IR 05000278/1978035
| ML19274D478 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/19/1978 |
| From: | Ebneter S, Jernigan E, Mcbrearty R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19274D477 | List: |
| References | |
| 50-278-78-35, NUDOCS 7902010226 | |
| Download: ML19274D478 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-278/78-35 Docket No.
50-278 License No. DPR-56 Priority Category C
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Licensee:
Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 Facility Name:
Peach Bottom Atomic Power Station Unit 3 Inspection at:
Philadelphia, Pennsylvania Inspection conducted. November 29-30, 1978 Inspectors:
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E. P. Jdrnigan, Reactor Inspector date signed
k$<'f ILlI N 7V R. A. McBrearty, React Inspector date' signed date signed Approved by:
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f a /ft1/74 S. D. Ebneter, Acting Chief, Engineering date signed Support Section No. 1, RC&ES Branch Inspection Summary:
Inspection on November 29-30, 1978 (Report No. 50-278/78-35)
Areas Inspected:
Routine, unannounced inspection by regional based inspectors of the licensee's inspection (ISI) examination documentation, associated with Class 1 System pressure retaining welds / components.
The inspection involved 28 inspector-hours by two NRC regional based inspectors.
Resul ts : No items of noncompliance were identified in the area inspected.
7902010226 Region I Form 12 (Rev. April 77)
DETAILS 1.
Persons Contacted Philadelphia Electric Company
- T. Anderson, Engineer, Research and Development
- J. Madara, Inservice Inspection Coordinator
- denotes those present at exit interview.
2.
Inservice Inspection (ISI) Data Review and Evaluation a.
Scope of ISI Interval The inspector reviewed the ISI program established for the current inspection interval in order to ascertain whether the data are consistent with the minimum requirements as delineated in the ASME %iler and Pressure Vessel Code,Section XI, 1970 Edition through Winter 1971 Addenda.
Included in the review were the following documents:
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Philadelphia Electric Company ISI Program for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3
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Southwest Research Institute Draft Plan 17-4337, Ten Year Inservice Examination Plan for PBAPS, Unit 3, November 1976 o
The inspector found that the examination schedule was evenly distributed over the ten year interval and that the records identify the welds cnd components which have been examined in addition to those requiring examination in subsequent refueling outages.
No items of noncompliance or deviations were identified.
b.
NDE Data Review The inspector selected records associated with the following for review to ascertain completeness of 1978 data package:
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Core Spray Loop B, 12 inch diameter piping Reactor Pressure Vessel Support Skirt Weld
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Reactor Pressure Vessel Closure Head Nuts
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The inspector found that the selected records cortained examina-tion results including method and exter.t of examination, ultra-sonic calibration sheets, indication evaluation data and disposi-tion of findings, equipment data (calibration and certification)
and identification of NDE material such as penetrant, penetrant cleaner and ultrasonic couplant.
In addition to the above, the inspector selected for review records associated with the following reactor pressure vessel and piping system welds:
RPV Support Skirt Weld Number RPV-SK (71" of weld)
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Core Spray Loop B Weld Number 14-B-21,12 inch elbow to
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pipe weld Core Spray Loop B Weld Number 14-B-26, reducer to safe end
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weld The inspector's review included, but was not limited to, the following parameters:
The method, technique and extent of examination are con-
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sistent with the licensee's ISI program and applicable NDE procedure
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The examination data are within the acceptance criteria as outlined in the applicable NDE procedure
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Calibration and recalibration data are within required limits Collected examination data and indications are properly
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recorded to permit accurate evaluation and documentation Evaluation of examination data was done by a Level II or
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Level III examiner The inspector noted that the core spray system loop B welds were ultrasonically examined using an examination frequency not specified in Appendix IX of Section III or in Section XI of the ASME Code.
The inspector discussed the item with licensee representatives and stated that such deviations are permitted by the code if justification for the deviation is provided or if the technique is demonstrated to be equivalent to or superior to comparable methods described in the ASME Cod '
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The inspector requested from the licensee documentation pro-viding justification for the use of 1.5 MHz or demonstration of equivalency of the method to that method described in the ASME Code.
The requested information was not available at the time of this inspection and the inspector stated that this item is considered unresolved pending availability and NRC evaluation of the re-quested documentation.
(78-35-01)
3.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. An unresolved item disclosed during the inspection is discussed.n Paragraph 2.b.
4.
Exit Interview The inspectors met with licensee rerresentatives (denoted in Paragraph 1) at the conclusion of the inspeccion on November 39, 1978.
The inspectors summarized the purpose and scope of the inspection and the findings.