IR 05000313/1973016
| ML19317H073 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/09/1973 |
| From: | Brownlee V, Crossman W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317H070 | List: |
| References | |
| 50-313-73-16, NUDOCS 8004110845 | |
| Download: ML19317H073 (6) | |
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UNITED STATES o
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q ATOMIC ENERGY COMMISSION l(.* <
l DIRECTORATE OF REGULATORY OPERATICNS l
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REGeoM li - Sus T E 818 230 PE ACMT R E E ST RE ET, NORT HWEST 34rg5 O*
7 t u mn: Muumn AT L. A NT A. G E oHG a A 30 M 3 RO Inspection Report No. 50-313/73-16 Licensee:
Arkansas Power and Light Company Sixth and Pine Streets Pine Bluff, Arkansas 71601 Facility Name: Arkansas Nuclear One, Unit 1 Docket No.:
50-313 License No.:
CPPR-57 Category:
A3/B1 Location: Russellville, Arkansas Type of License: B&W, PWR-2568 Mwt, 880 Mwe
)j Type of Inspection: Special, Announced, Construction Dates of Inspection: October 23-26, 1973 Dates of 2revious Inspection: September 11-14, 1973 and September 25-28, 1973 Inspector In Charge:
A. R. Herdt, Metallurgical Engineer Engineering Section
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Facilities Construction Branch Accompanying Inspectors: None Other Accompanying Personnel: None Principal Inspector:
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N V. L. Brownlee, Reactor Inspector Date Facilities Section, Facilities Construction Branch Reviewed by:
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W. A. Crossman, Senior Inspector Date Facilities Section, Facilities Construction Branch n
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SUFDfARY OF FINDINGS 1.
Enforcement Action
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Violations None B.
Safety Items None II.
Licensee Action on Previously Identified Enforcement Ifatters A.
Violations None B.
Safety Items None b)
III. New Unresolved Items
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73-16/1 Radiography Review The licensee agreed to review for weld acceptability and radiographic quality the radiographs for reactor building spray system spool pieces BS-HCB-A6-33 and BS-HCB-A4-32 and field weld HCB 6-8.
(Details I, paragraph 3)
IV.
Status of Previousiv Reported Unresolved Items
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72-12/2 Valve Wall Thickness Veri 1 cation (Region II Letters, June 30, 1972, and February 16, 1973)
The draft of the valve wall thickness verification program report was presented for review. The program and documentation was found to be incomplete. Thickness measurements were not made of valve bonnets and covers or all weldend preparation. This item remains open.
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Design Changes
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None
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VI.
Unusual Occurrences
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VII. Other Significant Findings A. Project Status None
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Personnel or Organizational Changes None C.
Inquiry Reports
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None VIII. Management Interview I
Our findings were discussed at the conclusion of the inspection with Mr. Moore, Chief QA Coordinator.
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RO Rpt. No. 50-313/73-16 I-l
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DETAILS I Prepared by:
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A. R. Herdt, Metallurgical Engineer ID' ate Engineering Section Facilities Construction Branch Dates of Inspection: October 23-26, 1973 Reviewed by:
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/ C'. B ryan t, Senior Inspector Date A ngineering Section Facilities Construction Branch 1.
Persons Contseted a.
Arkansas Power and Light Company (AP&L)
N. A. Moore - Chief Quality Assurance Coordinator C. L. Bean - Quality Assurance Inspector b.
Contractor Organizations Bechtel Corporation (Bechtel)
W. D. Schuster - Senior Field Welding Engineer P. W. Sly - Project Field Quality Control Engineer Babcock and Wilcox Construction Company (B&W)
F. J. Sattler - Manager, Inservice Inspection
2.
Preoperational (Raseline) Inspection Program Review According to the FSAR, the reactor coolant pressure boundary inservice inspection program is to be in accordance with Section XI of the ASME Boiler and Pressure Vessel Code,1971, including the 1971 winter addenda.
Prior to initial unit operation, B&W is performing the required non-destructive examination (NDE) of reactor coolant system pressure boundary welds to establish preoperational integrity and baseline data for future inspections. B&W reported that the required in-spections are complete except for the coreflood piping, decay heat removal crossover piping modification and the reactor vessel where the remote ultrasonic tool will be used.
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B&W has not completed its evaluation of all the indications found; however, one proble.' area on primary piping was identified.
In-dications were noted 'n MK39, a 74* 30' elbow in the outside seam of the lAl discharge line (reactor inlet line). The indications were detected by longitudir il beam normal to the pipe surface, which is the most likely method to find laminar types of indications. Angle beam showed nothing reportable and fabrication radiographs were reviewed as well as new radiographs taken in the suspected area.
After plotting and review of the ultrasonic and radiographic test results, B&W resolved the indications as laminations in the pipe.
The inspector reviewed the NDE procedures to be used for the baseline inspection and no discrepancies were noted. The inspector stated that a review of all the baseline inspection data, including the remote UT tool data used on the reactor vessel, would be required by RO prior to licensing. The licensee agreed to keep RO informed as to when the remaining baseline inspection would be performed so that this could be witnessed by the inspector.
3.
Followup Record Review of Welding and Nondestructive Testing The inspector conducted a walkthrough inspection of completed weld (' 'N joints on the decay heat removal crossover modification located in s
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the reactor building as well as the reactor building spray system, t
makeup and purification system, and decay heat system all located in the auxiliary building. Contour and weld profile appeared adequate except for the velds in the reactor building spray system, as noted below, and there were no indications of are strikes or weld splatter.
The inspector reviewed Bechtel's recordt of QC inspection of welding on the above mentioned systems. In order to test Bechtel's quality
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control records for completeness and accuracy, the inspector selected the following list of field welds during a visual inspection of welded joints:
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Decay Heat Removal Cross Over Modification (1) Iso. No. 7DH-23 Rev 3 Field Welds: CCB1-30, 1-33, 1-5N, 1-5M, 1-37 (2) Iso. No. 7DH-22A Rev 3 Field Felds:
CCB1-17,1-29,1-14C,1-25, CCA6-17 J
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Letter to Arkansas Power and Light Company dated ggy., y p.,,,
50-313/73-16 DISTRIBUTION:
D. Thornburg, R0 RO:HQ (h)
Directorate of Licensing (h)
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DR Central Files J. R. Lundy, L
- PDR
- Local PDR
- NSIC
- DTIE, OR
- State
- To be dispatched at a later date.
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