IR 05000445/1993027

Insp Repts 50-445/93-27 & 50-446/93-27 on 930614-0730.No Violations Noted.Major Areas Inspected:Startup Test Results Evaluations & Followup on Previous Insp Findings

ML20056E746
Person / Time
Site:	Comanche Peak
Issue date:	08/10/1993
From:	Constable G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20056E742	List: IR 05000445/1993027 ML20056E741
References
50-445-93-27, 50-446-93-27, NUDOCS 9308250133
Download: ML20056E746 (7)

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l APPENDIX

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U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Inspection Report: 50-445/93-27 50-446/93-27 Licenses: NPF-87 NPF-89 Licensee: TU Electric Skyway Tower 400 North Olive Street, L.B. 81 Dallas, Texas racility Name: Comancho Peak Steam Electric Station (CPSES), Units 1 and 2 Inspection At: CPSES,' Glen Rose, Texas Inspection Conducted: June 14 through July 30, 1993 Inspector: H. F. Bundy, Reactor Inspector, Plant Support Section -

Division of Reactor Safety 1

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Approved:

MMenstable, Chief, Plant Support Section o

Date /

/J Division of Reactor Safety Insoection Summary f

Areas Insoected (Unit 21: Routine, announced inspection of startup test results evaluations and followup on a previous inspection finding.

Areas Inspected (Unit 11: No inspection of Unit I was performed.

Results (Unit 2}1

• The startup test results packages reviewed were well organize Identified problems and deficiencies had been resolved (Section 1).

• The licensee had conducted a data review at the 50 percent power level :

plateau and extrapolated and compared test results with plant performance predictions for higher power levels (Section 1). -

• An example of a weakness in the licensee's configuration control program >

involving the selection of equipment options was identified (Section 2).

9308250133 930818 PDR ADDCK 05000445 G PDR

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Results (Unit 11: Not applicabl Summary of Insoection Findinos:

• Inspection Followup Item 446/9302-03 will remain ope Attachments:

• Attachment 1 - Persons Contacted and Exit Meeting l * Attachment 2 - Initial Startup Test Packages Reviewed l

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-3-DETAILS 1 STARTUP TEST RESULTS EVALUATION (72301, 72600, 72608)

The objective of this inspection was to determine if the licensee had met !

technical and administrative requirements during the evaluation of completed initial startup (ISU) tests. Another objective was to determine that the licensee had conducted a data review and extrapolated and compared test results available at the 50 percent power plateau to plant performance predictions for higher power levels prior to continuing the power ascension program.

l 1.1 Discussion j

The startup test procedures selected for this inspection were subjected to one of two different levels of review. The inspector either verified the licensee's evaluation of the test results and separately evaluated the test results, or only verified the licensee's evaluation of test result In reviewing the test results, the inspector determined that the licensee had complied with the following administrative procedures:

• Procedure STA-818, " Conduct of ISU Testing," Revision 2

• Procedure STA-817, " Review, Approval, Ra;sion of and Changes to ISU Tests and Results," Revision 2 The inspector reviewed the ISU test packages listed in Attachment 2.

l Completed ISU tests reviewed during this inspection were at various stages of

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the licensee's approval process and were determined to be either complete, i 1.e. approved by the station operating review committee (SORC); review ,

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complete, i.e. approved by the plant manager, but not yet approved by the ;

SORC; partially complete (partial), i.e. complete for a specified plateau, l l

with additional levels remaining to be completed; or partially complete and '

l approved by the plant manager for that plateau, but not having SORC approval (partial review). The status of each test is listed in Attachment For partial completions, the plateau for which the data package was reviewed is also indicated in the status block.

! For the tests reviewed, all acceptance criteria had been satisfied. The test data was well organized. All identified problems and deficiencies had either been suitably dispositioned or were being properly tracked for resolution in accordance with the licensee's administrative procedures. Except for Test ISU-019B, which involved the plant computer software vartfication, there was not a substantial number of problems and deficiencies. For Test ISU-019B, there were 13 problem reports, of which 8 remained open. Those problem reports remaining open were being properly tracked for resolution in accordance with the licensee's administrative procedures. There were review criteria, but no acceptance criteria for this test.

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. 1-4-The licensee had appropriately reviewed data at the 50 percent power plateau t in accordance with Test Procedure 150-2408, "50 Percent Reactor Power Test Sequence," prior to continuing the power ascension program. Test results had been extrapolated to higher power levels and compared to predicted plant performance prior to proceeding with the power ascension. Although the Final

Safety Analysis Report did not require a formal data review at a lower power level, the licensee obtained a reactor core neutron flux map at less than 30 percent power and determined that the measured peaking factors satisfied ,

applicable limits when the data was extrapolated for 70 percent power operatio .2 Conclusiontt For the initial startup test results packages reviewed, the data was well organized and identified problems and deficiencies had been suitably resolve The licensee had conducted a suitable data review at the 50 percent power level plateau and appropriately compared test results extrapolated to higher power levels with plant performance prediction FOLLOWUP (92701)

(0 pen) Inspection Followup Item 446/9302-03: Conficuration Control Issues Identified Durina Preoperational Testina The inspector reviewed the licensee's corrective actions in response to configuration control issues identified during preoperational testing. The following technical evaluations (TEs) were reviewed:

• TE 93-34 - Vender Drawing Does Not Show Grounding Option for Solid State Protection System (SSPS)

• TE 93-99 - Design Documentation Does Not Show Whether the Interlock Screw Used to Prevent Local Operation of Reactor Trip Breakers is Installed  ;

The inspector found that TE 93-99, which was issued on January 8, 1993, had not been dispositioned by the license The licensee had performed an evaluation in response to TE 93-34 and i determined that no further action was required. The licensee's position was l

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that the connections selected were depicted on plant design drawings, and it was not necessary to show the selected connections on the vendor drawing. The licensee had selected the grounded option for the solid state protection

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system, which resulted in bypassing two installed fuses. This had been l discovered during preoperational testing and was not readily apparent by l direct observation of the vendor drawings.

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The inspector confirmed that plant design drawings did depict the option !

selected and he was concerned whether journeyman electricians would be able to '

make this determination. The absense of a clear indication on vendor drawings ,

of equipment options that have been selected for installation in the plant l appeared to be a weakness in the licensee's configuration control progra '

This issue will remain open pending further review of the licensee's drawing l control progra ,

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ATTACHMENT 1 ]

i 1 PERSONS CONTACTED  !

1.1 Licensee Personnel D. Allen, Manager, Startup Test . Bhatty, Senior Licensing Coordinator, Site Licensing ,

J. Dean, Electrical Working Foreman  :

J. Greene, Licensing Engineer, Site Licensing l D. Mayer, ISU Test Engineer i M. McCutchen, System Engineer, Engineering l R. Nickels, Maintenance Electrician )

P. Shah, Design Engineer, Instrumentation and Controls Engineering  ;

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1.2 NRC Personnel j

D. Graves, Senior Resident Inspector l R. Latta, Resident Inspector l In addition to the personnel listed above, the inspector contacted othe I personnel during this inspection perio ]

2 EXIT MEETIi4G l A telephone exit was conducted with Mr. Obaid Bhatty on July 30, 1993. The staff's position on Inspection Followup Item 446/9302-03 was further clarified in a telephone conference between Mr. Bhatty and Mr. Bundy on August 19, 199 ,

During these conferences, the inspector reviewed the scope and findings of the '

inspection. The licensee did not identify as proprietary, any information provided to, or reviewed by the inspector.

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ATTACHMENT 2 l

TEST RESULTS PACKAGES REVIEWED (72301)

ISU N SEQ TITLE STATUS 150-2258 36 Remote Shutdown Capability Complete ISU-016B 14 Incore Movable Detector Alignment Complete ISU- 32 Dynamic Steam Dump Control Complete 12058 15U-2208 35 Turbine Generator Overspeed Complete 150-226B 21 Operational Alignment of Partial, 50% ,

Temperature & N16 Instruments l l

NUC-120 05 Rod Swap Measurements Complete !

ISU-101B 25 Boron and Moderator Temperature Complete Coefficients Heasurements 15U-2048 18 Operational Alignment of Nuclear Partial, 75%

i Instrumentation NUC-104 04 Evaluation of Flux Distribution Partial, 50%

NUC-201 NUC-203 NUC-208 l 150-019B 28 Plant Computer Software Validation Partial Review, l 50% l l

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150-2028 31 Calibration of Feedwater and Steam Partial Review, i Flow Instrumentation at Power 50%

ISU-020B 29 Startup Adjustments of Reactor Partial, 50%

Control Systems ISU-212B 34 Piping Vibration Monitoring Partial , 13% l l '

l ISU-238B 37 Main Feedwater System Test Partial Review,

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ISU-282B 23 Containment & Penetration Rooms Partial Review, Temperature Survey 50%

ISU-211B 33 Loose Parts Monitoring Baseline Partial Review, l Data

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75%

! 150-240B 08 50% Reactor Power Test Sequence Complete l

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