IR 05000338/1979051
| ML19290E208 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 01/24/1980 |
| From: | Hunt M, Mcfarland C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19290E204 | List: |
| References | |
| 50-338-79-51, 50-339-79-57, 50-404-79-08, 50-405-79-08, NUDOCS 8003050261 | |
| Download: ML19290E208 (6) | |
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NUCLEAR REGULATORY COMMISSION
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REGION 11 0, '.6 101 MARIETTA ST N.W.. SUITE 3100 ATLANTA, GEOP'll A 30303
3AN 2 41933 Report Nos. 50-338/79-51, 50-339/79-57, 50-404/79-08 and 50-405/79-08 Licensee: Virginia Electric and Power Company Richmond, Virginia 23261 Facility Name: North Anna Units 1, 2, 3 and 4 Docket Nos. 50-338, 50-339, 50-404, and 50-405 License Nos. NPF-4, CPPR-78, CPPR-114 and CPPR-115 Inspection at North Anna site near Mineral, Virginia Inspector:
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/-2V-8d C. R. McFarland Date Signed Approved by:
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M. D.' Hunt, Actilig Se'ction Chief, RCES Branch SUMMARY Inspection on December 18-20, 1979 Areas Inspected This routine, unannounced inspection involved twenty-two inspector-hours on site in the areas related to diesel generators and charging pumps (Unit 1), concrete testing (Units 2, 3, and 4), followup on 10 CFR 50.5Me) items (Units 2, 3, and 4), IE Bulletins (Units 3 and 4), and the extended construction delay of Units 3 and 4.
Results Of the areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- P. G. Perry, Senior Resident Engineer E. R. Bane, Supervisor, Construction QA
- P. A. Slater, Resident QA Engineer M. A. Harrison, QC Engineer D. S. Hart, QC Engineer, Civil J. E. Wroniewicz, QC Engineer R. T. Johnson, QC Engineer R. S. Johnson, QC Engineer M. C. Reynolds, Senior Advisory Engineer C. O. Weicht, Control Room Operator Contractor Organizations Stone and Webster Engineering Corporation (S&W)
- rf A. Dasenbrock, Resident Manager
- A. J. Foussekis, Resident Engineer
- K. C. Murray, Senior Construction Inspector J. Lehman, Field Engineer C. Heishman, Field Engineer NRC Resident Inspector (RI)
M. S. Kidd Other licensee and contractor employees contacted included several con-struction craftsmen and foremen.
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on December 20, 1979, with those persons indicated in Pa-sph 1 above.
3.
Licensee Action on Previous Inspection Findings (0 pen) Unresolved Item 404-405/79-02-01, Humidity in internals of compo-nents in storage, Units 3 and 4.
Discussions with the S&W resident engineer indicates that S&W Specification NAS3363 is to be issued in the near future to provide the storage and maintenance requirements for all items in storage (including the Babcock and Wilcox Company (B&W) supplied components and piping). NAS3363 is to incorporate the requirements of all previous docu-ments. The inspector observed work on cleaning the reactor vessel internals and on sealing the steam generators for storage with pressurized inert ga.
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4.
Unresolved Items There were no new unresolved items identified during this inspection.
5.
Independent Inspection The inspector inspected the Unit 3 and 4 facilities and the storage areas, observed work in Units 3 and 4 containment vessels, talked to various craft personnel and discussed the schedule for work with the VEPCO resident QA engineer, the S&W resident engineer, and the NRC Resident Inspector.
6.
Licensee Identified Items (LII), 10 CFR 50.55(e) Items (0 pen) LII 339/79-57-01 and 404-405/79-08-01, Concrete tester cali-a.
bration program deficient. On December 18, 1979, VEPCO advised the RI and the inspector of a significant breakdown in the QC program per-taining to the verification of the Forney (Model FT-40) compression testing machine. The tester had not been calibrated in the lower 10%
of the total range of the machine; i.e., below 25,000 pounds force.
Subsequent information indicates that the testing results indicated by the machine were lower than the actual as attested by a recent calibra-tion of the machine in the zero to 25,000 pound range.
The inspector reviewed the applicable S&W specifications, the referenced ASTM specifications and the VEPCO Nonconforming Report 1733CF02. The inspector discussed tb2 subject with the S&W and VEPCO staff and observed the equipment. This item is reported under 10 CFR 50.55(e)
by VEPC0 due to their QA Procedure 5.13 requirements to report automatically all items that cannot be completely evaluated within five days. No subsequent evaluation indicated a potential that the
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deficiency in the calibration program could have affected adversely the safety of operations of the plant, b.
(0 pen) LII 404405/79-08-02, Seismic code errors at B&W. On December 7, 1979, VEPC0 advised Region II of a nonconservative calculation of seismic response spectra used by B&W for North Anna Units 3 and 4.
Discussion with the VEPC0 staff indicated that B&W recognized the error before S&W used the B&W seismic information. B&W has generated revised seismic response spectra for North Anna Units 3 and 4 and is in the final process of incorporating this data into a specification revision per information in the VEPC010 CFR 21 report and the 10 CFR 50.55(e) final report to Region II dated December 12, 1979. This item remains open pending review of the B&W specification revision.
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c.
(0 pen) LII 404-405/79-07-02, Containment overpressurization. The VEPCO letter to Region II dated October 4, 1979, submits an interim 10 CFR 50.55(e) report that supplements the information in the initial 10 CFR 21 report dated September 7, 1979.
VEPCO is still evaluating modifications to limit auxiliary feedwater (AFW) flow to the affected steam generator in the event of a main steam line break. Virtually no progress has been made on the resolution of this problem for North
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-3-i Anna Units 3 and 4 due to the reduced engineering effort on the project due to the VEPCO study of the feasi'oility of utilizing North Anna Units 3 and 4 equipment in rF.iesign and construction of coal units.
d.
(Opua) LII 404-405/79-07-03, Defect in feedwater pump motor oil re s e rvoi r.
The VEPCO letter to Region II dated October 19, 1979, submits an interim 10 CFR 50.55(e) report that supplements the information in the initial 10 CFR 21 report dated September 25, 1979.
The vendor has agreed that there is a defect in the castings for these motors and that the problem will be corrected.
7.
Licensee Event Reports (LER) - Unit 1 The following reportable events or problems were reviewed by the inspector at the request of the RI to verify that the reporting requirements had been met, causes had been identified, corrective actions appeared to be appro-priate, generic applicability had been considered, and the Unit 1 LER forms were complete. Additionally, it was verified that the licensee had reviewed each event and the corrective actions.
79-05/0IT-0, Emergency diesel generator (DG) mufflers not missile a.
protected nor seismically restrained.
The inspector reviewed design changes (DC) 79-S14A, 79-S14B and 79-14C dated December 18, 1979, relative to the DG exhaust modifications.
Supports and restraints for the exhaust to the mufflers and the exhaust muffler by pass exhaust line have been installed. The inspector observed the rework and confirmed that the rework has been completed per the above design changes. The interim fix for Unit I was reported as completed by the RI in IE Report 50-338/79-09. Rework on Unit 2 has been inspected as reported in IE Reports 50-339/79-40 and 50-339/79-58. This inspection closes this item for the (long-term) design change for Unit 1.
b.
79-08/0IT-0, Service water (SW) flow to charging pump coolers inadequate.
The inspector reviewed DC 79-S09 dated December 17, 1979, relative to changes to the charging pump coolers and the related instrumentation.
The inspector also reviewed the applicable S&W piping and equipment drawings, the Fischback and Moore instrumentation drawings, and Section 9.2.1, Service Water, of the FSAR. The inspector observed the modifi-cation work on the SW piping headers and the instrumentation and the piping for the heat exchangers and instruments associated with charging pumps IA, IB and IC.
The inspector also observed that in the control room changes were made to the annunciators and temperature indicators as indicated in DC 79-S09. This item is closed.
8.,IE Bulletins (IEB)
a.
(Closed) IEB 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts, Units 3 and 4.
Region II considers the VEPC0 response to IEB 79-02 dated June 29, 1979, to be satisfactory. No Category I pipe supports have been installed to date. The present
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s-4-methods of design will attempt to minimize the use of concrete expan-sion anchor bolts for pipe support baseplated in seismic Category I systems, b.
(Closed)
IEB 79-11, Faulty Overcurrent Trip Device in Circuit Breakers for Engineered Safety Systems, Units 3 and 4.
Region II considers the VEPCO response to IEB 79-11 dated October 30, 1979, to be satisfactory, they have not used any Westinghouse DB-50 nor DB-75 breakers to date.
The checks recommended in IEB 79-11 will be performed if they have occasion to use these types of breakers.
c.
(Closed)
IEB 79-23, Potential Failure of '.mergency Diesel Generator Field Exciter Transformer, Units 3 and 4.
Region II considers the VEPCO response to IEB 79-23 dated October 26, 1979, to be satisfacoty.
The excitation power transformer is to be connected to the generator leads utilizing a floating-wye primary winding configuration. Steps will be taken to insure that this transformer primary winding is never grounded.
9.
Extended Construction Delay, Units 3 and 4
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On October 15, 1979, VEPCO announced that it is undertaking a study to determine the feasibility of converting North Anna Units 3 and 4 from nuclear to coal. The uncertainties associated with the construction and operation of nuclear power, with the national commitment to nuclear power, and with the constantly changing regulatory environment have combined with escalating construction costs to make it prudent to make the feasibility study. The study is expected to take six months to a year.
The plant is essentially in a caretaker status at this time.
The inspector limited the inspection to followup of those items previously identified as reported in Paragraphs 3, 6.b,c. and d.
10.
Inspector Followup Items a.
(Open) Inspector Followup Item (IFI) 404-405/79-06-01, Containment liner wall inspections. The inspector observed the completed cleaning and painting work of the containment base plat-and the lower part of the liner wall of both Units 3 and 4 (reference IE Reports 404-405/79-07).
Heat shrink sleeves have been installed over the cadweld sleeves that were welded over the bridging bar assemblies for Unit 4 as they were for Unit 3.
The inspector discussed the item with the S&W resident engineer. This item remains open pending review of future reports of the periodic inspections of the containment liner plate to assess any
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further corrosion or change in the corrosion rates.
b.
(0 pen) IFI 404-405/79-06-02, Containment liner dome inspections. The inspector discussed the subject with the S&W resident engineer and observed the restacked liner plates. Under the supervision of Chicago Bridge & Iron Company (CB&I), the plates have been restacked to have a greater number of stacks, and uniform spacers between the plates. An
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-5-i inspection program has been initiated to measure pitting and corrcsion of these dome plates. This item remains open pencing review of future reports of the periodic inspections of these plates.
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