ML20059F914
| ML20059F914 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 09/08/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | Illinois Power Co, Soyland Power Cooperative |
| Shared Package | |
| ML20059F917 | List: |
| References | |
| NPF-62-A-083 NUDOCS 9311050161 | |
| Download: ML20059F914 (5) | |
Text
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UNITED STATES 8'
NUCLEAR REGULATORY COMMISSION o
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ILLIN0IS POWER COMPANY S0YLAND POWER COOPERATIVE. INC.
DOCKET NO. 50-461 CLINTON POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 83 License No. NPF-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment by Illinois Power Company' (IP),
and Soyland Power Cooperative, Inc. (the licensees) dated February 17, 1993, and April 16, 1993, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
2 2.
Accordingly, the license is amended by changes to the Technical Specifications 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.
2Pages 5 and 6 are attached, for convenience, for the composite license to reflect this change.
9311050161 931018 PDR ADOCK 05000461-P PDR _
(
- (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as i
revised through Amendment No. 83, are hereby incorporated into this license.
Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
D.
The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. These include:
(a) an exemption from the requirements of 10 CFR 70.24 for the criticality alarm monitors around the fuel storage area; (b) an exemption from the requirement of paragraph III.D.2(b)(ii) of Appendix J, substituttrg 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); (c) an exemption from the requirement of paragraph III.C.3 of Appendix J, exempting the measured leakage rates 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); (d) an exemption from the requirements of paragraph III.B.3 of Appendix J, exempting leakage from the valve packing and the body-to-bonnet seal of valve IE51-F374 associated with containment penetration IMC-44 from inclusion in the combined leakage rate for penetrations and valves subject to Type B and C tests; and (e) an exemption from the requirement of paragraph III.D.l.(a) to conduct the third Type A test of each 10-year service period when the plant is shut down for the 10-year plant inservice inspections. The special circumstances regarding each exemption, except for Items (a), (d), and (e) above, are identified in the referenced section of the safety evaluation report and the supplements thereto.
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.
If 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.
The special circumstances regarding the exemption identified in Item (d) above are identified in the safety evaluation accompanying Amendment No. 62 to this license. The special circumstances regarding the exemption identified in Item (e) above are identified in the safety evaluation accompanying Amendment No. 83 to this license.
i 1 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) through (e), above 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.
3.
This license amendment is effective as of its date of issuance, to be implemented during the fourth refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION 1414 h.
ames E. Dye Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
1.
License pages 5 and 6 2.
Changes to the Technical Specifications Date of Issuance: September 8, 1993
4
' J 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.
The special circumstances regarding the exemption identified in Item (d) above are identified in the safety evaluation accompanying Amendment No. 62 to this license. The special circumstances regarding the exemption identified in Item (e) above are identified in the safety evaluation accompanying Amendment No. 83 to 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) through (e) above 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.
The licensees shall fully implement and maintain in effect all provisions of the Commission-approved physical security plan, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments 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 plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:
"Clinton Power Station Physical Security Plan,"
with revisions submitted through May 27, 1993; "Clinton Power Station Training and Qualification Plan," with revisions submitted through May 27, 1993; and "Clinton Power Station Safeguards Contingency Plan,"
with revisions submitted through May 27, 1993. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
F.
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 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 i
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 1
Operations Center via the Emergency Notification System with written
-l followup within thirty days in accordance with the procedures described in 10 CFR 50.13(b), (c), and (e).
Amendment No. 83 J
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE SURVEILLANCE RE0VIREMENTS (Coritinued) 4.6.1.2 (Continued) 2.
Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the primary containment or bled from the primary containment during the supplemental test to be between 0.75 La and 1.25 La.
d.
Type B and C tests shall be conducted ***," with gas at Pa, 9.0 psig, at intervals no greater than 24 months except for tests involving:
1.
Air locks, 2.
Main steam line isolation valves, 3.
Penetrations using continuous leakage monitoring systems, 4.
All containment isolation valves in hydrostatically tested lines which penetrate the primary containment, and 5.
Purge supply and exhaust isolation valves with resilient material seals.
e.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
f.
Main steam line isolation valves shall be leak tested with gas at Pa, 9.0 psig, at least once per 18 months.
g.
Type B tests for penetrations employing a continuous leakage monitoring system shall be conducted at Pa, 9.0 psig, at every other reactor shutdown for refueling, but in no case at intervals greater than 3 years.
h.
All containment isolation valves in hydrostatically tested lines which penetrate the primary containment shall be leak tested at 1.10 Pa, 9.9 psig, at least once per 18 months.
i.
Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Require-ment 4.6.1.8.3.
J.
The provisions of Specification 4.0.2 are not applicable to Specifica-tions 4.6.1.2.a, 4.6.1.2.b, 4.6.1.2.d, and 4.6.1.2.g.
- Except as provided in NRC-approved exemption to Appendix J to 10 CFR 50 for containment penetration IMC-44.
"The leakage rate for containment penetration IMC-4 is not required to be determined until startup from the fifth refueling outage in accordance with an approved exemption to Appendix J of 10 CFR 50.
CLINTON - UNIT 1 3/4 6-4 Amendment No. 83