ML20101R106
| ML20101R106 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 04/10/1996 |
| From: | Pickett D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20101R108 | List: |
| References | |
| NPF-62-A-104 NUDOCS 9604160057 | |
| Download: ML20101R106 (6) | |
Text
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UNITED STATES g
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j NUCLEAR REGULATORY COMMISSION 4
t WASHINGTON, D.C. 20006-0001
%..... p' ILLIN0IS POWER COMPANY. ET AL.
DOCKET NO. 50-461 CLINTON POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 104 License No. NPF-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Illinois Power Company * (IP), and Soyland Power Cooperative, Inc. (the licensees) dated December 14, 1995, complies with the standards and requirements 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 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 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 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:
- 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.
9604160057 960410 PDR ADOCK 05000461 P
i
. (2)
Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised 1
I through Amendment No.104, are hereby incorporated into this license.
Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental l
Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMISSION 7 y-K v' f Douglas V. Pickett, Project Manager Project Directorate III-3 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 10, 1996 l
ATTACl# TENT TO LICENSE AMENDMENT NO.104 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.
Ramave Paces Insert Paaes 3.3-41 3.3-41 3.3-47 3.3-47 3.3-58 3.3-58 3.3-60 3.3-60 i
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 5)
Emergency Core Cooling system Instrumentation j
APPLICABLE CONDITIONS NGES OR REFERENCED OTNER REQUIRED FRON SPECIFIED CNANNELs PER REQUIRED SURVEILLANCE ALLOW 48tE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE 3.
Nigh Preesure Core sprey (NPCs) system a.
Reactor vessel 1,2,3, 4(b)
B S4 3.3.5.1.1 k 47.7 inches Water Levet - Low sk 3.3.5.1.2 Low, Level 2 4(*),5(*)
st 3.3.5.1.3 sa 3.3.5.1.4 sa 3.3.5.1.5 b.
Drywett 1,2,3 4(b)
B st 3.3.5.1.1 5 1.88 pois Pressure - Nigh st 3.3.5.1.2 sa 3.3.5.1.3 sa 3.3.5.1.4 SR 3.3.5.1.5 c.
Reactor Vessel 1,2,3, 2
C sa 3.3.5.1.1 5 54.2 inches Water sa 3.3.5.1.2 Level - High, 4(a) $(a) sa 3.3.5.1.3 Level 8 sa 3.3.5.1.4 st 3.3.5.1.5 d.
RCIC storage Tank 1,2,3, 2
D sa 3.3.5.1.1 2 2.5 inches Level - Low sa 3.3.5.1.2 4(*),5(*)
sa 3.3.5.1.3 SR 3.3.5.1.4 sa 3.3.5.1.5 e.
S w ession Pool 1,2,3 2
o sa 3.3.5.1.1 s 12 inches Water Level-High SR 3.3.5.1.2 st 3.3.5.1.3 sa 3.3.5.1.4 st 3.3.5.1.5 f.
NPCs Pump 1,2,3, 1
E SR 3.3.5.1.1 t 120 pelg Discharge SR 3.3.5.1.2 Pressure - Nigh 4(*),5(*)
st 3.3.5.1.3 (sypass) st 3.3.5.1.4 st 3.3.5.1.5 g.
NPCs system Flow 1,2,3, 1
E st 3.3.5.1.1 t 500 spa Rate - Low SR 3.3.5.1.2 (Bypass) 4(a) 5(*)
SR 3.3.5.1.3 st 3.3.5.1.4 SR 3.3.5.1.5 h.
Menuet Initiation 1,2,3, 1
C SR 3.3.5.1.5 NA 4(*),5(*)
(continued)
(a) When essociated s e system (s) are required to be OPERABLE.
(b) Also required to initiate the associated diesel generator.
(c) When NPCs is OPERA 8LE for compliance with LC0 3.5.2, "ECCS - shutdown, and aligned to the RCIC storage tank while tank water level is not within the timits of SR 3.5.2.2.
CLINTON 3.3-41 Amendment No.104
4 RCIC System Instrumentation 3.3.5.2 Table 3.3.5.2 1 (pese 1 of 1)
Reactor core Isoletten Coeting system Instrumentation CONDITIONS REQUIRED REFERENCED CNANNELs PER FROM REQUIRED SURVEILLANCE ALLOWASLE FUNCTION FUNCTION ACTION A.1 REGUIREMENTs VALUE 1.
Reactor Vesset Water 4
B 3R 3.3.5.2.1 t -47.7 inches Level -Lou Low, Level 2 SR 3.3.5.2.?
sa 3.3.5.2.3 st 3.3.5.2.4 SR 3.3.5.2.5 2.
Reactor Vessel Water 2
C sa 3.3.5.2.1 s 52.6 inches i
Level - Nigh, Level 8 SR 3.3.5.2.2 sa 3.3.5.2.3 sa 3.3.5.2.4 SR 3.3.5.2.5 l
3.
RCIC storage Tank 2
0 SR 3.3.5.2.1 a 2.5 inches Level - Lou SR 3.3.5.2.2 SR 3.3.5.2.3 SR 3.3.5.2.4 sa 3.3.5.2.5 4.
s w eselon Poot Water 2
D sa 3.3.5.2.1 5 -3 inches Level - High SR 3.3.5.2.2 SR 3.3.5.2.3 i
54 3.3.5.2.4 SR 3.3.5.2.5 5.
Manuel Inittetten 1
C st 3.3.5.2.5 NA CLINTON 3.3-47 Amendment No.104
Primary Containment and Drywell Isolatien Instrumentation 3.3.6.1 Table 3.3.6.1 1 (pese 6 of 6) l Prlmery Contelnment and Drywell Isolation Instrumentation APPLICA8LE CONDITIONS MODES OR REeu! RED REFERENCED OTNER CNANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION F.1 REQUIREMENTS VALUE 3.
Reactor Core Isolation Cooling (RCIC) system Isolation l
e.
Auxillery Rullding 1,2,3 2
I st 3.3.6.1.1 s 118.5 inches RCIC steen Line SR 3.3.6.1.2 water Flow - Nigh sR 3.3.6.1.3 st 3.3.6.1.5 sa 3.3.6.1.6 b.
RCIC steen Line 1,2,3 2
I sa 3.3.6.1.2 5 13 seconds Flow - Nigh, SR 3.3.6.1.5 Time Delay sa 3.3.6.1.6
=
c.
RCIC Steen S w ly Line 1,2,3 2
I sa 3.3.6.1.1 t 52 pelg Pressure - Low st 3.3.6.1.2 sa 3.3.6.1.3 sa 3.3.6.1.5 sa
.'t.3.6.1.6 d.
RCIC Turbine Exhaust 1,2,3 6
I sa 3.3.6.1.1 s 20 pais Diephreen sa 3.3.6.1.2 Pressure - Nigh sa 3.3.6.1.3 SR 3.3.6.1.5 sa 3.3.6.1.6 e.
RCic Equipment Room 1,2,3 2
I SR 3.3.6.1.1 s 207'F Ashlent sa 3.3.6.1.2 Temperature - High SR 3.3.6.1.5 sa 3.3.6.1.6 f.
Main steen Line Tunnel 1,2,3 2
I sa 3.3.6.1.1 s 171'F Aa6 tent sa 3.3.6.1.2 Temperoture - H1sh sa 3.3.6.1.5 sa 3.3.6.1.6 9 Mein steen Line Tunnel 1,2,3 2
I Sa 3.3.6.1.2 5 28 minutes Temperature Timer SR 3.3.6.1.5 st 3.3.6.1.6 h.
Deleted I.
Drywell RCIC steen 1,2,3 2
I sa 3.3.6.1.1 s 188 inchee l
Line Flow - Nigh st 3.3.6.1.2 water st 3.3.6.1.3 sa 3.3.6.1.5 sa 3.3.6.1.6 (continued)
CLINTON 3.3-58 Amendment No. 104
Primary Centainment and Drywell Isolaticn Instrumentation 3.3.6.1 Table 3.3.6.1 1 (page 6 of 6) l Primary Contelnment and Drywett Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM sPECIFIED CNtJmELs PER REQUIRED SURVEILLANCE ALLOWASLE g
FUNCTION CONDITIONS FUNCTION ACTION F.1 REQUIREMENTS VALUE 5.
RMR system leetetton J
a.
RNR Neet Excheneer 1,2,3 2 per room I
st 3.3.6.1.1 s 160'F Ashlent at 3.3.6.1.2 Temperature - Nish SR 3.3.6.1.5 SR 3.3.6.1.6 0) i b.
Reactor vessel Water 1,2,3 4
I sa 3.3.6.1.1 t 8.3 inches Level - Low, Level 3 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 sa 3.3.6.1.6 c.
Reactor vessel Water 3(9) 4,5 4(h)
M SR 3.3.6.1.1 2 8.3 inches Level - Low, Level 3 SR 3.3.6.1.2 st 3.3.6.1.3 SR 3.3.6.1.5 sa 3.3.6.1.6 d.
Reacter Vessel Water 1,2,3 4
I st 3.3.6.1.1 t 147.7 Level Low Low Low, st 3.3.6.1.2 inches Levet 1 sa 3.3.6.1.3 st 3.3.6.1.5 SR 3.3.6.1.6 l
e.
Reactor vessel 1,2,3 4
I SR 3.3.6.1.1 s 110 pois Pressure - Nish sa 3.3.6.1.2
+
st 3.3.6.1.3 sa 3.3.6.1.'3 sa 3.3.6.1.6 f.
Drywetl Pressure-Nigh 1,2,3 8
I st 3.3.6.1.1 s 1.88 psig SR 3.3.6.1.2 st 3.3.6.1.3 SR 3.3.6.1.5 sa 3.3.6.1.6 g.
Manuel Initletion 1,2,3 2
J st 3.3.6.1.6 NA i
J (f) With reactor steem done pressure greater than or equal to the RHR cut in permissive pressure.
(g) With reactor steen done pressure less then the RNR cut in permissive pressure.
(h) only one trip system re@ ired in MODES 4 and 5 with RNR shutdown Cooling system integrity meintained.
i CLINTON 3.3-60 Amendment No. 104
.