ML20094M655

Amend 182 to License DPR-49,revising TS by Eliminating Scram & MSIV Requirement Associated W/Main Steam Line Radiation Monitors

ML20094M655
Person / Time
Site:	Duane Arnold
Issue date:	03/24/1992
From:	Shiraki C Office of Nuclear Reactor Regulation
To:
Shared Package
ML20094M660	List: ML20094M655
References
NUDOCS 9204010234
Download: ML20094M655 (17)

Text

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UNITED STATES g

p, NUCLEAR REGULATORY COMMISSION E

,-t WASHINGTON, D, C,20555 i

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10WA ELECTRIC LIGHT AND POWER COMPAM CENTRAL IOWA POWER COOPERATIVE _

CORN BELT POWER COOPERATIVF, DOCKET NO.- 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.182 License No. DPR-49 1.

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

A.

The application for amendment by Iowa Electric Light and Power Company, et al., dated August 30, 1991, and supplemented with additional information in a letter dated-January 27, 1992, 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) 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-r_egulations; 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 require-ments have been satisfied.

2.

Accordingly, the license is amended by changes to the' Technical Specifications as_ indicated in the attachment to this license-amendment and paragraph 2.C.(2) of Facility Operating. License No.

DPR-49 is hereby amended to read as follows:

\\M 9204010234 920324 PDR ADOCK 05000331 P

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(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.182, 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 1

Clyde Y. S iraki, Sr. Project Manager Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

March 24, 1992 l

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ATTACHMENT TO LICENSE AMENDMENT NO.182 FACILITY OPERATING LICENSF NO. OPR-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.

Paae 3.1-4 3.1-7a 3.1-9 3.1-12 3.1-14 3.1-18 3.2-5 3.2-19 3.2-29 3.2-33 3.2-39 3.2-44 3.7-19b 3.7-27

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TABLE 3.1-1 t h ntinued) 1

-i REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT l

l

- Minimum No.

Modes in Which Number of of Operable Function Must be Instrument instrument Operable Channels Channels Refuel Startup Run Provided i

System (1)

Trip Function Trip Level Setting (6)

By Design.

Action (1))

for Trip 2

.High Drywell Pressure 5 2.0 poig x(7) x(8) x 4 Iristrueent A

t channels f,

i 2

Reactor Low Water 2 +170" Indicated x

x x

4 Instrument A'

Channels Level Level (15) w 4

2

HLgh Water Level in 5 60 Gallone x(2) x x

4 Instrument A

+

Channels

' Scram Discharge Volume 1

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4 Main Steam Line 5 10% Valve closure x

x x(13) 8 Instrument A or C (3)(13)

(3)(13)

Channels Isolation valve Closure'-

N.

2 Turbine Control Valve.

Within 30 milliseconds x(4) 4 Ir.strument' A or D f

?-? :

l S.

Fast' Closure (Lose of-the Start of Control Channels

[

g of Control. Oil Valve Fast Closure.

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m Pressure) y 4

Turbine stop valve' S 10% valve Closure x(4) 8 Instrument

' A or D {

r+

Closure

~

Channele lg 2

First Stage

' Bypass below 165 poig x

x x

4 Instrument A or D l

.w Channels i

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3.

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4 4

4 THIS PAGE DELETED 4

6 4

Amendment No. 73J, 3.1-7a

4 TABLE 4.1-1 (Continued)

REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNC1'IONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS Mini== Frequency (3)

Group (2)

Functional Test A

Trip Chennel and Alarm Every 1 month (1)

High Drywell Pressure Reactor Low Water Level (5).

A Trip Channel and Alarm Every 1 month (1)

A Trip Channel and Alarm Every 3 months High Water Level in Scram Discharge Volume P'

Hain Steam Line Isolation Valve A

Trip Channel and Alarm Every 1 month (1)

Closure y

A Trip Channel and Alarm Every 1 sconth to Turbine Control Valve EHC 011 Pressure A

Trip Channel and Alarm Every 3 months (1)

Turbine First Stage Pressure Permissive A

Trip Channel and Alarm Every 1 month (1) y Turbine Stop Valve Closure A

Trip Channel and Alarm Every 3 months

$- Reactor Pressure Permissive N

A 5

N

TABLE 4.1-2 d

REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT' CALIBRATION MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS Instrument Channel Group (1)

Calibration (4)

Minimum Freq_;r.cf (2)

On Controlled Shutdown C

Comparison to APRM on IRM High Flux Controlled Shutdowne

'APRM High Flux Heat Balance.

Daily B

Output Signal With Standard Pressure Once/ operating cycle Flow Bias Signal 8

Source B

TIP System Traverse Every 1,000 ErPK LPRM Signal A

Standard Pressure Source Every 3 monthe

~ 7.High Reactor Pressure A

Standard Pressure Source Every 3 montha High Drywell Pressure Pressure Standard Every 3 monthe Reactor Low Water Level A

A Water Column Once/ operating cycle High Water Level in Scram Discharge volume Main' Steam Line Isolation A

Note (5)

Note (5)

Valve closure 8-5 Turbine First Stage Pressure A

Standard Pressure Source Every 5 monthe P rmissiva Turbine Control valve 011 A

Note (6)

Once per operating cycle l

'g Pressure' Trip N

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. _. = _ _. _ _ - _ ~. _ _... _ _. _.

DAEC-1 NOTES FOR TABLE 4.1-2

1. A description of three groups is included in the bases of this specification.

2. Calibration test is not required on the part of the system that is not

-l required to be operable or is tripped. Calibration test shall be performed prior to coturning 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 componento,-calibration shall be performed prior to returning to service.

3. Deleted l

4. Response time is not a part of the routine instrument channel test but will be checked once per operating cycle.

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5. Physical inspection and actuation of these position switches-will be performed once per operating cycle, i

6.-Measure time interval base-line data ;ur each operating cycle as l -

follows: From energitation of fast acting solenoid, meu.are time interval to response of oil pressure switch, HTA relay-(RPS) and position response of-l control valves.

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3.1-14 Amendment No. 29.P3,182

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The MsIV closure scram is set to scram when the isolation valves are 10% closed in 3 out of 4 lines. This v-am anticipates the pressure and flux transient which would occur vracq '.4 valves close. By scramming at th e setting, the result.

.anstant is less severe than either the prer wre or flux transient which would otherwise result.

A reactor modo switch is provided which actuates or bypasses the varicus scram functions appropriate to the particular pitnt operating status.

)

The manual scram function is active in all modes, thus providing for a.

manual means of rapidly inserting control rods during all modes of-reactor operation.

3.1-18 Amendment 131.182

TABLE 3.7-A INSTRUMENTATION THAT INITIATES PRIMART CONTAINMENT ISOLATIOft Number of

-Minimum No.

Instrument of Operable Channele valve Groupe Instrument.

Provided by Operated by Channele Per Trip Systess (1)

Instrument Trip Level Setting Design Signal Action (2) 2 (6):

-Reactor Low 2 +170" Indicated 14 vel 4

2,3,4,5 3

water Level (3)

(Sec. Cont., 3 E) 1 Reector Iow Free-5 135 peig 2

4 C

sure (Shutdown Cooling toolation) w 2

Reactor Iow-Low-Low 2 +18.5" indicated 4

1 A

Water Invol level (3) 2 (6).

High Drywell-

~5 2.0 peig 4

2,3,4,8,9*

A Pressure.

(Sec. coat., 3 E) 2 High mediation

$ 3 I Wormel Full 4

1**

3 g

Main Steam Line Power Background (8)

. p 8

Tunnel 2

Low Pressure Main 2 850 poig (7) 4 2

g L@-

Stoem Line-r+

- =. 2 (5)-'

Nigh Flow Main S.140% of Rated 4

1 3

?

Steen lirse Steam riow E

2-

' Mein Ste'un Line 5 200* r.

4 1

3

~ -

Tunnel / Turbine sidg.

%g Migh Temperature-h' 1 Reactor Cloenup-5 40 gped 2

5 D

w -

System High Diff.

Flow

• Group 9 valves isolate on high drywell pressure combined with reactor steem supply low pressure

• • Operates croop 1_velves except Masn Steam Line Isolation valves.

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1 TABLE 3.2-D l

TADtATION MONITORING SYSTEMS THAT INITIATE AND/OR ISOLATE SYSTEMS Number of f

Minimum No.

Instrument

[

of Operable Channele valve Groupe Instrument Provided by Operated by channels Trip Functioit Trip Level Setting Design Signal Action (1) l l

1

' Refreel Area Exhaust Upecale, < 9 mr/hr 2 Inst.-

3 A or B j

Monitos channels i

1 Reactor Building Upecale, < 11 ar/hr 2 Inst.

3 3

Area Exhavet Channele Monitors w

1 Offges Radiation Note 2 2 Inst.

Isote 2 C

j Monitore z

I 2

Main Steam Line

<3X Normal Full 4 Inst.

Note 3 D

I Radiation Mrmitor Fower Background channels I

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2' NOTES FOR TABIP. 3.2-D s

c.

Q 1.

Action s

A. Ceese operation of the refueling equipment.

y B.

Isolate secondary containment and start the standby gas treatment system.

C. Refer to Suboe.ction 3.2.D.1.

D. Refer to Jpecification 3.7.F.

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2.

For trip setting and valves leolated, see Specification 3.2.D.1.a l

ca 3.

Tripe Mechanical Vacuum Puep which ree.alte in a outz:;mt isolation of the Mechanical

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' Vacuum Puep suction valves.

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TABLE 4.2-D MINIMUM TEST AND CALIBRATIOft riu.vureCi FOR RADIATION M0ftITORING SYSTEMS Instrument Functional Source Instrument Instrument channels Test (9)

Calibration (9) check check Once/3 monthe Onco / operating cycle Once/ month Once/ day

1) Refuel Area Exhaust Monitore

2) Reactor Building Area Exhaust Monitore Once/3 monthe Oere/ operating cycle Once/ month once/ day

3) offges Post-treatment Radiation Monitore Once/3 months-(10)

Once/ operating cycle Once/ month once/ day Once/3 monthe (10)

Once/ operating cycle Once/mocth once/ day

4) Offges Pre-treatment Radiation Monitore

5) Main Steam Line Radiation Monitore (1) (3)

Once/ operating cycle once/

Once/ shift operating 4

cycle w

Simulated Automatic Isolation Logic system Functional Test (6) and Logic Test Fa y s.wy (9)

If,ReactorsuildingIsolation Once/ operating cyc.e

2) Standby cas Treatment-System Actuation Once/operatina cycle R

'3) Steam Jet Air Ejector Ofigas Line Isolation once/ operating cycle a

4)' Steam Jet' Air Ejector Charcoal Bed Bypase Once/ operating cycle

.5) Mechanical vacuum Pump Trip and Isolation once/ operating cycle l

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par;* 1 Thoc3 instrument chcnn31s will be eclibrcted using olmulcted electricci signals.

4.

Deleted 5.

Raactor low water level and high drywell pressure are also included on l

Table 4.1-2.

l 6.

The logic system functional tests shall include a calibration of time delay relafs 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 maintenar.ce has been performed on those components, functional tests and calibration shall be performed prior to returning to service.

10. The Instrument Tunctional Test ahall also demonstrate that control room l

alarm annunciation occurs if any of the following conditions existe l

1. Instrument indicates measured levels above the alarm / trip. : point.

2. Instrument indicates a downscale failure.

3. Instrument controle not set in operate mode.

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11. A functional test shall be performed for the ADS manual inhi. bit switches'as part of.the ADS subsystem tests.

3.2-33 Amendment No. 109,JJD,J78,JA3,JE0,182 l

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DAEC-1 Temperature monitoring instrumentation is provided in the main steam line tunnel and turbine building to detect leaks in this area. Trips are provided on this instrumentation and when exceeded, cause closure of isolation valves. See Spec 3.7 for va.1ve Group. The setting is 200'F for the main steam line tunnel detector. For large breaks, the high steam flow instrumentation is a backup to the temperature instrumentation.

High radiation monitors in the main steam line tunnel have been provided to detect y

gross fuel failure as in the control rod drop accident.

A trip setting of 3 times normal f ull-power background is established to close the main steam line drain valves, recirculation loop sample valves, H t rip tha Mechar.ical Vacuum Pump.

For changes in the Hydrogen Water Chemistry hydrogen injection rate, the trip setpoint may be adjusted based on a calculated value of the radiation level expected.

Hydrogen addition will result in an increase in the nitrogen (N-16) activity in the steam due to increased N-16 carryover in the main steam.

Reference subsection 15.4.7 of the Urdated TSAR.

Pressure inatt. mentation is provided to close the main steam isolation valves in RUN Hodo when the main steam line pressure drops below 850 psig.

The Reactor Pressure Vessel thermal transient due to an inadvertent opening of the turbine bypass valves when not in the RUN Hode is less severe than the loss of feedwater analyzed in subsection 15.6.3 of the Updated FSAR, therefore, closure of the Main Steam Isolation valves for thermal transient protection when not in RUN Hode is not required.

Amendment NO. 11A.731.182 3.2-39 l

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DAEC-1 closure (valve CV-4134A open and CV-4134B closing to route offgas 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 t ip. Customarily, the trip setting for bypass valve closure is lower than the trip setting for effgas system isolation valve closure.

Two sets of two radiation monitors are provided which initiate the

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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 ventila-tion isolation and standby gas treatment system operation so that none of the activity released during the refueling accident leaves r

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 back-ground radiation' levels'(accounting for the fi-16 carryover oue to 4

Hydrogen Water Chemistry) will trip the Mechanical Vacuum Pump, which in turn isolates the suction of the Mechanical Vacuum Pump from the j

high and low pressure condensers. This prevents the release of untreated fission products'to the environme'nt via the Mechanical-Vacuum Pump, Flow integrators are used to record the integrated flow of liquid from the drywell-sumps. The alarm unit in each-l l

t Amendment No.7M.12P,,182 3.2-44

DAEC-1 LIN& TING C@NDIE!ON FOR OPERATION SURVE11.1.ANCE REQUIREMENT F..

Mechanical Vacuum Pump F.

Hochanical Vacuum Pump 1.

The mechanical vacuum pump 1.

surveillanes requirements shall be capable of being are given in Table 4.2-D.

isolated and secured on a signal of high radioactivity in the steam lines whenever the main steam isolation valves are open.

2.

During mechanical vacuum pump operation the release rate of gross activity except for halogehs and particulates tath half lives longer than eight days shall not exceed 1 curio /sec.

3.

If the requirenents of 3.7.F.1 or 3.7.F.2 are not met, the Mechatical Vacuum Pump suction valves shall be closed.

o Amendment No. 109.143. 182 3.7-19b a

DAEC-1 NOTES FOR TABLE 3.7-3 i

1.

Isolaticn signals are as follows:

Group 1:

The valves in Group 1 are closed upon any one of the following conditions:

1.

Reactor vessel low-low-low water level.

2.

Main steam line high flow.

3.

Main steam line tunnel / turbine building high temperature.

4.

Low main steam line pressure at turbine inlet (run mode only).

5.

Main condenser low vacuum.

6.

Main steam line high radiation (main steam line drain valves and recirculation loop sa.mple valves only) croup 2:

The valves in Group 2 are closed upo! -

of the following-conditions:

1.

Reactor vessel low water level.

2.

High drywell pressure.

Amendment No. EP.182 3.7 27