IR 05000267/1988024

Insp Rept 50-267/88-24 on 880926-30.No Violations or Deviations Noted.Major Areas inspected:safety-related Surveillance Testing & post-mod Testing

ML20155J319
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/12/1988
From:	Bundy H, Mckernon T, Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20155J317	List: IR 05000267/1988024 ML20155J311
References
50-267-88-24, NUDOCS 8810250494
Download: ML20155J319 (4)

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APPENDIX

U.S. NUCLEAR D'GULATORY C0m !SSION ,

i hdGION IV NRC Inspection Report: 50-267/88-24 Operating License: DPR-34 :

Docket: 50-267 j

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i Licensee: Public Service Company of Colorado 2420 West 26th Avenue, Suite 15c -

j Denver, Colorado 80211 ,

e Facility Name: Fort St. Vrain l Inspection At: Platteville, Colorado Inspection Conducted: September 26-30, 1988 [

Inspectors: /d Dirt?

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g H. F. Bundj,'KeactOMnspector. Test Programs Section, Division of Reactor Safety

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M' T. O.Programs McKeftfon, Keettor Section, Inspector, Division Test Safety of Reactor Approved: M W. C. Seidle / Chief, Test Programs Section

/J z/d Date Division of Reactor Safety Inspection Surrrnary Inspection Conducted September 26-30, 1988 (Report 50-267/88-24)

Areas Inspected: Routine unannounced inspection of safety-related surveillance testing and post-modification testin Results: Within the two areas inspected, no violations or deviations were identifie G810250494 881017 POR ADOCK 05000267 0 PDC

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DETAILS Persons Contacted PSC ,

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• R. Williams, Jr., Vice President, Nuclear Operations

• D. Warembourg, Manager, Nuclear Engineering

• H. J. Ferris. QA Operations Manager

• H. E. Nieholl, Nuclear Design Manager

• M. H. Holines, Nuclear Licensing Manager

• N. Snyder, Maintenance

• Hugh O'Hegan, Outage Manager '

• H. Cappello, Central Planning and Scheduling Manager

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• L. Dee Scott, QA Services Manager

• F. J. Borst, Nuclear Training Manager

• J. M. Gramling, Supervisor, Nuclear I.icensing-Operations

• M. Block, Systems Engineering Manager

• H. L. Brey, Manager, Nuclear Licensing and Resources ,

• P. F. Tomlinson, Manager, Quality Assurance

• H. E. Deniston, Superintendent of Operations

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T. Staley, Nuclear Engineering M. Roush, Nuclear Engineering J. J. McCauley, Superintendent of 18C Maintenance R. W. Brunson, Supervisor, Systems Engineering l NRC

• E. Farrell, Senior Resident Inspector P. Michaud, Resident Inspector i

• Denotes those individuals attending the exit interview on September 30, 198 , Complex Surveillance Observations (61701)

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The purpose of this part of the inspection was to ascertain that ,

functional testing of selected systecis was perfonred in accordance with l regulatory requirements, applicable industry standards, and the licensee's l J procedures. To determine requirements and administrative controls, the 1

NRC inspector reviewed the following documents: i l *

Technical Specification (TS) 5.0, "Surveillance Requirements" -

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TS '? 5.4, "Instrumentation and Control Systems - Surveillance and j Caitir tion Requirements"

Station Manager Administrative Procedure (SMAP)-1, Issue 7. "TS i

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Surveillance Testing Program"

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Administrative Procedure G-7, Issue 20. "FSV Project Personnel ,

J Training and Qualification Programs"

Nuclear Plant Administrative Procedure (NPAP)-17, Issue 2. "Out of- ,

. Tolerance Report Form" ,

To ascertain compliance with requirements, the NRC inspector reviewed the following surveillance test procedures:

$R5.4.1.1.5.d-R, Issue 24,ProcedureDeviationReport(PDR) 88-0817, i

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"Wide Range Power Channel Calibration"

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SR 5.4.1.3.1.d-R1, Issue 13, PDR 88-0740, "Circulator Speed and ;

Feedwater Flow Refueling Calibration loop I"

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> The procedures appeared to satisfy all requireeents and were consistent with industry standards and good ergineering practice. However, Procedure SR 5.4.1.1.5.d-R. had eight PDRs attached, of which five had been issued prior to the start of the test. The NRC inspector observed that

parts of the procedure were confusing because of the PDRs and that a ,

' reissuance incorporating all the PDRs would have been appropriat ,

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k The NRC inspector verified that the test personnel assigned to perfonn

the above procedures were qualified in accordance with the licensee's administrative procedures. The NRC inspector witnessed partial '

performance of a work order to trouble shoot problems encountered in i performing Procedure SR 5.4.1.1.5.d-R and to perform applicable retestin ,

! All work observed was properly performed in accordance with the work order

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and the licensee's administrative procedures.

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No violations or deviations were identifie l

, 3. Modification Testing (72701)

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j During this portion of the inspection, the NRC inspector reviewed i i modification packages to include design evaluations, as-built drawings, f

installation instructions, cold-checkout tests, and functional tests. The ;

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following modification packages and associated controlled work i

procedures (CWPs) were reviewed: i L

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Changes Notice (CN)-2176, "SLRDS - Tie-in Console to PPS System," ;

i CWPS86-295, 86-296 .

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CN-2283, "Install SLRDIS Control Room Cabinets " CWPs86-260,86-261 l

l * CN 2190. "$LRDIS Bypas" Valves Modifications," CWPs65-193,86-194 !

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CN-1976, "Replacement oi bolts on the circulators to avoid corrosion"

• CN-1848, "Install metering sample Valve in sample line to grab sample facility" .

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i 4 i The NRC inspector reviewed the above documents to verify that *

modification work packages included wiring continuity and separation checks, cleaning end flushing requirements, and connection of support systems. The licensee properly reviewed completed test procedures to verify test results were within the stated acceptance criteria and that  !

cited deviaticas were resolved and retesting accomplished. Furthermore, the NRC inspector verified that the licensee's functional tests were i satisfactorily completed, reviewed, and quality control verification of l critical step completion had been accomplished. Test records had received  !

an independent QA audit and any changes to the test procedures were reviewed and approved in accordance with the Techaical Specification. In addition, the NRC inspector verified that the level of perfonnance for the ,

steam leak rupture detection isolation system (SLRDIS), CNs 2176, 2283, <

and 2190 were as described in license amendment No. 50, dated June 24,

198 , Within the scope of this inspection, no vic ations or deviation were

identifie . Exit Interview i J The NRC inspectors met with licensee personnel (denoted in paragraph 1) on  ;

, September 30, 1988. The NRC inspectors summarized the scope and findings -

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

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