IR 05000278/1979029
| ML19257C924 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/12/1979 |
| From: | Jernigan E, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19257C920 | List: |
| References | |
| 50-278-79-29, NUDOCS 8001310087 | |
| Download: ML19257C924 (5) | |
Text
U.S. i4UCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-278/79-29 Report No.
50-278 Docket No.
C DPR-56
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License No.
pggg Philadelphia Electric Company Licensee:
2301 liarket Street Philadelphia, Pennsylvania 19101 eat mA m c Power Madon Unit 3 Facility Name:
Inspection at: Delta, Pennsylvania Inspection condu ed:
ober 16-19, 1979
[. O M
/3//2/79 Inspectors:..-
M. P. Jerdifjan, Reactor Inspector date signed
/
date signed date signed Approved by:
.k M
/3//9[79 OL. E. Tripp/ Chief, Engineering date signed Section flo.1, RC&ES Branch Inspection Summary:
Inspection on October 16-19,1979 (Report flo. 50-278/79-29)
Areas Inspected:
Routine, unannounced inspection by a regicnal based inspector of the licensee's inservice inspection (ISI) program and related nondestructive examination (NDE) activities. Also, reviewed documentation associated with capping of the control rod drive hydraulic (CRD) return line nozzle.
The inspection involved 27 inspector hours by one NRC regional based inspector.
Results:
flo items of noncompliance with regulatory requirements were identified.
1843 086 Region I Form 12 (Rev. April 77)
8001310 087
DETAILS 1.
Persons Contacted Philadelphia Electric Company _
- W. T. Ullrich, Station Superintendent
- W. G. MacFarland, Construction Engineer
- T. C. Hinkle, ISI Engineer J. Madara, ISI Supervisor T. Anderson, ISI Engineer General Electri: Company (I&SE)
- J. S. Taylor, QA/QC Supervisor Hartford Steam Boiler
- K. S. Russell, Authorized Inspector
- Denotes those present at the exit meeting.
2.
Inservice Inspection (ISI) Program a.
Scope of ISI Interval The inspector audited the licensee's schedule of nondestructive excminations (NDE's) to be performed during the 1979 refueling outage. The audit was performed to determine whether documents establish requirements consistent with those of the 1974 edition of Section XI, including the Summer 1975 Addenda of the ASME Code.
The following documents were audited to ascertain compliance with the above requirements:
Inservice Inspection Program for Peach Bottom Unit 3
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SwRI, Nuclear Quality Assurance Program Manual
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Plan for 1979 Inservice Examinations
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SwRI Nuclear Quality Assurance Procedures Manual
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The inspector determined that:
1) these documents contain provisions and requirements for the administration, control and execution of the examinations which are scheduled to be conducted during the 1979 refueling outage; 2) the implementing procedures had been approved by the licensee; 3) the ISI program and the contractor's QA manual delineates the administrative and organizational responsibilities and 1843 087
defines the duties of the examiners; 4) audits, including frequency, criteria, basis for re-audit, management review and assessment, cor-rective action and followup and documentation of results as defined; and, 5) implementing procedures are provided for activities to be performed and are reviewed, approved, controlled and accessible to examiners implementing these procedures.
Procedures are also estab-lished for identification and correction of conditions adverse to quality.
The examinations scheduled to be accompli aed during this refueling was audited and found to be consistent with the ISI program.
No items of noncompliance with regulatory requirements were identified.
b.
NDE Procedures The inspector audited selected implementing NDE procedures for tech-nical adequacy and compliance with requirements of the applicable code.
The procedures audited included:
SwRI - NDT-200-1 Revision 47, dated July 1979
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SwRI - NDT-600-3 Revision 53, dated July 1979
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SwRI - NDT-900-1 Revision 46, dated July 1979
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SwRI - NDT-700-5 Revision 1, dated July 1979
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Sw3I - NDT-800-36 Revision 24, dated July 1979
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The above procedures were found to be consistent with requirements of the ISI program and Section XI of the ASME Code referenced therein.
No items of noncompliance with regulatory requirements were identified by the inspector.
c.
Data Review The inspector audited preliminary data sheets to ascertain; 1) per-formance of examinations by properly certified personnel; 2) equipment calibration / checks performed periodically; 3) use of specified equip-ment; and, 4) recorded examination data sufficient to provide adequate basis for evaluation.
The inspector found that the selected records contained examination results including method and extent of examiration coverage, equipment calibration sheets, indication evaluation data and disposition of results, equipment data (calibration and certification) and identifi-cation / certification of NDE material.
The recorded data is consistent with procedural requirements.
No items of noncompliance with regulatory requirements were identified by the inspector.
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3.
Control Rod Drive (CRD) Hydraulic Return Line Modification During the current refueling outage the licensee modified the CRD hydraulic system. The modification involvec' cutting and capping the CRD return line at the containment penetration and the reactor pressure vessel nozzle.
The NSSS contractor (GECo.) issued FDI-127 Revision 0, dated 1978 setting forth requirements for the elimination of the CRD hydraulic system return line.
The change in the CRD system piping and operation are necessary to eliminate CRD return line flow and thermal duty on the reactor pressure vessel. These are discussed in Contractor Documents AID 45-77 and Supple-ment 2 of 31L-200.
The inspector audited documentation associated with this modification to determine compliance with requirements established in the aforementioned document.
Included in this audit were the following:
specification SPPB No. 3, CRDN, Revision 2, 9/25/79
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FDI-126, dated February 13, 1978
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I&SE 18XA9404, Revision 0,
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traveler PB-CRD-R-I cap forging material certification
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filler metal certification
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process control sheet PB-CRD-NT 3/8
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procedure 18XA9602, Revision 2 I&SE-GWP-N-F1, Revision 2
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The above provide documentary evidence that work was accomplished in accordance with the 1974 Edition of Section XI and Section III and Summer 1975 and 1976 Addenda respectively of the ASME Codes.
However, radio-graphs evidenced an apparent repair of the cap to nozzle weld.
Further review disclosed that during welding operations approximately 1.5 inches of the root area and the consumable insert had been removed and subse-quently rewelded.
This was a through wall excavation resulting in a por-tion of the weld being of an open-butt configuration. Weldor qualifica-tion records did not substantiate that the weldor had been qualified using an open-butt weld joint.
Section IX of the ASME Code permits a weldor to qualify using radiography. The contractor had procedures to accomplish this and were consistent with applicable Code requirements.
This had not been documented at the close of the inspection.
This item is considered unresolved pending a review of pertinent documentation during a subsequent NRC inspection.
(79-29-01)
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4.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable itemt, items of noncompli-ance or deviations. An unresovled item disclosed during the inspection is discussed in Paragraph 3.
5.
Exit Interview At the conclusion of the inspection on October 19, 1979 a meeting was held at the site with representatives of the licensee. Attendees at this meet-ing included personnel whose names are indicated by an asterisk in Para-graph 1.
The inspector summarized the results of the inspection as des-cribed in this report. Mr. E. G. Greenman, the resident NRC inspector also attended this meeting.
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