IR 05000369/1993030

Insp Repts 50-369/93-30 & 50-370/93-30 on 931213-17.No Violations Noted.Major Areas Inspected:Design Changes & Plant Mods,Engineering & Technical Support Activities & follow-up on Previously Identified Insp Findings

ML20059G321
Person / Time
Site:	McGuire, Mcguire
Issue date:	01/07/1994
From:	Casto C, Wiseman G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20059G308	List: IR 05000369/1993030 ML20059G305
References
50-369-93-30, 50-370-93-30, NUDOCS 9401240100
Download: ML20059G321 (14)

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NUCLEAR REGULATORY COMMISSION

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. S REGloN ll 101 MARIETTA STREET, N.W., SUITE 2900 L ;

ATLANTA, GEORGIA 30323 0199 s

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Report Nos.: 50-369/93-30 and 50-370/93-30

Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.: 50-369 and 50-370 License Nos.: NPF-9 and NPF-17 Facility Name: McGuire 1 and 2 Inspection Conducted: December 13 - 17, 1993 Inspector: [.

G. R. Wiseman

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/[b Date Signed ,

Accompanying Personnel:_ H. Whitener Approved by: d-, I [

C.'Ca'sto, Chief

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Date Signed Test Programs Section Engineering Branch Division of Reactor Safety SUMMARY Scope:

This routine, announced inspection was conducted in the areas of design l changes and plant modifications (IP 37700), engineering and technical support activities, and follow-up on previously identified inspection findings. This i inspection supplemented a NRC inspection conducted in November 1993, NRC 1 Report No. 50-369, 370/93-2 Resul ts:

In the areas inspected, violations or deviations were not identifie i i

The modification program contained adequate requirements to implement design I changes in a satisfactory manner. The licensee had identified a programmatic weakness in management control of the design change process, evaluated the cause and initiated actions to resolve the proble Programmatic changes ~have recently been. implemented which appear adequate to establish more extensive management oversight and control of the design change approval function. The revised program provides for balancing implementation schedules and available resources against the plant needs. However, due to the recent initiation of program changes the inspectors could not evaluate the performance l

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effectiveness of these changes at this time. The NRC will re-evaluate the effectiveness of management oversight and backlog control at a future inspectio The licensee has an effective program for minor modifications. The use of minor modifications for controlling and tracking Motor Operated Valve (MOV)

torque and limit switch setpoint changes was considered a strengt Engineering's implementation of the prioritization and tracking process for open and backlog engineering drawings / documents was adequate. With contractor assistance, the overall trend of backlog engineering documents has shown a reduction during 1993. The licensee has recently initiated an "As-Built" Quality improvement Project (QIP) to address engineering drawing / document backlog issue Problems in the timeliness of implementation of resolutions for the old Station Problem Reports (SPRs) now included in the Problem Investigation '

Process (PIP) have been identified by the licensee as a backlog and are being addressed through the Modification Reduction Team backlog disposition actions and an enhanced review / screening process for newly identified issue f Design and system engineers are actively engaged in support of plant day-to-day operations and maintenance. The component engineering. Predictive Maintenance (PM) program has been effective in early detection and resolution of equipment problems which resulted in cost savings and more reliable plant operation. The engineering groups were actively involved in the identification and resolution of problems in support of reliable plant operations. Management has been supportive of engineering's role in the >

identification of plant system configuration problems as evidenced in the '

number of Plant Problem Investigation Reports initiated by the onsite engineering organizations. Engineering was involved in the initiation of about 23 percent of the PIPS in 1993. The engineering technical staff was knowledgeable, competent, and exhibited an attitude of providing a good effort in performing their engineering duties. The quality of communications betweer engineering and the plant staff was effectiv The Quality Verification Department had been actively involved in assessing engineering activitie These assessments had been successful in identifying engineering program areas that need improvement. Corrective actions in response to the assessments are generally being implemente '

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h REPORT DETAILS Persons Contacted

• J. Boyle, Superintendent Work Control (W/C)

W. Cross, Regulatory Compliance T. Curtis, Manager, System Engineering J. Effinger, Lead Auditor, Quality Assurance

• R. Hall, McGuire Engineering Manager (Acting)

M. Hatley, Engineering Supervisor, (Components)

P. Herran, Manager, Engineering

• Matthews,-Engineering Supervisor, (Electrical)

• T. McMeekin, Vice President, McGuire Nuclear Station J. Mead, System Engineer

• M. Pacetti, Engineering Supervisor, (Mechanical / Nuclear Engineering)

• R. Sharpe, Manager, Regulatory Compliance

• K. Thomas, Electrical Engineering Manager R. Wagner, Problem Investigation Process (PIP) Coordinator Licensee Employees Other licensee employees contacted during this inspection included engineers, operators, technicians, and administrative personne NRC Resident Inspector G. Maxwell, Senior Resident Inspector

• P. Hopkins, Resident Inspector Catawba

• Attended exit interview

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. Design Changes.and Modifications (37700)

The licensee identified the build up of large engineering backlogs in the areas of Nuclear Station Modifications (NSMs), Station Problem -

Reports (SPRs), Minor Modifications (mms), and Problem Identification Process Reports (PIPS) as a condition adverse to achieving excellence in engineering performance. A study was initiated to determine the root cause and propose an approach to resolution of the proble The :

inspectors examined certain aspects of the licensee's activities in this area to evaluate management oversight and control of.the design change process and problem resolutio Modification Backlog Control ,

The 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. The inspectors reviewed the program which

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included the Modification Reduction Team backlog disposition activities and implementat of Minor Modifications (MM). In this review the inspectors int ewed station engineering personnel and management, and reviewed station documentation including:

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Modification Planning Process, Modification Planning Quality Improvement Project Report, Revision 1, August 3, 199 NMS Modification Manual, as revised for the new approval proces Proposed backlog implementation schedul l l

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Proposed backlog resource allocatio The basic problem was determined to be a lack of pre-planning and controlled screening of the issues submitted for plant modifications. The failure to adequately evaluate the merits of proposed changes up front resulted in large numbers of approved modifications and~SPRs issued without time and resources for implementation (i.e, backlog). A three phase plan was devised and implemented by the licensee to resolve the backlog issue. In phase 1, a moratorium on plant modifications (except for emergency 1 modifications) was established to limit the continued build up of I backlogs. In phase 2, the modification review and approval process was revised and incorporated into the site modification manua The revised process was implemented in August 1993. The approval process now considers up-front the technical evaluation, j cost / benefit analysis, time involved in preparation for implementation, and resource availability. Phase 3 of the licensea's actions is ongoing and involves the review and re-evaluation of all existing (backlogged) NSMs, mms, and SPRs. A Modification Reduction Team was formed to re-evaluate and i disposition all open modifications and proposed modifications.' Re-prioritization under the new approval process involved. cost benefit analysis, allocation of resources, assignment of milestone schedules for both design and implementation activities, and evaluation of the modification effect in five broad areas which include employee satisfaction, environmental (waste control),

generation output, operations and maintenance readiness,-nuclear safety and regulatory, and personnel safety. Of the 633 items -

reviewed, the team recommended 265 items be implemented over the next 3 years. To this end the licensee has' allocated 80 percent of the modification budget for 1994 to backlog items, 60 percsnt for 1995 and 40 percent for 1996. Of the~265 items recommended to be impl'mented, 48 are NSMs, 72 are mms and 145 are PIP corrective actions and SPRs. Accordingly, the remaining 368 items are to be completed in 1993, canceled, or re-classified as editorial revisions or Engineering Work Orders (EWO). Management review'an approval of the recommended dispositions was not final at the time of the inspectio ._

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The inspectors reviewed proposed schedule lists of NSMs, mms, and ,

SPRs and determined that resource values have been defined and )

implementation scheduled over 1994, 1995, and 1996 in accordance with the five strategic areas discussed above.

One disposition of back log items was cancellatio Since final management approval had not been received for the recommended cancellations, the inspectors selected two other modifications ,

which had been previously cancelled to determine if adequate basis !

or justification was documente I The NSMs reviewed were as follows:

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NSM MG-22297: This package related to upgrading the air- l assist-to-close feature of the MSIVs from non-safety to safety grade. The licensee has documented tes'. results'on valve stroke time without air-assist and the etfect of I packing drag. On this data it was concluded to either ;j upgrade the closing feature by NSM MG-22297 or to delete the l closing feature based on justification of a longer closing !

time. The NRC approved the licensee's TS change request to 1 extend the stroke time limit from 5 seconds to 8 second The modification was then cancelle l

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NSM MG-12386: This package was developed to replace obsolete Rochester Instrument (RIS) under voltage and under frequency relays with Asea Brown Boveri (ABB) under voltage and under frequency relays in the Reactor Coolant Pump Power Monitoring System. The RIS relays are no longer.available 1 from the vendo The Unit I design package has been completed and drawing changes developed. The change involved moving the relays to new cabinets and installing converters. However, the licensee determined that the ABB relays could be. installed in the existing cabinets. The new parts have been procured, test qualification reports were available, and the design modification was on file. The licensee has deferred the .

modification to be implemented later on an as-needed basi '

From review of these NSMs the inspectors concluded that the licensee adequately documented and justified the basis for cancellation and deferment. Since the- proposed cancellation of backlog items was not complete, the inspectors indicated that this matter will be reviewed at a future inspection.

The Problem Identification Process (PIP) is the method through which most station problems are reported, documented, and tracked to closure. The problem is screened by the Safety Review Group (SRG) consisting of operations, engineering, quality assurance and human performance engineering personnel. In screening the

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l problems the SRG verifies completeness of infnrmation, assigns the-event code, determines the significance and PIP category, i determines if an operability review is required, determines- 1 reportability, and assigns the group responsible for cause determination and proposed resolutio Trend plots of PIP backlog from January through November 1993 showed an increasing backlog trend through October. In November the trend was turned with a reduction from about 740 to 660 open PIPS. Management oversight is established through daily review of PIP statu The inspectors concluded that the licensee identified a programmatic weakness in management control of the design change j process, evaluated the cause and initiated actions to resolve the l proble Programmatic changes have recently been implemented ,

which appear adequate to establish more extensive management l oversight and control of the design change approval function. The  !

revised program provides for balancing implementation schedules o and available resources against the plant needs. However, due to the recent initiation of program changes the inspectors could not evaluate the performance effectiveness of these changes at this time. The NRC will re-evaluate the effectiveness of management oversight' and backlog control at a future inspectio ;

l Minor Modifications The inspectors reviewed the licensee's Minor Modification (MM) H program to determine its adequacy for controlling and tracking  ;

minor plant changes. Nuclear Station Directive 301, Nuclear Station Modifications, Revision 1, dated May 7, 1993, Section 301.5, was reviewed to determine its requirements. This procedure defines the evaluation process for Minor Modifications (MM) and Nuclear Station Modifications (NSM). The inspectors considered the use of the minor modification for controlling and tracking Motor Operated Valve (MOV) torque and limit switch setpoints as a strength since the same level of operability and other technical reviews was procedurally required on mms as required on NSMs. The minor modification packages were examined to verify: (1) a safety evaluation was performed; (2) there was a work plan; (3) a ,

technical review was performed; (4) testing was specified; and (5)

drawings were revised. The following Minor Modifications were reviewed to determine that various items denoted above were l performed t

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MM # DESCRIPTION

MM-3213 Replace obsolete Emergency Diesel Generator ,

(EDG) 28 control air valve which had leake *

MM-3618 8-Hour Emergency Lighting System Enhancements to 1 improve illumination of Appendix R safe-shutdown components and' pathway * MM-5341 Lower High Temperature alarm setpoints' for Units 1 and 2 reactor coolant pumps upper and lower motor thrust bearings to allow time for problem -

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analysis before Technical Specification (TS)

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MM-5344 Replace obsolete duct-mounted ionization fire detector for Service Building Air Handling Unit with a new detector for Fire Zone 47 The inspectors concluded the licensee has an effective program for '

minor modifications. The use of minor modifications for controlling and tracking Motor Operated Valve (MOV) torque and ,

limit switch setpoint changes was considered a strengt )

c. Drawing Control The inspectors reviewed the licensee's program and procedures that were developed and implemented to maintain drawing control. The i program and procedures were examined to ensure that design control was maintained and drawings were updated in a timely manner to reflect the as-built plan The procedures and systems reviewed for drawing control included the following:

Modification Manual Section 11.3, "As-built Documents",

Revision 2, dated October 5, 199 *

Nuclear Mechanical, Electrical, and Civil Engineering Document Backlog Reduction Reports for November 1993, dated December 15, 199 The review indicated that in past periods, engineering follow-through in the update of as-built engineering and Vital-To-

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Operations (VTO) drawings following plant modifications had been inconsistent resulting in a drawing / document backlog. With contractor assistance, the overall trend of engineering backlog

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documents has shown a reduction during this year. In January 1993, the number of backlogged items was about 3000. As of !

November 1993 the number reached 99. In July 1993, the licensee i chartered an "As-Built" Quality Improvement Project (QlP) to ;

address the drawing backlog problems and the drawing update . i l

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process through the development of new standards of time requirements in the governing procedures. The results of this '

ongoing effort will be reviewed during future NRC inspection Within this area no violations or deviations were identified.

3. Engineering and Technical Support Activities  :

The inspectors reviewed activities performed by the various engineering '

and technical support departments to assess the effectiveness of the engineering support provided to the plant. Engineering and technical ;

support are provided by both . site engineering and technical support eng'ineering organizations. The inspectors interviewed licensee personnel, reviewed records, and observed plant activities to evaluate the engineering involvement and technical support'of day-to-day plant operation Plant documentation reviewed included portions or all of the following documents:

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PIP Backlog Trend, January - November,1993

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PIP Data Base, 1992 - 1993

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Internal Engineering Memos

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Predictive Maintenance Annual Report i

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Predictive Maintenance Case Histories 1

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SE Monthly Report, November 1993 - I

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McGuire System Teams Summary Report, September and October, 1993 .l Review of the monthly engineering reports, team summary reports, and internal engineering memos indicated engineering involvement in resolving plant problems. The inspector noted examples where system .j engineers were active in monitoring system performance,. performing analysis of system functions, performing system tests, writing and/or revising test procedures, responding to PIPS,. recommending problem resolutions, and in general overseeing and tracking the work activity on their systems. The documentation showed that a number of problems were identified while in the field performing tests or walking down the systems. A few examples characterizing the type of activities are listed below:

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SE worked with operations and work control groups in identifying and repairing six secondary side leaking . valves. This.resulted.in

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a significant reduction of input to the plant waste system. .

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SE led a team to resolve leaking containment bellows and developed ;

a revised test technique. This prevented extended plant downtime

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to replace bellow ,

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SE in cooperation with operations and maintenance groups identified and corrected a design problem which allowed air accumulation in the service water piping. Air entrained in this piping has the potential to cause air binding of the auxiliary feedwater pump SE (Reactor Engineering) observed faulty power range deviation alarms in the control room. Followup and correction of this problem eliminated an operator work aroun SE in cooperation with other groups developed an alcohol bath which resolved a problem of in-core detectors sticking in the thimble tubes. This enabled reactor engineers to obtain adequate flux map SE enhancement of'the integrated leak rate test method and procedure along with close coordination of SE, corporate engineers and operations to conduct a complicated test resulted in a savings of 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> critical path outage tim SE identification of a failed open steam drain valve during system walkdown and subsequent repair resulted in an increased generation output of about 2 M Design engineering responded to an urgent NSM requiring research and calculations to meet a window of opportunity for implementation. The modification involved the change from non-safety to safety grade water supply to the auxiliary feedwater pump Design engineering, in response to a relief valve leakage problem, performed field walkdowns and a piping analysis to determine the root cause and support maintenance on the valv The inspectors concluded that design and system engineers are actively engaged in support of plant day to day operations and maintenanc In addition to the above examples of engineering support, the inspectors found that the licensee has an active, involved Predictive Maintenance (PM) program. The 1992 PM annual report contained a number of case histories'and savings due to predictive maintenance application. Early detection of equipment problems has two major benefits. First, early detection of impending failure allows a planned, controlled approach to repair. This results in increased equipment availability and reduced-maintenance cost. Second, the circumventing of unexpected on-line equipment failure prevents potential plant transients and challenges to the plant safety systems. The types of predictive maintenance in use at McGuire include:

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Vibration Trending and Analysis

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011 Condition Trending and Analysis

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Infrared Thermography

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Motor Current Trending and Analysis

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Laser Equipment Alignments The inspectors concluded that the component engineering predictive maintenanca program has been effective in early detection and resolution of equipment problems which resulted in cost savings and more reliable plant operatio The PIP data base was reviewed to assess engineering involvement in identification and resolution of day-to-day problems. The : 4ble below shows engineering involvement in PIP program. The columns indicate quarterly results except for the September 17, 1993 date. This wasithe date the up front screening process was implemente Engineerina Involvement in PIP l

01/01/93 - 04/01/93 - 07/01/93 - 09/17/93 -

03/31/93 06/30/93 09/17/93 12/14 Total PIPS 274 346 271 379 Generated Eng. PIPS 44 70 74 101 Generated Caust Evaluation 68 104 108 155-Assigned to En Cause Completed 63 74 77 148 by En Proposed Resolution 123 131 123 162 Assigned to En Proposed Resolution 132 80 92 162 Completed by En Corrective Action 192 174 149 129 Assigned to En Corrective Action 136 80 133 197 Completed by En This data indicated that of the 1270 PIPS prepared in 1993, engineering initiated 289. Groups involved (and the nominal percent of the engineering initiated PIPS) included component engineering (70%), system engineering (20%), design engineering (6%), instrument and electrical engineering (3%), and civil engineering (1%).

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The inspectors concluded that engineering was actively engaged in identification and resolution of the day-to-day plant problem Engineering was involved in the initiation of about 23 percent of the PIPS in 1993. Management has been supportive of engineering's active- ,

role in. the identification of plant system configuration problems as '

evidenced in the number of PIPS initiated by the engineering organizations. The engineering technical staff was knowledgeable, competent, and exhibited an attitude of providing a good effort in performing their engineering duties. The quality of communications ,

between engineering and the plant staff was effectiv '

Violations or deviations were not identified in the areas inspecte l 4. Quality Assurance (QA) Assessment and Oversight The inspectors reviewed QA Program assessments, Self-Initiated Technical *

Audits (SITA), insurance audits, and consolidated performance assessments of the McGuire Nuclear Generation Department including an audit of site engineering's safety related activities conducted by the i Quality Verification Department. The assessments and audits were part-of the overall Duke Power quality assurance program at McGuire Nuclear- '

Station. The inspectors reviewed results of the following quality assurance activities that were either completed or in progress:

• Departmental Audit SITA-93-01(MC), March 1993, Self-Initiated l Technical Audit of McGuire Nuclear Service Water System.(RN).

• Nuclear Mutual Limited Property Loss Prevention Program Survey, Periodic Report, June 199 *

Departmental Audit NG-93-07(MC), August 1993, Consolidated-Performance Assessment of McGuire Nuclear Engineerin In addition to reviewing results of the above activities, the_ inspectors reviewed several response memorandums to Quality Verification Department assessment observations and recommendations. A number of Problem Investigation Reports were initiated to document' corrective actions to the audit finding Based on these reviews, the inspectors' concluded that the Quality Verification Department had been actively involved in assessing engineering activities. These assessments had been successful in identifying engineering program areas that need improvement. Corrective actions in response to the assessments were generally being implemente Violations or deviations were not identified in the areas inspecte . Licensee Actions on Previous Inspection Findir.gs (92701)

The inspectors reviewed the licensee's status of corrective actions for findings and other concerns identified during the Electrical Distribution System Functional Inspection (EDSFI) and a subsequent NRC

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follow-up inspection (NRC Report Nos.. 50-369, 370/91-09 and 92-22 i respectively). The following sections discuss the EDSFI. items reviewed l during this inspectio (0 pen) IFl 50-369,370/91-09-01, This item concerned four issues:

(1) Degraded Grid Voltage; (2) EDG Grounding; (3) Protective Coordination on 600 V MCCs; and (4) Coordination on 125V DC Vital Circuit Breakers:

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(1) Degraded Grid Voltage - This issue concerned an additional *

level of degraded grid protection by adding a degraded grid voltage alarm in the control room. During previous review of this item, the NRC inspectors noted that nuclear ,

modifications numbers MG-12392 and MG-22392 had been ..

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assigned. These modifications had not been implemented at the time of this inspection. The licensee indicated that the Modification Disposition Team has recommended to cancel -j these modifications, but the recommendation had not been approved by station management. The NRC will continue to follow the status of the resolution of this issue during future inspections. This item will remain ope ,

(2) EDG Grounding This issue involved the inadequate sizing ~of the grounding transformer and resistors. Modifications MG-12396 and MG-22396 were implemented to replace and relocate the grounding transformer and resistors.~ Both the Unit 1 and 2 modifications were completed during the last outag The inspectors reviewed the modification electrical drawings -

and performed a walk-down of the EDG rooms to. verify completion of the field change work. This issue was resolve '

(3) Protective Coordination on 600 V MCCs - The licensee has implemented modifications MG-12266 and MG-22266 to replace the 250 ampere feeder breakers with 400 ampere rated breakers to coordinate with the branch breakers. Both the

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Unit I and 2 modifications were completed during the last outage. The inspectors reviewed the modification electrical-drawings and performed a walk-down of the affected MCCs' to .,

verify completion of the field change work. This issue was :

resolve (4) Coordination on 125 V DC Vital Circuit Breakers. - This issue ; *

concerned inadequate breaker coordination. During previous review of this item, the NRC inspectors noted that a Station l Problem Report (SPR-4722) had been written as the base i document to initiate plant modifications. Nuclear station-modifications numbers MG-12411 and MG-22411 had been -!

assigned. These modifications had not been implemented.at the time of this inspection. The licensee indicated that ,

the Modification Disposition Team har. recommended that these ~

modifications be cancelled, but the recommendation had not 3

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been approved by station management. The NRC will continue to follow the status of the resolution of this issue during future inspections. This item will remain ope In summary, two issues [(2) EDG Grounding & (3) Protective Coordination on 600 V MCCs] had been resolved through successful *

implementation of plant modifications. Two issues [(1) & (4)]

remained open; therefore, IFI 50-369,'370/91-09-01 remains ope (OPEN)'IFI 50-369,370/91-09-02, Inadequate EDG Room Ventilation, -

The licensee has proposed several resolutions to address the diesel generator rooms ventilation flow and temperature rise problem that occurs during the warmer summer months. In 1993 minor modifications MGMM-3679 and MGMM-3680 were implemented to lower the standby " keep warm" temperatures maintained for the EDG jacket water and lubrication oil. The result was evaluated to have reduced the overall heat load of the EDG rooms sufficiently for normal ventilation to maintain room temperature below maximum limits. This issue remains open pending NRC review and evaluation of the trending of the room temperature rise during the summer !

periods in 1994, to determine if the modifications have been effectiv (CLOSED) IFI 50-369,370/91-09-03, Battery Room Ventilation Deficiency, The licensee's engineering evaluatian 0-M88-0321 for this issue was reviewed. The evaluation included the design aspects of the redundant direct-drive vane axial fans, loss of ventilation systems for each battery room and existing _ control room alarms for fan motor overloads and DP pressure drop. Fan operation was verified on semi-daily operator rounds. Based on the existing alarms and operational verification, the evaluation concluded that an additional flow ' alarm was not necessary. In addition, the inspector verified that the NRC _had found the existing battery room ventilation design acceptable in a 1979 McGuire Safety Evaluation Report, (NUREG-0422, SER Supplement No. 2) for the Branch Technical Position BTP 9.5-1 fire protection review addressing battery room hydrogen gas concentration contro Based on the inspectors' review of the engineering evaluation and the previous NRC review and approval of the battery rooms ventilation systems, this item is resolved. Exit Interview The inspection scope and results were summarized on December 17, 1993,-

with those persons indicated in paragraph 1. The inspectors described the areas inspected and discussed in detail the inspection result Although reviewed during this inspection, proprietary information is not contained in this report. Dissenting comments were not received from the license ~

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12 Acronyms and Initialisms j ABB -

Asea Brown Boveri BTP -

Branch Technical Position CE -

Component Engineer DC -

Direct Current ,

Differential Pressure

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EDG -

Emergency Diesel Generator EDSFI -

Electrical Distribution System Functional Inspection:

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Engineering Work Orders IFI -

Inspection Follow-up Item IP -

Inspection Procedure FSAR -

Final Safety Analysis Review MCC -

Motor Control Center MGMM -

McGuire Minor Modification MM -

Minor Modification M0V -

Motor' Operated Valve ,

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Main Steam Isolation Valve MW -

Mega-Watts NMS -

McGuire Nuclear Station l NSM -

Nuclear Station Modification NPF -

Nuclear Power Facility i NRC -

Nuclear Regulatory Commission PIP -

Problem Investigation Process PM -

Predictive Maintenance QA -

Quality Assurance QIP -

Quality Improvement Project -

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Nuclear Service Water RIS -

Rochester Instruments SE -

System Engineer SER -

Safety Evaluation Report SITA -

Self Initiated Technical Audit '

SPR -

Station' Problem Report SRG -

Safety Review Group TS -

Technical Specifications *

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Volts VT0 -

Vital To Operations

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