IR 05000412/1979003
| ML19225B141 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/12/1979 |
| From: | Folsom S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19225A931 | List: |
| References | |
| 50-412-79-03, 50-412-79-3, NUDOCS 7907230727 | |
| Download: ML19225B141 (6) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-412/79-03 Docket No.
50-412 License No.
CPPR-105 Priority
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Category A
Licensee:
Duquesne Light Company 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Facili ty Nma:
. Beaver Valley Power Station, Unit *
Inspection at:
Shippingport, Pennsylvania Inspection corducted: March 6-9,1979 Inspectors:
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/ 'f S. A. Folsom, Reactor inspector date/ signed
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[j). P. Uurr, Reactor inspector date signed date signed Approved by:
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R.' W. McGaucjhy, Shig, Projects.
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ste signed
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RC&ES Branch Inspection Summary:
Inspection on March 6-9, i979 (Report No. 50-412/79-03)
Areas Inspected: Routine, unannounced ir.spection by two regional based inspectors whicn commenced on the 4-12 shift on March 6, 1979.
The inspector examined equipment stcrage, reviewed welding quality assurance procedures, and inspected welding on safe h-related riping.
The inspector also performed a plant tour and reviewed licensee action on previous inspection findings.
The inspection involved 34 inspector-hours onsite by two NRC recional based inspectors.
Results: Of the six areas inspected, no items of noncompliance were identified in five areas; one apparent item of noncompliance was identified in one area.
44b Region I Form 12 7 90723 0 7,7 (D (Rev. April 77)
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DETAILS 1.
Persons Contacted Duquesne Light Company
- Mr. L. E. Arch, Senior Quality Assurance Engineer Mr. H. N. Crooks, Supervisor, Administrative Services
- Mr. R. Coupland, Director of Quality Control
- Mr. F. G. Curl, Construction Er.gineer
- Mr. C. R. Davis, Senior Quality Assurance Engineer Mr. H. H. Fetchen, Quality Control Engineer Mr. M. Hartman, Quality Control Engineer Mr. G. Maksin, NDE Field Supervisor Mr. G. Martin, NDE Supervisor, Level III
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- Mr. D. Rohm, Quality Control Engineer Mr. J. Shoemaker, Quality Control Engineer, Storage
- Mr. W. H. Sikorski, Quality Assurance '>pervisor Mr. R. Washabaugh, Manager, Quality Assurance Department Mr. R. L. Williamson, Quality Control Inspector Schneider, Inc.
- Mr. G. Bush, Welding Engi'aer
- Mr. C. W. Hilster, Project
.ntger Mr. W. J. Murray, Craft Support Supervisor Mr. J. W. Nickel, Field Engineer
- Mr. G. F. Sessler, Sita Quality Assurance Manager Stone and Webster
- Mr. R. F. Blake, Site Engineering Office Engineer Mr. W. K. Kollman, Material Controller
- Mr. A. C. McIntyre, Site Engineering Office Head M".
A. Niederst, Boilermaker
- Nr. H. W. Thomas, Assistant Superintendent
- Mr. v. E. Williams, Resident Manager Sicurity Bureau, Inc. (Security Services)
Mr. D. L. Denver, Clockman Mr. A. W. Fowler, Shift Sergeant i
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Other personnel Mr. T. L. Szymanski, Instructor, Career Management Branch, NRC Headquarters The inspector also interviewed other licensee and contractor personnel during the inspection including construction craftsmen.
- denotes those present at the exit interview.
2.
Plant Tour The inspector observed work activities in progress, completed work, and plant status in the containment, primary auxiliary building, and pipe fabricatio.: shop.
Specific activities observed included installation of containmant penetrations, insta%ation of electrical cable trays, rigging, equipment handling, and in-place storage practices.
The technical aspects of the work were discussed with craftsmen, supervisors, and quality control technicians.
The letdown heat exchanger, 2CHS-E-22, was observed by the inspector to be without the nitrogen ourge blanket on the tube side.
It was determined that the heat exchanger was recently moved from the storage area to its present location in the Primary Auxiliary Building.
A review of the Equipment Maintenance Nitrogen Blanket Log for the month of February disclosed that regular inspections are being performed and that the latest inspection was completed on February 28, 1979.
It appears that the nitrogen blanket was lost subsequent to its move from storage The licensee issued a Nonconformance and Disposition Report No. 6141, which directs that the nitrogen blanket be re-estab-lished.
The ir.spector had no further questions concerning this matter.
The Nuclear Class 3, 3" diameter, pipe-to-valve weld, 2CHS-010-F02, had what appeared to be excessive slope relative to the welded diameter transition requirements.
The applicable code, ASME III, 1971 Edition, with Winter 1972 addenda, paragraph NB-4425, requires that the length to offseg ratio be not less than 3 to 1.
A 3 to 1 slope is equivalent to an 18 rise.
The weld joint was measured by the licensee to be U
approximately 35.
The failure to provide the proper weld slopes for piping diameter trans?tions in accordance with the applicable code is contrary to 10 CFR 50, Ap endix B, Criterion IX.
This is an ' tem of noncompliance.
(412/79-03-01 445 352
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3.
Licensee Action on Pruvious Inspection Findings (Closed) Unresolved item (78-14-01): Grout tes ting.
The inspector examined several Master Builders Certificates of Confonnance fcr shipments of Masterflow 713 Grout, for example, Purchase Order 2BV51918, 33,000 lbs., Lot 713BR287, signed by Master Builders Quality Control, which included the statement that this Masterflow 713 Grout is formulated to be ased, and in contact with, anchorage stresses to less than 80,000 psi.
The inspector also examined the following:
Letter from the licensee io the si.one and Webster Prcject
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Engineer, January 22, 1979, with attached reports en non-shrink cementitious mixtures (grout) which showed that per-formance was acceptable.
Stone and Webster letter to the licensee's Directcr of Quality
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Control, February 9,1979, which included Masterflow 713 Grout in the listing of acceptable materials.
This item is considered resolved.
4.
Safety Related Piping - Observation of Welding The inspector observed the final cover welding pass on the Nuclear Class 2, 8" diameter, pipe weld 2-SIS-006-F-511.
He verified that the following listed attributes conform to selected requirements of the ASME III Code, Specification 2BVS-920, and the Schneider Nuclear Site Quality Assurance Manual:
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Welding sequence in accordance with the ASME Weld Data Sheet.
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Welding base and filler metals in accordance with the Weld Procedure Specification SPBV300H.
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Welding parameters, such as interpass temperature, purge gas, and gas flow rates were within the specified limits.
No items of noncompliance were identified.
5.
Reactor Coolant Loco and Safety Related Piping - Review of Quality Assurance Procedures A selective review of the licensee's quality assurance program procedures for pipe welding was performed. The review was to deter-mine that the requirements of the Beaver Valley Power Station, 445 353
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Unit 2 PSAR, Chapter 17; the ASf'E Code Sections III and IX; and NRC Regulation.e are being implemented. Selected portions of the fc110 wing documents were reviewed: the Duquesne Light Company (DLC) - Design and Construction Quality Assurance Program; DLC - Site Quality Control Manual; DLC - Site Quality Control (SQC) Inspection Plan Manual; D'C - SQC Nondestructive Examination Manual; DLC - SQC Calibration Manual; DLC - SQC Training Manual; Schneider, Inc. Nuclear Site Quality Assurance Manual; and Schneider Construction Procedures.
The review confirmed that procedures have been established' to control audits, quality requireme its, work activities, materials, corrective action, documents, test.quipment, and quality records for pipe welding activities.
fio items of noncompliance were identified.
6.
Storace of Reactor Vessel, Steam Generators, Pressurizer and Neutron Shield Tank The inspector examined the reactor vessel, steam generators and neutron shield tark in storage to detennine whether the requirements of Stone and Webster's Procedure FCP-ll were being met.
Quality control personnel responsible for storage were interviewed and selected storage records were examined. The specified storage con-ditions include dunnage, condition of seals, protective coating, humidity indicators and maintenance e' internal inert gas pressure.
The documentation reviewed included.
Stone and Webster Equipment Si.orage Specification 2BV-!.
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Stone and Webster Field Construction Procedure FCP-ll, Material
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Control Program.
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Nonconformance and Disposition Reports (N&D's) 4012, 4013, and 4015, with closecuts, regarding painting, documentafion, and nozzle sealing.
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Stone and Webster Equipment Storage History Cards, from October 1978 through February 1979.
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Schneider Nitrogen Blanket Log for February 1979.
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Schneider Pressurizer - Log for February 1979.
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Schnieder Reactor Vessel Head - Log for February 1979.
No items of noncompliance were identified.
445 354
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7.
Exit Interview The inspector met with licensee and contractor representatives (denoted in Paragraph 1) at the conclusion of the inspection on March 9,1979.
The inspector summarized the scope and findings of the inspection as described in this report.
445 355