ML18096A867

From kanterella
Jump to navigation Jump to search
Insp Repts 50-272/92-11 & 50-311/92-11 on 920706-09.No Violations Noted.Major Areas Inspected:Maint Program Implementation
ML18096A867
Person / Time
Site: Salem  PSEG icon.png
Issue date: 07/29/1992
From: Baunack W, Blumberg N
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML18096A865 List:
References
50-272-92-11, 50-311-92-11, NUDOCS 9208050335
Download: ML18096A867 (10)


See also: IR 05000272/1992011

Text

.

'

U.S. NUCLEAR REGULATORY COMMISSION .

Report Nos.

Docket Nos.

License Nos.

Licensee:

REGION I

50-272/92-11; 50-311192-11

50-272; 50-311

DPR-70; DPR-75

Public Service Electric and Gas Company .

P. 0. Box 236

Hancocks Bridge. New Jersey 08038

Facility Name:

Salem Nuclear Generating Station. Units 1 & 2

Inspection At:

Hancocks Bridge. New Jersey

Inspection Conducted:

July 6-9. 1992

Accompanying:

Allison G. Heggie, Engineering Aide (Co-Op), DRS

Inspectors:

Approved by:

Walter H. Baunack, Sr. Reactor Engineer

Performance Program Section

Operations Branch, DRS

erg, Chief

Performance Programs Section

Operations Branch, DRS

7/gq/92--

date

Areas Inspected: .Unannounced safety inspection to review the licensee's maintenance

program implemen~tion.

Results: The implementation of the maintenance program was found to be acceptable.

Improvements are being initiated to the work order process as their need is identified.

Adequate maintenance procedures have been provided. System engineers are knowledgeable

9208050335 920730 '

PDR

ADOCK 05000272

G

PDR

2

of maintenance performed on their systems and good communication between system

engineers, maintenance personnel and planners appears to exist. Improvements to the

preveritive maintenance program ~ave been made and are continuing. One apparent violation

for failure to follow measuring and test equipment procedures was identified .

DETAILS

1.0 . PERSONS CONTACTED

- Attachment 1 provides a listing of persons contacted during the inspection. -

_ -2.0

MAINTENANCE PROGRAM IMPLEMENTATION (MODULE 62700)

An inspection was conducted to determine whether the licensee's maintenance-program .

is being implemented in accordance with requirements, to determine 'the effectiveness

of the maintenance program on important plant equipment, and to determine the

ability of the maintenance staff to conduct an. effective maintenance program.

2.1

Review of Records Associated with Maintenance Activities

  • The licensee's procedure for the control of work on any Structure, system, or

compc>nent at the site was reviewed as were a number of completed maintenance work

packages. Documents which were reviewed are listed in Attachment 2.

-

In general, the work packages ~ere found to have been prepared in accordance with

the licensee's administrative requirements.

Work packages were noted to include procedures to be used, appropriate maintenance

. directives, drawings, and other reference material needed to perform the work. Shift

supervisors permission is required prior to beginning any work activity. Quality

assurance inspections were performed when required. Site personnel qualifications are

maintained; when contractors were used their qualifications were documented. -Parts

and materials which were used were identified.

-

The licensee's work control procedure states: Work Orders (WO) and the information

generated to document the work on the structures, systems, or component are

designated to support component history and the Station Performance Monitoring

Program. Also, the corrective action taken to prevent reoccurrence of the *problem

and a description of the cause of the failure is required to .be documented .

4.

The inspector noted that these procedural requirements were sometimes wen'

documented on some WO's while on others the documentation .was less complete.

  • This was discussed with the licensee. . The 'licensee indicated that this had been

recognized and that to improve documentation in these areas the WO form was in the

process of being modified.*. The modified form has an expanded activity description

portion, as well as an expanded description of the work performed section. The

description of work performed section will specifically require the identification of the

as found condition, the repair actions taken and the failure cause. The inspector was

provided with a draft of the new WO form. The licensee indicated that, when the

new form is issued, personnel training will be conducted which will emphasize the

importance of complete documentation.

The licensee's self-identification of the documentation weakness, as well as the

initiation of corrective action, is considered to be a positive initiative.

An additional existing effort to improve work packages is the inclusion of a planned

package feedback sheet in each WO. This sheet provides for work package

improvement suggestions, as well as documentation by the planner as to the action

taken as a result of the suggestions. The conscientious use of these sheets should help

. improve work packages.

. It was noted that a detailed procedure has been prepared which provides instructions

. for required post maintenance testing (PMT} and operability testing. However, the

. WO form does not have a PMT block and PMT is frequently identified under the

activity description. For several of the completed work packages.which were

. reviewed, identification of the PMT which was performed was difficult. The

requirement for and* the documentation of PMT was discussed with the licensee. *The

licensee indicated that the identification and documentation of required PMT was

currently under review and that improvements were anticipated.

2.2

Review of Maintenance Procedures

Several maintenance procedures used in the performance of the maintenance tasks

were reviewed by the inspector. Procedures which have been prepared- in accordance

with the procedure upgrade project conform to the licensee's administrative

requirement for updated procedures. Step by step instructions are included as are

.

.

inspection hold points. Reference material and drawings are identified or provided,

and provisions for control 9f equipment are prov:ided. Notes and caution statements

are highlighted. The procedures appear to provide sufficient detail for the work to be

performed .

5

2.3

  • Machinery History Records
  • Machinery history *records in four maintenance packages for equipment which was*

. worked that were reviewed by the inspector were discussed with the appropriate

. system engineers. The equipment worked on consisted of the No. 11 Boric Acid

Transfer Pump, No. 12 Diesel Generator Starting Air Compressor Safety Relief

Valve, 1-B Di~sel Generator Slip Ring Refurbishment, and the 22MS 167 Main Steam

Stop Valve Inspection and Rework.

.

.

.

.

Jn. each instance, the responsible system engineer was very familiar with the

machinery history which is available on the computer. For t}lree of the four

components, the system engineer maintained his own fog which contained equipment

history. For the Diesel Generator Starting Air Compressor Safety Relief Valve, based

on maintenance findings, additional preventive maintenance is being considered. For

the main steam stop valve, the system engineer was familiar with the vendors *rebuild

report and had scheduled a meeting with the vendor to discuss the valve overhaul and

future overhaul requireinents. Engineering assistance was requested as required.

Overall good communications appear to exist between system engineers, maintenance

personnel and maintenance planners.

  • The Reliability and Assessment Group is using machinery history records to provide

management with data associated with component failures. Several reports were

  • provided to the inspector which indicate systems and components that have had
  • * multiple corrective maintenance WO's prepared.

2.4

Preventive Maintenance Program

The licensee is in the process of making improvements to the preventive maintenance

(PM) program. PM's are being reviewed as a result of the reliability centered

maintenance reviews being conducted, certain PM reduction analyses are being

performed, work is*progressing on a predictive maintenance program, and an overall

review of the PM program is being conducted. Other activities associated with

maintenance program improvement include industry and in-house experience

. assessment, and system .maintenance effectiveness. An overdue PM report is prepared

and available to management. The overall result of the licensee's actions dealing with

PM's has been to significantly reduce overdue PM's. Also, to provide additional

  • protection a new PM procedure requires that an evaluation be performed prior to the

deferral of any PM.

  • ~*

6

2.5

Control of Measuring and Test Equipment (M&TE)

  • A review of records associated with several pieces of M&TE used to perform

. maintenance in the packages reviewed was performed.* This was a limited review

confined to only several pieces of equipment identified in Attachment 2. Step 5.1.4

. of procedure NC.NA-AP.ZZ-:-0022(Q), Rev. 1, Measurement and Test Equipment

(M&TE), and Tool Control, requires that, "M&TE shall be returned to the applicable

tool room immediately after completion of the WO or task for which it was signed

out, or after a period of seven days; whichever comes first." Although not part of the

M&TE procedure, ari M&TE tracking log is maintained at the issuing tool room.

This log for each piece of equipment, contains the issue and return date, requestors

identification, and usage data which includes the WO.the equipment was to be used

on .

. In the effort to follow up on several pieces of M&TE used on work activities reviewed

immediately upon examining the M&TE tracking log, it was obvious numerous pieces

of equipment had not been returned within a period of seven days. Ten pieces of

equipment were quickly identified which were out over seven days. One of these was

out past its calibration due date. A further review of four pieces of equipment showed

that two of the four were*not logged to the WO on which they were µsed. These two.

pieces: (1) SA-STR-1134, identified in a work package as being used during the

performance of WO 920406105; and (2) SA-SA-MMT 1520, identified as used during

the performance of WO 910730109, were never logged out to these WO's. This

appears to be contrary to the requirements of station procedures and is considered to

be a violation (50-272/92-11-01 and 50-311/92-11-01). No other.requirements

specified by the M&TE procedure were reviewed during this inspection.

3.0 *

CONCLUSION

The work control procedure adequately describes the preparation of work packages.*

.

.

Completed work packages were found to be prepared essentially in accordance with

procedural requirements. Deficiencies in documentation that appeared to exist had

been identified -by the licensee and corrective action was in the process of being *

. implemented. Improvements to the documentation to PMT is currently under review.

Adequate procedures for_ the performance of maintenance tasks are being provided ..

Machinery history records are being used to identify multiple maintenance on specific

components. Improvements to the PM program have been made and are continuing.

.

.

Deferred PMs are required to be evaluated. Progress has been made in reducing the

number of overdue PMs. *A lack of procedural adherence was identified relating to

the control of M&TE .

7

4.0

Management Meetings

Licensee management was iriformed of the scope and purpose of the inspection at an

  • . entrance meeting on July 6, 1992. The findings of the inspection were discussed with

licensee representatives during the course of the inspection and presented to licensee

management at an exit interview on July 9, 1992.

Attachments: .

1. Persons Contacted

2. Documents Reviewed

8

ATTACHMENT 1

PERSONS CONTACTED

Public Service Electric and Gas Company

  • M. Alpaugh, Licensing Engineer

P. Buzzard, Nuclear Maintenance Supervisor

S. Davies, System Engineer

F. Kaminski, IST Engineer

  • R. Kazunas, Supervising Engineer, Site Services

M. Maley, System Engineer

J. Nichols, Manager Reliability and. Assessment

W. O'Brien, Senior Engineer

  • M. Panko, Planning Engineer,
  • J. Pollock, Mechanical Maintenance Engineer

M. Shedlock, Maintenance Manager

  • S. Skabieki, Quality Assurance

D. Strong, Preventive Maintenance Project Manager

B. Thomas, System Engineer

  • E. Villar, Station Licensing Engineer
*C. Vondra, General Manager

U.S. Nuclear Regulatory Commission

  • S. Barr, Resident Inspector
  • A. Heggie, Engineering Aid (Co-Op), OPS Branch, DRS

. *Denotes those present at the exit meeting on July 9, 1992.

Other plant,. technical, and management personnel were contacted during the course of the

inspection.

..

9

ATTACHMENT 2

DOCUMENTS REVIEWED .

Nuclear Department Administrative Procedures

NC.NA-AP.ZZ-0009(Q), Rev. 4, Work Control Process

NC.NA-AP.:ZZ-0050(Q), Rev. 0, Station Testing Program

'

.

.

NC.NA-AP.ZZ-0048(Q), Rev. 0, Station Performance Monitoring Program

NC.NA-AP.ZZ-OOlO(Q), Rev. 1, Preventive Maintenance

'

.

.

NC.NA-AP.ZZ-0022(Q), Rev. 1, Measurement and Test Equipment (M&TE), and Tool

Control

Work Order Packages

. WO 9.107161S7, 22MS167 Disassemble, Inspect/Rework as Needed. Activities 1 through 24.

_WO 920406105, 12DAIA/Lift Set Test/Refurbish or Replace

WO 910730109, 1-B Diesel Gen/Gen Slip Rings/Refurbish. Activities 1_ through 3.

WO 920529059, #11 BAT Pump Mechanical Seal Leaking/Rebuild. Activities J through 6 .

. WO 920403148, 1DAE4 Perform 24 Hour Endurance Run

WO 920413077, ICVE8/High Dose Rates/Change Filters. Activities 1 through 3.

Maintenance Procedures

M2R, Control of Heavy Loads, Enclosure 2, Heavy Load Lift Check List.

MS167, Hydraulic Actuator Overhaul.

Ml lE-2, Shop and Field Machining.

SC.MD-CM MS-002(Q), Rev. 3, Overhaul of Main Steam Stop Valves MS167'.

M14C, Repacking of Main Steam Stop Valves MS167's

10-

SC.MD-CM.DG-0003(Q), Emergency Diesel Generator Collector. Ring Resurfacing.

MllE, Mechanica1.Equipment Troubleshootiiig and Repair.

M7C-2, Reactor Coolant Filter-Elevation 100

. Operating Procedure

SI.OP-PT.DG-0012(Q), lA Diesel Generator 24 Hour Load Study Run.

Measuring and Test Equipment

The following equipment was still out for use on July 9, 1992.

SA-MNT-0891, Logged Out 4/29/92 for WO 92117015.

.

.

SA-MNT-0910, Logged Out 6/29/92 for WO 870901208.

SA-MNT-:0917, Logged Out 5127192 for WO 920303193.

SA-MNT-0923, Logged Out 6/14/92 for WO 920610142,_the calibration due date for this

instrument is 6/21/92.

SA-STR-0040, Logged Out 4/16/92 for WO 901104007.

SA-STR-0049, Logged Out 4/28/92 for WO 920418059 ..

SS-STR-0083, Logged Out 6/25/92 for Info Only.

SA-STR-0122, Logged Out 6/11/92 for WO 910503173 .

. SA-SM-0158, Logged Out 6/11/92 for WO 910503173.

SA-STR-01_71, Logged Out 3/18/92 for WO 911231108.

SA-MNT-1520, Identified as used on WO 910730109 not logged to WO.

SA-STR-1134, Identified as used on WO 920406105 not logged to WO.