IR 05000498/1987073
| ML20147D290 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 01/05/1988 |
| From: | Gilbert L, Haag R, Seidle W, Vickrey R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20147D280 | List: |
| References | |
| 50-498-87-73, 50-499-87-73, NUDOCS 8801200121 | |
| Download: ML20147D290 (7) | |
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APPENDIX
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U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-498/87-73 Operating License:
NPF-71 50-499/87-73'
Construction Permit:
CPPR-129 H
Dockets:
50-498 50-499 Licensee: Houston Lighting & Power Company (HL&P)
P.O. Box 1700 Houston, Texas 77001 Facility Name:
South Texas Project (STP), Units 1 and 2 Inspection At:
STP, Matagorda County, Texas Inspection Conducted: November 30 through December 11,-1987 ff
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Inspectors:
L R. B. V(ckrey, Reactor Inspector, Operational Date Programs Section, Division of Reactor Safety
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//r'/ W L. D. Gilbert', Reactor Inspector, Materials Matg/
and Quality Programs Section, Division of Reactor Safety
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R. C. Haag, Reactor Inspector, Materials and Date i
i Quality Programs Section, Division of Reactor Safety a
Approved:
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W. C. Seic(lp, Chief, Operational Programs Date Section, Division of Reactor Safety Inspection Suninary Inspection Conducted November 30 through December 11, 1987 (Report 50-498/87-73; 50-499/87-73)
8801200121 880114 PDR ADOCK 05000498
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Areas Inspected:
Routine, unannounced inspection of selected instrument components and systems, welding of reactor vsssel internals, mechanical component work observations, procedure and record review, and followup of previously identified inspection findings.
Results: Within the four areas inspected, no violations or deviations were identified.
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DETAILS 1.
Persons Contacted -
- J. S. Phelps, Project Compliance
- S. Phillips, Project Compliance
S. liead, Lead Engineer, Licensing M. Glover, Quality Control Inspector Westinghouse C. Hahn, Lead Construction Engineer D. Mathews, Mechanical Engineer
- Denotes those attending the exit interviews on December 3 and December 11, 1987, 2.
Licensee Action On Previous Inspection Findings (Closed) Unresolved Item (498/8751-01) - bolt missing on second flange of the crankcase exhaust vent line on Diesel Generator (DG) No.12.
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item concerned a missing bolt that was identified to the licensee by the
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NRC. The NRC inspector verified visually that the missing bolt has been i
replaced and properly documented with Maintenanca Work Request DG-87022001.
j This did not affect operability.
This item is closed.
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3.
"A" Train Loss Of Offsite Power Signal The licensee issued a station problem report as a result of an "A" train loss of offsite power signal that occurred on December 9, 1987, at a
4:24 a.m. (CST).
The licensee could not determine the cause of the trip
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signal at the time but did indicate to the NRC inspector that all plant automatic functions performed as designed.
At the time of the event, the licensee was involved with the performance of Surveillance Tests 1 PSP 06-DG-0003, "Undervoltage Loss of Voltage Relay TADOT," and 1 PSP 06-DG-0004, "Sustained Degraded Undervoltage Relay TAD 0T."
The NRC inspector reviewed the written statement of the electrician performing the test and the previous four completed surveillance tests involved.
After being unable to determine the cause of the trip, the licensee performed both surveillance tests successfully without incident.
No violations or deviations were identifie _.
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4.
Completed Work of Instrument Components and Systems The NRC inspector observed and inspected the completed installation of various safety-related instrument components and associated items.
The selected instruments are listed below:
Instrument
' Associated Component / System C2EW-FT-6873 Essential Cooling Water Flow Transmitter C2EW-FT-6875 Essentia', Cooling Water Flow Transmitter A2HF-TSH-9517 Fuel Handling Building Temperature Switch A2HF-TSH-9574 Fuel Handling Building Temperature Switch B2HF-TSH-9575 Fuel Handling Building Temperature Switch C2SI-PT-0863 Safety Injection Pressure Transmitter D2SI-LT-0931 Safety Injection Level Transmitter A2CV-FT-0205 Chemical &' Volume Control Flow Transmitter A2CV-FY-0205 Chemical & Volume Control Flow Relay B2RC-HY-0602 Reactor Coolant Hand Relay-A2RC-HY-0601 Reactor Coolant Hand Relay
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B2RC-FT-0449 Reactor Coolant Flow Transmitter
A2RC-FT-0447 Reactor Coolant Flow Transmitter The NRC inspector determined that:
Location, configuration, and installation were according to the-latest approved design or construction specifications and drawings.
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Components were correctly and permanently identified and specified
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instrument components and associated items had been used.
Cleanliness requirements had been maintained and adequate separation and isolation were satisfied.
The installed equipment was adequately protected from adjacent construction activities.
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Nonconforming conditions had been identified and controlled in
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accordance with approved procedures.
Completion status, maintenance, and readiness for preoperational
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testing was indicated by documentation.
During the course of the inspection, the NRC inspector noted three of the instruments had discrepancies - a missing cover, a damaged cover, and a damaged conduit-flex hose.
The NRC inspector verified that they had been properly documented.
A review was made of 288 Nonconformance Reports (NCRs), that had been opened and closed in 1987, oa instrument.
components and systems.
The review was conducted to detennine if inadequate protection for instruments and components was a problem.
The
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NRC inspector was satisfied, as a result'of his review of the.NCRs, that there is no apparent problem with the protection being currently provided for instruments and components.
The NRC inspector examined receiving inspection records for the above listed instruments to. determine whether the receiving inspection activities were controlled and performed in a manner to ensure that applicable requirements were satisfied in the following areas:
Proper identification on components and documents.
- Physical condition of components.
Receipt of quality documentation with components and verification of compliance with the requirements.
The NRC inspector made a tour of the licensee's storage area for instruments to verify that proper identification, recordkeeping, housekeeping, and environmental conditions were being maintained.
The NRC inspector was accompanied by a licensee-qualified quality control (QC) inspector during part of his inspection.
The QC inspector demonstrated an excellent understanding of installation procedures, drawings, and specifications.
No violations or deviations were identified.
5.
Welding of Reactor Vessel Internals The NRC inspector reviewed the following activities in the area of field welding of the internals for the Unit 2 reactor vessel The installation documentation for the four welds that attached
the core support energy absorbers to the base plate was reviewed.
The welding requirements were specified on Westinghouse Drawing No. 6119E74 which was identified by Bechtel Log No. 14926-0042(02)00036.
The welding and inspections were documented in Westinghouse Traveler No. T-THX-210.
The installation documentation was reviewed for the 48 locking bars
welded to the 6 lower radial support clevis insert assemblies for the i
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Unit 2 reactor vessel internals.
The welding requirements were specified on Westinghouse Drawing No. 6120E19 which was identified by Bechtel Log No. 14926-0042(02)00146.
The welding and inspections
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were documented in Westinghouse Traveler No. T-THX-208.
Welding Procedure Specifications 8-8-GT-52, 43-43-GT-53, and supporting procedure qualification records were reviewed.
- Westinghouse procedures TGX-Q-10.01 and TGX-Q-10.02 for visual and liquid penetrant examinations were reviewed.
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Records were reviewed for the_ qualifications of welders and quality control examination personnel 'for Westinghouse.
The material certification reports for the liquid penetrant materials-and welding filler materials were reviewed.
The finished installation welds for attaching the four energy absorbers to the base plate were visually inspected by the NRC inspector.
Based on this review and visual inspection of.the completed welds,.the inspection identified no. violations or deviations.
6.
Safety-Related Mechanical Components The NRC inspector reviewed work packages and conducted observations for selected safety-related components to determine whether activities associated with the components were being accomplished in accordance.with NRC requirements, FSAR commitments, and licensee procedures, a.
Work Observations The NRC inspector observed removal of the Pressurizer Safety Relief Valve (PRSRV) Nos. 2RC-PSV-3450, -51, and -52.
Specific areas observed included the flange disassembly, valve rigging, and system closure.
The PRSRVs were being removed in preparation for the primary plant hydrostatic test.
The inspector also inspected the following equipment for which work had been completed or was in progress:
Spent Fuel Pool Cooling Pump No. 3R212NPA201B Manual Operated Gate Valve No. 2S102TMS0021 Reactor Coolant System (RCS) Flow Detector Nos. FT-417, -418, and -419 Component Cooling Water Pump No. 3R202NPA201A All attributes that could be visually inspected were ext
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adequacy of design and completeness of construction
...c"lar areas examined included welding, bolting, identific-
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flanges, switches, connections, tagging, restraints,.
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and cleanliness.
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Documentation Review The NRC inspector reviewed work packages associated with the installation of the equipment previously listed, with the exception
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of the RCS Flow Detectors FT-417, -418, and -419.
Dacosents reviewed
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. included installation drawings, mechanical equipment installation travelers, material lists, coupling' alignment sheets,-welding inspection reports, and process data checklists.
Rework. documentation, involving flange misalignment for the PRSRVs'was reviewed to assure that the problem with the inlet flange leakage on the Unit 1 PRSRV was properly addressed for the Unit 2 PRSRVs.
To identify if a flange misalignment problem existed, the licensee measured inlet piping flange movement after the PRSRVs were removed and then measured flange gaps and alignment during valve-reinsta11ation.
Proper flange alignment could not be obtained'on Valves 2RC-PSV-3450 and -3452.
To correct,the. misalignment for Valve 2RC-PSV-3450, two weld joints (tha inlet piping flange to pipe joint and the. loop seal piping to. elbow joint) were cut and remade.
For Valve 2RC-PSV-3452, only the inlet piping flange to pipe joint required cutting and rewelding.
During review of the above documentation, the NRC inspector also reviewed the following Standard Site: Procedures (SSPs) which were referenced in the work package and were critical to the associated work:
SSP 10, Revision 3, "Installation and Field Fabrication of Piping" SSP 52, Revision 1, "Installation and. Disassembly of Permanent Mechanical Plant Equipment" No violations or deviations were identified.
7.
Exit Interview The NRC inspectors met with licensee representatives, denoted in paragraph 1, on December 3 and 11, 1987, and summarized the scope and findings of the inspection.
The NRC construction resident inspector was present at both meetings.
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