IR 05000320/1979018
| ML19308B323 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/18/1979 |
| From: | Jernigan E, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19308B319 | List: |
| References | |
| 50-320-79-18, NUDOCS 7912280392 | |
| Download: ML19308B323 (5) | |
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O U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report No.
79-18 Docket No.
50-320 License No.
CPR-73 Priority Category C
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Licensee:
Metropolitan Edison Company 260 Cherry Hill Road Parsippany, New Jersey 07054 Facility Name:
Three Mile Island, Unit 2 Inspection At:
Middletown, Pennsylvania Inspection Conducted:
July 5-6, 11-13, 1979 Inspectors:
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/d//f[79
. P. Jernigad( Reactor Inspector
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'date date date Approved by:
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N
/OMf/7f L'. E. Tripp(' Chief, Engineering Support fdate
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Section No. 1, RC&ES Branch Inspection Summary:
Inspection on July 5-6, 11-13, 1979 (Report No. 50-320/79-18)
Areas Inspected:
Special, announced inspection by a regional based inspector of modifications being performed of various systems to provide long-term cooling of the reactor core.
This inspection was of the licensee and his contractor's acti-vities associated with these modifications being made under emergency conditions.
The inspection involved 39 inspector-hours on site by one regional based inspector.
ResulM:
No items of noncompliance with regulatory requirements were issued.
Region I Form 12
,9 912 280 3%g (Rev. April 1977)
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DETAILS 1.
Persons Contacted General Public Utilities (GPU)
J. Wright, Quality Assurance Site Manager J. Artuso, Consultant S. Levin, Project Westinghouse P. Cowfer, Quality Control Engineer W. Meyers, Quality Control Manager In addition to the above, the inspector contacted several other licensee and contractor personnel.
2.
Systems (s) Modifications As a result of the March 28, 1979 incident at TMI-2, the licensee initiated modifications to several systems at the affected unit.
These modifications are being made to provide long-term cooling capability of the reactor core, including a redundant (alternate) decay heat removal system.
The inspector performed a cursory review of the licensee's QA program and the major subcontractor's QA involvement for the system modifications.
These programs recognize the uniqueness and urgency for early completion of these modifications and provide for flexibility to accomplish the task.
Where quality standards cannot be achieved, these events will so be documented by the licensee and subjected to final disposition regarding their acceptability.
A description of modifications and applicable codes are identified in I&E Inspection Report Nos. 50-320/79-09 and 50-320/79-12.
This report covers the surveillance activities by the Reactor Construction and Engineering Support Branch of Region I.
3.
Redundant Decay Heat Removal (DHR) System (TS-15) Inspector Surveillance The inspector examined the DHR system which was in a temporary storage area. The inspector observed that associated electrical equipment was provided with energized heaters.
Also, final piping activities were in progress completing the system in preparation for installation.
The inspector examined the following activities relative to this installatio J
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Examined in: illed penetration module
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Jitnessed pipe welding activities associated with connecting piping
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Audited pipe welding procedures, procedure and weldor qualification
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records Audited field radiographs, procedures and personnel qualification
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recorde Audited material certification and data related to the penetration
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module assembly and associated connecting piping Reviewed WNSD-TMI-1, Revision 2, procedure titled " Installation of
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Alternate Decay Heat Removal System" Examined (via TV camera) the weldolet installation inside the auxiliary
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building Audited radiographs of weldolet to pipe attachment welds
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Audited ultrascnic examination data of weldolet to pipe attachment
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welds Reviewed procedures and records for control of cutting into existing
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DHR system pipes Reviewed arrangement drawing WTM-1-1088-2, for DHR, valve pit and
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associated piping Audited pipe supplier data packages and shop radiographs for selected
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pipe spool assemblies The inspector informed I&E site management of the inspection / modification status.
4.
Exit Meeting During this inspection the inspector met daily with the GPU Quality As-surance Site Manager and discussed the important aspects of the ongoing modifications.
However, due to the ongoing nature of the modification
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program no formal exit meeting was hald.
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