IR 05000029/1978022
| ML19259B391 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/20/1978 |
| From: | Ebneter S, Sanders W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19259B390 | List: |
| References | |
| 50-029-78-22, 50-29-78-22, NUDOCS 7902090140 | |
| Download: ML19259B391 (3) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-29/78-22 Docket No. 50-29 License No.
DPR-3 Priority
--
Category C
Licensee:
Yankee Atomic Electric Company 20 Turnpike Road Westborough, Massachusetts 01581 Facility Name:
Yankee Atomic Power Plant Inspection at:
Rowe, Massachusetts Inspection conducted:
December 6-7, 1978 Inspectors: #f[
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W. F. Saiiders, Reactor Inspector date signed date signed date signed Approved by:
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t.bneter, Acting Lniet, t.ngineering d'a te 's i g ned Support Section #1, RC&ES Branch Inspection Summary:
Inspection on December 6-7, 1978 (Recor: No. 50-29/78-22)
Areas Inspected: Routine, unannounced inspection of inserviceexamination, activities, rrodification of post LOCA recirculation sy'sstem and eddy current examination of Steam Generator' tubes.
The inspection involved T2 ins'pector-hours onsite by one regional based NRC inspector.
Results:
Of the three treas inspected, no items of noncompliance or deviations were identified.
790209D/ft)
Region I Form 12 (Rev. A gil 77)
.
.
DETAILS 1.
Persons Contacted Principal Licensee Employees
- Mr. H. Autio, Plant Superintendent
- Mr. R. Aron, Technical Assistant Mr. S. Durfee, Maintenance Supervisor
- Mr. M. Ebert, Plant Reactor Engineer
- Mr. R. Larque, Operations Quality Assurance De9t.
Mr. J. Lance, NSD, ISI Coordinator
- Mr. R. Randall, Engineering Assistant
- Mr. L. Reed, Operations Quality Assurance Dept.
- Mr. J. Staub, Technical Assistant to Plant Superintendent
- denotes those present at exit interview.
2.
Scope Previous inspections made during this refueling outage covered the program, procedures, personnel qualifications and observation of the testing activities in progress.
This inspection was made as a followup inspection of the test results and evaluation of data prior to plant starcup.
These results will be finalized and submitted to the NRC in a formal report within 90 days.
3.
Pressure Retaining Weids An inspection was made to ascertain whether the data obtained were consistent with the minimum examination requirements as defined in the program developed by the licensee to comply with the requirements of the ASME B&PV Section XI Code,1974 edition through Summer 1975 Addenda.
The following items were inspacted:
a.
Examination results and data sheets 5.
Examination equipment data
- .
Calibration data records d.
Examination evaluation data e.
Records on extent of examination and exceptions f.
Identification of NDE material g.
Method, technique and extent of examinations comply with licensee program h.
Evaluation of examination data was done by Level II or Level III examiner.
No items of noncompliance were identifie.
.
4.
Steam Generator Eddy Current Test The MIZ Eddy Current System was used to inspect the No. I and No. 4 steam generators. This system uses eddy current as the probing media to measure variations in effective conductivity and/or permeability of the tube being tested.
This method was used to inspect all the available tubes to the extent possible through the U-bend and in the No.1 and No. 4 steam generator hot legs.
Of the tubes inspected in the No. 1 generator, 17 tubes had defect indications.
The defect indications are located 1/2" to 3" above the tube sheet and all originate from the 0.D. of the tubes.
The indications ran Forty-four (44)ged from 29% to 100% penetration of the tube wall.
tubes were inspected for sludge height.
Of the tubes inspected in No. 4 steam generator, 26 tubes have defect indications. The defect indications are located 1/2" to 27" above the tube sheet and originate on the 0.D. of the tubes.
One (1) defect indication was located between support plates and originated from the I.D. surface.
Defect indications ranged from 20% to 90% penetration of the tube wall.
Forty-nine (49) tubes were inspected for sludge height.
No items of noncompliance were identified.
5.
Exit Interview At the conclusion of the inspection on December 7,1978.a meeting was held at the site with representatives of the licensee. Attendees at this meeting included personnel whose names a're indicated in paragraph 1.
The inspector summarized the results of the inspection as described in this report.