ML20097J653

Amend 209 to License DPR-49,revising TS Section 3.2.A to Refer to Offsite Dose Assessment Manual for Set Point of Offgas Stack Radiation Monitor

ML20097J653
Person / Time
Site:	Duane Arnold
Issue date:	04/25/1995
From:	Marcus G NRC (Affiliation Not Assigned)
To:
Shared Package
ML20097J660	List: ML20097J653 ML20097J663
References
NUDOCS 9504280260
Download: ML20097J653 (7)

Text

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-t UNITED STATES

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g NUCLEAR REGULATORY COMMISSION

't WASHINGTON, D.C. 20065 4 001

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IES UTILITIES INC.

.. CENTRAL IOWA POWER COOPERATIVE t

' CORN MtT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FAr:tITY OPERATING LICENSE Amendment No. 209 License No. DPR-49 1.

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

t

. A.

.The,applicatf ar for amendment by IES Utilities Inc., et al.,

l dated November 10, 1994, and supplemented March 1, 1995, 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 Commission; C.

~.There is reasonable assurance (1) thatsthe activities authorized by this amendment can be conducted without endangering the health j

and safety.of the publ.ic, 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 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:

i 9504200260 950425 PDR ADOCK 0$000331

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. (2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised

through Amendment No. 209, 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 shall be implemented within 90 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION y

Gail H. Marcus,' Dir ctor

/

Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation I

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Attachment:

Changes to the Technical Specifications Date of issuance:

April 25, 1995 i

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ATTACHMENT TO LICENSE AMENDMENT N0.209 FACILITY OPERATING LICENSE NO. DPR-49

.. DOCKET NO. 50-331

.. Replace the following pages. t,' the Appendix A Technical'5pecifications with the enclosed pages."' The revised: areas are indicated by vertical lines.

Remove Insert iii 111 3.2-4 3.2-4 3.2-7 3.2-7 1

3.2-46 3.2-46 s

1 DAEC 1 1

SURVEILLNACE LIMIflNG CONDif!Oa5 FOR OPERATIONS REQUIREMENTS PAGE NO.

3.7 Plant Containment Systems 4.7 3.71 A.

Primary Containment Integrity A

3.71 B.

Primary Contairinent Power Operated B

3.7 7 Isolation valves F

, C. -

eryneti Average air issyreture

'C 1.7-9 9.'

Wessure hospewasion themasse +ewarter D

3.7 10 Building vacu m Breakers E.

Drywell Pressure Suppression Chanuber E

3.7-11 Vacu m Breakers f.

Main Steam Isolation valve Leakage F

3.7 12 Control System (MSIV LCS)

G.

Suppression Poot Levet and fenperature G

3.7-13 H.

Contairement Atmospheric Dilution H

3.7-15 1.

Daygen Concentration 1

3.7-16 4,J. ' c. 5econstory Cantainment J

3.7-17 f.

K.

Secondary Contairunent Automatic K

3.7 18 Isolation Dampers L.

Standby Gas Treatment System L

3.7-19 M.

Mechanical Vacuum Punp M

3.7-21 3.8 Auxiliary Electrical Systems 4.8 3.8-1 A.

AC Poner Systems A

3.8 1 B.

DC Power Systems B

3.5-3 C.

Onsite Power Distritction Systems C

.3.3 5 D.

Auxiliary Electrical Equpment -

D 3.8-5 CoeE ALTERATIows E.

Emergency Service Water System E

3.8-6 3.9 Core Alterations 4.9 3.9 1 A.

Refuteing Interlocks A

3.9 1 B.

Core Monitoring B

3.9 5 C.

Spent fuel Pool Water Level C

3.9 6 D.

Auxiliary Electrical Eg4rnent -

0 3.9-6 CDRE ALiftAfl0WS 3.10 Ackfitional Safety Related Plant capabilities 4.10 3.10-1 A.

Main Control Room Ventilation A

3.10-1 B.

Remote Shutoown Panets B

3.10 2a C.

Control Building Chillers C

3.10 2a 3.11 aiver tevet Specification 4.11 3.11 1 AMINDMEh1 WO.)*:7.Jae, F.Dt. 209 til 5

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to Table 3.2-A (Continued]

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ISOLATION ACTUATION INSTRUMENTATION HINIMUM VALVE r+

OPERABLE CROUPS 2

APPLICABLE CHANNELS ISOLATED 0

OPERATING PER TRIP BY '.

TRIP FUNCTION TM1P LEVEL SETTING MODE SYSTEM (*)

SIGNAL ACTION ta Secondary Containment Refuel Floor Exhaust Duct - High s 9 mr/hr 1,2,3 and

• 1 3(*)

26 L

Radiation m7 Reactor Building Exhaust Shaft -

s 11 mr/hr 1,2,3 and

• 1 3(C) 26 High Radiation go Offgas Vent Stack - High Radiation Note k Note m 1

3(c) 27 RHR System Shutdown Coolino Reactor Vessel Pressure - High s 135 psig 1,2,3 1

4 23 jn Reactor Water Cleanuo RWCU Differential Flow - High 5 40 gpmd 1,2,3 1

5 23 RWCU Area Temperature - High 5 130*F 1,2,3 1

5 23 RWCU Area Ventilation Differential A14 *F(d) 1,2,3 1

5 23 Temperature - High Standby Liquid Control System NA Note 1 1

5(f) 23 Initiation RWCU Area Near Tip Room s 111.5'F 1,2,3 1

5 23 Ambient Temperature - High l

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i DAEC-1 Imble 3.2-A (Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTION ACTION 20 -

Be in at least HOT SRUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SEUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 21 -

.Se in at.least STARTUP with ths. associated isolation valves closed wkMm 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or km in'at;1eest IIOT smrIDONE withim.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and

. ' in COLD EBUTDOWN withis the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 22 -

• Be in at least JTARTUF within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 21 -

Close the affected system isolation valves within one hour and declare the affected system inoperable.

ACTION 24 -

Not used.

ACTION 25 -

Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or close the affected system isolation valves within the next hour and declare the affected system inoperable.

ACTION 26 -

Isolate Secondary Containment with the Standby Gas Treatment System l

operating within one hour.

ACTION 27 -

Within one hour, close the primary containment vent and purge valves, or establish administrative control of those valves with continuous monitoring of alternate instrumentation.

NOTES When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operatione with a potential for draining the reactor vessel.

When any turbine stop valve is greater than 90% open and/or when the key-locked bypass switch is in the NORM position.

(a) When a channel is placed in an inoperable status solely for performance of required surveillances, entry into associated Limiting conditions for Operation and required Actions may be delayed as follows: (1) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for RWCU Differential Flow-High, RCIC Manual Initiation, HPCI Manual Initiation; and (2) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for the remaining Trip Functions provided the associated Trip Function maintains isolation capability.

(b) Operates Group 1 valves 15g121 Main Steam Isolation Valves. Also trips Mechanical Vacuum Pump which results in a subsequent isolation of the Mechanical Vacuum Pump Suction valves.

(c) Also starts the Standby Gas Treatment system.

(d) Actual setpoint shall be 14*F above the 100% operation ambient temperature

. conditions as determined by DAEC plant. test procedure.

(e) Closes NO-2701 stad. 310-2740 only.

(f) Requires system steam supply pressure-low coincident with drywell pressure-high to close HPCI/RCIC exhaust vacuum breaker valves.

(g) Hanual isolation closes MO-2401 only, if RCIC initiation signal present.

(h) Manual isolation closes MO-2239 only, if HPCI initiation signal present.

(1) When the Standby Liquid control System is required to be OPERABLE per Specification 3.4.A.

(j) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full-power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test.

The background radiation level and associated trip setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of reestablishing normal radiation levels after completion of the hydrogen injection test or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20% rated power, while these functions are required to be operable.

(k) The monitors shall be set to initiate isolation at a setting equivalent to or below the dose rate limits in ODAM section 6.2.2.1.

(m) During VENTING or PURGING of primary containment at any time when PRIMARY CONTAINKENT INTEGRITY is required.

Amendment No. A9,M,1,MA 209 3.2-7

DAEC-1 i

Both of the scram discharge volume high level channels provide input to the "B"

i logic.

The refueling interlocks operate one logic channel, and are required for safety only when the mode switch is in the refueling position.

.For effective emergency core cooling for small pipe. breaks, the HPCI system snust

. function since reactor pressure does not decrease rapidly enough to allow either core spray or 1.PCI to operate in< time.

The Automatic,Depressurization System (ADS) is g

provided as a backup to HPC1.

The arrangement of the ADS logic 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 downscale 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-treatnernt monitors have three upscale trip setpoints, one (Hi) to initiate charcoal bed bypass valve closure (CV-4134A open and CV-4134B closing to i

route offgas through the charcoal) and another (Hi-Hi-Hi) to initiate offgas system

.isniation valve.(CV-4108pelosure.,The third. trip point (Hi-Hi) is.for alarm

.initiatier, and wilIc. initiate--prior;to.the of fgas.. isolation. trip.

Two eat s of two radiation monitors are provided which initiate the Reactor Building Isolation nr.ction and operation of the standby gas treatment system.

Two instrum(nt channels monitor the radiation from the refueling area ventilation exhaust ducts and two instrument channels monitor the building ventilation below the refueling floor.

A third set of two radiation monitors is included in the Offgas Vent Stack.

The offgas Vent Stack radiation monitors initiate a Group III isolation as a convenient l

means to terminate primary containment VENTING or PURGING upon detection of high radiation in the effluent. This isolation signal was added in response to NUREG 0737, Item II.E.4.2(7).

When these instruments are not OPERABLE, the activity for which the isolation was intended must be terminated or administrative control must be j

implemented. The VENTING or PURGING of Primary Containment may proceed under administrative control providing the following conditions are mets (1) an operator is stationed at the valve controls, and (2) that operator is instructed.to terminate 6

VENTING or PURGING when procedures direct valve closure.

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 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 treatment system.

High radiation monitors in the main steam line tunnel have been provided to detect gross fuel failure.

In the event of a gross fuel failure, the established setting of 3 times normal full power background radiation levels (accounting for the N-16 carryover due to Hydrogen Water Chemistry) will trip the Mechanical Vacuum Pump, which in turn isolates the suction of the Mechanical Vacuum Pump from the high and low pressure condensers.

This prevents the release of untreated fission preducts to the environment via the Mechanical Vacuum Pump.

Flow integrators are used to record the integrated flow of liquid from tne drywell sumps. The alarm unit in each timer is set to annunciate before the values specified in specification 3.6.C are exceeded.

An air sampling system is also provided, as a backup to the sump' system, to detect leakage inside the primary containment.

Amendment No. 444,209 3.2-46

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