IR 05000410/1979008
| ML17053B364 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/06/1979 |
| From: | Mcbrearty R, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053B363 | List: |
| References | |
| 50-410-79-08, 50-410-79-8, NUDOCS 8001310326 | |
| Download: ML17053B364 (6) | |
Text
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NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
I Report No..
79-08 Docket No.
50-410 License No.
CPPR-112 Priority Category Licensee:
Nia ara Mohawk Power Cor oration 300 Erie Bou'levard West S racuse New York 13202 Facility Name:
Nine Mile Point Nuclear Station Unit 2 Inspection At:
Scriba New York
.Inspection Conducted:
November 6-8 1979 Inspectors:
4 idi.
" R.
A. McBrearty, React r Inspector date date date Approved by:
.
E. Trip
, Chief, Engineering Support Section No. l,,
RC&ES Branch date Ins ection Summar
Ins ection on November 6-8 1979 Re ort No. 50-410/79-08)
P'd'PdP of reactor pressure vessel from barge to storage area including observation of work in progress; review of gA implementing. procedures and review of quality records associated with certification of lifting and transporting equipment.
The inspection involved ll inspector-hours onsite by one regional based NRC inspector.
Results:
No items of noncompliance or deviations were identified.
Region I Form 12 (Rev. April 1977)
aM
DETAILS 1.
Persons Contacted Nia ara Mohawk Power Cor oration S.
E.
Czuba, Associate gA Engineer
"J.,
L. Dillon, gA Engineer
"R. A. Norman, Senior Site gA Representative
~R.
L. Patch, Associate gA Engineer Denotes those present at the exit interview.
2.
Reactor Pressure Vessel The Nine Mile Point Unit 2 reactor pressure vessel was delivered by barge to the Power Authority of the State of New York (PASNY) barge slip on Lake Ontario approximately one mile from the Niagara Mohawk Power Corporation onsite storage area.
The inspector'reviewed procedures and records associated with off-loading and moving the reactor vessel from the barge to the onsite storage area, and observed a portion of the work in progress.
The inspector's review included the following gA documents:
Stone and Webster (S&W) Specification No.
NNP2-S204Z, Revision 1, entitled "Specification for Rigging of the Reactor Pressure Vessel, Biological Shield Mall and Primary Containment Liner" S8M Procedure No. MP"04, Revision 4, entitled "Off-Loading RPV from Barge and Setting Into Storage" Rigging International (RI) Procedure No. TP-01, Revision 3, entitled
"Field Testing; Load Test the Jacking Frame and Box Girders" RI Procedure No. TP-02, Revision 0, entitled "Field Testing; Load Test the Jacking Bars" Drawing No. 980-3, Revision
Drawing No. 980-4, Revision
Drawing No. 980-5, Revision
Drawing No. 980-8, Revision
Drawing No. 980-9, Revision
Drawing No. 980-10, Revision 1 RI gA Report, dated 9/27/79, File No. A-77-387-980-21 S&W gA Inspection Report (/AIR) No. M9000114, dated 10/19/79 S&W /AIR No. M9000115, dated. 10/20/79 S&W /AIR No. M9000116, dated 10/21/79 S&W /AIR No. M9000117, dated 10/21/79 S&W /AIR No. M9000122, dated 10/23/79 Certificate of Compliance for Lampson CT-600 Series Crawler Transporter, Units 015 and 016 At the time of this inspection, preparations were in progress for placing the reactor vessel on the transporter crawler.
These activities included reinforcement of the road surface along the route of travel in order to facilitate the move.
Criteria governing the handling of the reactor vessel were found in the S&W Procedure No. WP-04, Revision 4, entitled "Off-Loading RPV from Barge and Setting Into Storage."
The inspector found that the required load tests and inspections were performed on the appropriate equipment and the work in progress was performed in accordance with approved procedures.
The estimated time o'f arrival of the reactor vessel at the storage area was delayed due to deteriorating weather conditions which precluded the vessel move as scheduled.
At the time of the exit interview the vessel was still at the barge slip area.
In a subsequent telephone conversation on November 15, 1979, Mr.
R.
Norman, licensee representative, informed the'inspector that the reactor vessel had arrived, without incident, at the onsite storage area.
No items of noncompliance were identified.
3.
Exit Interview The inspector met with licensee representatives (denoted on Paragraph 1)
at the conclusion of the inspection on November 8, 1979.
The inspector summarized the purpose and scope of the inspection and the finding ti