IR 05000458/1990031

Insp Rept 50-458/90-31 on 901105-09.No Violations or Deviations Noted.Major Areas Inspected:Verification of Isolation Component Exemptions

ML20062G588
Person / Time
Site:	River Bend
Issue date:	11/19/1990
From:	Kelley D, Seidle W, Singh A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20062G579	List: IR 05000458/1990031 ML20062G577
References
50-458-90-31, NUDOCS 9011290332
Download: ML20062G588 (9)

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APPENDIX i

U.S. NUCLEAR REGULATORY COMMISSION-REGION IV l l

NRC Inspection Report: 50-45 Operating License: HPF-47 1

Docket: 50-458 Licensee: Gulf States Utilities 1 P.O. Box 220 J St. Francisville, Louisiana 70775:  !

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Facility Name: River Bend Station Inspection At: River Bend Station s'ite, St. Francisville, Louisiana Inspection Conducted: November 5-9,'1990 '

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Inspectors: bad @M M 3 O-A. Singh,\ Reactor' Inspector, Test Programs Date Section, Division of Reactor-Safety g II/t 9 /'t o

'D. L. Kelley, Reactor Inspector, Test Programs

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Date Section, Division of Reactor Safety Accompanying .

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Personnel: W. C. Seidle, Chief, Test Programs Section, Division of Reactor Safety (Hovember 8-9,1990)

Approved: IIfIt !f6 A W. C. Sei'd}e, hief, Test Programs Section Datei Division of R ctor Safet Inspection Summary Inspection Conducted November 5-9,1990~(Report 50-458/90-31)

Area Inspected: ' Routine, announced inspection _ involving the verification of isolation Hii5onent exemptions (VOICE).

Results: Within the area inspected, no violations'or deviations were identifie '

The inspectors concluded that the licensee had adequately addressed and implemented

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a program to' satisfy ~the re'quirements of. Appendix J to 10-CFR Part 50. In. addition, the inspectors found no discrepancies during the:100 percent visual inspection of accessible penetrations and boundary valves inside or outside the containment  :

-building. It was also.noted that the licensee had no exemptions to Appendix -J to 10 CFR Part 50 leak rate ' testing requirements. The, licensee had a stron training program .for the personnel. involved with the. Appendix J local leak rate -

testin PDR ADOCK 05000458 g PDC

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DETAILS i

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! PERSONS CONTACTED

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• E. M. Cargill, Director, Radiological Programs ,

• J. W. Cook, Technical Assistant / Licensing

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• T. L. Crouse, Manager, Administration

• P. D. Graham, Plant Manage E. Harper, local Leak Rate Test Coerdinato * K. Henry, Director Quality Operations-

• D. E. Jerragau, Assistant Plant Manager-

• G. R. Kimmell, Director, Quality Assurance (QA) Services R. H. Martin, Senior System Engineer:

• I. M. Malik, Supervisor, Operations, .QA . 2

• W. H. Odell, Monager, Oversight

• C, W. Welling, Process System supervisor-D..H. Williamson, QA Engineer '

• J. Venable, Operations Supervisor

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• E. J. Ford, Sent Resident Inspector D. P. Loveless,1 3ident Inspector

The inspectors also interviewed other licensee. employees during the *nspectio * Denotes those attending the exit meeting conducted on November 9,'199 . VERIFICATION OF CONTAINHENT INTEGRITY -(61715)'

The purposes of the inspection were to visually identify all-containment building penetrations and their. isolating components; to verify that the components were identified on current piping'and instrumentation diagrams or other 10 CFRdrawings;(Appendix Part 50 J) leak rate testing programs;~to determine-if theto determin criteria for exemptions were net, as set forth'in Appendix J; and to identify-any  !

isolating components:that had been givent test waiver approval by-the Office of i NuclearReactorRegulation(NRR). '

The inspectors performed a 100 percent walkdown of the accessible penetrations, which involved 109. mechanical:and 43 electrical-containment building

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penetrations ano.197 isolating components' associated,with these penetration The inspectors were not able to walkdown 12 penetrations and 13 associated isolating components because of radiological conditions. 'This inspection was performed inside and outside the containment building' including.the drywell, and

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L L wherever possible, the' inspectors traced associated system piping coming I through an identified penetration back to its designated containment building l l

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-3-isolation components on either side of the containment building wall. All of the penetrations, drawings, and associated procedures are listed in the Attachmen ;

it was noted during the walkdown that none of the penetrations were labele The inspectors also observed that four isolating components were without tag The licensee stated that in response to the maintenance team inspection findings (NRCInspectionReport 50-458/89-04), they had committed to walkdown five systems during each refueling outage and to provide the missing labels for those five systems. Regarding this commitment, the licensee has~ planned to label fiveLsystems prior to startup from this outage. The remaining associated i isolating components were, appropriately tagged. The inspectors compared piping 1 and instrumentation penetrations / isolation components for_ drawings with

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i Procedures STP-057-3703, " Primary Reactor Building Integrated Leak Rate Test,"

and STP-057-3800, " Local Leak Rate Test." The review did not identify any .. ' l discrepancies between the piping and instrumentation drawings and the procedure i The inspectors also noted that the licensee had established a program to. update the piping and instrumentation drawings regularl The' licensee stated that they did not have any exemptions to Type. A, B, o tests required by Appendix ~

No violations or deviations were identified in the review of this program are ' CONTAINitENT LOCAL LEAK RATE TESTING (LLRT) (61720)'

The purpose of this inspection was to verify that primary containment building local leak rate tests, as required by the River Bend Station Technical Specifications (TS), were performed to ensure that leakage through' testable l- containment building penetrations and isolation valves would not exceed the allowable leakage specified. This review included records, procedures, and independent calculations associated with the'LLRT Type C test During the inspection, the inspectors reviewed the primary containment building LLRT Pr_ocedure STP-057-3800, identified above.; The procedur was complete and satisf actorily stated the acceptance criteria for. each penetration. and the associated containment building isolation valve (CIV). Test procedure I instructions were concise and provided for independent' verification of test results and for system restoration. The inspectors reviewed records of LLRTs

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l conducted during 1987, 1988, and 1990. In conducting this review, the inspectors verified that corrective actions were taken on excessive leakage components and that appropriate retests were conducted on penetrations and CIVs. The cumulative-data-for containment building testable penetrations and CIVs were reviewed to verify that .;ntainment building local leak rate did not exceed the acceptance criteria. The LLRT results were well within the acceptance criteria as required by the T The inspectors also noted that the use of "N/A" [not applicable] was not prevalent in the data packages, and in several instances, a clear explanation was given in those cases where "N/A" was use .

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During this inspection, the inspectors also reviewed the training program for LLRT and the training records of the individuals who perforraed the LLRT test The training program was comprehensive and well documented. The individuals '

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niet the established qualifications. The inspectors concluded that the licensee

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had a strong training program for-the personnel involved with the Appendix J LLRT program.

No violations or deviations were identified in the review of this program area.

L EXIT MEETING

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l An exit meeting was held on November 9, 1990, with personnel identified in paragraph 1 of this report. At the' exit meeting, the inspectors summarized the scope and findings of the inspection. The licensee did not identify as proprietary any of the information provided to, or reviewed by, the inspectors.

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ATTAtlWEN H Penetration N System Type T'est ,P&ID No.- .

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, 1KJBZ6 Main Steam Line

A: -PID-3-1A'

1KJBZlB Main Steam Line .A' PID-3-1B~  !

IKJBZ1C; Main Steam Line A" PID-3-10 1KJBZ1D Main Steam Line A: PID-3-10 1KJBZ2 Turbine Plant = iPID-32-SC'

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Miscellaneous Drains ,

IKJBZ3A Feedwater Line C- PID-6-1 p IKJBZ3B- Feedwater Line C PID-6-1B- .

1KJBZ4 Reactor Water Clean A,-C: 71D-26-3A Up Discharge to Main ~ *

Condenser-IKJBZ5- Reactor Water Cleanup '

A ,1C ' PID-26-3B:

. Backwash Discharge 1KJBZ6 Reactor Water Cleanup' A JC > :PID-26-3B; Return to Feedwater-1KJBZ7 Reactor Water Cleanup C- :PID-26-3A Pump Suction 1KJBZ8 High Pressure Core; .C PID-27-4A ,

Spray Pump' Suction from Suppression Pool 1 .

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IKJBZ9 High Pressure' Core. Spray (A,C-l . .' P ID-27 -4 A to Reactor

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1KJBZ11 High Pressure Core Spra C PID '27-4A-

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L 1KJBZ12- Low Pressure Core Spray C PID-27-5 Pump Suction from

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Suppression Pool 1KJBZ13 Low Pressure Core- .C PID-27-5A Spray to Reactor IKJBZ15 RHR Steam Supply A, C' PID-27-6A and RCIC Steam Supply i

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e-2-i 1KJBZ16 RCIC Pump Suction C PID-27-6A from Suppression Pool 1KJBZ17 RCIC Turbine Exhaust .A. C PID-27-6A f to Suppression Pool 1KJBZ18A RCIC Pump Mininum Flow A,'C PID-27-6A .

By Pass to Suppression Pool f 1KJBZ18B RCIC Turbine Exhaust A, C - PID-27-6A 3'

Vacuum Breaker from - '

Above Suppression Pool-1KJBZ18C RCIC Turbine Exhaust A, C PID-27-6A Vacuum Breaker from Above Suppression Pool 1KJBZ19 RHR/RCIC Head - A, C PID-27-6A Supply 1KJBZ20 RHR anutdown Cooling Supply 'C PID-27-7A (SuctionIsolation)

1KJBZ21A LPCI to Reactor C PID-27-7A to'21C

1KJB23A RHR Heat Exchanger A PID-27-7A' ,

"A" Vent and Relief Valve Discharges to Suppression A Pool

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1KJB2313 RHR Heat Exchanger A- PID-27-7B

"B,"-Vent and Relief Valve Discharges to Suppression Pool  ;

IKJB24A RHR "A" and LPCS Test A, C PID-27-7A Returns and Minimum Flow Bypass-and Heat Exchanger Dump to Suppression Pool

IKJB24B RHR "B" Test Return A, C PID-27_-7B

! RHR Pump B, Minimum-

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l Flow Bypass and Heat-Exchanger Dump to Suppression-Pool 1KJB24C RHR-Return "C" Minimum A, C -

PID-27-7C Bypass Test Return to-Suppression Pool

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.l IKJB25A RHR Pump "A" Suction C -

PID-27-7A, 25B and 25C from Suppression Pool 78, and 7C respective 13 1KJBZ26 fuel tool Cooling A, C PID-34-2A and Cleanup Discharge 17JB227 Fuel Pool Cooling -

A, C PID-34-2A-and Cleanup Suction Line- t IKJBZ2s' Fuel Pool Purification A, C PID-34-2A Suction l

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IKJBZ29 CR0 Hydraulic System 'C PID-36-1A Supply 1KJBZ31 Containment and Drywell C- .PID-33-2A-and 33 Purge and Containment Hydrogen Purge Supply A.. PID-33-28-and Outlet Lines 1KJBZ35 Floor Drain Discharge C PID-32-9F IVJBZ36 Equipment Drain Discharge C PID-32-9P

'KJBZ41

. Fire Protection Header C PID-15-1C 1XJBZ42 cfARE i A43 l

l 1KJBZ44 Service Air Supply to C PID-12-2C Containment and Drywell 1KJBZ46 Instrument Air Supply C PID-12-1C to Containment and-Drywell 1KJBZ48 Reactor Plant Component A, C PID-9-1A Cooling Water Supply l

1KJBZ49 Reactor Plant Component A, C PID-9-1A Cooling Water Return 1KJBZ52A Service Water Supply C PID-9-10D and B 1KJBZ53A Service Water Return A, C PID-9-10D and B

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j 1KJBZ101 SPARE- q 1KJBZ102 Air Supply for Main PID-12-1C- 'i and 103 Steam Safety and I Relief Valve System' I 1XJBZ104', 105, SPARE l 106,-113, 114, 1 115,'116, 121, l 122, 125, and 1 126 1KJBZ129 Reactor Water Clean Up C PID-26-3A Pump Discharge 1KJBZ131 Ventilation Chilled A, C PID-22-14 Water Return 1KJBZ132 Ventilation Chilled A,' C PID-22-140 s Water Supply

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1KJBZ134 Condensate Makeup C PID-4-3C Supply 1KJBZ601A SPARE

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1KJBZ601B Reactor Plant Sampling A , C :- PID-21-2B IKJBZ601 SPARE C and D'

IKJBZ601E Containment and Dry.Well .C PID-33-2A Hydrogen Sample and Supply 1KJBZ602A Reactor Plant Ventilation:. N/A and B Differential Pressure Cell 1KJBZ602C SPARE

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1KJBZ602D PVLCS Pressure N/A Transmitter-l I

1KJBZ602F Reactor-Plant . H/A I

. Ventilation Differential 1 Pressure Cell l 1KJBZ603A Containment Leakage A, C PID-33-2 Monitoring Pressure Sensing  ;

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i 1KJBI603C Containment Leakage A, C -PID-33-2C Monitoring Pressure Sensing Line 1KJB26030 SPARE i E and F , ,

1KJBZ604A SPARE through F-1KJBZ605A Containnent Atmosphere N/A PID-33-2B and B, E Monitoring' Pressure H and F Service Line l IKJBZ605E Containment and Drywell A, C PID-33-2B ,

Hydrogen Supply Line 'i 1KJBZ605F Containnent and . A, C - PID-33-2B Drywell Hydrogen Sample Return Lin XJBZ606A Reactor Plant Ventilation 'N/A PID-33-2A "

r through F Differential Pressure Cell

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PROCEDURES Procedure N Title Date STP-057-3703 Primary Reactor Building Integrated Leak ' 3/9/89

. Revision 1 Rate Test STP-057-3800 Local Leak Rate Test' '5/21/90 TSP-0008 RCS Boundary and Hydro Leak Test Summation 8/13/90 Revision 2  :

ADM-0037 Equipment Identification and Labeling 8/10/90 !

Revision 3A-TSP-0001 System Engineering Personnel Training 8/17/90 ,

Revision 6 and Qualifications

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