ML20195J040

Amend 155 to License DPR-49,revising Tables 3.2-F,3.2-H & 4.2-H of Tech Specs to Reflect Proper Ranges,Surveillance Requirements & Nomenclature of Containment Water Level & Pressure,Torus Water Level & Temp Instrumentation

ML20195J040
Person / Time
Site:	Duane Arnold
Issue date:	11/30/1988
From:	Hannon J Office of Nuclear Reactor Regulation
To:
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ML20195J045	List: ML20195J040
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NUDOCS 8812010213
Download: ML20195J040 (9)

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UNITED STATES f

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NUCLEAR REGULATORY COMMISSION 7.

l WASHINGTON, D. C. 20655

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IOWA ELECTRIC LIGHT AND POWER.C0t4PANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 155 License No. OPR-49 1.

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

A.

The application for amendnunt by Iowa Electric Light and Power Company, et al., dated September 2,1988 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 appl Mation, the provisions of the Act, and the rules and regulations of e.he Comission; C.

There is reasonable assurance (1) that the activities author).wd 4

by this amendment can be conducted without endangering the hea'th and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

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

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

2.

Accordingly, the license is amended by changes to the Technical Specif1-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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8a1201o2 3 gg333g fDR ADock 0000o333 l

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. 1 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.155, 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 30 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION t//

w Jr WW *v g ~p John N. Hannon, Director Project Directorate III-3

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Division of Reactor Projects - I!!,

IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: November 30, 1988 0

ATTACHMENT TO LICENSE AMEN 0 MENT NO. 155 FACILITY OPERATING LICENSE NO. OPR-49 DOCKET NO. 50-331 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised arwas are indicated by marginal lines.

3 3.2-22 3.2-23a 3.2-23c 3.2-31 3.2-34a i.

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TABLE 3.2-F SURVEILLANCE INSTRUMENTATION Total No.

Minisus No.

Type Channels Channels Instrument Indication Action Provided Required and Range 3

2 Reactor Water Level Recorder, Indwetor

1) (2) 158"-218"*

3) 3 2

Reactor Pressure Recorder, Indicator (1) (2) 0-1200 psig (3) 2 2

Drywell Pressure Recorder (1)(2)

-10 to +90 psig (3) 8 2

Drywell Tenperature Recorder (1)(2) y 0-350*F (3) 2 2

Torus Water Temperature Recorder (1)(2) 20-220*F (3) l 2

2 Torus Water Level Recorder (1) (2)

-10"/0/+10" H O (3) 2 y

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2 1

Control Rod Position Process Computer, g

Full Core Display, g

Four Rod Group Display

=

4 3

Neutron Monitoring SRM** (10 1 to (1) (2) 106 CPS)

(3)'(4)

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E 3 (per Trip 2 (per Trip Neutron Monitoring IRM,** APRM (1) (2)

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System)

System) 0 to 125% power (3) (4)

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• Indicator scale is referenced to the T.op of Active Fuel (TAF), defined as 344.5 inches above u

vessel zero.

• • Not required when in the Run mode.

DAEC-1 NOTES FOR TABLE 3.2-F 1.

From and after the date that one of these parameters is reduced to one indication, when required, continued operation is pennissible during the succeeding thirty days unless such instrumentation is sooner made operable.

l 2.

From and after the date that one of these parameters is not indicated in the control room, continuad operation is permissible during the i

succeeding seven days unless such instrumentation is sooner made operable.

I 3.

If the. requirements cf notes (1) and (2) cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a Cold Condition I

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

4.

These surveillance instruments are considered redundant to each other.

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d 3.2-22 Amendment No. J3A,155

TABLE 3.2-H ACCIDENT DONITORING INSTRtMENTAtlOtl Minimus 8am.

Total Number of Type Indication Osennels lastrument Oiennels Prowlded and % nge bquired Action Safety / Relief Velve Nettfon indfcato- (Primary Detector) t/ Valve (l)

N/A t/ Valve (2)

Safety / Ret tet Velve Nottfon Indicefor (9mckup-Themocouple) t/Volve N/A 0

Safety Vetwo Nettfon indtcetor (Primary Detector)

$/ Valve (l)

N/A

)/ Valve (2)

Safety Vefwe Nettfon indfcator (lteckup-hwole) t/ Valve N/A 0

hector Osolent, (batef mant Atmosphere, and 2(each)

N/A 1(each)

(4) (5)

Torus meter Nst-Accfdent Sempt ing Entended Mange Ef fluent medletfon Ibattorst e) Anector IhstIdf ag Ewheest Stock 3

Recorder, fadfcator t

(5) 4 to 104 pct /cc 5 w 10 se4 b) Turbfne bilding Exhoust Stock i

Recorder, indigotor F

(6) 4 4

5 x t0 to 1&' pCf/cc us c) Of tges Stock 1

ftecorder, indfcefor t

(6) 5 w 10-2 to POS pCP/cc d

Drywi t/ Torus Radiation abattor 4

flacorder, Indfcator 2

(6)

I 1 to TO R/hr 9

die Dryuelt Pressure Ibattor 2

facorder, fadfcator 2

(7) (8) 0-250 psfg l

=

0 Dryuell Pressure Ibattor 2

Recorder, Indicefor 2-(7)(8)

-5 to +5 pstg ww7 Torus tanter Level Ibattor (Pr9mery Detector) 2 beorder, Indicator 2

(9) (1C) 1.5 to 16 feet vi (batelement tanter Lowei 5

.* (Backup level)*

2.

Hocorder Indicefor O to 98 feet (batef ament Hydrogen, centratton (3) 2 flacorder, Indicator 2

(f t)(F2) 0-10E or 0-258 02 0-POS or 0-20$ H Volume owygen/h rogen eg,tet t water Level is not part o f the Accident Pbaltortag lastrumentation.

It is o e wsed as a backup to torus seter level only.

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DAEC-1

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1 i.R TABLE 3.2-H (cont.)

(7)

If the number of OPERA 3LE channels (both indicator and recorder inoperable) is reduced to less than the Minimum Number Channels Required (e.',.

reduced to one channel) follow either step (a) or (b) below.

I a.

Operation may continue for the next thirty (36) days provided at least one (1) channel of instrumentation specified in Table 3.2-F for the identical parameter is OPERABLElorfollowstep(c)below.

l b.

Restore the inoperable channel to OPERABLE status within 7 days, should j

neither channel of instrumentation specified in Table 3.2-F'for the identical parameter be OPERABLE, or follow step (c) below.

c.

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

(8)

If the number of OPERABLE channels (both indicator and recorder inoperable) is reduced to zero (e.g., no channels available) restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> be in at i,

least HOT STANDBY and within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> be in COLD SHUTDOWN.

l (9)

If the number of OPERABLE channels (both indicator and recorder inoperable) is reduced to less than the Minimum Number Channels Required (e.g.,reducci to one channel) follow either step (a) or (b) below.

a.

Operation may continue for the next thirty (30) days provided at least i*

one torus water level channel and.ne containment water level channel is L

available2 If these conditions cannot be met, follow step (b) below.

b.

Operation may continue for the next 7 days if one torus water level channel is available and there are no other containment water level channels avail-l able.

If these conditions cannot be met, follow step (c) below, c.

Within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> be in at least HOT STANDBY and Within the L

next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> be in COLD SHUTDOWN.

(10)

If the number of OPERABLE channels (both indicator and recorder inoperable) is i

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reduced to zern (e.g., no channels available) restore at least one channel to 1

OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> be in at least HOT STANDBY ar.d within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> be in COLD SHUTDOWN.

(11)

If the number (

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channels (botn indicator and recorder inoperable) l l

is less than the ;'W NumberChannelsRequired(e.g.,reducedtoone l

j channel) follow either step (a) or (b) below.

a.

Within 30 days, incres e the number of OPERABLE channels to the Minimum NumberChannelsRequir:1orfollowstep(c)below.

)

IThe instruments in Table 3.2-F which measure the identical parameters are the

-10 to 90 psig drywell pressure monitors.

2The containment water level monitors provide indication from 0 to +98 feet.

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3.2-23c Amendment No. JM,155 I

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TABLE 4.2-F MINIMUM TEST AND CALIBRATION FR.EQUENCY FOR SURVEILLANCE INSTRUMENTATION Instrument Channel Calibration Frequency Instrument Check

1) Reactor Level Once/6 months Once Each Shift

2) Reactor Pressure once/6 months Once Each Shift

3) Orywell Pressure Once/6 eonths Once Each Shift

4) Drywell Temperatnre Once/6 months Once Each Shift i

5) Torus Water Temperature Once/6 mont!:s Once Each Shift I

6) Torus Water Level Once/6 months Once Each Shift l

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7) Cor. trol Rod ?osition NA Once Edch Shift

8) Neutron Monitoring Prior to Reaching 20%

Once Each Shift Power ar.d once per day (VNen in Startup when in Run Mode (AFRM or Run Mode)

Gain Adjust when in Run Mode)

N aa 3

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TABLE 4.2-H

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ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Calibration Frequency Instrument Check (2)

Safety / Relief Valve Position Indicator (Primary) (1)(2)

Onc?/operatir.g cycle Once/ month l

Safety / Relief Valve Position Indicator (Backup-Thermocouple)

Once/ operating cycle Once/ month l

Safety Valve Position Indicator (Primary) (1)(2)

Once/ operating cycle Once/ month Safety Velve Positics Indicator (Backup-Thermocouple)

Once/onerating cycle Once/ month i

Drywell/ Torus Radiation Monitor Once/ operating cycle (3)

Once/ month Extended Range Effluent Radiation Monitors a) Reactar Building Exhaest Stacks Annual (4)

Once/ week b) Turbine Building Exhaust Stack Annual (4)

Once/ week c) Offgas Stack Annual (4)

Once/ week Reactor Coolant. Coniainment Atmosphere, and Torus Water Annual (5)

N/A t

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Post-Accident Sampling Drywell Pressure Monitors Annual Once/ month Torus Water Level Monitor Once/ operating cycle Once/reonth l

Containment Water Level Monitor Once/operatir.g cycle Once/ month l

k Containment Hydrogen /0xygen Concentration Once/6 months (6)

Once/ month (6)

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HOTES FOR TABLE 4.2-H

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a 1.

Functional test of the relay is done once/3 months.

z 2.

Instrument check shall consist of the qualitative assessment af channel behavior during operation by 0

observation. This determinatien shall include, where possible, comparison of the channel indication

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and/or status with other indications a.71/or status derived from inAg.Aat instrument channels (e.g.

g backup themocouple) measuring tha same parameter.

3.

Channel calibration shall consist of an electrGaic calibration of the channel for ianges above 10 R/hr y

and a one point calibration check of* the detector below 10 R/hr with a portable gannu source.

4.

Accident range effluent monitors shall be calibrated by means of a built-in check source or a known radioactive source.

j 5.

Not a calibr< tion, but demonstration of system operability.

6.

Moniton shall be tested for operability usig standard bottled 1 and 0

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