ML20059N659
| ML20059N659 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 10/04/1990 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059N660 | List: |
| References | |
| NUDOCS 9010170099 | |
| Download: ML20059N659 (5) | |
Text
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,og UNITED STATES e
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NUCLEAR REGULATORY COMMISSION g.
.j WASHING TON, D. C. 205$5 A,,,,,/
ILLINOIS POWER COMPANY. ET AL.
- DOCKET NO. 50-461 CLINTON POWER STATION, UNIT N0! I' AMENOMENT TO FACILITY' OPERATING LICENSE; Amendment No.50 License No. NPF-62 l.'
The Nuclear Regulatory Commission (the Commission) has.found that:
A.
The application for amendment by Illinois Power Company * (IP), and Soyland Power Cooperative, Inc.L(the-licensees)~ dated December 21,.
1988. complies with the standards and. requirements: of f 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.operateLin conformity with the-application, the provisions of the Act', and;the rules and: regulations-.of the Commission; C.
There is reasonable assurance (i) that theLactivities authorized by this amendment can be conducted-without endangering the. health and safety of the-public, and (ii)sthat: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 Specifi-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:-
- lllinois 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.
9010170099 901004 PDR ADOCK 05000461 P
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(2) Technical Specifications and Environmental Protection' Plan -
The Technical Specifications' contained in Appendix A1and the Environmental Protection Plan contained in Appendix B,.:as revised through Amendment No. 50 :, are-hereby incorporated into:this1 license.
Illinois Power Company shall: operate the facility in:
accordance with the Technical Specifications and the Environmental Protection Plan.
3.
.This license amendment is effectiveLas of itsLdate of issuance.
4 FOR.THE NUCLEAR REGULATORY COMISSION dohnN.
annon',Dihector s
Project. Directorate III-3 Division of Reactor Projects --III, IV, V and SpecialjProjects Office of. Nuclear Reactor Regulation.
Attachment:
l Changes to the Technical-
-Specifications Date of Issuance: October 4, 1990 i
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i ATTACHMENT TO LICENSE AMENDMENT No. 50 -
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 correspondingi 4
overleaf pages'are provided to maintain document completeness.
Remove Insert-
'3/4'3-13 3/4-3-13 3/4 3-18a 3/4 3-18a-t t
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- q w w
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. TABLE 3.3.2-1 h
CRVICS ItSTRUMENTATION
~
E MINIMUM OPERABLE-APPLICABLE g
ISOLATION CHANNELS PER. TRIP OPERATIONAL
.Z TRIP FUNCTION:
SIGNAL tt SYSTEM CONDITION ACTION-H 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 b.
Reactor Vessel Water Level-Low B
2(a)-
- 1, 2, 3 29 Lov, Level 2 (ECCS'Div. I-and II) c.
Reactor Vessel Water Level-Low, Low, B
2(a)(m) 1,-2, 3 29 R
Level 2 (HPCS-NSPS Div. III and IV) d.
Drywell Pressure - High L(D)(#)
2(*)
1, 2, 3 20
[
e.
Drywell-Pressure High L
2(*)
1,'2,.3
.29 h
(ECCS Div. I~and II).
f.
Drywell P'ressure High (HPCS-NSPS Li 2(a)(n) 1, 2, 3^
29 Div. III and-IV)'.
g.
Containment Building Fuel Transfer.
Z(b)(f) 2(*)
25
- Pool. Ventilation Plenum
- Radiation - High-h.
Containment Building E'xhaust Radiation - High-
- 1) Outboard.(Div. I) Valve Isolat. ion M(b)(f).
2(*)( )
1,2,3
- 29 ;
25-g
'2) Inboard (Div. II). Valve Isolation M(b)(f) 2(*)-( )
1, 2, 3 29 25' i.-
Containment Building' Continuous 5(b)(f) 2(a) 1,2,3 29 g
Containment Purge (CCP) Exhaust 25 Radiation - High j.
Reactor Vessel Water Level-Low
- U 2(k) 72,3 29
-8 Low Low,~ Level 1 25 k.
Containment Pressure-High P
1(k)(1)'
1, 2, 3 -
29
-25
t TABLE 3.3.2-1 (Continued)
CRVICS INSTRUMENTATION TABLE NOTATIONS (m). Four. reactor vessel water level trip channels are logically' combined in a-J 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-of-two-twice configuration.
For the purposes of the associated ACTION -
each one-out-of-two logic is defined as a separate trip system.
(o) One trip system is associated with the A and B monitors; the other tripL system is associated with the C and.0 monitors.
(p) Each channel-consists of five temperature modules and their associated-sensors.
A-channel is OPERABLE if and only if.-five. temperature modules and their associated sensors are OPERABLE.
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-CLINTON - UNIT 1 3/4 3-18a Amendment Pk). 50
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