IR 05000339/1979040
| ML19209C910 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/29/1979 |
| From: | Bryant J, Mcfarland C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19209C903 | List: |
| References | |
| 50-339-79-40, 50-404-79-06, 50-404-79-6, 50-405-79-06, 50-405-79-6, NUDOCS 7910180465 | |
| Download: ML19209C910 (6) | |
Text
f atouq'o, UNITED STATES l'
NUCLEAR REGULATORY COMMISSION
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101 MARIETTA ST., N.W., SUITE 3100 o,
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ATLANTA, G EORGIA 30303
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Report Nos. 50-339/79-40, 50-404/79-06 and 50-405/79-06 Licensee: Virginia Electric and Power Company P. O. Box 26666 Richmond, Virginia 23261 Facility Name: North Anna Units 2, 3, and 4 Docket Nos. 50-339, 50-404 and 50-405 License Nos. CPPR-78, CPPR-114 and CPPR-115 Inspection at North Anna site near Mineral, Virginia Inspector:
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'd/- N C. R. McFarland Date Signed Approved by:
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J. C. Bryant, Section Chief, RCES Branch
'Ifate S'igned SUMMARY Inspection on August 7 - 10, 1979 Areas Inspected This routine, unannounced inspection involved twenty-eight inspector hours onsite in the areas of nonconformances related to concrete operations, 10 CFR 50.55(e) items (Unit 2), IE Bulletins (Units 3 and 4) and site QA and QC organi-zation and activities related to the extended construction delay of Units 3 and 4.
Results Of the four areas inspected, no items of noncompliance or deviations were identified.
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DETAILS
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1.
Persons Contacted Licensee Employees
- P. G. Perry, Senior Resident Engineer
- E. R. Bane, Supervisor, Construction QA
- P. A. Slater, QA Engineer
- M. A. Harrison, QC Engineer B. S. Brookman, Senior Engineering Technician, Civil QC C. G. Meyer, Control Room Operator Contractor Organization Stone and Webster Engineering Corporation (S&W)
A. A. Dasenbrock, Resident Manager C. A. Goody, Superintendent, Construction
- W. R. Whitley, Assistant Superintendent, Field Quality Control (FQC)
- F. F. Carchedi, FQC Engineer J. Crossland, FQC Engineer, Hangers S. K. Patel, Design Supervisor, Site Engineering Office (SEO)
R. Corneia, Senior Designer, SE0 P. Joshi, Stress Engineer, SEO R. Shaw, Engineer Associate, SEO NRC Resident Inspector
- M.
S. Kidd Other licensee employees contacted included several construction craftsmen and foremen.
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on August 10, 1979, with those persons indicated in Paragraph 1 above. No new items of noncompliance
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or deviations were identified.
3.
Licensee Action on Previous Inspection Findings (Closed) Deficiency 404/79-04-02, Testing of plastic concrete. The a.
inspector reviewed the VEPC0 response to Region II dated July 31, 1979 and the corrective action taken with the responsible QA and QC personnel.
The place of testing the plastic concrete has been changed to be the point of placement. This change has reduced the time between sampling and the start of testing to be within the times permitted by ASTM C-172.
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b.
(Closed) Unresolved Item 404-405/79-05-01, Auditing of construction activities.
The VEPC0 Construction Quality Contr&l Manual (CQCM)
procedure 1.1, Organization and Program, has been revised to clearly identify the CQC auditing engineers as being separate from the QC engineers who perform QC work related to the electrical, mechanical, civil, and other disciplines of work.
c.
(Closed)
Unresolved Item 404-405/79-05-02, Resident QC engineering evaluation of 10 CFR 50.55(e) items. The CQCM procedure 15.1, Noncon-formance Reporting and Processing, has been revised to require the senior QC engineer to evaluate each nonconformance report for potential reportability under the provisions of 10 CFR 50.55(e) and/or (Part 21)
in accordance with the requirements of the VEPC0 QA Manual, Section 5.1. 3.
d.
(0 pen) Unresolved Item 404-405/79-02-01, Humidity in internals of components in storage, Units 3 and 4.
The inspector reviewed documen-tation relative to the storage, refurbishment and warranty for Babcock and Wilcox Company (B&W) manufactured components. Work relative to the cleaning, evaluating and storing the major components is scheduled for completion in September.
The inspector observed that the new level B and level C warehouses are being erected, (siding, insulation, and roofing are in place to varying degrees).
The inspector was informed that the warehouses are expected to be completed in November 1979.
4.
Unresolved Items There were no new unresolved items identified during this inspection.
5.
IE Bulletins (IEB)
(Cloned) lEB 79-03, Longitudinal weld defects in ASME SA-312 type 304 a.
stainless steel pipe scools manufactured by Youngstown Welding and Engineering Company (YWs.) Units 3 and 4.
The inspector reviewed the VEPC0 responses to Region II dated June 11, 1979 and July 11, 1979, and discussed the subject with the construction QA supervisor.
A review of the items purchased by S&W and the items purchased and/or manufactured by the Nuclear Steam Supply System vendor, Babcock and Wilcox Company, shows that no YWEC materials were used nor a.e planned for use in Units 3 and 4.
IEB 79-03 remains open for Unit 2 pending further review of the VEPCO response by the NRC.
b.
(Closed) IEB 79-09, Failure of GE type AK-2 circuit breakers in safety related systems, Units 3 and 4.
The inspector reviewed the VEPC0 response to Region II dated June 19, 1979 and discussed the subject with the construction QA supervisor. The subject breakers will be used as reactor trip breakers and will be in a preventative maintenance program that will incorporate the requirements of IEB 79-09.
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c.
(Closed) IEB 79-14, Seismic analysis for as-built safety related systems, Units 3 and 4.
The inspector and the Regi'on II staff has reviewed the VEPC0 response to Region II dated August 1, 1979. The VEPC0 response provides for a program that satisfactorily addresses the requirements of IEB 79-14, 79-14 Rev. I and Supplement 1.
No safety-related piping systems have been installed inside any building to date.
d.
(0 pen) IEB 79-02, Pipe support base plate designs using concrete expansion anchor bolts, Units 3 and 4.
Region II has received the VEPC') response for Units 3 and 4 dated June 27, 1979 and is reviewing this item as a part of a review of piping systems. No category I pipe supports have been installed to date.
The present methods of design will attempt to minimize the use of concrete expansion anchor bolts for pipe support baseplates in seismic category I systems.
6.
Extended Construction Delay, Units 3 and 4 The inspector reviewed documentation dated April 26 and May 14, 1979, relative to the corrosion measurements of various sizes of reinforcing steel bars taken from various locations of the containment vessels for both units, the intake structures, the discharge tunnel, the vacuum priming pump house, the auxiliary building foundation, the service water pump house, and various caissons.
All samples exceeded the acceptance criteria of ASTM A-615.
The inspector reviewed the specification, NAS-30176 revision 1, section 4, relative to the surface preparation and painting requirements for the reactor containment liner floor, observed some painted surfaces in Unit 3 and reviewed the coating inspection records dated August 6 and 8, 1979 for Unit 3.
The inspection was conducted per CQC procedure 10.4, protective coating control program. The records were as required by attach-ments 7.3 and 7.4 of CQCP 10.4.
The overall study concerning the cleanup and remedial action requirements for Units 3 and 4 dated January 12, 1979, initiated the worL noted above and other work that is related to the extended construction delay of Units 3 and 4.
Inspector followup item (IFI) 404-405/79-06-01, containment liner wall inspections, will be used to identify the need to monitor S&W recommended program to periodically inspect the containment liner to assess any further corrosion or change in corrosion rates. IFI 404-405/79-06-02, containment liner dome plate inspections, will be used to monitor the S&W recommended program to set up a joint inspection program to determine the amount of pitting and corrosion, and the remaining plate thickness of these dome plates.
Work related to the extended construction delay effect on B&W supplied components is reported in paragraph 3.d of this report.
7.
Independent Inspection The inspector inspected the Unit 2, 3 and 4 facilities, the storage arees, observed work inside the Unit 2 containment vessel and the auxiliary building, talked to various craft personnel, and discussed the schedule for work to be performed with the VEPC0 Senior Resident Engineer, and the NRC Resident Inspector.
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No items of noncompliance or deviations were identified.
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8.
Licensee Identified Items (LII) 10 CFR 50.55(e) Items a.
(0 pen)
LII 339/79-28-03, 2 RS-P-1B Motor failure.
The inspector reviewed the VEPC0 responses to Region II dated April 11, 1979, May 4, 1979 and July 19, 1979 relative to the subject. The inspector reviewed documentation of the modifications and repair work documented as Engin-eering and Design Coordination Report (E&DCR) 13360 and Nonconformance and Disposition Report 3655. The motor bearings design has been changed and the bearings have been replaced, motor tests have been run by General Electric Company and the nameplates have been changed to properly identify the new bearings. The inspector observed the completed work in Unit 2 reactor building. This item r.: mains open pending review of the bearing temperatures during the preop performance tests of the modified pump and motor.
b.
(0 pen) LII 339/79-12-04, Diesel generator muffler seismic considerations.
The inspector reviewed the VEPC0 responses to Region II dated February 5 and March 2,1979. The inspector reviewed the documentation of the corrective action and the modification work related to E&DCR P-2588.
The modification provides for a by pass exhaust in parallel with the muffler.
The work related to the support of the by pass piping apparently was not complete.
c.
(Closed) LII 339/79-28-04, Main Steam Valve House (MSVH) seismic analysis, Unit 1.
The inspector reviewed the VEPCO responses to Region II dated April 16, 1979, May 10, 1979, and June 6, 1979, relative to the subject and the resultant reanalysis of piping and pipe supports using the appropriate MSVH structural responses.
The inspector reviewed the calculations for the following pipe hangers as typical of the various sizes and types of piping and hangers:
H-220, HSS-224, 2-SHP-SH 29, FPH-SHP-447-4, FPH-SHP-446-2, 2-QS-R-198, 2-SI-R-93, 2-SI-A-245, 2-SI-A-244, and 2-SI-R-87.
The inspector observed the field modificcations on the following hangers as typical of the various configurations and requirments: H-220, HSS-224, 2-SHP-SH-29, 2-QS-R-145, 2-QS-R-146, 2-SI-R-207, and 2-SI-R-87.
d.
(Closed) LII 339/79-21-03, 6" Check valves overweight, Unit 2.
The inspector reviewed the VEPC0 responses to Region II uated March 26, 1979, April 20,1979, and May 8,1979, relative to the overweight check valves supplied by Westinghouse for the safety injection system. The inspector also reviewed the reanalysis of the pipe supports resulting from the reanalysis of pipe stresses du( to the overweight check valves. The following pipe supports calculations were reviewed as typical examples for the modifications:
sketch numbers Z FSK-SI-416-4 in cubicle "C" and Z FSK-SI-421-1, 2, and 3 in cubicle "A".
The inspector also observed these same pipe support members in the field to confirm that they con-formed to the information on the appropriate engineering sketches incor-porated in E&DCR P-2 596-? with special emphasis on the modified work.
Similar work on Unit I w;4s reported to Region II in report 50-338/
79-20.
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e.
(Closed) LII 339/78-33-02. High density spent fuel rack bolts. The inspector reviewed the VEPC0 responses to Region II dated October 18, 1979, November 14, 1979 and February 9, 1979, relative to the subject.
The inspector reviewed documentation supporting the corrective action as stated in the final report that Speedway Machine and Tool Company (SMATCO) has replaced the bolts and provided VEPC0 with the proper documentation for the mechanical properties test after heat treating the 64 hex head bolts, item 7 on NUS drawing 5094M2000. The bolts are used to attach mechanical guard barriers to the sides of the high density spent fuel storage racks.
f.
(Open) LII 339/79-39-04, Pressurizer supports. The inspector reviewed the VEPC0 response to Region II dated June 22, 1979 and the applicable sections of NAS 377.
" Specification for Installation of Pressurizer Support and Pressurizer for North Anna Station - Units 1 and 2" revision 4 dated July 30, 1979. N&D 3800 and E&DCR 2521.2 document the provisions for new jam nuts and bearing lock washers and the installation of these items as required by NAS-377 The installation work apparently was not complete.
g.
(0 pen) LII 339/79-36-03, High density fcel storage rack welds. The inspector reviewed the VEPC0 responses to Region II dated November 27, 1978, December 21, 1979 and February 7, 1979.
The inspector also reviewed the applicable specification, purchase order, and drawings and observed the covered racks which are stored outdoors on dunnage and protected with a waterproof covering. The status of the specifi-cation and purchase order are the same as reported in Region II reports 50-338/79-05 and 50-339/79-07. The racks are to used for Units 1 and 2.
Since the racks are to be placed into the fuel storage pool in the near future the inspection of the welds was deferred.
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