ML20059M451

Amend 48 to License NPF-62,clarifying Divisional Arrangement for Reactor Vessel Water Level & Drywell Pressure Instruments Listed in Tech Spec Tables 3.3.2-1 & 3.3.3-1 & Combinational Logic Scheme for Reactor Water Low Level 2

ML20059M451
Person / Time
Site:	Clinton
Issue date:	09/25/1990
From:	Hannon J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20059M453	List: ML20059M451 ML20059M454
References
NUDOCS 9010040188
Download: ML20059M451 (12)

Text

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UNITED STATES

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y 3m g

NUCLEAR REGULATORY COMMISSION E

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WASHINGTON o. C. 20%5 I

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l ILLIN0IS POWER COMPANY. ET AL.

DOCKET NO. 50-461 CLINTON POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 -

l License No. NPF-62 1.

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

A.

Theapplicationforamendmentby1111noisPowerCompany*(IP),

and Soyland Power Cooperative Inc. (the licensees) dated February 5,1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Com-mission'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' Comission; C.

Thereisreasonableassurance(i)thattheactivitiesauthoriz2dby 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 Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-l cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No NPF-62 is hereby amended to read as follows:

1

• 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.

901004010e 900925 PDR ADOCK 05000461:

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! (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the I

Environmental Protection Plan contained in Appendix B, as revised i

through Amendment No. 48, are hereby incorporated into this license.

Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental t

Protection Plan.

3.

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

t FOR THE NUCLEAR REGULATORY COMMISSION

_=: x

/ John N. Hannon, Acting Director Project Directorate III-3 Division of Reactor Projects - 111, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuar,ce: September 25, 1990 i

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ATTACWENT TO LICENSE AMENDMENT NO. 48 FACILITY OPERATING LICENSE NO. NPT-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, j

Remove Insert 3/4 3-13 3/4 3-13 3/4 3-18 3/4 3-18 3/4 3-18a 3/4 3-36 3/4 3 36 3/4 3-37 3/4 3-37 i

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'53LE 3.3.2-1

'5 CRVICS INSTRUMENTATION E

MINIMUM OPERABLE APPLICABLE g

ISOLATION CHANNELS PER TRIP OPERATIOMAL q

TRID FUNCTION SIGNAL t_i_

SYSTEM CONDITION ACTION

~

1.

PRIMARY AND SECONDARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level-Low Low, B(b)(f) 2(a) 1, 2, 3 20 Level 2 25 IZ *I 1, 2, 3 29 b.

Reactor Vessel Water Level-Low B

Low, Level 2 (ECCS Div. I and II) c.

Reactor Vessel Water Level-tow, Low, B

2(a)(m) 1, 2, 3 29 Level 2 (HPCS-NSPS Div. III and IV) d.

Drywell Pressure - High L(b)(;

2(*}

1, 2, 3 20 I2 *)

e.

Drywell Pressure - High L

1,2,3 29 (ECCS Div. I and II) w f.

Drywell Pressure - High (HPCS-NSPS L

2(a)(n)

[

1, 2, 3 29 4

Div. III and IV) g.

Contairment Building Fuel Transfer Z(b)(f) 2 *)

25 I

Pool Ventilation Plenum Radiation - High h.

Containment Buildin ; Exhaust Radiation - High M(b)(f) 2(a) 1, 2, 3 29 25 i.

Containment Building Continuous 5(b)(f) 2(a) 1, 2, 3 29 Containment Purge (CCP) Exhaust 25 E

Radiation - High j.

Reactor Vessel Water Level-Low U

2(k) 1, 2, 3 29 Low Low, Level 1 25

=

I III) k.

Containment Pressure-High P

I 1, 2, 3 29

,5 25 0

p TABLE 3.3.2-1 (Contintet)

E g,

CRVICS INSTRUMENTATION z

e3 MININUM OPLRABLE APPLICABLE i

ISOLATION CHANNELS PER TRIP OPERATIONAL TRIP FUNCTION SIGNAL ii SYSTEN CONDITION Aril0N

(

1.

Main Steam Line Radiation - High C

2(a) 1, 2, 3 23 f

2 'I m.

Fuel Building Exhaust (b)(f)(j) 1, 2, 3 25 Radiation - High 25 n.

Manual Initiation R(b)(f) 1 1,2,3 26 t

25 APPLICABLE ISOLATION APPLICABLE OPERATIONAL

{

2.

MIN STEAM LINE ISOLATION t SIGNAL TABLE NOTES CONDITIONS ACTION y

a.

Reactor Vessel Water level-tow Low Low, tevel 1 U

NA 1,2,3 20 b.

Main Steam Line Radiation - High C

d-1,2,3 23 i

c.

Main Steam Line Pressure - Low H

MA 1

23 d.

Main Steam Line Flow - High D

NA 1, 2, 3 23 e.

Condenser Vacuum - Low '

J MA 1, 2**, 3**

23 f.

Main Steam Line Tunnel Temp.

- High E

NA 1, 2, 3 23 g.

Main Steam Line Tunnel a Temp.

?

- High F

M4 1, 2, 3 23 h.

Main Steam Line Turbine 81dg.

Temp. - High G

p 1,2,3 23 l

g i.

Manual Initiation R

NA 1, 2, 3 22

• o i

i i

e I

o in

]

i t

p TABLE 3.3.2-1 (Continued)

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CRVICS INSTRUDENTATION g

e MINIMUM OPERA 8tE APPLICABLE ISOLATION CHANNELS PER TRIP OPERATIONAL TRIP FUNCTION SIGNAL tt SYSTEM CONDITION ACTION l

5.

RHR SYSTEM ISOLATION 1

a.

RHR Heat Exchanger A, B i

t Ambient Temperature - High T

1/ room (g) 1, 2, 3 28 l

6 b.

RHR Heat Exchanger A, B ATemp. - High 5

1/roomg) 1, 2, 3 28 i

L 1

c.

Reactor Wessel Water g2,)

1 Level - Low, Level 3 A

1,2,3 28 w

d.

Reactor Vessel Water Level -

1 g) w Low Low Low, Level 1 U

2 1,2,3 28 i

e.

Reactor Vessel (RHR Cut-in Z '}

I Pemissive) Pressere - High X

1, 2, 3 28 f.

Drywell Pressure - High 2f,N

1) RHR Test tir.es L

1, 2, 3 28

2) Fuel Pool Cooling L

2 1,2,3 28 g.

Manual Initiation R

1 1,2,3 26 o

a n

1

, - + ---

4w, 4

,+

y w

, e w

<=

,. -...,,. - - -,,.,. -, +

-,--..-e.,,--w

,-.wwe,,+-

TABLE 3.3.2-1 (Continued)

CRVICS INSTRUMENTATION TABLE NOTATIONS 1

When handling irradiated fuel in the primary or secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

When handling irradiated fuel in the primary containment (building) and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

With any control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

When any turbine stop valve is greater _than 95% open or the reactor mode switch is in the run position, t

Main steam line isolation trip functions have 2 out-of-4 isoletion. logic except for tne main steam line flow - high trip function which has 2-out-of-4 isolation logic for each main steam line.

tt See Specification 3.6.4 Table 3.6.4-1 for valves which are actuated by these isolation signals.

(a) A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the trip system in the tripped con-dition provided at least one'other OPERA 8LE channel in the same trip t

system is monitoring that parameter.

l (b) Also actuates the standby gas treatment system.

(c) Deleted (d) Also trips and isolates the mechanical vacuum pumps.

(e) Isolates RWCU valves 1G33-F001 and 1G33-F004 only.

(f) Also actuates secondary containment ventilation isolation dampers per Table 3.6.6.2-1.

(g) Manual Switch closes RWCU system inboard isolation valves F001, F028 j

F053, F040 and outboard isolation valves F004, F039, F034 and F054.

(h) Vacuum breaker isolation valves require RCIC system steam supply pressure low coincident with drywell pressure high for isolation of vacuum breaker isolation valves.

(1) A single manual isolation switch isolates outboard steam supply line isolation valve (F064) and the RCIC p mp suction from suppression pool valve (F031) only following a manual or automatic (Reactor Vessel Water Level 2) RCIC system initiation.

(j) Only actuates secondary containment ventilation isolation dampers per l

Table 3.6.6.2-1.

Note tt is not applicable to this Trip Function.

(k) A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the trip system in the trip con-dition provided that the redundant trip system is OPERABLE and monitoring that parameter.

(1) Not required to be OPERABLE when valves IVR002A,B and IVQOO6A,B are sealed-closed in accordance with Specification 3.6.4.

I CLINTON - UNIT 1 3/4 3-18 Amendment No.25,#,48 j

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TABLE 3.3. 2-1-(Continued)

CRVICS INSTRUMENTATION TABLE NOTATIONS I

(m) -Four reactor vessel water level trip channels are logically combined in a one-out-of-two-twice _ configuration._ For the purposes of the associated ACTION, each one-out-of-two logic is defined as a separate trip system.

(n). Four drywell pressure trip channels are logically combined in a one-out-os-two-twice configuration. 'For the purposes of the associated ACTION, each one-out-of-two logic is defined as a separate trip system.

(p) Each channel-consists of five temperature modules and their associated sensore.

A channcl is OPERABLE'if and only if five temperature modules and their associated sensors.are OPERABLE.

l 1

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CLINTON - UNIT 1 3/4 3-18a Amendment No. 48' 1

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b TABLE 3.3.3-1 (Continued) b

-iMGsGENCY CORE COOLING SYSTEM ACTUATION INS',ASIENTATION 1

E

'MININUM OPERABtE-APPLICABLE-CHAf90ELS PER TRIP OPERATIONPi.

c-5 TRIP FUNCTION FUNCTION C00SITIOF3 ACTION

-e 8.

DIVISIOpi II TRIP SYSTEM 1.

RHR 8 & C (LPCI 9mDE) a.

Reactor Vessel Water Level - Low Low low, Level 1 2

1, 2, 3, 4*, 5*

30 2

1, 2, 3 30 b.

Drywell Pressure - High 4,)

1,2,3 32 4

c.

Reactor Vessel Pressure-Low (LPCI Injection Va?~, - Permissive) 4 *, 5* -

33 d.

LPCI Pump (B) Start T w Delay Logg Card 1

1, 2, 3,'4*, 5*

32 LPCI Pump (B) Discharge Flow - Low,,

1 1, 2, 3, 4*, 5*

40 e.

w) f.

LPCI Pump (C) Discharge. Flow - Low.

1(b) 1, 2 -3 4*, 5*

40

- g.

Manual Initiation 1

1, 2, 0, 4*, 5*

35

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m AUTOMATIC DEPRESSURIZATION SY.34 TRIP SYSTEM "2"#

2.

ADS LOGIC "8" afb F" a.

Reactor Vessel Water Level Low Low, g

2,,))

1, 2, 3 30 Level 1 g

b.

Drywell Pressure - Higt.

2 1,2,3 30 c.

ADS Timer 1

1,2,3 32 d.

Reactor Vessel Water Level Low,' Level 3 (Perrissive) 1-

-1, 2, 3 32 e.

'LPCI Pump (8 and.C) Discharge Pressure -

g)

-High (Permissive) 2/ pump 1,2,3 32 f.

ADS Dry w11 Pressure Bypass Timer

-2 1,2,3 30 g.

Man sal Inhibit ADS Switch 1

- 1, 2. 3 35 h.

Manual Initiation 2

1,-2, 3 35-

_. - -.. _ - -. -.... ~. _..,. -. - _.. _ -

_ = - -

TABLE 3.3.3-1 (Continued) r,

.C 2

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION E

a MINIMUM OPERABLE APPLICABLE c-Z.!

CHANNELS PER TRIP OPERATIONAL H

TRIP FUNCTION.

FUNCTION CONDITIONS ACTION v

C.

DIVISION III TRIP SYSTEM 1.

HPCS SYSTEM s

.a.

Reactor Vessel Water Level-Low,. Low, Level 2_

4 1, 2, 3, 4 *, 5*

~36 b.

Drywell Pressure - High t 4(c)(,g) 7 I, 2, 3 36 c.

Reactor Vessel Water Level-High, Level 8 2

1, 2, 3, 4*, 5*

32 I

i d.

RCIC' Storage Tank Level-Low 2((d)(a) 1, 2,_3, 4*, 5*

37 d)(a)

Suppression Pool Water Level-High,,

2 1, 2, 3, 4*, 5*-

37 e.

i HPCS Pump Discharge Pressg e-High 1

1, 2, 3, 4*,-5*

'40 g.

HPCS System Flow Rate-Low 1

.1, 2, 3, 4*, 5*

40 m}

h.

Manuai. Initiation t 1

1, 2, 3, 4*, 5* [

MINIMUM APPLICABLE e

T01.'l NO.

CHANNELS OPERABLE OPERATIONAL OF Chid:cLS TO TRIT CHAP'NELS CONDITIONS ACTION D.

LOSS Of POWER 1.

4.16-kV Emergency Bus _Undervoltage (Loss of Voltage) a.

Divisions I & II 2/ Division' 2/ Division 2/ Division 1, 2, 3, 4**, 5**

38 b.

Division III 4

2 4

1, 2, 3, 4**, 5**

38 2.

4.16 LV Energency Bus Undervoltage y

-(Degraded Voltage) g a.

Divisions I & II 2/ Division' 2/ Division 2/ Division 1, 2, "3, 4**, 5**

39 g-b.

Division III tt 3

3

.3-1, 2.,3, 4**, 5**

39

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l TABLE 3.3.3-1 (Continued) i EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION TABLE-NOTATIONS

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(a) A channel may be placed in an inoperable-status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during periods of required surveillance without placing the trip system in the

}i tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

i (b) Also actuates the associated division.oiesel generator.

I (c) Provides signal to close HPCS pump injection valve only.

@ *rovides signal-to HPCS pump suction valves only.

(el !ar reactor vessel water level trip channels are logically combined in a one-out-of-two-twice configuration.

For the purposes of the associated ACTION,'each one-out-of-two logic.is defined as a separate trip system.

(f) Four drywell pressure trip channels are logically combined in a one-out-of-two-twice configuration.

For the purposes-of the associated ACTION, each one-out-of-two logic is defined as a separate trip system.

(g) One half of these trip channels is associated with Nuclear Systems

' Protection System (NSP1) Division III;-the other half is associated with NSPS Division IV.

When the system is required to be OPERABLE per Specification 3.5.2 or 3.5.3.

d*

Required when ESF equipment is required'to be OPERABLE.

Not required to be OPERABLE when reactor steam dome pressure-is 5,100 psig.

These Trip Functions are not required for ECCS actuation.

t The HPCS initiation functions of the Drywell Pressure - High and Manual Initiation are not required to be OPERABLE with indicated reactor vessel water level on the wide range instrument greater than the Level-8 setpoint coincident with the reactor steam dome pressure less than 600 psig.

)

tt One relay.with three inputs in 3 out of 3 logic.

CLINTON - UNIT 1 3/4 3-37 Amendment No. 48 i

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l TABLE 3.3.3-1 (Continued)-

EMERGENCY CORE C00 LINO SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 30 -

With the number of OPERABLE channels less-than required by the Minimum OPERABLE Channels per Trip Function requirenent:

With one channel inoperable, place the inoperable channel a.

t/

in the tripped condition withiri 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

• or declare the associated system inoperable,

.g b.

'dith more than one channel inoperable, declare the' associated system inoperable.

ACTION 31 -

Deleted.

ACTION 32 -

With the number of OPERABLE channels less than required by the Minimum-OPERABLE Channels per Trip Function requirement, declare the associated ADS trip system or ECCS. inoperable.

ACTION 33 -

With the number of OPERAoLE channels less than'the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel (s)-in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

i ACTION 34 -

Deleted.

ACTION 35 -

With the number cf OPERABLE channels less than_ required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status-within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the associated ADS valve or ECCS inoperable.

ACTION 36 -

With the number of OPERABLE channels less than' required by the Minimum OPERABLE Channels _ per Trip Function requirement:

a.

For one trip

.em, place that trip system in the tripped condition wit...a one hour

• or declare the _HPCS system inoperable..

b.

For both trip systems, declar2 the HPCS system inoperable.

ACTION 37 -

With the number-of OPERABLE char.nels less than' required by the Minimum OPERABLE Channels per _ Trip Function requirement, place i

at least one inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

• or declare the HPCS system inoperable.

ACTION 38 With the number of OPERABLE channels less than the Total Number of' Channels, declare the associated. emergency diesel generator inoperable and take the ACTION required by Specifications-3.8.1.1 or 3.8.1.2, as appropriate.

i ACTION 39 -

With the number of OPERABLE channels one less than the Total' Humber of Channels, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> *; operation may then continue until performance of the next required CHANNEL FUNCTIONAL TEST.

ACTION 40 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.

Restore the inoperable channel to OPERABLE status within '7 days or declare-the associated system inoperable.

• The provisions of Specification 3.0.4 are not applicable.

CLINTON - UNIT 1 3/4 3-38 l