IR 05000338/1979018
| ML19246C209 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/10/1979 |
| From: | Brooks E, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19246C206 | List: |
| References | |
| 50-338-79-18, NUDOCS 7907230740 | |
| Download: ML19246C209 (5) | |
Text
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UNITED STA's CS gm Rf ou NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 M ARIETTA STREET.N.W.
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ATLANTA, GEORGIA 30303
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Report Nos.
50-338/79-18 and 50-339/79-26 Licensee:
Virginia Electric and Power Company P. O. Box 26666 Richmond, Virginia Facility Name:
North Anna 1 and 2 Docket Nos.
50-338 and 50-339 License Nos.
NPF-4 and CPPR-78 InspectionatNort.hAnnaSitgnearMineral, Virginia
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Inspector:
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E. H. Brooks Date Signed Approved by: ['
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f MaYti~n,' ~Section Chief,[Rd53 Branch
Date Signed
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SUMMARY Inspection on April 24-29, 19/9 Area. Inspected This routine, unannounced inspection involved 34 inspector-hours onsite in the areas of containment integrated leakage rate testing and inspection of pipe support and restraint systems.
Results Of the areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- W. R. Cartwright, Station Managet kS. Marvey, Operating Supervisor G
A. Mann, Engineer / Test Coordinator J. R. Eastwood, Mechanic / Snubbers P. Furman, Test Engineer W. Madison, NRC Coordina.or S. Trapani, Co-op Other licensee employees contacted during this inspection included tech-nicians and operators.
Other Organizations Stone and Webster B. C. Kuechler R. Parry C. Morrell R. Bernier NRC Resident Inspector M. Kidd
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on April 29, 1979, with those persons indicated in Paragraph 1 above. At this meeting the inspector discusse? the c.reas inspected and summarized the inspection as discussed in this report.
In the areas inspected the licensee was inf o rmed that no apparent items of noncompliance or deviations were identified.
3.
Licensee Action on Previous Inspection Finding _s Not inspected.
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Unresolved Items Unresolved items were not identified during this inspection.
5.
Containment Integrated Leakage Rate Testing (CILRT) - Unit 2 The inspector reviewed the licensee's revised procedure entitled Reactor Containment Building Integrated Leak Rate Test (2-PO-13, Rev. O dated 4-10-79). The procedure lists reference documents, initial test conditions, precautions, and limitations, test instructions, and acceptance criteria.
Attachments to the procedures included containment isolation valve lineups sheets, test instrumentation information and test data summary sheets.
Prior to the containment integrated leakage rate test, the inspector observed the containment structural acceptance test (SAT). During this test, audible leakage occurred via the containment purge valves. Subse-quent to the structural acceptance test, the purge valves were disassembled.
Construction debris (dust, etc.) was discovered on the seating surfaces of the valves. The seating surfaces were cleaned and the valves locally leak tested prior to the CILRT.
The containment, subsequent to the SAT, was at atmospheric pressure for a period in excess of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, thereby providing a sufficient period for degassing of insulation, concrete, etc. Prior to containment pressur-ization for the CILRT, the inspector accompanied by licensee persontel conducted an inspection of the valve lineup both inside and outside containment.
Random inspection of valve positions, tagging procedures, and valve checkoff lists provided assurance of correct valve lineup as indicated in the CILRT procedure 2-P0-13.
Containment pressurization for the CILRT was initiated at 01:13 p.m., on 4-27-19 using five compressors. A sixth compressor was added at 03:30 p.m.
Peak containment pressure, 59.22 psia, was achieved at 07:33 a.m.,
on 4-28-79, at which time the compressors were secured. Containment pressure decreased to 58.99 psia at 08:12 a.m. at which time the chilied water to the circulating fans in the containment was secured.
At 09:40 a.m.
chilled water at 500 gpm flowrate was again initiated to the circulating fans.
At 10:30 a.m. the stabilization period began. During the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> stabilization period, the average temperature change was 0.27 F/KR.
All temperature changes during the four hour period were within 0.5 F/HR. of the weighted average air temperature averaged over the four hour period.
The containment pressure was 58.668 at 06:30 p.m.,
on 4-28-79.
The integrated leakage rate test computer program was ini-tiated at 00:10 a.m.
on 4-29-79.
At 08:05 a.m., the packing gland on MOV 2890 B valve was tightened to eliminate minor leakage. Leakage was also discovered to be occuring via plugs on 2RS-P-1B and 25F-P-1B pump The leakage was terminated by tightening the plugs.
cans.
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-3-The inspector observed calculations of the containment leakage rate by Stone and Webster personnel using their computer program. The calculations were confirmed by the inspector using an NRC developed program. The acceptance criterion for the North Anna Unit 2 containment requires that the upper confidence (UCL) limit plus the type B and type C leakage penalties shall be less than 0.75 La (0.075%/ day).
The calculated leakage rate after 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> was 0.0539 percent / day and the upper confi-dence limit (UCL) was 0.057245 percent / day.
The licensee will include the type B and type C leakage as required in the final test report. By telephone conversation with Mr. Kidd, NRC resident inspector at North Anna, on April 30, 1979, it was confirmed that the CILRT was successfully completed including the verification test.
The licensee was advised that the valve and plugs that were adjusted during the CILRT to reduce or terminate leakages should be subject to local leak testing and any measured leakage should be added to the containment integrated leak rate as required.
6.
Hydraulic Snubbers During the period betweet. the structural acceptance test and the contain-ment integrated leakage rate test, the inspector performed an inspection of hydraulic snubbers inside the Unit 2 containment.
No discrepancies were observed during inspection of approximately 20 snubbers.
During the hot functional test of Unit 2, approximately 42 snubber discrepancies were documented.
(Stone and Webster Quality Control Inspection Report, Job No. 12050.) These discrepancies were identifie' due to fluid leakage, binding, limit of travel, and loose clamps.
D' cussions with licensee personnel indicated that all discrepancies were resolved.
Related documentation of the corrective action was in preparation ibis item is identified as an open item for future inspection (339-79-26-01).
telephone conversation was held with Subsequent to the inspection a
Mr. W. R. Whitley, of Stone and Webster Quality Assurance.
Mr. Whitley advised that most, but not all snubber deficiencies were corrected, i.e.,
adjustments to the snubbers were made as necessary while the reactor plant was at the hot functional test temperature of 550 Mr. W. R. Cartwright, Station Manager, was contacted on May 2, 1979, and advised of the inspectors concern that all snubbers may not have been inspected for adequate installation and operability at the hot functional temperature of 550 F.
Mr. Cartwright agreed that a visual inspection of all installed snubbers would be performed at hot functional temperature prior to proceeding to reactor plant conditious mode 2, i.e., crititaitty.
This item is identified for future inspection (339-79-26-02).
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Maintenance The inspector and resident inspector observed maintenance of the componcit cooling water piping tc, heat exchangers shared by both Units 1 and 2.
This piping had shifted such that the piping ends were of fset at the connecting expansion joint. The licensee was in the procesa of inspecting the expansion joints, installing fcur tie bolts across the expansion joint in place of two tie bolts, and adding extra piping restraints as necessary.
Responsible Quality Assurance personnel were observing the maintenance procedures.
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