ML20137A936

Insp Repts 50-498/85-13 & 50-499/85-13 on 850805-0927. Violation Noted:Components Used for Fabrication of 6x6 Fuel Rack Obtained from Other Purchase Orders & Not Properly Identified on Travelers

ML20137A936
Person / Time
Site:	South Texas
Issue date:	10/31/1985
From:	Constable G, Garrison D, Clay Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20137A817	List: IR 05000805/2009027 ML20137A812 ML20137A936
References
50-498-85-13, 50-499-85-13, IEB-83-06, IEB-83-6, IEIN-83-07, IEIN-83-7, IEN-83-7, NUDOCS 8511260142
Download: ML20137A936 (17)

See also: IR 05000498/1985013

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APPENDIX B

U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-498/85-13 CP: CPPR-128 and.129

50-499/85-13

Docket: 50-498 and 50-499

Licensee: Houston Lighting & Power Company (HL&P)

P. O. Box 1700

Houston, Texas 77001

Facility Name: South Texas Project, Units 1 and 2

Inspection At: . South Texas Project, Matagorda County, Texas

.-Inspection Conducted: August 5 - September 27, 1985

Inspectors: " -- W --D I- M

C. E. Johnson, Senior Resident Inspector .Date

Project Section C, Reactor Projects Branch

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W

D. L. Garrison, Resident inspector

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Date

Project Section C, Reactor Projects Branch

Approved: /d-3/-85 "

G.'L. Constable, Chief, Project Section C Date

Reactor Projects Branch <

Inspection Summary .

Inspection Conducted August 5 - September 27, 1985 (Rer:,rt 50-498/85-13;

50-499/85-13

Areas Inspected: Routine, unannounced inspection of licensee action on '

previous inspection findings, IE Information Notices and IE Bulletins,

protective coatings, spent fuel storage racks, reactor vessel internals,

post-tensioning system, and pipe supports. The inspection involved

384 inspection-hours onsite by two NRC inspectors.

Results: Within the scope of this inspection, one violation was identified and ,

is discussed in paragraph 10.

8511260142 851112

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DETAILS

1. Persons Contacted

Principal Licensee Employees

E. Hill - Project Compliance Engineer

'*F. White, Lead Project Compliance Engineer

K. O'Gara, Project Compliance Engineer

• R. R.'Hernandez, Supervisor, Project Compliance

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F. Alkov, Material Control Supervisor

• L.'Dolan, Project Compliance Engineer

M. McDaniels, QA

• R. Daly, Startup Manager

• A. G. Peterson, Startup

• T. J. Jordan, Project QA Manager

• D. R. Keating, Operations QA General Supervisor

• J. T. Westermeier, Project Manager

• R. C. Arthurs, Project QA General Supervisor

• M. S. Whittaker, Metrology Lab Supervisor

• W. H. Kinsey, Plant Manager

• S. M. Dew, Deputy Project Manager

Other Personnel

Bechtel Power Corporation (Bechtel)

B. Bittner, Design Engineer

• N. A. Joonejo, Engineering Group Supervisor

F. W. Joyce, Quality Assurance Engineer

Al Dansman, Civil Engineer

G. A. Koch, Contract Administrator

L. Vaupel, Site Coatings Engineer

B. Fultz, Coatings Engineer

M. Peters, Coatings Engineer

8. Nilius, QA

• L. W. Hurst, Project QA Manager

• R. D. Bryan, Deputy Project Manager, Construction

• R. Schulman, Site Civil Engineer

• J. B. Gatewood, Project QA Engineer

• R. H. Medina, Lead QA Engineer

• J. T. Minor, Deputy Site. Engineering Manager

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Ebasco Services, Inc. (Ebasco)

D. Calsyn, Mechanical Supervisor

C. Murray, Lead QC, Pipe Supports

C. Sist, Supervisor Pipe Supports

J. Tucker, QC, Pipe Supports

• A. M. Cutrona, QA Manager

• R. M. Zaist, Construction Manager

Prescon Corporation (Prescon)

W. Schneider, Quality Control Supervisor

G. Jewel, Project Manager

H. Williams, Corporate Quality Manager

D. Berthier, Director of Engineering

Westinghouse

C. Hahn, Welding Engineer

• Denotes those individuals attending the exit interview conducted on

October 3, 1985.

2. Site Tour

The NRC inspectors made several site tours in order to assess the general

cleanliness and housekeeping activities, condition of equipment, and plant

status. The following parts of the plants were inspected: containment

buildings, mechanical / electrical auxiliary buildings, fire protection

diesel pumphouse, and fuel building Unit II.

No violations or deviations were identified.

3. Licensee Action on Previous Inspection Findings

(Closed) Unresolved Item 8412-01:

This item concerns the purchasing of nonconforming material from Tube-Line.

An evaluation was performed by the NRC inspector and it was detennined

that none of the items of concern were supplied to the project. This item

was determined not to be a violation of NRC requirements. See para.10 below.

'(Closed) Open Item 8506-02:

This item concerns the material test report traceability of the

Units 1 and 2 6 X 6 spent fuel storage racks. Thisitem(8506-02)

is closed. It has now been escalated to a violation (8513-01).

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(Closed) Unresolved Item 8209-09:

This item concerned lack of supporting documentation for (120) 1 1/2"

and (32) 2" ASTM A540 Grade B23 class 3 nuts. The required documentation

has been received by HL&P and is acceptable to the NRC inspector. A

supplemental requirement of the purchase order for MT or PT testing has

been deleted and documented in a nonconformance report. The item is

considered closed and was determined not to be a violation.

(Closed) Violation 8324-02:

This item concerned the testing of soils, in which a scoop was used in

lieu of a funnel device. Prefiled testimony given to the Atomic Safety

and Licensing Board indicates that all affected relative soil density

tests were recalculated after incorporating the reduction in relative

density and were found to be within the specified criteria. Testing is now

in full accordance with the procedures.

4. Licensee Action on IE Bulletins

(Closed) IE Bulletin 83-06:

This item pertained to Tube-Line (see also URI 8412-01 above). HL&P

action on this IEB was reviewed by the NRC inspector and found to be

acceptable.

5. Licensee Action on IE Infonnation Notices

(Closed) IE Information Notice 83-07:

This item pertained to Tube-line (see URI 8412-01 andIEB83-06above).

HL&P action on this Information Notice was reviewed by the NRC inspector

and found to be acceptable.

6. Protective Coatings

. The NRC inspector reviewed the protective coatings system applied to

Units 1 and 2 containment steel liner plate. The purpose of this

review was to determine if the system was DBA (Design Basis Accident)

qualified and if the procedures and specifications were in accordance

with: NRC regulations, FSAR, ANSI coc'es and manufacturer's application

instructions.

Unit l's initial coating system was removed down to the steel substrate

from all surfaces except those inaccessible areas such as behind installed i

HVAC ducts. The containment liner was then coated with a two-coat epoxy '

system (Amercoat 90/Amercoat 90). The initial coating system for lfnit I

was Dimetcote 6 primer with Amercoat 90 topcoat. This system is still

applicable for Unit 2. The NRC inspector was informed by the Bechtel

coatings engineer that the Unit 1 initial coating system was removed

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because Brown & Root (B&R) had problems with the application of Amercoat

90 over the Dimetcote 6 primer, and that PDM, the steel liner fabricator,

had lost the documentation for the primer that they had applied. B&R then

elected to remove the Dimetcote 6/Amercoat 90 system and replace it with

the two coat epoxy system.

The NRC inspector reviewed the DBA test results on the

Dimetcote 6/Amercoat 90 and the Amercoat 90/Amercoat 90 protective coatings

system. The test rest.lts were acceptable for the required mil thickness

utilized at STP.

The NRC inspector compared DBA test results for the two systems

described in the specification. The specification requirement was in

accordance with the required mil thickness as used in the DBA test.

Review of the QC procedures and specification appear to be adequate.

Documents Reviewed

DBA Documents (Amercoat 90/Amercoat 90)

. LSR 2206 (12/17/75)

. LSR 2408 A-1 (1/20/77)

. ORNL Log Book No. A7562; 1-12-6 (3/9/76)

. ORNL Log Book No. A7562; 2-28-7 (3/28/77)

. ORNL Log Book No. A9675; A9-22-2 (9/30/82)

DBA Documents (Dimetcote 6/Amercoat 90)

. Test Report No. 2585 (7/2/79)

. ORNL Log Book No. A7562; A7-9-9 (7/24/79)

. ORNL Log Book No. A7562; A7-16-9 (7/24/79)

Test Report LSR 2206, 2207 (5/27/76)

Procedures / Specification

. QCP-10.8, " Protective Coatings Inspection," Revision 5, dated 4/26/85

. TPNS SA819A1001, " Painting and Coating," Revision 2, dated 1/25/83

. Specification #3C080AS1007, " Technical Specification for Field

Coating of Surfaces Inside the Reactor Containment Building,"

Revision 11, dated 5/9/85.

No violations or deviations were identified.

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7. Reactor' Vessel Internals -

The NRC inspectors reviewed procedures for the rigging and setting of

.the Unit 2 reactor vessel lower and upper internals. The procedures

were adequate.

.The NRC inspectors observed the craftsmen attaching the rigging to

the upper internals storage frame in the storage yard. The NRC

inspector did not observe the upper or lower internals being lifted

on to the trailer.

The NRC inspector observed that protection requirements for the Units 1

and 2, unit reactor pressure vessel and internals were met.

Units I and 2 reactor vessel and internals were properly covered to

prevent entry of foreign objects and debris. Platforms and

scaffolding around the vessel were nonflammable or treated to prevent

spread of accidental fire.

Documents Reviewed

. CSP-63, " Rigging for Setting the Reactor Head," Revision 0, dated 9/14/84

(Unit II)

. CSP-64, " Rigging for Setting Unit II Reactor Internals," Revision 0,

dated 2/5/85

. ICP-Nos. 3 and 4, '" Rigging for Setting Unit II Reactor Internals,"

Revision 0, dated 2/5/85

No violations or deviations were identified.

8. Post-Tensioning System Unit 1

The containment is a post-tensioned, reinforced concrete structure in

the shape of a vertical cylinder with a hemispherical dome and flat base.

The cylindrical portion and half of the dome are prestressed with tendons

in the horizontal direction utilizing three buttresses equally spaced at

120 degrees. The dome is prestressed with tendons in the vertical direc-

tion; these tendons extend over the dome and are anchored in the tendon

gallery beneath the base mat. The installation is basically as follows:

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- ~s hop fabricate and ship the tendons to the site, place the tendons into

the preinstalled sheathing, prepare the tendon ends for stressing, stress,

install a corrosion inhibitor and cover.

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The purpose of the inspection was to assure that the design and regulatory

requirements are carried out in fabrication, installation and stressing

operations,

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a. Procedures Review

(1) FSAR/ Specification

The FSAR in Section 3.8 outlines the requirements for the

materials to be used in construction, installation, stressing

and greasing. The NRC inspector has verified that these items

are addressed in the engineers specification (Bechtel) 2C239CS003

and are further defined in the fabricator / constructors (Prescon)

Quality Assurance and Quality Control procedures. The FSAR also

detailed the program for in service surveillance.

(2) Specification / Quality Procedures

The specification noted above was compared to the Quality

Control-Quality Assurance procedures for inclusion of require-

ments. The engineering design requirements as previously noted,

were included in the Prescon procedures. The specification was

noted to address deflection of tendons around the hatches or

penetrations.

The fabricator / constructors' programs were observed to include

the requirements in detailed written procedures addressing each

area'of fabrication, Quality Assurance and Quality Control. The

areas 'specifically reviewed were fabrication of washers, shop

buttonheading, corrosion protection and shipping, installation

of the tendon into sheathing, protection, field buttonheading,

stressing and sequencing, greasing, capping and QC records.

(3) Audit Programs

The licensee was noted to have an audit plan that included

a major audit of Prescon. Audit S12-501 of Bechtel and Prescon

if is scheduled for September 30, 1985, by the licensee.on-site QA

group.

The construction manager (Bechtel) is required by contract

to perform frequent surveillances of the fabricator's shop.

Quality Surveillance Reports QSR 11 and 19 were reviewed by the

NRC inspector and were found to be detailed, including hold

points and type of inspection or examination, with references to

the inspection requirement document.

A programmatic audit of Prescon, on site, by Bechtel QA was

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reviewed and it was noted that the auditor had issued five

site deficiency reports. At this writing, Prescon had responded

to each_ item, however, the implementation of corrective action

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had not been verified.

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.Bechtel has an ongoing surveillance of on-site work ,d QC

activities.- The.NRC inspector reviewed the survei.(_nces by.

Bechtel site QC for adequacy and effectiveness.

(4) Documents Reviewed

. South' Texas Project FSAR through Amendment 50

Concerning Tendons

.'Bechtel Specification 2C239CS003 Revision 4,

" Containment Post-Tensioning System"

. Prescon " Quality Assurance-Manual," Revision 9

. Prescon " Shop Fabrication Procedures," Revision 4A

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. Prescon " Field Quality Control Procedures," Revision ~3

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. Prescon ." Vertical and Horizontal Tendon Installation

Procedures"

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. Prescon "Q.C. Procedure for Cleaning and Checking

Post Tension Embedded Items," Revision 1

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. ASTM-A421 " Uncoated Stress-Relieved Wire for

Prestressed Concrete,"_1965

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. ASME Section III Division 2 Essential Variables in

Prestressing Element Materials

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. Construction drawings and plans for the system and '

other documents relating to the work.

. Qualification tests for the tendon system

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b. Engineering / Tests

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(1) Wire Relaxation Test

A minimum of three relaxation test of 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> duration 4

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are required in accordance with the requirements of ASTM -j

E-328, " Standard Recommended Practice for Stress-Relaxation

Tests for Materials and Structures." -The package which

included mill test reports, stress-strain curve, and

relaxation curves was complete.

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(2) Dynamic Tests-Tendons

Dynamic tests are required to be performed on the anchorage units

and tendon and shall duplicate the behavior of the full size

tendon. The testing is required to be performed on specimens

having at least 10% of the full size prestressing steel area of

the proposed production tendon. One test is to be 50 cycles of

stress varying from 40% to 80% of the unit's ultimate tensile

strength. The second test, is 500,000 cycles of stress from

60% to 66% of the unit's ultimato tensile strength. The test

report reviewed was atlequate for methods, calculations, set-up

and supporting documentation.

(3) Static Test - Stressing Washer

In this test, the specification requires a test assembly con-

sisting of standard manufacture anchorage units and a full size

tendon not less that 10 feet long. All items are to be identical

in material and manufacture as those proposed to be supplied in

this work. In lieu of special test programs of static and

dynamic tests on tendon units, the contractor may supply certi-

fied data from previous tests on like units.

(4) Static Test-Tendon

The specifications require that a test assembly, consisting of

standard manufactured anchorages and tendons of full size and

not less that 10 feet long, be tested to destruction in order to

prove the materials and system design. Certified data from pre-

vious like tests are acceptable. The NRC inspector reviewed

three reports of tests performed at Prescon in 1974. The testing

was witnessed by a third party as required in addition to

Prescon and Bechtel representatives.

The reports reviewed were:

(a) Test #1100H186-ll, Revision 1, test date 7/19/74

Static Test - Tendon

(b) Test #1100H186-3, test date 8/19 - 20/69

Static Test - Stressing Washer

(c) Test #1100H186-3, test date 8/19 - 20/69

Static Test - Bearing Plate

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(5) Static Test - Bearing Plates

The specification requires that the material for bearing

-plates be tested with the tendon in a series of static

tests. The material is required to be manufactured to ASTM

A633 grade E or equivalent. Review of the test data for

the bearing plates indicate that the test material meets

the ASTM requirements; also the test data, method and

recording appear to be adequate.

(6) Grease Test

The specification requires that test data for the sheathing

filler grease meet specific requirements. The NRC

inspector reviewed a report from Viscosity 011 Company and

a grease test report and determined that the requirements

for the compound used (Visconorust 2090P-4) meets the

requirements of the specification.

c. Work Observation

(1) Receiving

The NRC inspector observed the receipt of tendons on two

occasions in August and September and it was found that the

tendons were adequately wrapped and coated with preservative

grease. The unloading was performed with adequate assurance

against damage.

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(2) Storage

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The laydown storage of the tendons from receipt until install-

,- ation was found to be adequate during several inspections.

(3) Installation

The complete installation of two tendons was observed during the

inspection, additionally, partial inspectio'ns were made of

others. The two installations inspected were 1-H-094 and

2-H-087. The documentation was reviewed and was complete.

(Tendon Installation Card)

.(4) Buttonheading

The work process of buttonheading was observed on the field

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-made end on 1-H-028 and 1-H-022. This is a process of

upsetting or deforming the wire end so as it cannot go through

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the hole in the stressing washer. The Prescon QC inspector

examined 100% of the buttonheads for splits or defects and

checked each for size with a go-no go gauge. The tendon ends

were greased and tne wire was pulled up to the washer face and

the entire unit was pulled into the trumplate.

It was noted that the wire used by Prescon makes unusually

good quality buttonheads with near zero defects. The temporary

cover and weatherproof gasket was installed and work proceeded

to the next station. The documentation (Tendon Buttonheading

Card) was examined and found to be complete.

(5) Tendon Stressing

Tendon stressing was performed on approximately one-third of the

horizontal tendons from the number two buttress during the

inspection. One-half of the verticals have previously been

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stressed. A review of the process and records was made and it

was noted that the stressing cards are completed and include the

required data which reflected the actual work effort. On

completion of the stressing the protective can and gaskets were

affixed and tightened.

(6) Greasing

The-greasing operation was observed on several occasions and in

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detail'on two tendons (2-H-063 and 2-H-045). The grease was

pumped from the tank at 40 PSI (150 max) at 210 F (250 F max),

the air was bled off and the casing was filled and sealed off.

No spills have been or were observed and the records (Tendon

Greasing Cards) were reviewed and were found to be complete.

(7) Calibration

During the reporting period, many instruments were checked

for reading and calibration interval and due date. No discre-

pancies were noted concerning this item.

(8) Cans

The tendon cans were inspected and found to be fabricated as

required.

(9) Inspectors

Prescon provides an adequate number of inspectors (4) to the

job. In conversation with inspectors, and also review of

inspector qualifications and training records, it was observed

that the inspection process is being accomplished by adequately

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d. Records

(1) Procedures / Records

A review of the procedures by the NRC inspector revealed that

there are an adequate number of forms to be completed into

records covering all aspects of the program from receipt to

greasing.

(2) Vendor Surveillance Records

Two packages of Bechtel vendor surveillance reports (QRS 11 and

19) were reviewed for adequacy and it was noted that the inspec-

tor was descriptive of the items inspected, including reference

requirements, type of inspection and results, and the identifica-

tion of the hardware; i.e., tendons, shims, washers, and grease

caps. Also included was Prescon's certificate of conformance

and shipping documents.

(3) Shipping / Receiving Records

The basic shipping and receiving records in seven record packages

were reviewed for materials shipped to the site. The records

included stressing washer mill test reports Nos. H-917 and H-918;

-these two reports were for AISI.4330 modified steel. The required

elements, including mechanical and chemical properties, heat

treating, hardness and impact test were reviewed. Wire mill test

reports for Shinko Wire Co., specifically mill test

reports KA0490, KB7023, KB7473, KC2585, KA1419, and KC2920, were

reviewed for process, chemistry,. narking, grade, physical

properties and stress / strain curves. The reviewed reports were

adequate and meet the specification requirements.

(4) Receiving Records - Grease

The records for the grease were compared to the FSAR, Bechtel

specification, Prescon procedures, and ASME Code and it was noted

that the required tests were performed and properly documented

for Visconorust 2090-P-4 lot 5-6894.

(5) Training Records

The training records for a level II inspector for Prescon

was examined. The attributes covered were:

(a) Testing - which included assignments and tests covering

receiving, cleaning and checking, installation, button-

heading, greasing and stressing and protection. All of

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the documents reviewed indicated that the test was of

significant depth to assure that a person was qualified to

inspect the work if he had a satisfactory score on the test.

(b) On the job training - records were available to indicate

and record on the job training in the area of cleaning,

receiving, installation, buttonheadings, stressing,

greasing and calibration. Also, ample records were on file

to record past work experience on resumes.

(6) Calibration Records

For the records examined, each point on the inspection forms

would have an annotation for the measuring and test equipment

used. There are approximately nine items in the calibration

program and are buttonhead and eccentricity gauges, torque

wrenches, pressure gauges, micrometers, calipers, stressing

jack / gauges, and thermometers. The units are required to be

checked against national standards. No discrepancies were

noted.

(7) Completed Records Packages-Tendons V109, V127, V207, V223,

V235, V247

Completed record packages for six vertical dome tendons were

examined for completeness. These packages include the fabri-

cation record, mill tests for the washer and wire including back

up data. Hold points are noted throughout the fabrication

process traveler and all applicable hold / inspection points were

signed off.

Prescon deficiency and disposition report and supplier deviation

disposition requests were included in the package under the

appropriate heading and were completed and in order. The

following reports are required by the procedures and follow the

order of the work process. These records are:

. Tendon Receiving Card - Nine attributes are recorded, checked

and signed off; an attachment is the quality verification

documents requirements sheet.

. Tendon Void Check - This document records the check for

obstructions, clearance and cleanliness; each of which was

signed off as completed except for three columns that were

not applicable.

. Trumplate Assembly Check - Cleanliness, bolt holes, sealing

and protection are completed for this item.

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. Vent and Drain Check - Form properly filled out--vent

only applies here.

. Tendon Installation Card - This checklist records the

' results of installing the tendon into the sheathing and

spacing it on each end. All attributes were indicated

acceptable and checked.

. Temporary Tendon End protection - After the tendon is

inserted there is a time interval before stressing,

therefore the protruding ends must be covered; this form

indicated that the work was performed.

. Tendon Buttonheading Cord Field End - The 186 buttonheads

are made and checked with a go-no go gauge for concentricity

and splits. This form provides for 10 inspection attributes,

each of which was satisfactory.

. _ Tendon Stressing Card - These cards contain dimensional

data on slack pressure, gauge pressure, elcr.gation,

shimming and actual lift off or actual load. The cards

were noted to be ccn.pleted.

. Grease Can Installation Card - This card indicates that

the can, "0" rings, and bolting is satisfactory.

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Tendon Greasing Card - This card contains 10 items of

inspection in greasing; mainly, the grease, its

temperature, pressure and cycle through the tendon void and

capping. In this and previous cards, measuring and test

equipment used was noted on the cards.

e. Summary

During the review of the engineering test and qualification data and

the comparison of the specification /FSAR/ procedure requirements, scre

minor concerns were noted and are included in the body of this report.

The items of concern were promptly responded to and the corrective

actions were acceptable to the NRC inspector.

The Prescon program for tendon installation appears to be functioning

as required as no items of significance were observed in the

fabrication, work process, Quality Control or records.

No violations or deviations were identified.

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9. Safety-Related Pipe Supports / Restraint Systems

The purpose of this inspection was to determine the following:

. Whether technical requirements are detailed or referenced in the

FSAR with safety-related pipe supports / restraints, and have been

adequately addressed in construction specifications, drawings

and work procedures.

. Whether QA plans, instructions, and procedures for

safety-related pipe supports have been established in the QA

Manual.

. Through direct observation and independent evaluation of work,

whether the licensee's work control system is functioning

properly and whether the installation of safety-related pipe

supports /restrair.ts are in compliance with licensee

specification and procedures.

a. Procedures / Specification

The NRC inspector reviewed procedures and specifications to

determine whether technical requirements were detailed and

adequately addressed. The procedures reviewed contained some

technical requirements but mainly referenced the pipe support

specification and manufacturer's instruction. The specification

did contain adequate inspection criteria for purposes of

inspection and installation. The FSAR contained technical

requirements mainly for the design and stress analysis for

safety-related piping and pipe supports. Work procedures and

specifications were determined to incorporate controls to ensure

that: type and classification of pipe supports / restraints

systems comply with approved drawings, preinstallation and

in process inspections are performed at the appropriate time,

means to ensure that bolts, nuts, and washers are of the proper

type and correctly installed, and minimum bolt embedment and

thread engagement criteria are imposed.

The procedures / specifications that were reviewed are adequate.

Documents Reviewed

. FSAR

. QCP 10.12 " Component Support Fabrication & Installation

Inspection," Revision 4, dated 6/17/85

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Specification 4L360JS1000 " Specification for Pipe Supports

for ASME III Piping," Revision 4, dated 4/4/85

. Specification SL340JS1002 " Pipe Stress and Support

Construction Specification," Revision 7, dated 7-1-85

b. Observation of Work and Work Activities

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The NRC inspector visually examined 21 pipe supports of the Essential

Cooling Water (EW) system. These supports had previously been

QC-accepted. The purpose of this inspection was to determine if the

pipe supports installed were installed per the current design

drawings, procedures and specifications.

Review and examination of these supports by the NRC inspector

indicated correct configuration, alignment and installation, with

one exception. Pipe support #EW-9129-HL5003 contained two

discrepancies.

(1) NF welds shown on the drawing indicated 3/8" fillet

welds, the actual field weld was 1/4".

(2) The design drawing indicated a UH9 strap; actual field

installation indicated a UH9 A strap which is larger.

Investigation by the NRC inspector indicated that, shortly before

the final acceptance by QC, a new revision was issued. It

appears that the field revision list (FRL) possibly did not get

into the hands of the QC inspector. There was an NCR issued on

this support. The NRC inspector has determined that this

discrepancy was an isolated case.

Documents Reviewed

. EW-9114-HF5007 . EW-9229-HL5005

. EW-9113-HF5006 . EW-9229-HL5003

. EW-9114-HF5005 . EW-9129-HL5001

. EW-9114-HF5006 . EW-9130-HL5003

. EW-9114-HF5002 . EW-9107-HL5008

. EW-9113-HL5003 . EW-9129-HL5003

. EW-9130-HL5002 . EW-9114-HL5001

. EW-9114-HL5003 . EW-9130-HL5001

. EW-9329-HL5003 . EW-9130-HL5006

. EW-9107-HL5003 . EW-9113-HL5001

. EW-9330-HL5003

No violations or deviations were identified.

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10. Spent Fuel Storage Racks

A follow up on open item 8506-02 was performed by the flRC inspector.

Westinghouse was requested to provide traceable material test records

for the STP spent fuel storage racks to ensure proper fabrication and

use of materials. Certified material test records (CMTRs) for requested

shop orders were reviewed by the NRC inspector with the referenced

Westinghouse drawings. It was determined that the STP spent fuel racks

could not be directly tied to the provided CMTRs.

Documentation was obtained from Westinghouses' Pensacola Operations by

Westinghouse personnel. However, it was determined that material trace-

ability for eight (8) components used in the fabrication of the

6 X 6 fuel rack for Units 1 and 2 could not be determined. It appears

that the eight components were surplus materials obtained from other

purchase orders and were not properly identified on travelers for those

components. Open item 8506-02 will be closed and escalated to a violation.

This is an apparent violation. (8513-01)

11. Exit Interview

An exit interview was conducted on October 3, 1985, with those

personnel denoted in paragraph 1 of this report. During the exit

interview, the NRC inspectors summarized the scope and findings of

this inspection.

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