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Amend 135 to License DPR-49,revising Tech Specs to Incorporate Restrictions Re Radiation Monitor Installed in Ventilation Exhaust Stack of Low Level Radwaste Processing & Storage Facility
	ML20206Q378
Person / Time
Site:	Duane Arnold
Issue date:	08/26/1986
From:	Muller D; Office of Nuclear Reactor Regulation
To:	; Central Iowa Power Cooperative, Corn Belt Power Cooperative, Iowa Electric Light & Power Co
Shared Package
ML20206Q380	List: ML20206Q378; ML20206Q383;
References
	DPR-49-A-135 NUDOCS 8609040376
	Download: ML20206Q378 (8)
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kg UNITED STATES f

g NUCLEAR REGULATORY COMMISSION L

j WASHINGTON, D. C. 20555 k.....,/

IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET N0. 50-331 DUANE ARN0LD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.135 License No. DPR-49 1.

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

A.

The application for amendment by Iowa Electric Light and Power Company, et al, dated February 7, 1986, 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 (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 e

conducted in compliance with the Comission's regulations; J

D.

The issuance of this amendment will not be inimical to the comon 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.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and 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.135, 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, and must be implemented in 30 days after the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 0-A Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: August 26, 1986 k

.i 1

- - -.. - - - ~

4 ATTACHMENT TO LICENSE AMENDMENT N0. 135 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET N0. 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 3.15-7a *

,3.15-8a

3.15-9 3.15-11 3.15-13

Page added

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2 4

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l TABLE 3.15-1, continued 1

]

RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION Minimum 1

Channels Instrument 9 Operable Applicability #

Function Action 6.

LLRPSF Exhaust Vent Monitoring System (R7) a.

Noble Gas Activity Monitor 1

Monitor activity 33 concentration, alarm b.

Iodine Sampler Cartridge 1

Collect iodine sample 31 c.

Particulate Sampler Filter 1

Collect particulate 31 s ample d.

Effluent Flow Measuring Device 1

Measure air flow 26 ga e.

Sample Flow Measuring Device 1

Measure air flow 26 U"

h i

1 I

LLRPSF = Low-Level Radwaste Processing and Storage Facility l

Amendment No. 135

~

l TABLE 3.15-1 (Continued)

TABLE NOTATION ACTION 33 With no channel OPERABLE, effluent releases via this pathway may continue provided a grab sample is taken at least once per day and is analyzed for radioactivity or principal gamma emitters within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

k Amendment No. 135 3.15-8a l

M...

TABLE 4.15-1 i

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS S

CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL REQUIRED g

INSTRUMENT CHECK CHECK CALIBRATION TEST MODE #

1 1.

Offgas Hydrogen Monitor D**

N.A.

Q(4)

M 2.

Offgas Stack Monitoring System a.

Noble Gas Activity Monitor D*

M R(3)

Q(2)

C; b.

Iodine Sampler Cartridge W*

N.A.

u c.

Particulate Sampler Filter W*

N.A.

d.

Effluent Flow Measuring Device D*

N.A.

R Q

e.

Sample Flow Measuring Device D*

N.A.

R Q

3.

Reactor Building Vent Monitoring System w

a.

Noble Gas Activity Monitor D*

M R(3)

Q(2)

L b.

Iodine Sampler Cartridge W*

N.A.

T c.

Particulate Sampler Filter W*

N.A.

d.

Effluent Flow Measuring Device D*

N.A.

R Q

e.

Sample Flow Measuring Device D*

N.A.

R Q

4.

Turbine Building Exhaust Ventilation Monitoring System a.

Noble Gas Activity Monitor D*

M R(3)

Q(2) b.

Iodine Sampler Cartridge W*

N.A.

c.

Particulate Sampler Cartridge W*

N.A.

d.

Effluent Flow Rate Monitor D*

N.A.

R Q

e.

Sample Flow Measuring Device D*

N.A.

R Q

i 5.

LLRPSF Exhaust Ventilation Monitoring System a.

Noble Gas Activity Monitor D*

M R(3)

Q(2) i b.

Iodine Sampler Cartridge W*

N.A.

c.

Particulate Sampler Cartridge W*

N.A.

d.

Effluent Flow Rate Monitor D*

N.A.

R Q

e.

Sample Flow Measuri,ng Device D*

N.A.

R Q

j i

M...

r.

i i

a a

g TABLE 4.15-2 et RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM l

Minimum Lower Limit of Sampling Analysis Type of Detection (LLD)a

~3 Gaseous Release Type Frequency Frequency Activity Analysis (pCi/ml) b D

C A. Offgas Stack, and M Grab Sample M

Principal Gamma Emitters 1 x 10-4 e Reactor Building v'

9 Q Grab Sample Q

H-3 1 x 10-6 Vent d

B. Offgas Stack, Continuous Wc I-131 1 x 10-12 Reactor Building Charcoal Vent Turbine Sample Building Vent, i.a d

i and LLRPSF Vent Continuous Wc Principal Gamma Emitters 1 x 10-11 e i

Y' Particulate (I-131,Others) l l-~

Sample d

Continuous Q

Sr-89, Sr-90 1 x 10-11 Composite Particulpte Gross Alpha 1 x 10-11 Sample l

C. Offgas Stack, Continuous Continuous Radioactive Noble Gas 1 x 10-6 Reactor Building ganma activity 4

Vent, Turbine Building Vent, j

and LLRPSF Vent l

I

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), the turbine building vent (RS), and the LLRPSF vent. A l

remote indication and control unit located near each detector displays the detector reading and, whenever the setpoint is exceeded, an indicator light. Tne data are also routed to a control computer and a control room display and, except for the LLRPSF vent detector, do not cause a trip to isolate the ventilated area. The LLRPSF vent detector does isolate the LLRPSF ventilation system. However, the isolation function is not required by regulation but is provided as an engineering design conservatism.

In the event the control computer and/or control room display fail 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 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

It is intended that each affected remote indication and control unit display be observed at least once I

per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (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 g

service, alarm annunciation will still occur in the control room. In )

y the event the detector reading and the indication of exceeding the monitor setpnint are not provided at either the control room or the remote indication and control unit, then the affected channel is not OPERABLE and DAEC will either perform the appropriate ACTION or will provide an alternate monitoring system. This permits DAIC 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 No. 109, f28, 135 3.15-13

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ML20206Q378

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