IR 05000320/1976002
| ML19220C345 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 03/05/1976 |
| From: | Haynes R, Sanders W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220C341 | List: |
| References | |
| 50-320-76-02, 50-320-76-2, NUDOCS 7904300456 | |
| Download: ML19220C345 (6) | |
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E:I Form 12 Qan 75) (Rcv)
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G. S. NUCLEAR REGULATORY CC'tilSSION
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OFFICE OF INSPECTION AND ENFORCDiD;T
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REGION I
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IE Inspection Report No:
50-320/76-02 Docket No:
50-320
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Licensee:
Metropolitan Edison Cocoany License 'No: CPPR-66
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~~P.' O. Box 542 Priority:
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Reading, Pennsylvania 19603 Category:
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Safeguards
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Middletown, Pennsylvania (Three Mile Island 2)-~
Location:
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'ype of Licensec:
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t Routine - Unannounced Type of Inspection:
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Dates of Inspection:
January 27-30, 1976
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Dates of Previous Inspection:
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Repo' ting Inspector:
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W. F. Sanders, Peactor Inspector None Accompanying Inspectors:
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None Other Acccupanying Personnel DATE
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'k.Leviewed By:
e R. C. Haynes, Sec on Leader
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SUMMARY OF FINDINGS _
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Enforcement Action
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None
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Licensee Action on Previousiv Identified Enforcement _ Items
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Not Inspected Design Chances _
Not Applicable
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Unusual Occurrences
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None Other Significant Findings
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Current Findin g
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Acceptable Areas
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of Reactor Pressure Vessel Internals _
Cleati Areas for Assembly a.
An it spection was made of the Reactor Vessel internals the work in progress and the
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assenbly areas to inspect implementation of the Cleanliness Control Procedure 9A-li 7 /C6.
(Details, Paragraph 2)
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Proce dures f or Reactor Pressure Vessal' Internals, b.
An ir spection was made of six (6) procedures which are written to control ;;he work activities relative to assembly, recef ving, unloading, handling, placement,
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velding, visual inspection and cleanliness control.
(Details, Paragraph 3)
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_ Unresolved item _
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f Accountability of Spacer Shi=s Used during Shioment of Reactor Internals.
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, Spacer shims used on the Plenum assembly shipping container
were not accour.ted for prior to the final assembly of the
internals.
This has resulted in a completed assembly with the
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contractor unable to account for two (2) of the shims.
The problem has been identified on DR555.
An additional inspec-tion is planned by licensee.
(Details, Paragraph 4)
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Status of Previousiv Reported Unresolved Items Not Inspected C.
Deviations
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None
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Managenent Interview At the end of the inspection a meeting was held at the site with the following people. The listed items were discussed and acknowledged by the licensee's representative.
General Public Utilities Service Corporation - CPUSC
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R. F. Fenti, Quality Assurance Auditor S. levin, Project Engineer C. L. Rosby, Quality Assurance Engineer H. J. Strorberg, Quality Assurance Auditor United Engineers and Construction - UE&C J. Carrabba, Construction Qun"4ty Control Supervisor
- Burns & Roe - B&R
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F. I. Pindar, Jr., lead Quality Assurance Engineer
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Babcock and Wilcox - B&W Co.
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R. Kunz, Q.C. Supervisor B. E. Treadway, Project Manager
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A.
Scope of Inspection
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The inspector stated that the purpose of this trip was to inspect
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the completed work and the work in progress on the Reactor Pressure Vessel internals assembly and to inspect the implementation of the
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the various procedures used to control the activities throughout stages of work.
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B.
Clean Areas for Assembly of Reactor Pressure Vessel Internals An inspection was made of the clean room assembly areas relative to the implementation of cleanliness control procedure 9A-127/C6.
No items of noncompliance were identified.
(Details, Paragraph 2)
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Procedures for Reactor Pressure vessel Internals An inspection was made of six (6) procedures which are used to control the work activities throughout the period of receiving inspection, unloading, handling, placement, asse=bly, welding, visual inspection and cleanliness control.
No items of nonco=-
pliance were identified.
(Details, Paragraph 3)
of Reactor Internals _
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c'e'ountability of Spacer Shims' Used Durina; Shipment
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The inspector stated that he was informed of two (2) shims approx-imately 2"x4" used in the Plenum Assembly shipping container which could not be accounted for, and that the licensee's representative had issued DR555 to identify tl.e problem and specify actions to resolve the problem. The inspector stated that a review of the working procedures showed that the words in the procedure, if
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followed as written, could have precluded the search of the final assembly. This item is considered unresolved.
(Details, Paragraph 4)
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DETAILS
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Persons'Coatacted
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R. Fenti, GPUSC - QA Auditor
S. Icvin, GPUSC - Project Engineer
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W. Cunn, GPUSC - Project Manager O. Roshy, GPUSC - QA Engineer M. Stromberg, GPUSC - QA, Auditor J. Carrabba, UESC - Construction QC Supervisor F. Pindar, Jr., B&R - lead QA Engineer R. Kunz, B&W - Project Manager B. Treadway, B&W - Project Manager D. Usher, B&W - Field Supervisor R. !! app, B&W - Inspector J. Downey, B&W - Inspector Clean' Areas for Assembiv of Reactor Pressure Vessel Internals 2.
A visual inspection was made of the clean room assembly area for the reactor pressure vessel internals and an inspection of the work in progress which consist of permanently locating the lower keys.
The overall clean room structure, personnel entry control, tool and equipment control, and use of protective clothing were inspected to No items of the requirements of 9A-127/C6 - Cleanliness Control.
noncompliance were identified.
- Prdced'ures' for Reactor Pressure Vessel Internals 3.
The procedures listed below which are used to control the activ-ities affecting quality through receiving, handling, storage,
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assembly, placement, welding and cleanliness control were inspected for compliance to the FSAR and the applicable codes."'No
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items of noncompliance were identified.
9A-127/6C - Cleanliness Control
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F.Q.C. 245 Rev. 2 - Unloading and Temporary Storage of R.P.V.
Upper Internals F.Q.C. 244 - Transport and Placement of R.P.V. Internals 7.Q.C.'86 - Installation of R.P.V. Internals
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VIN 219-2/C6 - Weld Procedure 9T-191/C6 - Visual Inspections
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of Reactor Internals __
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[ Accountability'ofSpacerShimsUsedDurineShipment Procedure P.Q.C. 245 Rev. 2 states, " Remove, collect and inventory
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all foreign objects that were attached to or temporarily installed
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in or around the plenum assembly for shipping aids".
The Core
Support Shield, which is the mating piece, has the same require-
- ment. Prior to assembly of the two parts, Seq. 2.27.1 states, "At this time Q.C. shall compare the inventory list of foreign objects for the Plenum Assembly and the inventory list of foreign objects for the Core Support Shield with the documented installation records sent with the internals container.
These two sets af records must be in total agreement with all foreign objects..
accounted for."
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This activity was not performed until af ter the assembly was com-pleted. When the inventory lists were compared it was determined that the 25 shims were listed on the packing list as being installed and the receiving records indicated that 23 shi=s were found.
DR
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--- requ.i.re. s co.rrective actions prior to final sign-off by QC.
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The inspector was informed that a thorough inspection is planned after the assembly is placed in the Reactor Pressure Vessel and the upper plenum assembly is removed.
This vill make the internals more accessible for the search. DR #0555 was issued by UE&C which documented the missing shims and requires corrective actions prior
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to final sign-off by QC.
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This item is unresolved.
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