IR 05000382/1981014
| ML19350E833 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/05/1981 |
| From: | Randy Hall, Andrea Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19350E830 | List: |
| References | |
| 50-382-81-14, NUDOCS 8106230566 | |
| Download: ML19350E833 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION IV-Report: 50-382/81-14 Docket: 50-382 Category A2
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Licensee: Louisiana Power and Light Company 142 Delaronde Street New Orleans, Louisiana 70174 Facility Name: Waterford Steam Electric Station, Unit 3 Inspection at: Waterford Site, Taft, Louisiana Inspection Conducted: May 10-22, 1981 l#f5!Bl Inspector:
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A. R. Jatipsdn, Reagfpr. Inspector, Engineering and Date '
Maternfis Sectiert'
Other
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Accompanying
Personnel:
M. J. Roberds, Reactor Inspector Aida, Engineering and Materials
Section
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Approved:
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j], Atti~ng gef, Engineering and Materials R. E. Ha SectioV Inspection Summary:
Inspection on May 18-22,1981 (Report 50-382/81-14)
Areas Inspected: Routine, unannounced inspection of construction activities including inspection of Reactor Turbine Generator Control panels; observation of work and review of records for safety-related instrumentation and electrical cables; follow up of a previously identified unresolved item; and participation
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in meetings with the NRR Instrumentation and Centrol Systems Branch (ICSB), LPSL, and Ebasco regarding Safety Evaluation Report (SER) open items during the ICSB site visit on May 17-18, 1981.
The inspection involved 36 inspector-hours by one NRC inspector.
Results:
In the areas inspected, no violations or deviations were identified.
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OETAILS
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1.
Persons Contacted Principal Licensee Employees
- L. L. Bass, Project QA Manager
- B. P. Brown, Project QA Engineer
. B. M. Toups, Project QA Engineering Technician
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R. Prados, Project Engireer T. Brennan, Electrical Startup Engineer G. Wood, Project Engineer, Instrumentation and Control
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M. Srinivasan, Chief Power Systems Branch J. E. Rosenthal. I&C Safety Branch J. Elsbergas, I&C Consultant, Argonne Laboratory N. Kondic, Instrument Engineer, Consultant Other Personnel
- E. J. Ritzmann, Project QC Manager, Fischbach and Moore (F&M)
E. T. Thompson, QC Inspector, F&M
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R. Esnes, Site Support Engineer, Ebasco M. Walsh, Engineering, Ebasco V. Boynowsky, I&C Engineer, Ebasco R. Vidal, Electrical Engineer, Ebasco
- L. A. Sti"on, Manager, Site Quality, Ebasco K. Fojt, Licensing Engineer, Ebasco M. Horrell, Licensing Engineer, Ebasco B. Tessman, Project Engineer, I&C, Combustion Engineering J. L. Lewis, I&C Engineer, Combustion Engineering R. Lewis, I&C Engineer, Combustion Engineering R. Yanosy, I&C Engineer, Combustion Engineering The NRC inspector also interviewed other licensee and contractor personnel-including members of the engineering and QA/QC staffs.
- Denotes those attending the exit interview.
2.
Licensee Action on Previously Identified Insosction Findina (0 pen) Unresolved Item (50-382/80-31):
Installation of Safety-Related Electrical Penetrations.
During the course of the insoection, the NRC inspector had additional discussions with the licensee as to his responses discussed during the April 27 - May 1,1981, inspection regarding the use of AWS 01.1 field welds on the electrical penetration secondary side.
The NRC inspector reviewed Ebasco Engineering's resoonses and proposed solution-2-
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to revise Ebasco Specification LOU 1564.258 and Conax Drawing LOU 5817.1342 to reflect penetration secondary side welding performed in accordance with AWS 01.1.
Further information from Ebasco clarifying the need for the Code stamping on secondary side penetration assemblies (and if Code stamped, what safety implications are involved) is necessary before this item can be closed; therefore, this matter is still considered unresolved.
3.
NRR ICSB Site Inspection Visit - May 17-18, 1981 The NRC inspector participated in the NRR Instrumentation and Control Systems Branch site visit on May 17-18, 1981, following their instrumentation and control systems inspection and drawing review at Bethesda, Maryland, on April 15. 1981.
The NRC inspector participated particularly in meetings with the licensee and architect engineer where 20 Safety Evaluation Report (SER)
open items were addressed. Discussion and status of the SER open items will be included in the NRR ICSB trip report.
4.
Safety-Related Electrical and Instrumentation Cables and Termination -
Observation of Completed and In-Process Work The NRC inspector traced out the total route of six safety-related (Main Control Room PFcress Protection ESFAS) instrumentation and electrical cables to ensure thet the cables had been installed in accordance with FSAR, Ebasco specifications, LP&L orocedures, F&M procedures, and industry standards.
The cables were checked for routing, color coding, raceway installation, identification, separation, and correct size.
The following cables were inspected:
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30266G-SMO
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30267C-SMA 3026SA-SMA 30266G-SMB 30267C-SRS 30266A-SMA No violations or deviations were identified.
5.
Safety-Related Instrumentation Cable Terminations Internal to the Reactor Turbine Generator Control Panels The NRC inspector inspected the Reactor Turbine Generator Control panels in the main control room for instrumentation cable routing and termination
at the field terminal blocks internal to the panel to assure that field
installation was in accordance with Ebasco's Internal Panel and Cable Separation drawings.
The NRC inspector traced out the total route of six
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safety-related terminating instrumentation cables from the panel conduit bottom entry through internal wireways and bundles to the appropriate
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fanning strips /teminal blocks. The cables were checked for. proper conduit i
entry, color coding, wiraway installation, routing, identification, correct
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size, and physical separation.
It was observed by the NRC inspector that physical' separation of electrical /-
instrumentation cabling was not being maintained at this time within the
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~ Reactor Turbine Generator Control panels in accordance with Regulatory Guide 1.75, Revision 2; industry standard.IEEE-384-1974; hnd Ebasco Internal
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Panel 'and Cable ^ Separation Drawing LOU 1564 B288, Revision 0.
This matter.
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-has been previously identified as an unresolved item during NRC Inspection 50-328/80-08. The licensee indicated his intent to implement the previously identified separation _ measures by use of fire barriers, including foam
barriers at bottom entries, once the pending NRR Fire Protection Review and t
Audit is perfomed and the licensee's commitments to 10 CFR Part 50, Appendix R have been establis' $d.
This review / audit is scheduled upon 90%
electrical / instrumentation cat * pulling completion (early 1982) by the NRR Chemical Engineering Branch, Bethesda, Maryland.
The NRC inspector also reviewed the applicable site document control proce-
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dures governing updating and revision requirements to the Ebasco Internal Panel and Cable Separation drawings used in the above inspection of internal
. panel cable tracing /teminations. Tne current revisions (Revision 0) of drawings in force was issued on October 16, 1979. The drawings used by the
.NRC inspector had over 30 DCNs and FCRs issued against them.
It was necessary to obtain the latest and most current information red line marked up drawings from Ebasco Site Support Engineering (ESSE) to successfully perform the inspection. The_ applicable site document control procedures are weak in that
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they do not require timely revisions to drawings by Ebasco.
Ofscussions with ESSE personnel indicated that timeliness in site drawing revisions was too restrictive.
ESSE stated that Revision 1 to the Ebasco Internal Panel and
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Cable Separation drawings used during the inspection would be forthcoming within'one month's time.
Two successive QA audit reports in the area of controlling revisions to ESSE drawings were reviewed by the NRC inspector.
The audit report of May 19, 1981, identified the procedure weakness in that FCRs and DCNs are not required to be incorporated ii.to drawings or specifi-cations within a specific time period. The report conclusion recomended that a requirement be included in the procedure to establish criteria for incorporating FCRs and DCNs into drawings and specifications.
Both audit reports indicated that drawing and specification revisions to sita documents
.were being adequately controlled.
The following instrumentation cable routing and teminations internal to the Reactor-Turbine Generator Control Panel CP-8 were inspected:
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30530C-SA'
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30623G-SA 305130-SB
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30211G-SMD i
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300100-SMB
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31550G-SA8
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The following Ebasco Site Support Engineering drawings were reviewed by the NRC inspector:
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LOU 1564 B-288, Sheet 10H, Revision 0 LOU 1564 B-288, Sheet 10H-1, Revision 0 LOU 1564 B-288, Sheet 10H-2, Revision 0 LOU 1564' B-288, Sheet 10H-3, Revision 0 LOU 1564 B-288, Sheet 10H-4, Revision 0 The following Ebasco Engineering and QA documents were reviewed by the NRC inspector:
Procedure ASP III-2, Revision 0, November 14, 1980 Quality Assurance Report W30A-14108, May 20,1981 Quality Assurance Audit Report W3QA-9385, January 30, 1980
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No violations or deviations were identified.
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6.
Permanent Plant Equipment Removal and Reinstallation The NRC inspector also reviewed Ebasco administrative procedures governing permanent plant equipment removal for plant startup testing and reinstal-lation. These procedures are primarily for LP&L/Ebasco startup personnel prior to equipment release to LP&L (L?&L has their own startup procedures for the station startup governing equipment release to LP&L).
Both administrative procedures reviewed by the NRC inspector and discussed with Ebasco lacked proper controls in areas such as required docurentation, audits, and turnover responsibilities.
Both administrative procedures were '
currently undergoing revision by Ebasco.
The following Ebasco administrative procedures were reviewed by the NRC inspector:
ASP-IV-48, Revision G, March 10, 1981 ASP-IV-50, Revision C, December 1, 1980 No violations or deviations were identified.
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Exit Interview The NRC inspector met with the licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on May 22, 1981. The NRC inspector sumarized the purpose, scope, and findings of the inspection.
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