IR 05000395/1978015

IE Inspec Rept 50-395/78-15 on 780808-11 During Which 1 Item of Noncompliance Was Noted:Use of Unapproved Tape on stainless-steel Piping

ML20062C354
Person / Time
Site:	Summer
Issue date:	09/20/1978
From:	Conlon T, Girard E, Vandoorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20062C336	List: IR 05000395/1978015 ML20062C332 ML20062C337 ML20062C343 ML20062C348
References
50-395-78-15, NUDOCS 7811080158
Download: ML20062C354 (6)

Text

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, Mah UNITED STATES

= jog NUDLEAR REGULATORY COMMISSION 3 , g REGloN il 5 '-*- ,..g 101 M ARIETTA STREET, * 8 ATLANTA, GEORGI A 30303

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Report No.: 50-395/78-15

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4 Docket No.: 50-395 .. .

License No.: CPPR-94

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? Category: A3/B1

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a- Licensee: South Carolina Electric and Gas Company

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P. O. Box 764 Columbia, South Carolina 29202

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Facility Name: Virgil C. Summer Nuclear Station, Unit 1

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I nspection at: Fairfield County, South Carolina

. O Inspection conducted: August 8-11, 1978 Inspectors: P. K. VanDoorn T. E. Conlon E. H. Girard (Training)

Reviewed by: [MI C 9/m/.7F T. E. ConIon,IchiEf , /

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'Dat6 Engineering Support Yection No. 2 Reactor Construction and Engineering Support Branch

! Inspection Summary i

Inspection on August 8-11, 1978 (Report No. 50-395/78-15) Areas Inspected:

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Q Routine unannounced inspection of safety-related and reactor coolant pressure l

boundary pipe welding, handling, and protection; containment quality record No part 21 or 50.55(e) items were included in this inspection. The inspection i involved 69 inspector-hours on site by three inspector I Results: Of the three areas inspected, no apparent items of noncompliance

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or deviations were identified in two areas, one item of noncompliance (Infraction - use of unapproved tape on stainless-steel piping) was identified in one are .j i I 781108oiT8 :

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RII Rpt. No. 50-395/78-15 I-1

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. DETAILS I- Prepared by: ] X 9/2/

[ P. K. VenDoorn, Metallurgical E6gineer Date '

- -. Engineering Support Section No. 2 Reactor Construction and Engineering

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} Support Branch

,o Dates of Inspection: August 8-11, 1978 *

q Reviewed by: [

T. E. Conlon, Chief c: v'

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Engineering Support Section No. 2 Reactor Construction and Engineering

Support Branch Persons Contacted Q South Carolina Electric and Gas (SCE&G)

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• J. F. Algar, Nuclear Site Manager

• D. A. Nauman, QA Hanager

• H. I. Donnelly, Jr., Site QA Coordinator J. E. Bocock, QA Engineer Supervisor

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T. A. McAlister, QA Surveillance Specialist I

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j Contractor Organizations

! (1) Daniel Construction Company (DCC)

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! *R. D. Gunderson, Project Manager

! *J. M. Harvey, Construction Manager

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Curtis, QC Supervisor CJa *G J. H. Witherspoon, Welding and Piping QC Engineer

{ L. Heaton, QC Engineer

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D. L. Welker, Welding Engineer J. Roach, Welding Engineer L. Hartsell, Welding Engineer (2) Gilbert Associates, Incorporated (GAI) ,

• R. H. Fleming, Resident Mechanical Engineer

• Denotes those present at the exit intervie i k .

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., RII Rpt. No. 50-395/78-15 I-2

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- Licensee Actions og Previous Inspection Findings

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.. (Closed) Unresolved Item (395/78-10-01): Poor Weld Grounding Practice. This item was originally identified

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on June 23, 1978, and concerned the fact that grounding for T; welding was being performed directly to safety-related components c' and in such a manner as to create the possibility of are strike

'. , . + damage to the component. The inspector reviewed the actions taken

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into procedures and identifying responsible personnel for grounding activities, and considers these actions to be adequate. This item

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is close I (0 pen) Infraction (395/78-10-02): Iailure to Follow Weld Procedur This item was originally identified on June 23, 1978, and concerned Q inadequate preheat temperature for a safety-related pipe weld N ICC-01-01 -W-1. Response to this item was received in a letter to

, Mr. O'Reilly, Director, RII dated August 4, 1978. The welding are had not been initiated and therefore the immediate corrective action was to obtain adequate preheat temperature and verification. Further licensee actions included review of weld joint packets to assure ' hat preheat signoffs are provided for, a procedure change to allow QC personnel to initiate continuation sheets to provide for preheat signoffs, and retraining of welders and welding supervisors. The inspector reviewed the above actions and considers them to be adequat All actions had been completed at the time of the inspection except retraining of welders and welding supervisor This item will remain open until this training can be verified by NR i

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- (Closed) Unresolved Item (395/78-11-01): Unrequired Signoffs 1 Performed at the 30% Weld Leve This item was initially identified on June 29, 1978, and concerned unrequired signoffs being performed which could result in confusion at the time of final inspections. The inspector reviewed the licensee actions taken, which included a procedure change to clarify signoff requirements and retraining of inspection personnel, and considers them to be adequate. This item is closed (Closed) Inspector Followup Item (395/78-12-04): Measurement and Adequacy of Interpass Temperature. This item was originally identified on July 13, 1978, and concerned whether or not interpass temperature was being properly measured and whether

] interpass temperature was appropriately qualified for Main j Steam System pipe welding. The inspector discussed interpass y temperature measurement with licensee and contractor personnel t

'and reviewed the applicable procedure qualification records and d considers these to be adequate. This item is close _ . _ _ . , , , _ ._ .

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RII Rpt. No. 50-395/78-15 I-3 L

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o Unresolved Items

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Unresolved items are matters about which more information is required

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noncompliance, or deviations. One unresolved item disclosed during

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the inspection is discussed in paragraph ;;7 Independent Inspection Effort

> ' The inspectors conducted a walk-through inspection of the

, containment and auxiliary buildings to observe construction

, progress and construction activities such as welding, material handling and protection, housekeeping, and material storag The inspectors conducted a review of Work Procedures, O, Quality Control Procedures, and Welding Procedures associated with safety-related pipe weldin During procedure review it appeared that the guidelines for cold spring of safety-related piping were not adequately defined. Specific guidelines were not defined for QC inspectors and it was not clear that specific joints, -

such as closure joints, where cold spring is most likely to occur, are adequately identified to QC personnel in order that cpecial attention can be given to inspection for cold spring. Also it could not be determined during the time of the inspection whether QC inspection personnel were adequately trained and were knowledgeable of cold spring requirements. Licensee actions in this area will be inspected at a later date. This is Unresolved Item No. 395/78-15-0 .

() The applicable code for safety-related piping installation is the ASME Boiler and Pressure Vessel Code,Section III, 1971

Edition plus addenda through the Summer of 1973. The inspectors j

observed intermediate welding of .656" X 10.75" carbon steel l  ! penetration weld FW-1 of ISO DE-SI-426P. The inspectors also l observed final welding of 1.109" X 38" carbon steel penetration l

J weld FW-1 of ISO DE-FW-306. The inspectors observed the welding for conformance to procedure and code requirements, physical appearance of welds, evidence of QC inspection, and welder and inspector qualificatio No items of noncompliance or deviations were identifie i l

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RII Rpt. No. 50-395/78-15 I-4

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,, Reactor Coolant Pressure Boundary Piping - Observation of Work

!< and Work Activities n , .. ;

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< The applicable Code for reactor coolant pressure boundary

,. piping is the ASME Boiler and Pressure Vessel Code,

'Q] Section III, 1971 Edition plus addenda through the Summer

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of 1973. The inspectors observed handling,' protection,

- J and installation activities of reactor coolant loeps B-1 and B-5 to determine if Code, NRC and SAR requirements

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were being met. Specific areas reviewed included conformance

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to inspection and work performance procedures, record keeping requirements, installation specification requirements, issuance and use of specified materials, and utilization of l

j qualified inspection personne On August 9, 1978, during inspection of reactor coolant loop B, the inspectors observed that sheets of plastic used for cleanli-ness protection were attached to the stainless steel piping with tape commonly called " duct" tape. Additional inspection of reactor coolant loop A revealed that the same condition existed

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on loop A stainless steel piping. DCC work procedure WP-VII-05, Rev. 4, paragraph 3.6-11 lists three tapes approved for use on stainless steel pipin " Duct" tape is not included. The two examples described above represent noncompliance with Criterion V of 10 CFR 50, Appendix B, as implemented by the-FSAR, paragraph 17.1.5. This noncompliance is categorized as an infraction and is identified as Item No. 395/78-15-0 No items of noncompliance or deviations, except as indicated in

, paragraph 5.b. , were identified.

I Reactor Coolant Pressure Boundary Piping (Welding) - Observation I

h- of Work and Work Activities The applicable Code for reactor coolant pressure boundary piping is delineated in paragraph 5.a. The inspectors observed welding activities on reactor coolant loop B-1 to determine if Code, NRC and

! SAR requirements were being met. Fitup and root welding were observed on weld W-15. Fitup, root welding, and hot pass welding were observed j on weld W-16. Both welds were 2.366" X 33.732" butt welds. Specific

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areas included, as applicable, were weld identification / location, joint preparation and alignment, evidence of QC verification, use of specified weld procedure, physical appearance of the weld, welder identification .

< and qualification, interpass temperature, use of specified weld material, j use of specified purge, grinding of starts and stops, verification of periodic welding checks, control of unused filler material, and the

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presence of an adequate number of qualified QA and QC personnel.

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j No items of noncompliance or devjations were identifie ~

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RII Rpt. No. 50-395/78-15 I-5 i

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' Containment (Steel Structures and Supports) - Review of Quality Records

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The applicable Code for the containmeut is the ASME,Section III, Subsection NE, 1971 Edition plus addenda through the Summer of 197 The inspector reviewed quality records to determine if Code, NRC

~N and SAR requirements were being met. Records were reviewed for one ~

- '. .I shipment of anchorages (Westinghouse QR 30467, PO 216922), the steam

, j generator lower lateral support Number 911211-4 (Westinghouse QR 28238, I PO 207002),, and the reactor coolant pump tie rod Number 9112-7-3

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] (Westinghouse QR 30467, PO 216922). Areas specifically reviewed were

material quality release (QR) records, vendor manufacturing and

.I inspection records, and receiving inspection report ,

- No items of noncompliance or deviations were identifie . Exit Interview The inspectors met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on August 11, 1978. The inspector summarized the scope and findings of the inspection. The unresolved item described in paragraph i and the noncompliance described in paragraph 5.b. were discussed l in detai I l

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