member _ of the public determined to-exceed 40 CFR -

Part 190 dose limit, (specification 3.16.1.b)~.

(effective date' 1/1/86) l.

Radioactive liquid' waste released without ' treatment when activity concentration exceeds 0.01 Ci/ml, ( specification' 3.14.4.a).

(effective date 1/1/86)

Amendment 199,128 6.11-7

{: