ML19210D543

From kanterella
Jump to navigation Jump to search

Summary of Teleconference with Northern States Power Company on Potential License Amendment Request to Adopt Probabilistic Risk Assessment Model
ML19210D543
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 08/20/2019
From: Robert Kuntz
Plant Licensing Branch III
To:
Northern States Power Co
Kuntz R
References
EPID L-2019-LRM-0045
Download: ML19210D543 (4)


Text

August 20, 2019 LICENSEE:

Northern States Power Company FACILITY:

Prairie Island Nuclear Generating Plant

SUBJECT:

SUMMARY

OF JULY 22, 2019, TELECONFERENCE WITH NORTHERN STATES POWER COMPANY REGARDING A POTENTIAL LICENSE AMENDMENT REQUEST TO ADOPT A PROBABILISTIC RISK ASSESSMENT MODEL FOR ABEYANCE SEAL AT PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (EPID: L-2019-LRM-0045)

On July 22, 2019, a Category 1 public teleconference was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Northern States Power Company. The purpose of the meeting was to discuss a potential license amendment request for a probabilistic risk assessment (PRA) model for a reactor coolant pump (RCP) abeyance seal for the Prairie Island Nuclear Generating Plant (PINGP). The meeting notice and agenda, dated July 9, 2018, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML19190A229. A list of attendees is provided in the Enclosure.

The licensee presented information (ADAMS Accession No. ML19210D451) related to the potential license amendment request. The licensee presented an overview of the planned amendment including, the schedule for submittal.

The NRC staff queried the licensee on how the abeyance seal affects the time for operators to manually trip the RCP in the PRA model. The licensee responded that the time for operator action is limited by the material of the seal and is not increased by the abeyance seal. Also, the NRC staff asked the licensee how inadvertent actuation of the abeyance seal was modeled.

The licensee stated that inadvertent actuation would not be noticed, but that the seal would not performed as designed if subsequently called upon to actuate. The licensee further stated that inadvertent actuation is not credible and any probability that the seal would fail to actuate due to a prior inadvertent actuation is included in the probability of failure due to improper installation.

The licensee indicated that this would be the first request to credit the abeyance seal. The NRC staff stated to the licensee that the Advisory Committee for Reactor Safeguards (ACRS) has expressed interest in RCP seal reviews and that if the licensee submitted the proposed amendment, it may well be subject to ACRS review.

Members of the public were not in attendance. No comments were provided to the NRC staff.

Please direct any inquiries to me at 301-415-3733, or Robert.Kuntz@nrc.gov.

/RA/

Robert F. Kuntz, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-282 and 50-306

Enclosure:

List of Attendees Cc: Listserv

Enclosure LIST OF ATTENDEES JULY 22, 2019 TELECONFERENCE WITH NORTHERN STATES POWER COMPANY POTENTIAL LICENSE AMENDMENT REQUEST TO ADOPT PROBABILISTIC RISK ASSESSMENT MODEL FOR THE ABEYANCE SEAL PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 U. S. Nuclear Regulatory Commission Robert Kuntz Ching Ng Mihaela Biro Stephen Dinsmore Michael Markley Ed Miller Jay Robinson Todd Hilsmeier Northern States Power Company (NSPM)

Sara Scott Jeff Kivi Jayne Ritter Mark Brossart Adam Reiter NSPM Contractors David Zagres - Flowserve Ray Dremel - Enercon

Meeting Summary ML19210D543 Handouts ML19210D451 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DORL/LPL3/BC(A) NRR/DORL/LPL3/PM NAME RKuntz SRohrer LRegner RKuntz DATE 7/30/19 7/30/19 8/20/19 8/20/19