IR 05000445/1982009

IE Insp Repts 50-445/82-09 & 50-446/82-04 on 820427-0527.No Noncompliance Noted.Major Areas Inspected:Const Activities, Site Tour,Review of Records for Spent Fuel Racks,Protective Coatings,Electric Cable Installation & Calibr Records

ML20055B904
Person / Time
Site:	Comanche Peak
Issue date:	06/29/1982
From:	Boardman J, Crossman W, Hunnicutt D, Clay Johnson, Redano R, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20055B896	List: IR 05000445/1982009 ML20055B895
References
50-445-82-09, 50-445-82-9, 50-446-82-04, 50-446-82-4, NUDOCS 8207230527
Download: ML20055B904 (8)

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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-445/82-09 50-446/82-04 Docket: 50-445 Category A2 50-446

, Licensee: Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 Facility Name: Comanche Peak, Units 1 and 2 Inspection at: Comanche Peak Steam Electric Station Inspection conducted: April 27 to May 27, 1982 Inspectors: [/ e , -- , f g2-J. R. Boardman, Reactor Inspector, Reactor Project Section B Date t

1. (Paragraphs 1,2,7,8,and9)

C. E. Johr4 , Rhactor 4 Liv W spector,tEngineering Section h-29-OL-Date (Paragrapt ,2,3,4,@and9)

R. T. Reda h A bv M Repcto'r Irfjpector, Gngineering Section 6-2.9-9>t Date~

(Paragrap , 2, 5, 6, 4nd 9)

Reviewed- . #f T. F. Westerman, Chief, Reactor Project Section A Date Approved: --

W. A. Crossman, Chief, Reactor Project Section 8

[Datef[L B207230527 020706 PDR ADOCK 05000445 G PDR

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-2-Approved:

D. M. Hunnicut Mh lo-Z9 -BL Date Chief, Engi@ering Sekttion Inspection Summary Inspection conducted April 27 to May 27, 1982 (50-445/82-09)

Areas Inspected: Routine, unannounced inspection of construction activities including a site tour, review of records for spent fuel racks, protective coatings, electrical cable installation, installation tool calibration records, and procurement documentatio The inspection involved.61 inspector-hours by three NRC inspector Results: Within the six areas inspected, no violations or deviations were identifie Inspection conducted April 27 to May 13, 1982 (Report No. 50-446/82-04)

Areas Inspected: Routire, unannounced inspection of construction activities including a site tour and review of procurement documentation. The inspec-tion involved 16 inspector-hours.by one NRC inspecto Results: Within the two areas inspected, no violations or deviations were identified, i

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-3-DETAILS Persons Contacted Prinicipal Licensee Employees

• D. N. Chapman, Quality Assurance Manager TUGC0

+#*R. G. Tolson, Site Quality Assurance Supervisor, TUGC0 B. G. Scott, Quality Engineering Supervisor, TUGC0

• C. T. Brandt, QA/QC Supervisor - Mechanical / Civil, TUGC0 Other Personnel T. Brown, Quality Engineering, TUGC0 C. Dupre, Mechanical Engineer,'TUSI D. Dybala, Mechanical Engineer, Westinghouse J. Gore, Warehousing Supervisor D. Kissinger, Project Civil Engineer D. Leigh, QA Special Project Staff Assistant, Brown & Root (B&R)

R. Meissner, Project Quality Engineer, B&R J. Walker, QA Engineering, TUGC0 H. Williams, QC Superintendent, B&R

• Denotes those attending exit interview on May 12, 1982

1. Denotes those attending exit interview on May 13, 1982

+ Denotes those attending exit interview on May 27, 1982 The NRC inspectors also contacted other licensee and contractor employees during the course of the inspectio . Site Tour The NRC inspectors toured Unit 1 reactor building, auxiliary building, paint shop, and warehouse storage yard to observe construction in progress and to inspect safety-related equipment storage condition No violations or deviations were identifie . Spent Fuel Storage Racks Review of Procedures / Specifications The NRC inspector reviewed quality control procedures pertaining to receiving, storage, and installation of spent fuel racks by Brown & Root and Westinghouse for Unit Drawings, specifica-tions, work instructions, and inspection procedures have been established to assure technical adequacy of the activites per-taining to spent fuel storage rack >

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-4-The NRC inspector verified that receiving inspection instructions required inspections for damage, conformance to purchase spec-ifications, proper identification, and verification that the proper supplier / vendor documentation was receive Site storage procedures appear to be adequate and they provided for proper identification, handling, and cleanliness preservatio Installation procedures provided adequate instructions for instal-lation and also for dimensional checks for levelness, alignment, and clearance Procedures reviewed are listed below:

CP-QAP-8.1, Rev. 3, "QC Receiving Inspection" CP-QAP-5.1, Rev. 2, "QA Review of Procurement Documents" QI-QAP-8.1-8A, Rev. O, " Receiving Westinghouse Renewal Parts (Supplement)"

QI-QAP-8.1-8, Rev. 4, " Receiving of Westinghouse Safey-Related Equipment" Westinghouse Manual, "NSS Component Receiving & Storage Criteria" Specification F-8, Rev. 8, " Fuel Assembly, Storage and Refueling Equipment Design Interface Specification" (Westinghouse)

" Spent Fuel Storage Rack Installation Procedure," Rev 1, (Westinghouse)

b. Observation of Work and Work Activities The NRC inspector visually examined the new spent fuel storage racks for Unit 1 in the warehouse yard prior to installatio Appearance and size of welds appeared to be adequat Configu-ration of the spent fuel racks appeared to be in conformance with the design drawings. No defects (i.e., cracks, dents, and/or missing parts) were observe Work in progress was not observed on the spent fuel racks during this inspection since there were no ongoing activities being performed. Work had been performed on the spent fuel rack being installed in the containment, but work had been stopped because of a modification change.

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-5- Review of Records

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The NRC inspector reviewed the receiving inspection records for the Unit 1 spent fuel racks. The records indicate that applicable requirements and commitments have been met. All information was documented on receiving inspection reports (IR's). The NRC

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inspector reviewed all documentation contained in the traveler for the spent fuel rack being installed in containmen The traveler contained all necessary information and instructions for proper installation, including leveling, alignment, and clearance The design change authorization (OCA) was present with the-traveler and contained all details and disposition of the spent fuel rack modificatio No violations or devfations were identifie . Protective Coating Review of Procedures The NRC inspector reviewed new and/or revised procedures pertaining to protective coatings inspection for Unit Procedures reviewed have been revised and now include appropriate inspection attributes and inspection forms and checklist for a more detailed inspectio Procedures reviewed were found to be adequat Procedures reviewed by the NRC inspector are listed below:

CP-QP-11.4, Rev. 5, " Inspection of Protective Coating"

QI-QP-11.4-1, Rev. 7, " Inspection of Steel Subs'4:te Surface Preparation and Primer Application" QI-QP-11.4-5, Rev. 9, " Inspection of Steel Substrate Primer Repair and Seal and Finish Coat Application and Repair" QI-QP-11.4-9, Rev. 2, " Inspection of Shop Primed Equipment" QI-QP-11.4-10, Rev. 6, " Inspection of Concrete Substrate Surface Preparation and Coatings Application and Repair" QI-QP-11.4-20, Rev. 0, " Final Inspection of Steel Substrate Finish Coat Application" QI-QP-11.4-23, Rev. 5, " Reinspection of Seal Coated and Finish Coated Steel Substrates for Which Documentation is Missing or Discrepant" l

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-6-QI-QP-11.4-24, Rev. 2, " Reinspection of Protective Coatings on Concrete Substrates for Which Documentation is Missing or Discrepant" Review of Records for Ongoing /Backfit Program The NRC inspector reviewed records for the ongoing program and for the back-fit program which were established because of the noncon-formance identified in NRC Inspection Report 81-15. Documentation reviewed for-the back-fit program was found to be retrievable and identifiable. The ongoing program has improved considerably because of the back-fit program. The last two procedures in paragraph 4.a, above, were established for the back-fit progra Licensee Action on Previous Findings (Closed) Unresolved Item (50-445; 50-446/81-15): Discrepancies In Concrete Coatings Application. (paragraphs 4.a and 4.b for details)

(Closed) Notice of Violation (50-445; 50-446/81-15): Failure to Follow Quality Assurance Procedures for the Inspection of Coating (paragraphs 4.a and 4.b for details)

No violations or deviations were identifie . Electrical Cable Installation The NRC inspector examined the origin and destination terminations of eight selected power cables and five selected control cables for Unit 1 to ascertain whether or not the terminations complied with the drawings used with the cable connection signoff cards. The cables identified below were inspected:

Power Cables Control Cables E0100815 E0112286 E0100805 EG113703 EG100198A AG123716 E0100161A EG123670 E01001618 EG109771 E0100389 E0100230 EG100035 All cable terminations agreed with the cable connection signoff card drawings except the destination termination for Cable EG10977 The improper destination termination of Cable EG109771 did not constitute a violation because it had not yet been transferred to

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-7-the licensee's startup group by the licensee where it will undergo a final inspection by the license No violations or deviations were identifie . Records of Cable Installation Tool Calibration The NRC inspector reviewed the calibration records of selected tools used to install the inspected cables for Unit 1 and deter-mined that these tools were properly calibrated at the time they were used to install the electrical cable. Calibration records were inspected for the following tools:

Crimping Tool CT-1657 Crimping Tool CT-1661 Torque Wrench CT-934 Torque Wrench CT-1154 Cylinder CT-1404 Cylinder CT-1438 Pump CT-1547 Pump CT-1548 Die CT-158 Die CT-1405 No violations or deviations were identifie . Procurement Documentation The NRC inspector reviewed representative procurement document Licensee Purchase Order 35-1195-18588, Change Order 2, Item 7 was

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for 10000 1-inch hex head structural bolts, ASTM A325, Type 1,

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Heat Number L 60891, Lot 552 ASTM A325 requires 3 or 13 mechanical property tests to be performed on a lot size of 10000, depending upon the method of material control l utilized by the vendor and fastener manufacturer. In addition, ASTM A325 requires a finished fastener proof load of 51,500 lbf using the

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length measurement method or an alternate proof load utilizing yield j strength method of 55,750 lbf using the yield strength metho The vendor reported only one mechanical property test and this test report did not show the proof load (or alternate proof load).

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, These will remain unresolved items (445/8209-01 and 446/8204-01)

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pending further investigation by the NRC inspector, including determination of use of these bolt No violations or deviations were identified.

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-8-8. Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, violations, or deviations. Unresolved items disclosed during this inspection are discussed in paragraph . Exit Interviews Exit interviews were conducted May 12, 13, and 27, 1982, with those persons listed in paragraph 1. At these exit interviews, the NRC inspectors discussed the findings indicated in the previous paragraph The licensee acknowledged these finding .,