IR 05000364/1978016
| ML20204D234 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/30/1978 |
| From: | Hunt M, Wright R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20204D216 | List: |
| References | |
| 50-364-78-16, NUDOCS 7812110313 | |
| Download: ML20204D234 (5) | |
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e UNITED ST ATES
[pu alcq*'o, NUCLE AR REGULATORY COMMISSION
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'e REGION 11
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101 M ARIETT A sTRE E T, N.W 2-
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gs.....f Report No.-
50-364/78-16 Docket No.-
50-364 License No.
CPPR-86 Category:
A2 Licensee:
Alabama Power Company P. O. Box 2641 Birmingham, Alabama 35291 Facility Name Joseph M. Farley Plant, Unit 2 Inspection at:
Ashford, Alabama inspection Conducted:
October 17-20, 1978 Inspectors:
M. D. Hunt R. W. Wright
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~ a Reviewed by:
A. R s' Herdt, Chief
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,1)a te Projects Section Reactor Construction and Engineering Support Branch Inspectior. Summary l_nspection on October 17-20, 1978 -(Report No. 50-364/78-16)
Areas inspected:
Cable tray supports, conduit and electrical channel i
supports, warehouse storage, licensee identified iten, IE bulletins and circulars, and unresolved items.
This inspection involved 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> by two NRC inspectors.
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Results:
No items of noncompliance er deviation were identified.
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V RII Rpt. No. 50-364/78-16-1-DETAILS I Prepared by:
/2 ) 2 - l) < s i.
/I// 3/'JS M. D. Hunt, Principal Inspector
/ bat 6 Projects Section Reactor Construction and Engineering Support Branch
'h A h.g~/I~
i f ? "' 4 R. W. Wright, Principal Inspector Date Projects Section Reactor Construction and Engineering Support Branch Dates of Inspection:
0ctober 17-20, 1978
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Reviewed by:
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A. R. Herdt, Chief Date Projects Section Reactor Cor.struction and Engineering Support Branch 1.
Persons Contacted Alabama Power Company (APCO)
- J. A. Mooney, Project Manager-Construction
- R. E. Hollands, Jr., QA Supervisor
- R. S. Fucich, QA Engineer
- D.
B. Hartline, QA Engineer
- A W. Hankins, QA Engineer
- J. 2 Payson, QA Staff Engineer
- J. G. Hegi, Project QC Engineer
- L. F. Warrick, Construction Manager
- L. C. Easterwood, QC Manager l
- R. H. Roehn, QA Engineer Diversified Electrical Contractors (DELCON)
- J. C. Weaver, Project Engineer
- Denotes those present at the exit interview.
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b RII Rpt. No. 50-364/78-16-2-2.
Licensee Action on Previous Inspection Findings (Open) Unresolved Item 78-09-01, Anchor bolt measurement base system. The licensee has developed a procedure for this investiga-tion which defines the quantity of hangers using expansion type concrete anchors to be examined.
Due to commitments of NDE person-nel to an outage of Unit 1, all work has not been completed.
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Unresolved items No new unresolved items were identified during this inspection.
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Independenc Inspection Effort Change in Principle Project Inspector This inspection trip was utilized to turnover the Farley Nuclear Plant Unit 2 project inspector responsibilities and duties from Robert W. Wright to Milton D. Hunt.
Mr. Hunt was introduced to responsible site QA/QC, construction and management personnel representing the licensee and DCC. Messrs. Hunt, Wright and the APC0 QA Supervisor discussed all outstandiug items remaining open (50.55(e)'s, noncompliances, unresolved items, IEB's).and the current status of these i'. ems for the subject facility.
The inspec-tors reviewed various cable tray support installations which incor-porated concrete anchor bolts. The details and instructions for installation of these anchors were examined. A review of the electrical conduit and channel installation was also made.
In several areas extra support members had been added to the horizon-tal cable tray supports for the installation of conduit and channels.
The inspector was advised that each support would be evaluated later for compliance with Bechtel Corporation Drawing Nos. D-203551, D-203552 and D-203553.
A walk-through examination of the class A and B storage areas was made.
Within the areas examined, no items of noncompliance or deviation were identified.
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IE Bulletins (IEB) and Circulars (IEC)
(Closed) IEC 78-08 Environmental Qualification of Safety-related Electrical Equipment at Nuclear Power Plants - The inspector reviewed a report dated October 9, 1978, which addressed each ites listed in this circular with exception of the terminal blocks (reported to RIl October 11, 1978, in accordance with 10 CFR 50.55(e)) all other items in this IEC are qualified or have been identified and qualified replacements are on order.
Ri! has no further questions at this time.
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RII Rpt. No. 50-364/78-16-3-
(Open) IEB 78-12 Atypical Weld Material in Reactor Pressure Vessel Welds - The licensee has requested their A-E to collect inf o rma t ion regarding this bulletin. The results of this review will be examined during a future inspection.
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Licensee Identified Items (10 CFR 50.55(e))
(Closed) Item 78-16-01, Current Transformers Associated With 4160V Switchgear - Additional Corrective Action - This item was originally reported to the NRC November 3, 1975 and subsequently closed.
Further investigation revealed that a modification of the licensee's corrective action s'ubmitted was required.
This report of the modified corrective action dated July 20, 1978, was reviewed and RII has no further questions at this time.
(Open) 78-16-02 - Terminal Blocks in Containment Do Not Meet Quali-fications Specified in the FSAR. The licensee notified RIl of a possible deficiency regarding the terminal blocks installed in the containment. The discovery was made as a result of the examination required by IEC 78-08.
The terminal blocks had not been subjected to the testing required to meet the qualification required by the FS AR.
(Open) Item 78-10-01 - Additional Corrective Action AFVS - Single Failure Criteria Not Met.
The licensee has submitted a final report for this item.
At this time no drawitys have been revised and no work has started.
This item will remain oren pending further action.
(open) Item 78-7-06 - Unauthorized Use of 3M Type 433 Aluminum Tape. To date all this tape has not been removed due to the cables being energized.
This item remains open pending further licensee action.
(Open) Item 78-05-01, Diesel Generator Electrical Circuitry Design Error.
The licensee has submitted a corrective action report for the extension of the diesel generator problem concerning operation of the river water pumps under loss of offsite power and LOCA conditions.
The revision to the diesel generator sequencing and l
load distribution is being reviewed by the NRC.
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Part 21 The licensee has received two letters from the manufacturer of their diesel generators regarding possible defects which the manufacturer has reported to the NRC, At the present time the licensee is awaiting further information f rom the supplier but has started a preliminary evaluation. This will be identified as an inspector
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RII Ept. No. 50-364/78-16-4-follovup item 364/78-16-03, Diesel Generator manufacturer reported deficiency, Part 21.
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Exit Interview The inspector met with the licensee representatives and others (denoted in paragraph 1) at the conclusion of the inspection.
The scope and findings of the inspection of cable tray supports, conduit and channel supports; licensee actions on IE bulletins and circulars; construction deficiencies; unresolved items; and storage facilities were discussed.
There were no deficiencies or noncompliances identified.
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