IR 05000425/1988038

Insp Rept 50-425/88-38 on 880627-0803.No Violations or Deviations Noted.Major Areas Inspected:Fire Protection, Reactor Vessel & Internals,Piping Sys & supports,safety- Related Components & Raceways & Instrumentation

ML20151Z990
Person / Time
Site:	Vogtle
Issue date:	08/19/1988
From:	Burger C, Schepens R, Sinkule M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20151Z989	List: IR 05000425/1988038 ML20151Z986
References
50-425-88-38, NUDOCS 8808300353
Download: ML20151Z990 (21)

Text

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Ett UNITED 5TATES

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. NUCLEAR REGULATORY COMMISSION

l y 3 REOl0 Nil -

e o 101 MARIETTA STREET. U* "

ATL ANTA, GEORGI A 30323

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i i Report No.: 50-425/88-38 .;

Licensee: Georgia Power Company I P.O. Box 4545  ;

Atlanta, GA 30302  :

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s Docket No.: 50-425 Construction Permit No.: CPPR-109

Facility Name: Vogtle 2 -

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Inspection Conducted: June 27 - August 3, 1988 I

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Inspector:A b4-  % 8fm/s s j 'R. J. Schepens, Senior Resident Inspector Date Signed l

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l C. W. Burger, Resident Inspector Date 51gned Approved By: h 224u M. v7 51nkule, Sect <on chter 8!/9!//f  !

Date Signed DivisionofReactorProjects l

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I j SU R RY 3 Scope: This routine, unannounced inspection entailed resident inspection in i

the following areas: fire protection, reactor vessel and internals, ,

piping systems and supports, safety related components, auxiliary systems, electrical e raceways and instrumentation,

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preoperational testing,quipment,qualit

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affecting quality, and followy programs and administrative up on previous inspection identifiedcontrols  !

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items, i I

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) Results: No violations or deviations were identifie )

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REPORT DETAILS

' Persons Contacted

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Licensee Employees

*P. D. Rice, Vice President, Vo' t1e Project '"rector i *R. M. Pinson, Vice President,,roject Construction i G. Bockhold, General Manager i T. V. Greene, Plant Support Manager

• C, W. Hayes, Vogtle Quality Assurance Manager

! * D. Groover, Quality Assurance Site Manager - Construction M. Fiquett, Profect Construction Manager - Unit 2

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• A. B. Gallant, Pro;ect Compliance Coordinator C. L. Coursey, Maintenance Superintendent (Startup)

M. M. Handfinger, Assistant Plant Support Manager A. W. Harrelson, Construction Electrical Manager C. W. Rau, Construction Mechanical Manager L. N. Brooks, Construction Civil Manager L. B. Glenn, QC Manager

• R. W. McManus, Readiness Review Manager

• J. E. Sanders, Assistant Project Manager W. C. Ramsey, Project En ineering Manager L. D. Marless, Manager, uality Concerns

• R. J. Pope, Mechanical F eld Office Staff Engineer

• W. R. Cheatwood, Mechanical Engineering Supervisor

• L. Larson, Mechanical Fire Protection Group

• J. J. Maddry, Fire Protection Manager Other licensee employees contacted included craftsmen, technicians, supervision, engineers, inspectors, and office personne Other Organizations C.Marcum,WestinghouseProjectManager D. L. Kinnsch, Project Engineering - Bechtel T. E. Richardson, Project Engineering Manager - Bechtel

• D. W. Strohman ProjectQAEngineer-Bechtel A.J.Ayob,VSAMU, Supervisor-Westinghouse, B. Edwards, Site Manager - Pullman Power Products J. Miller, Quality Assurance Manager

• Attended Exit Interview Licensee Action on Previous Enforcement Matters - (92702)

(Closed) Violation 50-425/88-27-01 "Failure To Implettent Adequate Design Control." This violation identified the failure to provide the' function to display pressurizer primary safety valve position indication status on

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1 plasma dis 31ay per FSAR table 7.5.2.1. The licensee's letter of response dated Octo3er 3,1986, has been reviewed and determined to be acceptable.

', The inspector held discussions with the licensee's responsible engineers and examined the corrective action described in the letter of respons The inspector external has conducted connection a review drawings (2X6 of the p&lant AZO 2-121 133)safety monitoring to verify the system incorporation of pressurizer primary safety valve position indication

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status to the plasma display module of the plant safety monitoring system on Unit 2. In addition, a review was conducted of the post accident monitoring system preoperational test procedure (2-3RP-03, Rev. 0) to verify that this function on plasma display will be tested. Based on the above review the inspector determined that the corrective action has been

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implemented, therefore this item is considered to be close (Closed) Violation 50-425/88-01-01 "Rejectable Radiographic Indication In a Code Class 1 System Weld (2-1201-030-W30)." This violation identified a weld that had an elongated indication of 1 inch in length which exceeded ASME code section III acceptance criteria. 'he licensee's letter of response dated May 3,1988, has been reviewed and determined to be acceptabl The inspector held discussions with the licensee's responsible engineers and examined the corrective actions to prevent

recurrence in the letter of response. The insoector verified that the corrective action had been implemented, therefore this item is considered a to be close ! (Closed) Violation 50-425/88-10-01 "Failure To Issue Field Change Request

! For Addition Of Fire Protection Piping To Cable Tray Supports." The grevious inspection idertified three cable tray supports (TS-154-370,

, iS-154-493, and 75-154-508) which had fire equipment supports welded on them without a FCR being issued which would permit the weld attachmen The licensee's letter of response dated April 28, 1988, has been reviewed and determined to be acceptable. The inspector held discussions with the licensee's responsible engineers and examined the corrective actions

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described in the letter of response. The inspector verified that the corrective actions had been implemented and complete . Genersi Construction Inspection - (92706)

! Periodic random surveillance inspections were made throughout this reporting period in the form of general type inspections in different

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areas of the facilit The areas were se:ected on the basis of the

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scheduled activities and were varied to provide wide coverag Observations were made of activities in progress to note defective items or items of noncompliance with the required codes and regulatory l

requirements. On these inspections, particular note was made of the

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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 l housekeeping. Interviews were conducted with craft personnel, supervisers, j

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coordinators, quality control inspectors, and others as they were available in the work areas. The inspector reviewed numerous construction ,

deviation reports to determine if requirements were met in the areas of '

documentation, action tu resolve, justification, and approval signatures inaccordancewithGPCFieldProcedureNo.GO-T-0 During this inspection period, the inspector observed licensee activities relative to the preparation for Hot functional Testing, which is scheduled for September 23, 1988, at which time the plant will be taken ebove 180 degrees Fahrenheit. Management has directed their attention in the weekly management oversight meeting for preoperational testing to HFT support systems status given by the lead test supervisor. During these meetings, managements attention is focused on the following key areas: preopera-tional test actual verses scheduled start and finish dates; testing  !

progress including early identification of hard spots, minimizing punch  ;

list open items, and the early identification of material / procurement f problems in support of HFT. The inspector noted that management is effective in these meetings relative to the coordination of construction,  !

preoperational testing, and support organizations such as engineering, and i procurement to ensure proper and timely completion of prerequisites required for HF No violations or deviations were identifie ! Fire Prevention / Protection and Housekeeping Measures - (42051C)

The inspector observed fire prevention / protection measures throughout the  :

inspection period. Welders were using welding permits with fire watches and extinguishers. Fire fighting equipment was in its designated areas througnaut the plan The inspector reviewed and examined portions of procedures pertaining to the fire prevention / protection measures and housekeeping measures to i determine whether they comply with applicable codes, standards, NRC  !

Regulatory Guides and licensee commitment The inspector observed fiee pre'ention/ otection measures in vork areas containing safety related equip N nt during the inspection period to verify the following:  !

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Combustible waste material and rubbish was removed froa the work areas as rapidly as practicable to avoid unnecessary accumulation of combustible !

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Flammable liquids were stored in appropriate containers and in l designated areas throughout the plan !

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Cutting and welding operations in progress have been authorized by an appropriate permit, combustibles have been moved away or safely covered, and a fire watch and extinguisher was posted as require t

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Fire protection / suppression equipment was provided and controlled in accordance with applicable requirement :

During the inspection period, the inspector- conducted a review of the  !

! following documents which covered the design construction, testing of the 1 deluge, water spray, sprinkler, and halon systems fire suppression '

system f Procedure N Title '

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X4AX03,R-16 Technical Provisions For Automatic Sprinkler And t Halon Fire Suppression Systems '

MD-T-22,R-0 National Fire Protection Association Piping i Installation '

MD-T-23,R-1 Testing Of NFPA Systems '

MD-T-24,R-0 NFPA Piping Support Installation  !

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MD-T-25,R-2 In-Process Evaluation Of Separation For I l Mechanical Commodities  !

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The ins ector conducted a walkdown of the diesel generator train A & B

) electri al tunnel installed sprinkler systems for compliance with the l

) applicable design and construction reouirement The following drawings were utilized by the inspector in the inspection:

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2X40F00276,R-0 Fire Protection Sprinkler System #29 Startup System

2KC-08

. 2X40F00277,R-1 Fire Protection Sprinkler System #30 Startup System 2KC-08 i

No violations or deviations were identified.

' Reactor Coolant Pressure Boundary and Safety Related Piping - (49053C)

) (49063C)

System Walkdown Inspection

i Selected portions of the Spent Fuel Pool Cooling & Purification i System Train "B" were walkec dow The constructed piping system was

! compared to the pipin and instrumentation diagrams. Examples of

! items checked were pi ng configuration, aipe class, weld location, j and appearance type va ve location and ot"entation, labeling, piping su,tport location, vent and drain connections, instrumentation connections, and engagement of threaded fasteners.

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The inspectors conducted the walkdown inspection with the piping and !

instrumentation diagra:n to verify that the system was constructed as shown on the current, approved revision and in accordance with the >

p ng and instrementation construction specification X4AZ01. The '

p ng runs inspected were designed and constructed to ASME Boiler & :

1 Pressure Vessel Code Section III, Class III and seismic category 1 i requirements. The following drawings were used in the walkdow ,

Dwg No./Re Title 2X4D8130, R-12 P&I Diagram SFPCPS J

2K7-1213-002-02,R-8 SFPCPS Fabrication Isometric Fuel Building Area 30 Level A 2K7-1213-006-01,R-13 SFPCPS Fabrication Isometric fuel Bu11 ding Area 3A Level A J

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2K7-1213-006-02,R-6 SFPCPS Fabrication Isometric Fuel Building Area 30 Level A 2J7-1213-006-01,R-2 SFPCPS Fabrication Isometric Fuel Building Area 30 Level A b. Safety-Related Containment Isolation Valve Installation Review l A representative sample of installed valves were inspected to verify i

that the as installed conditioned was accordance with the require-

} ments specified in the applicable piping and instrumentation

drawings, isometric drawings, and instrumentation index or valve j designation list. The following attributes were inspected

proper j valve orientation and flow direction; proper valve sizing and type;

) proper piping class (i.e, code class, pressure N ting, material type, and end connection type); proper tag and serial number; proper piping of instrument air to air operated valves to ensure that valve will fail to the safe position on loss of air pressure; and proper operator sizing to ensure closure against maximum operational differential pressure conditions. The following valves were randomly selected by the inspector and inspected for the above noted

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Valve N Description Drawing N Size / Type

2HV-781 Reac Cav & Cnmt 2X4AR01-366 3" Air

! Operated l Sump Hdr Iso Gate

2HV-3502 NSSL Res Hot 2X5AC01-193 1/2" Air Leg #1 & 3 Sample Operated Globe i

! 2HV-3508 NSSL Pzr Liq 2X5AC01-193 1/2" Air Sample Operated Globe

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Valve N Description Drawing N Size / Type 2HV-3514 NSSL Pzr Stm 2X5AC01-193 1/2" Air I Sample Operated Globe 2HV-7136 WPSL RCDT 2X6AA06-256 3" Air Operated l Pump Disch Iso Diaphragm i 2HV-7150 WPSL RCDT 2X6AA06-263 3/4" Air Vent Iso Operated Diaphragm 2HV 8105 Charg Pump 2X6AA06-560 3" Motor To RCS Iso Operated Gate 2HV-8106 Charg Pump 2X6AA06-560 3" Motor To RCS Iso Operated Gate 2HV-8116 Charg Pump A 2XGAA06-552 1" Motor Disclarge Operated Globe 2HV-8152 Letdown 2X6AA06-445 3" Air Isolation Control 2HV-8835 Sis Cold leg 2X6AA06-406 4" Hotor In Hdr Iso Operated Gate 2HV-8888 Safe Inj Pump 2X6AA06-261 3/4" Air Accum Test Iso Operated Iso Control 2HV-8954 Accum Holding 2X6AA06-26) 3/4" Air Tk Iso Operated Control During the records review inspection, the inspector noted a Westinghouse letter which requested the return of several valves to the manufacturer, Fisher, for a modification to meet seismic requirements. The inspector was unable to determine the nature of the required modification nor verify its incorporation; therefore, pending further review, this matter will be identified as Inspector Followup Item 50-425/88-38-01 "Review Licensee's Finding Relative To The Seismic Qualification Of Valves 2HV-8152, 8888, & 896 No Violations or Deviations were identifie . Contain:nent Penetrations (Mechanical) Record Review (53055)

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The inspector reviewed and examined a random sample of containment penetration installation records by Chicago Bridge and Iren Incorporated  ;

(CBI) to determine whether:  !

- The system for preparing, reviewing, and maintaining records had been implemented properly

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- The selected records reflect work was accomplished consistent with the specification and code requirements 1

- The records indicate any potentially generic problems, management control inadequacies, or other weakness that could have safety i significance

- Installation activities were conducted with refarence to specified procedures and by qualifiea personnel where required

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- Non Destructive Examination (NDE) was performed in accordance with procedures, and examination personnel are qualified

- Inspection (QC) activities were performed as required by proper procedures and by properly qualified personne The applicable construction specification for the installation of the flued head pipe penetrations is X4AZ01 Division P-1 and P-3. Installation activities, testing, examination, inspection and N-Stamping was in accordance with the ASME Boiler and Pressure Vessel Code Section III, 1977 Edition, including addenda through Winter 197 The inspector reviewed pertinent records associated with the flued head pipe penetrations listed below to determine conformance with requirements for receipt inspection and material certiff cation, installation and

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i testing,nonconformance/deviationrecords,andqualificationofcraft,QA andinspectionQCpersonne !

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This review included the welding and NDE associated with the flued head '

pipe penetration installation by Chicago Bridge and Iron. The following ,

types of documentation were reviewed: 1) CBI stores release for item or .

material, 2) CBI skt.tches and record table for field welds, 3) CBI NDE l reports for welds involved, 4) CBI N-5 data reports, 5) CBI welding material authorization and release reports, and 6) CBI welder qualifi- '

cations for welders involve ;

The following flued head pipe penetrations were randomly selected by the inspector and inspected for the above noted attributes:

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Penetration N System Description Size Type Material

, 24 Reactor Coolant 1/2" II SS-304L

Loop 1 & 3 Hot

! Leg Sample Line 30 Safety Injection 4" II SS-304L Cold Leg Loop Inlet  ;

Header Isolation

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41 SafetyInjectionTest 3/4" II SS-304L Line To RWST

! 48 Normal Letdown To CVCS 3" I SS-304L Letdown Heat Exchanger i

50 Positive Dis)1acement 3" I SS-304L l

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l Charge Pump Jischarge To Regenerative Heat Exchanger

, 67 Pressurizer Steam And 1/2" III SS-304L LiquM Samp!e Line Ano Ctmt Pressure Transmitter

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77 RCOT Heat Exchanger 3" II SS-304L .

Disch To WPS Waste  !

! Hold Up Tank 79 RCOT H Su 3/4" II SA-350LF2 Wastedas]plyAnd Removal

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During the above inspection, the inspector determined that the required !

j documentation had been properly completed and Ws being maintained as <

required for future review and reference, The inspector noted a strength '

in this area relative to proper filing, and completeness of documentation ;

so as to make it easily accessible for future referenc No violations or deviations were identified, I

7. Reactor Coolant Pressure Boundary and Safety Related Piping Welding -

(55073C) (55083C)

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Periodic inspections were conducted during daily plant surveillances on i safety-related pipe welding at various stages of weld completion, The '

purpose of the inspection was to determine whether the requirements of i applicable specifications, codes, standards, work performance procedures and QC procedures are being met as follows:

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- Work was conducted in accordance with a process sheet which '

identifies the weld and its location by system, references procedures or instructions, and provides for production and QC signoff i

- Welding procedures, detailed drawings and instructions, were readily l

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available in the immediate work area and technically adequate for the welds being mad !

- Welding procedure specification were in accordance with l the applicable Code requirements and that a Procedure Qualification i Record is referenced and exists for the type of weld being mad :

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- Base metals, welding filler materials, fluxes, Ipses, and insert

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materials were of the specified type and grade, have been properly inspected, tested and were traceab't to test reports or certification Purge and/or shielding gas flow ano composition were as specified in the welding procedure specification and ' hat protection was provided to shield the welding operation from adverse environmental condition Weld joint geometry including pipe wall thickness was specified and that t surfaces to be welded have been prepared, cleaned and inspected in accordance with asplicable procecures or instruction A sufficient numt.er of adequately qualified QA and QC ins)ection personnel were present at the work site, commensurate wit 1 the work in progres The weld area cleanliness was maintained and that pipe alignment and fit-up tolerances were within specified limit Weld filler material being used was in accordance with welding specifications, unused filler material was separated from other types of material and was stored properly tnd that weld rod stubs were properly removed from the work locatio N t there were no evident signs of cracks, exaessive heat input, sugaring, or excessive crown on weld Welders were qualified to the applicable process and thickness, and that necessary controls and records were in plac No violations or deviations were identifie , Reactor Vessel, Integrated Head Package, and Internals - (50053C)(50063C)

The inspection consisted of examinations of the Reactor Vessel installed s*

in containment, and the Integrated Head package which is tensioned in support of hot functional testin Inspections also determined that proper storage protec+40n practices were in place and that entry of foreignobjectsanddeLeiswasprevente Also, during this inspection period, the inspector observed the removal of the missile shield from the reactor vessel integrated head package to facilitate the installation of the control rod drive position indication and the incore thermocouple cable connector No violations or deviations were identifie _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____ _

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10 Safe'y Related Components - (50073C)

The inspection consisted of 31 ant tours to observe storage, handling, and protection; installation; anc preventive maintenance af ter installation of safety-related components to determine that work is being performed in accordance with applicable codes, NRC Regulatory Guides, and licensee commitment During the inspection the below listed areas were inspected at various times during the inspection period to verify the following as appitcable:

- Storage, er<fronment and protection of components were in accordance withmanufacturer'sInstructionsand/orestablishedprocedure Implementation of special storage and maintenance requirements such as:

rotation of motors, pumps, lubrication, insulation testing (electrical),

cleanliness, etc.

1 - Performance of licensee / contractor surveillance activities and

documentation thereof was being accomplished.

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- Installation requirements were met such as: proper location, placement,

) orientation alignment, mounting (tor J anchors),flowdirection, tolerances,quingofboltsandexpansion and expansion clearance, j - Appropriate stamps, tags, markings, etc. were in use to pravent

oversight of required inspections, completion of tests, acceptance, and

, the prevention of inadvertent operation.

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! Safety-Related piping, valves, pumps, heat exchangers, and instrumentation

! were inspected in the following areas on a random sampling basis throughout the inspection period:

l - Residual Heat Removal Pump Rooms i - Diesel Generator Building

- Auxiliary feedwater Pum) house

- Containment Spray Pump Rooms

] - Pressurizer Rooms

- Main Coolant Pump Areas

- Steam Generator Areas

-SafetyInjectionPumpRooms, 1 - RHR and CS Containment Penetration Encapsulation Vessel Rooms 1 - Component Cooling Water Heat Exchangers, Surge Tanks & Pump Rooms j - Cable Spreading Rooms j - Accumulator Tank Areas a - Chemical and Volume Control System Letdown Heat Exchanger j Pump Room-Battery &CharkerRooms

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- Spent ruel Poo Heat Exchanger Rooms

- Pressurizer Relief Tank Area I - CVCS Centrifugal Charging Pumps & Pcsitive Displacement Pump Rooms 1 - Bottom Mounted Instrumentation Tunnel and Seal Table Area l

- BMI and Supports Under Reactor Vessel j

- NSCV Tower Pump Rooms and Pipe Tunnels

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) i The inspector noted to the licensee that there still exists a large

quantity of construction support material within the power block (such as scaffolding, welding machines, flushing fixtures and hoses, etc.) and that much of this material will be required to be removed in support of hot functional testing. Licensee management acknowledge the present situation >

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and stated that this item is on their priority list and improvements l l should be noted in the near futur j j No violations or deviations were identified.

) 10. Safety Related Pipe Support and Restraint Systems - (500900)

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Periodic random inspections were conducted during the inspection period to j j observe construction activities during installation of safety-related pipe  :

supports to determine that the following work was performed in accordance  !

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with applicable codes, NRC Regulatory Guides, and licensee commitments.

- Spring hangers were provided with indicators to show the approximate E j "hot" or "cold" position, as appropriat !

1 - No deformation or forced bending was eviden ;

] - Where pipe clamps are used to su) port vertical lines she i welded to the pipe (if required )y Installation Drawings)ar to prevent lugs were !

i slippag !

j - Sliding or rolling supports were provided with material and/or (

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lubricants suitable for the environment and compatible with sliding

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- Supports are located and installed as specified, '

- The surface of welds meet ap)11 cable code requirements and are free d

from unacceptable grooves, aarupt ridges, valleys, undercuts, cracks, discontinuities, or other indications which can be observed on the welded surfac !

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No violations or deviations were identified.

l 11. Electrical and Instrumentation Componente ar1 Systems - (51053C)(52153C)

Periodic inspections were conducted during the inspection period to j observe safety-related electrical equipment in order to verify tha+, the ,

storage, installation, and preventive maintenance was accomplished in ,

accordance with applicable codes, NRC Regulatory Guides, and licensee  :

commitments, f Ouring the inspection period inspections were performed on various pieces of electrical equipment during storage, installation, and cable terminating phase in order to verify the following as applicable:

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- Location and alignment

- Type and size of anchor bolts I

- Identification I

- Segregation and identification of nonconforming l items  !

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- Location, separation and redundancy requirements

- Equipment space heating

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- Cable identification

- Proper lugs used l

- Condition of wire (not nicked, etc.), tightness of -

connection

- Bending radius not exceeded i

- Cable entry to terminal point '

- Separation The inspector selected a random sample of installed electrical penetration ,

assemblies and conducted a walkdown of their as installed condition and J records review to verify compliance with applicable codes, NRC Regulator i Codes, and licensee commitments,

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i Construction specification X3A803, Revision 8, specifies the technical provisions governing the design, f abrication, testing and delivery of

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electrical penetration assembines and electrical conductor seal assemblies (ESCA) which consist of an electrical conductor seal attached to a

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stainless steel flex conduit with national pipe threads at both ends, The

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design and fabrication of these assemblies is in accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section III, Subsection NE, for electrical penetration assemblies, including all

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addenda and code interpretation accordance with NCA-1140. Class HC

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components manufacturer data reports (form N-2) and code stamps were  ;

{ require ;

The inspector reviewed aertinent records associated wi*,h the electrical ,

penetrations to determ'ni conformance with requirements for recei)t  !

inspection and material certification, installation and testing, anc non ,

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conformance/ deviation record The following types of documentation were

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- ASME N-2 Data Reports  :

- Certified Material Test Reports  !

- Certificate of Conformance  !

- Supplier Quality Verification Documentation List ,

- Supplier Deviation Disposition Request i

- Equipment Material Receipt Inspection Report I L

The following electrical penetration were randomly selected for walkdown l and records review inspection:

Penetration N Equip. Tag N Type Service Class l t

24 21818H3P24 2 Large Power Safety- I Related ('

Train A 25 21818H3P25 3 Controls Safety- ;

(Spare) Related .

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Penetration N Equip. Tag N .Ty Service Cjay I

56 21818H3P56 2 Small Power Safety -

Related Train 8 58 21818H3P58 2 Large Power Safety- l Related Train B 12. ElectricaiandInstrumentationCablesandTerminations-(51063C)(52063C)

(53053C) ,

I Raceway / Cable Installation  !

i The inspector reviewed and examined portions of the following .

procedures pertaining to raceway / cable installation to determine whether they comply with applicable codes, NRC Regulatory Guides and licensee commitment E0-T-02, Raceway Installation-ED-T-07, Cable Installation

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Periodic inspections were conducted to observe construction activities of Safety Related Raceway / Cable Installatio ,

areas were f In reference inspected to thecompliance to verify raceway installation, the follcwinfrements:

with the applicable requ i (

- Identification  !

- Alignment '

- Buslings (Conduit)  !

- Grounding i

- Supports and Anchorages In reference to the cable installation the following areas were I inspected to verify compliance with the applicable requirements:

Protectionfromadjacentconstructionactivities(welding,etc.)

- Colled cable ends properly secured

- Non-terminated cable ends taped i

l -Cabletrays,junctionboxes,etc.lledreasonably

- Conduit capped, if no cable insta free of debris l

l - Cable supported  ;

- Bend radius not exceeded  ;

- Separation , Cable Verminations  !

t The inspector reviewed and examined portions of the following (

procedures pertaining to cable termination to determine whether they :

I comply with appifcable codes, NRC Regulatory Guides and licensee i

! Commitments.

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-ED-T-08, Cable Termination

In reference to cable terminations the following areas were inspected to verify compliance with the applicable requirements.

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- Cable identification J

- Proper lugs used

- Condition of wire (not nicked, etc.)

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- Tightness of connection I - Bending radius not exceeded

- Cable entry to terminal point q

- Separation

No violations or deviations were identified, j 1 Followuo on Inspection Items - (92701)

(0 pen) IFI 50-425/88-12-02 "Followup Licensee's Corrective Actions i Relative To The Identification Of Unit Applicability For Calculations."

The previous inspection revealed several calculations with incorrect unit 1 designators on calculation control log. The inspector examined the 1 licensee commitments stated in the previous inspection. The licensee has initiated a program to review calculations to determine and specify the appropriate unit designation. In addition, project reference manual

section 9 is being revised to reficct the requirements for

! part C, le unit designator annotation on the calculation cover shee applicab I the completion of calculation review and annotation of the i However, calculat ion cover sheet with the unit designator is expected on

! October 14, 1988. There, this item is to remain open pending completion

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of the licensee's corrective action, a

j (0 pen) NRC Bulletin No. 88-05 "Non Conforming Materials Supplied By

Piping Supplies, Incorporated At Folson, New Jersey And West Jersey

) Manufacturing Company At Williamstown, New Jersey.- This bulletin

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addressed the alleged falsification of certified materials test reports by

! two suppliers, PSI and WJM, of piping flanges and fitting. NUMARC, through the technical management of EPRI, develo to assist utilities in addressing this bulletin. ped a multifacted program

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! Ouring the inspection period, the inspector held discussions with appropriate ifcensee personnel to review their test plan which was a

] formalized program instituted to comply with the actions requested by the I subject bulletin. Key areas discussed were: VEGP pro I data base development, daily status reports, schedule,and grams interface flow chart, with

, NUPARC and NRC.

I Upon receipt of the bulletin GPC initiated an aggressive management response team to address this issu GPC sent engineering personnel

. immediately to the suspect vendor facilitics to review and accumulate

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! 15 L available data. In parallel with this cctivity a review of on-site  !

documentation and contractor off-site documentation was initiated to

identify the location of all suspect material in ASME and safety related 't systems. This review identified 1,143 suspect items of which 1,015 were

! carbon steel and 128 were stainless steel. With regards to procedure (

j development CPC coordinated this process witn NUMARC, EPRI Bechtel, and '

s Consultants to ensure that proper techniques were utilized which would i address the technical concern j

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j The inspector conducted a review of the following procedures developed by J the licensee for implementation of their test plan on suspect WJM/ PSI i material, t

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MD-A-08 Equotip Hardness Testing  ;

MD-A-09 duidelines For The Use Of The Texas Nuclear i i Alloy Analyzer l J

MO-A-10 Data Base Control i

! MD-A-11 IE3 88-05 Procedure For Identification - i Testing Of Pipe Fitting - Flanges i MD-T-26 Replication Technique i M0-T-27 Magnetic Testing l GPCstartedhardnesstestinfyof stainless steel items en Ju 11, 198 carbonTosteel date,items 944 ofand the magnetic testing of suspect items

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have been tested with a total of 24, (20 are ASME and 4 are non ASME),

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falling outside of the acceptance range with engineerMg evaluation pendin In addition, GPC has conducted Insitu Replication-Material j Sensitization Evaluation and Alloy Anlysis-Chemical Analysis Test on one

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item from each WJM/ PSI ldentified heat and five Unit 2, ASME III, Class 1 items of austenite stainless steel. All test results were determined to be acceptab h I The inspector has noted a programmatic strength in the area of mars.mment I

involvement and immediacy of respor.se to NRC concerns relative to 631s i area. This has been displayed by GPC's timely program developeent and

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implementation to test suspect materials and by their continued periodic briefing of the NRC's staff on their testing progres This item will remain open pending the licensee's completion of tasting and final review by a Region II specialist inspecto . Followsp of Reportable Items - (92700)

(0 pen) CDR 88 145 "Non Water Tight Penetration Seals." This condition involved Unit 2 penetration seals which were found not to be water tigh During the inspection period, the inspector witnessed the licensee's mockup testing utilizi.ig several different types of sealant material so as to determine an acceptable engineering "solution of the subject

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deficienc The inspector noted engineering involvement to be extensive and aggressive in regard to finding the best possible solution. In addition, management was effective in ensuring that engineering's resolution could be acceptably applied to the actual field condition Once the licensee identified the sealant material to be used, a mockup was constructed and then hydrostatically tested to very no seepage of water through the seal. The inspector witnessed the hydrostatic test of the mockup which utilized Dow Corning Silicone Building Sealant in the joints and the between foam sealtheandembed angle and pipe conduit, andstructure, cable tray.theIn embed angle addition, to foam,50 a 50/ blend of Dow Corning 314d RTV coding and 3145 DTV adhesive was used to seal the cable bundles. The test results were determined to be acceptabl The inspector conducted a review of the following procedures & drawings developed by the licensee which were utilized to conduct the mockup testing. In addition, the installation procedure which will be utilized for field application was reviewe Procedure N Title HT-M00-40 Hydrostatic Test Procedure for The Upper Cable Spreading Room Sleeve Extension Assembly Sealed With Fillet Weld Between Angle Iron And Sleeve Extension HT-M03-42 Hydrostatic Test Procedure for the Upper Cable Spreading Room Sleeve Extension Assembly Sealed With Dow Corning 790 Silicone Building Sealant HT-E01/03-43 Hydrostatic Test Procedure For the Upper Cabie Spreading Room Sleeve Extension Assembly Sealed With Dow Cora ng 790 Silicone Building Sealant Dow Corning 3-6549 RTV Silicone foam HT-E03/40-46 Hydrostatic Test Procedure For the Upper Cable Spreading Room Sleeve Extension Assembly Sealed With Ocw Corn'ng 790 Silicone Building Sealant Dow Corning 3-6548 RTV Silicone foam AX1AG11-138-1 Installation Procedure AX1AG11-140-1 Typical Detail V-E-03/40-28 AX1AG11-141-1 Typical Detail V-M-03-19 This item will remain open pending the completion of the licensee activities with regard to sealing the penetratie.s in the upper cable spreading roo . Reactor Coolant System Hot functional Test - (70308)

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This inspection consisted of an review of the a3plicable procedure listed below to ascertain the overall scope, technical adecuacy, and that the test is consistent with regulatory requirements gu' dance and licensee committnent The procedure was comsared with licensee commitments from the applicable FSAR chapter, Re Evaluation Report (NUREG - 1137).gu'atory Guide 1.68 and the SafetyThis incl prerequisites were identified, initial test conditions and system status were specified, acceptance criteria were specified and clearly identified and management approval indicate Procedure N Test Title 2-300-07 RCS Hot functional Preoperational Test Procedure No violations or devia h uns were identifie . Preoperational Test Program Implementation / Verification - Unit 2 (70302)(71302)

The inspector reviewed the present implementation of the preoperational test program. Test program attributes inspected included review of administrativerequirements,documentcontro:,documer.tationofmajortest events and deviations to procedures, operating practices, instrumentation calibrations, and correction of problems revealed by testin Periodic inspections were conducted of control room operations to assess plant condition and conduct of shift personnel. The inspector observed that control room operations were being conducted in an orderly and professional manne Shif t personnel were knowledgeable of plant conditions, i.e., ongoing testing, systems / equipment in or out of service, and alarm / annunciator status. In addition, the inspector observed shif t turnovers on various occasions to verify the continuity of plant testing, operational problems and other pertinent plant information during the turnovers. Control Room logs were reviewed and variour. entries were discussed with operations personne Periodic facility tours were made to assess equipment and plant conditions, maintenance and preoperational activities in progres Schedules for program completion and progress reports were routinely monitore Discussions were held with responsible personnel, as they were available, to determine their knowledge of the preoperational program. The Inspector reviewed numerous operation deviation reports to determine if requirements were met in the area' of documentation, action to resolve, justification, corrective action and approvals. Specific inspections conducted are listed below:

Test Witnessing (70312)

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The inspector witnessed selected portions of the following preoperational test procedures as they were conducted. The inspection included (

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attendance at briefings held by the test supervisor to observe the  ;

coordination and general knowledge of the procedure with the test '

participants. Overall crew performance was evaluated during testin A preliminary review of the test results was compared to the inspector s own observations. Problems encountered during performance of the test were i

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verified to be adequately documented, evaluated and dispositioned on a  !

selected basi !

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Procedure Test Title Activity Observed N '

2 3EG-01,R 0 Component Coding Miscellaneous Alarms Water Control Circuitry Preoperational Checkout ,

Test j The inspector observed the operation of control room HVAC testing to verify compliance with plant standing orders to ensure compliance with (

i Unit 1 Technical Specifications. Also, the inspector witnessed the  !

initial AFW Terry Turbine Overspeed Test in accordance the 501-80. With j regard to maintenance act.'vities the inspector observed the performance of r the train "A" diesel generator engine inspection af ter the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> loaded  :

run per the Delaval Olesel Owner Group Requirement. This work was '

conducted under Maintenance Work Order No. 2880335 Nuclear Operations QA Surveillance Review The inspector conducted a review of the following licensee conducted surveillance reports performed by the QA department of varidus phases of the preoperational test progra Report N Description 2-PG-88 001 Class IE 480 Volt Switchgear 2-GJ-88-001 Essential Chilled Water System Preep 2-300-88-017 Containment Local Rate Testing 2 50-88 00) Nuclear Instrumentation Preop 2 G-88-11 Ultrasonic Inspection Of Steam Generator No. 1 2-AL-88-009 Steam Driven Auxiliary Feedwater System Preep 2-BG-88-014 Boric Acid Blender Preep The above surveillances were examined to determine if they were meaningful, effective, reflected quality perfornance, and whether corrective actions taken as a result of surveillance findings were proper, timely, and complet No violations or deviations were identifie .

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1 Inspection To Datermine Compliance With ATWS Rule,10 CFR 50.62 -

l (T125020)

This inspection was to determine that ATWS mitigating systems that are not safety related comply with the 10 CFR 50.62 rule and that the effectiveness of the QA controls applied to major activities (design, procurement, installation, and testing), for ATWS equipment that is not safety related complies with Generic Letter 85-06, "QA Guidance for ATWS Equipment That Is Not Safety Related," and to assess the operational readiness of ATWS equipment that is not safety relate Georgia Power submitted on July 30, 1987, their proposal pursuant to the role. This letter states that the system being installed was submitted to the NRC in WCAP-10858P-A, "ASMAC Generic Design Package" and was approved in an NRC Safety Evaluation Report dated July 17, 198 The letter then providea the site specific informatio Georgia Power has selected and will implement an ATWS Hitigating Systems Actuation Circuitry (AMSAC) logic which detects a loss of heatsink by monitoring the feedwater flow to each of the steam generators. This actuation logic incorporates an automatic arming and block circuitry based upon turbine load by monitoring the first-stage turbine impulse chamber pressur These signal, referred to as the C-20 signal, block AMSAC utuation at low power levels to prevent spurious trip during plant startup The inspector reviewed the material purchase requ'sition PARVAR-10 dated ' 7tember 23, 198 This requisition specifies quality requirements of : t order are subject to 10 CFR 50 Appendix B Quality Controls, ANSI Nb.< 2 Level B storage requirements, and the AP. SAC cabinet and subassemblies qualifies to IEEE 297 The Unit 2 installation has been completed and preoperational testing remains. The inspection included examination of the installed equipment and control panel alarms. Inspection of preoperational testing wi I be performed in a future inspectio The inspector noted that NRR has not issued the safety evaluation report for Vogtle. Further inspection requirements may result when issued, No violations or deviations were identifie . Manigement Meetings - (307C?)

This activity involves inspector participation and preparation in support of the following meeting which presented site readines The resident inspector attended a meeting held with the NRC staff and the licensee at the Vogtle Electric Generating Plant. In attendance from the regional and headquarters office were Mr. V. L. Brownlee, Chief Reactor Projects Branch 3 Division of Reactor Projects and Mr. David B. Matthews,

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Cirector of Project Director II- The licensee discussed the construc- l tion and areoperational test status of Unit II in regard to preparedness j for upcom ng ifcensin ;

1 Exit Interviews - (30703C) i The inspection scope and findings were sumarized on August 3,1988 with  !

those persons indicated in paragraph 1 above. The inspector described the  ;

areas inspected and discussed in detail the inspection result No !

dissenting comments were received from the license The licensee did not !

identify as proprietary any of the materials provided to or reviewed by tha inspector during this inspection. Region based NRC exit interviews  ;

were attended during the inspection period by a resident inspector. This  !

inspection closed 3 Violations. One item in the area of seismic l qualification was identified during tnis inspection as noted below:

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(0 pen) Inspector Followup Item, 50-425/88-38-01 "Review Licensee's '

Finding Reiative To The seismic Qualification Of Valves 2HV-8152, 8888, (

and 8964." - Paragraph S . Acronyms And Initialism

AFW - Auxiliary Feedwater System i ASME - American Society of Hechanical Engineers (

CBI - Chicago Bridge and Iron l CVCS - Chemical & Volume Control System l EPRI - Electric Power Research Institute '

FCR Field Change Request l FSAR - Final Safety Analysis Report  ;

GPC - Georgia Power Company i

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HFT - Hot Functional Test H, - H f NFPA ydrogen National Fire Protection Association NSSL - Nuclear Sampling System - Liquid  !

NUMARC - Nuclear Utility Management and Resources Comittee '

PSI - Piping Supplies, Incorporated QA - Quality Assurance QC - Quality Control liCOT - Reactor Coolant Drain Tank ,

RCS - Reactor Coolant System r PWST - Refueling Water Storage Tank l SFPCPS - Spent Fuel Poo Cooling and Purification System i 501 - Startup Operating Instruction L VEGP Vogtle Electric Generating Plant VSAMU - Vogtle Structural Analysis Hobile Unit W)H - West Jersey Manufacturing Company WPSL - Waste Processing System - Liquid l l

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