IR 05000010/1975021
| ML19340A573 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 12/22/1975 |
| From: | Key W, Ledoux J, Eric Lee NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19340A572 | List: |
| References | |
| 50-010-75-21, 50-10-75-21, NUDOCS 8008280631 | |
| Download: ML19340A573 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report of Construction Inspection IE Inspection Report No. 050-010/75-21 Licensee:
Commonwealth Edison Company Post Office Eox 767 Chicago, Illinois 60690 Dresden Nuclear Power Station License No. DPR-2 Uni,t 1 Category: C Morris, Illinois Type of Licensee:
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Type of Inspection:
Special, Unannounced Dates of Inspection:
November 24, 25, 26 and December 15, 1975
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Principal Inspector:
E. W. K. Lee (Date)
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(Date)
Other Accompanying Personnel: None J.C.LeDou!'"**,,
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Reviewed By-Section Leader (Date)
Engineering Support
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S_U__MMARY ( " FINDINGS
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Inspection Summary Inspection on November 24, 25 and 26 and December 15, 1975, (75-21): '
Review ISI NDE records and six-inch cleanup demineralizer and unloading heat exchanger return line re-work NDE records.
Enforcement Items-None identified.
Licensee Action on Previousiv Identified Enforcement Items None.
Other Significant Items A.
Systems and ' Components 1.
Re-work on ehe'six-inch cleanup demineralizer and unloading heat exchanger return line of Loop A has been completed, except baseline ultrasonic examination of welds. A new
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thermal sleeve design was installed.
(Report Details, Paragraph 1)
2.
The licensee is preparing a final report on the flaw indication on the No. 6 (saf ety valre) nozzle of the primary steam drum.
This' report is scheduled for submittal to NRC for review on or before January 2, 1976.
B.
Facility Items (Plans and Procedures)
None.
C.
Managerial Items None.
D.
Noncompliance Identified and Corrected by Licensee None.
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Status of Previously Reported Unresolved Items
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Tapes used on stainless Steel Surface (IE Ins'pection Report No. 050-010/75-18)
As previously reported, the QC procedure was revised and was in printing.
During this inspection, the inspector reviewed Commonwealth Edison Company (CE) procedure No. DWP-1, Revision 0, dated November 1975, entitled " Packing, Receiving, Handling and Storage of Items in the Storeroom." The inspector noted that instructions to storeroom personnel relative to tapes suitable for use on stainless steel surfaces has been included.
This matter is considered resolved.
2.
Discrepancy Between 1971 Edition of the ASME Boiler and
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Pressure Vessel Code,Section XI and Technical Specification.
(IE Inspection Report No. 050-010/7 5-18)
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This unresolved matter was not reviewed and the status remains unchanged.
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Management Interview A.
The following Commonwealth Edison Company (CE) personnel attended the management interview at the end of the inspection.
J. S. Abel, Administrative Assistant G.'J. Harrison, Lead Engineer (Unit 1)
B. B. Stephenson, Station Superintendent B.
Matters discussed and comments, on the part of the >bnagement
personnel were as follows:
1.
The inspector stated that the flaw indication on the No. 6 (safety valve) nozzle of the Primary Steam Drum has been referred to NRR for resolution.
2.
The inspector reviewed the status of previously reported unresolved matters described in the Summary of Findings section of this report.
3.
The inspector stated procedures, records and personnel qualifications, relative to ISI and re-work of the six-inch
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line, have been reviewed, and they appear to be acceptable.
(Report Details, Paragraph 2)
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REPORT DETAILS Persons Contacted
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The following individuals, in addition to those listed under the Ibnagement Interview Section of this report, were contacted during the inspection.
Commonwealth Edison Company (CE)
R. C. Herbert, Technical Staff Engineer D. Flaxwell, QC Engineer Results of Inspection 1.
As previously reported, additional longitudinal cracks in the thermal sleeve, found af ter the replacement of portion of the six-inch clea~ up demineralizer and unloading heat exchanger n
return line of Loop A, were repaired. The licensee has replaced the cracked thermal s'leeve.
The design of the new thermal sleeve is thinner than the old one.
Ths six-inch schedule 80 pipe inserted into the 18" special cast elbow was. machined to 1/8 inch thick. The
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licensee's contractor is perforning a stress calculation of the new design and will be finished prior io startup.
2.
The inspector reviewed the following documents and determined them to be acceptable and in accordance with the applicable cede requirements:
a.
Work Request No. WR 11247 dated November 10, 1975, for the re-work of the six-inch cleanup demineralizer and unl'oading heat exchanger line, b.
Station' Traveler for Work Request No. WR 11247.
c.
All PT records on the re-work of the six-inch cleanup deminerali:er and unloading heat exchanger line, d.
Twenty (20) Phillips Getschew welders' qualification records, e.
bbterial certification of 8" schedule 160 pipe with heat No. X90568.
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Material certification of a 6" schedule 80 90 elbov vith heat No. JFBW.
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}bterial certification of ER 308L electrode with heats No. 402188 and No. 13200.
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Material certification of E308L-16 electrode with heats
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No. 336153, No. 546156 and No. 64863.
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Material certification of 6" schedule 80 consumable insert rings with heat No.-ARCOS-1966T 308L.
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Material certification of 10" schedule 80 consumable insert rings uith Hers No. ARMCO-03403'..
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Radiographic filra of final welds No. FW4, No. SW8, No. SW2, FWl-R2 of the re-work on the six-inch cleacup demineralizer
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and unloading heat exchanger line.
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ISI ultrasonic examination and liquid penetrant rcccrds of steam drum nozzle and safe ends welds for Nozzles No.1,
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No. 4, No. 6 and No. 10.
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ISI visual examination records of hangers No. H-4-A and B Loop. item 4.6, No. H-10-A and B Loop item 4.6, No. H-19-B Loop and No. H-3-D Loop.
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ISI ultrasonic" examination records of six-inch unloader
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system welds No. F9, No. 76, No. 3795 and No. SS398.
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CE Procedure No. NDT-C-18, Revision 0, entitled, " Ultrasonic
Evaluation of Reflectors in Vessel Welds."
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Material certification of UT calibration block S/N 99996.
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Heat treating procedure No. M-2288-75 dated November 26, 1975, j
and Heat treating record for calibration block S/N 99996.
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Nuclear ~ Service Corporation, level I and II inspection
personnel rec ords.
3.
The inspector observed portion of the UT Mapping of the No. 6
(Safety valve} nozzle of the primary steam drum and determined method and transducers used were in accordance with specification.
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