Text

Amend 85 to License NPF-62,increasing AOT for Differential Temp Instruments Associated W/Crvics
	ML20059J282
Person / Time
Site:	Clinton
Issue date:	11/05/1993
From:	Dyer J; Office of Nuclear Reactor Regulation
To:	;
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ML20059J284	List: ML20059J282; ML20059J286;
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	NUDOCS 9311120148
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UNITED STATES

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NUCLEAR REGULATORY COMMISSION i

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WASHINGTON, D.C. 205554001 3

1 ILLIN0IS POWER COMPANY. ET AL.

DOCKET NO.'50-461 CLINTON POWER STATION. UNIT NO. 1 l

i AMENDMENT TO FACILITY OPERATING LICENSE

-l Amendment No. 85' License No. NPF-62~

1 1.

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

A.

The application.for amendment by Illinois Power Company * (IP), and i

Soyland Power Cooperative, Inc. (the licensees) dated December 15, 1992, complies with the standards and requirements of the Atomic j

Energy Act of 1954,.as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I-1 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 (i) that the activities authorized by l

this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be

-t conducted in compliance with the Commission's regulations;

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D.

The issuance of this amendment will not be inimical to the common l

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 i

been satisfied.

I 2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and j

paragraph 2.C.(2) of facility Operating License No.-NPF-62-is hereby

'i amended to read as follows:

Illinois Power Company is authorized to act as agent for Soyland Power Cooperative, Inc. and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

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9311120148 931105 9{

i PDR ADOCK 05000461 f4 1

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(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.

85, are hereby incorporated into this license.

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

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION V 9 James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 5, 1993

ATTACHMENT TO LICENSE AMENDMENT NO. 85 i

FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461-Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages, indicated by an asterisk, are provided to maintain document completeness.

Remove Pages Insert Paoes 3/4 3-11 3/4,3-11 t

3/4 3-12*

i 3/4 3-19 3/4 3-19 3/4 3-20*

3/4 3-20*

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INSTRUMENTATION-il 3/4.3.2 CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM LIMITING CONDITION FOR OPERATION j

i 3.3.2 The containment.and reactor vessel isolation control system-(CRVICS) j

. channels shown in Table 3.3.2-l'shall. be OPERABLE

with their trip setpoints i

set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME as shown in Table 3.3.2-3.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

a.

With a CRVICS channel trip setpoint less conservative than'the value shown in the Allowable Value column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b.

For CRVICS Main Steam Line Isolation Trip Functions:

l 1.

With one of the four channels required for any Trip Function l

inoperable, operation may continue provided the inoperable channel 1

is placed in the tripped condition within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . The provisions i

of Specification 3.0.4 are not applicable.

l 2.

With two of the four channels required for any Trip Function.

j inoperable, place one channel in the tripped condition within six hours provided no tripped channel for that Trip Function already '

exists. The provisions of Specification 3.0.4 are not applicable.

3.

With three or four channels required for any Trip Function!

inoperable, take the ACTION required by Table 3.3.2-1.

c.

For other CRVICS Isolation Trip functions.

i 1.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip ' System requirement for one trip i

system, place the inoperable channel (s) and/or that trip system-in d

the tripped condition ** within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The provisions of

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Specification 3.0.4 are not applicable.

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For CRVICS Main Steam Line Isolation Trip Function, a channel may be placed.

in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required surveillance provided at least two OPERABLE channels are monitoring that parameter.

For other CRVICS Isolation Trip function, a channel may be placed in an in-l operable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required surveillance provided the requirements of Table 3.3.2-1 are fulfilled.

- An inoperable channel need not be placed in the tripped condition where this I

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would cause the Trip Function to occur.

In these cases, the inoperable channel shall. be restored to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or the ACTION j

required by Table 3.3.2-1 for that Trip' Function shall be taken.

i CLINTON - UNIT 1 3/4 3-11 Amendment' No. 85 l

1 1NSTRUMENTATION CONTAINMENT AND REACTOR VESSELr1 SOLATION CONTROL SYSTEM LIMITING CONDITION FOR'0PERATION (Continued) 3.3.2 ' ACTION fContinued):

2.

With the number of OPERABLE channels less than required by the.

Minimum OPERABLE Channels per Trip System requirement for both trip

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systems, place at least one trip system

in the tripped condition-i within I hour and take the ACTION required by Table 3.3.2-1.

SURVEittANCE REOUTREMENTS Each CRVICS channel shall be demonsfrated OPERABLE by the performance' 4.3.2.1 of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION cperations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.2.1-1.

4.3.2.2 LOGIC SYSTEM FUNCTIONAt TESTS shall be performed at least once per 18

-l months.

CRVICS main steam line isolation divisional logic and portions of the channel coincident logic shall be manually tested independent of the SELF TEST

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SYSTEM during each refueling outage. Each of the two trip systems or-i divisions of the CRVICS trip system logic shall be alternately and manually j

tested independent of the SELF TEST SYSTEM during every other refueling outage. All manual testing shall be completed such that all trip functions are tested at least once every four fuel cycles..

['

4.3.2.3 The CRVICS RESPONSE TIME of each CRVICS trip function shown in Table 3.3.2-3 shall be demonstrated to be within its limit at least once per 18 conths.

Each test shall include at least one logic train tested at least once

.i per 35 months, and one channel per trip function such that all channels are tested at least once every N times 18 months, where N is the total number of l

redundant channels in a specific CRVICS trip function.

i

The trip system need not be placed in the tripped condition if this would cause the Trip Function to occur. ifhen a trip system can be i

tripped condition without causing the_ Trip Function to occur,placed in the place the trip-system with the most inoperable channels in the trip systems have the same number of inoperable channels, ped condition;'if both place'either trip system in the tripped condition.

.CLINTON - UNIT 1 3/4 3-12 Amendment No. 71

=!

l TABLE 3.3.2-1 (Continued)

CRVICS INSTRUMENTATION ACTION' ACTION 20 -

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

ACTION 21 -

Deleted.

3 ACTION 22 -

With one channel in either trip system inoperable restore the manual initiation function to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 23 -

Be in at least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 24 -

Be in at least STARTUP within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 25 -

CORE ALTERATIONS, operations with a potential for draining the reactor vessel, and handling irradiated fuel in the primary or secondary containment may continue provided that SECONDARY CONTAINMENT INTEGRITY is established with the standby gas treatment system operating within I hour.

ACTION 26 -

Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 27 -

Close the affected system isolation valves within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months " and declare the affected system inoperable.

ACTION 28 -

Lock the affected system isolation valves closed within I hour" and declare the affected system inoperable.

l-ACTION 29 -

Operations may continue provided that the affected CRVICS isolation valve (s) are closed within I hour and, as appropriate, declare the affected system or component inoperable and follow any ACTIONS appropriate to Specifications of the affected system. Otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

For inoperable Main Steam Line Tunnel oTemp.-High Trip Functions, this time limit may be increased to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provided at least two Main Steam Line Tunnel Temp.-High channels remain OPERABLE.

- For inoperable ATemp.-High Trip Functions, this time limit may be increased to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provided the Minimum OPERABLE Channels per Trip System requirement for the Amnient Temperature-High Trip function for the associated area is met for both Trip Systems.

CLINTON - UNIT I 3/4 3-19 Amendment No. 85

n TABLE 3.3.2-2 r

CRVICS INSTRUMENTATION SETPOINTS E-E 1 RIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE h

1.

PRIMARY AND SECONDARY CONTAINMENT ISOLATION H

a.

Reactor Vessel Water Level -

Low Low, Level 2 1 -45.5 in.*

1 -47.7 in, b.

Reactor Vessel Water Level - Low Low, Level 2 (ECCS Div. I and II) 1 -45.5 in.*

1 -47.7 in, c.

Reactor Vessel Water Level - Low Low, level 2 (ECCS Div. III) 1 -45.5 in.*

1 -47.7 in.

d.

Drywell Pressure - High i 1.68 psig i 1.88 psig

',k e.

Drywell Pressure - High 4

(ECCS Div. I and II) 1 1.68 psig i 1.88 psig o

f.

Drywell Pressure - High (ECCS Div.III) i 1.68 psig i 1.88 psig g.

Containment Building Fuel Transfer Pool Ventilation Plenum Radiation - High 1 100 mR/hr.

1 500 mR/hr h.

Containment Building Exhaust-

)

Radiation - High-1 100 mR/hr S 400 mR/hr

- g 1.

Containment Building Continuous

- m Containment Purge (CCP)-Exhaust QE Radiation - High-

< 100 mR/hr.

< 400 mR/hr co 2

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Reactor Vessel Water Level Low y -.

Low Low-Level 1 1-145.5 in.*

1-147,7 in.

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ML20059J282

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