IR 05000404/1981002
| ML20010J081 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 08/14/1981 |
| From: | Debbage A, Upright C, Wright R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20010J055 | List: |
| References | |
| 50-404-81-02, 50-404-81-2, NUDOCS 8109290575 | |
| Download: ML20010J081 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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E REGION 11
o 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303
[MMb 8 //3 /8/
R. W. Wright
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Date Signed LUw Y/
A. G. Uebbage,
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Date S'igned Approved by:
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C. M. Sprightdection Chief Date' Signed Engineering Inspection Branch Engineering and Technical Inspection Division SUMMARY i
Inspection on July 27-31, 1981 l
Areas Inspected l
This routine, unannounced inspection involved 68 inspector-hours onsite in the areas of extended construction delay implementing procedures; observation of work
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and work activities; review of quality records; and licensee action on previous
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inspection findings.
l Results l
Of-the four areas inspected, no violations or deviations were identified in three areas; cne violation was found in the storage area (Failure to follow storage requirements for reactor containment dome plates paragraph 5.c.(1)(d)).
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- S. C. Brown, Jr., Senior Vice President, Power Station,
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Engineering & Construction (PSE&C)
- J. V. Harrison, Project Manager, PSE&C
- P. G. Perry, Site Manager, PSE&C
- G. A. Helm, Manager, QA Engineering and Construction Projects
- S. B. Riggs, Resident Quality Control Engineer (RQCE)
- F. B. Motley, Senior QC Inspector (SQCI)
- L. E. Carter, Senior QC Engineer (SQCE)
- D. S. Hart, Senior QC Engineer (SQCE)
- W. F. Shaw, Preventive Maintenance Supervisor
- W. L. Mabe, Services and Controls Coordinator Other licensee employees contacted included QA/QC inspectors, security force members, and office personnel.
- Attended exit interview 2.
Exit Interview
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The inspection scope and findings were summarized on July 31', 1981 with those persons ina1ceted in paragraph I above.
3.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item 404,405/79-2-1:
Humidity in internals of components in storage. VEPC0 has upgraded its storage facilities for B&W equipment to allow for extension of its warranty.
B&W conducts monthly storage inspections of NSSS equipment in accordance with a warranty extension contract administered by VEPC0 engineeriag. VEPCO QC inspectors accompany B&W QC inspectors on these inspections and the results are forwarded to the VEPCO RQCE for review and action, if required. The present
method of storing the steam generators is in enclosed build'ngs with primary and' secondary nitrogen purge. The pressurizers are also stored in enclosed
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buildings using internal desiccants to control humidity. These items were inspected during this inspection (paragraph 5.c.(1)(c) to ensure proper
environmental protection and preservation measures were being maintained.
B&W's lef.ter (NBC 385) dated June 12, 1981 states, "the present method of storing the generators appears to be adequate to prevent hardware deterioration." Equipment storage and history cards for the subject steam generators and pressurizers were examined and VEPC0 records revealed their
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refurbishment is completed-for these components.
Equipment storage and history cards examined for the reactor vessel internals also revealed s
corrective actions taken appear to have been adequate to prevent recurrence of the humidity problem. This item is closed.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Extended Construction Delay
a.
Construction Status In the fall of 1978, VEPC0 suspended all major construction activity on the site and licensee QC activities have been limited since that time primarily te storage and~ preventive maintenance inspections, maintenance of QA records, and limited material receipts. Unit 3 is still currently undergoing this construction delay status. VEPC0 has announced the cancellation of Unit 4; however, the licensee is
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maintaining Unit 4's materials, equipment and components received onsite 4 accordance with those procedures that apply to Unit 3.
Peter Kiew Son's Company has been awarded the contract to handle th-limited cor. truction activities (caisson, retaining wall, rock anchor,
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and spray pu.- foundation work) necessary-to prepare the Unit 3 site for reactivation.
This work is anticipated to commenua late August 1981. Discussions with the RQCE revealed the existing " Champion". batch
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plant will be employed with VEPCO site personnel performing-the QC functions to include: batch plant, laboratory, in place testing, and concrete placement inspection activities.
Richmond's corporate QA department will audit VEPCO's QC and the construction activity during this phase of work.
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resumes, VEPCO plans to perform the quality assurance function somewhat similar to that which they performed during the construction of North
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Anna Units 1 and 2.
VEPC0 will perform certain quality control work in l
areas outside that covered by the ASME Code utilizing its own QC l
organization supplemented with the contractors QC organizations as
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needed.
The principal contractor selected for ASME code work will provide quality control over the activities governed by the N-stamp.
i When ASME III is invoked, VEPCO QC will assume a QA monitoring audit function on the contractor. VEPCO's Richmond office will audit the construction activities.
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Review of Quality Assurance Implementing Procedures (920518)
.The following QA specifications, procedures, and instructions for
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extended construction delay activities were reviawed to confirm that
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the licensee has established a quality assurance prr' ram to handle Unit 3's limited site construction delay activities.
Specifications NAS-3363, Storage and Maintenance During Storage of Permanent Plant Equipment B&w Field Specification For NSS Components (In-Place) (BWCC 31610)
B&W Amendment to Above Specification - Long Term Storage Specification Manual For B&W Supplied Equipment Quality Assurance Manual Procedures QAM-1.1, Rev. 10
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Organization QAM-5.7, Rev. 1
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Reporting of Items to the NRC as defined by 10 CFR 50.55(e) or 10 CFR Part 21 QAM-6.1, Rev. 4
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Document Control Construction Quality Control Manual Procedures and Instructions CQCM-7.1, Rev. 0
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Receiving Inspection CQCM-10.0, Rev. 0
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Surveillance Inspection CQCM-12.1, Rev. 1
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Control and Calibration of Measuring and Test Equipment CQCM-13.1, Rev.1
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Storage of Materials and Equipment CQCM-13.2, Rev. 0
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Handling and Rigging CQCM-15.1,'Res
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Nonconformance Reports CQCM-18.1, Rev. 2
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CQC Audits CQCM-13.1.1, Rev. 2 -
Storage of Materials and Equipment CQCM-13.1.2, Rev. 0 -
Storage Surveillance Inspection VEPC0 is in a transitional procedural phase tt this time in that the licensee is revising its site CQCM procedurus and instructions to reflect VEPC0's new organizational approach i.s discussed in QAM 1.1, Rev.10 and the proposed construction QA/QC organizational charts which l
were being drafted at the time of the inspection for the revitalization of the North Anna 3 project. The organizational arrangement shown on the subject charts reveals the RQCE on site reports directly to the VEPC0 corporate manager of QA.
The RQCE is directly responsible to
establish and insure the implementation of VEPCO construction QC
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programs for Unit 3.
Supporting the RQCE are four VEPC0 Senior Quality Control Engineers (SQCE) in the administrative, civil / structural, mechanical / piping, electrical / instrumentation disciplines, who prepare QC instructions, train and supervise QC inspectors under their cognizance. The inspectors examined the training, education and i
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experience records of eleven onsite VEPC0 QC personnel. The quarterly QC training schedule for the months of July, August, and September 1981 was examined to verify that required training was implemented. The-licensee is training its personnel in their respective assigned QC inspection disciplinas first, and then cross training their QC personnel. Proceaure QAM 1.1. Rev. 10, assigns stop work authority to the RQCE.
'The licensee has established audit procedures. The inspectors examined a proposed audit schedule which calls for four corporate QA audits to be conducted over a 12 month period covering all applicable 10 CFR 50 Appendix B criteria.
Procedures for identification and disposition of materials and components, control and review of nonconformances, handling conditions adverse to quality, and document control have been generated.
Suspension of construction was at an early date such that material and component receipt and storage was in progress, but no installation or testing of equipment had commen u. Work and inspection procedures examined were found to be approved prior to their use, controlled, and the personnel performing the QC inspection and maintenance activities had them readily available for their use.
The licensee site security which encompasses the buildings and stored
equipment and components for Unit 3 and should prevent unauthorized use or alteration thereof.
Within the above area of construction delay procedural review, no items of violations or deviations were identified.
c.
Work Observation (92053B) and Review of Quality Records (920558)
(1) The following representative safety related items were randomly selected for inspection to ascertain whether applicable construction delay requirements and activities, as delineated by work and inspection procedures are being met, and that related quality work and inspection records reflect work accomplishrtent consistent with applicable mquirements.
(a) The control rod driva sere inspected in the main warehouse in the Level A storige facility. Components of the drives were secured in their shipping crates and stored on shelves in accordance with the vendors recommended procedures. Plant computer cable assembly V014, and electronic display control 31H-CLT-306 were also examined in this. facilty and found stored in their proper Level A environment. The thermometer and psychrometer present in the-Level A storage facility was observed to be currently calibrated and marked. The
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temperature and humidity levels for that day were found to be t
within specification tolerances specified for Level A storage. Weekly inspection records (2/27/81 through 7/1/81)
of Level A storage temperatures and relative humidity readings were examined by the inspector.
(b) High pressure injection valve 3MU-HV51A for the make-up and purification system and two decay heat removal pumps with motors (3DH-PIA, 3DH-P1B).were inspected in a Level B warehouse.
The valve was on a shelf with its internals capped and enclosed in a plastic bag. The humidity indicator examined on the valve was at an acceptable level. The decay heat removal pump motor heaters were found to be activated.
Motor rotation and oil changes were made as required ~ as indicated on the equipment storage and history cards attached to the stored item.
(c) Unit 3's steam generators (3KC-SG1A, 3RC-SG1B)
and pressurizer (3RC-PRE 1) were examined in a locked Level C storage facility. In accordance with B&W's requirements the present method of storing the generators is in enclosed buildings with a. primary and secondary nitrogen purge.
Nitrogen purge pressures for steam generators and humidity indicators associated with the pressurizer indicating internal desiccant material condition were found satisfactory.
Protective coatings, supports and sealed surfaces on the NSS' components were adequate.
(d) The Unit 3 and 4 reactor containment dome liner plate which is stored "on top of the hill" in a Level D environment i
between reactor containments 3 and 4 and the spray ponds was examined. Specification NAS 3048, Specific Requirements for Equipment Storage 011, Rev. 1, entitled " Reactor Containment Dome Plate" specifies that Unit 3 and 4 reactor containment dome plate assemblies shall be stored stacking individual plate assemblies one atop the other in separate stacks.
Additionally, blocks are to be placed between the plates to provide air space between adjacent plates.
Four stacks of dome liner plate were found stored consistent with the above requirements.
However, the fifth stack of reactor containment closure plates did not have the blocks placed between the plates as required to provide an air space between plates.
The above example of " Failure to follow storage requirements for reactor containment dome plates" was identified to the licensee as violation 50-404/81-02-01.
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(e) The inspectors examined Unit 3's rt. actor containment structure. When work ceased, the cont.ainment wall liner
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plate had been erected by CB&I to approximately the spring line and the cylindrical containment reinforced concrete wall had progressed to grade level. The floor liner plate was noted to have been painted to control corrosion, pitting and plate thinning.
Inspection records pertinent to -the floor liner plate painting were examined. The ends of some exposed rebar was noted to have been coated with a preservative. The inspectors reviewed documentation dated September.10,
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October 9, October 16, 1979, and October 28, 1980, relative l
to the corrosion measurements of various ' sizes of reinforcing
steel bars taken from various locations of the reactor i
containment, turbine building, caissons, and yard storage.
All samples exceeded the acceptance requirementsi of ASTM A-615; however, two #18 bars were found to have marginal deformation heights.
(2) General Inspection Findings All items located in storage by using the Warehouse Inventory System Master File Report, were found in proper environment and storage locations as specified by B&W's Equipment Crest or S&W's
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In many cases actual storage levels exceeded. ANSI N45.2.2 requirements. All items (with the exception.of dome liner plate) were observed to be stored and maintained as required in-accordance with approved currrent procedures which were readily available to the persons doing the work. Control and distribution o' procedures and revisions appeared to be adeqcate.
Protective covering, internal preservation, supports, cleanliness, weather protection ana fire protection were all observed to be within the requirements of the particular item in storage.
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Records of nonconforming conditions or activities (N&D Reports, NCR's, Unsatisfactory Reports) pertinent to the above inspected cafety related items were examined to see if they were legible, i
complete, and that proper corrective action was taken.
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Discussions conducted with the supervisor of preventive maintenance revealed he was able to meet his work requirements on schedule with approximately fourteen craftstren (millwrights, pipe fitters, boilermaters and electricians) he has assigned to him. '
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The RII inspectors conducted discussions with the lead calibration inspecter concerning his responsibilities, scops of work,- and knowledge of procedure CQCM 12.1, Rev. 1.
The calibration inspector discussed the chronological sequence of events for issue, retrieval and ~ calibration of all site measuring and test equipment under his control. Calibration records for high-low
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thermometer (Serial No. 6639) observed in use at the Level A storage warehouse were examined and found satisfactory.
The inspector stated he was able to stay abreast of the required frequency of testing and his work load.
Two corporate QA auditors were observed onsite conducting an audit coincident with this RII inspection.
The scope of their audit along with another VEPCO corporate QA audit conducted April 1-2, 1981, were discussed and pertinent audit check lists examined.
Access control to Unit 3 safety related components is essentially the same as prior to the construction delay in that storage areas are fenced with gates, storage buildings and Level A warehouses are padlocked. Security forces man the entrance gate and provide general overall security against unauthorized intrusion.
(3) Records Review-Additional records examined pertinent to the safety related items selected for review included:
(a) equipment storage and history cards (b) QC inspection receiving reports (c) material receiving reports (d) construction QC inspection reports for the reactor containment floor and dome liner plate.
(e) equipment inspection reports for period 5/16/80 - 2/9/81 (f) - monthly storage area inspection reports for period 11/80 -
6/9/81 (g) biweekly equipmert and tank purge inspections for period 11/5/80 - 6/9/81 (h) letters, memoranda and site acknowledgements pertinent-to corporate QA audits of 6/18/79, 9/20/79, 10/25/79 and 12/5/79.
Within the above areas of construction delay work observation, and records review activities examined, no deviations were identified; one violation,
" Failure to 'ollow storage requirements for reactor containment dome plates (paragraph 5.C.(1)(d)) was identified and acknowlecged by the licensee.
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