IR 05000382/1981011

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IE Insp Rept 50-382/81-11 on 810413-16.No Noncompliance Noted.Major Areas Inspected:Observation of Work & Review of Records for safety-related Instrumentation & Electrical Cables
ML20037D193
Person / Time
Site: Waterford 
Issue date: 05/06/1981
From: Randy Hall, Andrea Johnson
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20037D189 List:
References
50-382-81-11, NUDOCS 8105220197
Download: ML20037D193 (7)


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O U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

REGION IV

Report: 50-382/81-11 Docket:

50-382 Category A2 Licensee: Louisiana Power and Light Company 142 Delaronde Street New Orleans, Louisiana 70174 Facility Name: Waterford Steam Electric Station, Unit 3 Inspection at: Waterford Site, Taft, Louisiana Inspection Conducted: April 13-16,1981 Inspector:

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Reactor Inspector, Engineering and Materials Date Other Accompanying Personnel : M. J. Roberds, Reactor Inspector Aide, Engineering and Materials Section

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Approved:

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R. E. Hall, Acfing Chief, Engineering and Materials Section 06tef Inspection Summary:

Inspection on April 13-16,1981 (Report 50-382/81-11)

Areas Inspected:

Routine, unannounced inspection of construction activities including inspection of Reactor Turbine Generator control boards; observation of work and review of records for safety-related instrumentation and electrical cables; and follow up of a previously identified unresolved item.

The inspection

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l involved twenty-fi,e inspector-hours by one NRC inspector.

Results:

In the areas inspected, no violations or deviations were identified.

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DETAILS 1.

Persons Contacted Principal Licensee Employees

  • L. L. Bass, Project QA Manager
  • R. G. Pittman, Project QA Engineer
  • R. G. Bennett, Project QA Engineer T. F. Gerrets, QA Manager
  • B. M. Toups, Project QA Engineering Technician Other Personnel E. J. Ritzmann, Project QC Manager, Fischbach and Moore (F&M)

E. T. Thompson, QC Inspector, F&M

  • L. A. Stinson, Site QA Program Manager, Ebasco J. Gutierrez, Site QA Engineer, Ebasco The NRC inspector also interviewed other licensee and contractor personnel including members of the engineering and QA/QC staffs.
  • Denotes those attending the exit interview.

2.

Licensee Action on Previously Identified Inspection Findings (Closed) Unresolved (50-382/80-28): Reactor Turbine Control Board Wiring Separation. The unresolved item relating to control board wiring has been resolved as discussed in paragraph 3.b of this report.

The NRC inspector had no further questions on this matter.

3.

Safety-Related Electrical and Instrumentation Cables and Terminations a.

Observation of Completed and In-Process Work The NRC inspector traced out the total route of four safety-related (fuel Handling Building HVAC) instrumentation and electrical cables to ensure that the cables had been installed in accordance with FSAR, Ebasco specifications, LP&L procedures, F&M procedures, and industry standards. The cables were checked for routing, color coding, race-way installation, identification, separation, and correct size.

The following cables were inspected:

31231A-PB 31230A-PA 31228A-PB 31238E-SA No violations or deviations were identified.

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b.

Inspection of' Reactor Turbtne' Generator Control Boards The NRC inspector also inspected the Reactor Turbine Generator Control Boards (CP-1, 2, 7, 8, and 18) in the Main Control Room and the Reactor Turbine Generator Auxiliary Control Board (LCP-43)

located remotely from the Main Control Room. The Ebasco Engineering Field Change DCN-NY-IC-426, dated February 18, 1981, to the above control boaros as reflected on the following Ebasco wire trough detail "as built" drawings was reviewed:

1564-9160 R3, Rev. EF-2 1564-9298 R1, Rev. EF-1 1564-9301 R1, Rev. EF-1 1564-9333 R2, Rev. EF-1 1564-9336 R2, Rev. EF-1 1564-9338 R2, Rev. EF-1 The control board modifications, as ordered by DCN-NY-IC-426, correc.ed the physical clearance and separation of wireways / trough problems cited as an unresolved item during NRC inspection 80-28 on October 21-24, 1980. The conflict between the "as built" control board drawings and maintaining the required separation distances required Ebasco to investigate reasons why the control board supplier (Reliance) did not build in compliance with Ebasco's Procurement Specification LOU 1564.415. Specification LOU 1564.415 requires compliance to Industry Standards IEEE 323-1971, 344-1975, 383-194, 384-1974, and 420-1973 to meet Regulatory Guide 1.75, " Physical Independence of Electrical Systems," criteria.

The minimum internal control board separation distance between.

Class IE division cabling and non Class !E cabling has been estab-lished by analysis r,f the proposed control board installation by Reliance.

This analysis has been based on the tests performed to determine that flame retardant characteristics of the wiring, wiring materials, equipment, and other materials internal to the control boards are in compliance with IEEE 384-1974, Section 5.

Reliance has elected to employ the use of ba-riers (1/4" glastic -

flame retardant sheet stock, UTR grade 1494) in lieu of maintaining the minimum separation distances of 6 inches anc I inch as cited during NRC Inspection 80-28.

Ebasco Enginee-ing Field Change DCN-NY-IC-426, as implemented, now meets the internal separation requirements of Ebasco Procurement Specification LOU 1564.415.

The NRC inspector verified that the modifications to the control boards were in agreement with Ebasco Engineering Field Change DCN-NY-IC-426 and reflected accurately on the above "as built" drawings under Revision EF-1 and EF-2, respectively.

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inspector also verified that the Engineering Field Change was implemented on site appropriately by F&M t. raftsmen under Reliance supervision, witnessed ansi signed off by Ebasco QA/QC, and observed by LP&L QA. Ebasco QA Audits 1383 (February 18,1981) and 1182 (February 21,1980) verified that DCNs were being implemented effectively and were programmatically in control.

No violations or deviations were identified.

c.

Instrumentation / Electrical Cable Environmental Qualification Documentation Records A review of the environmental qualification documentation records relative to 15 safety-related instrumentation and electrical power / control cables, selected for quality record review during the NRC inspection of March 2-6,1981 (NRC Report 81-05), was performed.

B/M Reel numbers, from the document review of March 2-6, 1981, were used to obtain the environmental qualification documentation for review (B/M Reel Nos. D25-04, D50-01, D50-03, D50-06, D74-01, and 083-01) in support of the following type cables:

(1) 600V, 2C, 14AWG, 7 strand, nonshielded, Neoprene Jacket over single conductors and Hypalon Jacket overall Manufacturer: The Okonite Company, Passaic, New Jersey Manufactured in accordance with Ebasco Procurement Specifica-tion LOU 1564.267, Revision 5, June 30, 1975 The following environmental qualification documentation and records were reviewed by the NRC inspector:

Ebasco QA Engineering Records / Documentation Checklist (Site QA Records Review Shaet)

i Ebasco Materials Engineering and Vendor Quality Compliance Report (Release for Shipment)

Ebasco Materials Engineering and Quality Compliance Deviation Report No. 3 (Change from Neoprene to Hypalon Jacket)

Okonite Certified Test Report No. 591, July 23,1975 Okonite Inspection Sheet for wire and cables Okonite QA Traceability Schematic Okonite Physical Test Report for Aging Properties, Oil Immersion Aging, and Vertical Flame Tests i

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Okonite letter of certification, April 3,1975, for gravimetric and accelerated water absorption, dielectric constant, and ozone resistance The above environmental qualification documentation was reviewed by the NRC inspector to substantiate that Okonite had met their responsibilities in perfonning the required testing and quality control for qualifying the above electrical cables as Class IE in accordance with IEEE 278, 323, 383; IPCEA 5-19-81; IPCEA 5-68-516 (Interim Standard No. 1); LOU 1564.267 Nuclear Addendum (prototype testing requirements); LOU 15E4.267 para-graph 3.3 (flame tests); and Ebasco Specification 860-72 (quality control requirements).

(2) 300V, 14AWG, and 20AWG instrumentation cable (2, 4, and 6 conductor twisted shielded pair, twisted quad, and 9 conductor shield), ethylene propylene rubber insulation, heavy duty chlorosulphonated polyethylene jacket overall Manufactured: Samuel Moore and Company, Aurora, Ohio Manufactured in accordance with Ebasco Procurement Specification LOV 1564.269C, Revision 4, February 1,1977 The following environmental qualification documentation and records were reviewed by the NRC inspector:

Ebasco QA Engineering Records / Documentation Checklist (Site QA Records Review Sheet)

Ebasco Materials Engineering and Vendor Qualtiy Compliance Report (Release for Shipment)

Samuel Moore Certificate of Compliance, meeting Ebasco Specifications:

LOU 1564.269C, Revision a IPCEA 5-19-81 IPCEA 5-68-516

ASTM D4.2 ASTM B33 l

ASTM B.8 l

Ebasco Receiving Inspection Report, February l',1977 l-5-

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Samuel Moore Laboratory Inspection Reports to meet IPCEA 5-19-81 including:

General Lab Report (flame test)

Tensile Property Test Heat Distortion Test IR DC Voltage Applied Test Water Immersion Test Gravimetric Test on Jacket Accumulated Water Absorption Test Tensile Strength and Elongation Tests Environmental Laboratory Test Report - Flame Test-Franklin Institute prepared for Samuel Moore and Compan.y No. F-C476-1, August 1977, meeting Ebasco Specification LOU 1564.267 for IEEE 323-1974 and IEEE 383-1974 Environmental Laboratory Test Report - Qualification Test of Thermally Aged Electric Cables under a simulated LOCA/DBE by Sequential Exposure to Environments of Radiation, Steam, and Core Spray.

Prepared by Isomedix, Inc., Parsippany, New Jersey, for Samuel Moore and Comoany, May 1976 The above environmental qualification documentation was reviewed by the NRC inspector to substantiate that Samuel Moore and Company had met their responsibilities in performing the required te>',ing and quality control commitments in qualifying the above instrumentation cables as Class IE in accordance with IEEE 323-1974, 383-1974; IPCEA 5-19-81; IPCEA 5-68-516 (Interim Standard No. 1);

LOU 1564.269C Nuclear Addendum (prototype testing requirements);

l LOU 1564.269C paragraph 3.o (flame tests); and Ebasco Specifica-l tion 860-72 (quality control requirements).

(3) Thermocouple wire, 2 conductor, type KX-XLPE/NE0-CA

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Manufactured:

Cerro Wire and Cable Company in accordance with

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Ebasco Procurement Specification 211-73 l

The following environmental qualification documentation and records l

were reviewed by the NRC inspector:

Ebasco Material Receiving Inspection Report No. 75-1783

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Ebasco QA Engineering Records / Documentation Checklist (site QA Records Review Sheet)

Ebasco Materials Engineering and Quality Compliance Deviation Report No.1, September 1,1975 (change from Neoprene to Hypalon Jacket)

Ebasco Materials Engineering and Vendor Quality Compliance Report (Release for Shipment, Note: released and accepted with Neoprene Jacket)

Cerro Wire and Cable Company Certification of Compliance

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meeting Ebasco Specification No. 211-73 for IEEE 383 requirements (radiation, LOCA)

Cerro Wire and Cable Company Certification of Conformance June 9, 1975 (as above)

Cerro Wire and Cable Company QA Traceability Log Cerro Wire and Cable Company Certified Test Report June 9, 1975 Cerro Wire and Cable Company Generic Certified Test Report -

Firewall III The above environmental qualification documentation was reviewed by the NRC inspector to substantiate that Cerro Wire and Cable Company had met their responsibilities in performing the required testing and quality control commitments in qualifying the above thermocouple cables as Class IE in accordance with IEEE 323, 383; IPCEA 5-19-81; IPCEA 5-68-516; and Ebasco Procurement Specifica-tion (211-73) requirements for prototype testing, flame testing, and quality control requirements.

No violations or deviations were identified.

4.

Exit Interview The NRC inspector met with the licensee representatives (denoted in para-graph 1) at the conclusion of the inspection on April 16, 1981. The NRC inspector summarized the purpose, scope, and findings of the inspection.

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