IR 05000424/1982006

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IE Insp Repts 50-424/82-06 & 50-425/82-06 on 820211-0310. Noncompliance Noted:Failure to Follow Procedures Re Transport of Steam Generators
ML20053E376
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 04/12/1982
From: Brownlee V, Sanders W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20053E352 List:
References
50-424-82-06, 50-424-82-6, 50-425-82-06, 50-425-82-6, NUDOCS 8206070845
Download: ML20053E376 (6)


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UNITED STATES

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E REGION 11

101 MARIETTA ST., N.W., SUITE 3100 o,

ATLANTA, GEORGIA 30303 s

Report Nos. 50-424/82-06 and 50-425/82-06 Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Facility Name: Alvin Vogtle 1 and 2 Docket Nos. 50-424 and 50-425 License Nos. CPPR-108 and CPPR-109 Inspection at Vogtle Nuclear Station llaynesboro, Georgia

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Ddte Signed Approved by: f _

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V. L. Jrownlee, Section Chief, Division of

'%te S4gned Project and Resident Programs SUf1 MARY Inspection on February 11 - !! arch 10,1982 Areas Inspected This routine, announced inspection involved 140 inspector-hours on site in the areas of Heavy Rigging, installation and inspection of Rebar, imbeds, and forms, Concrete pours, Category 1 back fill and compration, piping, NDE of liner shields and inspection of pipe welds.

Reviewed licensee's action on previous inspection findings.

Results Of the eight areas inspected, no violations or deviations were identified in seven areas; one violation was found in one area (Failure to follow procedures -

paragraph 7).

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D; TAILS 1.

Persons Contacted Licensee Employees

  • H. H. Gregory, III, Construction Project Manager
      • W. T. Nickerson, flanager Generating Plant Construction
    • B. F. Barrett, Senior QA Field Representative
    • J. L. Blocke, QC Supervisor
    • W. R. Evans, Project Section Supervisor
  • lt. H. Googe, Manager of Field Operations
    • B. C. Harbin, Project Section Supervisor
    • D. P. Ross, Civil Engineering Supervision
    • C. Sarver, Senior QA Engineer
    • D. F. Wilkerson, Senior Welding Specialist
  • E. D. Groover, QA Site Supervisor

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Other licensee employees contacted included technicians, quality control inspectors, supervisors and office personnel.

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Other Organizations H. R. Reuter, Resident Engineer - Betchel Power Company W. G. Uhouse, Resident Engineer - Betchel Power Company J. R. Runyan, Quality Assurance Manager - Pullman Power Piping 2.

Exit Interview The inspection scope and findings were reviewed in a meeting held March 4, 1982 and were summarized at the monthly exit meeting on itarch 12, 1982 with i

those in attendance as noted by asterisks.

      • Personnel attending flarch 4 meeting only
    • Personnel attending March 12 meeting only.
  • Personnel attending both meetings 3.

Licensee Action on Previous Inspection Findings (Closed) Unresolved Item 424, 425/82-04-01 Load Test of Transporter.

This item was considered unresolved pending additional information relative to the clarification of the requirements for load testing the transporter and the rationale for the elimination of the 10% incline road test.

Additional infonnation was obtained by correspondence M-2807 from the Heavy Rigging Coordinator and a meeting with Georgia Power site Mechanical Engineering.

The inspector was infonned that procedure HRP-7 was originally written for the load testing of a rented, chain driven transporter that was subsequently used to transport the Reactor Pressure Vessel from the river to

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the NSSS storage yard and was no longer applicable even though it was still

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included as part of the program HPJ-32. The rationale for the elimination of the included road test of the transporter used to move the steam generator was based on the design of the transporter (flanitowoc 4100) which has a hydraulic travel drive system in lieu of chain drive and travel brakes which are spring set and automatically apply in the event of a charge pressure loss to the hydraulic motors.

Although both crawlers are equipped with brakes, the specifications state that the brake on one crawler frame can hold a 400 ton load in a 10% grade.

The transporter was load tested on level ground at the facility with test weights equal to 884,600 lbs.

The licensee has stated by letter that a review of all Heavy Rigging Programs (HRP) procedures will be made prior to the next (HRP) activity, currently scheduled for flay,1982, (Unit 2 pressurizer).

This item relative to the actual load testing is considered resolved, however the failure to follow procedures is considered to be severity severity level 6 Violation and is described in the following paragraph 4.

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Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-tions. A new unresolved item identified during this inspection is discussed in paragraph 6.

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Plant Tours During this reporting period, inspections were periodically made through the power block and other sections of the facility to inspect the work in progress for obvious defects or noncompliance with regulatory requirements and license conditions.

Particular note was made of the presence of quality control inspectors and Quality Control evidence such as inspection records, material identification, nonconforming material identification, material protection and housekeeping.

The inspector interviewed craft personnel, supervision, Quality Control Inspectors as such people were available in the work areas. The inspections included:

Observation of Quality Control inspection of imbeds, rebar and forms

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for wall A11-032 prior to pour Observation of Isothermic copper welding of bolting ground plate to

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copper cable in wall A11-A-080. per X3AR01 Installation of rebar in primary containment, Control Auxiliary

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building, and control building Observed the layout for the location of ths shield walls in the Unit 2

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Primary Containment. The locations were established using an optical Theodolite

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Observed the placement, moisture preparations, compaction and

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inspection of the category 1 back fill between the No.1 Primary Containment and the Administration building. The acceptance criteria appear in the Bechtel Specification X2AB01 " Site Preparation and Earth Work" and Georgia Power procedure CD-T-01 " Earth Work Quality Control" Visually inspected Spent fuel cooling and purification system piping

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1-1213-005-S-05 which will subsequently be imbedded in the fuel pool walls.

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An inspection was made of the installation and shop fabrication records for the primary shield liner plate assembly and the reactor vessel support seat.

These two items were fabricated by a sub-contractor to the requirements of specification X2AG05.

It was noted that for purposes of identifying the work to be performed by the contractor, the technical requirements are specified in two parts.

Part 1 consists of items in accordance with ASt1E Section III, Division 1, Nuclear power plant components, subsection NF.

Part II contains those items fabricated in accordance with A.W.S and ASTM specifications. The items selected for this inspection were taken from both parts of the specifications:

X2AG05 - Part 1 - Reactor Vessel Support Seat.

X2AG05 - Part 2 - Primary Shield liner Plate.

Periodic inspections were made throughout the fit up preparation and welding of the Primary Shield liner plate sub assemblies for compliance to the requirements of the AWS D1.1 structual welding code. The review of NDE requirements revealed a difference between the fabrication specification X2AG05 and the installations procedure X2AP01 relative to the N.D.E to be applied to the welds. X2AG05 para 7.2 states that all welds shall be examined by the maginetic particle method.

Whereas X2AP01 only requires a visual examination.

This discrepancy in N.D.r, requirements has been transmitted to the licensee with a request for additional infonnation relative to justification for the differences and evaluation of the field examination of visual examination only.

This is unresolved items.

(50-424,425/82-06-01).

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Heavy Rigging Program An examination of the activities and a review of the records relative to the off loading and movement of the (4) Unit 1 Steam Generators from the barges to the N.S.S.S. storage yard reveal certain activities which were not performed in accordance with the referenced procedures as described.

Heavy Rigging Procedure (HP,P)-32 Rev. 3 section VI - Inspection states "The following shall be inspected and documented by the Georgia Power Company inspector concerning the transhipping, transporting and setting to storage of steam generators for Unit 1".

This procedure also lists items for inspection and states "the road and transporter tested per procedure no.

HRP 7 records on file".

This procedue HRP-7 Rev. O item 12 states "the transporter will proceed to the storage yard along the river facility road

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to the beginning of the verticle curve, observe the transporter and road bed during the travel period" Step 14 states " Proceed upgrade, Recheck load at start and during horizontal curve." These tests were not performed and revisions to these procedures were not made according to the requirements of the program which has a provision for revising which states " Revision to these procedures should be allowed only by T. S. Webber - Bechtel SF0, R. W.

Komachi - Bechtel LAPD, T. J. Batchelor-GPC or C. D. Mauldin - GPC. These four persons or others made necessary by Personnel changes will reach agreement on needed revisions and updating of procedures".

Contrary to these requirements the information obtained and records reviewed show that these tests were eliminated and the required procedural steps were rot taken to revise the procedures.

It should be noted that the Steam Generators were moved up the 10 inclince hill without incident, and the Heavy Rigging Coordinater has committed to review and revision as necessary of the Heavy Rigging Program. This failure to follow procedure is considered to be severity level 6 violation.

(50-424/82-06-02).

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Record Review A review was made of the fabrication and Quality related records furnished by the shop fabrication contractor for the weldments listed:

Primary Shield Liner Plate Assembly

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Material test reports for 1" plate SA537 CL1.5 heats were reviewed for

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compliance to the listed specification Material test reports for 3/8" plate, SA537 CL1.3 heats were reviewed

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Supplier Deviation Disposition Requests

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Weld material certification records for 3 lots of Electrodes 3/32",

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1/16" and 1/8" N.D.E Report for flagnetic Particle Examination Report No.14 per

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procedure Bristol Steel HT 0316 - 2. Rev 1 Certificate of compliance for the protective coating material Carbolinc

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Zinc No. 11 A review of the records for the Reactor Vessel Support Seat assemblies (4-1 MIC, 4-1-MIA, 4-1-MIB, 4-1-tilD) was made as listed ibterial test reports for 3 heats of material A578-77C

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Weld material certifications for 2 heats of material 5/32" and 1/16"

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N.D.E. Reports for Magnetic Particle Examination Report No 34 per

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Bristol Steel Specification M.0316-2 Re _ -

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N.D.E Report for Ultrasonic Examination by the material supplier for 3

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heats of material.

No items of noncompliance were identified.

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ASME Survey The inspector attended the entrance meeting and the exit critique of the ASME Survey team for the site piping contractor, Pullman Power Piping. The survey was conducted by a 5 member team to approve the extension of the stamp authority to the field for NA 1101-3 and NPT 1102-3.

The survey will recommend approval.

No items of noncompliance were identified.

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