IR 05000498/1985011

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Insp Repts 50-498/85-11 & 50-499/85-11 During Jul 1985.No Violations or Deviations Noted.Major Areas Inspected:Site Tours,Licensee Action on Previous Findings,Differential Settling of Unit 1 & Startup Testing
ML20151M256
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 12/17/1985
From: Carpenter D, Constable G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20151M237 List:
References
50-498-85-11, 50-499-85-11, NUDOCS 8601020514
Download: ML20151M256 (6)


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APPENDIX-

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  • 'U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

'NRC Inspection Report: 50.498/85-11 CP: CPPR-128 and 129 50-499/85-11

. Dockets: ' 50-498 50-499 4

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

. . O. Box 1700 Houston,' Texas 77001

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Facility'Name: South Texas. Project, Units 1 and 2 Inspection At: South Texas Project, Matagorda County, Texas Inspection Conducted: July 1-31,~1985

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' Inspectors: .

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hD.R. Carpenter,ResidentInspector

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Ofte '

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y / ~ Project Section C,~ Reactor Projects

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Branch-

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Approved: w -

G'L. ' Constable, Chief, Project Section C - Datb-Reactor Projects Branch Inspection Summary

. Inspection Conducted July-1-31, 1985 (Report 50-498/85-11; 50 499/85-11 Areas Inspected: . Routine, unannounced inspection included site tours, licensee

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. action on previous findings,. differential. settling of; Unit 1 and startup testing. The inspection involved'107. inspection-hours- onsite by one NRC;

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Results: Within_the scope of this inspection, no violations $r deviations were

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a 8601020514 851219 PDR ADOCK 05000498 G PDR

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. DETAILS Persons Contacted-Principal Licensee Employees

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  • E: Hill - Project Compliance Engineer
  • F. White, Lead Project Compliance Engineer K. O'Gara', Project Compliance Engineer R.' R..Hernandez, Supervisor, Project Compliance F. Alkov, Material Control Supervisor e *L. Dolan, Project' Compliance Engineer

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.*R. Daly, Startup" Manager

  • A. G. Peterson, Startup r T. J. Jordan, Project QA Manager

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  • D. R. Keating, Operations QA General-Supervisor J. T. Westermeier, Project Manager

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  • R. C.'Arthurs, Project QA General Supervisor W. H. Kinsey, Plant Manager
  • S. M. Dew, Deputy Project Manager Other Personnel Bechtel Power Corporation (Bechtel)
  • J. B. Gatewood, Project QA Engineer R. H. Medina, Lead QA Engineer
  • D. M. Stover, Construction Manager
  • J. E. Noxon, QA Engineer

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Ebasco Services, Inc. (Ebasco)

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.*A. M. Cutrona, QA Manager

  • R..M. Zaist~, Construction Manager

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-Westinghouse

A. Hogarth, Site Manager u .

  • Denotes those individuals attending the exit interview conducted on

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August 2, 198 Th'e NRC inspector made plant tours, both independently and with licensee and contractor personnel. These tours were to assess general housekeeping, plant cleanliness, protection of inplace plant equipment, fire protection, construction safety, plant status and general

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, . .s t-3-construction testing, and maintenance activitie'.s The areas toured included: Unit 1 -- Mechanical and Electrical Auxiliary Building (MEAB),

Fuel Handling Building, Diesel Generator Building, and Reactor Containment-Building; Unit 2 -- Reactor Containment Building, MEAB and Turbine Building, Balance of Plant (B0P), Emergency Cooling Pump Building, and

- laydown yards and warehouses. Within the areas observed, activities.were-acceptable with isolated anomalies being resolved in a timely manner by

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No violations or deviations were identifie . Licensee Action on Previous Inspection' Findings '

(Closed) Violation 498/499-8501-01' Failure to Follow Procedures Startup Training:

-This violation concerns a failure to follow procedures regarding training requirements for startup personnel. Several inconsistencies existed between the training files and the requirement of Startup Administrative Instruction (SAI) 10, "Indoctrinatio.n Training and Certification of. Test Personnel." Additionally, the startup manager failed to attend a required QA prograra indoctrination training session as required by Operations Quality Assurance Plan, Section >

The training files were audited by the licensee and. inconsistencies were rectifie All personnel requiring QA program indoctrination have been trained. The NRC inspector reviewed the original suspect training files plus randomly-selected additional training files and found no deviations from the requirements of SAI 10. The attendance roster of the QA program indoctrination training was reviewed and the required attendees were noted

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to have been present. The actions of the licensee are acceptable and this violation is considered close (Closed) IRC-123 Leak Detection System in the SIS / CSS Pump Cubicles:

This item concerns a 10 CFR S0.55(e) notification of July 1, 1982 (IRC-123), regarding the potential for flooding all three Safety Injection System (SIS) Containment Spray System (CSS) pump cubicles in the event a failure of moderate energy piping or a pump seal failur Several failure scenarios were developed where unmonitored flooding could occur to the point of rendering all three trains of the SIS an CSS inoperable at the

same tim Licensee and A-E analysis of the approved design indicated that a modification to the sump level alarm system would provide indication of flooding in any one cubicle. The level detectors were upgraded to seismic Category I instrumentation and the power supplies were upgraded tc Class 1E. A control room alarm was added on the Qualified Displa _

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-4-n Processing System (QSPS). Two independent Class 1E high level alarms are

provide Only one alarm must remain functional to provide the minimum leak detection capability. In the event of an alarm, adequate time (4 to 92.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />) -is allowed for. operator action, assuming a calculated leak ,

j rate of 50 to 100 gpm to mitigate the flooding before impacting operation

of the SIS / CSS cubicle equipment. Each cubicle has its own sump and 4 - duplex sump pumps. These sump pumps and associated piping from the cubicles are designated nonseismic equipment. Under worse conditions,

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operator action would be required to-isolate the source of cubicle i flooding.

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- The NRC inspector reviewed the IRC package, P&ID revision, purchase orders for seismic Category I instrumentation 'and FSAR revision. The revisions to these systems will be acceptable for the elimination of this failure

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[' mode for equipment located in the SIS / CSS Pump Cubicles. This item, IRC-128, is considered close (Closed) IRC-124 Unanalyzed Release of Radioactivity to the Environment:

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This item concerns a 10 CFR 50.55(e) notification of July 1, 1982

! (IRC-124), regarding the unanalyzed release of radioactivity to the environmentduringaLossofCoolantAccident(LOCA).

The scenario involved a postulated LOCA in which recirculation has been

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radiocctive water in that cubicle. This leakage would be transferred to

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the ficar drain tank in the MEAB via the cubicle sump pumps. Since the  ;

j HEAB is not served by an ESF filtration system, a pathway exists for an

unanalyzed release of radioactivity to the environment during a LOC [

[ ' The deficiency has been corrected by revising the system design to

preclude the automatic operation of the SIS / CSS pump cubicle sump pumps following a LOCA.

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The NRC inspector has reviewed the data package for IRC-124, including

> sump pump logic diagram 6Q06-9-Z-42313, Revision 11, FSAR revisionsfand

potential radioactive release data and find the resolution to the design
deficiency acceptable. This item is-considered close > (0 pen) Unresolved Item 498/499-8508-01 Permanent Plant Maintenance

. u This item concerns the greasing phase of the Permanent. Plant Maintenance

(PPM) pro Initially, the motor bearings for the Unit 1 and 2 Service

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Air (SA) gram. compressors (4 units) (not safety related) were found without

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grease, this is in conflict with the Maintenance Action Cards (MAC) that indicated the SA compressors had been greased every 6 months for the past

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s- 2 years. This finding plus similar information received from a allegation under review by HL&P prompted a licensee investigation of the entire PPM program.

l l- The initial phase of this investigation related to greasing of PPM

! equipmen A total of 551 pieces of permanent plant equipment were

!- examined with the following preliminary results:

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Total items: 551 Maintenance Deficiencies: 216 Percentage: 41%

Safety Related: 234~ Maintenance Deficiencies: 92 -Percentage: 39%

! The bulk of Maintenance Deficiencies (MD) were for overgreasing or

! commingling of greases. A series of activities were undertaken by_HL&P to determine the status of'the greasing of permanent plant equipment. These included a 100% grease check of all PPM equipment with a QC verifier for all safety-related equipment to record the "as found" condition, training sessions for all craftsmen, foreman, and supervisors involved in the PPM

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program on requirements and proper methods of greasing, and the l segregation and tagging for type of grease and grease equipment used in l ,

the PPM program.

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. This unresolved item 498/499-8508-01 remains open pending issuance of the

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" Grease Verification ~ Program Followup Report."

r Differential Settling of Unit 1 0 -

[ The NRC inspector reviewed Bechtel Specification 7Y310YS1000, " Power Block Geotechnical Monitoring," and all of the plots for this specification.

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Monitoring Type No. of Points Min. Frequency

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! Structural bench marks 160 monthly

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Borehole heave points 25 monthly Standpipe piezometer 190 weekly Pore pressure cells 35 periodically Snode extensometers 10 monthly l~ Horz. and Vertical Monuments 30 monthly

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The data was plotted several ways, including a point-by point historical, depending on when the point was established, which in some cases went as far back as 1973. The settling data ~ is reviewed 'either biweekly or monthly. An independent consultant, Woodward Clyde Inc.,'also reviewed

this data periodically.

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There have been no substantive additions or deletions of monitoring points

~during the past.3-years.. All points reviewed on a sampling basis by the

. NRC inspector indicated'a point-to point consistency and no indication of l significant differential settling was identifie The settling, as

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-6-indicated by point plots, was tracking the projections within the assumption made at the time of projection Some deviation is actual v projected, which is due to a delay in filling of the main cooling reservoir and continued dewatering of plant areas. The data reviewed by the flRC inspector was transmitted to Region IV office for further evaluatio No violations or deviations were identifie . Startup Testing The flRC inspector observed prerequisite testing on Class 1E and non-Class 1E electrical breakers located in Unit 1 MEAB and the Unit 1 Turbine Building. The testing was being conducted to approved procedures and the startup engineer was present. Equipment was properly tagged and all test equipment was within calibration. Both startup and maintenance personnel had a clear understanding of the test and acceptances criteri No violations or deviations were identifie ,

5. Exit Interview An exit interview was conducted on August 2, 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 inspectio . _ _ . - . _ - _ . _ _ -