NUREG-1235, License NPF-62 for Full Power Operation.W/O Tech Specs (NUREG-1235)
| ML20212Q898 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 04/17/1987 |
| From: | Murley T Office of Nuclear Reactor Regulation |
| To: | Illinois Power Co, Soyland Power Cooperative, Western Illinois Power Cooperative |
| Shared Package | |
| ML20212Q900 | List: |
| References | |
| RTR-NUREG-1235 NUDOCS 8704240125 | |
| Download: ML20212Q898 (9) | |
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NUCLEAR REGULATORY COMMISSION I
WASHINGTON, D. C. 20555 k.....,o ILLINOIS POWER COMPANY SOYLAND POWER COOPERATIVE. INC.
WESTERN ILLINDIS POWER COOPERATIVE. INC.
DOCKET NO. 50-461 CLINTON POWER STATION UNIT NO. 1 FACILITY OPERATING LICENSE License No. NPF-62 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 on behalf of itself and as agent for Soyland Power Cooperative, Inc.'andWesternIllinoisPowerCooperative,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 mt.de; B.
Construction of the Clinton Power Station, Unit No.1 (the facility) has been substantially completed in confonnity 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 confonnity 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)thattheactivitiesauthorizedby 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.
8704240125 B70417 PDR ADOCK 05000461 P
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. G.
The issuance of this license will not be inimical to the comon 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 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 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-55, issued on September 29, 1986, 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,.peWitt County, approximately six miles east of the city of Clinton in east-central Illinois and is described in the licensees' Final Safety Analysis Report, as 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 Part 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;
s (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-i ation monitoring equipment calibration, and as fission detectors in amounts as required; (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 4
(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.
i C.
This license shall be deemed to contain and is subject to the condi-tions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and J
to the rules, regulations and orders of the Commission now or here-after in effect; and is subject to the additional conditions specified or incorporated below:
a l
(1) Maximum Power Level i
IP is authorized to operate the facility at reactor core power levels not in excess of 2894 megawatts thermal (100 percent rated 4
power)inaccordancewiththeconditionsspecifiedherein.
4 l
The items identified in Attachment 1 to this license 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 accordance 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.
1
s 4-(4) Contrcl System Failures (Section 7.7.3.1 SER and SSER 61*
IP shall submit, in accordance with commitments 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 4
any corrective actions found acceptable by the staff shall be completed prior to plant startup after the first refueling outage.
(5) New Fuel Storace (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.
(6) Plant Operation Experience (Section 13.1.2.1 SSER 5)
IP shall have a licensed senior operator on each shift who has had at least 6 months of hot operating experience on a large commercial BWR, including at least 6 weeks at power levels greater than 20 percent of full power, 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.
(7) ENeroency Plannino (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 emeroency preparedness, the provisions of 10CFRSection50.54(s)(2)willapply.
- 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.
4 4
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. (8) Post-Fuel Loading Initial Test Program (Section 14, SER, SSER 5 and 55tR 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.
(9) Emergency Response Capabilities (Generic Letter 82-33, Supplement 1 to NUREG-0/37, Section /.b.3.1, 55tR b and SSER 8, and Section 18, SER, 55tR b and 5afety Evaluation Dated April 1/, 198/)
a.
IP in accordance with the commitment contained in a letter dated December 11, 1986, shall install and have operational separate power sources for each of the fuel zone level channels as provided for in Regulatory Guide 1.97 prior to startup following the first refueling outage.
b.
IP shall submit a detailed control room design final supplemental summary report within 90 days of issuance of the full power license that completes all the remaining items identified in Section 18.3 of the Safety Evaluation dated April 17, 1987.
(10) 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.
D.
The facility requires exemptions from certain requirements of 10 CFR therequirementsof10CFR70.24forthecrit(a)anexemptionfromicality alar Part 50 and 10 CFR Part 70. These include:
around the fuel storage area; (b) an exemption from the require-ments of Appendix A to 10 CFR Part 50,letion of preoperationalGeneral to permit a schedular deferral of comp testing of a portion of the Fuel Handling System until prior to off-loading fuel from the reactor vessel (Section 14 (c)an exemptionfromtherequirementofparagraphIII.6.SSER8));
2(b)(ii of Appendix J substituting the seal leakage test at Pa of paragraph III.D.2(
iii)fortheentireairlocktestatPaofparagraph III.D.2(
ii)ofAppendixJwhennomaintenancehasbeenperformed in the a ockthatcouldaffectitssealingcapability(Section and(d)anexemptionfromtherequirementof 6.2.6ofSSER6)$ofAppendixJ,l paragraph III.C.
exempting the measured leakage rates from the main steam isolation va ves from inclusion in the combined leakrateforthelocalleakratetests(Section6.2.6ofSSER6).
Thespecialcircumstancesregardingeachexemption,exceptforitem(a) above, are identified in the referenced section of the safety evalua-tion report and the supplements thereto.
1 l
. An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1886, issued November 27, 1985, and relieved IP from the requirement of having a criticality alarm system.
IP is hereby exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.
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.
The exemptions in items (b), (c) and (d) above are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in con-formity 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 pursuant to the authority under 10 CFR 50.90 and 10 CFR 50.54(p). 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.
IP shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analy' sis 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 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 would not adversely affect the ability to achieve and maintain safe 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 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).
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. H.
The licensees shall have and maintain financial protection of such type and in 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 and shall expire at midnight on September 29, 2026.
FOR THE NUCLEAR REGULATORY COMMISSION original signed by 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 4.
Appendix C - Antitrust Conditions Date of Issuance:
April 17, 1987 Previously concurred *:
Telephone MKarman concurrence for
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ATTACHMENT 1 TO NPF-62 Prior to achieving the milestone indicated, the following items shall be com91eted to the satisfaction of Region III.
1.
Preoperational test PTP-FH, Fuel Handling System, shall be completed prior to off-loading irradiated fuel.
2.
IP shall resolve audibility problems encountered on evacuation of personnel in high noise areas in accordance with IP letter dated July 8, 1986. A survey of high noise areas shall be completed within 30 days after achieving maximum anticipated noise level.
All corrective actions required by the survey shall be completed prior to the completion of the first refueling outage.
In the interim for those areas which are identified as havina deficient siren audibility, temporary administrative measures will be taken to ensure that these areas are evacuated as required.
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ATTACHMENT 2 TO NFF-62 f4EW 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 loadino 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 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.
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