IR 05000339/1979023
| ML19261D858 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/25/1979 |
| From: | Herdt A, Mcfarland C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19261D854 | List: |
| References | |
| 50-339-79-23, 50-404-79-01, 50-404-79-1, 50-405-79-01, 50-405-79-1, NUDOCS 7906260527 | |
| Download: ML19261D858 (6) | |
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UNITED STATES e# 8800g
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E 101 M ARIETT A STREET, N.W.
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Report Nos. 50-339/79-23, 50-404/79-1, and 50-405/79-1 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
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Inspection at North Anna site near Mineral, Virginia Inspector:
2f '1 i
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C. R. McFar and
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Dite Sfgned Approved by:
M Mfi,, ylb 8hEhs A.R.Herdt',S'ectionChieffRCE5 Branch Vate Signe'd SUMMARY Inspection on April 10-12, 1979 Areas Inspected This routine, unannounced inspection involved 20 inspector-hours onsite in the areas of 10 CFR 50.55(e) items (Unit 2), Blasting of Foundations (Units 3 and 4), and Posting of Part 21 Notices (Units 2, 3 and 4).
Results Of the three areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS
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1.
Persons Contacted Licensee Employees Virginia Electric and Power Company (VEPCO)
P. G. Perry, Senior Resident Engineer
- M. A. Harrison, QC Engineer R. T. Johnson, Jr., QC Engineer B. J. Brockman, Sr. Engineering Technician J. G. Jones, Enginscring Technician B. W. Smith, Engineering Technician Contractor Organization Stone and Webster Engineering Corporation (S&W)
- A. A. Dasenbrock, Resident Manager
- R. L. Spence, Superintendent, Field Quality Control (FQC)
P. J. Tacy, FQC Inspector F. P. Carchedi, FQC Engineer
- B. R. Hall, Senior FQC Engineer T. Arrantone, Geotechnical Engineer W. Davis, QC Inspector NRC Resident Inspector M. S. Kidd
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on April 12, 1979 with those persons indicated in Paragraph 1 above. The inspector stressed the need for more effort by the licensee to close the outstanding work required for the outstanding 10 CFR 50.55(e) items before fuel loading.
The Construction QA Supervisor stressed the need for more work on 10 CFR 50.55(e) items for Units 3 and 4.
There were no unanswered questions nor dissenting comments.
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Licensee Actions on Previous Inspection Findings No previous inspection findings were available for inspection.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Licensee Identified Items VEPCO has reported a number of items to Region II as reportable items in compliance with 10 CFR 50.55(e) and/or 10 CFR 21, and the inspector reviewed the items noted below and the supporting documentation, and discussed the items with responsible staff during the inspection.
a.
(0 pen) Item 50-339/78-24-02, Reactor Vessel Insulation, (Unit 2).
The inspector reviewed the VEPCO final report dated February 27, 1979 serial number 456C and the interim reports dated September 1, 1978 and November 10, 1978. The final report and Engineering and Design Coordination Reports (E&DCR) P2526-2 and P2526A-2 document the redesigned insulation support system that provides for no interference between the incore instrumentation tubes (ICI) and the insulation and the structure supporting the insulation. The support system as shown on S&W drawings 12050-FV-194A and 194B " Reactor Insulation Support" provides for a bolted structure that is bolted to the stiffners for the lead panels of the nuetron shield tank.
The structural integrity of the ICI tubes will not be affected by the isulation. The inspector observed the completed work. The ICI tubes are not uniformily positioned relative to the openings in the mirror insulation. This item remains open pending an interference check of the ICI tubes versus the mirror insulation material and the support structure drawing the post fuel load, precritical test of the reactor systems at design operating temperature and pressure.
b.
(Closed) Item 50-339/78-24-05, Embedment Plates for Upper Steam Generator Support Snubbers, (Unit 2). The inspector reviewed the VEPC0 final report dated September 28, 1978, serial number 543, and the supplementary information submitted February 7, 1979 serial number 543A, reviewed the design modifications and other docu-mentation relative to the corrective actions taken by VEPC0 and S&W, discussed the subject with PSE personnel, and observed the completed work for the steam generator in cubicle B as representa-tive of the complet<td work. The design criteria is acceptable since it is within c.he limits accepted for the reactor pressure vessel supports as s'ated in the Safety Evaluation Report NUREG-0053, Supplement Number 7, issued in August, 1977. The design modification provides for marking the clevis base at an 2313 211
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-3-angle to obtain proper alignment and to reduce the stresses during a seismic event. Nonconformance Disposition Report (N&D) number 3059 documents the corrective action for the steam generators in cubicles B and C.
c.
(Closed) Item 50-339/77-35-05, Revirculating Spray Pump Motors-Low Meggaring (Unit 2). The inspector reviewed the VEPC0 interim report dated August 17, 1977, serial number 345, and the final report dated November 14, 1977.
Inspection of the earlier repair work on the motors for the subject pumps, 2RSPIA and 2RSPIB was reported in IE Report 50-339/78-33. The inspector reviewed the final meggar QC reports dated March 26, 1979 for 2RSP1A and April 5, 1979 for 2RSPIB. The repair work is documented by E&DCR 13360. The inspector observed the motors as installed. The cables enter the motors from the bottom of a terminal box on the side of the motor.
An expoxy qualified for post "LDCA" conditions is used to fill the conduit area surrounding the cable near the termination.
d.
(Closed) Item 50-339/79-12-03, Castings for Recirculation Spray Pump Motors (Unit 2). The inspector reviewed the VEPC0 final report dated January 22, 1979, serial number 043, N&D 3655 which documents the corrective action, the rework control forms for motors 1A and IB, and the rework inspection checklists for the repair work. The original IB motor was returned to the vendor for repair and a replacement motor from Surry was installed. The QC report of the completed retest of the IB motor was reviewed. The inspector observed the installation of the 1A and IB motors.
e.
(Closed) Item 50-339/79-21-04, Limit Switch Actuating Arms (Unit 2). The inspector reviewed the VEPC0 interim letter dated March 26, 1979 and subsequently the final report dated April 19, 1979. The inspa: Lor reviewed N&D 3721, E&DCR 6789, Rework Control Form Number 1-740 for the work involved in removing the clamp rod arms and clamps and with stronger actuating arms per N&D 3721 for designated Masoneilan valves in the reactor coolant, safety injection, charging and sampling systems. Retesting of the valves was performed per procedure TIP-4 " Checkout Procedure for Air Operated Valves and Dampers". The inspector observed representa-tive valves that had been changed and reviewed representative rework control forms and rework inspection check lists. The checkout procedure verifies the installation and determines by a functional test that,the components and devices operate, control and perform in accoraande with accordance with the requirements N&D 3721 was completed and signed by FQC on April 9, 1979.
f.
(Closed) Item 50-339/79-12-05, Hydraulic Transient in Recirculation Spray Coolers (Unit
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The inspector reviewed the VEPC0 final report dated April 1, 1979, serial number 080B and other related 2313 212
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t-4-documentation including the vendors analysis of the structural capabilities of the subject coolers for the hydraulic transient which would occur with the startup of the recirculation spray pumps. The design of the coolers has been found to be adequate.
No modifications are required to the existing design.
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(Closed) Item 50-404/405/78-07-06, Recirculation Spray Coolers Vent Problem (Units 3 and 4). The inspector reviewed the VEPC0 final report dated July 31, 1978 and the supplemental report dated April 10, 1979, serial number 383B. The existing cooler design is satisfacotry and capable of withstanding the startup hydraulic transient. Vent piping will be appropriately sized and supported.
The coolers will be vented to a suitable location inside the containment.
No items of noncompliance nor deviations were identified.
6.
Site Preoperation - Blasting (Units 3 and 4)
The inspector reviewed the VEPC0 Construction QC Procedure Number 10.4, entitled Blasting Control and NAS 30110, Specification for Excavation for Structures, Section 2, Excavation (section relative to blasting),
and blasting data sheets representative of typical work conducted since January 4, 1979, when VEPC0 assumed QC responsibility for the blasting work on Units 3 and 4.
On April 11, 1979, the inspector observed blast 322, a string of time delay shots to remove high spots of rock north of the auxiliary building. The affect of the blasting was routinely monitored by recording accelerometers, blast mats were used appropriately, safety precautions were taken, and experienced personnel were utilized for the work. The potential for structural damage was minimal due to the size of the charge the distance to the nearest structure, and other parameters as limited by NAS 30110 requirements and the Blast Data Sheet for blast 322.
No items of noncompliance or deviations were identified.
7.
10 CFR Part 21 Inspection (Units 2, 3 and 4)
The site facilities were inspected to determine if the posting require-ments specified in 10 CFR 21.6 had been implemented. The licensee had posted notices prepared per 10 CFR 21.6(b) in four conspicuous locations in the construction area. The posting requirements of 10 CFR 21.6 had been implemented at North Anna.
No items of noncompliance or deviations were identified.
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Independent Inspection The inspector toured the Unit 2, 3 and 4 facilities, the ptorage areas, 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. Limited work on the rebar and concrete for the containment vessels for Units 3 and 4 has been initiated.
No items of noncompliance or deviations were identified.
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