ML14314A322
| ML14314A322 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Point Beach, Arkansas Nuclear, Vermont Yankee, Fort Calhoun  |
| Issue date: | 11/13/2014 |
| From: | Andrew Waugh NRC/NRR/DIRS/IPAB |
| To: | Nathan Sanfilippo NRC/NRR/DIRS/IPAB |
| Andrew Waugh (301) 415-5601 | |
| References | |
| Download: ML14314A322 (4) | |
Text
November 13, 2014 MEMORANDUM TO: Nathan Sanfilippo, Chief Performance Assessment Branch Division of Inspection and Regional Support Office of Nuclear Reactor Regulation FROM:
Andrew Waugh, Reactor Operations Engineer /RA/
Performance Assessment Branch Division of Inspection and Regional Support Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF THE REACTOR OVERSIGHT PROCESS WORKING GROUP PUBLIC MEETING HELD ON OCTOBER 22, 2014 On October 22, 2014, the U.S. Nuclear Regulatory Commission (NRC) staff hosted the Reactor Oversight Process (ROP) Working Group (WG) public meeting with the Nuclear Energy Institute (NEI) ROP Task Force and other industry representatives. Enclosure 1 contains the meeting attendance list; Enclosure 2 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14314A512) contains the Frequently Asked Questions (FAQs) Log and the FAQs discussed during the meeting. Meeting attendees discussed topics related to ROP FAQs.
Staff and industry discussed the following FAQs (see Enclosure 2):
FAQ 14-02: This FAQ was discussed. This is a site-specific FAQ developed by Fort Calhoun Station (FCS) to address the validity of Mitigating System Performance Index (MSPI) performance indicators as a result of an extended shutdown. FCS predicted future MSPI values using a Pressurized Water Reactor Owners Group What-if tool and expected plant data. Based on the results of this analysis, FCS proposes that the high pressure injection system MSPI, heat removal system MSPI, and cooling water system MSPI become valid on the 4th quarter of 2014. However, FCS proposes that the Emergency AC power and residual heat removal system components of the MSPI become valid on the 1st quarter of 2015 and 1st quarter of 2016, respectively. FCS provided additional information on their analysis of the heat removal system MSPI validity. The staff will review this information and provide a response during the next ROP WG public meeting.
FAQ 14-03: This FAQ is tentative final. This is a site-specific FAQ for Arkansas Nuclear One (ANO), Unit 2. This FAQ addresses the Unplanned Scrams with Complications performance indicator guidance on the flowchart question regarding the status of main feedwater availability after the scram.
CONTACT: Andrew Waugh, DIRS/NRR (301) 415-5601
N. Sanfilippo Specifically, ANO proposes that because of the unique design of their feedwater system, the intention of the flowchart question regarding the availability of feedwater is met and that the scram should not be considered complicated.
ANO provided additional information about the procedures to recover main feedwater with loss of condenser vacuum. The NRC staff acknowledged that main feedwater could have been recovered within 30 minutes and concluded that this event should not count under the Unplanned Scrams with Complications PI. The staffs response to this FAQ will be revised and this FAQ is expected to become final in the next ROP WG public meeting FAQ 14-05: This FAQ is final. This is a site-specific FAQ for Hatch. This FAQ addresses the validity of the Alert and Notification System PI for Hatch. The licensee proposes to report the results in accordance with NEI 99-02 and enter zeroes for trailing quarters until four quarters of data have accumulated. This FAQ will become effective in the reporting of 1Q2015 PI data.
FAQ 14-06: This FAQ was discussed. This is a site-specific FAQ for Vermont Yankee. This FAQ addresses the Unplanned Power Changes per 7,000 Critical Hours performance indicator guidance on identification and response to degrading conditions. The staff noted that this FAQ might not be resolved prior to the Vermont Yankees expected transition to decommissioning. However, the staff recognized that this FAQ provides an opportunity to explore clarifying the terms sudden degradation and rapid response in NEI 99-02, Regulatory Assessment Performance Indicator Guidance. The staff will review this FAQ and the need for revising NEI 99-02 and will provide a response during the next ROP WG public meeting.
FAQ 14-07: This FAQ was introduced. This is a site-specific FAQ for Point Beach Nuclear Plant (PBNP). This FAQ discusses the transition of siren responsibility from Kewaunee to PBNP for those sirens in the area of overlap of Emergency Planning Zones (EPZ) between both sites. This FAQ proposes a revision to NEI 99-02 Appendix D, Plant-Specific Design Issues, to account for the transition in responsibility for the sirens in PBNPs EPZ.
The next ROP WG public meeting is scheduled to be held on November 19, 2014.
Enclosures:
- 1. Attendance List - October 22, 2014
N. Sanfilippo Specifically, ANO proposes that because of the unique design of their feedwater system, the intention of the flowchart question regarding the availability of feedwater is met and that the scram should not be considered complicated.
ANO provided additional information about the procedures to recover main feedwater with loss of condenser vacuum. The NRC staff acknowledged that main feedwater could have been recovered within 30 minutes and concluded that this event should not count under the Unplanned Scrams with Complications PI. The staffs response to this FAQ will be revised and this FAQ is expected to become final in the next ROP WG public meeting FAQ 14-05: This FAQ is final. This is a site-specific FAQ for Hatch. This FAQ addresses the validity of the Alert and Notification System PI for Hatch. The licensee proposes to report the results in accordance with NEI 99-02 and enter zeroes for trailing quarters until four quarters of data have accumulated. This FAQ will become effective in the reporting of 1Q2015 PI data.
FAQ 14-06: This FAQ was discussed. This is a site-specific FAQ for Vermont Yankee. This FAQ addresses the Unplanned Power Changes per 7,000 Critical Hours performance indicator guidance on identification and response to degrading conditions. The staff noted that this FAQ might not be resolved prior to the Vermont Yankees expected transition to decommissioning. However, the staff recognized that this FAQ provides an opportunity to explore clarifying the terms sudden degradation and rapid response in NEI 99-02, Regulatory Assessment Performance Indicator Guidance. The staff will review this FAQ and the need for revising NEI 99-02 and will provide a response during the next ROP WG public meeting.
FAQ 14-07: This FAQ was introduced. This is a site-specific FAQ for Point Beach Nuclear Plant (PBNP). This FAQ discusses the transition of siren responsibility from Kewaunee to PBNP for those sirens in the area of overlap of Emergency Planning Zones (EPZ) between both sites. This FAQ proposes a revision to NEI 99-02 Appendix D, Plant-Specific Design Issues, to account for the transition in responsibility for the sirens in PBNPs EPZ.
The next ROP WG public meeting is scheduled to be held on November 19, 2014.
Enclosures:
Attendance List - October 22, 2014 ROP Task Force FAQ Log - October 22, 2014 DISTRIBUTION:
RidsNrrDirsIpab RidsNrrOd NrrDistributionIpab NrrDistributionIrib RidsOgcMailCenter RidsOPAMail RidsAcrs AcnwMailCenter RidsRgnIMailCenter RidsRgnIIMailCenter RidsRgnIIIMailCenter RidsRgnIVMailCenter SMorris AHowe NSanfilippo CRegan HChernoff SSloan SWeerakkody SWong HNieh MScott JTrapp BWelling JMunday MLesser TReis MMiller ABoland KObrien GShear MShuaibi TPruett MHay AVegel JClark RPowell SRose JLara GMiller DPassehl RFranovich ESchrader RKahler ADAMS ACCESSION NO: ML14314A322 ADAMS Package No. ML14314A587 OFFICE NRR/DIRS/IPAB NRR/DIRS/IPAB BC:NRR/DIRS/IPAB NAME AWaugh LCruz NSanfilippo DATE 11/7/14 11/7/14 11/13/14 OFFICIAL RECORD COPY
REACTOR OVERSIGHT PROCESS PUBLIC MEETING ATTENDANCE LIST October 22, 2014 Nathan Sanfilippo NRC Andrew Waugh NRC Luis Cruz NRC Steve Vaughn NRC Chase Franklin NRC Mary Anderson NRC Eric Schrader NRC Jim Slider NEI Larry Parker STARS Alliance Robin Ritzman FENOC Adrienne Driver Duke Energy Bruce Mrowca ISC Tony Zimmerman Duke Ken Heffner Certrec Suzanne Leblang Entergy Steve Catron NextEra Energy Lenny Sueper Xcel Energy Elijah DeVaughn Southern Nuclear Carlos Cisco Winston Roy Linthicum PWROG/Exelon Ron Gaston Exelon Kevin Boston OPPD Shirelle Allen Duke Gary Miller Dominion Peggy Rescheske TVA Justin Wearne PSEG Jana Bergman Scientech Steve Huntzater Colley Chapel James Coyle Justin Hiller Enrique Melendez Asensio