ML20199G180
| ML20199G180 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 03/27/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20199G167 | List: |
| References | |
| NUDOCS 8604090081 | |
| Download: ML20199G180 (2) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.131 TO LICENSE N0. DPR-49 IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DUANE ARNOLD ENERGY CENTER DOCKET N0. 50-331
1.0 INTRODUCTION
By submittal dated January 3,1986, the Iowa Electric Light and Power Company proposed a Technical Specification change to permit a Temporary increase in the Duane Arnold Energy Center main steam line high radiation scram and isolation setpoints to facilitate the testing of hydrogen l
additiun water chemistry at their plant. This proposed change is necessary since it is anticipated that main steam line radiation levels may increase during the test by factor of five over the routinely experienced radiation levels.
2.0 EVALUATI_0N The staff reviewed the proposed Technical Specification change to assure that the licensee has considered the radiological implications of the dose rate increase associated with N-16 equilibrium changes during hydrogen addition. The review also intended to determine that the licensee has adequately considered radiation protection measures for the course of the test, in accordance with 10 CFR 20.1(c) and Regulatory Guide 8.8, "Information relevant to ensuring that Occupational Radiation Exposure at Nuclear Power Stations will be As low As Is Reasonably Achievable."
An overall objective of the test is to determine general in-plant and site boundary dose rate increases due to hydrogen addition. The licensee has indicated that normal radiation protection ALARA (As low As Reasonably Achievable) practices and procedures for Duane Arnold Energy Center (DAEC) will be continued throughout the test. Additionally, main steam system dose rates will be monitorec' by surveys on a routine basis.
Also, specific locations where temporary shielding may be needed for long term implementation of hydrogen injection will be identified.
The licensee will preserve the trip function of the main steam line radiation monitors (MSLRM) for the design basis rod drop accident during hydrogen injection. This will be done by adjusting the MSLRM setpoints only when the reactor is at 20% power or above.
Fuel defects and failures will be monitored using MSLRM, and the steam jet air ejector off-gas monitor, as well as through routine radiation surveys, and daily primary coolant analysis.
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-9 The staff has verified from the licensee the details of the dose control measures and surveillance efforts planned by the li.censee for the hydrogen addition test.
Similar tests have been proposed and conducted at other BWRs of design similar to DAEC during their successful hydrogen addition tests. None of these t.ests involved any significant unanticipated, radiological exposures or releases.
On the basis of the adequacy of the licensee's radiation protection /ALARA program, utilization of special surveys to monitor dose rate increases on site and at the site boundary, capability to monitor for fuel failures, as well as the success of similar efforts at other operating BWRs, the staff finds the licensee's request acceptable. Hence, the staff recommends that t,he Technical Specification change be approved as requested.
3.0 ENVIRONMENTAL CONSIDERATION
S This amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
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 nat be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
M. Lamastra Dated: March 27, 1986
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