IR 05000395/1978030
| ML19276F236 | |
| Person / Time | |
|---|---|
| Site: | Summer |
| Issue date: | 01/04/1979 |
| From: | Conlon T, Girard E, Hardwick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18043B144 | List: |
| References | |
| 50-395-78-30, NUDOCS 7903280121 | |
| Download: ML19276F236 (11) | |
Text
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Report No.: 50-395/78-30 Docket No.:
50-395 License No.:
CPPR-94 Category: A3/B1 Licensee:
South Carolina Electric and Gas Company P. O. Box 764 Columbia, South Carolina 29218 Facility Name:
Virgil C. Summer Nuclear Station, Unit No. 1 Inspection at: Fairfield County, South Carolina Inspection Conducted: December 11-14, 1978 Inspectors:
E. H. Girard R. J. Hardwick D. K. Walters Reviewed by: d
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m T. E. Conlon, Chief
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Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch Inspection Summary Inspection on December 11-14, 1978 (Report No. 50-395/78-30)
Areas Inspected:
Licensee Actions on Previous Inspection Findings; Storage and Identification of ASME Section III, C1. 2 Piping; Shop Welding of ASME Section III, C1. 3 Piping; Reactor Coolant Pressure Boundary Piping (Welding) - Observation of Work and Work Activities; Reactor Coolant Pressure Boundary Piping - Observation of Work and Work Activities; General Housekeeping and In-Place Storage of Electrical Motors and Panels; Electrical (Cables and Terminations) - Observation of Work and Vork Activities; and Electrical (Cables and Terminations) -
Review of Quality Records. The inspection involved 72 inspector-hours on-site by three inspectors.
Results: Of the eight areas inspected no items of noncompliance were identified in seven areas; one item of noncompliance was identified in (deficiency - failure to follow procedures for calibration one area reviews - Paragraph 6, Details II). No deviations were identified.
7903280121
RII Rpt. No. 50-395/78-30 1-1 DETAILS I Prepared by: [. h
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E.11. Girard, Reactor Inspector Date Engineering Su,; port Section No. 2 Reactor Construction and Engineering Support Branch Dates of Inspection: December 11-14, 1978 Reviewed by & Y gr v
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Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch 1.
Persons Contacted South Carolina Electric and Cas Company
- J.
F. Algar, Nuclear Site tianager
- H.
I. Donnelly, Jr., Sitt: QA Coordinator
- D. R. Moore, Senior QA Fngineer
- T.
A. McAllister, QA Surveillance Specialist J. L. Gypin, QA Surveillance Specialist In addition to the above personnel, the inspector interviewed other licensee and contractor personnel.
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings a.
(Closed) Infraction (395/78-12-02): Failure to comply with Code (ASME Section III) requirements for welding.
The inspector verified the licensee's implementation of special welder training and qualification requirements, repair of the defective welds, and other corrective actions described in the licensee's letters of August 18 and October 31, 1978.
b.
(Closed) Infraction (395/78-16-01): Failure to follow inspection and welding procedures.
The inspector verified changes to procedures FQCP 6.1.5 and 6.1.2, reinspection of welds, additional indoctrination of welding supervisors, and other licensee corrective actions as described in his letter of October 26, 1978.
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RII Rpt. No. 50-395/78-30 I-2 3.
Unresolved Items No unresolved items were identified during this inspection.
4.
Independent Inspection The following areas were examined by the inspector:
a.
Housekeeping The inspector reviewed Daniel Construction Company (DCC)
Administrative Procedure AP-IV-10, Rev. 2, " Housekeeping", and verified the " Housekeeping Zone Designation Matrix" (dated 12/4/78) required by the procedure.
Compliance with the cleanliness requirements was examined for the reactor vessel.
b.
Storage and Identification of ASME Section III C1. 2 Piping The inspector examined an ASME Section III, Class 2, spool piece stored adjacent to the reactor building for identification and for compliance with storage requirements of DCC Procedure QCP-VII-Os Rev. 5.
The spool piece was identified as 1-CS-73-02.
Capping, segregation, and separation from contact with dissimilar metals in compliance with DCC QCP-VII-05 was verified.
Shop Welding of ASME Section III C1. 3 Pipe c.
The inspector observed shop welding activities for ASME Section III C1. 3 pipe welds. The welds and specified welding procedures are identified below to the specific stages of weld completion at which the welding activities were observed.
(1) Fitup complete, welding not started Weld:
SW-25, Isometric CS-77, Chemical Volume Control System (CVCS)
Welding procedure:
8-8-B-1 Rev. 2 (2) Root pass (only) complete Weld:
SW-25 Isometric CS-77, CVCS Welding procedure:
8-8-B-1 Rev. 2
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(3) Welding in progress beyond the root pass (a) Weld:
SW-2, Isometric CS-77, CVCS B
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RII Rpt. No. 50-395/78-30 I-3 Welding procedure:
8-8-B-1 Rev. 2 (b) Weld:
SW-25, Isometric CS-77, CVCS Welding procedure:
8-8-B-1, Rev. 2 The welding activities were examined for compliance with the applicable code, specification, procedures, and isometric drawing, which are listed below:
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Sections III (71S73) and IX (74W74) of the ASME B&PV Code
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GAI Specification SP-220-044461-000 Rev. 3
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DCC Procedure QCP-II-03 Rev. 5
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Welding procedure: 8-8-B-1 Rev. 2
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Isometric: CS-77 The specific aspects of the welding activities that were examined included (as applicable to the stage of welding observed):
(1) Weld identification and location (2) Joint preparation and alignment (3) Evidence of QC verifications (4) Specified weld procedure used (5) Welder identification (6) Welder qualification for the procedure and position (7) Preheat and interpass temperature (8) Use of specified purge (9) Use of specified weld material (10) Grinding and cleaning performed where necessary (11) Physical appearance of weld (12) Periodic checks of welding variables (13) Control of unused welding material In the areas inspected no deviations or items of noncompliance were identified.
5.
Reactor Coolant Pressure Boundary Piping (Welding) - Observation of Work and Work Activities The inspector observed field welding activities for five reactor coolant pressure boundary pipe welds.
The welds observed, sizes, isometric drawings, piping systems, and the specified welding and NDE procedures are identified below to the specific stages of weld completion at which welding activities were observed:
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RII Rpt. No. 50-395/78-30 I-4 a.
Fitup complete, welding not started (1) Weld:
FW-4, Size:
3.5 0.D. x.438 wall, Isometric:
CS-89, System:
CVCS, Welding procedure:
8-8-B-2 Rev. 3 b.
Root pass (only) complete (1) Weld:
FW-4, Size:
3.5 0.D. x.438 wall, Isometric:
CS-89, System:
CVCS, Welding procedure:
8-8-B-2 Rev. 3 (2) Weld:
FW-15, Size:
2" Sch 160, Isometric:
RC-15, System: Reactor Coolant (RC),
Welding procedure:
8-8-B-11 c.
Welding in progress beyond the root pass (1) Weld:
FW-7R2, Size:
12.75 0.D. x 1.125 wall (pipe to valve), Isometric:
RH-09, System: Reactor Heat Removal (RHR), Welding procedure:
8-8-BA-3 (2) Weld:
FW-7, Size:
12.75 OD x 1.125 wall (pipe to pipe fitting), Isometric:
SI-13, System:
Safety Injection (SI), Welding procedure:
8-8-B-22 d.
Welding and surface preparation complete, NDE in progress (1) Weld:
FW-7, Size:
12.75 0.D. x 1.125 wall, Isometric:
SI-13, System:
WE-I-08 Rev. 0 (Liquid Penetrant)
(2) Weld:
FW-7, Size:
3.5x.438, Isometric:
CS-92, System:
WE-1-08 Rev. 0 (Liquid Penetrant)
The inspector also examined weld material issuance slips for the welding observed and inspected the handling and control of welding material at issuing locations identified as WR#3 and #4.
The welding activities were examined for compliance with the isometric drawings, welding procedures and NDE procedure noted above and for compliance with the requirements of:
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Sections III (71S73) and IX (74W74) of the ASME B&PV Code
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GAI Specification SP-220-044461-000 Rev. 3
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DCC Procedure QCP-II-03 Rev. 5
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DCC Procedure WE-II-02 Rev. 3 The specific aspects of the welding activities that were examined included (as applicable to the welds, welding and handling of welding materials noted above):
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RII Rpt. No. 50-395/78-30 I-5 a.
Weld identification and location b.
Joint preparation and alignment c.
Evidence of QC verification d.
Specified welding procedure used e.
Welder identification f.
Welder qualification for the procedure and position g.
Preheat and interpass temperature h.
Use of specified purge i.
Use of specified weld material j.
Grinding and cleaning performed where needed k.
Physical appearance of weld 1.
Periodic checks of welding variables m.
Control of unused welding material n.
Surface preparation suitable for the NDE performed o.
Appropriate NDE performed at the proper stage of fabrication p.
Storage of welding materials at issuing station (identification, segregation, cleanliness and storage temperature)
q.
Weld material issue records (approval, amount withdrawn, identity of withdrawer, dates, identification with weld)
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Handling of material returned to the weld station In the areas inspected no deviations or items of noncompliance were identified.
6.
Reactor Coolant Pressure Boundary Piping - Observation of Work and Work Activities The inspector examined two spool pieces of reactor coolant pressure boundary piping stored outside the reactor building for compliance with ASME Section III identification requirements and with the storage and identification requirements of procedure DCC QCP-VII-05 Rev. 5.
The pieces examined were identified as:
a.
Spool piece SI-15-02 (Safety Injection System), ASME Code nameplate manuf acturers serial number 7715.
b.
Spool piece SI-21-03 (Safety Injection System), ASME Code nameplate manuf acturers serial number 7742.
The inspector verified capping, tagging, segregation, and marking on the pieces as required by the Code and procedure.
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RII Rpt. No. 50-395/78-30 I-6 No deviations or items of noncompliance were identified.
7.
Exit Interview The inspector met with the licensee representatives denoted in paragraph 1 at the conclusion of the inspection and summarized the scope and findings of the inspection.
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RII Rpt. No. 50-395/78-30 II-I
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DETAILS II Prepared by:
%A D. K. Walters,%Electrij, al Engineer
'Date Engineering Support Section No.1 Reactor Construction and Engineering Support Branch CLNaN
R. M iardwick, Electrical Engineer
' Date Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch Dates of Inspection: December 11-14, 1978 Reviewedby:hh.
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J. C. Ifryant,\\ Chief V
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Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch 1.
Persons Contacted a.
South Carolina Electric and Gas Company (SCE&G)
- J.
F. Algar, Nuclear Site Manager
- H.
I. Donnelly, Jr., Site QA Coordinator
- D. R. Moore, Senior QA Engineer
- D. A. Lavigne, QA Surveillance Specialist
Contractor Organizations (1) Daniel Construction Company (DC_C)
- R. D. Gunderson, Project Manager
- C. E. Hackney, QA Engineer In addition to the above personnel, the inspector interviewed other licensee and contractor personnel.
- Denotes those present at the exit interview.
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RII Rpt. No. 50-395/78-30 II-2 2.
Licensee Actions on Previous Inspection Findings (0 pen) Unresolved Item 76-08-03, General Warning Alarm System (GWAS).
SCE&G has issued Engineering Change Notice (ECN) number 1014FM(E) dated October 11, 1978, to install GWAS modifications in the Solid State Protection System (SSPS) per Westinghouse Field Change Notice (FCN)
number FCN-CGE-10512-002.
Quality control procedures for installation inspection have not been issued as of December 14, 1978.
3.
Unresolved Items No new unresolved items were identified during this inspectica.
4.
Independent Inspection In place storage and general housekeeping of safety-related electrical motors and panels was observed.
Daniel Construction Administration Procedure (AP) VIII-03, " Cleaning, Handling and Preservation", specifies storage and housekeeping requirements for installed equipment.
The
" Plant Equipment Maintenance Log" fora of AP VIII-03 provides for periodic maintenance and inspection of installed equipment.
The inspector observed one battery charger to which the power cord to the heating lamp had been disconnected; one battery charger which was excessively dusty internally and four motor operated valve motors to which heat lamps were mounted on the valve stem instead of the motor.
The inspector was informed that SCE&G had initiated Corrective Action Request (CAR) 41 due to previous problems which had been documented on QA surveillance reports. The inspector reviewed CAR 41 and QA surveil-lance reports from July 1978 to December 1978.
Current status for CAR 41 has a corrective action completion date of January 1978.
The in place storage and housekeeping problem has been identified as Inspector Followup item 50-395/78-30-02.
5.
Electrical (Cables and Terminations I) - Observation of Work and Work Activities The 125 VDC and 480 VAC safety-related power distribution cables listed below were selected to assure compliance with FSAR requirements.
EDE 29C (125 VDC)
EMC 84A (480 VAC)
EDE 26A (125 VDC)
EMC 86A (480 VAC)
EDE 24\\ (125 VDC)
EMC 87C (480 VAC)
EDE 21A (125 VDC)
EMC 93B (480 VAC)
EMC 96B (480 VAC)
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RII Rpt. No. 50-395/78-30 II-3 Cables were examined to assure that the FSAR requirements were complied with in the areas of storage, handling, identification, use of specified material and installation. The routing of these cables was verified from the components and breaker panels to the cable trays. Raceway loading and identification appeared adequate. Cable pulling and termina-tion sheets had been completed in accordance with Daniel Construction Company (DCC) Work Procedure (WP)
7.1.1,
" Cable Pulling", and DCC WP-XIII-01, " Cable Terminations" Terminations had not been completed for 480 VAC cables EMC-84A, EMC-86A, EMC-87C, and EMC-96B.
Within the areas examined, no items of noncompliance or deviation were identified.
6.
Electrical (Cables and Termination I) Review of Quality Records The records for the cables listed in paragraph 5 were reviewed to assure FSAR requirements were met in the areas of receiving, storage, te rmina tions, installation and testing. Cable pulling and termination inspections were documented per SCE&G FQCP 7.1.1, " Cable Pulling", and FWPC 7.1.2, " Cable Terminations". All cable records reviewed for site cable reels identified as EK-A2A-1, EK-A2S-1, EK-A3E-3, EK-A3H-3, and EK-A1E-2 were traceable to the vendor certifications.
The inspector reviewed closed Deficiency Notices (DN) identified as 1516E and 1517E which related to cable installation. The DN's reviewed indicated disposition and reinspection after corrective action had been completed.
Maintenance of termination tools per manufacturer's instructions is per-formed in accordance with DCC WP-XIII-01 by contractor personnel.
Paragraph 5.6 of SCE&G FWPC 7.1.2,
" Cable Termination", requires a weekly review of " Contractor Tool Control" program to verify that tools are being maintained in accordance with manufacturer's instructions. A check of inspection forms for weekly inspections performed from July 12, 1978 to December 8,1978, revealed that QC inspections were not performed during the weeks beginning and ending on the following dates.
September 10, 1978 through September 16, 1978 October 22, 1978 through October 28, 1978 October 29, 1978 through November 4, 1978 November 5, 1978 through November 11, 1978 November 26, 1978 through December 2, 1978 A review of contractor calibration records for several tools indicated that tools were within calibration during the periods listed.
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RII Rpt. No. 50-395/78-30 II-4 This failure to perform weekly QC inspections appears to be a deficiency and is identified as 50-395/78-30-01, failure to follow procedure for calibration review.
7.
Exit Interview The inspectors met with the licensee representatives and others denoted in paragraph 1.
The scope and findings of the inspection of storage and housekeeping for electrical motors and panels and safety-related power cable records were discussed.
Deficiency 395/73-30-01, failure to follow procedures for calibration review, and inspector followup item 395/78-30-02, storage and house-keeping of electrical equipment, were discussed in detail.
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