IR 05000348/1979033
| ML19256G438 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/08/1979 |
| From: | Ang W, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19256G436 | List: |
| References | |
| 50-348-79-33, NUDOCS 7912310300 | |
| Download: ML19256G438 (5) | |
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UNITED STATES 8'
'n NUCLEAR REGULATORY COMMISSION
- r REGION 11
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o 101 MARIETTA ST., N.W., sulTE ?'Go e*
ATLANTA, G EORGI A 30303
NOV 151973
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Report No. 50-348/79-33 Licensee: Alabama Power Company 600 North 18th Street Birmingham, Alabama 35202 Facility Name: Farley Nuclear Plant, Unit 1 Docket No. 50-348 License No. NPF-2 Inspection at Farley Nuclear Plant near Dothan, Alabama and at EDS Nuclear near Atlanta, Georgia Inspector: [b Il l' M s
W.'P.
An i
Date Signed Approved by:
! I/6
//' N -7 7 A. R. Herdt Date Signed SUMMARY Inspection on October 10-12, 1979 and October 19, 1979 Areas Inspected This routine, unannounced inspection involved 20 inspector-hours onsite and six inspector-hours at the EDS Nuclear design offices in the areas of as-built safety related piping system inspection procedures, work activities and records; and concrete expansion anchor repair procedure.
Results No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- W. G. Hairston - Plent Manager
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- J. A. Mooney - Project Manager (Construction)
- W. R. Shipman - Maintenance Superintendent
- *R. L. George - Project Engineer
- J. C. Bozeman - Construction Supervisor Other Organizations Bechtel Power Corporation (Bechtel)
- A. Vizzi - Farley Engineering Manager
- J. Munzberg - QA Program Supervisor
- G. K. Wang - Stress Group Supervisor
- C.
Obst - Plant Design Staff
- M. Brobst - Project Quality Engineer Westinghouse Electric Corporation (1])
- D. Miller - Reactor Coolant Systems Analysis Manager EDS Nuclear (EDS)
1+1E. A. Wais - Office Manager
- R. Delay - Project Manager
+3 T - M. Trompo - Project Engineer
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- 1J M. Abeles - QA Coordinator
- Atterced Exit Interview
- Conte:ted by Telephone
- Attended Exit Interview at EDS Nuclear
- Attended both exit interviews 2.
Exit Interview The site inspection scope and findings were summarized on October 12, 1979 with those persons indicated in Paragraph I above. The EDS inspection scope and findings were summarized on October 19, 1979 with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings
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(Closed) Unresolved item 50-348/79-25-01 - Repair of Safety-Related Pipe Supports. Records for hangers SI-1267 and CVCS-A21 were reviewed for 1664 199
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documentation and when required, reanalysis of revised repair instructions.
FNP-1-ETP-123 Rev. 2-Analysis of Pipe Support Base Plate-Anchor Bolts in Safety-Related Systems was reviewed for procedural requirements for revised repair instructions. The records and procedure review indicate that the unresolved item had been corrected and that new procedural requirements should prevent recurrence of the noted condition. This item is closed.
4.
Unresolved Items
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Unresolved items were not identified during this inspection.
5.
As-Built Safety-Related Piping System Inspection Procedures, Work Activities and Records Inspection at Farley Nuclear Plant a.
In response to IE Bulletin 79-14, the licensee initiated and completed an inspection program for verifying that the seismic analysis performed for safety-related piping systems reflect the as built condition.
The following procedures used for the inspection program were reviewed:
(1) FNP-1-ETP-141 - Inspection Procedure for Safety-Related Piping to verify adequacy of Input for Piping Seismic Analysis (2) FNP-1-ETP-143 - Interface Responsibilities for Evaluation of Safety Related Piping System Inspection Results The procedures noted above were based on Bechtel's implementation program for IE Bulletin 79-14.
Approximately 1000 discrepancies were noted by
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the licensee inspection program.
The discrepancies were subsequently analyzed by Bechtel and W for their significance with regard to the Seismic analysis an? their effects on system operability.
Bechtel subsequently determined that 13 of the reported piping system dis-crepancies required further analysis or restoration to the original design requirements. W determined that none of the discrepancies they evaluated needed further analysis or restoration. Bechtel and W were contacted by telephone and were questioned regarding the methods and procedures used for evaluating and analyzing the discrepancies.
The inspection records for the following isometric sketches were reviewed for licensee compliance with IE Bulletin 79-14 requirements and licensee commitments:
(1) SK-H-603 - Chemical and Volume Control System (CVCS)
(2) SK-H-604 - Chemical and Volume Control System (CVCS)
(3) SK-H-605 - Chemical and Volume Control System (CVCS)
(4) Sketch No. 273 - Auxillary Feed Water System The portion of the Auxillary Feed Water System shown on Sketch No. 273 was inspected to verfy that licensee's inspection records reflect the as-built condition of the piping.
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Construction work requests for the repair of eleven discrepancies requiring restoration were reviewed for compliance with licensee commitments.
FNP-0-AP-8 - Design Modification Control was reviewed to determine compliance with IE Bulletin 79-14 requirements for procedural controls of design changes and re-analysis were required.
Based on a review of the licensees responses to IE Bulletin 79-14, discussions with the licensee and the inspections mentioned above, the following items were identified:
(1) Seismic Analysis Input for valve weights were being verified by checking the weights noted on the vendor valve drawings. The licensee commited to perform a sampling verfication of valve weights by contacting valve vendors to re-confirm the drawing valve weight data. The licensee further commited to complete this action prior to completion of the second refueling.
(2) The licensee reported that portions of the RCS system inside the pressurizer shield wall was inaccessible for direct measurements and was inspected by visual estimation.
Discussions with the licensee indicate that inspection techniques could be developed to more accurately inspect this piping.
The licensee commited to perform a more accurate inspection of the RCS piping portion that was inspected by visual estimation prior to completion of the second refueling.
No items of noncompliance or deviations were identified. However, pending completion of IE Bulletin 79-14 requirements and licensee commitments, IE Bulletin 79-14 shall remain open.
b.
Inspection at EDS Nuclear
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EDS Nuclear, Atlanta, Georgia, EDS Nuclear, New York and Teledyne Engineering Services are providing Bechtel technical assistance for the review and evaluation of Farley pipe supports for IE Bulletin 79-14.
An inspection of EDS Nuclear, Atlanta, was conducted to verify licensee compliance with IE Bulletin 79-14 requirements and licensee commitments. A preliminary EDS procedure for processing, evaluation and qualifying support walkdown packages was reviewed. A procedure for interface control for the support analysis program was reviewed.
The EDS QA manual portions dealing with design calculations and records were also reviewed.
As built design calculations had not yet been performed for the inspec-tion packages to determine the hangers that required analysis. The 1664 201
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-4-following hanger packges were reviewed to determine compliance with licensee commitments and IE Bulletin 79-14 requirements:
(1) CVC-R-246 (2) RHR-8-R54 (3) CVC-R170 (4) MS-H 585 (5) CCW-R 334 (6) CVC-R 263 (7) CS7-R 46 No items of noncompliance or deviations were identified.
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