IR 05000219/1993016
| ML20057A101 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/27/1993 |
| From: | Gray E, Mcbrearty R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20057A099 | List: |
| References | |
| 50-219-93-16, GL-89-08, GL-89-8, NUDOCS 9309130044 | |
| Download: ML20057A101 (5) | |
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U. S. NUCLEAlt REGULATOltY CO.%D11SSION
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REGION I
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Report No.:
50-219/93-16 i
Docket No.:
50-219 i
License No.:
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Licensee:
GPU Nuclear Corporation
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Facility Name:
Oyster Creek Nuclear Generating Station
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inspection At:
Forked River, New Jersey
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Inspection Conducted:
July 26 - 30,1993 l
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/f f 3 Inspectors:
/ ate R. A. McBrearty, Reactor EI1gr.
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Materials Section EB, DRS j
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Approved by:
^W 827/93
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i E. II. Gray, Chief, Materials Date j
Section, EB, DRS j
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Areas inspected: An announced inspection was conducted of the licensee's crosion/ corrosion l
(EC) inspection program to ascertain that activities relative to the long-term EC monitoring
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program are being accomplished in accordance with Generic letter 89-08 and licensee
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commitments and procedures.
Results The program and its implementation are generally good. The staff responsible for
_ the EC program development and implementation (corporate engineering and site NDE/ISI)
are qualified and knowledgeable of the activities for which they are responsible.
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930913o044 93o903
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I DETAILS i
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1.0 BACKGROUND (INSPECTION PROCEDURE 49001)
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Concerns regarding erosion and corrosion in balance of plant piping systems has been
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heightened as a result of the December 6,1986, feedwater line rupture that occurred at Surry
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Unit 2. This event was the subject of NRC Information Notice 86-17, Bulletin 87-01 and j
Generic letter (GL) 89-08. The GL specifies that all licensees provide assurances that a f
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program consisting of systematic measures to ensure that erosion / corrosion (EC) does not
lead to degradation of single and two-phase flow, high energy carbon steel systems, has been l
implemented.
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An effective EC program will detect degradation of high energy carbon steel piping before j
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the pipe wall is significantly reduced below the design or piping code Ir.inimum wall
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thickness. This program should reduce risk to the plant staff and prevent unnecessary system l
transients, thereby contributing to the safety of the public.
Each GPUN nuclear facility has an established long-term EC monitoring program. The
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inspection procedures (ultrasonic examination) used for the detection of erosion / corrosion I
l damage in piping systems are common to each of the facilities. The programs are intended
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to assure that the structural integrity of all high-energy, single-phase, and two-phase flow, j
l carbon steel systems is maintained.
2.0 INSPECTION OlUECTIVE
a The inspection was conducted to determine whether licensee activities relative to the long-i
term EC monitoring program were being accomplished in accordance with NRC
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requirements and licensee commitments and procedures.
3.0 PROGRA31 ORGANIZATION
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i The EC monitoring program is organized to operate with the cooperation of engmeermg, j
g project management, and Implementation Services, three interfacing disciplines. Mechanical i
Engineering, Systems Engineering, and Plant Engineering comprise the engineering staff.
l Project management staffing includes the project engineer and project engineering l
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management. Implementation Services includes Non-destructive Examination / Inservice
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Inspection (NDE/ISI) and Site Services Division (SSD). The Project management and the l
mechanical engineering portion of Engineering are common to the EC monitoring program
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applications at Oyster Creek and Three Mile Island Unit 1. Insp!cmentation Services,
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l Systems Engineering, and the Plant Engineering portion of engineering are specific to each site, assuring compliance with site specific requirements.
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)2 4.0 PROGRA51 RESPONSIBILITIES
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990-.134,
Responsibilities of the various GPUN groups are delineated in Report No.
" Project Organization and Responsibilities Document (PORD)," which is applicable to the
Oyster Creek Nuclear Generating Station and the Three Mile Island Nuclear Generating
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Station, Unit 1.
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4.1 Technical Functions Division-Parsippany l
The Mechanical Engineering (ME) Section of Technical Functions is responsible for selecting and prioritizing the EC program scope. The list of selected items is based on the criteria j
identified in Technical Data Report (TDR) No. 861, Revision 1. The listing for Oyster l
Creek is found in Specification No. SP-1302-12-237, Revision 5, and SP-1101-12-110, Revision 5, contains the Three Mile Island, Unit I listing. Other ME responsibilities include
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responding to engineering evaluation requests (EER) including repair / replacement requirements, providing technical support for repairs, and maintaining and updating the EC program TDRs. Additionally, the ME Section, in conjunction with Technical Functions
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Systems Engineers and Plant Engineering, is responsible for performing root-cause analyses.
The Project engineer responsibilities include the coordination of data acquisition, evaluation i
and problem resolution activities, and managing the project.
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i Plant Engineering, jointly with Systems Engineering, supports Mechanical Engineering with i
respect to inspection teruits evaluation, Material Nonconformance Report (MNCR)
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resoludon, and the preparation of repair / replacement engineering packages.
The NDE/ISI performs inspections and reports the results in accordance with instructions l
provided by Mechanical Engineering. Additional NDE/ISI responsibilities include performing repair / replacement examinations and issuing MNCRs and EERs as required.
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4.2 Systems Selection and Prioritization-l Technical Data Report No. 861 provides information relative to the selection of systems requiring EC inspection. Selection criteria identified in the report must be considered by the
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Mechanical Engineering staff engineer who is responsible for the erosion / corrosion inspection i
program. General criteria identified in the TDR and used in the selection process include:
i Moisture content equal or greater than 2%
Water chemistry - pH level l
Fluid velocity Piping layout - geometry l
Temperature l
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The systems included in the Oyster Creek EC inspection program are listed in Table 8.2 of f
l the TDR. Inspection prioritization is based on output from CHEC/CHECMATE predictive i.
computer codes developed by the Electric Power Research Institute (EPRI), and engineering
j judgment that considers plant experience, industry experience, industry recommendations,
and regulatory requirements. Records reviewed by the inspector conGrmed that the system
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CHECMATE analyses were performed. Systems subjected to CHECMATE analysis include:
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Feedwater system I
Drains system a
Extraction steam system i
5.0 INSPECTION ACTIVITIES
j The Oyster Creek inspection sample for the 14R outage is listed in Table 4 of speci6 cation
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j SP-1302-12-237, Revision 5. The listing was used by the site to schedule the EC inspections for the outage.
The licensee's EC inspection method incorporates ultrasonic examination techniques for
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l measuring pipe wall thickness. Specinc techniques, depending upon the radiation dose rate j
in the area, are described in the speciEcation. The appropriate grid size is based on pipe i
diameter, and is denned in the speci6 cation as follows:
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Nominal Required
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Pioe Diampter Grid Si7e 2 " - 6" 1"
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g _12-2-
i 14" - 18" 3"
20" and greater 4"
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Readings are taken at grid line intersection points unless otherwise specified, and the grid
size is identified on the inspection report. Procedure No. 6100-QAP-7209.31, Revision 0,
" Ultrasonic Examination of Components for Erosion / Corrosion," outlines the requirements
for the layout of components prior to the performance of ultrasonic thickness measurements.
Datum points are permanently etched or stamped with low stress stamps to permit accurate
relocation of grids for subsequent inspections. The procedure provides specific details regarding the location of datum points for various piping con 6gurations. A sketch showing
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how the grid should be applied to the pipe surface illustrates the gridding of a section of
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straight pipe. The procedure could be improved and made more informative if sketches
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showing the application of grids on other, more complex, pipe geometries were included.
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t Erosion / Corrosion inspection data are acquired using an ultrasonic data logger that stores the readings until they are loaded into a personal computer, after which the information is i
i recorded on a computer disc and on a hard copy report. Those reports showing reportable or unacceptable thickness measurements are quickly submitted to the cognizant ME EC engineer
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for evaluation. That process was expedited during the 14R outage by having the cognizant
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EC engineer located at the site, where the data review and evaluation were performed on a i
daily basis, and included all EC inspection reports. The inspection reports include a printout of the thickness readings, the applicable grid size, and the minimum and maximum measured thickness and their respective grid location.
When piping must be replaced, the new piping is either carbon steel or a chrome-moly alloy steel, which is more resistant to erosion / corrosion than is carbon steel. A safety / environmental determination and 50.59 review to permit the replacement of carbon steel with chrome-moly alloy steel has been prepared by engineering.
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6.0 CONCLUSIONS i
The General Public Utilities Nuclear Corporation (GPUN) has an established long-term erosion / corrosion monitoring program. Corporate Engineering and Site EC staff responsibilities are clearly identified, and the staff at each location is knowledgeable in its
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l area of responsibility. Participation in industry organizations, such as the CHEC/CHECMATE Users Group (CHUG), and attendance by the staff at related functions i
is encouraged by the licensee. Responsibility for the EC programs at Oyster Creek and
Three Mile Island has been assigned to two corporate-based engineers, one for each site,
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i The EC program incorporates the use of the CHECMATE computer code for system analysis. These recent changes are program-strengthening actions taken by GPUN.
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7.0 EXIT MEETING The inspector met with licensee representative (denoted in Attachment 1) at the conclusion of the inspection on July 30,1993. The inspector summarized the scope and findings of the
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inspection, which were acknowledged by the licensee.
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ATTACllMENT 1 PERSONS CONTACTED General IWilclililies Nucirar Cornantli9n
- D. Holland, Senior Project Engineer
- S. Levin, Director O&M J. P. Logatto, Engineer, Mechanical Systems
- P. Manning, Manager, NDE/ISI Services D. J. Masiero, Fluid Hydraulics Manager R. Nademus, ISI Engineer
- J. Rogers, Senior Licensing Engineer
- A. Rone, Site Director, Technical Functions A. Smith, NDE Engineer V. P. Zeppos, Mechanical Components Engineer ILS. Nuclear Rfgulatory Cununission
- S. M. Pindale, Resident Inspector
- D. J. Vito, Senior Resident inspector
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