IR 05000219/1985031

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Insp Rept 50-219/85-31 on 851007-10.No Violation Noted.Major Areas Inspected:Inservice Insp Data Obtained During 1983 Outage
ML20205G386
Person / Time
Site: Oyster Creek
Issue date: 10/31/1985
From: Kerch H, Wiggins J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20205G383 List:
References
50-219-85-31, NUDOCS 8511130235
Download: ML20205G386 (4)


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U.S. NUCLEAR REGULATORY COMMISSION REGION I.

Report No.

50-219/85-31

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Docket No.

50-219 License No. DRP-16 Priority

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Category C

Licensee:

GPU Nuclear Corporation P. O. Box 388 Forked River, New Jersey 08731 Facility Name: Oyster Creek Nuclear Station Inspection At:

Forked River, New Jersey Inspection Conducted: October 7-10, 1985

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Inspectors:

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gfns,Chiff date fals&ProYe[asesSection Ma Inspection Summary:

Inspection on October 7-10, 1985,-(Report No. 50-219/85-31)

Areas Inspected: Routine announced inspection of the licensee's inservice inspection data obtained during the outage of 1983. This inspection included 27 onsite hours by one inspector.

Results: No violations were identified.

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DETAILS 1.

Persons Contacted GPU Nuclear (GPUN) Corporation

P. Fiedler, Vice President and Director, Oyster Creek T..Paterson, Manager Special Processes and Program

G.:Rhedrick, Lead ISI Programs Engineer

T.-Conner, Quality Control Manager

J. Rogers, Licensing Engineer

R. Ostrowski, Inservice Inspection Supervisor USNRC

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W. Bateman, Senior Resident Inspector J. Wechselberger, Resident Inspector.

'*~ Denotes those personnel present at the exit interview 2.

Inservice Inspection (ISI) activities 14.

Data Review and Evaluation The inspector reviewed nondestructive examination (NDE) data included within the below' listed ASME categories per tables IWB-2500 and IWC-2520.

The review was conducted to ascertain completeness and accuracy in accordance with the ASME Code and regulatory requirements; the ASME categories. included:

B-A B-K-1 B-B B-K-2

.B-C B-M B-D B-0

~B-E-C-C B-F C-E-1 B-G-1 C-E-2 B-G-2 C-F B-H C-G

B-5 Also the inspector reviewed the NDE data for the welds included in sample number 3 of the licensee's augmented examination program for the isolation condenser system and reviewed repair records for weld NE-1-15.

This weld was selected because it had been rejected and replaced as a result of the augmented program. The repair weld trave-1er and associated quality records were reviewed for completeness and accuracy.

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-3-For all of the above, the methods, technique and extent of examinations were found to comply _with the 1983 ISI program and its applicable procedures.

However, this review revealed that several welds on the reactor vessel bottom head were not listed within the licensee's ISI Program (i.e. welds 3-562-A thru F).

Further-investigation revealed that relief from the Code-required volumetric examination for these welds had been2 granted by the NRC in a letter dated June 28, 1983, with the

' understanding that an alternative visual examination be performed

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during vessel hydrostatic tests in accordance with station procedure

'602.4.007 Rev. 3.

Following discussions with the inspector, the licensee agreed to-list these visual examination requirements within the ISI program.

Results: No violations were identified.

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Procedure Review The inspector reviewed the following NDE procedures for technical adequacy and content:

a Liquid Penetrant Examination Procedure MTIS-007 Rev 3 Magnetic Particle Examination Procedure MTIS-004 Rev 3 Ultrasonic Examination Procedure MTIS-013 Rev 3 Results: No violations were identified.

C.

Document Review The inspector reviewed the following documents in order to establish the basis for judging the acceptability of the licensee's ISI program:

1983 Inservice Inspection Final Report Schedule for the April 1986 Outage Relief Request Letters dated June 28, 1983 and May 22, 1985 GPUN Technical Data Reports 571 and 657

cs GPUN Letter dated June 5,1981

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Subject: ASME Year and Addenda for ISI.

i GPUN Augmented Inspection Procedure SP-1302-23-006 This review revealed that the following fifteen overlaid safe end welds have not been surface or volumetrically examined due to as-welded surface conditions:

10 recirculation system welds 2 isolation condenser supply line welds 2 core spray line welds I control rod drive hydraulic system return line weld

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However the inspector noted that GPUN has committed to develop an-adequate examination technique for these bimetallic safe end nozzle welds, in order to satisfy.the requirements of Generic Letter 84-11 by April 1986 outage.

Results: No violations were identified.

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Equipment Calibration

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The inspector verified the calibration records for the below listed equipment used for ISI examinations during the 1983 outage:

Ultrasonic

Kaulkramer-- Branson USL-38 Serial Number 211050 USL-37 Serial ~ Number 211581 Magnaflux P5710 Serial Number 821646 Sonic Mark 1 FTS-1 Serial Number 780839 Magnetic Particle Magnaflux Yoke Serial Number 6034-11 Magnaflux Yoke Serial Number 6034-10 Magnaflux Yoke Serial Number 6035-1 Results: No violations were identified.

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Exit Interview

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The. inspector met with licensee representatives = listed in Paragraph 1 at

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the conclusion of the inspection on October 10, 1985. The inspector summarized the purpose and the scope of the inspection and the findings.

'At no time during this inspection was written material provided to the i

'Itcensee by the inspector, f

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