ML071380510

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Summary of Meeting with Representatives of Wolf Creek Nuclear Operating Corporation for Wolf Creek Generating Station on License Application Request to Update Main Steam and Feedwater Isolation System
ML071380510
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 06/04/2007
From: Donohew J
NRC/NRR/ADRO/DORL/LPLIV
To:
Donohew J N, NRR/DORL/LP4, 415-1307
Shared Package
ML071420095 List:
References
TAC MD4839
Download: ML071380510 (8)


Text

June 4, 2007 LICENSEE: Wolf Creek Nuclear Operating Corporation (WCNOC, the licensee)

FACILITIES: Wolf Creek Generating Station (WCGS)

SUBJECT:

SUMMARY

OF MAY 17, 2007, MEETING WITH REPRESENTATIVES OF WOLF CREEK NUCLEAR OPERATING CORPORATION FOR WOLF CREEK GENERATING STATION ON LICENSE APPLICATION REQUEST TO UPDATE MAIN STEAM AND FEEDWATER ISOLATION SYSTEM (TAC NO. MD4839)

A meeting was held on Thursday, May 17, 2007, between the Nuclear Regulatory Commission (NRC) staff and the licensee for Wolf Creek Generating Station (WCGS). The meeting was held at the request of the licensee to allow the licensee to explain why it believes that there is sufficient information provided in its submittals for the NRC staff to start its review of the licensees application to upgrade the main steam and feedwater isolation system (MSFIS) controls at WCGS. The proposed MSFIS upgrade was submitted in the license application request (LAR) dated March 14, 2007, as supplemented by letter dated April 18, 2007 (Agencywide Documents Access and Management System (ADAMS) Accession Nos.

ML070800193 and ML071160332, respectively). The notice for the meeting was issued on May 3, 2007.

The licensee is intending to replace the existing (1) hydraulically-operated actuators for the main steam isolation valves (MSIVs) and main feedwater isolation valves (MFIVs), (2) MSIV and MFIV bodies, and (3) MSFIS controls in the refueling outage scheduled for the spring of 2008. As explained in its application, the licensee is using the following organizations within the project for the MSFIS upgrade: CS Innovations, Nutherm International, and Baseline Engineering, P.C. The design, fabrication, and testing of the MSFIS controls is to be performed by CS Innovations, a commercial-grade vendor. The Appendix B supplier of the MSFIS controls is Nutherm International. The validation and verification consultant is Baseline Engineering, P.C.

The purpose of the meeting was to determine where the licensee was in the development life cycle of the MSFIS upgrade project, and what information needed by the staff to do its review was available and had been submitted, or the time frame in which the information will be submitted. The meeting was to address if the NRC staff had sufficient information to start its review of the licensees application. is the list of attendees. Enclosure 2 is the material handed out by the NRC staff.

There was no handout from the licensee. The agenda for the meeting was the following:

  • Introductions
  • Brief Statements by NRC Staff and Licensee
  • Timeline to Where the NRC Staff and Licensee Are Now (NRC staff)
  • Where is Licensee in Development Life Cycle of MSFIS Project (Licensee)
  • Information Needed by NRC Staff (NRC staff)
  • Discussion on Information Needed by NRC Staff The NRC staff and the licensee provided opening statements. The NRC staff stated that it knew this project was important to the licensee and would improve the safe operation of the plant; however, the NRC staff could not accept a review until it understands that sufficient information had been provided to start the review and a firm schedule existed for when the needed information not yet available would be provided. The NRC staff had interacted with the licensees staff since the application was submitted March 14, 2007, but there had not been a resolution of whether the license had provided sufficient information for the NRC staff to begin its review. This meeting was to expedite this process. The licensee stated that the project was important as part of the licensees continuing efforts to improve safety at the plant and the project would improve the reliability of the MSIVs and MFIVs, and the MSFIS controls for these valves.

The NRC staff began with a summary of the interactions between the NRC staff and licensee staff since March 14, 2007, which culminated in the meeting. This summary is the second page in Enclosure 2.

The licensee addressed where it was in the development life cycle of this project. The development life cycle is shown on the last page of Enclosure 2 and is slide number 16 in the licensees handout at the June 28, 2006, pre-application meeting on this project. (See the June 28, 2006, meeting summary issued July 12, 2006, ADAMS Accession No. ML061810456.)

The licensee stated that the MSFIS Project had completed the "Implement Hardware phase for the printed circuit boards and the rack that would hold the boards. Therefore, the licensee stated that overall the project was at the back-end of the "Implement Hardware phase and had not yet progressed to the "System Test" phase.

The NRC staff presented its list of the information it needed for its review of the proposed upgrade to the MSFIS controls. This list described the information needed on the work being done by the licensee, CS Innovations, Nutherm International, and Baseline Engineering, P.C.,

and, therefore, the list contained subparts that addressed the work being done by the licensee, CS Innovations, Nutherm International, and Baseline Engineering, P.C. This list is in Enclosure

2. The list was also contained within the NRC staffs e-mail to the licensee on May 16, 2007, that provided the list to the licensee prior to the meeting.

The NRC staff explained that the list of information was necessary for the staff to determine if the specification, design, development, test, production, verification and validation, and commercial-grade dedication processes were of sufficient high quality to result in a product useable in a safety-related application at a nuclear power plant. It was understood that each of the listed documents may not be an independent document, and that several of these documents may be combined, or that the information may be contained in several documents.

If this was the case, it was requested that the licensee provide a reference document showing where the various information may be found. It was also understood that some information, particularly that concerning the later stages of the life cycle process, may not yet be completed and reviewed. In those cases, a schedule for submission of these documents should be

provided. It was expected, however, that planning documentation and procedures for activities already performed would be available. The NRC staff discussed the information that would be needed by the NRC staff to begin its review of the MSFIS upgrade LAR, and recognized that some of the information would not be completed until near the end of the NRC staffs review of the LAR and some may be completed after the review is completed.

This list was presented to the licensee in the meeting so that the licensee could identify which of the listed information had been submitted to NRC and when the other information could be submitted.

The NRC staff and the licensee went through each of the 22 areas of information in the list of information needed by the NRC staff. This list ended with number 23, Installation, Operations and Maintenance Documentation; however, there was no number 4. At the end of its presentation, the NRC staff stated that to start its review, it needed information for each of the following areas on the list:

  • 2, Verification & Validation (V&V) Plans and Procedures
  • 3, Configuration Management (CM) Plans
  • 5, Quality Assurance Plans and Procedures
  • 6, Management Plans
  • 7, Development Plan
  • 8, Test Plan
  • 9, Installation Plan
  • 10, Maintenance Plan
  • 11, Safety Plan
  • 12, Requirements Specification
  • 14, Design Specifications
  • 19, Diversity and Defense-in-Depth Analysis
  • 22, The Standard Used by CS Innovations During The Design Process In the discussion, the licensee stated that some of the information requested by the NRC staff was contained in documents that had not yet been completed by the licensee. The licensee stated that it would submit the planning information for the above areas within 1 month, except for the following:
  • For area 8 above, Test Plan, the licensee would provide the system test plan developed by Baseline Engineering (8.A), but only a schedule for submitting the test plans for CS Innovations (8.B) and Nutherm International (8.C) within 1 month.
  • For area 11 above, Safety Plan, the licensee would provide the safety plan for CS Innovations (11.A) and the licensees evaluation and acceptance of the CS Innovations safety plan (11.C) within 1 month. The representative from Nutherm International was not sure if the Nutherm International safety plan had been completed and evaluated by the licensee. If this plan had not been completed, the licensee would provide a schedule for when the Nutherm International safety plan and licensees evaluation of that plan would be submitted.

For the other areas of information listed above, the licensee stated that it would provide the schedule for submitting the information to NRC within 1 month.

Where the information to be submitted within 1 month is not complete for the above areas, the licensee agreed to provide the schedule for submitting the complete information. Therefore, the licensee will be addressing all the areas of information addressed in the meeting.

The NRC staff and the licensee completed their discussion of the information needed by the NRC staff, and the meeting was closed.

A member of the public was in attendance. A Public Meeting Feedback form was distributed, but has not yet been received. Any comments received will be forwarded to the NRR Senior Communications Analyst who will forward them to the Office of the Executive Director for Operations.

Please direct any inquiries to me at 301-415-1307, or jnd@nrc.gov.

/RA/

Jack Donohew, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No: 50-482

Enclosures:

1. List of Meeting Attendees
2. NRC Staffs Handout cc w/encls: See next page

Pkg ML071420095 (Mtg Notice ML071220489, Mtg Summary/Encl 1 ML071380510, Encl 2 ML0713703640)

OFFICE NRR/LPL4/PM NRR/LPL4/LA ECIB/BC NRR/LPL4/BC NAME JDonohew:sp JBurkhardt AHowe THiltz DATE 6/4/07 5/23/07 5/31/07 6/4/07 Wolf Creek Generating Station cc:

Jay Silberg, Esq. Chief, Radiation and Asbestos Control Pillsbury Winthrop Shaw Pittman LLP Section 2300 N Street, NW Kansas Department of Health Washington, D.C. 20037 and Environment Bureau of Air and Radiation Regional Administrator, Region IV 1000 SW Jackson, Suite 310 U.S. Nuclear Regulatory Commission Topeka, KS 66612-1366 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Vice President Operations/Plant Manager Wolf Creek Nuclear Operating Corporation Senior Resident Inspector P.O. Box 411 U.S. Nuclear Regulatory Commission Burlington, KS 66839 P.O. Box 311 Burlington, KS 66839 Supervisor Licensing Wolf Creek Nuclear Operating Corporation Chief Engineer, Utilities Division P.O. Box 411 Kansas Corporation Commission Burlington, KS 66839 1500 SW Arrowhead Road Topeka, KS 66604-4027 U.S. Nuclear Regulatory Commission Resident Inspectors Office/Callaway Plant Office of the Governor 8201 NRC Road State of Kansas Steedman, MO 65077-1032 Topeka, KS 66612 Attorney General 120 S.W. 10th Avenue, 2nd Floor Topeka, KS 66612-1597 County Clerk Coffey County Courthouse 110 South 6th Street Burlington, KS 66839 February 2006

LIST OF ATTENDEES AT MEETING OF MAY 17, 2007 WITH WOLF CREEK NUCLEAR OPERATING CORPORATION NAME AFFILIATION J. Donohew NRC/NRR/LPLIV J. Lubinski NRC/NRR/DORL T. Hiltz NRC/NRR/DORL P. Hiland NRC/NRR/DE M. Galloway NRC/NRR/DE A. Howe NRC/NRR/EICB P. Loeser NRC/NRR/EICB S. Bailey NRC/NRR/DORL W. Kemper NRC/RES/IEEB E. Coffman NRC/NRO/DE T. Garrett WCNOC S. Wideman WCNOC P. Guevel WCNOC G. Clarkson WCNOC S. Sorensen CS Innovations (WCNOC contractor)

D. Martin Nutherm International (WCNOC contractor)

K. Keithline Nuclear Energy Institute Where: EICB = Instrumentation and Controls Branch LPLIV = Plant Licensing Branch IV NRC = Nuclear Regulatory Commission NRR = Office of Nuclear Reactor Regulation RES = Office of Nuclear Regulatory Research WCNOC = Wolf Creek Nuclear Operating Corporation ENCLOSURE 1

NRC STAFF'S HANDOUT FOR MAY 17, 2007, MEETING AGENCYWIDE DOCUMENTS ACCESS AND MANAGEMENT SYSTEM ACCESSION NO. ML071370364 The NRC staff's handout (20 pages) contained the following:

1. Timeline for Review of Licensees Request for MSFIS* Upgrade
2. Licensees E-mail Dated April 6, 2007 (Attachment 1)
3. NRC Staffs E-mails Dated May 1 and 2, 2007 (Attachment 2)
4. NRC Staffs E-mail Dated May 16, 2007 (Attachment 3)
5. Development Life Cycle of the MSFIS Upgrade Project (Attachment 4)

ENCLOSURE 2