IR 05000225/2005003

Insp Rept 50-458/85-18 on 850225-0503.Deviation Noted: Ranges of Display Instrumentation for HPCS Flow & RHR Svc Water Flow Contrary to Table 7.5-1 of Fsar,Amend 11, Dtd Jan 1984

ML20125A850
Person / Time
Site:	River Bend, Rensselaer Polytechnic Institute
Issue date:	06/04/1985
From:	Bess J, Jaudon J, Mullikin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20125A831	List: IR 05000225/2005003 ML20125A828 ML20125A836
References
50-458-85-18, NUDOCS 8506110220
Download: ML20125A850 (13)

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APPENDIX B J

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U. S. NUCLEAR REGULATORY COMMISSION

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REGION IV

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.NRC Inspection Report:

50-458/85-18 Construction Permit:

CPPR-145

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Docket:

50-458 Category:

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~ Licensee: Gulf States Utilities (GSU)

P. O. Box 2951 Beaumont, Texas. 77704

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Facility Name:

River Bend Station,(RBS).

lInspection - At: - River Bend Station,' 5t. Francisville, Louisiana Inspection. Conducted:- February 25 - May 3,1985

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R. P. Mullikin, Reactor. Inspector,' Project Date

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Section A, Reactor Project Branch'2-

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(/). E. Bess, Reactor Inspector, Project Date /

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Section B, Reactor _ Project Branch 2

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Approved:

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p,e A J. P..Jaudon, Chief,. Project Section A, Date

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Reactor Project Branch 1 e,

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.I 8506110220 850605 PDR ADOCK 05000458 G

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-2-Inspection Summary-

' Inspection Conducted February 25 - May 3l~1985 (Report 50-458/85-18)

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Areas Inspected:

Routine, unannounced inspection of electrical equipment and

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instrumentation installations, review of records and procedures, verification of electrical cable terminations and routing. review of QC personnel qualification records,' review of electrical separation, and review of licensee's' QA audits and surveillance. The inspection involved 188_ inspector-hours onsite and 26 inspector-hours in-office by two NRC

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Results: Within the areas inspected, one apparent deviation was identified (paragraph 2.b.(3)).

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r-3-DETAILS 1.

Persons Contacted Principal Licensee Personnel

• T. L. Crouse, Quality Assurance (QA) Manager

• B. E. Hey, Engineer, Licensing

• L. A. England, Supervisor, Nuclear Licensing W. H. Benkert, Senior QA Engineer B. Bemis, Electrical Maintenance QA Engineer Stone and Webster (S&W) Personnel

• R. J. Fay, Chief Inspection Supervisor R. L. Spence, Superintendent, Field Quality Control (FQC)

R. Otis, Senior Inspector, FQC The NRC inspectors also interviewed other licensee and contractor employees during the course of the inspection.

• Denotes those attending the exit interview.

2.

Observation of Completed Electrical Installations a.

Safety-Related Electrical Equipment The NRC inspector selected several examples of electrical equipment and components for examination.

The examination consisted of verifying that the field installation agreed with applicable design drawings, and that separation and protection requirements were being met.

The following equipment and components were inspected:

125V DC Standby Switchgear B(IENB*SWG018)

120V AC Standby Vital Regulated Power Bus A(1VBS*XRC14A1)

Vital Bus B Inverter - (IENB*INV018)

Hydroger. Recombiner Power Panel B - (1HCS*PWRS18)

480V AC Standby Load Center - (1EJS*LDC1B)

125V DC Standby Batteries and Racks - (IENB* BAT 01A)

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Diesel Generator Fuel Oil Transfer Pump - (IEGF*P1B)

Containment Unit Cooler - (1HVR*UCIA)

Standby Service Water Pump 2A - (1SWP*P2A)

Residual Heat Removal Pump C - (1E12*C002C)

Valve Operators for Motor Operated Valves (1E12*F073A,

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IE21*F005, 1SWP*MOV505A, 1SWP*MOV511A)

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,r iThe'above equipment'and components were found.to conform to design

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sdrawings.. Separation from redundant equipment, protection and

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'housekeepin'g were:found to be adequate.

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During the iinspection.of the motor operator'for valve 1E12*F073A, it

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.was discovered that the space. heater was inoperable.

This' condition

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was brought to the attention of a GSU maintenance department QA

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,( v =:q'uost recent inspection.of.these valve operators.,The GSU inspection.,

i engineer who promptly showed the NRC inspector the results off the' ;

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report'(85-IR-20180) showed that this space heater, along with'.

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iseveral others, were found to be. inoperative.

Since :this deficiency

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was discovered by GSU and.was being corrected through their

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phy'sw y :0 maintenance program, this item requires no followup by the NRC.

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No violations ~or deviations.were' identified in this area.

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' Safety-Related Instrumentation

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]N By direct observation, the NRC inspector inspected completed-

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work to: determine whether specific-instrument, components and

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associated. devices had been installed in accordance with NRC

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requirements. -The instruments inspected were as follows:

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LInstruments-Nodel No.

Serial No.

Rated Rance

'PT N052A 1152-406269 0-3000 Psig i

PT N0528 1152 l406103 0-3000 Psig.

PT N052C

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.407012-0-3000 Psig

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FT N003A 1152 97048R 0-750" H O

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FT N003B 1152-97057R 0-750"'H O s

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1152 97051R 0-750" H O

FT N056 1152 269146 0-150" H O

FT N005-1152 270544 0-750" H O

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PT N050

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272205 0-100 Psig r

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The NRC' inspector verified that the installation of.the

• referenced safety-related instruments met NRC requirements in the following areas:

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('a)' Identification and location (b) Protection and cleanliness preservation after installation.

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(c) Construction testing, including calibration and functional.

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(d) -Inspections, including the generation of inspection records.

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by qualified Quality Control (QC) personnel.

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(2) ' Radiation Monitoring Systems By direct observation, the NRC inspector inspected completed work to determine whether specific radiation monitoring equip-

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ment and associated devices had been installed in accordance with NRC requirements.

The equipment inspected were as follows:

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1 RMS* REY 13B

1 RMS* RE111

1 RMS* CAB 12

1 RMS* CAB 16A-The NRC inspector verified that the' installation of the referenced safety-related radiation monitoring equipment and devices met NRC requirements in the following areas:

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(a) Identification and location.

(b) Protection and cleanliness preservation after, installation (c) Construction testing including functional tests (d) Inspection, including the generation of inspection records by qualified QC personnel.

(e) Identification and documentation with respect to nonconforming components.

(3) Safety-Related Display Instrumentation The NRC inspector compared the actual installation of several examples of safety-related display instrumentation with Table 7.5-1 of the River Bend Station FSAR (Amendment 11, dated January 1984).

The following instrumentation were inspected:

FSAR System Parameter Stated Range Emergency Core Cooling HPCS Discharge 0-1,500 psig HPCS Flow 0-8,000 gpm LPCS Flow 0-8,000 gpm RHR Service Water Flow 0-10,000 gpm Containment Atmosphere Drywell Pressure 0-75 psia Monitoring Containment Pressure 0-75 psia Drywell Atmosphere 40-440 F Temperature Suppression Pool 0-200 F

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Temperature

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3 Contrary to.the above, the NRC inspector identified the display instrumentation for the High Pressure Core Spray (HPCS) Flow and

':Residual Heat Removal-(RHR) Service Water Flow as having actual ranges of 0-7,000 gpm and 0-8,000 gpm, respectively.

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This is a'n apparent deviation.

(458/8518-01)

Review of Qu'ality Records'(Electrical Installations)

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(1) Safety-Related Electrical Equipment Records The NRC inspector' reviewed the Stone and Webster (S&W) quality assurance inspection reports for the electrical equipment denoted in paragraph 2.a above.

Included in this review were

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receipt inspection and material

certification;c torage, handling and identification; s

installation inspection; and calibration and trip settini data

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(where applicable).

In addition, the qualification and trsining records for eight S&W field QC (FQC) inspectors that performed

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.the above inspections were reviewed.

The inspection reports were found to be~ complete, performed by qualified personnel, and

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reviewed by QA.

No violations or deviations were identified in this area.

(2) Safety-Related Instrumentation Records

The NRC inspector reviewed the calibration and data sheets for the following instruments:

Instruments System

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1 E22 PT-N050 Hi-Pressure Core Spray 1 E22 PT-N005 Hi-Prescure Core Spray 1 E22 FT-N056 Hi-Pressure Core Spray

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1 C71 PT-N052A Turbine 1st Stage Pressure 1 C71 PT-N0528 Turbine 1st Stage Prc.,ure 1 C71 PT-N052C Turbine 1st Stage Pressure In the areas reviewed, the records confirmed that proper calibration and instrument settings were made as specified, including use of specified procedures and test equipment.

Records also confirmed that calibration and related data were current, controlled and reflected " actual conditions."

No violations or deviations were identified in this area.

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~ Observation of Completed Electrical Cable Work-

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Safety-Related Electrical' Cable Terminations A

The NRC inspectors inspected the completed terminations of several

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safety-related cables.

The terminations were inspected in accordance with15&W conductor termination sheets, site drawings,'and site procedures. The attributes inspected were whether the terminations were performed in a craftsman-like manner and separation,'

~c identification, minimum bend radius, and protection requirements were met. :The terminations for the following cables were inspected:

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Cable No.

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1ENBARL600 Power 1ENB* BAT 01A~

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1ENBARL607 Power 1ENB* BAT 01A

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1ENBBBK500 Power-

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1ENBBBL600'

Power 1ENB* BAT 01B

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'1ENBBBL601 Power 1ENB*INV01B

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1ENBBBL602 Power IENB*SWG01B 1ENBBBL603 Power 1ENB*SWG01B

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1ENBBBL606 Power IENB*SWG018

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1EGFBBK001 Power

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1EHSBBL201 Power 1EJS*LDC1B

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1CSLNRK005 Power 1E21*F005 r.',

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1HCSBBC500 Power 1HCS*PWRSIB.

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1HVCBBL201 Power IEJS*LDC1B

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1HVCBBL202 Power 1EJS* LOC 1B

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1HVKBBL200 Power IEJS*LDC1B

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1HVPBBL200 Power IEJS* LOC 1B 1SWPARH300 Power ISWP*P2A

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1SWPARK023 Power 1SWP*MOV511A

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IICSCRK603 Power 1ES1*F019

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ICSLNRC005 Control 1E21*F005

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1EGSNBC704 Centrol 1EJS*LDC1B 1HVCBBC519 Control IEJS*LDC1B'

1HVKDBC509 Control 1EJS*LDC1B IICSNRC003 Control 1E51*F045

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1RHSNRC518 Control 1E12*F073A 1RHSNRC519 Control 1E12*F073A 1RHSRRC600 Control

- 1E12*F073A 1RHSARC073 Control IE12*F073A ISWPARC040 Control ISWP*MOV511A i

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.1CSHN0X400 Instrumentation 1E22*FTN005 E-1CSHN0X405 Instrumentation.

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ICSLNRX400 Instrumentation 1E21*FTN003

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1ENBBBX800 Instrumentation 1ENB*SWG01B 31HCSBBX400 Instrumentation 1HCS*PWRSIB

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-1HCSBBX407 Instrumentation 1HCS*PWRSIB-1RHSNRX414 Instrumentation IE12*FTN007A

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During the inspection of the terminations for cables ICSHN0X400, 1CSHN0X405, ICSLNRX400 and IRHSNRX414, the NRC inspector noted that the instrument cables had been spliced and not terminated as specified by issued termination tickets.

The licensee responded to this concern by informing the NRC inspector that the instruments had been installed with a sealed conduit (spliced) because the terminal

, blocks used on these panels were not qualified for use in containment.

The rework control forms used to document and track this work was reviewed by the NRC inspector.

All documentation appears to reflect the "as-built" status of the installed instruments.

The NRC inspector also observed that an actual termination ~for cable 1CSCRU603 for motor operated _ valve 1E51*F019 did not agree with the wiring drawing and the S&W termination sheet. A further investigation revealed that this was a probable drafting error and had been previously discovered by S&W FQC.

An engineering and design coordination report (E&DCR) had been issued and was pending incorporation into the affected design drawing.

This error was not identified when the valve was terminated but was discovered when

.another valve was inspected with the same wiring drawing.

Since there appears to be no safety significance to these findings and no others were discovered by the NRC inspector, this item is considered an isolated case.

The NRC inspectors observed that'the standby 480 volt load center (IEJS*LDC1B) and 125 volt D.C. standby switchgear (IENB*SWG01B) had an accumulation of dust and dirt within the cubicles.

This apparently was due to the floor penetrations within the cubicles not being scaled or covered to prevent the entrance of dust from construction activities on the floor below.

This was brought to the attention of the GSU maintenance department and two work requests (Nos. 472 and 473) were initiated to clean these cubicles when they

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are deenergized.

The NRC inspectors felt that there was no need to provide temporary covers for these penetrations at that time since the permanent seals were to be installed when the equipment was to be o

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deenergized.

Although, the cubicles had not received a thorough

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maintenance program', :The corrective action: proposed by GSU appears

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No violations' or deviations were identified in this area.

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b. _. Safety-Related Electric 51 Cable Routing.

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The NRC inspector selected severa'l power cables.to' verify that the

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' field installation agreed with'the S&W cable pull tickets.

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cables selected were. identified at each termination point-and then

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were traced.from'end to end.

The cable trays and conduits that the cables traversed were compared with the routing sequence on'the cable

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pull tickets.

The cables selected for examination were as follows:

t 1EHSBBL201 1HCSBBL200

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IENBARL600 1HCSBBL201 1EN8ARL607 1HVCBBL200:

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1ENBBBL600 1HVCBBL201 1ENBBBL601 1HVCBBL202 1ENBBBL602 1HVKBBL200

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No violations or deviations were identified in this area.

4.

Review of Licensee's QA Audits The NRC inspector reviewed several GSU QA audits of electrical cable and associated equipment.

The reports were examined to' determine whether the required audits were performed and whether. deficiencies identified were

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corrected (or being corrected) in a'. timely manner, and documented.

Also, the' audits were examined to ascertain whether the corrective action precluded repetition of the deficiency.

The audit documents examined were:

Site Audit No. 31 - W.0. No.12210.50; " Electrical Equipment

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Installation / Raceway and Cable Termination," dated September 28, 1983.

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Site Audit No. 33 - W.O. No. 12210.50, " Electrical Equipment

Installation and Inspection, Raceway and Cable Installation," dated

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March 9, 1984.

Site Audit No. 35 - W.O. No. 12210.50, " Electrical Installation and

Inspection," dated October 1, 1984.

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Site Audit No. 36 - W.O. No. 12210.50, " Raceway and Cable

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Installation / Inspection," dated January 4,1985.

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In addition to audits, GSU QA perform planned surveillances of work activities which are narrower in scope. The NRC inspector reviewed 14 recent scheduled surveillances of electrical cable work for the same attributes as stated above for audits. The following GSU QA surveillance plan and reports were reviewed:

CSEF 85-01-10 SEG 84-05-14 CSEF 85-02-02 SEG 84-06-01 CSEF 84-08-19 SEG 84-05-02 SEF 84-03-04 CSEG 85-01-09 I

SEF 84-01-13 CSET 85-01-03 SEF 84-05-03 CSET 84-10-09 SEF 84-01-18 CSET 84-08-12 No violations or deviations were identified in this area.

5.

Review of Nonconformance Reports The NRC inspectors reviewed several S&W nonconformance and disposition reports (N&Ds) relative to electrical cable, equipment, and components.

The documents were examined to determine whether the records were legible, complete, reviewed, and readily retrievable.

In addition, the records were reviewed to determine whether the nonconformances were adequately described and included the status of the corrective action or resolution.

The following N&Ds were examined:

N&D No. 4001 N&D No. 4008 N&D No. 4017 N&D No. 4018 N&D No. 5700 N&D No. 5710 N&D No. 5711 N&D No. 5720 N8D No. 5721 N&D No. 5749 N&D No. 5752 N&D No. 5756 N80 No. 5768 N&D No. 6013 N80 No. 6018 N&D No. 6019 N80 No. 6024 N&D No. 6026 N&D No. 6027 N&D No. 6032 N80 No. 6042 N&D No. 6059 N&D No. 6305 N&D No. 6310 N&D No. 6311 N&D No. 10366 N&D No. 10500 N&D No. 10514 l

N&D No. 10520 N&D No. 10525

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N&D No. 10538 N&D No. 10549 N&D No. 10614 N&D No. 10647 N8D No. 10687 N&D No. 10816 N&D No. 10877 N&D No. 10904 N&D No. 10941 N&D No. 10799 No violations or deviations were identified in this area.

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Observation of Electrical Separation The NRC inspectors inspected selected areas in the control building, auxiliary building, containment, and diesel generator building for conformance to electrical separation requirements. The River Bend Station is committed to NRC Regulatory Guide 1.75 and IEEE-384 which define the required separation for cables, trays, and conduits.

However, lesser separation requirements are allowed by IEEE-384 based upon analyses or tests. GSU has performed tests to allow smaller distances between circuits, and submitted a proposed FSAR change to NRR on January 28, 1985.

Formal acceptance by NRR of this change has not been received as yet.

The NRC inspectors performed their inspection based upon the proposed separation criteria.

If NRR does not allow the FSAR change then the NRC will have to perform another inspection of electrical separation.

During the inspection, the NRC inspectors found the following separation discrepancies:

Nonsafety-related flex conduit ICX016NAZ was within 1 inch of several

safety-related cables entering cabinet IENS*SWG1B from tray 1TC0518.

(Auxiliary Building - 98' El.)

Nonsafety-related cable ISPRDNX800 was within 6 inches of safety-related cable 1HVCBBC206 inside cabinet 1 ENS *SWG1B.

(Auxiliary Building - 98' El.)

Safety-related cables exiting conduit ICC020C and entering tray 1TK0010 were in contact with a 120 VAC lighting conduit above MCC E22*S002.

(Auxiliary Building - 115' El.)

These discrepancies were brought to the attention of GSU QA and S&W FQC.

An S&W QA inspection report (IR No. E5000833) was promptly initiated to correct the above items. The NRC inspectors noted that the discrepancies were in areas of ongoing construction activity and the lack of required separation could easily have occurred after installation and initial inspection. The final S&W FQC inspection of conduits and trays has not been performed as yet.

This gives further assurances that other separation violations will be detected and corrected.

Due to the large number of separation interactions inspected by the NRC, the identified items are considered isolated cases with no safety significance.

In addition, it was noted that the two safety-related flex conduits connected to junction box CRB-1162-CS (containment-162'El.) were of greater length than allowed. One conduit (ICL540BB) was 7 feet in length, but drawing EE-34YA-3 lists the maximum allowable support span of fire wrapped conduits to be 5 feet. The Appendix R fire wrapping had not been performed at the time of the inspection. The other conduit connecting to containment air handler 1HVR-UC1B was 6 feet long, but only 4 feet

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-12-6 inches of unsupported conduit is allowed per inspection plan R 1248000F0557.

This conduit had not been inspected by FQC but was scheduled to be done.

This item will be followed up by the closure of open item 458/8527-03 concerning the completion of all Appendix R fire wrapping as stated in NRC Inspection Report 50-458/85-27.

No violations or deviations were identified in this area.

7.

List of Documents Reviewed During the course of the inspection, the NRC inspectors reviewed various documents relative to electrical construction.

The procedures reviewed were found to be adequate for their intended purposes.

The following documents were reviewed:

RBS Spec. 248.000, Section 2, Revision 8. " Installation of

Equipment," dated December 18, 1984.

RPS Spec. 248.000, Section 3, Revision 8, " Installation of Raceway

and Cable," dated December 20, 1984.

S&W Quality Standard QS-10.51, " Electrical Equipment Installation,"

dated January 24, 1978.

S&W Quality Standard QS-13.12-RB, Revision 0, " Material / Equipment

Maintenance," dated December 7, 1983.

S&W Quality Standard QS-15.1, Revision B, "Nonconformance and

Disposition Repnrt," dated December 20, 1982.

S&W Quality Standard QS-10.52, Revision 0, " Raceway and Cable

Installations," dated February 16, 1978.

S&W Quality Standard QS-7.1, Revision D, " Receiving Inspection,"

dated June 15, 1979.

S&W Quality Standard QS-10.53, Revision 0, " Cable Terminations and

Connections," dated October 5, 1979.

S&W QA Directive QAD-2.5, Revision G, " Qualification and

Certification of Personnel Performing Quality Assurance Activities,"

dated October 19, 1983.

S&W QC Instruction QCI No. FR1-D14.1-02D, " Preparing and Reviewing

Quality Control Inspection Reports," dated January 14, 1985..

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-13-S&W Construction Department Standard CMP No. 9.2-4.76, " Construction

Methods Procedure for Installation of Electrical Equipment," dated April 1976.

.GSU Procedure QAI-2.3, Revision 1, " Planning, Scheduling and

Reporting QA Surveillances of Plant Activities," dated October 26, 1984.

S&W Construction Site Instruction CSI-1.12.1, Revision 9, " Storage

and Maintenance of Permanent Plant Equipment," dated October 1, 1984.

S&W Construction Site Instruction CSI-1.5.14, Revision 3 " Processing

Nonconformance and Disposition Reports," dated March 29, 1985.

S&W QA - Inspection Plan No. R1248000F0543, Revision 0, " Electrical

Equipment Installation," dated July 26, 1984.

S&W QA - Inspection Plan No. R1248000F0542, Revision A, " Electrical

Installation," dated December 17, 1984.

S&W QA - Inspection Plan No. R1248000F0518, Revision E, " Electrical

Cable Installation Inspection Plan," dated January 18, 1985.

S&W QA - Inspection Plan No. R1248000F0536, Revision G, " Electrical

Installation," dated January 9, 1985.

.

S&W QA - Inspection Plan No. R1248000F0557, Revision A, " Electrical

Installation," dated March 25, 1985.

S&W QA - Inspection Plan No. R1248000F0525, Revision D, " Electrical

Installation," dated January 9, 1985.

No violations or deviations were identified in this area.

8.

Exit Interview The NRC inspectors met with licensee representatives (denoted in paragraph 1) and R. E. Farrell, NRC senior resident inspector, on May 3, 1985, and summarized the scope and findings of the inspection.