ML20086R597

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Safety Evaluation Supporting Amend 93 to License DPR-49
ML20086R597
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 02/14/1984
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20086R586 List:
References
NUDOCS 8402290439
Download: ML20086R597 (2)


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%.% : y SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTIkG AltENDMENT N0. 93 TO LICENSE NO. DPR-49 IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331 1.0 introduction _

By letter dated November 10,1981 (IELP LDR-81-297) the Iowa Electric Light and Power Company (the licensee) requested changes to the Techni-cal Specifications (Appendix A) appended to Facility Operating License No. DPR-49 for Duane Arnold Energy Center (DAEC).

The proposed amendment would revise the Technical Specifications and incorporate the following administrative changes into the DAEC Technical Specifications: change

.a reference regarding Accident Monitoring Instrumentation Table; change the Reactor Pump Trip response time setting; change Special Reports sec-tion to require reports "within 30 days"; change a position title; change High Radiation Areas access requirements of 10CFR20.203; and add a refer-ence to the Fire Protection System Special Reports section.

2.0 Evaluation

2.1 Background

Several administrative changes are being made to the Technical Specifications.

These include a change regarding a reference to the Accident Monitoring Instrumentation tables, a revision to the section on Special Reports to include the requirement "within 30 days" for the purposes of achieving consistency throughout the Technical Specifications, a change in a posi-tion title, and a change adding a reference to the Fire Protection Systems Special Reports section.

We find these changes to be purely administrative and, therefore, acceptable.

2.2 Reactor Pump Trip Resconse Tine Setting A new requirement has been added to assure that the Reactor Pump Trip re-sponse time will not exceed 140 milliseconds, measured from initiation of turbine control valve fast closure or turbine trip valve closure to actuation breaker secondary (auxiliary) contact.

This requirement replaces the previous specifications which allows the response time to be determined by testing after installation, j

8402290439 840214 DR ADOCK 05 y

I l I The licensee has completed the response time tests and has determined that the response time will not exceed 140 milliseconds.

No further response time tests are needed and the requested Technical Specification change which is intended to clearly specify the response time limit, is acceptable.

2.3 Hioh Radiation Areas Access Requirements Positive control of personnel access into high radiation areas is required.

Each entry must be controlled unambiguously in a manner which in consistent with good radiation protection practice. The Standard Technical Specifi-cations for high radiation area access control have been written to express i

clearly the manner in which positive control for entry into high radiation areas will be exercised. The Duane Arnold submittal of November 10, 1981 is acceptable because the modification establishes improved physical and administrative methods for access control and provides clear, definitive conditions fnr positiv,e access control for entry into high radiation area.

The proposed change is, therefore, acceptable.

l 3.0 Environmental Considerations We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.

Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environnental 1

impact, and pursuant to 10 CFR 951.5(d)(4), that an environmental 4

impact statenent, or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.

4.0 Conclusion i

We have concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the-Commission's regulations, and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Reviewer:

M. Thadani Dated:

February 14, 1984 1

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