IR 05000338/1980008
| ML19309C071 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/21/1980 |
| From: | Compton R, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19309C067 | List: |
| References | |
| 50-338-80-08, 50-338-80-8, 54-339-80-06, 54-339-80-6, NUDOCS 8004080129 | |
| Download: ML19309C071 (4) | |
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UNITED STATES
/' 8 NUCLEAR REGULATORY COMMISSION n
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REGION 11
101 MARIETTA ST N.W.. SUITE 3100 o
\\.....,f ATLANTA, GEORGIA 30303
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FEB 2 51990 Report Nos. 50-338/80-08 and 50-339/80-06 Licensee: Virginia Electric & Power Company Richmond, VA 23261 Facility Name: North Anna Units 1 & 2 Docket Nos. 50-338 and 50-339 License Nos. NPF-4 and CPPR-78 Inspection at ot Anna Site near Mineral, Virginia
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d/ 89 R. M.) Compton Ifa te' Signed Approved by:
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k0 A. R. lierdt, Section Chief, RC&ES Branch Date Signed SUMMARY Inspection on February 6-8, 1980 Areas Inspected This routine announced inspection involved 16 inspector-hours on site in the areas of IE Bulletin 79-14, " Seismic Analysis for As-Built Safety-Related Piping Systems".
Results 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. Smith, Jr., Superintendent - Technical Services - Operations
- P. A. Slater, Resident QC Engineer
- A. J. Foussekis, Resident Engineer, Stone & Webster (S&W)
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- C. A. Goody, Resident Manager, S&W E. Spurrell, Head-Site Engineering, S&W S. K. Patel, Supervisor-Engineering Mechanics, S&W
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G. W. Hires, Authorized Nuclear Inspector, Hartford Steam Boiler i
NRC Resident Inspector M. S. Kidd
- Atteuded exit interview
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2.
Exit Interview The inspection scope and findings were summarized on February 8,1980, with l
those persons indicated in Paragraph I above.
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items were not identified during this inspection.
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(Open) IE Bulletin Number 79-14, " Seismic Analysis for As-Built Safety-Related
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Piping Systems"
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VEPCO letter 552/070279, dated August,1, 1979, identified seismic analysis
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inputs and the methods used to verify the accuracy of this input. VEPCO considered that the program of quality control and inspection requirements used for North Anna 1 and 2 provide assurance of as-built plant conformance to design requirements. However, correct valve and valve operator weight inputs are being reverified for computer analyzed safety-related systems.
The following documents, referenced by VEPCO as providing assurance of con-formance to design documents, were examined:
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-2-FQC Procedures QC-11.2,11.4 and 15.1
'S&W Company Quality Assurance and Control Manual - ASME - Section III (Including prior editions)
Nuclear Project Operation Procedures POP-506 and 814 North Anna Specifications NAS - 271 and 416 Actual dimensional verification of system geometry was not performed except for Q1 systems. General configuration, branch line location and component installation were verified by QC inspectors and field stress engineers.
Actual dimensional control was provided by weld joint records and the fact that almost all large bore (greater than 2\\ inch) piping was prefabricated offsite. Piping changes and added or deleted welds required documentation and approval on Engineering and Design Coordination Reports.
The following portions of safety-related piping systems were walked down to compare as-built conditions to design drawings. Supports / restraints listed were inspected for conformance to detail drawings.
Unit 1 18" and 24" Component Cooling Water System - stress MSK-118C1-5 from data point 170 to anchors AS-900 and A9-550.
6" Component Cooling Water system - Line 6" CC-397-151 Q3 on stress MSK-118x 3-3 and piping detail drawing FP-18C-12. Restraint CC-R-360.
4" Component Cooling Water System - Line 4" CC-587-151 Q3 on stress MSK-118x 4-1 and MSK 118x5-1 and piping detail drawings FP-18D-9 and FP-18E-11.
Re-straint R-273 on MFSK 2999A; restraint R-271, anchor 272 and supports H 268 and H 269 on FP 18AJ-2; supports H 265 and H 266 on FP-18AL-1; support H 267 on SK 5201 and support H 263 on FP-18AK-2.
Unit 2
CVCS Loop Drain system - Lines 2" RC-459-1502-Q1, 3" RC-619-1502Q1 and 2"
RC-620-1502 Q1 on stress isometric SSR-10, revision 2 (stress problem 722)
from data points 1 to 132.
Service Water system - 8 lines shown on MSK-105B1-5, MSK-105Al-5, FP-5A-7 and FP-5B-7 from the penetrations to the expansion joints at data points 30, 71,145 and 182.
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Vertical constraints indicated at data points 177 and 300 on Unit 1 Component
Cooling system MSK-118C1-5 were actually dead weights supports. However, the
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net design loads at these supports were very large downward - no uplift.
Thus, modelling the one-directional vertical support as a two way vertical constraint is consistent with S&W design memorandum EMD-79-18. A lateral strut was installed on this same line at approximately data point 195 and
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-3-was not shown on the MSK. This strut had just been installed as a result of reanalysis due to the amplified response spectra curve problem previously reported. No other discrepancies were noted.
As an example of the stress as-builts (SAB's) generated during the stress engineers walkdown of Q1 systems, SAB-103AY-4 was examined.
The status and site program for the valve weight reanalysis was reviewed.
All analysis was complete and all but two modifications complete on Unit 1.
For Unit 2, all Boston office pipe stress analysis was complete and support designs were being analyzed by the site engineering office for the new loads for 10 MSK's.
The valve weight analysis program will be examined further in a future inspection at S&W's Boston office.
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No deviations or items of noncompliance were identified.
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