IR 05000339/1979024
| ML19241B153 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/07/1979 |
| From: | Ang W, Bryant J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19241B135 | List: |
| References | |
| 50-339-79-24, 50-404-79-02, 50-404-79-2, 50-405-79-02, NUDOCS 7907110743 | |
| Download: ML19241B153 (5) | |
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NUCLEAR REGULATORY COMMISSION
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101 M ARIETTA STREET, N.W.
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ATLANTA, GEORGIA 30303
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Report Nos. 50-339/79-24, 50-404/79-02 and 50-405/79-02 Licensee: Virginia Electric and Power Company Post Office Box 26666 Richmond, Virginia 23261 Facility Name: North Anna Power Station, 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 5 ' r /7 <,
Inspector:
_3 W. P. Ang Date Signed
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gg cp Approved by: _,C.
_ryant,(.Fection Chief, RC&ES Branch Date Sighed SUMARY Inspection on April 17-19, 1979.
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Areas Inspected This routine, unannounced inspection involved 16 inspector-ho s onsite in the areas of QA procedures, work activities and records (Units 3 and 4) for the extended construction delay; and housekeeping and hydraulic snubber installation (Unit 2).
Results Of the areas inspected, no apparent iteus of noncompliance or deviations were identified.
7907110743 307 242
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DETAILS 1.
Persons Contar*nd Licensee Employees
- P. A. Slater, Resident QA Engineer
- N. B. Dillon, Resident Engineer - Construction
- D. M. Powell, Associate Mechanical Engineer - Construction
- M. P. Kalan, Administrative Supervisor E. R. Bar.e, QA Construction Supervisor Other Organizations Stone and Webster Engineering Corporation
- A. A. Dassenbrock, Resident Manager
- R. S. Jennings, canior Construction Engineer
- A. Foussekis, Resident Engineer Babcock and Wilcox R. Nelson, QA E. Carls a, Construction Contract Administrator NRC Resident Inspector M. S. Kidd
- Attended exit interview 2.
Exit Interview The inspection scope and findings were sum:,rized on April 19, 1979, with those persons indicated in paragraph I above.
Unresolved item 50-404/79-2-1 and 50-405/79-2-1 (Humidity in internals of components in storage) was discussed.
3.
Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items
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Unresolved items are matters about which more information is,< quired to determine whether they are acceptable or may involve nont pliance 307 243
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-2-or deviations. A new unresolved item identified during this inspection is discussed in paragraph 8 5.
Independ nt Inspection Effort - Unit 2 An inspection of the containment building was accomplished. Housekeeping and installed hydraulic snubbers were inspected.
No items of noncompliance or deviations were identified.
6.
Extended Construction Delay - Review of Quality Assurance Implementing Procedures - Urits 3 and 4 The following procedures were reviewed for compliance with licensee commitments and NRC requirements:
VEPC0 construction QC procedure 13.1 hev. 0 - Storage of Material a.
and Equipment b.
VEPCO Construction QC Manual 15.1 - Nonconformance Reporting Stone and Webster (S&W) Nuclear Project Operating Procedure P0P-811 c.
Rev.
1 - Field Procedure for the Storage and Maintenance of Materials and Equipment d.
Babcock and Wilcox (B&W) Long Term Storage Specification Manual for B&W Supplied Equipments - Sections FS-III-1A,
-2, -5 and -8 e.
VEPC0 QC Procedure 1.1 Rev.
1 - Organization A recent (January 1979) change of the VEPC0 QA/QC organizational structure was shown in QCP 1.1 Rev.
1.
This change was also discussed with the licensee. Tha licensee indicated that S&W would no longer perform QC for Units 3 'nd 4.
The site VEPC0 organization for Units 1, 2, 3 and 4 will be periorming the QC function for Units 3 and 4.
The VEPCO Headquarters QA organization would be performing the QA function for Units 3 and 4, but would be working out of its Richmond office.
No items of noncompliance or deviations were identified.
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7.
Extended Construction Delay - Observation of Work and Work Activities - Units 3 and 4 The containment liners and partially completed installation of containment wall reinforcing bars were inspected for general condition and licensee compliance with VEPCO commitments and NRC requirements. Significant corrosion was noted on the outside surface of the containment liner and on the installed containment wall reinforcing bars.
The licensee stated that a Stone and Webster (S&W) study had been performed on the corrosion of the containment liners and reinfcrcing bars. The study showed that the reinforcing bars had not significantly deteriorated to date. However, the study showed that the corrosion rate for the containment floor and wall liners would reduce the plate thickness below specified thickness in slightly more than two years for the floor and three and a half years for the wall if no corrective action is taken.
The study recommended placement of containment wall concrete to cover inaccessible areas of the exterior wall and to periodically inspect the remaining exposed area of the liner wall.
The study further recommended that the containment floor be cleaned and painted to prevent further corrosion. The licersee stated that the S&W recommendations were to be accompliched.
The stored reactor vessel, reactor vessel internals and steam generators were inspected for compliance with licensee, NSSS and NRC storage requirement.
No items of noncompliance or deviations were identified.
8.
Extended Construction Delay - Review of Quality Records Units 3 and 4 Quality records were reviewed for compliance with licensee commitments and NRC requirements. The following records were reviewed:
a.
QA audits 682, 683 and 687 b.
Headquarters QA audit dated 3-19-79 c.
Nonconformance Report Nos. 3-0001, 3-0002, 3-0003, 3-0004, 3-0005, 3-0006, 4-0002, 4-0003, 4-0004, 4 0005, 4-0006, 4-0007, 4-0008 d.
Completed equipment history cards of steam generators, reactor vessels and reactor vessels internals Repetitive humidity problems in the internal atmosphere of various safety related components including the steam generators and reactor vessel internals were recorded on the equipment history cards.
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action did not appear adequate to prevent recurrence of the humidity problem.
B&W Letter NBC 2953 dated January 25, 1979 was obtained from the licensee. The letter indicated that B&W inspection of site stored B&W supplitd equipment revealed deterioration of some critical surfaces, rust and moisture. The letter further indicated that because of the condition of the steam generators and reactor internals, B&W has voided the warranties on these components. The letter provided a B&W requirement for upgrading of storage facilities for B&W equipment to allow extension of the warranties on P1W supplied equipment except the steam generators and reactor internals. The licensee stated that they were currently studying both the humidity prob 1.em and the storage upgrading requirements of B&W.
Pending completion of the iicensee stud 3 and corrective action to prevent deterioration of stored safety related components, this shall be identified as Unresolved Item 50-44/78-6-01 and 50-405/78-6-01.
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