IR 05000498/1987074

Insp Repts 50-498/87-74 & 50-499/87-74 on 871121-880115.No Violations Noted.Major Areas Inspected:Site Tours,Licensee Action on Previous Insp Findings,Fastener Testing & Reactor Internals

ML20149F317
Person / Time
Site:	South Texas
Issue date:	02/08/1988
From:	Constable G, Garrison D, Clay Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20149F314	List: IR 05000498/1987074 ML20149F310
References
50-498-87-74, 50-499-87-74, NUDOCS 8802170030
Download: ML20149F317 (7)

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e APPENDIX U. S. NUCLEAR REGULATORY COMMISSION  :

l REGION IV

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NRC Inspection Report: 50-498/87-74 Operating License: HPF-71

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50-499/87-74 Construction Permit: CPPR-129

Dockets: 50-498 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 (STP)

Inspection at: STP, Matagorda County, Texas  ;

Inspection Conducted: November 21, 1987, through January 15, 1988 C

Inspectors: __ 7 N

[C.E.%hnson,"3eniorResidentInspector Dat'e

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Project Section D, Division of Reactor Projects i

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D. L. Garrison, Resident Inspector, Project Date Section D, Division of Reactor Projects N

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Approved: _r 2/ '

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. L. h m uiu, unfef, Project Section 0 Dat'e l Division of Reactor Projects l

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i 8802170030 880210

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PDR ADOCK 05000498 O DCD

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2 Inspection Summary Inspection Conducted November 21, 1987, through January 15, 1988 (Report 50-498/87-74; 50-499/87-74)

Areas Inspected: Routine, unannounced inspection including site tours, licensee action on previous inspection findings, fastener testing, and reactor internal Results: Within the three areas inspected, no violations were identifie :

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i DETAILS

, Persons Contacted Principal Licensee Employees

"J. T. Westermeier, Project Manager

• T. J. Jordan, Project Quality Manager

• J. S. Phelps, Project Compliance Supervisor

• S. D. Phillips, Project Compliance Engineer

• J. E. Geiger, Nuclear Assurance Manager M. Bower, Principal Engineer Bechtel Power Corporation (Bechtel)

• R. Bryan, Field Construction Manager

• R. Medina, Quality Assurance Supervisor A. Lopez, Civil Engineering Supervisor

• R. Miller, Project Quality Assurance Manager Ebasco Service Inc. (Ebasco)

• D. White, Project Manager

• R. Able, Quality Control Supervisor Westinghouse D. Bokesch, Quality Control Supervisor

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In addition to the above, the NRC inspectors also held discussions with other merbers of the HL&P, Bechtel, Westinghouse, and Ebasco staff * Denotes those individuals attending the exit interview conducted on January 19, 198 . Site Tour 1

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The NR311nspectors made frequent tours of the Unit 1 and 2 reactor i containment building (RCB), Unit 2 mechanical electrical auxiliary building (MEAB), diesel generator building (DGB), fuel handling building (FHB), isolation valve cubicle (IVC), warehouses, storage l yards, and outlying areas. The tours were made during normal working 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, backshift, and weekends. Some safety items observed during '

these tours were pressurizer PORV, code safeties, RHR pump repair of the leaking gaskets, Unit 2 reactor internals and welding on various safety-related piping. No discrepancies were foun l l

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4 Licensee Action on Previous Inspection Findings I

(Closed) Violation 499/8748-01 1 This item concerned the commingling of hot-dipped galvanized nuts used 1 with electromagnetic zinc-coated bolts and hot-dipped galvanized bolts used with electromagnetic zinc-coated nuts which was in violation of Specification SV279VS1003, Revision Since identification of the problem, the licensee has taken immediate corrective actio Review of

the corrective actions appear satisfactory.

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(Closed) Violation 498;499/8770-02 This item concerned the failure by Westinghouse to translate design requirements; specifically, the hold down torque values for bolting that secures the fuel racks to the fuel pool floo The licensee and Westinghouse have reanalyzed the design loads and procedures and it was determined that, although the original design loads were not met, the loads that were applied are adequate. The licensee had taken corrective action in reviewing other Westinghouse procedures for similar problem (Closed) Violation 499/8770-01 This violation concerned the welding of a Class 9 penetration cover plate to a Class 3 safety related structural member which was not in accordance with design drawings and a field change request (FCR) and was not reviewed or accepted by engineering. Followup of this violation indicated that the licensee had taken appropriate corrective action.

Fastener Testing (35065 and TI 25026)

An inspection of the activities concerning fasteners was performed in order to verify the adequacy of the program and its effectiveness in j detecting nonconforming materials. This inspection implemented the requirements of NRC Compliance Bulletin No. 87-02 "Fastener Testing to Determine Conformance with Applicable Material Specifications." l Procedures

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NNRCinspectorreviewedthelicensee'sprogramforpurchasing, receipt inspection, testing, storage, and issuance of fasteners from

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warehouse storage. The following documents were reviewed:

Specifications 4A010GS1009, "Safety-related Non-ASME Bolting i Materials"; 4A900PS1007, "ASME Section III Nuts and Stud Bolts"; and 4L360JS100, "Pipe Supports for AMSE Piping"; and Standard Site t

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Procedure (SSP) 13. "Material Control."  ;

l It was determined that the mate-ials were purchased utilizing the l above mentioned specifications which were appropriate for each of the i fasteners. The site quality program contained adequate procedures ,

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to receive, test, inspect, store, and issue the material i t l l I i l i

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5 Selection and Testina j The NRC inspector selected samples of the fasteners from warehouse stock. The number and type of fasteners were chosen on the basis of ;

plant usage. This was determined by using estimates from the civil and piping engineering groups and a computer generated bulk item listin The listing was further used to determine the location of '

the fasteners.

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For each of the selected fasteners in the listing, it was found that l the items were in their proper locations, easily retrievable, and ,

j properly stock code The sample size was 52 fastener For each fastener selected it was verified that the item was correctly marked with the manufacturer's mark, grade, or type and size.

! The NRC inspector verified that the samples used for testing were adequately segregated, tagged, or identified. The purchase order was adequate in specifying the testing to be performed. The purchase order was also assigned to a certified laboratory for testing of the fastener '

The following samples taken were tested:

i Bolts / Studs N Nuts N A-325 Gr. A 2 A-194 Gr. 2H 6 i l

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A-325 Gr. B 2 6 2 A-307 3 6F 2 l l A-490 2 7 2

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l A-193-B7 4 8 1 J

A-193-88 2 A-563 Gr. A 4 A-320-L7 2 C 2 A-499 1 DH 1 i *A-193-B7 2 l

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• All. samples are safety-related except this ite TNefollowing12fastenerswereextrasamplestakenfortesting,due '

to the manufacturer's mark being the same as that identified in TI No. 2500/2 i

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i l Bolts / Stud _s, N Nuts N A-193-86 1 A-194 Gr. 2H 3 A-193-B7 2 A-194 Gr. 6 4 A-193-B8 1 A-194 Gr. 88 1  ;

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A review of the laboratory test reports indicated that 50 fasteners were acceptable to the specification requirements. Two of the items tested were A-194-6F nuts. These nuts were found to be out of tolerance for sulphur which is added for machinability.

- It was determined, however, that the certificates which indicate chemistry, that were supplied with the nuts, were test results from the producing steel mill and are actually ladle gnalyci Sulphur segregates excessively; therefore, it is not expected that a product analysis or user test would show the true sulphur content. The test indicated conformance to the specifications .

except in this area. These two reports are considered satisfactory l

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and the materials are acceptable for their intended us It was determined that the licensee program in the area of material control is adequate, and the request for information as outlined in the Compliance Bulletin have been complied wit No violations or deviations were note . Reactor Internals (Thimble Guide Tube And Flow limiter Inspection)

(50051, 50053, 50055, and 57050)

A surveillance of the Eddy Current testing (by Westinghouse) of the

thimble guide tubes in Unit 1 was performed in order to verify that j the tubes were in good mechanical condition and to establish a

baseline of data for future planned examinations; also a test of the '

Bottom Mounted Instrumentation (BMI) flow limiter was performed in ;

Unit 2 in order to assess the fit-up when a fuel bundle is placed on ;

top of the limite Testina Procedures (

) The Eddy Current tests were performed by a qualified Westinghouse Leuel III examiner using Westinghouse Procedure M.P.2. ,

T.S.X.-1, "Eddy Current Inspection of Bottom Mounted l

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Instrumentation at South Texas Project Unit " The equipment  !

{ probe and reference standard was calibrated to Westinghouse

Procedure "Etalon Thimble Pour Westinghouse," dated December 16,

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1987. The work was performed in accordance with standard i

Westinghouse work packages and drawings, i

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e 7 Testina-Thimble Tubes Testing was performed on the .313-inch outside diameter thimble tubes which were pulled back 16 feet into the equipment room in order to take the tubes out of the probable wear and core are The testing utilized multifrequency/multiparameter data collection equipment and techniques which are applicable to the

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collection of baseline and future postoperational testing. The .I test data was permanently recorded on strip charts and applicable data sheets per the procedure. The NRC inspector verified conformance to parts of the procedure and work. The results were reviewed and analyzed by teams of specialists from Westinghouse and the licensee. The NRC inspector also discussed the program ,

with NRR specialists and it was concluded that the 58 tubes ~

examined did not appear to have any recordable defect . Testing-BMI Flow limiter l l

The flow limiter that was tested is a round spring-loaded device that rests on the lower support plate and is loaded in compression by a fuel bundle. This device guides the thimble ;

between the lower plate and fuel bundle. Improper positioning of this device in foreign plants is suspected of causing wear or fretting of thimble guide tubes. This test consisted of lowering a dummy fuel bundle onto a positioned limiter and observing _any displacement. The test was performed in the Unit 2 vessel. A ;

a movement of .0010 inch was observed which was within the expected ;

design parameters; this movement will normally occur because the-spring-loaded limiter is being compressed and seated. The guide

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tube alignment remained tru ,

i No violations or deficiencies were noted.

! 6. Exit Interview The NRC inspectors met with the licensee (denoted in paragraph 1) on January 19, 1988, and summarized the scope and findings of this l inspecgion.

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