ML20043B530

From kanterella
Jump to navigation Jump to search
Amend 36 to License NPF-62,adding Action to Tech Spec 3.5.1 for Inoperable Automatic Depressurization Sys Low Pressure Alarm Sys Instrumentation Channnel
ML20043B530
Person / Time
Site: Clinton 
Issue date: 05/24/1990
From: Jocelyn Craig
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20043B531 List:
References
NUDOCS 9005300156
Download: ML20043B530 (5)


Text

_._

?

j f,

0, UNITED STATES

't 9

8-NUCLEAR REGULATORY COMMISSION n

[

I WASHINGTON, D. C. 20555 l

ILLIN0IS POWER COMPANY,LET AL.

DOCKET NO. 50-461 CLINTON~ POWER STATION.-UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE

-i Amendment No. 36 i

License No. NPF-62 1.

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

Theapplicationforamendmentby(thelicensees)datedOctober30,IllinoisPowe A.

Soyland Power Cooperative, Inc.

1987, 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.

. Thel facility will operate in conformity with the application, the I

provisions of the Act, and the rules and regulations of.the Comission; C.

.Thereisreasonableassurance(1)thattheactivitiesauthorizedby 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 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 Commission's regulations and all applicable requirements have been satisfied.

L 2.

Accordingly, the license is amended by changes to the Technical Specifications as'indicatedintheattachmenttothislicenseamendment,andparagraph2.C.(2) of facility Operating License No NPF-62 is hereby amended to read as follows:

l

  • Illinois Power Company is authorized to act as agent for Soyland Power L

Cooperative, Inc. and has exclusive responsibility and control over the.

physical construction, operation and maintenance of the facility.

%;;;;r#

9005300156 900524 PDR ADOCK 05000461 P

PDC

~ '~ ~ l

.c e

2 Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.- 36, are hereby incorporated into this license.

Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

9

~3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

(

In

}l Ik John W.

raig, Direct r Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance:

May 24,1990 l

l 1

l.

1

~~

n.

s

'*,i

,l 1

~ ATTACHMENT'T0 LICENSE AMENDMENT NO. 36-FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 Replace the following > ages of the Appendix "A" Technical Specifications with the attached pages. Tie revised pages are identified by amendment number and-l contain-vertical lines indicating the area of change.

t Remove.

Insert 3/4 5-3 3/4 5-3 3/4 5-4 3/4 5-4 d

i f

4-

\\

+-

l'

EMERGENCY CORE COOLING SYSTEMS ~

L..

ECCS -OPERATING LIMITING CONDITION FOR OPERATION (Continued) 3.5.1' ACTION (Continued):

e.

For ECCS Divisions I and II, provided that ECCS Division III is OPERABLE and Divisions I and II are otherwise OPERABLE:-

1.

With one of the above required ADS valves inoperable, restore the

. inoperable ADS valve to.0PERABLE status within 14 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce reactor steam.

dome pressure to { 100 psig within the next 24 hourt,.

2.

With two or more of the above required ADS valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce reactor steam dome pressureto{100psigwithinthenext24 hours.

f.

With an ADS accumulator low pressure alarm system instrumentation channel (s) inoperable:

1.

Determine the associated ADS accumulator system pressure from alternate indication and verify that ADS accumulator pressure is greater than or equal to 140 psig at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, 2.

Restore the inoperable ADS accumulator low pressure alarm system instrumentation channel (s) to OPERABLE status within'30 days or submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and-the plans for restoring the instrument (s) to OPERABLE status, 3.

The provisions of Specification 3.0.4 are not applicable, g.'

In the event an ECCS system is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the-Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to.date.

The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

SURVEILLANCEREQUIREMENTS 4.5.1 ECCS Divisions I, II, and III shall be demonstrated OPERABLE by:

a.

At least once per 31 days for the LPCS, LPCI, and HPCS systems:

1.

Verifying by venting at the high point vents that the system piping from the pump discharge valve to the system isolation valve is filled with water.

CLINTON - UNIT 1 3/4 5-3 Amendment No. 36

~ ~

J

i

]

~ r g.

EMEitGENCY CORE C0OLING SYSTEMS ECCS - OPERATTHG-3 SURVEILLANCE REQUIREMENTS (Continued) 4.5.1:(Continued) 2.

Verifying that each valve (manual, power operated, or automatic) in c

the flow path that is not locked, sealed, or otherwise secured in position, is in its correct

  • position, b.

Verifying that when tested pursuant to Specification 4.0.5 each:

i 1..

LPCS pump develops a flow of at least 5010 gpm with a pump differential pressure greater than er equal to 276 psid.

2.

LPCI pump develops a flow of at least 5050 gpm with a pump differential pressure greater than or equal to 113 psid, j

3.

HPCS pump develops a flow of at least 5010 gpm with a pump differential pressure greater than or equal to 363 psid.

For the LPCS, LPCI, and HPCS systems, at least once per 18 months perform-

c. -

ing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence and verifying that each automatic valve in the flow path actuates to its correct position.

Actual injection of coolant into the reactor vessel may be excluded from this test.

d.

For the HPCS system, at least once per 18 months, verifying that the suction is automatically transferred from the RCIC storage tank to the suppression pool on a RCIC storage tank low water level signal and on a suppression pool = high water level signal.

e.

For the ADS by:

1.

At-least once per 31 days, performing a CHANNEL FUNCTIONAL TEST of the accumulator low pressure alarm system.

4 2.-

At least once per 18 months, performing a system functional test which i

includes simulated automatic actuation of the system throughout its emergency operating sequence, but excluding actual valve actuation.

l 3.

At'least once per 18 months, manually opening each ADS valve when the l

reactor steam dome pressure is greater than or equal to 100 psig** and observing that:

i L

a.

The control valve or bypass valve position responds accordingly, b

or b.

There'is a corresponding change in the measured steam flow, or c.

The acoustic tail pipe monitor alarms.

4.

At least once per 18 months, performing a CHANNEL CALIBRATION of the accumulator low pressure alarm system and verifying an alarm setpoint of,> 140 psig on decreasing pressure.

I

  • Except that an automatic valve capable of automatic return to its ECCS posi-tion when an ECCS signal is present may be in position for another mode of operation.
    • The provisions of Specification 4.0.4 are not applicable provided the surveil-lance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate l '

to perform the test.

CLINTON - UNIT 1 3/4 5-4 Amendment No. 36 1

vs m.,

--w