ML20211J863

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Forwards Draft Low Power License NPF-55,w/o Attachment 1 & Apps,For Review & Comment to Ensure Accurate Reflection of Commitments Described in Fsar,Ser & Other Documents.Comments Requested within 10 Working Days of Ltr Receipt
ML20211J863
Person / Time
Site: Clinton Constellation icon.png
Issue date: 06/18/1986
From: Butler W
Office of Nuclear Reactor Regulation
To: Spangenberg F
ILLINOIS POWER CO.
References
NUDOCS 8606270078
Download: ML20211J863 (13)


Text

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JUN 18 586 DISTRIBUTION JUocreT7TTes DVassallo,F0B Docket No. 50-461 PD#4 Rdg.~~ RBernero NRC PDR RGoddard,0 ELD LPDR WButler BSiegel Mr. Frank A. Spangencerg M0'Brien Manager-Licensing and Safety EJordan Clinton Power Station BGrimes P.O. Box 678 JPartlow Mail Code V920 ACRS(10)

Clinton, Illinois 61727 NThompson

Dear Mr. Spangenberg:

SUBJECT:

DRAFT LOW POWER LICENSE Re: Clinton Power Station, Unit No. 1 As you are aware, the staff is preparing a low power license (NPF-55) for the Clinton Power Station. Enclosed is a draft copy of this license but without attachment I and appendices. It is provided for your review and comment to ensure that it accurately reflects the commitments required of you as described 4

in the FSAR, SER and other documents. We request that you review this draft low power license and provide any comments in writing within 10 working days of receipt of this document.

If you have any questions regarding this draft low power license, contact the staff's Project Manager for your application, Byron Siegel, at (301) 492-9474.

l Sincerely, original signed by Walter R. Butler, Director BWR Project Directorate No. 4 i

Division of BWR Licensing

Enclosure:

As stated cc: w/ enclosure See next page

! PD#1) PD#4/?M k PD#4/D M0 ' B r, BSiegel:f6 WButler -

86 06/tW86 06/ly/86 06/[

8606270078 860618 PDR ADOCK 05000461 A PDR

Mr. Frank A. Spangenberg Clinton Power Station Illinois Power Ccmpany Unit 1 cc:

Mark Jason Richard B. Hubbard Assistant Attorney General Vice President Public Utilities Division Technical Associates Office of the Attorney General 1723 Hamilton Avenue - Suite K State of Illinois Center San Jose, California 95125 100 West Randolph Street - 12th Floor Chicago, Illinois 60601 Chairman of DeWitt County c/o County Clerk's Office Mr. D. P. Hall DeWitt County Courthouse Vice President Clinton, Illinois 61727 Clinton Power Station P. O. Box 678 Director, Criteria & Standards (ANR-460)

Clinton, Illinois, 61727 Office of Radiation Programs V. S. Environmental Protection Agency Mr. D. C. Shelton Washington, DC 20460 Manager-Nuclear Station Engineering Dpt.

Clinton Power Station EIS Review Coordinator P. O. Box 678 .

Environmental Protection Agency 4.

Clinton, Illinois 61727 Region V 230 S. Dearborn Street Sheldon Zabel, Esquire Chicago, Illinois 60604 Schiff, Hardin & Waite 7200 Sears Tower Illinois Department of Public Health 4 233 Wacker Drive ATTN: Chief, Division of Nuclear Safety Chicago, Illinois 60606 535 West Jefferson Springfield, Illinois 62761 Resident Inspector U. S. Nuclear Regulatory Commission Director, Eastern Environmental RR 3, Box 229 A Radiation Facility Clinton, Illinois 61727 U. S. Environmental Protection Agency i P. O. Box 3009 i Mr. R. C. Heider Montgomery, Alabama 36193 Project Manager Sargent & Lundy Engineers 55 East Monroe Street Chicago, Illinois 60603 Mr. L. Larson Project Manager General Electric Company 175 Curtner Avenue, N/C 395 San Jose, California 95125 Regional Administrator, Region III 799 Roosevelt Road )

Glen Ellyn, Illinois 60137 l

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ILLIN0IS POWER COMPANY S0YLAND POWER COOPERATIVE, INC.

WESTERN ILLINOIS POWER COOPERATIVE, INC.

DOCKET NO. 50-461 ,,

CLINTON POWER STATION, UNIT'NO. 1 FACILITY OPERATING LICENSE 1.icense No. NPF-55

1. The Nuclear Regulatory Commission (the Commission 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. 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 Commission's regulations set forth in

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h. - --40.CFR Chapter If 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 conformity 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 2.0.

below);

D. There is reasonable assurance: (i) 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 Commission'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.
e. .

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 c'ontidering 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 Pcwer Station, Unit No. 1, a boiling water nuclear reactor and associated equipment (the facility), owned by Illinois Power Company, Soyland Pcwer 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 ar.d 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 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;

(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; - -

(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-tions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all. applicable provisionstof the..A. t agg ,

- -to the rules, regulations and orders of the Commission now ors (he m 4 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 levels not in excess of 2894 megawatts thermal (100 percent rated 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 I 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.

i W. 1

(4) Inservice Inspection Program (Section and 6.6, SER, SSER 1 and SSER 5)*

.IP shall submit the initial inservice inspection program required by 10 CFR 50.55(a) for NRC staff review and approval

. . - = within six (6) months after exceeding five percent of rated powert -

(5) New Fuel Storage (Section 9.1.1, SER and SSER 6)

IP shall store new fuel assemblies in accordance with the requirements specified in Attachment 2. Attachment 2 is hereby incorporated into this license.

(6) Fire Protection (Section 9.5.1, 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) i dated February 1982 and Supplement Nos. I thru 6 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.

(7) Post-Fuel Loading Initial Test Program (Section 14, SER and SSER 5)

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. 1 (8) Partial Feedwater Heating (Section 15.1, SER, SSER 5, and SSER 6)

The facility shall not be operated with partial feedwater heating for the purpose of extending the normal fuel cycle.

After the first operating cycle, steady state operation with reduced feedwater temperature during the normal fuel cycle l

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! *The parenthetical notation following the title of many license conditions l denotes the section of the Safety Evaluation Report and/or its supplements ,

wherein the license condition is discussed. I

shall be prohibited until plant specific analyses justifying such operation are provided by IP and approved by the staff.

(9.) Emergency Response Capabilities (Generic Letter 82-33, Supplement 1 to NUREG-0737, Section 7.5.3.1, SSER 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 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.

(10) 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 1 an adequate state'of emergency preparedness, the provisions of '

10 CFR Section 50.54(s)(2) will apply.

(11) Salem ATWS Event, Generic Letter 83-28 (Section 15.2.2, SSER 5 and SSER 6)

IP shall implement the requirements of Generic Letter 83-28, for those items not already completed, on a schedule which is consistent with that given in IP's letter dated October 1, 1984, 1

1 w- .

The facility requires exemptions from certain requirements of 10 CFR D.

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 fo'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 No. 6 to the SER. These include: (a) A schedular exemption from the requirements of General Design Criterion (GDC) 29, permitting deferral of completion of pre-operational acceptance testing of the Turbine Electrohydraulic Control System until prior to reactor heatup (Appendix to SSER 6); (b) A schedular exemption from the requirements of GDC 13, permitting deferral of completion of preoperational testing of the Traversing Incore Probe System until prior to reactor heatup (Appendix to S3ER 6); (c) A schedular exemption from the requirements of GDC 60, permitting deferral of preoperational testing related to the Off-Gas System until prior to reactor pressure vessel headset before heatup (Appendix TOSSER 6);

(d) A schedular exemption from the requirements of GDC 41 and 64, permitting deferral of preoperational testing related to portions of the Containment (Appendix to SSERMonitoring) Systemexemption 6); (e A schedular until priorfrom to initial criticality the requirements of GDC 30 and 64, permitting deferral of preoperational testing of the Leakage Detection System until prior to initial criticality (Appendix to SSER 6); (f) A schedular exemption from the requirements of GDC 61, permitting deferral of completion of preoperational testing of a portion of the Fuel Pool Cooling and Cleanup System until prior to exceeding five percent of rated reactor power or before removal of the reactor pressure vessel head after initial criticality (Appendix TOSSER 6);

(g) A schedular exemption from the requirements of GDC 61, permitting deferral of completion of preoperational testing of a portion of the Fuel Handling System until prior to exceeding five percent of rated reactor power or before removal of the reactor pressure vessel head after initial criticality (Appendix 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 prior to initial criticality (Appendix to SSER 6); and (1) A sched-ular exemption from the requirements of GDC 41, 57, 60, 61, 63 and 64 permitting deferral of various tests of the Heating, Ventilation and Air Conditioning Systems until prior to reactor heatup or before removal of the reactor pressure vessel head after initial criticality (Appendix 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)AnexemptionfromtherequirementofParagraphIII.D.2(b)(ii) l l

6

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 been performed in the airlock that could affect its sealing capability (Section 6.2.6 of SSER 6); and (b) An exemption from the requirement of

- - Pa5 graph III.C.3 of Appendix J, exempting the measured leakage rates +L from the main steam isolation valves from inclusion in the combined 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 comon 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-l 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, 1936, "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: 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).

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.

H. This license is effective as of the date of issuance and shall expire at midnight on 2026 FOR THE NUCLEAR REGULATORY COMMISSION

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cG4. . s Harold R. Denton, 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:

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H. This license is effective as of the date of issuance and shall expire at midnight on 2026 FOR THE NUCLEAR REGULATORY COMMISSION

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Harold R. Denton, 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:

PD#4/LA PD#4/PM SAB/DE SP SP OELD OELD M0'Brien BSiegel:1b WLamb IDinitz JSaltzman RGoddard EReis

/ /86 / /86 / /86 / /86 / /86 / /86 / /86 OELD PD#4/D DD/ DBL D/BDL DD/NRR D/NRR JScinto WButler RHouston RBernero DEisenhut HDenton

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ATTACHMENT I DETAILS TO BE PROVIDED AS APPROPRIATE BY REGION III

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I ATTACHMENT 2 TO NPF-55 NEW TUEL 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 and storage racks 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 for the initial core, when stored dry in the Contain-i ment Fuel Storage Pool, shall be stored such that: no more than 12 rows of fuel assemblies shall remain uncovered during the loading or unloading of fuel assemblies; fire retardant covers shall cover all other rows containing fuel assemblies during loading and unloading of fuel assemblies; when loading or unloading of fuel assemblies is not in progress, fire retardant covers shall cover all rows of fuel assemblies; increased surveillance of the Containment Fuel Storage Pool vicinity will be maintained to assure that the area is kept free of extraneous combustible material; the fire protection hose stations servicing the Containment Fuel Storage Pool area will be equipped-with solid stream nozzles prior to the dry storage of fresh fuel assemblies in the Containment Fuel Storage Pool; and the containment spray system will be tagged out prior to the dry storage of fresh fuel as'semblies in the Containment Fuel Storage Pool in a status that will prevent initiation of a spray or mist.
d. 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.
e. 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.

l f. Fresh fuel assemblies after the initial core loading shall be stored in the containment fuel storage pool only under water.

g. No fuel assemblies shall be stored in the control rod racks.

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