ML20137B867
| ML20137B867 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 01/09/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Central Iowa Power Cooperative, Corn Belt Power Cooperative, Iowa Electric Light & Power Co |
| Shared Package | |
| ML20137B870 | List: |
| References | |
| DPR-49-A-129 NUDOCS 8601160109 | |
| Download: ML20137B867 (4) | |
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o UNITED STATES E'
P( g NUCLEAR REGULATORY COMMISSION o
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IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.129 License No. DPR-49 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Iowa Electric Light and Power Company, et al, dated October 17, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 l
Commission; 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 Commission's regulations-D.
The issuance of this amendment will not be' inimical to the common defense and security or to the health and safety of the public; j
and f
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is' amended by. changes to the Technical Specifi-I cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby amended to read as follows:
l 8601160109 860109 l
DR ADOCK 05000331 p
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. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.129, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMIS 10 d{
N Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: January 9, 1986 1
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ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Revise the Appendix A Technical Specifications by removing the current pages and inserting the revised pages listed below. The revised areas are identified by vertical lines.
LIST OF AFFECTED PAGES 3.7-i8 e
b 9
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F
DAEC-1 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT maintain the renainder of the secondary containment at 1/4 inch of water negative pressure under calm wind conditions.
2.
If Specification 3.7.C.1 cannot be met:
- a. Suspend reactor building fuel cask and irradiated fuel movement, and
- b. Restore secondary containment integrity within one hour; or,
- c. Be in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D.
Primary Containment Power D.
Primary Containment Power Operated Isolation Valves Operated Isolation Valves 1.
During reactor power operating 1.
The primary containment conditions, all isolation isolation valves surveillance valves listed in Table 3.7-3 shall be performed as follows:
and all instrument line flow check valves shall be OPERABLE a.
At least once per operating except as specified in cycle the OPERABLE isolation 3.7.0.2.
valves that are p6wer opo ated and automatically initiated shall be tested for simulated automatic initiation and closure times.
b.
At least once per quarter:
1)
All normally open power operated isolation valves (except for those exempted as noted In Table 3.7-3) shall be j
fully closed and reopened.
2)
With the reactor power less l
than 75%, trip main steam isolation valves individually and verify closure time, c.
At least once per week the main steam line power-operated isolation valves shall be exercised 3.7-18 Amendment No. 129