IR 05000346/1979024
| ML19250A581 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/11/1979 |
| From: | Danielson D, Yin I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19250A580 | List: |
| References | |
| 50-346-79-24, NUDOCS 7910240006 | |
| Download: ML19250A581 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-346/79-24 Docket No. 50-346 License No. NPF-3 Licensee: Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, Ohio 43652 Facility Name: Davis-Besse Nuclear Power Station, Unit 1 Inspection At:
Davis-Besse Site, Oak Harbor, Ohio Inspection Conducted: August 30-31, 1979
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Inspector:
I. T. Yin p.H.Danielson,Chiefak-vd-7!D!7f Approved By:
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Engineering Support Section 2 Inspection Summary Inspection on August 30-31, 1979 (Report No. 50-346/79-24)
Areas Inspected: Licensee actions relative to IE Bulletins No. 79-02, No. 79-04, and No. 79-14, including general discussion on NRC requirements work procedure review and review of program implementation records.
Results: No items of noncompliance or deviations were identified.
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DETAILS
Persons Contacted Toledo Edison Comapny (TECo)
- C.L. Mekbel, Senior Engineer
- B. R. Beyer, Assistant Station Superintendent
- P. N. Carr, Maintenance Engineer
- D. Mominee, Assistant Field QA Representative Bechtel Power Corporation,Gaithersburg Power (B-GPD)
- C. M. Foltyn, Plant Design Engineer, Group Supervisor
- R.
Kies, Plant Design Engineer The inspector also contacted other TECo and B-GPD personnel during the course of inspection.
- Denotes those attending the exit interview.
Functional or Program Areas Inspected 1.
Program Review a.
IEB 79-02, " Pipe Support Base Plate Design Using Concrete Expansion Anchor Bolts", Revision 1, dated June 21, 1979.
The inspector reviewed the licensee's report, "A Report on Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts", dated July 6, 1979, and commented:
(1)
In the area of plate flexibility studies, NRR is in the process of reviewing the acceptability of the licensee's response.
(2) The parabolic formula developed for shear-tension interaction consideration appeared to be conservative.
(3) The design safety factor for faulted load conditions should be the same as service load conditions. This item is being reviewed by NRR.
(4) Preload requirement during cyclic tension and shear inter-acting loading conditions was not addressed or tested at Fast Flux Test Facilities (FFTF).
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(5) The results of the statistical semple of bolt tests evenly distributed among the system isometric drawings met the NRC requirement that results should achieve 95% confidence level with less than 5% defective samples.
b.
IEB 79-14, "Seiemic Analysis for As-Built Safety-Related Piping System", Revision 1, dated July 18, 1979.
The inspector reviewed a licensee report " Seismic Analysis for As-Built Safety Related Piping Systems", dated August 1, 1979,
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and had no adverse comments.
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IEB 79-04, " Incorrect Weight for Swing Check Valves Manufactured by Velan Engineering Corporation", dated March 30, 1979.
The inspector reviewed licensee response letter dated May 1, 1979, and discussed the problems in conjunction with requirements stated in IEB 79-14.
The inspector stated that the re-analysis based on the new valve weights will be reviewed together with IEB 79-14 data at the A-E's office. Furthermore, the inspector stated that he had a genuine concern regarding use of preliminary valve weights in piping system analyses without subsequent actual valve weight verification.
No items of noncompliance or deviations were identified.
2.
Procedure Review a.
IEB 79-02 The inspector reviewed the following B-GPD procedure and test reports:
(1) Procedure PDP-1, " Inspection and Testing Procedure for Concrete Expansion", Revision 2, dated May 21, 1979.
(2) Technical Report, " Concrete Wedge Anchor Torque / Tension Test", dated September 16, 1974.
(3) Technical Report, "Hilti Kwik Bolt Torque / Tension Verification Test", dated August 23,1976.
The inspector had the following comments after review:
(1) In PDP-1, the wedge type bolt torque test valves are based on the Item (2) report listed above and user a moly-sulfide based thread lubricant such as Felpro C-100 or Molykote-G paste, applied to both the thread areas and at the nut to washer interface. This procedure did not require lubrication
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of the wedga type bolts during the torque test because, as-3-120i2 149
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v it was told, the bolts were lubricated two to three years ago during installation. The inspector questioned that since approximately 50% of the bolts can be verified with QC records indicating that lubrication was applied during construction, whether or not bolts should be removed prior to torque test for examination to ensure all threads and washers are properly lubricated and there is no surface rust and deterioration.
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(2)
PDP-1, the shell type bolt torque test valves were without torque / bolt load correlation verification records. The validity of the torque valves used are questionable.
(3) Supplementary data obtained from the work procedure and test records:
(a) Proof load test for both wedge and shell type bolta -
Table 1A of PDP-1.
Bolt Diameter (inches)
Test Load (1bs.)
1/2 2125 5/8 2925 3/4 4050 7/8 4475 (b) Torque test for wedge type bolts with lubrication -
Data Sheet 1 of FDP-1.
Bolt Diameter (inches)
- Torque (for ft.-lbs.)
1/2 18-20 5/8 23-26 3/4 35-40 7/8 75-85
- Correlates with proof load tests.
(c) Torque test for wedge type bolts without lubrication
- Table IV of Test Report (2) above.
Bolt Diameter (inches)
Torque (for ft.-lbs.)
1/2 45-55 5/8 100-115 3/4 140-160 7/8 200-220
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(d) Torque test for shell type bolts without lubrication
- Data Sheet 2 of PDP-1.
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Bolt Diameter (inches)
Torque (for ft.-lbs.)
1/2 25-30 5/8 40-45 3/4 65-70 7/8 90-95 b.
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The inspector reviewed the B-GFD procedure PDP-2," Inspection Procedure for As-Built Configuration of Nuclear Safety Related Piping Components", Revision 1, dated August 15, 1979, and commented that the procedure did nat address the following requirements:
(1) Evaluation process af ter nonconformances have been identified including:
(a) specific time allowance for reporting to NRC, i.e. an engineering judgeeent within 2 days followed by an analytical engineering evaluation within 30 days, and (b) licensee corrective actions and criteria for allowing temporary plant operation if system operability is in jeopardy.
(2) Verification of pipe sizes, schedules, and materials.
(3) Reporting excessive clearance or gaps in pin connecting bolt holes.
(4) Verification of pipe clamp tightness or required torquing to ensure functionability of the restraint system.
(5) Cut insulation for inspection if required.
(6) Procedural requirements for indirect measurements such as using plumb lines, measuring multiple dimensional offsets, etc., and the determination of the accuracy of such indirect measurements.
No items of noncompliance or deviations were identified.
3.
Records Review IEB 79-02 Tie inspector reviewed some of the bolt testing records.
Since the 3st procedure adequacy was in question, final review of program implementation will be not conducted until all issues are resolved and rework, if required are coopleted.
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IEB 79-14 The inspector reviewed records of indoctrination and training held in B-GPD office on July 26, 1979, and on July 30, 1979, and considered them in good order. The piping inspection is still in progress, and the data collected will be reviewed by the inspector during a future site visit.
Exit Interview The inspector met with licensee representatives at the conclusion of the inspection on August 31, 1979. The inspector summarized the scope and findings of the inspection. The licensee acknowledged the findings reported herein.
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