ML21300A027

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Clarification Call, Summary of October 21, 2021, Clarification Call with Pacific Gas and Electric Company Regarding Final Status Survey Report HBL-21-010, Survey Unit OOL01-03
ML21300A027
Person / Time
Site: Humboldt Bay
Issue date: 10/28/2021
From: Amy Snyder
Reactor Decommissioning Branch
To:
Pacific Gas & Electric Co
Snyder A
References
Download: ML21300A027 (3)


Text

October 28, 2021 LICENSEE: Pacific Gas and Electric Company FACILITY: Humboldt Bay Power Plant, Unit 3

SUBJECT:

SUMMARY

OF OCTOBER 21, 2021, CLARIFICATION CALL WITH PACIFIC GAS AND ELECTRIC COMPANY REGARDING FINAL STATUS SURVEY REPORT HBL-21-010, SURVEY UNIT OOL01-03, FOR THE HUMBOLDT BAY POWER PLANT, UNIT 3 The U.S. Nuclear Regulatory Commission (NRC) conducted a clarification call with Pacific Gas and Electric Company (PG&E), the licensee, on October 21, 2021. The purpose of the call was to ensure NRC staff understands certain aspects of the final status survey report (FSSR) that was submitted on June 8, 2021 (Agencywide Documents Access and Management System Accession No. ML21160A224).

The meeting began with opening remarks by the NRC staff, followed by introductions of the attendees. From NRC, Amy Snyder and Gregory Chapman were on the call. Brandy Lopez, Kris Rowberry and Bill Barley represented PG&E.

The NRC staff asked the licensee to clarify how it resolved whether there was an elevated measurement in Survey Unit OOL01-03. In the submittal, the licensee stated that it had an investigative sample that analyzed at ~27 pCi/g Cs-137. To resolve the issue, the licensee made mention of performing an In Situ Object Counting System (ISOCS) measurement that gave a result of ~0.5 pCi/g.

The licensee stated that they did follow up scanning using a 2x2 NaI detector which indicated there was no elevation in activity. Also, the licensee indicated that the sampling procedure indicated that the elevation was extremely discrete such that sampling likely was effective as remediation as demonstrated by the ISOCS measurement.

Also, the NRC asked why some radionuclides were not addressed in the evaluation. The licensee said that for any specific survey unit, if any radionuclides of concern were neither deselected nor reported (e.g., Nb-94, Eu-152, Eu-154, Np-237, and Am-24 are typically not reported in most of the FSSRs), then those radionuclides were not detected at concentrations above their respective minimum detectable concentrations and/or were of such low concentration that it had, on average, negligible potential dose impact. Therefore, those radionuclides were not reported for that particular survey unit.

2 The NRC staff informed the licensee that the NRC staff needs the licensee to provide the clarification in writing to the NRC so it can complete its safety evaluation. PG&E said that it would be able to provide that in writing in the near future.

At this meeting, the NRC staff made no regulatory decisions about the merits of the applicable FSSR.

Please direct any inquiries to me at (301) 415-6822 or Amy.Snyder@nrc.gov.

Sincerely, Signed by Snyder, Amy on 10/28/21 Amy M. Snyder, Senior Project Manager Reactor Decommissioning Branch Division of Decommissioning, Uranium Recovery and Waste Programs Office of Nuclear Material Safety and Safeguards Docket No.: 50-133 License No. DPR-7

ML21300A027

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BWatson NAME ASnyder AS ASnyder AS JParrott for JP DATE Oct 27, 2021 Oct 28, 2021 Oct 28, 2021