IR 05000425/1988056

Insp Rept 50-425/88-56 on 880913-1031.No Violations or Deviations Noted.Major Areas Inspected:Fire Protection, Piping Sys & supports,safety-related Components,Auxiliary Sys,Electrical Equipment,Raceways & Instrumentation

ML20206G712
Person / Time
Site:	Vogtle
Issue date:	11/15/1988
From:	Burger C, Schepens R, Sinkule M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20206G703	List: IR 05000425/1988056 ML20206G701
References
50-425-88-56, NUDOCS 8811220375
Download: ML20206G712 (14)

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[ 4 UNITED STATES '" j NUCLEAR REGULATORY COMMISSION

.g 'f REGION ll g- j a 101 MARIETTA ST ATLANTA, GEORGIA 30323

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Report No.: 50-425/88-56 Licensee: Georgia Power Company -

P. O. Box 1295 Birmingham, AL 35201 Docket No.: 50-424 License No.: CPPR-109 Facility Name: Vogtle 2 '

Inspection Conducted: September 13 - October 31, 1988  !

Inspectors; a b.< kICm

. J. Schepens, Senior Resident Inspector Isbs /t s Date Signed 6 (*. .. vh- "/,s h s C. W. Burger, 'tesident Inspector Date Signed ,

Approved by: bht I l @/

M. V. Sinkule, Section Chief Date Signed Division of Reactor Projects SUMMARf Scope: This routine, unannounced inspection entailed resident inspection in the following areas: fire protection, piping systems and supports, i

> safety related components, auxiliary systems, electrical equipment, ;

raceways n.nd instrumentation, preoperational testing, quality '

programs and administrative controls affecting quality, and follow-up !

of reportable item l Results: No violations or deviations were identifie !

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8811220375 891116 ,

PDR ADOCK 05000425 PNV j

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REPORT DETAILS ,

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. Persons Contacted I Licensee Employees .

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P. D. Rice, Vice President, Vogtle Project Director  !

• R. H. Pinson, Vice President, Project Construction  !

G. Bockhold, General Manager i T. V. Greene, Plant Support Manager f

• C. W. Hayes, Vogtle Quality Assurance Manager  ;

• E. D. Groover, Quality Assurance Site Manager - Construction i D. M. Fiquett, Project Coratruction Manager A. B. Gallant, Project Compliance Coordinator i I- C. L. Coursey, Maintenance Superintendent (Startup) i 4 "H. M. Handfinger, Assistant Plant Support Manager A. W. Harrelson, Construction Electrical Manager l C. W. Rau, Construction Mechanica! Manager  !

l L. N. Brooks, Construction Civil Manager '

L. B. Glenn, QC Manager  ;

R. W. McManus, Readiness Peview M& nager  ;

J. E. Sanders, Assistant Project Manager  ;

! W. C. Ramsey, Project Engineering Manager  ;

L. D. Harless, Manager, Qualicy Concerns j Other iteensee employees contacted included craftsmen, technicians, ,

j supervision, engineen, inspectors, and of fice personne [

, t j Other Organizations j

) C. Marcum, Westinghouse Project Muager  !

j T. E. Richardson, Project Engineering Manager - Bechtel {

B. Edwards, Site Manager - Pullman Power Products [

l J. Miller Quality Assurance Manager g F

• 0 D. Smith, Cnnstruction Engineer - Oglethorpe Power Company !

! *B. A. Dragon, Quality Assurance Supervisor - Bechtel  !

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NRC Inspectors t l  :

I * D. Hunt, Reactor Inspector [

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' F. Rogge, Senior Resident Inspector - Operations I

' F. Aiello, Resident - Operations

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• Attended Exit Interview

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l Acronyms and initialisms used throughout this report are itsted in the ,

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4 General Construction Inspection - (92700)

Periodic random surveillance inspections were made throughout this reporting period in the form of general type inspections in differtnt areas of the facilit The areas were selected on the basis of the scheduled activities and were varied to provide wide coverag Observations were made of activities in progress to note defective items or items of noncomplian a with the required codes and regulatory .

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

presence of quality control inspectors, supervisors, and quality cor. trol  !

evidence in the form of available process sheets, drawings, material

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identification, material protection, perfo.mance of tests, and housekeepin Interviews were conducted with craft personnel, supervisors, coordinators, quality control inspectors, and others as they

were available in the work area The inspector reviewed numerous i construction deviation reports to determine if requirements were met in the areas of documentation, action to resolve, justification, and approval

, signatures in accordance with GPC Field Procedure No. GDaT-0 '

During routine NRC inspections of work in containment, the inspector '

identified a concern to the licensee with regard to the cleanliness of '

cable trays. The inspector met with the electrical discipline mansger and identified several cable trays in containment that contained debris such as tools, tape, paper, nails, scrap sheet metal, et Management acknowledged the concern and initiated a procedure awareness notice which i

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gave explicit language concerning cleanliness expectations and '

verification requirements. This notice for cable tray cleanliness was  !

reviewed with all electrical craf t personnel. In addition, the licensee conducted a walkdown of all cable trays to identify the magnitude of the

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l problem. The licensee found one area in containment where debris had been '

covered up in the trays by rable tray covers and several areas in the containment and auxiliary building where debris was present. in open cable ,

tray The licensee has addressed and corrected the specific items that l were identified and have retrained craf t and engineers toward cable tray i

cleanliness inspection requirement In conclusion, at the time of

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identification by the inspector, none of the covered trays had been r

released for QC inspection, nor had any of the areas been turned over to l i nuclear operations, at which point they are inspected for cleanlines [

! Therefore, tranagement was not aware that tr e problem existed. However, j upon identification prompt corrective action was taken by the managemen l

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i No violations or deviations were identifie :

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1 Fire Prevention / Protection ard Housekeeping Measures - (42051C)

l The inspector observed fire prevention / protection measures throughout the (

i inspection period. Welders were usinQ welding permits with fire watches and extinguishers. Fire fighting equipment was in its designated areas ,

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j The inspector reviewed and examined portions of procedures pertaining to ,

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the fire prevention / protection measures and housekeeping measures to determine whether they comply with applicable codes, standards, NRC Regulatory Guides and itcensee commitment The inspector observed fire prevention / protection measures in work areas containing safety related equipment during the inspection period to verify the following: i

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

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Flammable itquids wne stored in appropriate containers and in 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 !

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Fire protection / suppression equipment was provided and controlled in accordance with applicable requirements, j

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No violations or deviations were identifie ,

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

(49063C)

Periodic inspections were conducted to observe construction activities of

the Reactor Coolant Boundary and other safety-related piping installations ,

inside and outside Containment. Verifications included but were not limited to the following: ,

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Material and components were being properly handled and stored in i order to prevent damage.

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Fit-ups and alignments were within tolerances per specifications and i j drawings, j

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Specified clearances from pipe to pipe and adjacent ecmponents ws e i i met, i 1 -

Piping was installed end inspectte in accordance with applicable !

drawings, specifications, and protecaire !

- Those people engaged in the activity are qualified to perform the

, aoplicable functio "

Drawing and specification changes (revisions) are being handled and

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- i used correctl No violations or deviations were identifie { Reactor Coolant Pressure Boundary and Safety Related Piping Welding -

(55073C) (55083C) ,

periodic inspections were conducted during daily plant surveillances on safety-related pipe welding at various stages of weld completion, The I purpose of the inspection was to determine whether the requirements cf j

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applicable specifications, codes, standards, work performance procedures and QC procedures are being met as follows:

- Work was conducted in accordance with a proccss sheet which identifies the weld and its location by system, references procedures or instructions, and provides for production and QC sigaoff Welding procedures, detailed drawings and instructions, were readily available in the immediate work area and technically adequate for the welds being mad Welding procedure specification (WPS) were in accordance with the applicable Code requirements and that a Procedure Qualification Record (PQR) is referenced and exists for the type of weld being mad Base metals, velding filler materials, fluxes, gases, and insert materials were of the specified type and grade, have been properly inspected, tested and were traceable to test reports or certification Purge and/or shielding gas flow and composition were as specified in the welding procedure specification and that protection was provided to shield the welding operation froni adverse environmental condition Weld joint geometry including pipe wall thickness was specified and that surfaces to be welded have been prepared, cleaned and inspected in accordance with applicable procedures or instruction A sufficient number of adequately qualified QA and QC inspection personnel were present at the work site, commensurite with 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 weluing specifications, unused filler material was separated from other types of material and was stored properly and that weld rod stubs were properly removed from the work locatio That there were no evident signs of cracks, excessive 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 in containment, and the integrated head package which was installed and tensioned for hot functional testin The licensee monitored and maintained reactor temperature within the applicable requirements during heat up and cooldown operation No violations or deviations were identifie . _ _ _ _ _ _ _ _ _ _ _ _ _ _

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7, Safety Related Components - (50073C)

The inspection cons'sted of plant tours to observe storage, hardling, and protection; installation; and preventive auintenance after installation of  ;

safety-related components to determine that work is being performed in ,

accordance with applicable codes, NRC Regulatory Guides, and licensee

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commitments, During the inspection the below listed areas were inspected at various times during the inspection period to verify the following as applicable: [

u Storage, environment, and protection of components were in accordance with manufacturer's instructions and/or establishei procedure Implementation of special storage and maintenance ivguirements such  !

as: rc,tation of motors, pumps, lubrication, insulaticn tesv.ing l (electrical), cleanliness,et !

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Performance of licensee / contractor surveillance activities and l documentation thereof was being accomplisheri, l proper location,

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Installation requirements were met such as:

placement, orientation, alignment, mounting (torquing of bolts and l expansion anchors), flow direction, tolerances, and expansion l clearanc l

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Appropriate stamps, tags, markings, etc, were in use to prevent i oversight of required inspections, completion of tests, acceptance, {

and the prevention of tradvertent operatio i

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Safety-Related piping, valves, pumps, hest exchangers, and instrumentation ,

were inspected in the following areas on a random sarn11ng basis 1 throughout the inspection period:  !

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- Residual Heat Removal Pump Rooms

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Diesel Generator Building ,

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Auxiliary Feedwater Pumphouse  ;

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Containment $ pray Pump Rooms t

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Pressurizer Rooms I

- Main Coolant Pump Areas l

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Steam Generator Areas i I

- Safety Injection Pump Pooms

- RHR and CS Containment Penetration Encapsulation Vessel Rocms

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Component Cooling Water (CCW) Heat Ex-hangers, Surge Tanks & Pump  !

I Rooms

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Cable Spreading Rooms l

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- Chemical and Volune Control System (CVCS) Letdown Heat Exchanger Pump  ;

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- Battery & Charger Rooms  !

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Spent Fuel Pool Heat Exchanger Rooms I

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Pressurizer Relief Tank Area [

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CVCS Centrifugal Charging Pumps & Positive Displacement Pump Rooms l

- NSCW Tower Pump Rooms and Pipe Tunnels t

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No violations or deviations were identdfie . Safety Related Pipe Support and Restraint Systems - (50090C)

l Periodic random inspections were conducted during the inspection period to ,

observe construction activities during installation of safety-related pipe supports to determine that the following work was performed in accordance wi' h applicable codes, NRC Regulatory Guides, and licenset commitment Spring hangers were provided with indicators to show the approximate t

"hot" or "cold" posit 4n, as appropriat No deformation or forced bending was eviden "

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Where pipe clamps are used to support vertical lines, shear lugs were welded to the pipe (if required by Installation Drawings) to prevent l slippag '

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Sliding or rolling supports were provided with material and/or lubricants suitable for the environment and compatible with sliding contact surface l

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Supports are located and installed as specifie The surface of welds meet applicable code requirements and are free I from unacceptable grooves, abrupt ridges, valleys, undercuts, cracks, discontinuities, or other indications which can be observed on the welded surfac No violations or deviations were identifie . Electrical and Instrumentation Components and Systems - (51053C)(52153C) l Periodic inspections were conducted during the inspection period to observe safety-related electrical equipment in order to verify that the  ;

storage, installation, and preventive maintenance was accomplished in  ;

accordance with applicable codes, NRC Regulatory Guides, and licensee l commitments, j

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

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Location and al;gnment i

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Identification 1

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Segregation and identificatior of nonconforming iteas  !

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Location, separation and redundancy requitements t

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Equipmens space heati i

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Cable identification ,

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Proper lugs used i

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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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No violations or deviations were identifie . Electrical and Instrumentation Cables and Terminations - (51063C)(52063C)

(53053C) Raceway /Cablo Installation

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The inspector reviewed and examined portions of she following procedures pertaining to raceway / sable installation to determine whether they comply with applicable codes, NRC Regulatory Guides and licensee commitment ; - EO-T-02, Raceway Installation

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CD-T-07, Cable Installation

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Periodic inspections were conducted to observe construction activities of Safety Related Raceway / Cable Installatio In reference to the raceway installation, the following areas were j inspected to verify compliance with the applicable requirements:

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In reference to the cabis installation the following areas were inspected to verify compliance with the applicable requirements:

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Protection from adjacent construction activities (welding, etc.)

- Coiled cable ends properly secured

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Non-terminated cable ends taped

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

- Conduit capped, if no cable installed

- Cable supported

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Bend radius not exceeded

- Separation Cable Terminations The inspector reviewed and examined portions cf the following procedures pertaining to cable termination to determine whether they comply with applicable codes, NRC Regulatory Gt. ides #ad licensee commitment ED-T-08, Cable Termination In reference to cable terminations the following areas were inspected to verify compliance with the applicable requirement _ ,

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Cable identification

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No violations or deviations were identifie . Followup of Reportable Items - (92700)

(Closed) CDR 50-425/82-33 "Transamerica Delaval Diesel Generator - ,

Goverrior Drive Coupling " As a followup to inspection report '

No. 50-425/88-46, the inspector reviewed completed WO package i Nos. 288')9139 and 28810038 which documented the licensee's actions relative to the inspection and verification that neoprene coupling inserts were installed in diesel generators 2A & 28 governor drive flexible couplings. As a result of the inspections, the licensee verified that the 2A DG had a "N" stamped on the neoprene coupling inser However, relative to the 2B DG, the licensee was unable to find a "N" st:mped on the coupling insert. The licensee initiated the appropriate documentation ie., a deficiency report which identified the approved disposition which was to replace it with a neoprene coupling insert. The licensee provided i the inspector with the appropriate documentation which documented that the replacement coupling insert had been verified to have an "N" stamped on 1

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ft. Based on the acticn taken oy the licensee,this itiem is considered to be close ;

12. Hot Functional Test (70314)  ;

The inspectors observed conduct of the Hot Functional Test (HFT) portion of the preoperational test program. This revitw included attendance at coordination meeting, discussions with the test program director and test engineers, general observation of testing and operations in the control '

room as was as observation of the specific tests described below. A broad !

review of all incident repor*.s and major test procedure changes was conducted to verify that probiws were being adequately docume ited and i procedure changes administratively controlled, j The inspector reviewed the HFT controlling precedure to verify that all [

prerequisites and initial conditions were met during RCS heatup. The 6 inspectors cone.luded that the licensee was corducting a well organized program, personnel had a good understanding of responsibilities and i conduct of specific test, control of organizational interfaces was good, !

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procedures were properly approved and current drawings and manual were '

being utilized. Management involvement in the test program was eviden No violations or deviations were identifie . _ .

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1 Preoperctional Test Program Implementation / Verification - (70302)(71302)

The inspector reviewed the present implementation of the preoperational :

test progra 'iest program attributes inspected included review of administrative requirements, document control, documentation of major 17st events and deviations to procedures, cperating practices, instrumentanan calibrations, and correction ef problems revealed by testir?.

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 manner. Shift personiel were knowledgeable of pl a conditions, i.e., ongoing testing, systems / equipment in or out of service, and alarm / annunciator status. In addition, the insoector observed shif t turnovers on various occasions to verify the continuity of plant testing, operational problems and other pertinent plant informction during the turnover Control Room lo;? v<re reviewed and various 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 monitored. Discussions were held with responsible personnel, as they were available, to determine their knowledge of the preoperational progra The Inspector reviewed numerous operation deviation reports to determine if requirements were met in the areas of documentation, action to resolve, justification, corrective action and approval Specific inspections conducted are listed below: Preoperational Tests (1) Test Procedure Review (70300)

The inspector reviewed the following listed preoperational test procedure Each test was reviewed for administrative format and technical adequac The procedures we.e compared with licensee commitments from the applicable FSAR Chapters, Regulatory Guide 1.68 and the Safety Evaluation Report (NUREG-1137). This included verifying that pertirent prerequisites were identified, initial test conditions and system status were specified, acceptance criteria were specified and management approval indicated:

Procedure N NRC Insp. N Test Title 2-300-10 70352 Shutdown Panel 2-300-07 70308 RCS Hot Functional i

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(2) TestWitnessing(70312)

The inspector witnested selected portions of the following ;

preoperational test procedurer as they were conducted. The inspection included attendance at briefings held by the test supervisor to observe the coordination and general knowledge ef the procedure with the test participant Overall crew performance was evaluated during testing. A preliminary review of the test results was compared to the inspector's own observation Problems encountered during performance of the test were verified to be adequately documented, evaluated and dispositioned on a selected basi Procedure NRC Ins Preoperational Activity N N Test ittle Observed 2-300-07 70314 RCS Hot RCS Heat Up Functiona', And Coordination Of Testing At L ^*F, 245'F, p.F, 450'F,

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Platea AE-01 70448 Main Feedwater Main Feedwater Pump B Run, 2-3SF-01 70432 Aod Control  ;

i 2-3AL-03 70438 AFW Testing TDAFV Pump 48 During HFT Hour Run Per ,

Step l TDAFV Pump 1 Hour Operation !

On Restart After Cooldewn Per S'.ep 6.8.1 '

2-3BB-05 70447 Pressurizer Pressurizer Pressure And Pressure Level Control Control, ,

Response, And l Stability Demonstration ;

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2-3AB-01 70437 Main Steam Main Steam Isolation Valve Stw #g During H~ rer Step 6. G-04 70433 Boric Acid Boric Acid Blender Blending Operation Per

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Step 6.15, 2-300-10 70452 Shutdown Panel Preparation F*o r Cooldown Per Step '

Plant Cooldown To 450*F Per Ster 6.2.

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Transfer From Motor Driven AFW Pump Per Step KJ-06 70441 DG 28 35 DG Starts, Consecutive Starts Operation, &

Shutdown (3) Test Results Evaluation (70400)

1he inspector reviewed the following listed preoperational test results. This review was performed to ascertain if an adequate evaluation of the test results has been performed; test data was within the established acceptance criteria, or that deviations are properly dispositioned; appropriate retesting was performed where necessary; administrative practices were adhered to; and that appropriate review, evaluation and acceptance of the test results have been performe Procedure NRC Ins N N Preoperational Test Procedure Title 2-3PK-01 70540 C; ass IE 125 V DC Syst am/Switchgear

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1 b. Construction 4ceptance Testing The inspector conducted a review of the following completed construction acceptance tests:

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NRC Ins Cat. N N Description 87-548 70433 2LV-0459 RCS Letdown To Regen HTEX~

87-548 70433 2LV-0460 RCS Letdown To Regen HTEX 87-648 70434 2HV-8843 SI Boron Inj. Test Line Bypass

87-817 70434 2HV-8871 SI Test Line Containment Isolation a

87-817 70434 2HV-8881 SI Hot Legs 1 & 4 Inf. Ch Viv. Test Is HV-8882 SI Boron Inj. Chk. Viv. Test 87-817 70434 2HV-8809A SI Recirc Test Isolation l

c. Preoperational Testing QA Surveillance Report Review The inspector conducted a review of the following licensee conducted

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surveillance reports performed by the QA department during various

phases of the preoperational test program.

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i Report N Description l 2-AB-88-017 HFT Response Test Of SG Blowdown Isolation Valves

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2-GT-88-001 HFT Containment Air Purification And Clean Up

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2-BJ-88-011 SI Check Valve Preop Testinn During HFT 2 A8-88-016 Preop Testing Of Atmospheric Relief PV-3020 2 2 38-001 Reactor Protection Preop Testing d. Followup of Event Occurring During Testing The inspectors reviewed the following events which occurred as a result of testing:

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During HFT at the 557*F plateau, the licensee identified numerous interferences around the reactor coolant pumps as a result of walking dcwn the ACCW system for the thermal growth &

vibrction program. The inspector fellowed the licensee actions relative to the proper identification, documentation, :qd justification for continued operation for the interferences to be fixed after cooldown from HF The inspector also observed the interferences and attended licensee meetings where engineering, startup, & construction personnel prioritized the working of the interferences. Unit 2 personnel notified Unit 1 of the identified problem and Unit 1 management stated that they intended to look at unit 1 RCPs for the same pottntial interferences, No violations or deviations were identifie . Exit Interviews - (30703C)

The inspection scope and fi

>ts were summarized on Octobur 31, 1988,

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with those persons indicatec sa paragraph 1 abov The inspector described the areas inspected and discussed in detail the inspection results. 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 inspectio Region based NRC exit interviews were attended during thw inspection period by a resident inspector. This inspection closed one Construction Deficiency Repor . Acronyms And initialism AFW Auxiliary Feedwater System DG Diesel Generator HFT Hot Functional Test NRC Nuclear Regulatory Commi ssion PAC Prccedure Awareness Notice QA Quality Assurance QC Quality Control RCP Reactor Coolant Pump SG Steam Generator SIS Safety Injection System TDAFV Turbint Driven Auxiliary Feedwater VEGP Vogtle Electric Generating Plant

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