IR 05000369/1993026
| ML20059C057 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/15/1993 |
| From: | Casto C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20059B987 | List: |
| References | |
| 50-369-93-26, 50-370-93-26, NUDOCS 9401040347 | |
| Download: ML20059C057 (7) | |
Text
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REGION II
E 101 MARIETTA STREET, N.W., SUITE 2900
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Report Nos.:
50-369/93-26 and 50-370/93-26 Licensee: Duke Power Company
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422 South Church Street
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Charlotte, NC 28242 Docket Hos.:
50-369 and 50-370 License Nos.: NPF-9 and NPF-17
Facility Name:
McGuire 1 and 2
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Inspection Conducted:
November 15 - 19, 1993
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7 ate Sig'ned
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Inspector:
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M. D. Hunt Approved by:
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C. Casto, Chief Date Signed
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Test Programs Section Engineering Branch Division of Reactor Safety
SUMMARY
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Scope:
This routine, announced inspection was conducted in the areas of engineering
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and technical' support of plant modifications, design changes and plant operations.
Results:
In the areas examined the inspector determined that the licensee has a technical support staff of knowledgeable and experienced engineers.
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The licensee implements an effective modifications program that allows
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corrective actions to be taken in a timely manner.
In the areas inspected, violations or deviations were not identified.
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9401040347 931216 PDR ADOCK 05000369 G
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REPORT DETAILS I
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Persons Contacted
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P. Anderson, Component Engineer
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K. Caldwell, Component Engineer
R. Demuro, Project Manager i
J. Dial Jr., Unit Operator i
J. Freeze, Production Specialist, (Components)
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- G. Gilbert, Manager Safety Assurance
- R. Hall, McGuire Engineering Manager (Acting)
M. Hatley, Engineering Supervisor, (Components)
i G. Holbrooks, Component Engineer
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- L. Kunka, Component Engineer i
B. McDowell, Modification Coordinator
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- T. McHeekin, Vice President, McGuire Nuclear Station
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C. Neuman, Unit Operator
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J. Owen, Technical Specialist
- M. Pacetti, Engineering Supervisor, (Mechanical / Nuclear Engineering)
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- T. Pedersen, Manager, Safety Review Group
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- R. Roberts, Systems Engineer
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J. Snyder, Shift Manager
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- K. Thomas, Electrical Engineering Manager
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- B. Travis, Component Engineering Manager
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- R. Wagner, Senior Engineer Licensee Employees
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i Other licensee employees contacted during this inspection included i
engineers, operators, technicians, and administrative personnel.
NRC Resident Inspector l
G. Maxwell, Senior Resident Inspector
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- Attended exit interview 2.
Design Changes and Modifications (37700)
l The purpose of this inspection was to verify that engineering is
functioning in a manner that provides adequate support for safe, reliable, and efficient plant operations. This licensee has component
engineers (CE) and systems engineers (SE) that are involved in the day to day plant operations as needed. Also located at the plant site is
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the design engineering group. These engineering groups are under one
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manager located at the site.
The CE has the programmatic lead in the technical support program for generic components and programs. In addition to components and programs, CE also has responsibility for structures, inspection activities, and testing. The CE Electrical Section is divided into two sections,'a
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power systems unit and an Instrumentation (I&C) unit. The CE is also responsible for initiating minor modifications, temporary modifications, test procedures, maintenance procedures, and issuing yearly technical reports (self assessment) for each of their activities. This unit has approximately 68 persons including supervisors.
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The system engineering section has approximately 35 persons including supervisors. The function of the SE is to manage activities related to an assigned system to maximize the performance,. availability, and reliability of the system. This involves maintaining an overview of all activities related to the system. Also, as the technical expert for a i
system, the SE provides technical input to support major modifications, l
initiates minor modifications, evaluates test data for adequate system performance, and participates in problem resolutions to ensure a system meets required design function.
The design engineering section is located at the site.
This section is
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responsible for all design changes and major modifications. The design, and oversight of the field work required by the modification is performed by the design engineering section in co-ordination with the responsible SE or CE sections.
This licensee is currently changing the modification process to provide for improved planning and tracking of modifications.
In the past the approval process for modifications had allowed projects to come into the schedule without addressing the amount of resources that were available or the time frame for performance of the modification. This resulted in a back log of modifications. There is currently a re-prioritization of the back log list to reduce it to a number.that can be supported with the resources available. This effort is scheduled for completion-by the end of 1993. The inspector reviewed the program which included two activities, Technical Evaluation and Business & Benefit Evaluation.
Modifications for McGuire are controlled by the MNS Modification Manual which describes the processes used to identify and perform modifications to systems, structures, or components. This includes the assignment of personal responsibilities and the methods for processing minor, temporary, and permanent plant modifications. The manual contains guidance for the development of post-modification testing requirements
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and procedures.
MNS Modification Manual is a sub-tier document to Duke Power Company's Nuclear System Directive 301, Nuclear Station Modifications. This
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manual defines the evaluation process for Station Problem Reports (SPR),
Minor Modifications (MM), and Nuclear Station Modifications (NSM).
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The inspector selected 7 modifications which were perf.ormed during the
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last refueling outage for each unit to review in part the items listed below to:
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determine the adequacy of the 10 CFR 50.59 evaluations performed (2)
verify that the DCPs were reviewed and approved in accordance with TS and applicable administrative controls (3)
verify the subject modifications were installed (for those that could be physically inspected) in accordance with the DCP package (4)
verify that applicable plant operating and design documents (drawings, plant procedures, FSAR, TS, etc.) were ravised to reflect subject modifications (5)
verify that the modifications were reviewed and incorporated into the operations training program as applicable (6)
verify that post modification test requirements were specified and that adequate testing wa., performed
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The following modifications were reviewed to determine that various items denoted above were performed.
NSM #
DESCRIPTION 12302 & 12305 Replace and Reorient S/G 1A Main Steam Safety Valves 22096 Replace Loose Parts Monitor System 12410 (Urgent Mod)
CF Control Valve Solenoid Valve Change 12333 Modify Pressurizer Safety Valves 21414 Busline Breaker Control Circuitry in Switchyard (This Mod is important to Safety)
22401 Main Steam Drain Valve Modification which changed from FAIL OPEN to FAIL CLOSED The Problem Investigation Program (PIP) is the method through which most
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statien problems are reported.
The identified problems are screened by the PIP coordinator.
The problems are then reviewed by the Safety Review Group who validate the significance and decide if an event is reportable and if an operability determination is required. Through this review process, resolution of a problem is assigned to a specific
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group and person, frequently the SE. The inspector reviewed seven open i
PIPS that had been open for at least 2 months in order to ascertain engineering involvement in identifying and resolving station praMems.
PIP #
DESCRIPTION 2-M89-0263 Mud / Sludge Build Up Was Discovered in the Piping Between IRFil and IRF12
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l-M93-0226 No Power Available to B NV Pump for 10 Hours 1-M93-0232 Tubing to Valve is Not Installed IAW Drawing MC-1499-RN.49-
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0-M93-0004 Tech. Spec. Does Not Reflect New Temperature
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Design Basis Information
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0-M91-0146 Numerous Examples Exist In Which Labeling / Instrumentation On The Auxiliary
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Shutdown Panels Is Not In Accordance With The
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Associated Design Drawings 1-M89-Oll3 Shipping Bars on Expansion Joints are Supposed to be Removed When Finally Installed; However, Some were Discovered Still Welded in Place.
Various Other Dimensional Discrepancies were Discovered.
2-M88-0323 The Hot Leg RTD's Installed Exhibit a 6 Degree Variation Between the 2 Highest and Lowest Reading RTDs. Also, the Lowest Reading RTD Unde goes Periodic Oscillations.
The PIPS reviewed by the inspector had each been evaluated for reportability as required under 10 CFR 50.59.
Discussions with the.
responsible engineer or supervisor indicated that in each case the
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reason for the PIP remaining open was prudent and well supported by sound engineering judgement and documents.
The inspector selected five Temporary Modifications that could be walked down during plant operations. The inspector verified that the temporary modifications were logged in the log book set aside for them in the control room. Discussions with the operation personnel on duty indicated that they were knowledgeable of the modifications but that there was no formal method of review of the modifications log book required.
This fact was discussed with licensee representatives by the inspector to point out that temporary modifications could occur while a certain shift was in the training phase rotation and could be missed when that crew again comes on duty. The licensee acknowledged that this could be a problem and agreed to review the item for enhancement.
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5 The following Temporary Modifications were walked down to the extent possible:
TEMPORARY DESCRIPTION
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MODIFICATION #
6142 1A Diesel Motor Fuel Oil Drip Tank Pump Motor 6289 & 6290 Jumpers in EDG Control Cabinet IB to Clear Alarms 62B1 & 6282 DG 2A Control Cabinet, Jumpers Between Terminals to Clear Alarms After review of the NSMs, Temporary Modifications, and PIPS listed
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above, the inspector concluded that the licensee has an effective and
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well supported engineering program for the technical support of operations and the design and modification of McGuirc Nuclear Station.
Within this area no violations or deviations were identified.
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Exit Interview
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The inspection scope and results were summarized on November 19, 1993, with those persons indicated in paragraph 1.
The inspector described the areas inspected and discussed in detail the inspection results listed below. Although reviewed during this inspection, proprietary
information is not contained in this report. Dissenting ~ comments were not received from the licensee.
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Component Engineer CFR
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Code of Federal Regulations DCP
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Design Change Package i
DS Design Study
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I&C Instrumentation and Controls
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Final Safety Analysis Review kV Kilovolts
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Modification MP
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Maintenance Procedure NSM Nuclear Station Modification
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NPF
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Nuclear Power Facility NRC
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Nuclear Regulatory Commission NV
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Nuclear Volume Control System NV
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Chemical and Volume Control
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-PIP Problem Investigation Process
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RC
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Fire protection RHR
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Residual Heat Removal System RN
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Nuclear Service Water SE System Engineer
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SPR
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Station Problem Report TS
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Technical Specifications
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Work Request
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