IR 05000424/1982010

IE Insp Repts 50-424/82-10 & 50-425/82-10 on 820511-14.No Noncompliance Noted.Major Areas Inspected:Reactor Vessel installation,safety-related Components & Steel Structures & Supports

ML20054M924
Person / Time
Site:	Vogtle
Issue date:	06/16/1982
From:	Economos N, Kleinsorge W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20054M920	List: IR 05000424/1982010 ML20054M919
References
50-424-82-10, 50-425-82-10, NUDOCS 8207150146
Download: ML20054M924 (12)

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UNITED STATES 8' 'n NUCLEAR REGULATORY COMMISSION g s REGION ll o * 101 MARIETTA ST., N.V4., SUITE 3100 ATLANTA, GEORGIA 3o303

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Report Nos. 50-424/82-10 and 50-425/82-10 Licensee: Georgia Power Company 270 Peachtree Street Atlanta, GA 30303 Facility Name: Vogtle Docket Nos. 50-424 and 50-425 License Nos. CPPR-108 and CPPR-109 Inspection a near Waynesboro, Georgia Inspector: /i /_ jg~ = _ _ _de_ k

. [ eins rge Date Signed Approved by: -

' 42% <% e N. Econoritos%Asting Section Chief s m ce_ /4,// h Date Sigrfed Engineering Inspection Branch Division of Engineering and Technical Programs SUMMARY Inspection on May 11-14, 1982 Areas Inspected This routine, unannounced inspection involved 33 inspector-hours on site in the areas of reactor vessel installation (Units I and 2) reactor vessel internals installation (Units 1 and 2), safety related components (Units 1 and 2), steel structures anc supports (Units 1 and 2), safety related piping (Units 1 and 2)

and inspector follow-up item Results No violations or deviations were identified.

8207150146 820618 PDR ADOCK 05000424 G PDR ,

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REPORT DETAILS Persons Contacted Licensee Employees

• H. H. Gregory, III, Construction Project Manager

• E. D. Groover, QA Site Supervisor

• R. E. Folkes, Sr. QA Engineer B. F. Barrett, Sr. QA Field Representative M. H. Googe, Manager of Field Operations

• D. F. Wilkerson, Sr. Welding Specialist

• B. C. Harbin, Civil Project Section Supervisor

• A. B. Gallant, Mechanical Engineering Supervisor Gther licensee employees contacted included construction craf tsmen, tech-nicians, crd office personnel .

Other Organizations

• H. R. Reuter, Resident Engineer, Bechtel Power Corporation (BPC)

J. P. Runyan, QA Manager, Pullman Power Products (PPP)

C. L. Fields, Welding and QA Superintendent, Chicago Bridge and Iron (CB&I)

• G. Ryan, QA/0C Coordinator, Walsh Construction Company (WCC)

NRC Resident Inspector

• F. Sanders

• Attended exit interview Exit Interview The inspection scope and findings were summarized on May 14, 1982, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussea in detail the inspection findings listed below. No dissenting comments were received from the license Unresolved Item 424, 425/82-10-01. " Marker - Halogen Control" - paragraph Unresolved Item 424, 425/82-10-02: " Weld Rod Control" paragraph 9 Unresolved Item - 424, 425/82-10-03: " Motor Heater Indicator Lights" -

paragraph 8b(1).

Unresolved Item - 424, 425/82-10-04: " Purge Gas For Storage of Components" paragraph 8b(2).

Unresolved Item - 424, 425/82-10-05: " Adequacy of Storage Maintenance Inspection Program" paragraphs 6b and 8b(3).

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3. Licensee Action on Previous Inspection Findings (Closed) 425/82-05-01: " Failure To Follow Inspection Procedure". >

On March 11, 1982 this inspector noted undercut adjacent to the completed ,

and accepted weld joining plates 8-1 MIL To 8-1 MI The inspector discussed the above undercut with the licensee. The Licensee reinspected the weld and informed the inspector that the undercut exceeded that allowed by GPC specification XZAP01. Based on the above the Licensee was cited for failure to follow specification requirement !

Subsequent to the inspection of March 9-12, 1982 the Licensee reinspected the above weld and determined that the above undercut was acceptabl During this inspection this inspector reinspected the weld and agreed that there was no violation of regulatory requirement . Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-tions. New unresolved items identified during this inspection are discussed in paragraph 5, 6b 8b(1), 8b(2) 8b(3) and 9 . Independent Inspection Effort (Units 1 and 2)

The inspector conducted a general inspection of the units 1 and 2 contain-ment construction sites, auxiliary building, weld ter.t shop, and Cleveland Electric Contractors (CEC), Ingall's Iron Works (IIW A, and Walsh Construc-tion Company (WCC) welding materials issue stations t o observe construction progress and construction activities such as welding, nondestructive examination, material handling and control, housekeeping, and storag With regard to the above, the inspector on May 13, 1982, noted that a welder was marking on stainless steel, associated with the fuel pool, with a black

"Blaisdell Liquid Tip 6100" felt ti p marker.. The above marker is not included on the licensee list of approved marking materials for stainless steel. At the time of this inspection it could not be determined whether that marker's halogen content was consistent with the licensee's program requirements relative to stainless steel application. The inspector indi-cated that the above would be unresolved item 424, 425/82-10-01: " Marker Halagen Control ."

Within the areas examined, no violations or deviations were identifie . Reactor Vessel Installation (Units 1 and 2)

The inspector reviewed procedures, made a physical inspection, and reviewed quality records to ascertain whether procedures, field activities, and records pertaining to the installation of the reactor vessel were consistent with NRC requirements, applicable codes standards, and commitment __-

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3 Review of Quality Assurance Implementing Procedures The inspector reviewed the below listed documents to determine whether provisions established for receipt inspection and handling of the reactor vessel were in conformance with applicable requirement DOCUMENTS N TITLE GO-A-30 Rev 3 " Receipt, Receipt Inspection, Storage and Handling" GD-T-09 Rev 3 " Inspection of Items in Storage and Storage Areas" GD-T-17 Rev 0 " Housekeeping"

" Westinghouse Nuclear Energy Systems Mechanical Service Manual" -

Second edition dated April 1,1978

"destinghouse - "NSSS Component Receiving and Storage Criteria",

Volume 1 " Mechanical Equipment" dated March 1976 Observation of Work and Work Activities The inspector examined the stored reactor vessels, and reviewed the documents indicated in paragraph 6a; and their associated records for the stored reactor vessels to determine whether the requirements of the applicable specifications, work procedures, and inspection procedures were met in the area of stored vessel protectio With regard to the above inspection on May 11, 1982, the inspector noted rust on the exterior of the Unit 2 reactor vesse The above should have been identified during the scheduled maintenance inspection for attribute "perservatives and coatings" The inspector could not find either an acceptance criteria for attribute "perservatives and l

I coatings" or documentation identifying the deteriorated coating and rust on the Unit 2 reactor vesse The above is part of unresolved item 424, 425/82-10-05 discussed further in paragraph 8b(3). Review of Quality Records i

The inspector reviewed pertinent quality related work and inspection (QC) records relative to the reactor vessel to ascertain whether the records are in conformance with established procedures and whether they reflect work accomplishment consistent with applicable requirements in the area cf storage inspectio Within the area; examined no violations or deviations were identifie *

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7. Reactor Vessel Internals Installation (Units 1 and 2)

The inspector reviewed procedures made a physical inspection, and reviewed auality records to ascertain whether procedures, field activities, and records pertaiaing to the installation of the reactor vessel internals were consistent with NRC requirements, applicable codes standards and commit-ment Review of Quality Assurance Implementing Procedures The inspector reviewed the below listeo documents to determine whether provisions had been estabidshed relative to the reactor vessel internals to assure conformance with applicable requirements for receipt inspection and handlin DOCUMENTS N TITLE

._ GD-A-30, Rev. 3 " Receipt, Receipt Inspection, Storage and Handling" GD-T-09 Rev. 3 "Inspecti(n of Items in Storage and Storage Areas" GD-T-17, Rev. O " Housekeeping"

" Westinghouse Nuclear Energy Systems Mechanical Service Manual" -

Second edition dated April 1,1978

" Westinghouse - "NSSS Component Receiving and Storage Criteria",

Volume 1 "Mecnanical Equipment" dated March 1976 Observation of Work and Work Activities The inspector examined the stored internals and reviewed the documents indicated in paragraph 6a; and their associated records for the reactor vessels internals to determine whether the recuirements of the applic-able specifications, work procedures, and inspection procedures were met in the area of stored internals protectio Review of Quality Records The inspector reviewed pertinent quality related work and inspection (QC) records relative to the reactor vessel internals to ascertain whether the records are in conformance with established procedures and whether they reflect work accomplishment consistent with applicable requirements in the area of storage inspectio Within the areas examined no violations or deviations were identifie .

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5 Safety Related Components (Units 1 and 2)

The inspector reviewed procedures, made a physical inspection, and reviewed I quality records to ascertain whether procedures, field activities, and records pertaining to the installation of the safety related components were consistent with NRC requirements, applicable codes, standards and commit-ment Review of Quality Assurance Implementing Procedures The inspector reviewed the below listed documents relative to the components indicated below to assure conformance with applicable requirements for receipt inspection; storage and protectio DOCUMENTS N TITLE GD-A-30, Rev. 3 " Receipt, Receipt Inspection, Storage and Handling" GD-T-09, Rev. 3 " Inspection of Items in Storage and Storage Areas" GD-T-17, Rev. 0 " Housekeeping"

" Westinghouse Nuclear Energy Systems Mechanical Service Manual" -

Second edition dated April 1,1978

" Westinghouse - "NSSS Component Receiving and Storage Criteria",

Volume 1 " Mechanical Equipment" dated March 1976 COMPONENT Pressurizer - Unit 1 4 Steam Generators - Unit 1 4 RHR Heat Exchangers - Units 1 and 2 4 RHR Pumps - Units 1 and 2 Observation of Work and Work Activities The inspector examined the stored components and reviewed the documents indicated in paragraph S.a and their associated records for the safety related components indicated above, to determine whether the require-ments of the applicable specifications, work procedures, and inspection procedures were met in the area of storage and protectio (1) With regard to the inspection above, the inspector noted on May 13, 1982, that two of the four RHR pump motors shared a heater indicator light with an adjacent valve, electrically up stream from the RHR Pump motor. The inspector indicated that a separate indicator light for each motor heater or relocating the indicator

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lights to the electrical end of the string, would provide a greater degree of confidence that the motor heaters were ener-gize The licensee indicated that they would look into the matter. The inspector stated that the above would be examined in 425/82-10-03: " Motor Heater Indicator Lights."

(2) With regard to the inspection above, the inspector noted on May 12, 1982, that a number of safety related components experienced a drop in nitrogen purge blanket pressure, and required the addition of nitroge The inspector further noted that the licensee does not have a program to determine whether the moisture content of the added nitrogen, or the moisture content of the purge blanket af ter the addition, is consistent with the component manufacturers recommendation The licensee indicated that they would look into the matter. The inspector stated that the above would be identified as unresolved item 424, 425/82-10-04: " Purge Gas for Storage of Components".

(3) With regard to the inspection above the inspector, on May 11-12, 1982, noted the following discrepancies:

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The oil reservoir on the 1A RHR pump motor was overfille Purge pressure readings below specified minimums were not documented as required by GD-T-09, thus precluding identi-fication by trend analysi Concrete completely covering several of the tube sheet flange bolts on the RHR heat exchanger in room 91 was not identified and documented during the scheduled maintenance inspection for attribute " Environmental / Physical Damage" as required by GD-T-0 The Rolodex Cards identified in paragraph 3f of GD-T-09 are not filed in a fire proof file cabinet as required by para-graph 4 of GD-T-0 The inspector was unable to locate specific acceptance criteria for the following " Maintenance Report" attributes:

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Area / Equipment Cleanliness

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Environmental / Physical Damage

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Perservatives and Coatings

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Lubrication Checked The above discrepancies comoined with those discussed in paragraph 6.b indicated that the storage maintenance inspection program is inadeouat The inspector discussed the above discrepancies as well as those described in paragraph 6.b with the licensee. The licensee

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indicated that they would evaluate the degree of degradation, if any, to the components examine The inspector stated that the safety signficance of the above would be determined upon the completion of the licensee's evaluation. The above matter will be identified as unresolved item 424 425/82-10-05: "Adequady of Storage Maintenance Inspection Program" Review of Quality Records The inspector reviewed pertinent quality related work and inspection (QC) records relative to the safety related components indicated above to ascertain whether the records were in conformance with established procedures and whether they reflect work accomplishment consistent with applicable requirements in the areas of storage inspection and installation inspectio Within the areas examined, no violations or deviations were identifie . Steel Structures and c.upports (Units 1 and 2)

The inspector observed welding work activities for steel structures and supports as described below to determine whether applicable code and procedure requirements were being met. The applicable code for containment fabrication is the ASME B and PV Code Section III 1974 edition with addenda through summer 75, and Section VIII 1974 edition with addenda through summer 75. The applicable code for structural embeds, tube steel conduit supports and fuel pool structure is AWS 01.1-1977. The applicable code for embedded HVAC duct is ANSI B3 The inspector observed in process welding activities of structural field welds as described below to determine whether applicable code and procedure requirements were being me Welding (1) Inside Containment The following in process welds were examined to determine whether i work was conducted in accordance with traveler; welding procedures l were available and whether welding technique and sequence; weld l geometry; fit-up; electrical characteristics ar d equipment condi-tion were consistent with applicable Code and/or specification requirements.

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STRUCTURE UNIT LOCATION OR IDENTIFICATION Containment Dome 1 Plate 458A to 459A l (2) Outside Containment

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The following in process welds were examined to determine whether work was conducted in accordance with traveler; welding procedures were available and whether welding technique and sequence; weld geometry; fit-up electrical characteristics equipment condition were consistent with applicable Code and/or specification requirement STRUCTURE UNIT LOCATION OR IDENTIFICATION Embed 1 A012-5 Embed 1 A012-13 Tube Steel 2 R-C-39 Conduit Support 1 PAV-511608 Fuel Pool Structure 1 7-F b. Welder Qualification The inspector reviewed the GPC and P/K-F programs for qualification of welders and welding operators for compliance with QA procedures and ASME Code requirements. The applicable Code for welder qualification is ASME B&PV Code Section IX as invoked by GPC Specification X2AG06 Rev. 4 and X4AZ01 Section P.1 Rev. (1) The following welder qualification status records and " Records of Performance Qualification Test" were reviewed relative to the weld joints listed in paragraph 9 WELDER SYMBOL ORGANIZATION APPLICATION GC IIW Steel Structures and Supports CTT IIW Steel Structures and Supports QY CEC Steel Structures and Supports RP CEC Steel Structures ard Supports KD WCC Steel Structures and Supports J1L CB&I Steel Structures and Supports

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(2) The inspector observed in process performance qualification testing for the below listed welders:

WELDER ID OUALIFICATION TEST APPLICATION AC IIW-003-61 Steel Structures and Supports ADP IIW-136-64 Steel Structures and Supports EGI PPP-C18 Safety Related Piping LT PPP-S-5 Safety Related Piping DTI PPP-C18 Safety Related Piping (3) The inspector observed the removal preparation and testing of side band specimens from qualification test assemblies for the below listed welde WELDER ID OUALIFICATION TEST APPLICATION AC IIW-003-61 Steel Structures and supports (4) The inspector examined Welder Qualification Test radiographs for the below listed welder:

)! ELDER ID ORGANIZATION APPLICATION BHJ PPP Safety Related Piping c. Welding Filler Material Control The inspector reviewed the GPC program for control of welding materials to determine whether materials are being purchased, accepted, stored, and handled in accordance with QA procedures and applicable code requirements. The following specific areas were examined:

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Purchasing procedure receiving, storing, distributing and handling procedures, material identification, inspection of welding material issuing station Welding material purchasing and receiving records for the following materials were reviewed for conformance with applicable procedures and code requirements:

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HEAT LOT OR TYPE SIZE BATCH N APPLICATION E-7018 3/32" D0-073 Steel Structures and Supports E-7018 1/8" EE-085 Steel Structures and Supports E-309L-16 1/8" 05766 Steel Structures and Supports ER-308L 3/32" 05394 Steel Structures and Supports With regard to the inspection above the inspector, on May 12, 1982, noted that several different heats of type E-7018, 5/32" diameter covered welding electrodes were mixed, in oven No. 1, in the CEC welding material issue station at the power block. This is not consistent with Paragraph VIB2 and VI B6 of GPC Procedure GD-T-14 revision 1, which requires welding materials to be issued and con-trolled by heat / lot or control numbers. At the time of this inspection the safety significance of the above could not be determine The inspector stated that the above would be examined in a subsequent inspection and identified as unresolved item 424, 425/82-10-02: " Weld Rod Control" Within the areas examined no violations or deviations were identifie . Safety-Related Piping (Units 1 and 2)

The inspector observed welding work activities for safety-related piping as described below to determine whether applicable code and procedure require-ments were being met. The applicable code for safety-related piping is the ASME B and PV Code,Section III, Subsection NC and ND, 1977 edition with addenda through winter 197 Ooservation of Welding Activities The inspector observed in process welding activities of safety-related piping field welds as described below to determine whether applicable code and procedure requirements were being me Welder Qualification Welder Qualification is discussed in paragraph Within the areas examined no violations or deviations were identifie . '

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11. Inspector Follow-up Items (Closed ) 425/82-05-7: " Material Identification." This item concerned incorrect material identification on weld process sheets (travelers). The licensee has investigated and corrected the errors. The inspector has no further questions.

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