ML20141F083
| ML20141F083 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/23/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20141F080 | List: |
| References | |
| NUDOCS 8601080596 | |
| Download: ML20141F083 (3) | |
Text
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NUCLEAR REGULATORY COM, MISSION o
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 99 TO FACILITY OPERATING LICENSE NO. DPR-66 4
DUQUESNE LIGHT COMPANY OHIO EDIS0N COMPANY PENNSYLVANIA POWER COMPANY BEAVER VALLEY POWER STATION, UNIT NO. 1 DOCKET NO. 50-334 Introduction By application dated June 17, 1985, Duquesne Light Company (the licensee),
submitted a proposed amendment to the Technical Specification set forth in Appendix A to Operating License No. DPR-66 for the Beaver Valley Power Station, Unit 1.
This amendment would remove the iodine sampler cartridges from the radioactive gaseous effluent monitoring instrumentation listed in Tables 3.3-13 and 4.3-13.
4 Discussion and Evaluation During the implementation of NUREG-0737 (post-TMI) action items, the licensee became awam <:f the projected difficulties of retriev1ng and analyzing iodine sampler cartridges from the gaseous effluent monitors located in various buildings under accident conditions. The licensee has redundant capability for monitoring effluent releases: the original gaseous effluent monitor (Victoreen) and the more recent Special Particulate Iodine and Noble Gas (SPING) radiation monitor (Eberline).
Iodine sampler cartridges can be retrieved from the SPING system with less hazard to site personnel during emergencies.
The licensee, therefore, requested a deletion of the requirement to maintain iodine sampler cartridges in the original gaseous effluent monitors.
The proposed change would not remove the requirement for iodine sampling, analysis and reporting. This would continue to be required under Section 4.11.2 (Radiological Environmental Technical Specification RETS), and the licensee has routinely used the SPING iodine cartridges as a source of data for the effluent reporting requirements in accordance with Regulatory Guide l
1.21.
This proposal is consistent with the Beaver Valley Unit 1 FINAL SAFETY ANALYSIS Report Section 11.3.3.3, " Monitors", i.e., both the Gaseous Waste Gas Monitor (Section 11.3.3.3.2) and the High Range Noble Gas Monitors (Section 11.3.3.3.23) have provision for an iodine sampler cartridge but do not require their continuous use.
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I The licensee performed a study in response to NRC Unresolved Item 50-334/
83-30-05 to determine the capability of the SPING monitors to collect repre-sentative samples. The Unresolved Item resulted from a routine radiation safety inspection, in which the inspector questioned whether the wide separa-tion between the sample nozzle location and the monitoring cabinets could result in losses in the interconnecting piping. This could result in errone-ously low readings for radioactive particulates and iodine. The systems affected included Process Vent, Ventilation Vent and the Supplementary Leak Collection and Release System (SLCRS). Each is a potential release path to the environment for airborne activity.
On December 14, 1984, the Duquesne Light Company sent the results of an eval-uation of the effluent radiation monitors to the Regional Administrator. The study carefully profiles the air flow in one section of the SLCRS and resulted in the design of a temporary isokinetic sampling probe. The licensee used guidance contained in ANSI N13.1 and ANSI N13.10 (Now ANSI N42.18-1980). Grab samples of iodine activity obtained via this probe for a six-month period were compared with readings from the permanently installed monitors. Good correlation was obtained for the iodine activity. The licensee's report has been reviewed (Inspection Report No. 50-334/85-17) and found to provide a reasonable and technically competent approach to the resolution of'NRC Unresolved Item 83-30-05. The NRC concurred that good correlation was obtained among all radiation monitors for measuring Iodine 131.
Environmental Consideration This amendment involves a change in the 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 amourts, 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 Comission has previously issued a proposed finding that this amendment involves no l
significant hazards consideration and there has been no public coment on such finding. Accordingly, this amendment meets the eli for categorical exclusion set forth in 10 CFR Sec 51.22(gibility criteria c)(9). Pursuant to i
10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
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 Comission's regulations and the issuance of this amendment will not i
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3-be inimical to the common defense and security or to the health and safety of the public.
Dated:
December 23, 1985 Principal Contributors:
R. Struckmeyer T. Dragoun i
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