ML20206T929
| ML20206T929 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 09/29/1986 |
| From: | Vollmer R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206T932 | List: |
| References | |
| NUDOCS 8610070236 | |
| Download: ML20206T929 (12) | |
Text
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s p r.a r UNITED STATES y
g NUCLEAR REGULATORY COMMISSION t,
j WASHINGTON, D. C. 20555
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ILLIN0IS POWER COMPANY S0YLAND POWER COOPERATIVE, INC.
WESTERN ILLINDIS POWER COOPERATIVE, INC.
DOCKET NO. 50-461 CLINTON POWER STATION, UNIT NO. 1 FACILITY OPERATING LICENSE License No. NPF-55 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for license filed by Illinois Power Company * (IP),
acting en behalf of itself and as agent for Soyland Power Cooperative, Inc. and Western Illinois Power Cooperative, Inc. (licensees) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I, and all required notifications 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 confomity with Construction Permit No. CPPR-137 and the application, as amended, the provisions of the Act and the regulations of the Commission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Section 2.D.
below);
D.
There is reasonable 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 conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D.
below);
E.
Illinois Power Company is technically qualified to engage in the activities authorized by this operating license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F.
The licensees have satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements,"
of the Comission's regulations;
- Illinois Power Company is authorized to act as agent for Soyland Power Cooperative, Inc. and Western Illinois Power Cooperative, Inc. and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
8610070236 860929 PDR ADOCK 05000461 P
! 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-55, 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 regulations 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, Facility Operating License NPF-55 is hereby issued to Illinois Power Company, Soyland Power Cooperative, Inc.
and Western Illinois Power Cooperative, Inc. (the licensees), to read as follows:
A.
This license applies to the Clinton Power Station, Unit No. 1, a boiling water nuclear reactor and associated equipment (the facility), owned by Illinois Power Company, Soyland Power Cooperative. Inc. and Western Illinois Power _ Cooperative, Inc. The facility is located in Harp Town-ship, DeWitt County, approximately six miles east of the city of Clinton in east-central Illinois and is described in the licensees' Final Safety Analysis Report, es supplemented and amended, and in the licensees' Environmental Report-0perating License Stage, as supplemented and amended.
B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:
(1) Illinois Power Company (IP), pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the designated location in Harp Township, DeWitt County, Illinois, in accordance with the procedures and limitations set forth in this license; (2) Soyland Power Cooperative, Inc. and Western Illinois Power Cooper-ative, Inc. pursuant to Section 103 of the Act and 10 CFR 50, to possess the facility at the above designated location in accord-ance with the procedures and limitations set forth in this license; (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 required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; i
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(4)
IP, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any. time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radi-ation monitoring equipment calibration, and as fission detectors in amounts as required;
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(5)
IP, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive,' possess, and use in amounts as required any byproduct.
source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)
IP, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the condi-1 tions specified in the Comission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Comission now or here-after in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level IP is authorized to operate the facility at reactor core power i
levels not in excess of 2894 megawatts themal (100 percent rated l
power) in accordance with the conditions specified herein.
Pending Commission approval this license is restricted to power levels not to exceed five percent of rated power (144.7 megawatts thermal). The items identified in Attachment 1 to this license i
shall be completed as specified. Attachment 1 is hereby incorporated into this license.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
IP shall operate the facility in n cordance with the Technical Specifications and the Environmental Protection Plan.
(3) Antitrust Conditions IP shall comply with the antitrust conditions in Appendix C attached hereto, which is hereby incorporated into this license.
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(4)
Inservice Inspection Program (Section 6.6, SER, SSER 1 and 55ER 5)*
IP shall submit the initial inservice inspection program required by 10 CFR 50.55a(g) for NRC staff review and approval within six (6) months after exceeding five percent of rated power.
(5) Control System Failures (Section 7.7.3.1, SER and SSER 6)
IP shall submit, in accordance with comitments contained in letters dated May 15, 1986 and July 16, 1986, the results of the additional evaluations of control system failures and the proposed implementation of any corrective actions that may be found necessary, for staff review four months prior to plant startup after the first refueling outage.
Implementation of any corrective actions found acceptable by_the staff shall be completed prior to plant startup after the first refueling outage.
(6) New Fue_1 Storage (Section 9.1.1, SER, SSER 6 and SSER 7)
IP shall store new fuel assemblies in accordance with the requirements specified in Attachment 2. is_hereby incorporated into this license.
(7) Fire Protection (Section 9.5, SER, SSER 1. SSER 3, SSER 5 and SSER 6)
IP shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report 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 7 thereto subject to the following provision:
IP may make changes to the approved fire protection program without prior approval of the Comission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
(8) Plant Operation Experience (Section 13.1.2.1, SSER 5)
IP, at the time of fuel load, shall have a licensed senior operator on each shift who has had at least 6 months of hot operating experience on a same type plant, including at least 6 weeks at power levels greater than 20 percent of full power,
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.
, and who has had BWR startup and shutdown experience. This license condition shall be effective for a period of 1 year' from fuel load or until the attainment of a nominal 100 percent..
power level, whichever occurs later.
(9) Emergency Planning (Section 13.3, SSER 6)
In the event the NRC staff finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emergency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.
(10) Post-Fuel Loading Initial Test Program (Section 14, SER, SSER 5 and SSER 6)
Any changes to the initial test program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
(11) Emergency Response Capabilities (Generic Letter 82-33, Supplement 1 to NUREG-0737, Section 7.5.3.1, 55ER 5, Section 7.5.3.2, SSER 6 and Section 18, SER and 55ER 5) a.
IP shall install and have operational separate Class IE power sources on the fuel zone level channels and inform the staff
.that the fuel zone level instrument item has been environmentally qualified in accordance with the requirements of 10 CFR 50.49 prior to startup following the first refueling outage.
b.
IP shall submit a detailed control room design supplemental summary report within six (6) months of receipt of a low-power license that addresses all the items identified in Section 18.3 of Supplement 5 to the SER.
c.
The SPDS modifications related to the display of the con-tainment isolation valve group status in the main control room and the incorporation of the 51 additional isolation valves and the isolation valves currently statused on the SPDS into 13 valve groups, instead of 11, shall be completed on the schedule contained in IP's June 11, 1986 letter.
(12) Partial Feedwater Heating (Section 15.1, SER, SSER 5, and SSER 7)
The facility shall not be operated with reduced feedwater temper-ature for the purpose of extending the normal fuel cycle. After the first operating cycle, the facility shall not be operated with a feedwater heating capacity which would result in a rated thermal power feedwater temperature less than 420*F unless analyses supporting such operation are submitted by the licensee and approved by the staff.
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!. D.
The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. An exemption from the criticality alarm requirements of 10 CFR 70.24 was granted in an Amendment to the Special Nuclear Material License No. SNM-1886 dated November 27, 1985.
This exemption is described in Section 9.1.1 of Supplement No. 6 to the SER. This previously granted exemption is continued in this operating license. Exemptions from certain requirements of Appendix A to 10 CFR Part 50 are described in Supplement Nos. 6 and 7 to the SER.
These include:
(a) A schedular exemption from the requirements of General Design Criterion (GDC) 29, permitting deferral of completion of preoperational acceptance testing (Appendix N, 52.1 to SSER 6); (b) A of the Turbine Electrohydraulic Control System until reactor heatup schedular exemption from the requirements of GDC 13, permitting deferral of completion of preoperational testing of the Traversing Incore Probe System until exceeding five percent of rated reactor power (Appendix N, 52.2 to SSER 6); (c) A schedular exemption from the requirements of GDC 60, permitting deferral of preoperational testing related to the Off-Gas System until reactor pressure vessel headset before heatup (Appendix N, 52.3 to SSER 6 and Section 14 of SSER 7); (d) A schedular exemption from the requirements of GDC 41 and 64, permitting deferral of preoperational testing related to portions of the Containment Moni-toring System until initial criticality (Appendix N, 62.4 to SSER 6);
i (e) A schedular exemption from the requirements of GDC 30 and 64, per-mitting deferral of preoperational testing of the Leakage Detection System until initial criticality (Appendix N, 52.5 to SSER 6); (f) A schedular exemption from the requirements of GDC 61, permitting 4
deferral of completion of preoperational testing of a portion of the Fuel Pool Cooling and Cleanup System until exceeding five percent of rated reactor power or before removal of the reactor pressure vessel head after initial criticality (Appendix N, 52.6 to SSER 6);
(g) A schedular exemption from the requirements of GDC 61, permitting t
deferral of completion of preoperational testing of a portion of the Fuel Handling System until exceeding five percent of rated reactor power or before removal of the reactor pressure vessel head after initial criticality (Appendix N, 52.7 to SSER 6); (h) A schedular exemption from the requirements of GDC 19 permitting deferral of completion of preoperational testing of the in-place filters on the Control Room Heating (, Ventilating and Air Conditioning (System until initial criticality Appendix N, 62.8 to SSER 6); and 1) A schedular exemption from the requirements of GDC 41, 57, 60, 61, 63 and 64 i
j permitting deferral of various tests of the Heating, Ventilation and l
Air Conditioning Systems until reactor heatup or before removal of the reactor pressure vessel head after initial criticality (Appendix N, 52.9 to SSER 6). Additional exemptions from two requirements of Appendix J to 10 CFR Part 50 are described in Supplement No. 6 to the SER. These are: a) An exemption from the requirement of Paragraph l
III.D.2(b)(ii) of Appendix J, substituting the seal leakage test at Pa of paragraph III.D.2(b)(iii) for the entire airlock' test at Pa of paragraph III.D.2(b)(ii) of Appendix J when no maintenance has l
been performed in the airlock that could affect its sealing capability I
(Section 6.2.6 of SSER 6); and (b) An exemption from the requirement i
- - ~ _
" j of Paragraph III.C.3 of Appendix J, exempting the measured leakage rates from the main steam isolation valves from inclusion in the com-bined leak rate for the local leak rate tests (Section 6.2.6 of SSER 6).
These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. These exemptions are hereby granted. The special circumstances regarding each exemption are identified in the referenced section of the safety evaluation report and the supplements thereto. These exemptions are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
E.
IP shall fully implement and maintain in effect all provisions of the physical security, guard training and qualifications, and safe-guards contingency plans previously approved by the Commission and all amendments and revisions to such plans made authority under 10 CFR 50.90 and 10 CFR 50.54(p) pursuant to the The plans, which contain safeguards information protected under 10 CFR 73.21, are entitled:
"Clinton Power Station Physical Security Plan," with revisions submitted through January 17, 1986, "Clinton Power Station Guard Quali-fication and Training Plan," with revisions submitted through September 19, 1985; and "Clinton Power Station Safeguards Contingency Plan,"
with revisions submitted through September 20, 1985.
F.
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:
1nitial 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 Operations Center via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73 (b), (c), and (e).
G.
The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accord-ance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
8-H.
This license is effective as of the date of issuance and shall expire at midnight on September 29, 2026.
FOR THE NUCLEAR REGULATORY COMMISSION h
Richard H. Vollmer, Acting Director Office of Nuclear Reactor Regulation
Enclosures:
1.
Attachments 1 and 2 2.
Appendix A - Technical Specifications (NUREG-1203) 3.
Appendix B - Environmental Protection Plan 4.
Appendix C - Antitrust Conditions Date of Issuance: September 29, 1986 4
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H.
This license is effective as of the date of issuance and shall expire at midnight on September 29, 2026.
FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Richard H. Vollmer, Acting Director Office of Nuclear Reactor Regulation
Enclosures:
1.
Attachments 1 and 2 2.
Appendix A - Technical Specifications (NUREG-1203) 3.
Appendix B - Environmental Protection Plan 4.
Appendix C - Antitrust Conditions Date of Issuance:
September 29, 1986 Previously concurred *:
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ATTACHMENT 1 TO NPF-55 Prior to achieving the operational modes indicated, the following items shall be completed to the satisfaction of Region III.
1.
The preoperational tests and test deferrals shall be completed in accordance with the scheduled commitments contained in letters from IP to the NRC, dated March 12, 1986; September 10, 1986; and September 17, 1986.
2.
The following open or unresolved items must be resolved.
a.
IP shall resolve audibility problems encountered on evacuation of personnel in high noise areas in accordance with IP letter dated July 8, 1986, within 6 months of exceeding 5 percent power.
(461/79018-BB) b.
IP shall complete installation and testing of the high range radiation monitors per NUREG-0737 Item 2.F.1 Attachment 3 commitments prior to exceeding 5 percent power.
(461/85004-05) c.
IP shall provide its program for resolving adequacy of Ray Chem splices prior to nuclear heatup.
(461/86008-EE) d.
IP shall provide administrative throttling controls to preclude further degradation of the Anchor Darling globe valve stem to disc tack welds until resolution of 10 CFR 50.55(e) item, but no later than prior to initial criticality.
(461/86007-EE)
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's ATTACHMENT 2 TO NPF-55 NEW FUEL STORAGE IP shall store new fuel assemblies in accordance with the following requirements.
a.
No more than three fuel assemblies shall be outside their shipping containers, storage racks, or the reactor vessel at any one time.
b.
The minimum edge-to-edge distance between the group of three fuel assemblies and all other fuel assemblies shall be 12 inches.
c.
Fuel assemblies, when stored in the New Fuel Storage Vault, shall be stored such that:
no more than 12 rows of fuel assemblies shall remain uncovered during the loading or unloading of fuel assemblies; metal covers shall cover all other rows containing fuel assemblies during loading and unloading of fuel assemblies; and when loading or unloading of fuel assemblies is not in progress, metal covers shall cover all rows of fuel assemblies.
d.
Fuel assemblies shall be stored in such a manner that water would drain freely from the assemblies in the event of flooding and sub-sequent draining of the fuel storage area.
e.
Fuel assemblies after the initial core loading shall be stored in the containment fuel storage pool only under water.
f.
No fuel assemblies shall be stored in the control rod racks.
g.
All fire hoses servicing the New Fuel Storage Vault shall be equipped with solid stream nozzles.
IP shall store new fuel assemblies for the initial core, that will be stored dry 1
in the Containment Fuel Storage Pool, in accordance with the following requirements.
a.
No more than 12 rows of fuel assemblies shall remain uncovered during j
the loading or unloading of fuel assemblies.
l b.
Fire retardant covers, meeting the requirements of National Fire Pro-l te: tion Association (NFPA) Standard 701, shall cover all other rows containing fuel assemblies during loading and unloading of fuel assemblies, c.
When loading or unloading of fuel assemblies is not in progress, fire retardant covers meeting the requirements of NFPA 701 shall cover all rows of fuel assemblies.
d.
Increased surveillance of the Containment Fuel Storage Pool vicinity will be maintained to assure that the area is k yt free of extraneous combustible material, I
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2-f.
The containment spray system will be tagged out prior to the dry storage of fresh fuel assemblies in the Containment Fuel Storage Pool in a status that will prevent initiation of a spray or mist.
g.
All other sources of water to the containment fuel area shall either be equipped with solid stream nozzles or be locked out and safety tagged shut.
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