IR 05000424/1985021

Insp Repts 50-424/85-21 & 50-425/85-21 on 850507-0607.No Violation or Deviation Noted.Major Areas Inspected:Qa, Concrete placement,safety-related Piping,Flushing Activities & Cavity Liner Plate Welding

ML20209E605
Person / Time
Site:	Vogtle
Issue date:	06/14/1985
From:	Rogge J, Sanders W, Sinkule M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20209E604	List: IR 05000424/1985021 ML20209E599
References
50-424-85-21, 50-425-85-21, NUDOCS 8507110653
Download: ML20209E605 (15)

Text

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UNITED STATES

/stka M4,% NUCLEAR REGULATORY COMMISSION

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1. x REGION 11

h*'-.. 101 MARIETTA STREET. 'c ATLANTA, oEORGI A 30323

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Report Nos.: 50-424/85-21 and 50-425/85-21 Licensee: Georgia Power Company P.O. Box 4545 Atlanta, GA 30302 Docket Nos.: 50-424 and 50-425 License Nos.: CPPR-108 and CPPR-109 Facility Name: Vogtle 1 and 2 Inspection Conducted: May 7, 1985 - June 7, 1985 Inspectors: W. F. Sanders, Senior Resident (o//2/f5 Date Signed b Inspector, Construction

'<A ' W . 6//2/g5 p J. F. Rogge, Senior Resident D' ate Signed Inspector, Operations Accompanying Pers nnel: R 4 . Schepens, Resident Inspector, Construction Approved By: f /44tu/ tAtw M.~V. SJnktle,'Tection Chief '

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04te' Signed Division of Reactor Projects SUMMARY Scope: This routine, unannounced inspection entailed 315 resident inspector-hours on site (64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br /> were on backshifts) inspecting: quality assurance, concrete placement, safety related piping, flushing activities, control rod drive mechanism canopy seal weld welder qualification test, cavity liner plate welding, containment post tensioning, reactor coolant system primary loop piping installation and welding, safety-related piping installation and welding, reactor coolant pump motor installation and reactor vessel, upper and lower internals, integrated head package, and' safety-related equipment storage and protectio Results: No violations or deviations were identifie PDR ADOCK 05000424 G PDR r -1 m F - ~

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REPORT DETAILS Persons Contacted Licensee Employees D. O. Foster, Vice President and Project General Manager

• J. T. Beckham, Vice President and General Manager, Nuclear Operations P. D. Rice, Vice President and General Manager, W. T. Nickerson, Deputy Project General Manager W. C. Ramsey, Readiness Review Manager H. H. Gregory III, General Manager-Nuclear Construction

• H. Googe, Project Construction Manager G. Bockhold, Jr. , General Manager-Nuclear Operations 0. Batum, General Manager Engineering and Licensing C. W. Hayes, Vogtle Quality Assurance Manage *C. E. Belflower, Quality Assurance Site Manager - Construction

• E. D. Groover, Quality Assurance Site Manager - Construction C. E. Spell, Jr., Quality Assurance Engineering Support Supervisor W. E. Mundy, Quality Assurance Audit Supervisor 1 J. E. Sanders, Project Construction Manager - Unit 1 D. M. Fiquett, Project Construction Manager - Unit 2 B. C. Harbin, Manager Quality Control

• J. L. Blocker, Assistant Quality Control Manager T. L. Weatherspoon, Assistant Quality Control Manager

• G. A. McCarley, Project Compliance Coordinator W. C. Gabbard, Assistant Project Compliance Coordinator

• J. O. Dorough, Administrative Manager

• A. J. Spencer, Senior QA Field Representative J. F. D' Amico, Regulatory Compliance Supervisor-Nuclear Operations

• E. A. Meadows, Regulatory Compliance Engineer - Nuclear Operations

• R. M. Bellamy, Initial Test Manager

• A. L. Mosbaugh, Preoperational Test Supervisor

• C. L. Coursey, Maintenance Supervisor R. M. Grant, Procedure Specialist Other licensee employees contacted included craftsmen, technicians, super-visors, engineers, inspectors, and office personne Other Organizations F. B. Marsh, Project Engineering Manager - Bechtel M. Malcom, Deputy Project Engineering Manager - Bechtel D. L. Kinnsch, Project Field Engineering - Bechtel D. W. Stroham, Project Quality Assurance Engineer - Bechtel R. J. George, Mechanical Discipline Manager - Bechtel G. H. Fredy, Project Field Engineer / APE - Bechtel

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S. S. Hayter, Engineering Construction Supervisor - Bechtel

• J. L. Ruud, Field QA Supervisor - Bechtel G. Introcaso, Administration Manager - Pullman Power D. R. Murphy, Construction Engineer - Oglethorpe Power Corporation

• Attended Exit Interview Exit Interview (30703C)

The inspection scope and findings were summarized on June 6,1985, with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection findings listed belo No dissenting comments were received from the license (Closed) Inspector Followup Item 50-424/85-13-02 " Resolution of VSL NCR#

F19"-Paragraph 3 (Closed) Violation 50-424/85-09-01 " Failure to Follow Procedure to Prevent Dissimilar Metallic Materials From Coming in Direct Contact With One Another"-Paragraph 3 (0 pen) Inspector Followup Item 50-424 & 425/85-21-01 " Review Revision to Prequalified Concrete Expansion Anchors File No. X28QO2 Calculation N X2CQS.2.7"-Paragraph 98 (0 pen) Inspector Followup Item 50-424/85-21-02 " Review Rewrite of Battery Maintenance Procedures"-Paragraph 8 The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio . Licensee Action on Previous Enforcement Matters (92702)

(Closed) Violation 50-424/85-09-01 " Failure to Follow Procedure to Prevent Dissimilar Metallic Materials From Coming in Direct Contact With One Another". The inspector has reviewad Georgia Power Company's (GPC) response dated May 17, 1985 and has determined that the corrective actions have been acceptably addressed. Since the initial occurrence, the inspector has observed the implementation of GPC's corrective actio (Closed) Inspector Followup Item 50-424/85-13-02 " Resolution of VSL NCR#

F19". The inspector has reviewed VSL's NCR# F19 dated May 3, 1985 and determined that the recommended disposition based on the technical justification is acceptable. Water was only observed exiting the anchorage of tendon end No.10 (of vertical tendon No.10-102) in the tendon galler Immediate action taken by the licensee consisted of: 1.) Connecting a filtered air supply to the dome low point grease vent in tendon end No.10 to evacuate water and dry out the tendon and sheathing, 2.) Inspection of

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the dome two (2) low point grease vents and one (1) high point grease vent-for each vertical tendon No's. 6-106, 8-104,12-100, 10-102, and 14-98. All grease vent extensions were confirmed to be at a greater elevation than the maximum possible water level that could exist in the recess pocket, except the dome low point vent on tendon No. 10, therefore only tendon end No. 10 could have accepted rain. water through the dome low point grease vent. 3.)

The anchorages of vertical tendon No's, 6-106, 8-104,12-100, 10-102, and 14-98 were monitored for moisture and were found to be free of any evidence of moisture except for the anchorage at tendon end No. 10, and 4.) Filtered air was also applied. to vertical tendon No's. 6-106,88-104, 12-100, and 14-98 through the dome high point vents and no evidence of moisture was found during the inspection of the above vertical tendon anchorages in the tendon galler . Unresolved Items (92701)

Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or deviation Unresolved items were not identified during this inspectio . Construction Inspection - Units 1 & 2 (92706C)

Periodic inspections were made throughout this reporting period in the form

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of general type inspections in different areas of both facilitie The areas were selected on the basis of the scheduled activities and were varied to provide wide coverage. Observations were made of activities in progress to note defective items or items of noncompliance with the required codes and regulatory requirements. On these inspections, particular note was made of the presence of quality control inspectors, supervisors, and quality control evidence in the form of available process sheets, drawings, material identification, material protection, performance of tests, and housekeepin Interviews were made with craft personnel, supervisors, coordinators, quality control inspectors, and others as they were available in the work area Unit 1 independent inspection encompassed but was not limited to the following areas:

(1) Crane Rail Blockout - Pour Number 1-01C-125G, 15, 25 in Unit Number 1 Containment was observed to verify proper placement of concrete in accordance with the applicable Field Procedure Manual procedure (2) The inspector walked down the main steam lines in Unit No. I steam tunnel and observed the installation of permanent insulation on the ANSI B31.1 power piping portion with the exception of the welds where temporary insulation is being installed for burn protection. Temporary insulation is also being installed on the

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ASME portion for burn protection. Insulation is being installed in support of the main steam line chemical cleaning. The licensee intends on removing the temporary insulation from the welds on the ANSI B31.1 portion prior to performing the main steam line hydr Unit 2 independent inspection encompassed but was not limited to the following areas:

(1) Cavity Liner Plate Welding - The inspector conducted a general inspection of the welding operation, i.e. , weld filler metal control and storage, fit-up cleanliness requirements, slag removal and grindin No violations or deviations were identifie . Containment (Prestressing) - Observation of Work Activities -

Unit 1 (47063C) Installation Activities The inspector witnessed portions of the installation activities indicated below to verify the following:

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The latest issue (revision) of applicable drawings or procedures is available to the installers and were being use Tendons were free of nicks, kinks, corrosion; were installed in designated locations; and that the installation sequence and technique was per specified requirements.

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Installation crew was properly trained and qualifie QC inspection was properly performed by qualified personnel in accordance with applicable requirement Adequate protective measures were being taken to ensure mechanical and corrosion protection during storage, handling, installation, and post installatio The greasing of a tendon is within 15 days after tendon stressin The grease is free of foreign material or moisture contaminatio Grease temperature is within tolerance recommended by manufac-ture Vertical tendon greasing is being pumped from both ends simultaneousl . .

5 The following vertical tendons were observed:

Vertical Tendon N Sea. N Activity 14-98 3 Tendon Greasing 12-100 4 Tendon Greasing 10-102 5 Tendon Greasing 49-137 13 Tendon Installation

• Surveillance Tendon '

No violations or deviations were identifie . Containment (Steel Structures and Supports) - Units 1 & 2 (48053C)

Periodic inspections were conducted to observe containment steel and support installation activities in progress, to verify the following:

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Components were being properly handled (included bending or straightening).

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Specified clearances were being maintaine i

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Edge finishes and hole sizes were within tolerance Control, marking, protection and segregation were maintained during storag Fit-up/ alignment meets the tolerances in the specifications and drawing ;

No violations or deviations were identifie . Followup on Regional Request - Unit 1 (92705B)

NRC Region II requested review of Class 1E station battery operation, maintenance and inspection activitie This inspection reviewed the licensee's preparation for these activities due to the preoperational status of the batter The following procedures and manual were reviewed:

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27835-C, Rev 1, Class Non-1E Battery Inspection

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28805-C, Rev 0, Control Building Battery Inspection

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28810-C, Rev 0, Control Building Class 1E Battery Service Test

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28815-C, Rev 0, Control Builcing Class 1E Battery Performance Test

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28910-C, Rev 1, Class IE 18-Month Battery Inspection

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28911-C, Rev 0, Class 1E Seven-Day Battery Inspection and Maintenance

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28912-C, Rev 1, Class 1E Monthly / Quarterly Battery Inspection and Maintenance

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GEN-5301, Rev 3, Stationary Battery Maintenance and Performance Tests

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CAT-E-16, Rev 2, Batteries

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SUM-12-C, Rev 1, Class IE 125V DC System /Switchgear

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AX3AD01-25-2, Vendor Manual, C&D Stationary Battery Installation and Operating Instructions

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X3AD01, Rev 5, Specification for Batteries and Battery Chargers The following standards and commitments were utilized:

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Regulatory Guide 1.129, Rev 1, February 1978, Maintenance , Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants ,

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IEEE 450-1975 and IEEE 450- 1980

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FSAR Section 1.9.129, Licensee Commitment to RG 1.129

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FSAR Section 14.2.8.1.74, 125V dc Class 1E Preoperational Test

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Draft Technical Specification (DTS) 3.8.2.1, 3.8.2.2 and Surveillances 4.8.2.1, 4.8. The above procedures were reviewed to verify that the proper reference material and commitments were incorporated. During this review, the inspector noted the following items:

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FSAR Section 1.9.129.2 clarifies that when a performance test and service test are due simultaneously that either test shall constitute compliance with both requirements. This statement conflicts with DTS surveillance 4.8.2.1.c which states in part that only once per 60-month interval the performance test may be performed in lieu of the service test. It also was noted that DTS 4.8.2.1.d will require a service test once per every 18 months and FSAR Section 8.3.2.15 commits to once each refueling cycle but not to exceed 18 month The batteries will be subjected to a performance test. The licensee was requested to resolve this conflic In the review of procedures 27835-C thru 28912-C, numerous discre-pancies were noted to the point that the inspector concluded that these procedures would not, as written, have satisfied the DTS and IEEE 450 1975 requirements. This conclusion had been previously identified by the licensee, and a procedure rewrite was in progress. The inspector discussed the pending changes with the licensee and will review the new revision at a later dat Review rewrite of battery maintenance procedures is identified as IFI 50-424/85-21-0 . Safety-Related Structures (Structural Steel and Supports) and Safety-Related Pipe Support and Restraint Systems - Units 1 & 2 (48063C) (50090C) Procedure and Document Review The inspector reviewed and examined implementation portions of the following procedures and specifications pertaining to the installation of Phillips Redhead wedge concrete expansion anchors on seismic category I supports to determine whether they comply with applicable codes, standards, NRC Regulatory Guides and licensee commitment . . .___ ______

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Bechtel Specification X2AP01 Division C9 Section C Revision 10, Furnishing, Installation and Testing of Concrete Anchor GD-T-27, Revision 1, Installation of Concrete Expansion Anchors

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Pullman Power Products Document No. IX-1, 2/26/85 Installa-tion and Inspection of Concrete Anchors Pullman Power Products is the only contractor on site using their own procedure which has been approved by Bechtel and references Bechtel's '

specification and Georgia Power Company's procedure. The remaining contractors use Georgia Power Company's procedure which references Bechtel's specification for the installation of concrete expansion anchors. These contractors are Walsh Construction, Ingalls, Cleveland Electric and Pullman Kenith Fortson.

. Seismic Category 1 Support Design Calculation Review The inspector reviewed a sample calculation to determine that the ultimate pullout loads for Phillips Redhead wedge concrete expansion anchors used in Bechtel's design criteria was based on the commercial grade expansion anchor and not the nuclear grade expansion anchor since these anchors were being used interchangeably throughout the plant on seismic category 1 support The following documents were reviewed:

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Calculation No. X2CQ2.7, Control Building Non-Std Cable Tray Supports Unit #1 Level A Area 12 Partial Plan of Area 2A1 & 201

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DC-1000C, Rev F General Design Criteria (Civic and Structural)

for Alvin W. Vogtle Nuclear Plant Units 1 & 2

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Design Change Notice 1000-C-2-Revision 3 Table G-1 Allowable Design Loads for Concrete Expansion Anchors

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Calculation No. X2CQS.2.7 Prequalified Expansion Anchors

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Phillips Redhead; Report Prepared by Abbot A. Hanks, In Testing Laboratories; Report No. 4420, File No. H2968-S2, dated October 6, 1977 - NWS (Nuclear Grade) Concrete Expansion Anchors

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Phillips Redhead; Report Prepared by Abbot A. Hanks, In Testing Laboratories; Report No. 2821, File No. H2968-S1, dated March 15, 1977 - WS (Commercial Grade) Concrete Expansion Anchors Calculation No. X2CQ5.2.7 Prequalified Expansion Anchors supported the fact that the ultimate pull out load used in Bechtel's design criteria was for commercial grade (WS) redhead wadge concrete expansion anchor i

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During this review,- the inspector noted that calculation No. X2CQ5. for prequalified expansion anchors utilized the ultimate pull out loads from a Phillips catalog dated 3/83 and that there existed a later Phillips catalog with reduced ultimate pull out load values. The inspector questioned why the vendors latest ultimate pull out load values were not reflected in calculation No. X2CQ5.2.7 and would these values reduce the factor of safety below the required amount of 4 in accordance with IEB 79-02, Revision Bechtel Field Engineering contacted the vendor (Phillips) and confirmed that the ultimate pull out load values were reduced. The vendor stated

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that the values shown in their March 1983 catalog are based on test reports CH-1597, dated 9/20/71 and CH-2658 dated 6/28/74. Phillips published their revised ultimate pull out load values in their catalog dated 4/84 based on test report No. 2821 dated 3/15/77. Phillips said the reason for the reduce value in ultimate pull out load was due to a standardization in the method of performing Redhead test in accordance with ASTM E488-(1976) (Test Method For Strength Of Anchors In Concrete And Masonry Elements). This new method of testing was utilized in test report No. 2821, dated 3/15/77 for commercial grade (WS) and test report No. 4420, dated 10/6/77 for nuclear grade (NWS) redhead wedge concrete expansion anchors. The new test method required a higher quality control on aggregate size (e.g. the test method ~in 1971 & 1974 allowed an aggregate size of 1-1/2" diameter versus a 3/4" diameter now) and the distribution of the load was to be from the load cell to be transmitted via a support tripod to the concrete ' slab over a 20" diameter circle around the expansion anchor whereas before the load cell was placed directly around the expansion anchor which put compressive stresses into the concrete and accounted for the previously higher ultimate pull out load value Bechtel Field Engineering then contacted Bechtel LA to determine why the vendor's latest ultimate pull out load values were not reflected in their calculation No. X2CQ5.2.7 and would any of these revised values impact the minimum factor safety requirement of 4 in accordance with IEB 79-02, Revision 2. Bechtel LA informed the site that the vendor (Phillips) first published their revised ultimate pull out load values

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in their 4/84 catalog and that the 8echtel Engineering group in LA responsible for this calculation No. X2CQS.2.7 first became aware of this revised information in December of 198 The calculation N X2CQ5.2.7 was originated in 11/3/83 thus it reflected the test data of report No's. CH-1597, dated 9/20/71 and CH-2658, dated 6/28/74. A preliminary evaluation by Bechtel LA Engineering using the vendor's (Phillips) revised ultimate pull out load values has confirmed that the minimum factor of safety of 4 as required by IEB 79-02, Rev. 2 will still be maintained without affecting hardwar The revised calculation No. X2CQ5.2.7 is due out tentatively 6/14/85. Bechtel LA Engineering was aware of the vendor's (Phillips) revised test data and had it on their list of things to do to revise the calculation N X2CQ5. . .

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Pending review of the revised calculations for the design of concrete expansion anchors Calculation No. X2CQ5.2.7 this this matter is identified. as Inspector Followup Item 50-424/85-21-01 and 50-425/85-21-0 . Reactor Coolant Pressure Boundary Piping, Safety Related Piping -

Observation of Work and Work Activities - Unit 1 (49053C) (49063C)

During the inspection period, the inspector walked down flush path 16.0 CVCS auxiliary spray line contained in flush procedure 1-1BG-16. This was a back '

flush from the CVCS auxiliary spray isolation valve 8145 to the outlet of the tubeside of the regenerative heat exchange No violations or deviations were identifie . Reactor Vessel Protection - Unit 2 (50053C)

The inspection consisted of examination of the Unit 2 Reactor Vessel installed in containment to determine that proper storage protection practices were in place and that entry of foreign objects and debris was prevented. The inspector noted that protective covers were installed on the bottom mounted instrumentation penetration No violations or deviations were identifie . Reactor Vessel Integrated Head Package - Unit 1 (50053C)

The inspection consisted -of examination of the Unit 1 integrated head package stored on the refueling floor in its designated laydown area to determine that proper storage protection practices were in place, entry of foreign objects and debris was prevented, and that access was controlle No violations or deviations were identifie . Reactor Vessel Head - Unit 2 (50053C) Procedure and Document Review The inspector reviewed and examined implementation portions of the following drawings and process sheets pertaining to the installation of the control rod drive mechanisms to determine whether they comply with applicable codes, standards, NRC Regulatory Guides and licensee commitments:

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PCS #2-115-2, Revision 0, dated 3/2/85 Tackweld the Consumable Insert to the CRDM's and Capped Latch Housings

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PCS #2-115-3, Revision 0, dated 3/6/85 Tackweld of the Consumable Insert onto the Head Adapter Plugs

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2X6AB02-292-1 Closure Head General Assembly W1679E60 Sht 2 of 2

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2X6AB02-291-1 Closure Head General Assembly W1679E60 Sht 1 of 2

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NISCO 80.5.2S Rev. E Special Welding Procedure Specification for Welding of the Mechanisms Lower Canopy Seal Welds (Machine Gas Tungsten ARC Welding Method) Welding Qualification Test Witnessed the Welder Qualification Mock-Up Test of Welder Number N-32 for welding -the control rod drive mechanism's lower canopy seal wel This inspection was conducted to veri fy that the requirements of applicable specifications, codes, standards, work performance procedures and inspection (QC) procedures are being met as follows:

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Mock-Up tests are being conducted on welders for welding in confined are Welding procedures, detailed drawings and instructions were readily available and technically adequate for the weld to be mad The Mock-Up test simulated actual conditions under which the weld was to be made i Sufficient number of adequately qualified QA and inspection (QC) personnel are present at the work site commensurate with the work in progres That the purge and/or shielding gas flow and composition is as specified in the welding procedure specification and that protection is provided to shield the welding operation from ,

adverse environmental condition That the welding equipment including power cables and gas lines are in good condition and that ammeters and voltmeters used for control of the process have been calibrated in accordance with the applicable procedures requiremen No violations or deviations were identifie . Reactor Vessel Internals - Unit 1(50063C)

Periodic inspections were conducted during the inspection period when the upper and -lower internals were stored in their designated storage area to determine that proper storage protection practices were in place, entry of foreign objects and debris was prevented and that access was controlle No violations or deviations were identifie . Safety Related Components - Units 1 & 2 (50073C)

The inspection consisted of plant tours to observe protection of installed components to determine that adequate protection from dirt, debris, water, or adjacent construction activities were in plac Unit 1 equipment examined included:

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Residual Heat Removal (RHR) Pumps

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Diesel Generators

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Boric Acid Storage Tank

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Containment Spray (CS) Pumps

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Containment Penetration Encapsulation Vessel for Train A&B RHR and CS

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Auxiliary Feed Pumps

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Pressurizer

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Main Coolant Pump Casings

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Steam Generators

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Safety Injection Pumps

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Auxiliary Component Cooling Water (ACCW) Heat Exchangers

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Component Cooling Water Heat Exchangers

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ACCW Pumps

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Reactor Makeup Pumps Boron Injection Tank

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Cable Spreading Room Train A & B

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Integrated Reactor Pressure Vessel Head

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4160V Train A & B Switchgear (IAA02 & IBA03)

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13.8KV Reactor Coolant Pump Switchgear

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Reactor Vessel Lower Internals

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Reactor Vessel Upper Internals

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Sigma Refueling Bridge

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Ac:umulators

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Refueling Water Storage Tank

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Reactor Coolant Pump Motors Unit 2 Equipment Examined Included:

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Residual Heat Removal (RHR) Pumps

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Containment Spray (CS) Pumps

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Containment Penetration Encapsulation Vessel for Train A&B RHR and CS

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Pressurizer

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Steam Generators

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Safety Injection Pumps

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Reactor Vessel

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Sigma Refueling Bridge

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Accumulators

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Reactor Coolant Pump Casings The installation of the reactor coolant pump motor on Loop No. 2 in Unit I was witnesse During the installation process, the following items were found to be in accordance with the applicable requirements:

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Cleanliness

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Handling / Rigging

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Alignment

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Levelness No violations or deviations were identifie . . .

16. Electrical (Components and Systems) - Units 1 & 2 (51053C)

Periodic inspections were conducted during the inspection period to observe safety-related electrical equipment to verify that the installation and storage were accomplished in accordance with applicable requirements. The following areas were examined at during the inspections:

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Location and alignment

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Type and size of anchor bolts

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Identification

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Segregation and identification of nonconforming items

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Equipment space heating

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Rotation of motor shafts

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Lubrication and fluid levels

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Protective coatings, preservations, desiccant, inert gas blanket, et No violations or deviations were identifie . Electrical (Cables and Terminations) - Unit 1(51063C)

Periodic inspections were conducted during the inspection period to determine whether the raceway installation and protection of installed cable is in accordance with applicable codes, standards, and NRC Regulatory Guide In reference to the raceway installation, the following areas were inspected to verify compliance with the applicable requirements:

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Identification

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Alignment

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Bushings (Conduit)

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Grounding

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Supports and Anchorages In reference to the installed cable, the following areas were inspected to verify compliance with the applicable requirements:

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Protection from adjacent construction activities (welding, etc.)

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Coiled cable ends properly secured

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Unterminated cable ends taped

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Cable trays, junction boxes, etc., reasonably free of debris

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Conduit capped, if no cable installed

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Cable supported No violations or deviations were identified.

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18. Reactor Coolant Pressure Boundary (Welding) - Unit 2 (55073C)

Periodic inspections were conducted on Reactor Coolant System Primary Loop pipe welds at various stages of weld completio The purpose of the inspection was to determine whether the requirements of applicable specifications, codes, standards, work performance procedures and (QC)

procedures were being met as follows:

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Work was conducted in accordance with a process sheet which

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identifies the weld and its location by system, references procedures or instructions, and provides for production and QC signoff Welding procedures, detailed drawings and instructions, were ,

readily available and technically adequate for the welds being mad Welding procedure specification (WPS) were in accordance with the applicable ASME Code requirements and that a Procedure Qualifica-tion Record (PQR) is referenced and exists for the type of weld being mad That the base metals, welding filler materials, fluxes, gases, and insert materials were of the specified type and grade, have been properly inspected, tested and were traceable to test reports or certification That the purge and/or shielding gas flow and composition were as specified in the welding procedure specification and that protection was provided to shield the welding operation from adverse environmental condition That the weld joint geometry including pipe wall thickness was specified and that surfaces to be welded have been prepared, cleaned and inspected in accordance with applicable procedures or instruction That the pipe to be welded to the component was assembled and held in place within specified gap and alignment tolerances allowed by the ASME Cod That a sufficient number of adequately qualified QA and QC inspection personnel were present at the work site, commensurate with the work in progres That disbursement of welding materials was controlled in accordance with approved ~ procedure No violations or deviations were identifie .

1 Safety Related' Piping (Welding) - Unit 1 (55083C)

Periodic inspections were conducted on safety-related pipe welding at various stages of weld completion. The purpose cf the inspection was to determine whether the requirements of applicable specifications, codes, standards, work performance procedures and QC procedures are being met as follows:

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.That the wcld area cleanliness was maintained and that pipe alignment and fit-up tolerances were within specified unit That weld filler material being used was in accordance with welding specifications, that unused filler material was separated from other types of material and was stored in heated cans, and stubs properly removed from the work locatio That there were no evident signs of cracks, excessive heat input, sugsring, or excessive crow Installation Activities During the inspection period, welds at various stages were observed in the following systems:

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Residual Heat Removal System

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Component Cooling Water System

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Chemical & Volume Control System

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Nuclear Service Cooling Water System No violations or deviations were identifie . Fire Prevention / Protection - Units 1 & 2 (42051C)

The inspector observed fire prevention / protection measures through out the inspection period. Proper housekeeping measures to limit the amount of combustible materials and proper storage requirements are being maintaine Welders are using a welding permit with a fire watch and extinguisher. Post indicator valves were being maintained in the open position. Fire fighting equipment is in its designated areas through out the plan No violations or deviations were identifie . Management Meetings On June 7, 1985, the Regional Administrator and Staff attended the licensee's monthly Vogtle Project Board Meeting.