IR 05000424/1985048
| ML20137R193 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/14/1985 |
| From: | Livermore H, Rogge J, Schepend R, Schepens R, Sinkule M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20137R173 | List: |
| References | |
| 50-424-85-48, 50-425-85-35, NUDOCS 8512050447 | |
| Download: ML20137R193 (9) | |
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NUCLEAR REGULATORY COMMISSION
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Report Nos.: 50-424/85-48 and 50-425/85-35 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-September 27 - October 31, 1985 Inspectors: N Y h /_
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H. H. Livermore, Senior Resident Date Si Inspector, Construction YY L. IV 19ff
- g J. F. Rogge, Senior Resident-Date Si'gned Inspector, Operations
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@ R. J. Schepens, Resident Date Signed liispector, Construction Approved By.
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M. V. Sinkule, Section Chief Dat.e S'igned Division of Reactor Projects SUMMARY Scope:
This routine, unannounced inspection entailed 245 Resident inspection hours on site (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> were on backshifts) inspecting: containment and safety-related structures, piping systems and supports, safety-related components, auxiliary systems, electrical equipment and cables, instrumentation, quality programs and administrative controls affecting qu'a l i ty, preoperational test program implementation and verification, and follow-up on previous inspection identified items.
Results: No violations or deviations were identified.
8512050447 B51118
{DR ADOCK 05000424 PDR
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REPORT DETAILS 1.
Persons Contacted
' Licensee Employees
- D. O. Foster, Vice' President and Project General Manager P. D. Rice, Vice President and General Manager, Q.A.
- W. T. Nickerson, Deputy Project General Manager-D.'G. Smith, Assistant Deputy Project General Manager W. C. Ramsey, Readiness Review Manager
- H. H. Gregory III., General Manager Nuclear Construction M. H. Gouge, Project Construction Manager G. Bockhold, Jr., General Manager Nuclear Operations 0. Batum, General Manager Engineering and Licensing
- C. W. Hayes, Vogtle Quality Assurance Manager
- C. E. Belflower, Quality Assurance Site Manager - Operations
- E. D. Groover, Quality Assurance Site Manager - Construction S. D. Haltom, Quality Assurance Engineering Support Supervisor W. E. Mundy, Quality Assurance Audit Supervisor J. E. Sanders,' Project Construction Manager - Unit 1 D. M. Fiouett, Project Construction Manager - Unit 2
- B. C. Harbin, Manager Quality Control
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C. R. Brewer, 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 W. F. Kitchens, Operations Superintendent P. T. Ciccanesi, Regulatory Compliance T. Dannemiller, Senior QA Engineer R. C. Walker, Quality Assurance Field Representative G. C. Lapsley, Quality Control - Mechanical
- J. F. D' Amico, Regulatory Compliance Superintendent C..W. Joyner, Jr., Quality. control Construction J. G. Adkins, Civil Engineering - Southern Company Services
- H. W. Swain, Mechanical QC Section Supervisor Other licensee employees contacted included craftsmen, technicians, supervision, engineers, inspectors, and office personnel.
Other Organizations
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- J..Mamon, Quality Engineer - Bechtel H. M. Handfinger, Preoperational Test Superintendent - Bechtel M. L. Bagale, QA Surveillance Specialist - Bechtel B. F. Hurless, QA Surveillance SpecialistJ-Bechtel S. S. Pietrzyk, Assistant Project Engineer - Bechtel R. Johnson, Discipline Group Supervisor, Electrical - Bechtel
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G..Reardon, Pullman-Kenith Fortson - Welding G. Singer, Pullman-Kenith Fortson - Welding-A. F. Raatz, Vice President - American Welding Society
- Attended Exit Interview 2.
' Exit Interview (30703C)
The inspection scope and findings were summarized on October 31, 1985, with those persons indicated in paragraph - 1 above. The inspector described the areas inspected and discussed in detail the inspection finding listed below.
No. dissenting comments were received from the licensee.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
(Closed) Inspector Followup Item, 50-424/85-37-03 " Review Licensee Action On QA Surveillance Report-Finding No. 85-016-BJ"- Paragraph 3.
The following NRC exit interviews were attended during the inspection period by a resident inspector:
Date Inspector September 30, 1985 R. W. Newsome October 4, 1985
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R. McCoy October 18, 1985 T. D. Gibbons 3.
Licensee Action on Previous Inspection Items (92702)
(Closed) Inspector Followup Item, 50-424/85-37-03 " Review Licensee Action On QA Surveillance Report Finding No. 85-016-BJ."
The inspector has reviewed Georgia Power Company's (GPC) corrective action for surveillance finding No. 85-016-BJ, dated 8/6/85 and has determined that the finding has been acceptably addressed.
The inspector verified that SUM-16 was revised to provide specific direction with respect to the inclusion of design or other velocity ia flush procedures. Also, that Change Request #04 issued against Procedure 1-1BJ-02 (Safety Injection Pump Discharge Piping Flush) incorporated the design velocity requirements.
The licensee also reviewed all active flush procedures to~ assure compliance to the new requirements contained in Revision 5 of SUM-16.
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Unresolved Items (92701)
Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or aeviations. Unresolved items were not identified during this inspection, u
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Construction Inspection - Units 1 & 2 Periodic inspections were made.throughout this reporting period in the form of general type. inspections in different areas of both facilities.
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 housekeeping.
The inspections were performed in the containment buildings, auxiliary building, control building, and storage areas.
Interviews were made with craft personnel, supervisors, coordinators, quality control inspectors, and others as they were available in the work areas.
The inspector reviewed numerous deviation reports to determine. if requirements were met in tne areas of documentation, approvals evaluation, justification, and corrective action.
The Resident Inspectors attended and audited the licensees training session on October 22, 1985, for Quality Control Welding Inspectors concerning the training manual for inspectors of structural welds at nuclear power plants using the acceptance criteria of NC1G-01.
This covered the visual weld acceptance criteria for structural welding at nuclear power plants (Appendix VC, Rev. 10).
During this inspection, the inspector observed work in progress associated with the steam ~ generator J-nozzle modification being accomplished by Westinghouse Electric Corporation on Unit I and 2 steam generators.
This modification consists of replacing existing carbon steel J-nozzles in the feedwater distribution ring with Inconel J-nozzles for improved erosion-corrosion resistance.
The feedwater distribution ring J-nozzle assembly is classified Safety Class II. The feedwater ring assembly is not part of the pressure vessel boundary.
The inspector examined in process werk on steam generator No. 2 in Unit 1 and No.1 in Unit 2.
The inspector inspected fitups in process welding and completed welds on several nozzles.
No violations or deviations were identified.
6.
Fire Prevention / Protection and Housekeeping Measures - Units 1 & 2 (42051C)
The inspector observed fire prevention / protection measures throughout the inspection period. Welders were using welding permits with fire watches and extinguishers.
Post indicator valves were being maintained in the open position. Fire fighting equipment.is in its designated areas throughout the plant.
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The inspector reviewed and examined implementation portions of the following procedures ' pertaining to the fire prevention / protection measures and housekeeping measures to-determine whether they comply with applicable codes, standards, NRC Regulatory Guides and licensee ~ commitments.
SD-T-05, Rev. 6 Fire-Protection Equipment Inspection and Testing
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GD-T-15, Rev. 5 Welding and Cutting
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GD-T-17, Rev. 3 Housekeeping
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The inspector observed fire prevention / protection measures in work areas containing safety related equipment during the inspection period to verify the following:
' Combustible waste material and rubbish was removed from the work areas
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as rapidly as practicable to avoid unnecessary accumulation of combustibles Flammable liquids are stored in appropriate containers and in
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designated areas throughout the plant-Cutting and welding operations in progress have been authorized by an
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appropriate permit, combustibles have been moved away or safely covered, and a fire watch and extinguisher was posted as required Fire protection / suppression equipment was provided and controlled in
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accordance with applicable requirements
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No violations or deviations were identified.
7.
Containment (Structural Concrete) - Unit 2 (47053C)
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Procedure and Document Review The inspector reviewed and examined implementation portions of the following procedures pertaining to the placement of concrete to determine whether they comply with applicable codes, standards, NRC Regulatory Guides and license commitments.
CD-T-02, Rev. 15 Concrete Quality Control
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CD-T-06, Rev.
Rebar and Cadweld Quality Control
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CD-T-07, Rev. 8 Embed Installation and Inspection
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CD-T-20, Rev.
Installation and Inspection of Trumpets,
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Rigid Extensions, and Duct Sheathing b.
Installation Activities The inspector witnessed portions of the concrete placement indicated below to verify the following:
(1) Forms, Embedment, and Reinforcing Steel Installation
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. Forms were properly placed, secure, leak tight and clean.
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accordance with construction specifications and drawings, secured, free of concrete and excessive rust, specified distance from forms, proper on-site rebar bending (where applicable) and clearances consistent with aggregate size.
(2) ' Delivery, Placement and Curing Preplacement inspection was completed and approved prior
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to placement utilizing a Pour Card (Exhibit CD-T-02*18).
Construction joints were prepared as specified.
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Proper mix was specified and delivered.
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Temperature control of the mix, mating surfaces, and ambient
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were monitored.
Testing at placement location was properly performed in
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accordance with the acceptance criteria and recorded on a Concrete Placement Pour Log (Exhibit CD-T-02*20).
Adequate crew, equipment and techniques were utilized.
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Inspections curing the placement were conducted by qualified
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personnel.
Curing temperature was monitored.
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Pour No.
Location Inspection Activity 2-071-004B Diesel Generator Building Placement North - Center Quadrant Walls Periodic inspections were conducted of the containment dome reinforcing steel and tendon sheathing installation - and the diesel generator building walls-(Train
"A" North & West walls and Center-South half
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wall) reinforcing steel & embedment installation to determine that the requirements. of. applicable specifications, codes, standards, work performance procedures and inspection (QC) procedures were being followed.
No violations or deviations were. identified.
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Containment (Prestressing) - Unit 1 (47063C)
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Procedure and Document Review The. inspector reviewed and examined implementation portions of the following specification, procedure, and quality assurance manual pertaining to the installation of horizontal tendons, to determine whether they comply with applicable codes, standards, NRC Regulatory-Guides and licensee commitments.
AX2AF04-100-12 Field Instruction Manual for Installation of
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VSL E5-55 Post-Tensioning System Within Nuclear Containment Structures, Rev. 9 IX2AF04-50-5 Horizontal Tendon Elevation-Unit 1 Buttress #1
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to #2
.1X2AF04-51-4 Horizontal Tendon Elevation-Unit 1 Buttress #3
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to #1 IX2AF04-52-3 Horizontal Tendon Elevation-Unit 1 Buttress #2
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to #3 AX2AF04-78-4 Horizontal Tendon Stressing Data
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AX2AF04-79-4 Horizontal Tendon Stressing Data
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Installation Activities The inspector witnessed portions of the installation activities indicated below to verify the following:
The latest issue (revision) of applicable drawings or procedures
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are available to the installers and were being used.
Tendons were free of nicks, kinks, corrosion; were installed in
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designated locations; and that the installation sequeace and technique was per specified requirements.
Installation crew was properly trained and qualified.
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QC inspection was properly performed by qualified personnel in
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accordance with applicable requirements.-
Adequate protective measures were being taken to ensure mechanical
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and corrosion protection during storage, handling, installation,
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and post installation.
~ Tendons were stressed in the proper sequence.
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All strands in the tendon were moving together during the
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stressing and the tendon is beitig stressed from both ends simultaneously.
Elongation measurements were being taken properly and being
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compared to the calculated elongation.
Anchorhead lift-off force was being taken and documented properly.
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The stressing operation was being monitored to identify any strand
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slippage.
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Horizontal From Buttress Tendon No.
to Buttress Sequence No.
Activity
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3 West-2 West 6.
Elongation l
Measurement
1 North-3 East
Stressing
2 West-1 South
Stressing i
Ram Installation
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3 East
Anchor Head
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Installation l
1 North
Grease Cap
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i Installation
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1 North
Grease Cap Installation No violations or deviations wer,e identified.
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9.
Containment (Steel Structures and Supports) - Units l' & 2 (48053C)
l Periodic inspections were conducted to observe containment steel and support installation activities in progress, to verify the following:
Components were being properly handled.
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Specified clearances were being maintained.
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l Edge finishes and hole sizes were within tolerances.
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storage.
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Fit-up/ alignment meets the tolerances in the specifications and
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drawings.
No violations or deviations were identified.
10.
Safety-Related Structures (Structural Steel and Supports) - Units 1 & 2 (48063C)
Periodic inspections were conducted,to observe construction activities of safety-related structures / equipment supports for major equipment outside the containment to verify that:
Materials and components were being properly handled to prevent damage.
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Fit-up/ alignment were within tolerances in specifications and drawing
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requirements.
Specified clearances from adjacent components were being raet.
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No violations or deviations were identified.
11. Safety-Related Piping - Unit 1 (49063C) (337301)
During the inspection period, pipe run walkdowns were performed where piping installation is near completion to determine whether the piping run is installed as shown on current, approved drawings and in accord ance with applicable construction specifications.
Specific pipe run walkdowns included a walkdown of portions of the following lines listed below:
p&ID No./ Revision Pipe Run Inspected 1X4DB159-1, Rev. 17 Steam Generator No's. 3 & 4 Connections ard Main Steam Lines IX4DB159-2, Rev. 14 Steam Generator No's. 1, 2, 3, & 4 Main Lines 1X4DB159-3, Rev. 11 Steam L.
ator No's. 1 & 2 Connections and Main Stet Lines IX4DB168-3, Rev. 15 Steam Generator No's. 1 & 4 Main Feedwater Line IX4DB161-2, Rev. 14 Steam Generator No's.1 & 4 Auxiliary Feed-water Supply Line
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Specific areas examined during the pipe run walkdown for compliance with the applicable drawings and the plant design and Instrumentation Construction Specification No. X4AZOI were as follows:
Vent and Drain Connections and Locations Instrumentation Connections and Locations Valve Installation and Orientation-Line Size and Location Fittings Type and Size Pipe / Valve / Fitting /End Connections Hanger Locations and Types No violations o deviations were identified.
12.
Reactor Vessel Protection - Unit 1 & 2 (50053C)
l The Unit No.1 inspection consisted of examination of the 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 Unit No. 2 inspection consisted of examination of the 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.
No violations or deviations were identified.
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Reactor Vessel Integrated Head Package - Unit 1 & 2 (50053C)
The Unit No.1 inspection consisted of examination of the 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 controlled.
The Unit No. 2 inspection consisted of examination of the Reactor Vessel head with the installed control rod drive mechanisms on the refueling floor in its designated laydown area. During the assembly of the integrated head package, proper storage protection practices were observed to be in place and maintained during the performance of this work.
No violations or deviations were identified.
14.
Reactor Vessel Internals - Unit 1(50063C)
Periodic inspectinns 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
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foreign objects and debris was prevented and that access was controlled.
No violations or deviations were identified.
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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, dust, debris, water, or adjacent construction activities were in place.
Unit 1 equipment examined included:
Residual Heat Removal (RHR) Pumps
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Diesel Generators
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Containment Spray (CS) Pumps
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Pressurizer
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Main Coolant Pumps
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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 (CCW) Heat Exchangers
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Cable Spreading Room Train A & B
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Accumulator Tanks
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Reactor Coolant Drain Tank Pumps
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Chemical and Volume Control System (CVCS) Letdown Heat Exchanger
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Reactor Coolant Drain Tank & Heat Exchanger
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Reactor Cavity Pumps
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Battery & Charger Rooms Train A, B, C & D
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Nuclear Grade Piping, Valves & Fittings
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Spent Fuel Pool Heat Exchangers
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Pressurizer Relief Tank
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Nuclear Service Cooling Water (NSCW) Pumps
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CVCS Centrifugal Charging Pumps & Positive Displacement Pump
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Unit 2 equipment examined included:
RHR Pumps
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CS Pumps
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CVCS Centrifugal Charging Pumps & Positive Displacement Pump
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Safety Injection Pumps Train A & B
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ACCW Heat Exchangers
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CCW Surge Tank
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Accumulator Tanks
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Pressurizer Relief Tank
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Diesel Generator Fuel Oil Tanks
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An inspection was conducted of the equipment maintenance storage listing (EMSL) program records for the below listed safety-related pump motors. The purpose of this inspection was to verify that the EMSL maintenance report cards for the below selected equipment was stored in the vault and that the required inspections / preventative maintenance had been performed and
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properly documented. The inspector reviewed the following EMSL maintenance r
report cards:
Equipment Tag No.
Description 1-1203-P4-001-M01 Component Cooling Water Pump Motor 1-1203-P4-003-M01 Component Cooling Water Pump Motor 1-1205-P6-002-M01 Residual Heat Removal Pump Motor Train "B" 1-1206-P6-001-M01 Containment Spray Pump Motor Train "A" l
1-1206-P6-002-M01 Containment Spray Pump Motor Train "B" 1-1208-P6-001-M01 Chemical Volume Control System Positive Displacement Pump Motor 1-1208-P6-002-M01 Chemical Volume Control System Charging
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Pump Motor Train "A" l
1-1208-P6-003-M01 Chemical Volume Control System Charging
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Train "B"
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2-1204-P6-003-M01 Safety Injection Pump Motor Train "A" l
2-1204-P6-004-M01 Safety Injection Pump Motor Train "B"
2-1205-P6-001-M01 Residual Heat Removal Pump Motor Train "A" l
2-1205-P6-002-M01 Residual Heat Removal Pump Motor Train "B" 2-1206-P6-001-M01 Containment Spray Pump Motor Train "A" 2-1206-P6-002-M01 Containment Spray Pump Motor Train "B" 2-1208-P6-001-M01 Chemical Volume Control System Positive Displacement Pump Motor 2-1208-P6-002-M01 Chemical Volume Control System Pump Motor Train "A" 2-1208-P6-003-M01 Chemical Volume Control System Pump Motor
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2-1217-P4-002-M01 Auxiliary Component Cooling Water Pump Motor l
The inspector noted that each of the above EMSL cards reflected that a deviation notice No, M02729 was written on May 24, 1984, which documented discrepancies with the above motors su:h as oil leaking from around sight glass or drain plug and oil levels in upper and lower motor bearings either high or low. Again on November 1, 1984, it was documented that another deviation notice was written on the above equipment for the same apparent i
reasons and then on November 10, 1984, Deviation No. ES-00403 was issued to i
document the above discrepancies and the deviation report was signed off on February 28, 1985, as being resolved.
At the time this discrepancy was first documented on May 24, 1984, Georgia Power Company's (GPC's) field procedures required that the inspector first l
document the discrepancy on a deviation notice.
However, if corrective action was not instigated within two (2) working days then the matter was to be reported on a deviation report per GPC's Field Procedure GD-T-01. In the above case this procedural requirement was not followed and therefore, i
appears to be a violation of procedure.
The inspector requested to review other deviation notices in this time frame to see if this was an isolated case or if there existed other examples where deviation notices were not turned into deviation reports in a timely manner l
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as required by procedure.
The licensee stated that their procedures have been changed since that time and that since deviation notices were not official documents (i.e. they were used like a memo to notify Engineering of a deviation), they did not save them so there was not a file on hand for the inspector to review.
Based on this being the only example, the inspector considers the above matter to be an isolated case and since the licensee identified and took the necessary corrective action, no enforcement action will be taken for the apparent procedural violation.
No violations or deviations were identified.
16.
Safety-Related Pipe Support and Restraint Systems - Unit 1 (50090C)
Periodic inspections were conducted to observe construction activities of safety-related systems to verify that:
Supports are located and installed as specified.
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The surface of weld meets applicable code requirements and is free from
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unacceptable grooves, abrupt ridges, valleys, undercuts, cracks, discontinuities, or other indications which can be observed on the welded surface.
The insoector conducted a walkdown of the NSCW Train A & B Supply & Return Header Pipe Supports in the NSCW Tunnel.
An inspection of the above attributes was conducted for the following completed / accepted pipe supports:
pipe Support Dwg. No./ Revision Support type VI-1202-088-H035, Rev. 3 Fixed - Spring Can V1-1202-088-H036, Rev. 4 Fixed - Spring Can V1-1202-088-H038, Rev. 5 Fixed - Spring Can V1-1202-004-H059, Rev. 2 Fixed - Spring Can No violations or deviations were identified.
17.
Electrical (Components and Systems) - Units 1 & 2 (51053C)
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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 during the inspections:
Location and align 5ent
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Type and size ci 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, desiccants, inert gas blanket, etc.
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l During the inspection period, periodic inspections were conducted of the
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licensee preparations for the initial diesel vendor run on Train
"B".
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inspector reviewed the startup operation instructions (501's) titled:
Initial Diesel Generator Startups and Diesel Generator Phase Sequence Verification.
The inspector witnessed the following operations in preparation for the initial diesel vendor run on Train "B" diesel in accordance with the applicable SOI:
l Prerequisites, and initial conditions were satisfied prior to the
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initial diesel start Operating instructions, preparation for engine initial startup, and
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l electrical preparation Cylinder moisture checks
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Diesel run
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l Functional testing of the diesel engine control panel
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No violations or deviations were identified.
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Electrical (Cables and Terminations) - Unit 1(51063C)
a.
Raceway / Cable Installation The inspector reviewed and examined implementation portions of the following procedures pertaining to raceway / cable installation to determine whether they comply with applicable codes, standards, NRC Regulatory Guides and licensee commitments.
ED-T-02, Rev. 8 Raceway Installation
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ED-T-07, Rev. 9 Cable Installation
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In reference to the raceway installation, the following areas were inspected to verify compliance with the applicable requirements:
Identification
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Alignment
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Bushings (Conduit)
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Grounding
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Supports and Anchorages
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In reference to the cable-installation the following areas were l
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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.Non-terminated cable ends taped
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Conduit capped, if no cable installed
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Cable supported
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Bend radius not exceeded.
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j-Separation-
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The inspector reviewed the EE580 cards for cable pull no's. ICD 1M04SN and ICD 1M03SN.
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Cable Terminations i
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Guides and licensee commitments, i
ED-T-08, Rev. 7 Cable Termination f
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In reference to. cable terminations-the following areas were inspected l
to verify compliance with the applicable requirements.
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Cable' identification
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Proper lugs used
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Condition of~ wire (not nicked, etc.), tightness of connection
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' Bending radius not exceeded
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Cable' entry to terminal point
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Separation
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The inspector witnessed the Quality Control Inspector inspections of r
the following Class IE terminations:
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Number Number Box Number i
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.1BBB23SF2 IBHJB2669 X2 1
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1AH12604SJ1 1AHJB2555 N1 11
'C4 12'
t IBH121485R1 IBHJB1311, N1 13
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IBH12148WC2 IBHJB1311 CD5 19
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CD6 20 SHLD 21 IBBC20LA1 1-1805-S3-BBC IBBC20 M1 A M2 8 1BBC06SC1 1-1805-SC-BBC IBBC06W HI U24 IBBA295C2 IBHJB2670 XI 1
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C6 2 C1 3 C2 4 No violations or deviations were identified.
19. Preoperational Test Program Implementation / Verification - Unit 1 (70302)
(71302)
The inspector reviewed, in part, the implementation of the preoperational test program.
Test program attributes inspected included review of administrative requirements, document control, documentation of major test events and. deviations to procedures, operating practices, instrumentation calibrations, and correction of problems revealed by the test.
Specific activities reviewed included the following test procedure:
Preop No.
Preop test Procedure Title 1-300-17, Rev. O Steam Generator Secondary Side Hydrostatic Test The inspector also conducted a verification of the initial valve lineup on the following lines in accordance,with Appendix VIII-1 of the above procedure on October 17, 18, 1985:
P&ID No./ Revision Pipe Run Valve Lineup Inspected IX408159-1, Rev. 17 Steam Generator No's, 3 & 4 Connections and Steam Lines IX4DB159-2, Rev. 14 Steam Generator No's, 1, 2, 3, &4 Main Steam Line IX4DB159-3 Rev. 11 Steam Generator No's. 1 & 2 Connections and Main Steam Lines IX4DB168-3, Rev. 15-Steam Generator No's. 1 & 4 Main Feedwater Lines L-
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1X4DB161-2, Rev. 14 Steam Generator No's. 1 & 4 Auxiliary Feedwater Supply Line The inspector noted the following discrepancies in the valve lineup:
Required Tagged As Found Valve No.
position Position Position 1-1301-X4-024 Open Open Less Than 1/2 Open 1-1301-U4-118 Open Open Closed 1-1301-X4-071 C1'osed Closed Closed Tagged 072 1-1301-X4-072 Closed Closed Closed Tagged 071 1-HV3006A Open Open 1/2 Open 1-HV13005A Open Open 1/2 Open 1-HV3026A Open Open 1/2 Open 1-HV13008A Open Open 1/2 Open 1-1302-X4-098 Closed Open Closed 1-1302-X4-099 Closed Open Closed.
1-1302-X4-100 Closed Open Closed 1-1302-X4-101 Closed Open Closed On October'18, 1985, the inspector conducted an inspection of the official Secondary Hydro Procedure Package. The inspector noted in that Step 5.29 which stated to install the thermocouples per Appendix XIII had been signed off as being completed on October 14, 1985. However, at the time of this inspection only four of eight thermocouples were in fact installed and Appendix XIII had not been completed. The valve lineup and thermocouple discrepancies were identified to the licensee.
The licensee informed the inspector the following:
(1) A valve line-up reverification would be performed on the initial, valve line-up - and that a final valve line-up had yet to be performed which would reverify all the boundary valves prior to the hydro, and- (2) 'The thermocouples had apparently been removed by construction for pre-service inspection on the welds at the main steam and feedwater nozzle connections. Operations would discuss this matter with construction to reinforce the importance of not
' removing testing equipment.
In addition, the fact that the thermocouples c
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were not installed would have been picked up on the data logger since these monitoring points would not indicate.
The inspector stressed with the licensee the importance of properly conducting preoperational testing; valve line ups must be accurate, procedures must reflect the system test status, and test equipment must be closely controlled. Management attention should be increased to ensure that safety-related system testing will be properly controlled.
The inspector witnessed the Secondary Hydrostatic Test on October 21, 1985.
The following attributes were verified by the inspector during the test:
Sufficient management on hand to supervise / observe the hydrostatic
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test.
Pullman ANI and Westinghouse ANI on hand during the Hydrostatic Test.
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Test pressure held at 1487+12, -0 psig for a minimum after (10)
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minutes.
Leak checking visual inspection within the hydro pressure boundary was
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conducted with Pullman Hydro Package 1-1305-15.
Steam generator temperatures were monitored at designated locations
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throughout the test in accordance with applicable requirements.
Calibrated test gauges were used for the official and back-up test
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No violations or deviations were identified.
20.
SafeEy-Related Piping (Welding) - Unit 1 (55083C)
Periodic inspections were conducted on safety-related pipe welding at various stages of weld completion.
The purpose of the inspection was to determine whether the requirements of applicable specifications, codes, standards, work performance procedures and QC procedures are being met as follows:
That the weld area cleanliness was maintained and that pipe alignment
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and fit-up tolerances were within specified units.
That weld filler material being used was in accordance with welding
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specifications, that filler material was separated from other types of material and was stored in heated rod caddies, and stubs were properly removed from the work location.s-That there were no evident signs of cracks, excessive hcat input,
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sugaring, or excessive crown.
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During the inspection period, welds at various stages were observed in the l
following systems:
l Residual Heat Removal. System
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Component. Cooling Water System
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l Chemical & Volume Centrol System
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Nuclear Service Cooling Water System
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j No violations or deviations were identified.
21. Management Meetings (307028)
t On_ September 27, 1985, the Resident Inspectors attended a project status l
meeting presented by the licensee to R. Walker, Director, Division of Reactor Projects out of Region II. -The topics presented by the licensee are as follow:
(1) Present Site Organization (2) Anti-Drug Program, (3)
Construction Overview, (4) Nuclear Operation Overview, (5) Quality Assurance, & (6) Readiness Review.
The meeting was followed by a tour of the facility and the Training Center / Simulator.
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