IR 05000498/1988029

Insp Rept 50-498/88-29 on 880425-29.No Violations or Deviations Noted.Major Areas inspected:RCPB,safety-related Sys & Associated Mechanical Components

ML20154S576
Person / Time
Site:	South Texas
Issue date:	05/31/1988
From:	Ireland R, Singh A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20154S560	List: IR 05000498/1988029 ML20154S556
References
50-498-88-29, 50-499-88-29, NUDOCS 8806090099
Download: ML20154S576 (5)

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APPEN0!X U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: -50-498/88-29 Operating License: NPF-76 50-499/88-29 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: April 25-2 1988 Inspector:

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h Reactor Inspe~ or, Pldn stems T.te 3) '

M Sec o ivision eactor fe Apprcved: -i

,,4. Ifela n,, W 7c'tt'Tig Chief, Plant Systems 1 3l $

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ecti{n Division of Reactor Safety Inspection Sunnary Inspection Conducted April 25-29, 1988 (Report 50-498/88-29)

Areas Inspected: No inspection of Unit I was conducte Results: Not applicabl Inspection Conducted April 25-29, 1988 (Report 50-499/88-29)

Areas Insaected: Routine, unannounced inspection including reactor coolant pressure coundary, safety-related systems, and associated mechanical component Results: Within the areas inspected, no violatior ; deviations were identifie .

8806090099 880531 PDR ADOCK 05G00498 O DCD

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-2-DETAILS Persons Contacted HL&P

• J. T. Westermeier, Project Manager

• S. D. Phillips, Project Compliance Engineer

• G. L. Parkey, Plant Superintendent, Unit 2

• D. C King, Construction Manager, Unit 2

• G. Ondriska, Start Up Supervisor

• W. Trujillo,"Nuclear Assurance Supervisor

• M. Duke, Engineering

• M. E. Powell, Supervising Engineer, Licensing T. J. Jordan, Project Quality Assurance (QA) Manager

• D. R. Nester, Supervisor

• A. R. Mikus, General Supervisor

• J.. A. Slabinski, Operations Quality Control (QC) Supervisor, Unit 2

• R. A. Hernandiez, QA Bechtel Power Corporation (Bechtel)

• R. Bryan, Field Construction Manager

• R. Medina, QA Supervisor

• R. Miller, Project QA Manager R. G. Hess, Project Manager Ebas,co Service Inc. (Ebasco)

C. F. O'Neal. Unit 2 Engineering Manager

• R. Able, QC Supervisor

• A. Garcia Field Engineer D. D. White, Construction Manager In addition to the above, the NRC inspector also held discussions with other members of the HL&P, Bechtel, and Ebasco staffs.

! * Denotes those individuals attending the exit interview conducted on April 29, 198 . Safety-Related Components (50071, 50073, and 50075)

l l The purpose of this inspection was to determine whether activities l relative to safety-related components are being accom l

with NRC requirements, Final Safety Analysis Report (plished in accordance FSAR) comitments, l and licensee procedures by direct observation and independent evaluation l of work performance, work in progress, completed work, and records review.

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-3- Procedure Review (50071)

An assessment of specifications and procedures for safety-related components was performed in order to determine whether the technical requirements of the FSAR are adequately addressed in onsite specifications and procedures and whether QA plans and procedures provide adequate inspection criteri The NRC inspector reviewed the following documents:

. FSAR, Sections 5 and 6, "Design Parameters and Material Specifications"

. Specification No. 5A300GS1002, Revision 8, "Storage Requirements for STPEGS Safety-Related Engineered Equipment"

. Standard Site Procedure (SSP) 13 Revision 3 "Material Control"

.. SSP 44, Revision 0, "Storage and Maintenance of Permanent Plant Equipment" 4 . SSP 52, Revision 2 "Installation, Assembly and Disassembly of Permanent Mechanical Plant Equipment"

. SSP 3. Revision 5. "System Completion and Release for Test"

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The NRC inspector also reviewed other related procedures and specifications that make up the documented programs which govern site activitie No violations or deviations were identifie Work Observations (50073)

The NRC inspector selected a representative number of mechanical components within the reactor coolant pressure boundary and in safety-related systems outside the reactor coolant pressure boundar Two of these components were motor-operated valves. Components examined are listed below:

. RC Purification Pump 3R172NPA204A

. RHR Pump 2A

. ESW Strainer 3R282NSP201A

. ESW Strainer 3R282NSP201B ar- 201C

. EW M0V 3R282NPA202A

. EW MOV 3R282NPA2028

. EW MOV 3R282NPA202C

, EW Pump 3R282NPA201A

. EW Pump 3R282NPA2028

. EW Pump 3R282NPA202C L

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. Pressurizer PSARV Valves

. N2RC-PSV-3450

. N2RC-PSV-3451

. N2RC-PSV-3452

. Spent Fuel Pool Heat Exchanger 3R212NHX201A All attributes of inspection that could be visually inspected were examined for conformance with the design and completeness of construction. The following were examined: welding, bolting, component identification, damage to flanges, alignment, mounting, switches, connections, grounding, clearances, insulation, restraints, and cleanlines One concern was identified which involved lack of tagging of the pressurizer safety and relief valves. After further investigation, the licensee produced a document which provides the mechanism for retagging of the valves. The licensee stated that the missing tags were replaced, and this was verified by the NRC inspector. During the walkdown in the other safety-related areas, it was observed that the components were labeled properly 5 accordance with Procedure SSP-20, "Equipment Labeling." The licensee stated that tagging is accomplished and verified during construction, installation, and inspection In the event a tag is discovered to be missing, it is replaced immediately or tracked on the maintenance control list (McL) until replaced. Further, the system is walked-down by the Nuclear Plant Operation Department (NP00) in preparation for system's acceptanc No violations or deviations were identified, c. Records (50075)

The following safety-related component records were retrieved from the licensee vault to determine whether the licensee's system for preparing, reviewing, and maintaining records was functioning properly:

. Regenerative Heat Exchange 2R172NHX201A

. Letdown Heat Exchanger CV5R172NHX202A

. RC Purification Pump 3R172NPA204A

. Letdown Filter 3R172NFR205A

. Reactor Coolant Filter 2R172NFR201A

. Mixed Bed Demineralizer 3R172NDM201A

, Cation Bed Demineralizer 3R172NDM202A

. Letdown Filter 3R172NFR2058

. Reactor Coolant Filter 2R172NFR201B

. Mixed Bed Demineralizer 3R172NDM201B

. Cation Bed Demineralizer 3R172NDM202B

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-5-The NRC inspector reviewed the records and concluded that the records were consistent with the NRC requirements and the licensee's FSAR commitment During the review of the preceding records, no violations or deviations were identifie Audit Reports (50075)

The NRC inspector reviewed Audit Report Nos. M16-801 and S72-70 These audits were performed by Ebasco QA and HL&P auditors to determine the proper implementation of the quality-related

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requirements for the safety-related components. The NRC inspector's review of the audit reports revealed that the required audits were performed in accordance with the schedule, that findings were reported in adequate detail for proper assessment and corrective action, and that the licensee / contractor has taken proper followup action on the deficiencies identifie #

No' violations or deviations were identifie . Exit Interview An exit interview was conducted on April 29, 1988, at which time the scope and findings of this inspection were discussed with HL& ,

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