ML101680383

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Summary of Public Meeting with Progress Energy to Discuss Their Proposed Digital Modifications in Support of Fast Cooldown System for Extended Power Uprate
ML101680383
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 06/25/2010
From: Siva Lingam
Plant Licensing Branch II
To:
Lingam, S NRR/DORL 415-1564
References
TAC ME3949
Download: ML101680383 (6)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 25, 2010 LICENSEE: Progress Energy, representing Florida Power Corporation FACILITY: Crystal River Nuclear Generating Plant, Unit NO.3

SUBJECT:

SUMMARY

OF JUNE 7, 2010, PUBLIC MEETING WITH PROGRESS ENERGY ON THEIR PROPOSED DIGITAL MODIFICATIONS IN SUPPORT OF FAST COOLDOWN SYSTEM FOR EXTENDED POWER UPRATE (TAC NO. ME3949)

On June 7,2010, a Category 1 public meeting was held among the Nuclear Regulatory Commission (NRC) staff and representatives of Progress Energy, representing Florida Power Corporation (the licensee), and the licensee's contractor, INVENSYS. The purpose of the meeting was to discuss the licensee's plans for extended power uprate and related digital modifications in support of Fast Cooldown System (FCS) at Crystal River, Unit NO.3 Nuclear Generating Plant. Enclosure 1 contains a list of attendees. The licensee presented slides that may be accessed from the NRC Agencywide Documents Access and Management System, Accession No. ML101680556.

NRC staff expressed the following concerns in short:

  • Human factor concerns regarding manual actuation of FCS by operator within 10 minutes
  • Need for addition of battery surveillance requirements
  • Need to address physical and software security concerns
  • Schedule concerns associated with submittals in phases and submittal to Advisory Committee on Reactor Safeguards for approval contains the meeting discussion, which elaborates the above concerns and/or items of discussion.

NRC staff suggested to the licensee to request for a follow-up meeting to further discuss digital inadequate core cooling instrumentation, and a conference call with NRC to discuss security issues.

-2 No commitments or regulatory decisions were made by the NRC staff during the meeting.

Members of the public were in attendance, however, no Public Meeting Feedback forms were received.

Please direct any inquiries to me at 301-415-1564, or by email to siva.lingam@nrc.gov.

~-"",- \J' ~.~

Siva P. Lingam, Project Manager Plant Licensing Branch 2-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosures:

1. List of Attendees
2. Meeting Discussion cc w/encl: Distribution via Listserv

List of Attendees U. S. Nuclear Regulatory Commission (NRC)

Public Meeting with Progress Energy.

Regarding Crystal River Unit 3, Digital Modification in Support of Fast Cooling System for Extended Power Uprate Conditions June 7. 2010 NRC William Kemper Steve Wyman Angela Wu Eva Brown Gursharan Singh Ann Ramey-Smith Rich Stattel Tom Alexion Barry Marcus Siva P. Lingam Progress Energy Robert Muzzi Ted E. Williams Dan Westcott Jay Pritchett Ken Wilson Larry Sexton David Porter INVENSYS Brian Haynes Lewis Wetzel NEI Gordon Clefton AEP (By Telephone)

D. Burgoyne Enclosure 1

Meeting Discussion U. S. Nuclear Regulatory Commission (NRC)

Public Meeting with Progress Energy, Regarding Crystal River Unit 3, Digital Modification in Support of Fast Cooling System for Extended Power Uprate Conditions June 7, 2010 Progress Energy, representing Florida Power Corporation (the licensee) addressed the potential issue of inadequate core cooling that will result from the implementation of extended power uprate (EPU) at Crystal River, Unit 3 Nuclear Generating Plant. The licensee plans to implement fast cooldown system (FCS) to limit loss of reactor coolant system inventory for small break loss-of-coolant accident conditions. Major points of discussion of the meeting are noted below.

The licensee stated that operator action to depressurize the primary system was planned at 10 minutes after identification of inadequate subcooling margin and inadequate high pressure injection flow. NRC staff stated that the proposed 10 minute operator action had to be fully justified along with human factors review considerations. NRC staff further suggested that the licensee should consider automatic action in lieu of operator action to ease the review complexity. The manual operator action could be credited as a back-up action in case of failure of automatic system actuation. The licensee agreed to consider the NRC staff suggestion.

The licensee plans to use Triconex version 9.5.3 platform for some post-accident monitoring indications. Triconex platform version 9.5.3 has already been reviewed and accepted for use by the NRC.

The licensee was further advised to identify and include all technical specification (TS) changes, including any TS changes resulting from addition of new batteries required to support the proposed FCS/EPU.

The licensee was advised to include system build documents (part of software development process documents) as part of phase 2 documents per draft Interim Staff Guidance 06 (ISG-06) and not include them as audit documents only.

The licensee was also advised to include final factory acceptance test (FAT) reports and summary of test reports as part of documentation for compliance with Institute of Electrical and Electronics Engineers (IEEE) Standard 603-1991 as a phase 2 document per draft ISG-06 and not as audit documents as proposed. In addition Summary of FAT reports, and verification and validation reports in support of IEEE 7-4.3.2 as endorsed by Regulatory Guide (RG) 1.152 should also be phase 2 documents.

Enclosure 2

-2 The licensee was advised that regulatory positions 2.6 through 2.9 of RG 1.152 for software security related issues will now fall under the purview of the new regulation described in Title 10 of the Code of Federal Regulations, Section 73.54. The licensee can use the guidance of draft Regulatory Guide 1249, which was recently posted for public comments. For additional guidance, the licensee can consider the NRC's safety evaluation for the Oconee Reactor Protection System/Engineered Safety Features Actuation System digital upgrade.

Progress Energy noted that all documents required as part of phase 1 of ISG-06 will not be available in the original license amendment request submittal and requested that NRC to consider a phase 1a approach to facilitate the submittal review. NRC staff agreed to consider the phased approach, as long as, Progress Energy proposes an expedited schedule and adheres to it. However, the NRC staff was concerned that with the schedule and approach presented by Progress Energy, the review of the portions of EPU that are associated with ISG-06 may be extended.

The licensee was advised to update its presentation slides pertaining to draft ISG-06 and provide NRC details of schedule and supporting documents.

-2 No commitments or regulatory decisions were made by the NRC staff during the meeting.

Members of the public were in attendance, however, no Public Meeting Feedback forms were received.

Please direct any inquiries to me at 301-415-1564, or by email to siva.lingam@nrc.gov.

Siva P. Lingam, Project Manager IRAJ Plant Licensing Branch 2-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosures:

1. List of Attendees
2. Meeting Discussion cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrLACSola RidsNrrLABClayton RidsNrrPMCrystalRiver RidsNrrOd RidsRgn2MailCenter S. Lingam, NRR RidsNrrDeEicb RidsAcrsAcnw_MailCTR RidsOgcRp C. Steger, NRR N. Sanfilippo, EDO S. Wyman, NRR A. Wu, NRR E. Brown, NRR G. Singh, NRR A. Ramey-Smith, NRR R. Stattel, NRR T. Alexion, NRR B. Marcus, NRR PACKAGE ACCESSION NO.: ML101690157 MEETING

SUMMARY

ACCESSION NO.: ML101680383 SLIDES PRESENTATION ACCESSION NO.: ML101680556 OFFICE LPL2-2/PM LPL2-2/LA DE/EICB/BC LPL2-2/BC NAME Sl.lncarn CSoia /BClavton for WKemper DBroaddus DATE 06/24/10 06/24/10 06/25/10 06/25/10 OFFICIAL RECORD COpy