IR 05000010/1976001
| ML20037A998 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/10/1976 |
| From: | Ledoux J, Lee E K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20037A997 | List: |
| References | |
| 50-010-76-01, 50-10-76-1, NUDOCS 8008280634 | |
| Download: ML20037A998 (4) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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REGION III
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Report of Construction Inspection IE Inspection Report No. 050-010/76-01'
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Licensee:
Commonwealth Edison 00:.:pany Post 0ffice Box 767 Chicago, Illinois 60690 Dresden Nuclear Power Station License No. DPR-2 Unit 1 Category: C Morris, Illinois Type of Licensee:
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Type of Inspection:
Special, Unannounced
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Date of Inspection:
January 27, 1976
/k(('.bv Principal Inspector:
E. W. K.
ee
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(Date)
Accompanying Inspectors: None Other Accompanyin P,e pn el: None El Af Reviewed By:
J. C. LeDoux a
g Section Leader
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(Date)
Projects
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,3008240
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."N SUMMARY OF FINDINGS
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Inspection Summary IL.pection on January 27, C'6- 01) : Review documents related to the repairs of steam drum safe-end.e and baseline UT reports of the 6" cleanup demineralizer and unicsding heat exchanger return line.
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Enforcement Items None identified.
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Other Sicnificant Items
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A.
Systems and Components The licensee discovered surface indication on safety valve nozzl,es No. 3, No. 4, No. 7, No. 8 and No. 9.
The indications were removed by grinding. UT and PT were perf ormed before and af ter grinding.
UT reports indicated that material. removed was between 0.020" to 0.106".
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B.
Facility Items (Plans and Procedures)
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None.
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C.
Managerial Items
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None.
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Noncompliance Identified and Corrected by Licensee
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None.
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E.
Deviations None.
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F.
Status of Previously Reported Unresolved Items Discrepancy Between 1971 Edition of the ASME Boiler and Pressure Code,Section XI and Technical Specification (IE Inspection Report No. 050-010/75-21)
This unresolved matter was not reviewed and the status remains unchanged.
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Management Interview
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A.
The following Commonwealth Edison Company (CE) personnel attended the management interview at the end of the insocction:
J. S. Abel, Administrative Assistant J. D. Eenigenburg, Engineer
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T. Watts, Technical Staff Supervisor.
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B.
Matters discussed and comments, on the part of the Management personnel were as follows:
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1.
The inspector stated procedures,' records relative to the repair of steam drum safe-ends and base line UT of the 6" cleanup demineralizer and unloading heat exchanger return line have been reviewed and they appear to be acceptable.
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The inspector stated that the previously reported unresolved item relative to the discrepancy between ASME B & PV code section XI and Technical Specification remains unchanged.
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REPORT DETAILS
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Persons Contacted The following Commonwealth Edison Company (CE) individuals, in addition to those listed under the Management Interview section of this report,
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were contacted duriag the inspection:
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R. C. Herbert, Technical Staff Engineer M. Wright, Q-C Engineer
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Results of Inspection
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The inspector reviewed the following documents and determined them to be acceptable and in accordance with the applicable code requirements:
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1.
Base line UT reports and calibration records of welds No.
FW-11247-4, No. FW-11247-3, No. FW-11247-2, No. FW-11247-1,
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No. SW-9652-7, No. SW-9652-8, No. FW-9652-9, FU-9652-3, No.
SW-9652-10, No. FW-9652-2, No. FW-9652-4 and No. FW-11247-8 in the 6" cleanup demineralizer and ' unloading heat exchanger return line.
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Work Request No. UR183 for the veld repair of No.1 (safety valve)
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nozzle safe-end of the prl=ary steam drum.
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Station Traveler for Work Request No. WR183 and final PT records.
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Work Request No.11959 for grind 'out of PT indications' on Safety 4.
Valve nozzles No. 3, No. 4,- No. 7, No. 8 and No. 9 of the primary steam drum.
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Station Traveler for Work Request No.11959, PT and UT measurement f
records.
CE Ultrasonic Procedure No. NDT-C-6, rev. 2 entitled " Ultrasonic 6.
Pulse Echo measurement of wall thickness of cast, forged and i
wrought carbon and stainless steel caterials."
Letters from CE's Station Nuclear Engineering Department dated 7.
28, 1976 and January 21, 1976 relative to stress January Calculations for the ' steam drum safety valve nozzle wall thickness and 6" unloader return line thermal sleeve.
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