IR 05000219/1986019

Insp Rept 50-219/86-19 on 860707-11.No Violation Noted. Major Areas Inspected:Aws D1.1 Welding,Emergency Svc Water Line Visual Exam,Inservice Insp Per ASME Code Section XI & Generic Ltr 84-11 Requirements

ML20204H366
Person / Time
Site:	Oyster Creek
Issue date:	07/30/1986
From:	Gray E, Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20204H348	List: IR 05000219/1986019 ML20204H343
References
50-219-86-19, GL-84-11, NUDOCS 8608080093
Download: ML20204H366 (6)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /86-19 Docket N License N DPR-16 Licensee: GPU Nuclear Corp Oyster Creek Nuclear Generating Station P0 Box 388 Forked River, New Jersey 08731 Facility Name: Oyster Creek Nuclear Generating Station Inspection At: Oyster Creek Plant, Forked River, New Jersey Inspection Conducted: July 7-11, 1986 Inspectors: h) J-46x 7-3d 5 C lirly! gi Reactor ngineer date Approved by: % Me ~7-f4 -84 J/T. Wiggip,fhief Tlaterials and date Mocesses SMF on, EB, DRS Inspection Summary: Inspection on July 7-11, 1986 (Report No. 50-219/86-19)

Areas Inspected: Routine unannounced inspection in the areas of AWS D welding, emergency service water line visual examination, Inservice Inspection (ISI) per ASME Code Section XI and GL 84-11 requirements, atmospheric butterfly valves (Part 21), condenser eddy current tube examination and QA involvement in ISI activitie Results: No violations were identified.

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DETAILS Person Contacted GPU Nuclear Corporation (GPUN)

• J. Abramovici, Engineering Manager, Heat Exchangers, Pressure Vessels

• J. Barton, Deputy Director of Operations

• T. Corrie, QC Manager P. Deeds, UT Level III, IGSCC, GL 84-11

• G. Faulkner, Corp. Welding Manager R. Nademus, QC, NDE Engineer

• R. Ostrowski, ISI Program Manager

• T. Patterson, Manager, Special Processes and Programs

• M. Radvansky, Manager, Tech. Functions

• G. Rhedrick, Lead ISI Program Engineer

• J. Rogers, Licensing Engineer S. Saha, Materials Engineering (Reading GPU)

R. Turner, QC Supervisor NRC W. Bateman, Senior Resident Inspector

• J. Wechselberger

• Indicates persons present at exit meeting on July 11, 1986. Licensee Action on Previously Identified Items (0 pen) Violation (219/85-35-01) Inclusion of certain AWS D1.1 code specifics in the GPUN welding progra The inspector reviewed this violation, the GPUN response to the violation dated April 18, 1986, parts of GPUN welding manual 6150-QAP-7220.03 and Technical Data Report (TDR) No. 770, revision 0, which evaluates the applicability of using ASME Section IX code welders and procedures on AWS D1.1 welded structures. GPUN engineering presented how the

" Engineer" referenced in AWS D1.1 provides for review and approval of designated welding procedures and weld joint details for a particular AWS D1.1 structure.

l While portions of the AWS D1.1 code are referenced in the GPUN welding manual, details or references to specifics in the areas of partial penetration welding and skewed fillet weld joints were not contained in l the welding manua These details are needed by engineering during design j and by the field during installation. Tentative revisions to the welding l manual were proposed by GPUN to address these AWS D1.1 welding factors.

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In particular, the proposed changes included paragraphs 4.1.1 and 4.10 and the addition of AWS tabular data defining partial penetration and skewed weld joint details. This item remains open pending review of the above welding manual revisions.

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(0 pen) Unresolved Item (219/85-23-04). Emergency service water (ESW)

line, coal tar coating removal area, system testing and visual examinatio Previous system testing and inspection identified that the bitumastic or coal tar enamel had become detached from the ESW Systems I and II resulting in this material partially blocking flow to the system heat exchangers. The area of loosened coating was found to be limited to the pipe length between the pump discharge and the point of chlorinatio During inspection 86-19, the inspector reviewed the current outage TV optics examination tape for 59 feet of the south ESW Line from the pump elbow where the coating was previously removed. The present plan of GPUN is to inspect the ESW lines in the area of coating removal during each refueling outage to identify significant pipe degradatio The ESW pipe has a projected life (estimated by GPUN) to be 20 more years in these areas, without internal coatin This item remains unresolved pending NRC review of the items identified in inspection report 219/85-2 . Inservice Inspection (ISI)

During the current outage, the second period of the ASME Code Section XI ISI examinations of the second ten year interval are scheduled for completion. The outage augmented examinations include the ultrasonic testing scope established by generic letter 84-11 which is intended to identify intergranular stress corrosion cracking (IGSCC) in stainless steel pipin Examinations in progress included visual inspection by remote TV optics of reactor vessel internal components, including the core spray sparger and shroud head bolts. The inspector observed visual examinations in progress and reviewed portions of video tapes of visual inspections performed during this outage. Of particular interest, is the demonstration of visual resolution by focusing on a one mil wire (0.001" diameter) that was more clearly evident when viewed through the TV optic system than by the unaided eye. The observations made and visual inspection documentation were compared to the applicable GE Procedure 1630-QAP-7209.30 Rev 0-00 requirements. To date, the visual video examination during this outage had identified minor localized corrosion but no component crackin In the area of visual examination of pipe hangers and snubbers, the inspector sampled records of ISI visual examination of these items performed to procedure 6130-QAP-7209.05, 7209.25 or 7209.29, as applicable. The sample included components in the following major systems: reactor recirculation, shutdown cooling, isolation condenser, fuel pool cooling, core spray, emergency service water and feedwate No violations were identifie __ _

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In the area of UT of stainless steel piping welds to meet the scope of generic letter (GL) 84-11, the inspector reviewed a sample from the UT records of examinations made prior to the application of induction heating stress improvement (IHSI) during this outage. The following welds were included in this review sample:

ISO Condenser Piping Recirc Piping NE-1-32 NG-A-14 NE-1-64 NG-B-5 NE-2-91 NG-B-20 NE-2-103 NG-C-23 NE-1-27 Welds NE-1-27 and NG-C-23 were shown in the UT reports to contain indications of IGSCC. Evaluation and review of the indications was noted to be in progres Technical Data Report, TDR 657, Revision 2, presents the licensee's plan to IHSI all Class I welds in the recirculation, reactor water cleanup, isolation condenser, core spray and shutdown cooling systems. This is a total of approximately 354 IHSI treatment This TDR states that the welds on which IHSI is performed will then subsequently be UT examined for IGSC TDR 571, Revision 1, is the GPUN response to GL 84-11, defining the scope of inspections during the 1986 outage to detect the presence of IGSCC in stainless steel weld joints. The inspector reviewed portions of TDR 571 and TDR 657 for comparison of the GPUN IGSCC inspection program to the actions identified in GL 84-1 IHSI and the subsequent UT examination of these welds were scheduled to start during the weeks of July 14 and 21,1986. The post IHSI-UT examinations will be the basis to establish compliance to the NRC IGSCC detection commitmen No violations were identifie . Quality Assurance of ISI Program Activities The inspector reviewed the QA Inservice Inspection Audits S-0C-84-04 and S-0C-85-04 dated 6/18/84 and 5/13/85 and noted thorough QA involvement in verification of the definition and implementation of the Oyster Creek ISI Program. The next QA audit of the ISI program is scheduled for April 1987. The audits covered the following essential ISI program areas:

qualification and certification, procedures, document control, records management, conduct of ISI, control of recordable indications and equipment calibration. Provisions were noted to assure corrective action for problems identified during the audit No violations were identified.

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5, 10 CFR Part 21 Report on Clow Corporation Butterfly valves for atmospheric servic Philadelphia Electric Company (PECo) issued a Part 21 report dated 5/13/86 which describes a problem of carbon steel bearings corroding fast to the valve stainless steel shaft, preventing valve seat movement. The valves identified provide for containment isolation and vacuum relief in one torus to reactor building lin During the entrance meeting, the inspector outlined the reported problem, provided the GPUN licensing engineer with a copy of the Part 21 report and requested GPUN to establish if this concern was applicable to the Oyster Creek Plan The licensee established that no Clow butterfly valves, similar to those described, are in service at Oyster Cree However, the licensee did determine that Clow valves purchased for a vent and purge modific'ation

, were on site but not installed. The inspector reviewed the GPUN licensing action items 86158.01 and 86158.02, dated 7/11/86, which provide for evaluation and corrective action of this Part 21 identified conditio No violations were identifie . Independent Inspection

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The inspector observed the setup and examination of test standards for the Eddy Current (ECT) testing of titanium condenser tubes with M1Z-12 equip-ment. The test standards include the ASME ECT required test standard with specific holes and a separate tube thinning standard. Approximately 11,000 of the 50,000 condenser tubes (0.875 " Diameter, 0.028" Wall) are scheduled for ECT during the 11R outag No violations were identifie . Coating of Carbon Steel Components to Reduce Corrosion The reactor building closed cooling water heat exchangers are being

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replaced during this outage. The inspector noted the field had identified areas of non-bond in the shop applied corrosion barrier in the heat exchanger heads and water boxes. The work authorization A150-30523 provided for coating removal and replacement with a two layer coating of the trade name Belzona. This material requires mixing of two components at specific temperatures and application within a definite time for maximum adhesion. The surface condition of the material to be covered is also an important application variabl The inspector observed coated surfaces and reviewed the quality control coverage of the application process. A QC inspector is intended to be present during the mixing and application process to observe work in progress and inspect surfaces prior to coating. The inspector sampled QC surveillance and inspection reports typical of coating application Q No violations were identifie _ _ _

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8. Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)

at the conclusion of the inspection on July 11, 1986. The purpose, scope and findings of the inspection were summarized and discussed. At no time during this inspection,-except as noted in paragraph 5, was written material provided to the licensee by the inspecto .