ML20073K386

Amend 86 to License DPR-49,changing Tech Specs to Establish Revised Vessel Level Setpoints That Are Consistent W/New Common Instrument Zero Level

ML20073K386
Person / Time
Site:	Duane Arnold
Issue date:	04/01/1983
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Iowa Electric Light & Power Co, Central Iowa Power Cooperative, Corn Belt Power Cooperative
Shared Package
ML20073K389	List: ML20073K386 ML20073K394 ML20073K398
References
DPR-49-A-086 NUDOCS 8304200209
Download: ML20073K386 (15)

Text

'o UNITED STATES

• g NUCLEAR REGULATORY COMMISSION

["

g wAssiwaTow, o. c. zossa g

\\*...+/

IOWA ELECTRIC LIGHT AND POWER COWANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 License No. DPR-49 1.

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

A.

The application for amendment by Iowa Electric t.ight & Power Company, et al, dated December 13, 1982 complies with the standards and re-quirements 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) 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; 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 Spec "

ifications 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:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 86, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

DOh[o!ook PDR

2,-

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 1, 1983 4

8 e

l r

~ATTACHMENTTdLICENSEAMENDMENTNO.86 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Revise the Appendix A Technical Specifications by inserting revised pages listed below. The revised area is identified by the vertical line.

Revised _ Pa'ges 1.1-3 1.1-4 3.1-4 3.1-7 3.2-5 3.2-6 3.2-8 3.2-9 3.2-15 3.2-23 3.2-36 3.2-37 e

OAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 3.

APRM Rod Block when in Run Kode.

For operation with'MFLP0 less

.than or equal to FRP the APRM Control Rod Block setpoint shall be as shown on Figure 2.1-1 and shall be:

S JL (0.66 W + 42)

The definitions used above for the APRM scram trip apply.

For a MFLPD greater than FRP, the APRM Control Rod Block setpoint shall be:

FRP S 1 (0.66 W + 42)

-MFLPD 4.

IRM - The IRM scram shall be set at less than or equal to 120/125 of full scale.

B.

Scram and 2 514.5 inches isolation above vessel on reactor zero (+170" low water indicated level

. level)

C.

Scram - turbine i 10 percent stop valve valve closure closure D.

Turbine control valve f ast closure shall occur within 30 milliseconds of the start of turbine control valve f ast closure.

l l

1 Amendment No. 67, 86 y,y,3

DAEC-1 v

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENI E.

Scram - main,

JL 10 percent steam line-valve closure isolation valve F.

Main steam jt 880 psig

~

isolation valve closure nuclear system low pressure G.

Core spray

_E'363 inches

& LPCI above vessel actuation -

zero (+18.5

-l reactor low inches water level

-indicated level)

H.

HPCI & RCIC JL 464 inches actuation -

above vessel reactor low zero (+119.5

.l water level inches indicated level)

I.

' Main steam jt 464 inches.

isolation above vessel valve closure-zero (+119.5-j.

reactor low

. inches water-level

. indicated

. level.)

J.

Main steam 1 10 inches'Hg isolation.

vacuum valve closure-

-loss of main condenser vacuum-l.

i i

t i

l 1.1-4 Amendment No. 86

..y__,

TABLE 3.1-1 (Continued) to 3

REACTat FHOTECTION SYSTD4 (SCRAM) INSTRtNENTATION REQUIRD4ENT Pu a

Minimum No.

g Modos in Which Number of O

of Operablo Instrument Function Must be I ns t rumon't Channels Operable Channels for Trip Refuel Startup Run Provided System (1)

Trip Function Trip Level Setting (6)

By Design Action (1) 2 High Drywell Pressure 5.2.0 psig X(7)

X(8)

X 4 Instrument A

Channel; 2

Roactor Low Water 2 +170" Indicated X

X X

4 Instrument A

Level Level' (15)

Channels

,ta 2

liigh Water Lavol I r, i 60 Gallons X(2)

X X

4 instrument A

{

Scram Discharry Volume Channels 2

Main Steam Line 13 x Normal Rated X

X X

4 Instrument A

High Radiation Power Background

• Channels 4

Main Stoam Line i 105 Valve Closuro X

X X(13) 8 Instrument A or C isolation valve (3 )(13) (3 ) (I 3 )

Channels Closuro 2

Turbino Control valve within 30 milliseconds X(4) 4 Instrument A or D

~

Fast Closure (Loss of the Start of Control Channels of Control Oil Valve Fast Closure Pressuro) 4 Turbine Stop Valve 1105 Valve Closure X(4 )

8 Instrument A or D Closure Channels 2

First Stage Bypass below 192 psig

'X X

X 4 Instrument A or D Channels

' Alarm setting <l.5 X Normal Rated Power Background

n DAEC-1

+

7.

Not required to be operable when primary containme,nt. integrity is not i

required.

8.

Not required to be operable when the reactor pressure vessel head is not bolted to the vessel.

1 9.

The APRM downscale trip is automatically bypassed when the IRM instrumentation is operable and not high.

10. To be considered operable, APRM's A, B, C and 0.must have at least 9 LPRM inputs while APRM's E and F must have at least 13 LRPM inputs.

2 Additionally each APRM must have at least 2 LPRM inputs per level.

11. W is.the recirculation loop flow in percent of rated.

12. See Subsection 2.1.A.l.

13. The design permits closure of any two lines without a scram being initiated.

1

14. Deleted.

15.

Zero referenced to top of active fuel.

l t

3.1-7 Amendment No. 59, 86 bas.en M ene

-em***

..-ee

?

,+w.w

-m.. - +

-.-..w.

~+

7- - -

n.,

n e,,-,y

- - - - +

-g w,

.g.,

y

,e-y y

,y-

TABLE 3.2-A INSTRUMENTATION TilAT INITIATES PRIMARY CONTAINMENT ISOLATION 9

5 Number of 2

Minimum No.

Instrument 5

of Operable Channels Valve Groups Instrument 2

?

Channels Per Provided by Operated by Trip System (1)

Instrument Trip Level Setting Design Signal Actiun (2) wN

?

2 (6)'

Reactor Low

> t170" Indicated Level 4

2,3,4,5 A

Water Level (3)

(Sec. Cont., 3 E)-

=w 1

Reactor Low Pres-f 135 psig 2

4 C

m sure (Shutdown m

2 Cooling Isolation) 2 Reactor Low-Low-At nr above +119.5" 4

1, 8 A

Water Level indicated level (3) w

. bb 2 (6) liiqh Drywell f 2.0 psig 4

2,3,4,8,9*

A (Sec. Cont., 3 E)

Pressure 2

High Radiation 13 X Normal Rated 4

1 B

Main Steam Line Power Background Tunnel 2

Low Pressure Main 1 880 psig (7) 4 1

B Steam Line 2 (5) liigh Flow Main

$ 140% of Rated 4

1 B

Steam Line Steam Flow

__ 200* F.

4 1

B 2

Main Steam Line Tunnel / Turbine Bldg.

High Temperature 1

Reactor Cleanup 5 40 gpmd 2

S D

System liigh Dif f.

Flow i

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

0AEC-1 40TES FOR TABLE 3.2-A 1.

Whenever Primary Containment integrity is required by Subsection 3.7, i

there shall be two coerable or tripped systems for each function.

2.

If the first column cannot be met for one of the trip systems, that trip system shall be trioped or the appropriate action listed below shall be taken.

ACTION A - Se in at least HOT SHUTOOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

t ACTION B - Se in at least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ACTION C - Close the affected system isolation valves within one hour and 1

declare the affected system inoperable.

1 ACTIO" D - Be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION E - Isolate secondary containment and start the standby gas treatment system.

I 3.

Zero re#erence; to top of active fuel.*

• Top of the active fuel zone is defincd to be 344.5 inches above vessel zero (see Bases 3.2).

3.2-6 Amendment No. 59, g4, 86

TABLE 3.2-8 E

INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS

$n Minimum No.

z P

of Operable Number of Instrument instrument Channels 03 Channels Per Trip System (1)

Trip Function Trip Level-Setting

'Provided by Design Remarks 2

Reactor Low-Low JL + 119.5 in. indicated 4 HPCI & RCIC Initiates HPCI & RCIC Water Level level (4)

Instrument Channels 2

Reactor Low-Low-Low 2 + 18.5 in, indicated 4 Core Spray & RilR

1. In conjunction with Water Level level (4)

Instrument Channels Low Reactor Pressure initiates Core Spray 4 ADS Instrument and LPCI Channels

2. In conjunction with w

confirmatory low m

f3 level liigh Drywell Pressure, 120 second time delay and LPCI or Core Spray pump interlock initiates Auto Blowdown (AUS)

3. Initiates starting of Diesel Generator 2

Reactor liigh Water i + 211 in. indicated 2 Instrument Channels Trips llPCI a'nd RCIC turbines Level level (4) 4 l-

TABLE 3.2-8-(Coutinued)

INSTRIJMENTATION TilAT INITIATES OR CONTROLS Tile CORE AND CONTAINMENT COOLING SYSTEMS Minimum No.

{

of Operable Number of Instrument s

Instrument Channels

[

Channels Per g

Trip System (1)

Trip Function Trip Level Setting Provided by Design Remarks 5

1 Reactor Low Level

.2 + 305.5 in above 2 Instrument Channels Prevents inadvertent (inside shroud) vessel zero (2/3 core operation of contain-height) ment spray during accident condition 2

Containment High 1 < p < 2 psig 4 Instrument Channels Prevents inadvertent

. operation of contain-Pressure ment spray during w

6 accident' condition

.o 1

Confirmatory Low 1 + 170 in. indicated 2 Instrument Channels AUS Permissive Level level (4) 2 liigh Drywell s'2.0 psig 4 tiPCI Instrument 1.

Initiates Core Channels Spray LPCl; HPCI Pressure 2

Reactor Low 2 450 psig 4 Instrument Channels Permissive for open

-Core Spray and LCPI Pressure Injection valves.

Coincident with high drywell pressure, start LPCI and Core Spray pumps 6

OAEC-1 NOTES FOR TABLE 3.2-6 1.

Whenever any CSCS subsystem is required tur Subsection 3.5 to be operable, there.shall be two operable trip systems.- If the first column cannot be met for one lof the trip systems, that trip system shall be placed in the tripped condition or the reactor shall be placed in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

Close isolation valves in RCIC subsystem.

3.

Close isolation -valves in HPCI subsystem.

4.

Zero referenced to top of active fuel.*

S.

HPCI has only one trip system for these sensors.

6.

The relay drop-out voltage will be measured once per operating cycle and the data examined for evidence of relay deterioration.

i 7.

Four undervoltage relays with integral timers per 4KV bus. The relay outout contacts are-connected to form a one-out-of-two-twice coincident logic With one relay inoperable, operation may proceed provided that the matrix.

-inoperable relay is placed in the tripped condition within one hour.

l l

l

• Top of active fuel zone is defined to be 344.5 inches above vessel zero (see i

Sases 3.2).

Amendment No. 39, 86 3.2-15 l

L

TABLE 3,2-G

,E INSTRUMENTATION THAT INIIIATES RECIRCULATION PUMP TRIP E

Minimum Number of Number of Instrument

[

Operable Instrument Channels Provided Channels per Trip o

System (1)

Instrument Trip Level Setting By Design Action (1) 1 (AfWS) Reactor High i 1120 psig 4

(2)

Pressure 1

(ATWS) Reactor Low-2 +119.5 in indicated 4

(2)

Low Water level (5)

Level 1

(EOC) RPT Logic N/A 2

(3) 1 (E0C) RPT System i

• msec (4) 2 (3)

'?

(Response Time)

"w NOTES FOR TABLE 3.2-G Whenever the reactor is in the RUN Mode, there shall be one operable trip system for each parameter for 1.

operating recirculation pump.

If this cannot be met, the indicated action shall be taken.

Reduce power and place the mode selector-switch in a mode other than the RUN Mode.

2.

3.

Two EOC RPT systems exist, either of which will trip both recirculation pumps. The systems will be individually functionally tested monthly.

If the test period for*one RPT system exceeds two consecutive If both RPT systems are inoperable or if one RPT system hours, the system will be declared inoperable.

is inoperable for more than 72 consecutive hours, an orderly power reduction shall be initiated arid the reactor power shall be less than 85% within four hours.

This response time is from initiation of turbine control valve fast closure to actuation of the breaker 4.

auxiliary contact.

5.

Zero referenced to top of active fuel.

To be determined by testing after installation.

(Valve to be design requirement for breaker opening less difference between cycle time for loaded vs. unloaded breaker.)

Top of active fuel zone is defined to be 344.5" above vessel zero (see Bases 3.2).

DAEC-1 explicitly stated where the high and low values are both critical and may have a substantial effect on safety.

The setpoints of other instrumentation', where only the high or low end of the setting has a direct bearing on safety, are chosen at a level away from the normal operating range to prevent inadvertent actuation of the safety system involved and exposure to abnormal situations.

Actuation of primary containment valves is initiated by protective instrumentation shown in Table 3.2-A which senses the conditions for which isolation is required. Such instrumentation must be available whenever primary containment integrity is required.

The instrumentation which initiates primary system isolation is connected in a dual bus arrangement.

Many of the reactor water level trip settings are defined or described in terms of '.' inches above the top of the active fuel."

In the new reload fuel the column of fuel pellets in each fuel pin of a bundle is 150 inches long; whereas in the initial core load and first few reloads it was 144 inches long.

Thus, during the period of reloads until all of the 144 inch bundles are replaced with bundles with 150 inches of fuel pellets the core will be composed of fuel bundles with fuel pins containing differing lengths of fuel pellet c

columns and the term " top of active fuel" no longer has a precise physical Since the basis of all safety analyses is the absolute level (inches meaning.

above vessel zero) of the trip settings', the " top of the active fuel" has been This definition is-arbitrarily defined to be 344.5 inches above vessel zero.

the same as that given by the FSAR for the initial core and maintains the consistency between the various level definitions given in the FSAR and the technical specifications.

3.2-36 Amendment No. 86

DAEC-1 4

adequate to prevent uncovering the core in the case of a break in the t

' largest line assuming a 60 second valve closing time.

Required closing times are less than this.

The low-low reactor water level instrumentation is set to trip when reactor I This trip closes water level is 119.5" above the top of the active fuel.

Main Steam Line Isolation Valves, Main Steam Drain Valves, Recirc Sample Valves (Group 1), initiates the HPCI and RCIC and trips the recirculation The low-low-low reactor water level instrumentation is set to trip pumps.

This trip when the water level is 18.5" above the top of the active fuel.

activates the remainder of the CSCS subsystems, closes Group 7 valves, and These trip level settings were starts the emergency diesel generators.

chosen to be high enough to prevent spurious actuation but low enough to initiate CSCS operation and primary system isolation so that post accident cooling can be accomplished and the guidelines of 10CFR100 will not be For large breaks up to the complete circumferential break of a exceeded.

22-inch recirculation line and with the trip setting given above, CSCS initiation and primary system isolation are init,iated-in' time to meet the above criteria. Reference Paragraph 6.5.4 FSAR.

l 3.2-37 Amendment No~. 86 L