IR 05000382/1981026
| ML20031H428 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/08/1981 |
| From: | Randy Hall, Andrea Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20031H415 | List: |
| References | |
| 50-382-81-26, NUDOCS 8110270472 | |
| Download: ML20031H428 (9) | |
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e APPENDIX U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report: 50-382/81-26 Docket: 50-382 Category A2 Licensee: Louisiana Power and Light Company 142 Delaronde Street New Orleans, Louisiana 70174 Facility Name: Waterford Steam Electr;c Station, Unit 3 Inspection at: Waterford Site, Taft, Louisiana Inspection conducted: September 14-17, 1981
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Inspector:
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g A. R. Johnson, Reactor' Inspector, Engineering and fat 6
Materials Section Approved:
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d" / W R. E. Hall, Acting Chief ( Engineering and Materiais Dfits Section Inspection Summary Inspection Conducted on September ___14-17,1981 (Report 50-382/81-26)
Areas Inspected: Rcutine, unannounced inspection of safety-related construc-tion activities pertaining to installation, inspection, and documentation of Reactor Turbine Generator Control panels; observation of work and review of records for safety-related instrumentation cables; and follow up of a previ-oasly identifien unresolved item involving an NRR Fire Protection Review and Audit at the Waterford, Unit 3 site conducted September 9-10, 1981. The inspection involved 24 inspector-hours by one NRC inspector.
Results: No violations or deviations were identified.
8110270472 811009'
PDR ADOCK 05000382 O
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DETAILS 1.
Persons Contacted Princip61 Licensee Employees
- L. L. Bass, Project At Manager 4R. G. Bennett, Project QA Engineer
- C. J. De:areadx. Project Construction Coordinator R. Prados, Technical Services Other Personnel
- J. Gutierrez, QA Site Supervisor, Ebasco J. Hernandez, Senior QA Engineer, Ebasco M. Walsh, Engineering Site Support, Ebasco F. Brown, QC Electrical Inspector. Fischbach and Moore (F&M)
E. J. Ritzmann, Project QC Manager, F&M The NRC inspector also interviewed other licensee and contractor personnel including memebers of the engineering and QA/QC staffs.
- Denotes those attending the exit interview.
2.
Licensee Action on Previously Identified Inspection Findings (0 pen) Unresolved Item (50-382/80-08): Physical Separation of Safety-Related Instrumentation Cables in the Main Control Room Reactor Turbine Generator Control Panels.
During this inspection, the NRC inspector discussed, with the licensee's representative, the physical separation of electrical / instrumentation
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cabling within the Reactor Turbine Generator Control Panels CP-1, 7, 8, and 18 and compliance with Regulatory Guide 1.75, Revision 2; Industry i
Standsrd IEEE-384-1974; and Ebasco Internal Panel and Cable Separation Drawing LOU-1564, B-288.
This natter had been previously identified as an unresolved item during NRC Inspection 50-382/80-08 and subsequent follow-up Inspection 50-382/81-14. The licensee's representative, during Inspection 50-382/81-14, had indicated his intent to implement the previously identified separation measures by use of fire barriers, including foam barriers at bottom cabinet entries. The then pending NRR Fire Protection Review and Audit and the licensee's commitments to 10 CFR Part 50, Appendix R were necessary to define these separation requirements.
The NRR Fire Protection Review and Audit was conducted at the Waterford, Unit 3 site on September 9-10,19o1, by Messrs P. Sears (NRC) and R. Bruce
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(NRC Consultant). The NRC inspector reviewed the exit meeting minutes of September 10, 1981, as recorded by the licensee, and observed that the-2-
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above electrical / instrumentation cabling areas in the control panels were i
not as yet addressed. Discussion and status of the NRR Fire Protection
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Review and Audit will be included in the NRR CEB trip report, at which time the licensee's commitments to Appendix R will be established, and I
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the requirements for separation barriers resolved.
This matter is still considered unresolved.
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3.
Safety-Related Instrumentation Cable Terminations Internal to the Reactor
Turbine Generator Control Panels The NRC inspector inspected the Plant Protective System (PPS) Remote Control Panel (CP 7) in the main control room for instrumentation cable routing and termination at the field terminal blocks internal to the panel. This inspection was to assure that field installation was in i
accordance with Ebasco's Internal Panel and Cable Separation drawings, FSAR commitments, Ebasco specifications / procedures, LP&L procedures, F&M procedures, and industry standards. The NRC insnector traced out the total route of twenty-six safety-related terminating instrumentation cables, from the panel conduit bottom entry through internal wireways and bundles to the appropriate fanning strips / terminal blocks or panel
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equipment connectors. The cables were checked for proper conduit entry, l
color coding, wireway installation, wireway reuting, identification, correct size, grounding, shielding, and physical separation. The NRC inspector reivewed the quality related records (F&M cable pull and termi-nation slips, QC checklists for caole pulling and cable terminations /
splices, and QC system inspection reports) relative to the above twenty-six installed instrument cables, to ascertain whether these records reflect work accomplishment consistent with the established construction procedures.
Six of the above twenty-six safety-related cables inspected by the NRC j
inspector were vendor prefabricated connector type cables supplied by Combustion Engineering (CE) for purposes of interconnecting the PPS Operators Panel (CP-7) and the PPS Auxiliary P otective Back Panel (CP-22), using the lower cable chase spread area. The six cable assemblies were twenty conductor, twisted jair No. 20 AWG, with overall shield type cable.
Each was equipped wion 42 pin MS 3057-204 connectors (manufactured by Glen Air, Inc. No. G1513S2020A4A) on both ends. The NRC inspector reviewed the Ebasco Material Receiving Inspection Report (MRIR) and the F&M QC Receiving Inspection Checklist for proper' QC sign-off and acceptance. The Combustion Engineering Power Systems
" Certification of Equipment" for the Core Protection Calculator System (major components to the PPS Auxiliary Protective Back Panel - CP-22)
was also reviewed by the NRC inspector; this included the CE prefabri -
cated cables mentioned above.
During the inspection, the NRC inspector observed that the cable floor penetrations in the bottom of the PPS Panels did not bear the electrical conduit identification markings.
F&M's response was that the floor penetrations require no identification marking as they constitute part
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of the panel structure. The NRC inspector referred to the FSAR, para-graph 8.3, which does not address the identification marking require-ment on floor penetrations, but does address marking requirements for electrical conduit runs.
Ebasco Drawing.00-1564, B-288, Sheet 5, Revision 8 and Construction Procedure CP-301, Revision 4, paragraph 6.6 implement the FSAR requirements in that electrical conduit must be identified (by self-adhesive printed color coded markers) every 50 ft.
and at each end when passing through walls and floors. F&M uid request
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clarification via a " Request for Information" (RFI) fran Ebasco Site Support Engineering (ESSE) as to whether electrical floor penetrations should be identified by markers. The NRC inspector was satisfied that the licensee had met his commitments and FSAR requirements.
The following safety-related cables for the Plant Protection System (PPS)
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n;11ed and terminated by F&M were inspected:
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Cable No.
30189N-SMA
i 30191A-SMA
30189P-SMB 30191C-SMB 30191L -SMB 30191M-SMB
30621G-SMB
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30189Q-SMC 30191E-SMC 30194A-SMC 30194B-SMC
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30194C-SMC 30194E-SMC 30195E-5MC i
30195F-SMC 30189B-SMD
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30191R-SMD 306210-SMD
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30621R-SMD
'ollowing safety-related prefabricated cables by CE for PPS, pulled oy F&M were inspected:
Cable No.
301800-SMA 30189E-SMB 30i80F-SMB 30180L-SMC 30180Q-SMD 30180N-SMD The following F&M QC Checklists for cable pulling (including associated cable pull slips) for PPS were reviewed by the NRC inspector:
QCP-306,30189N-SMA QCP-306,30191A-SMA QCP-306, 30189P-SMA QCP-306,30191C-SMB QCP-306,30191L-SMB QCP-306,30191M-SMB QCP-306,30621G-SMB QCP-306,30189Q-SMC QCP-306,30191E-SMC QCP-306,30194A-SMC QCD-30'.,30194B-SMC QCP-306, 30194C-VT QCP-306,30194E-SMC-5-
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QCP-306,30195E-SMC QCP-306,30195F-SMC QCP-306,301898-SMO QCP-306,30191Q-SMD
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QCP-306,30191R-SMD QCP-306,30621Q-SMD QCP-306,30621R-SMD QCP-306,30180C-SMA QCP-306,30180E-SMB QCP 306, 30180F-SMB QCP-306,30180L-SMC QCP-306,30180Q-SMD QCP-306,30180N-SMD The following F&M QC Checklists for terminations and splices (including associated cable termination worksheets) for PPS were reviewed by the NRC inspectcr:
QCP-307,30189N-SMA QCP-307,30191A-SMA QCP-307,30189P-SMA QCP-307,30191C-SMB QCP-307,30191L-SMB QCP-307,30191M-SMB QCP-307,30621G-SMB QCP-307,30189Q-SMC QCP-307,30191E-SMC QCP-307,30194A-SMC QCP-307,30194B-SMC-6-
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QCP-307,30194C-SMC QCP-307,30194E-SMC QCP-307,30195E-SMC QCP-307,30195F-SMC QCP-307,30189B-SMD QCP-307,30191Q-SMD QCP-307,30191R-SMD QCP-307,30621Q-SMD QCP-307,30621R-SMD The following F&M QC System Inspection Reports for PPS safety-related cables were reviewed by the NRC inspector:
IR No.
Date Subject 308-57-192 4/14/80 Identification at terminated cables 307-68-225 6/16/80 Seismic qualification of conduit support 307-88-11 2/26/81 B/M call out on Ebasco Drawing R288 -
discrepancy / disposition cf short prefab cable / redirected cable due to conduit volume 159-71-41 7/18/80 Rerouting of cables inside panel The following F&M QC Receiving Inspection Checklist for PPS safety-related cable was reviewed by the NRC inspector:
No.
Date Description
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133-6563 2/13/81 Components for CP-22 Plant Protective
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System Panel (including vendor pre-fabricated cables to CP-7 Operators
Remote Panel)
The following Ebasco Material Receiving Inspection Report for PPS was reviewed by the NRC inspector:
No.
Date Description MRIR 80-04019 12/17/80 Components for Combustion Engineering Core Protection Calculator System
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The following Combustion Engineering Certification of Equipment for PPS was reviewed by the NRC inspector:
Contract No.
Ship No. Component Mfg.
Cert. Date
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9270
Core Protection Systems Engr. 6/25/80 Calculator System Labs (includes vendor prefabricated cables to CP-7 Operators Remote Panel)
The following Ebasco Drawings for PPS were reviewed by the NRC inspector:
Drawing No.
Revision Title LOV-1564, B-288, O
CP-7 Panel Cable Bundling Sheet 10G Details LOV-1564, B-288,
CP-7 Cable 'armination Sheet 10G-1 Sheets LOV-1564, B-288,
CP-7 Cable Termine 2*n Sheet 10G-2 Sheets L00-1564, B-288,
CP-7 Bundling General Sheet 10G-3 Notes The following Ebasco Field Change Request (FCR) for PPS was reviewed by the NRC inspector:
No.
Date Subject FCR-E-1915 1/13/80 Physical separation of cable bundles The following Construction Procedures were reviewed by the NRC inspector:
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No.
Rev.
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Installation of Electrical Conduit CP-306
Safety-Related and Non Safety-Related l
Cable Pulling f
Cable Terminations and Splices l
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The frilowing Ebasco site Procedures were reviewed by the NRC inspector:
No.
Rev.
Title ASP-II-2
Site Document Control No violations or deviations were identified.
4.
Exit Interview The NRC inspector met with the licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on September 17, 1981.
The NRC inspector summarized the purpose, scope, and findings of the inspection.
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