Letter Sequence Request |
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MONTHYEARML20133A5951996-12-13013 December 1996 Proposed TSs Re Transfer of Minority Ownership Project stage: Request ML20134A9951997-01-23023 January 1997 Forwards Notice of Consideration of Approval of Transfer of License & Issuance of Conforming License Amends,Proposed NSHC Determination & Opportunity for Hearing, for Plant, Unit 1 Project stage: Other 1996-12-13
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20199H2771999-01-20020 January 1999 Proposed Tech Specs Changing Table 3.3.8.1-1 to Revise Allowable Values for Degraded Voltage Relay Reset & Dropout Setpoints as Specified Per Items 1.c,1.d,2.c & 2.d ML20196A0941998-11-20020 November 1998 Proposed Tech Specs Re Div 3 Diesel Generator Droop Issue ML20196A1501998-11-20020 November 1998 Revised Pages Constituting Rev 3 to CPS TS Bases,Consisting of Pages Annotated with Rev Numbers 3-1,3-2,3-3,3-4 & 3-5. Changes to Text Identified with Rev Bars.No Rev Bars Included for Changes to Format ML20155A5631998-10-23023 October 1998 Proposed Tech Specs LCO 3.6.1.9, FW LCS (FWLCS) for Implementation of FWLCS Mode of RHR Sys U-603088, Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7)1998-10-0505 October 1998 Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7) ML20153F4201998-09-23023 September 1998 Corrected Proposed Tech Specs Bases Page B 3.8-94 Re SVC Protection Sys ML20237E4191998-08-24024 August 1998 Proposed Tech Specs SR 3.8.1.17,revising Acceptance Criteria for Meeting ready-to-load Requirement for Division 3 DG ML20237C3501998-08-17017 August 1998 Proposed Tech Specs Partially Reducing Load at Which DGs Are Required to Be Tested Per Affected SRs in Order to Reduce Stress & Wear on Machines While Still Sufficiently Challenging Machines to Confirm Operability ML20236X0071998-07-31031 July 1998 Proposed Tech Specs,Revising Acceptance Criteria of SRs 3.8.1.7,3.8.1.12,3.8.1.15 & 3.8.1.20 ML20216B1511998-05-0404 May 1998 Proposed Tech Specs Pages,Incorporating Requirements for Static Var Compensator (SVC) Protection Sys Under New TS ML20217M3351998-04-27027 April 1998 Proposed Tech Specs Re Mgt Changes Occurring in Operations Organization at Plant ML20212C6951997-10-23023 October 1997 Proposed Tech Specs,Constituting Rev 2 to CPS TS Bases.Rev Consists of Pages Annotated W/Rev Numbers 2-1 Through 2-14 ML20149J1701997-07-22022 July 1997 Proposed Tech Specs Requesting Exemption to 10CFR50,App a, General Design Criteria to Allow Operation W/Identified Offsite Circuit Condition U-602714, Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation1997-04-0101 April 1997 Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation ML20133F2051997-01-0707 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A5951996-12-13013 December 1996 Proposed TSs Re Transfer of Minority Ownership ML20134M3181996-11-19019 November 1996 Proposed Tech Specs Revising Table 3.3.8.1-1, Loss of Power Instrumentation, by Dividing Function, Degraded Voltage - 4.16 Kv Basis & Degraded Voltage Dropout - 4.16 Kv Basis, re-numbering Items in Table & Revising Associated Notes ML20128K0711996-10-0404 October 1996 Proposed Tech Specs 3.3.8.1,adding Action Statement & Note Requiring Restoration of Inoperable Degraded Voltage Relays, Rev to Table 3.3.8.1-1 ML20134C1631996-09-20020 September 1996 Proposed Tech Specs,Revising TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months U-602623, Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling1996-08-15015 August 1996 Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling ML20116N1101996-08-15015 August 1996 Proposed Tech Specs 2.0, Safety Limits, Changing TS to Incorporate Revised SLMCPR as Calculated by GE for CPS Cycle 7 U-602619, Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses1996-08-15015 August 1996 Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses ML20113E7261996-06-28028 June 1996 Proposed Tech Specs,Allowing Removal of Inclined Fuel Transfer Sys Primary Containment Blind Flange While Primary Containment Required to Be Operable U-602591, Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures1996-06-21021 June 1996 Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures ML20108C9431996-05-0101 May 1996 Proposed Tech Specs,Implementing 10CFR50,App J - Option B ML20107L0011996-04-19019 April 1996 Proposed Tech Specs,Revising Listed TS to Eliminate Core Alterations as Applicable Condition for Which Associated LCO Must Be Met ML20100H7741996-02-22022 February 1996 Proposed Tech Specs,Proposing to Revise TS 3.6.5.1, Drywell, to Allow Drywell Bypass Leakage Tests to Be Performed at Intervals of Up to Ten Yrs Based on Demonstrated Performance of Drywell Barrier ML20100H7901996-02-22022 February 1996 Proposed Tech Specs,Deleting SR 3.3.8.1.1 Which Requires Channel Check for Loss of Power Instrumentation & Changing TS Table 3.3.8.1-1 to Change Allowable Value for Degraded Voltage Function from 3762V & 3832V to 3876V ML20100H8171996-02-22022 February 1996 Proposed Tech Specs,Changing TS 3.4.11, RCS P/T Limits, to Incorporate Specific P/T Limits for Bottom Head Region of Rv Separate & Apart from Core Beltline Region of Rv ML20100H8411996-02-22022 February 1996 Proposed Tech Specs,Changing TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months ML20095G4791995-12-14014 December 1995 Proposed Tech Specs 3.4.2, Flow Control Valves Re Proposed Deletion of Average Rate of Movement Verification Requirement ML20095G5141995-12-14014 December 1995 Proposed Tech Specs 3.3.1.1, RPS Instrumentation & TS 3.3.6.1, Primary Containment Dwl Isolation Instrumentation to Eliminate Periodic Response Time Testing of Analog Trip Modules ML20095G6401995-12-14014 December 1995 Proposed Tech Specs Instrumentation Associated W/High Pressure Core Spray Sys,Reactor Core Isolation Cooling Sys & Residual Heat Removal Sys ML20094D2141995-10-27027 October 1995 Proposed Tech Specs,Consisting of Changes to TS 5.2.2.e to Revise Requirements for Controls on Working Hs of Unit Staff That Perform SR Functions ML20094D2031995-10-27027 October 1995 Proposed Tech Specs,Consiting of Changes to TS 3.1.3 to Include 25% Surveillance Overrun Allowed by LCO 3.0.2 Into Allowances of Surveillance Notes for Control Rod Notch Testing Per SR 3.1.3.2 & SR 3.1.3.3 ML20085N0621995-06-23023 June 1995 Proposed Tech Specs Bases,Per TS 5.5.11, TS Bases Control Program ML20085F5961995-06-0909 June 1995 Proposed Tech Specs,Incorporating Description of Exclusion Area Boundary ML20085J9701995-02-16016 February 1995 Proposed Tech Specs Reflecting Enforcement Discretion Re TS LCO for Div 2 DC Electrical Power Sources ML20078Q2931995-02-14014 February 1995 Proposed Tech Specs 3.8.2, AC Sources-Shutdown, 3.8.5, DC Sources-Shutdown & 3.8.8, Inverters-Shutdown ML20078N2701995-02-10010 February 1995 Proposed TS 3.3.2.1, Control Rod Block Instrumentation ML20078E9701995-01-27027 January 1995 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements U-602372, Proposed Tech Specs Requesting Complete Rev of CPS TS for Conversion to Improved TS Per Guidance Provided by NUREG-1434, Improved BWR-6 TS, Rev 0,dated Sept 19921994-11-18018 November 1994 Proposed Tech Specs Requesting Complete Rev of CPS TS for Conversion to Improved TS Per Guidance Provided by NUREG-1434, Improved BWR-6 TS, Rev 0,dated Sept 1992 ML20076G2721994-10-14014 October 1994 Proposed Tech Specs,Allowing Drywell Bypass Leakage Test to Be Performed at five-yr Interval ML20072E6701994-08-12012 August 1994 Proposed Tech Specs Eliminating Requirement to Perform Manual Testing of solid-state Logic Independently from self-test Sys ML20072E6191994-08-12012 August 1994 Proposed Tech Specs Allowing Drywell Bypass Leakage Rate Tests to Be Performed at Intervals as Long as Ten Years ML20072C1251994-08-0505 August 1994 Proposed Tech Specs Re Requirement for Accelerated Testing of Div 1 DG ML20069Q3851994-06-27027 June 1994 Proposed Tech Specs 3/4.4.3.1, Reactor Coolant Sys Leakage- Leakage Detection Sys ML20069N3201994-06-16016 June 1994 Proposed Tech Specs Adding -89 After ASTM D3803 in Testing Requirements Specified for SGTS & MCR Filter Sys Charcoal & Changing Test Temp for Testing SGTS Charcoal from 80 C to 30 C ML20069K8191994-06-13013 June 1994 Proposed Tech Specs to Allow 36-inch Isolation Valve Leak Measurement Be Performed at Least Once Per 18 Months, Providing Valves Remain Closed During Period ML20070N6951994-04-26026 April 1994 Proposed Tech Specs Adopting Changes Recommended in NRC Re NUREG-1434 1999-01-20
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20209E0551999-07-0606 July 1999 1999 Business Plan ML20206F2231999-04-27027 April 1999 NRC Manual Chapter 0350 Restart Action Plan for Clinton Power Station ML20199H2771999-01-20020 January 1999 Proposed Tech Specs Changing Table 3.3.8.1-1 to Revise Allowable Values for Degraded Voltage Relay Reset & Dropout Setpoints as Specified Per Items 1.c,1.d,2.c & 2.d ML20206E6281998-12-31031 December 1998 Rev 17 to ODCM for Clinton Power Station ML20196A0941998-11-20020 November 1998 Proposed Tech Specs Re Div 3 Diesel Generator Droop Issue ML20196A1501998-11-20020 November 1998 Revised Pages Constituting Rev 3 to CPS TS Bases,Consisting of Pages Annotated with Rev Numbers 3-1,3-2,3-3,3-4 & 3-5. Changes to Text Identified with Rev Bars.No Rev Bars Included for Changes to Format ML20155A5631998-10-23023 October 1998 Proposed Tech Specs LCO 3.6.1.9, FW LCS (FWLCS) for Implementation of FWLCS Mode of RHR Sys U-603088, Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7)1998-10-0505 October 1998 Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7) ML20153F4201998-09-23023 September 1998 Corrected Proposed Tech Specs Bases Page B 3.8-94 Re SVC Protection Sys ML20237E4191998-08-24024 August 1998 Proposed Tech Specs SR 3.8.1.17,revising Acceptance Criteria for Meeting ready-to-load Requirement for Division 3 DG ML20237C3501998-08-17017 August 1998 Proposed Tech Specs Partially Reducing Load at Which DGs Are Required to Be Tested Per Affected SRs in Order to Reduce Stress & Wear on Machines While Still Sufficiently Challenging Machines to Confirm Operability ML20236X0071998-07-31031 July 1998 Proposed Tech Specs,Revising Acceptance Criteria of SRs 3.8.1.7,3.8.1.12,3.8.1.15 & 3.8.1.20 ML20236Q4661998-07-17017 July 1998 Rev 0 to Procedure 2800.93, Emergency Reserve Auxiliary Transformer Integrated Test ML20236Q4651998-07-17017 July 1998 Rev 0 to Procedure 2800.92, Emergency Reserve Auxiliary Transformer Integrated Test ML20236Q4571998-07-17017 July 1998 Rev 0 to Procedure 2800.91, Emergency Reserve Auxiliary Transformer Test ML20216B1511998-05-0404 May 1998 Proposed Tech Specs Pages,Incorporating Requirements for Static Var Compensator (SVC) Protection Sys Under New TS ML20217M3351998-04-27027 April 1998 Proposed Tech Specs Re Mgt Changes Occurring in Operations Organization at Plant ML20203D5651998-02-19019 February 1998 Plan for Excellence ML20212C6951997-10-23023 October 1997 Proposed Tech Specs,Constituting Rev 2 to CPS TS Bases.Rev Consists of Pages Annotated W/Rev Numbers 2-1 Through 2-14 ML20149J1701997-07-22022 July 1997 Proposed Tech Specs Requesting Exemption to 10CFR50,App a, General Design Criteria to Allow Operation W/Identified Offsite Circuit Condition ML20149H8991997-06-30030 June 1997 CPS Long Term Improvement Plan U-602714, Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation1997-04-0101 April 1997 Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation ML20133F2051997-01-0707 January 1997 Proposed Tech Specs 2.0 Re Safety Limits ML20133A5951996-12-13013 December 1996 Proposed TSs Re Transfer of Minority Ownership ML20134M3181996-11-19019 November 1996 Proposed Tech Specs Revising Table 3.3.8.1-1, Loss of Power Instrumentation, by Dividing Function, Degraded Voltage - 4.16 Kv Basis & Degraded Voltage Dropout - 4.16 Kv Basis, re-numbering Items in Table & Revising Associated Notes ML20128K0711996-10-0404 October 1996 Proposed Tech Specs 3.3.8.1,adding Action Statement & Note Requiring Restoration of Inoperable Degraded Voltage Relays, Rev to Table 3.3.8.1-1 ML20134C1631996-09-20020 September 1996 Proposed Tech Specs,Revising TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months ML20116N1101996-08-15015 August 1996 Proposed Tech Specs 2.0, Safety Limits, Changing TS to Incorporate Revised SLMCPR as Calculated by GE for CPS Cycle 7 U-602619, Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses1996-08-15015 August 1996 Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses U-602623, Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling1996-08-15015 August 1996 Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling ML20137A1101996-08-14014 August 1996 Rev 19 to App V Second 10-Yr Interval Pump & Valve Testing Program Plan ML20137A1021996-07-10010 July 1996 Rev 5 to App IV Second 10-Yr Interval Inservice Exam Plan ML20113E7261996-06-28028 June 1996 Proposed Tech Specs,Allowing Removal of Inclined Fuel Transfer Sys Primary Containment Blind Flange While Primary Containment Required to Be Operable U-602591, Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures1996-06-21021 June 1996 Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures ML20108C9431996-05-0101 May 1996 Proposed Tech Specs,Implementing 10CFR50,App J - Option B ML20107L0011996-04-19019 April 1996 Proposed Tech Specs,Revising Listed TS to Eliminate Core Alterations as Applicable Condition for Which Associated LCO Must Be Met ML20100H8411996-02-22022 February 1996 Proposed Tech Specs,Changing TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months ML20100H7901996-02-22022 February 1996 Proposed Tech Specs,Deleting SR 3.3.8.1.1 Which Requires Channel Check for Loss of Power Instrumentation & Changing TS Table 3.3.8.1-1 to Change Allowable Value for Degraded Voltage Function from 3762V & 3832V to 3876V ML20100H8171996-02-22022 February 1996 Proposed Tech Specs,Changing TS 3.4.11, RCS P/T Limits, to Incorporate Specific P/T Limits for Bottom Head Region of Rv Separate & Apart from Core Beltline Region of Rv ML20100H7741996-02-22022 February 1996 Proposed Tech Specs,Proposing to Revise TS 3.6.5.1, Drywell, to Allow Drywell Bypass Leakage Tests to Be Performed at Intervals of Up to Ten Yrs Based on Demonstrated Performance of Drywell Barrier ML20095G5141995-12-14014 December 1995 Proposed Tech Specs 3.3.1.1, RPS Instrumentation & TS 3.3.6.1, Primary Containment Dwl Isolation Instrumentation to Eliminate Periodic Response Time Testing of Analog Trip Modules ML20095G6401995-12-14014 December 1995 Proposed Tech Specs Instrumentation Associated W/High Pressure Core Spray Sys,Reactor Core Isolation Cooling Sys & Residual Heat Removal Sys ML20095G4791995-12-14014 December 1995 Proposed Tech Specs 3.4.2, Flow Control Valves Re Proposed Deletion of Average Rate of Movement Verification Requirement ML20117E3001995-11-0606 November 1995 Rev 18 to App V Pump & Valve Testing Program Plan ML20094D2031995-10-27027 October 1995 Proposed Tech Specs,Consiting of Changes to TS 3.1.3 to Include 25% Surveillance Overrun Allowed by LCO 3.0.2 Into Allowances of Surveillance Notes for Control Rod Notch Testing Per SR 3.1.3.2 & SR 3.1.3.3 ML20094D2141995-10-27027 October 1995 Proposed Tech Specs,Consisting of Changes to TS 5.2.2.e to Revise Requirements for Controls on Working Hs of Unit Staff That Perform SR Functions ML20085N0621995-06-23023 June 1995 Proposed Tech Specs Bases,Per TS 5.5.11, TS Bases Control Program ML20085F5961995-06-0909 June 1995 Proposed Tech Specs,Incorporating Description of Exclusion Area Boundary ML20087J5691995-05-17017 May 1995 Rev 17 to App V, Pump & Valve Testing Program Plan of CPS ISI Program Manual ML20085J9701995-02-16016 February 1995 Proposed Tech Specs Reflecting Enforcement Discretion Re TS LCO for Div 2 DC Electrical Power Sources 1999-07-06
[Table view] |
Text
.
, Attachment 3 !
to U-602675 RS/LS-96-011 Page1 of5 ;
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Marked-up Operating License Pages $
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l 9612310177 961213 PDR ADOCK 05000461 P PDR
l UNITED STATES Attachment 3 o,,
8 o NUCLEAR REGULATORY COMMISSION to U-602675 y, I WASHINGTON. D. C. 20555 RS/LS-96-011 g / Page 2 of 5 1
ILLINOIS POWER COMPANY
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A DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO. 1 C
FACILITY OPERATING LICENSE i
License No. NPF-62 l
- 1. The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A. The manlication for lie- fi1=A hv filinois P Fnmnanb(IP
~ :hi5;:it 2 ?! 5i "" hi ; '%%iIoms -b.% i5~a.R,g=
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Ire. bit.nergrYt n 1x n'ofS1954, M wit.n de - nd requ wesents oi ws '
as amended (the Act), and the Comission's I regulations set forth in 10 CFR Chapter I, and all required notifica- i tions to other agencies or bodies have been duly made; B. Construction of the Clinton Power Station, Unit No.1 (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-137 and the application, as amended, the provisions of the Act and the regulations of the Comission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comis-sion (except as exempted from compliance in Section 2.0. below);
i D. There is reasdnable assurance: (1) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public; and (ii) that such activities will be con-ducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.0. ,
below); i E. Illinois Power Company is technically qualified to engage in the activ-ities authorized by this operating license in accordance with the Com-mission'tregulations set forth in 10 CFR Chapter I; '
F. ,$Pbs 1 %1 = nn h= Jatisfied the applicable provisions of 10 CFR ,
i arn dr,- Finanual Protection Requirements and Indemnity Agreements,"
I of the Comission's regulai. ions; N y y y y
^ I l l liiv i a .Gw.- Ca po ,' i Ou d.v. ? Cd to LCC 6; ;; cat for 00yl;r.d I:'.;;r C ^p r; t h. , ! :. =f Sn :=h:i .; . sp;nibilit, u . sv.,;.. v; m.m. um W , . .ua j
cv...i. ctica, sp;r:. tic: =d m: Ht==ce cf the f d ' 4 +y _ ^-
f - - -
e Attachment 3 4
. . to U-602675 RS/LS-96-011
- Page 3 of 5 j i )
G.
.The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public;
- H. After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No. NPF-62, subject to the conditions for protection of the '
environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Commission's regulation: and all applicable requirements have been satisfied; and I.
The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70.
- 2. Based on the foregoing findings regarding this facility, and pursuant to approval by the Nuclear Regulatory Commission at a meeting on April 10, 1987, Facility Operating License No. NPF-62, which supersedes the license for fuel loading and low power testing, License No. NPF-5 rJ9m QAfj heew incued to Illinois Power compan ::d ;jt: .,n. jQT-)
{":::::::Jto read as follows.
A. This license applies to the Clinton Power Station, Unit No.1, a boil-ing water nuclear reactor and asmciated.saninmant (tha facili1vL owned by Illinois Power Company"O 1:nQ."nf 5;;5Cf, :7.O The facility is located in Harp Tcanip,-venitt county, ipproxunately l six miles east of the ci Clinton in east-central Illinois and is described in the licens nal Safe alysis Report, as supple-mented and amended, and he licens nvironmental Report-Operating License Stage, as supplemented and ame B. Subject to the conditions and requirements incorporated herein, the Connission hereby licenses:
(1) Illinois Power Company (IP), pursuant to Section 103 of the Act l and 10 CFR Part 50, to possess, use and operate the facility at !
the designated location in Harp Township, DeWitt County, Illinois, 1 in accordance with the procedures and limitations set forth in this license;
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(3) IP, pursuant to the Act and 10 CFR Part 70, to receive, possess and to use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts re-
. quired for reactor operation, as described in the final Safety Analysis Report, as supplemented and amended;
_ _ _ _ m ___ . - - . _ __ _ __ _ . _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ .-
l ,
Attachment 3 4
' " to U-602675 j RS/LS-96-011 j Page 4 of 5 j 4 1
~
An exemption was previously granted pursuant to 10 CFR 70.24. The i exemption was granted with NRC material license No. SNM-1886, issued November 27, 1985, and relieved IP from the requirement of having a i criticality alarm system. IP is hereby exempted from the criticality l alarm system provision of 10 CFR 70.24 so far as this section applies to j the storage of fuel assemblies held under this license.
i 1 Thase exemptions are authorized by law, will not present an undue risk ,
i to the public health and safety, and are consistent with the common 1
! defense and security. The exemptions in items (b) and (c) above are j granted pursuant to 10 CFR 50.12. With these exemptions, the facility I will operate, to the extent authorized herein, in conformity with the !
application, as amended, the provisions of the Act, and the rules and {
. 1 tions of the Commission. !
T I l
- E. C j ::: hall fully implement and maintain in effect all l l 1
pravmons vr the Commi.ssion-approved physical security plan, guard !
training and qualification, and safeguards contingency plans including ;
I amendments made pursuant to provisions of the Miscellaneous Amendments '
l and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and
! 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The i plans, which contain Safeguards Information protected under 10 CFR :
l 73.21, are entitled: "Clinton Power Station Physical Security Plan,"
l with revisions submitted through May 27,-1993; "Clinton Power Station i
- Training and Qualification Plan," with revisions submitted through i l May 27, 1993; and "Clinton Power. Station Safeguards Contingency Plan," J with revisions submitted through May 27, 1993. Changes made in l
- accordance with 10 CFR 73.55 shall be implemented in accordance with the 4
schedule set forth therein. '
- F. IP shall implement and maintain in effect all provisions of the approved F fire protection program as described in the Final Safety Analysis Report i
as amended, for the Clinton Power Station, Unit No.1, and as approved in the Safety Evaluation Report (NUREG-0853) dated February.1982 and
} Supplement Nos. I thru 8 thereto subject to the following provision:
IP may make changes to the approved fire protection program
- without prior approval of the Commission only if those changes 4
cx1d not adversely affect the ability to achieve and maintain
" fe shutdown in the event of a fire.
G. Except as otherwise provided in the Technical Specifications or
{ Environmental. Protection Plan, IP shall report any violations of the
! requirements contained in Section 2.C of this license in the following
- manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC I Operations Center via the Emergency Notification System with written i followup within thirty days in accordance with the procedures described j_ in 10 CFR 50.73(b), (c), and (e). )
1 i
Attachment 3 to U-602675 ,
RS/LS-96-011 l Page 5 of 5 IP -
H.(?ti 't: :::: hall have and maintain financial protection of such type ~ano m such amounts as the Comission shall require in accord-ance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
I. This license is effective as of the date of issuance an.d shall expire at midnight on September 29, 2026, i FOR THE NUCLEAR REGULATORY COMMISSION f --
Thomas E. Murley, Director Office of Nuclear Reactor Regulation
Enclosures:
- 1. Attachments 1 and 2
- 2. Appendix A - Technical Specifications (NUREG-1235)
- 3. Appendix B - Environmental Protection Plan l 4 Appendix C - Antitrust Conditions l
l Date of Issuance: April 17, 1987 1
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