IR 05000309/1970007
| ML19209C588 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 07/11/1979 |
| From: | Durr J, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19209C581 | List: |
| References | |
| 50-309-79-07, 50-309-79-7, NUDOCS 7910160180 | |
| Download: ML19209C588 (3) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-309/79-07 Docket No. 50-309 License No. DPR-36 Priority:
Category:
C
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Licensee:
Maine Yankee Atomic Power Company 20 Turnpike Road Westborough, Massachusatts Facility Name:
Maine Yankee Nuclear Power Station Inspection at:
Wiscasset, Maine Inspection conducted:
June 4-6, 1979 D
/ l
<,xx),,h4a f//// >9 Inspectors:
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J. P. Durr, Reactor Inspector Mte / signed Approved by: %IWYL Z J.f CAo
> //i /19 L. E.~Tripp, Chief, Engineering date siigned Support, Section No. 1, RC&ES Branch Inspection Summary:
Inspection on June 4-6, 1979 (Report '!o. 50-309/79-07 Areas Inspected:
Routine, unannounced inspection by a regional based inspector of licensee activities relative to IE Bulletin 79-02.
The inspection involved 16 inspectors-hours on site by one NRC inspector.
Results:
No items of noncompliance were identified in t.he one area inspected.
1147 353
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7910160;ffO
-2-DETAILS 1.
Persons Contacted Maina Yankee Atomic Power
- P. Anderson, Administration Department Head
- M.
David, Training Supervisor
- C. Frizzle, Assistant Plant Manager
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- J. Hebert, Plant Engineering and QA Group Head
- S. Sadosky, QC and Audit Coordinator
- M. Veilleux, Mechanical Engineer Yankee Atomic Electric Company S. Chi,n, Mechanical Engineer
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J. Lance, NDE Engineer, Level III
- T. Rennell, Engineer
- Denotes those persons present at the exit..iterview.
2.
Review of Bulletin 79-92 Activities The purpose of this inspection was to review the licensee's activities concerning IE Bulletin 79-02.
The licensee stated that approximately 300 pipe >upports, for 2 " diameter piping and greater, are involved in the anchor bolt testing program.
At the time of this inspection, 14 of the pipe supports had been tested and the facility was returning to power operation.
The testing was proceeding with pipe supports accessible during operations.
The inspector reviewed the procedure No. 4-41, Revision No. 1, titled, " Verification of Correct Installation and Design Load of Embedded Concrete Anchors." The following items were identified:
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The preload torque values are based on calculations by the licensee and are not substantiated by test data.
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The procedure test program does not address the cyclic load requirement of Bulletin 79-02, Paragraph 4.(a).
There is no definitive acceptance criteria for determining
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the difference between a "Phillips Red Head" and a " Star Slugin" anchor when the bolt or stud cannot be removed.
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There is no acceptance criteria to identify slippage of the anchor during torquing.
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-3-The licensee stated that the foregoing items would be reviewed and addressed as necessary in a revision to the procedure.
These items are unresolved pending revision of the procedure or other appropriate actions and review by the NRC (309/79-07-01).
During the review of supplemental information, a discrepancy between the " Star Slugin" manufacturers recommended shear load values and the Stone and Webster specification data was noted.
Stone and Webster Stanuard, STD-FC-7A3, titled " Details-cinch anchors," appears to allow less conservative shear values for sizes 5/8" diameter and larger, than the manufacturer.
TP's item is unresolved pending further evaluation by the licensee.ad review by the NRC (309/79-07-02).
The inspector observed the testing of base plate anchor bolts using the foregoing procedure.
He verified the bolt torque using the licensee's calibrated torqua wrench and that the test was performed in accordance with tb procedure.
No items of noncompli-ance were identified.
The inspector noted what appeared to be cracks in the welds on pipe restraint H-72A and H-75 in the Secondary Component Cooling Water piping system.
It also appears that the base plate to side plate weld on restraint H-72A is not full length.
This item is unresolved pending evaluatien and correction by the licensee and review by the NRC (309/79-07-03).
3.
Unresolved Items Unresolved items are matters about which more information is required to ascertain whether they are acceptable items, items of noncompliance, or deviations.
Unresolved items disclosed during the inspection are discussed in Paragraph 2.
4.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on June 6, 1979.
He summarized the scope and findings of the inspection.
,