IR 05000289/1978026
| ML19322A292 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/05/1970 |
| From: | Ebneter S, Mcbrearty R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19322A288 | List: |
| References | |
| 50-289-78-26, NUDOCS 7903300470 | |
| Download: ML19322A292 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-289/78-26 Docket No. 50-289 License No. DPR-50 Priority Category C
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Licensee: Metropolitan Edison Comoany P. O. Box 542 Reading, Pennsylvania 19640 Facility Name: Three Mile Island Nuclear Station, Unit 1 Inspection at: Middlatown, Pennsylvania Inspection conducted:
December 12-14, 1978
A 4 /977 Inspectors:
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R. A. McBrearty, Reac Inspector date signed S. D. Ebneter, Section Chief date signed date signed N
i/<'/W Approved by:
g S. D. Ebneter, Chief, Engineering Support da te' signed Section No. 1, RC&ES Branch Inspection Summary:
Inspection on December 12-14,1978 (Report No. 50-289/78-26)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector of the licensee's inservice inspection examination data.
The inspection involved 29 inspector-hours on site by one NRC regional based inspector and one supervisor.
Results:
In the area inspected, one apparent item of noncompliance was identified (infraction - failure to adhere to procedures during inservice inspection ultra-sonic examination - Paragraph 2a).
7 90 3 30 0 4 to Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted Metropolitan Edison Company
- Mr. R. O. Barley, Lead Mechanical Engineer
- Mr. W. C. Ream, ISI Coordinator
- Mr. M. J. Ross, Unit 1 Supervisor of Operations
- denotes those attending the exit interview.
2.
Inservice Inspection (ISI) Data Review and Evaluation The Three Mile Island Unit 1 ISI program which was submitted to the NRC, in accordance with 10 CFR 50.55(g), for the second forty month period of the first ten year inspection interval is intended to meet the requirements of the ASME Code,Section XI,1974 Edition through Summer 1975 Addenda as modified by the facility Technical Specification. The examinations done during the 1978 refueling outage constituted the commencement of the second forty month period.
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The inspector found that major program deviations from the ASME Code are pending NRC approval and that the examinations done durir.g the 1978 outage were intended to meet the more conservative
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of the Code and Technical Specification requirements.
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a.
NDE Data Review The inspector reviewed data associated with the following welds and/or base materials:
Reactor Pressure Vessel Closure Head to Flange Weld
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RH-001-C Feedwater System Weld FW-W-1
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Pressurizer Heater Bolts Number PRb-0lM thru PRb-16M
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Steam Generator "A" Lower Manway Studs Number SGa-17-M
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thru SGa-32-M Reactor Pressure Vessel Studs and Nuts Number 21 thru
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40 inclusive Reactor Coolant Pump 1A Weld Number RC-026
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Records for the above listed welds and/or base materials were reviewed to ascertain compliance with regulatory re-quirements in the following areas:
Examination results and data sheets
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Examination equipment data
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Calibration data sheets
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Examination evaluation data
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Records on extent of evaluation
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Records on deviations from program including inacessi-
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bility The method, technique and extent of examinatio'n are
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consistent with the licensee's ISI program and appli-cable NDE procedure The method used for NDE was sufficient to determine
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the full extent of indication or acceptance Evaluation of examination data was done by a Level II
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or Level III examiner Examinations were done by properly certified NDE per-
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sonnel The inspector found that the following ultrasonic examirations were done using techniques that appear to deviate from ASME Code and specific NDE procedure requirement Steam Generator "A" lower manway studs SGa-17M thru SGa-
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32M
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Pressurizer Heater bolts PRb-OlM thru PRb-16M
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Feedwater weld FW-W-1 and weld FW-W-2
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The ultrasonic examination of the lower manway studs and the pressur'ar heater bolts was governed by NES procedure NIP-020, Peusion 1, " Manual Ultrasonic Exar..ination Procedure for Pressurizer Retaining Bolting (Bolts, Studs and Nuts)," which requires that all straight beam examinations be done using a frequency of 2.25 MH.
Section XI of the ASME Code permits z
the use of frequencies other than 2.25 MHz if the use is justified and documented.
Data sheet number 020-1, dated March 25, 1978 and data sheet number 020-2, dated March 25, 1978 indicate that the straight beam examination of the above material was done using a test frequency of 5.0 MHz.
Documentation justifying the use of 5.0 MH was not available.
z The examination of the feedwater welds and the hydrogen purge system weld was governed by NES procedure NIP-018, Revision 1,
" Ultrasonic Procedure for Piping Butt Welds and Longitudinal Welds", which requires that all straight beam and angle exami-nations be done using a frequency of 2.25 MHz.
Procedure NIP-018 permits the use of other frequencies if 2.25 MHz cannot be used.
In the event that another test frequency is used, the reason and justification for its use must be documented on the associated data sheet.
This requirement is consistent with the ASME Code,Section XI.
Data sheet number 018-23, dated April 5,1978, indicates that the feedwater system welds were examined using a 3.5 MHz trans-ducer with the instrument pulser set at 5.0 MHz.
Data sheet number 018-28, dated April 6,1978, indicates that the hydrogen purge system weld was examined using a 5.0 MHz transducer with the instrument pulser set at 2.25 MHz.
Documentation justifying the frequency combinations used was not found on the associated data sheets and was not available at the sit '
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The inspector discussed the above items with licensee repre-sentatives at the site and in a subsequent telephone conversa-tion on December 18, 1978.
The failure to perform ultrasonic examinations as required by the governing NDE procedure is considered an item of noncom-pliance regarding Criterion V of 10 CFR 50, Appendix B.
(78-26- 01 )
3.
NDE Personnel Certification The inspector reviewed qualification and certification records for the licensee's ISI contractor NDE personnel who performed examinations during the 1978 refueling outage.
The inspector found that certification records were incomplete for the technician responsible for the magnetic particle examination of reactor pressure vessel studs number 27, 28 and 29, and reactor pressure vessel nuts neaber 26, 27, 28, 29 and 30 on April 1,1978.
After the inspector left the site, additional information was for-warded by mail to him.
The records made available to the inspector indicate that recertifi-cation of the individual was apparently done on site during the outage, but the records do not show the extent of qualification for the certifying examiner, nor are they clear on the method used for recertification.
This item was discussed with licensee representatives at the site and in subsequent telephone conversations on December 15 and 18,
1978.
The inspector stated that this item is considered unresolved pending availability and NRC review of the complete certification record for the two involved individuals.
(78-26-02)
4.
Unresolved Items Unresolved items are matters about which more information is re-quired in order to ascertain whether they are acceptable items, items of noncompliance, or deviations.
An unresolved item dis-closed during the inspection is discussed in Paragraph 3.
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5.
Exit Interview The inspector met with licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on December 14, 1978.
The inspector sumarized the purpose and scope of the inspection and the findings.
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