IR 05000423/1985028
| ML20133F739 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/29/1985 |
| From: | Anderson C, Paolino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20133F728 | List: |
| References | |
| 50-423-85-28, NUDOCS 8508080414 | |
| Download: ML20133F739 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-423/85-28 Docket No.
50-423 License No.
CPPR-113 Priority Categor.v B
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Licensee: Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101 Facility Name: Millstone Nuclear Power Station, Unit 3 Inspection At: Waterford, Connecticut Inspection Conducted: June 3-7, 1985 Inspectors:
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T 7-2 7-8f R.J.faolino, Lead eactor Engineer date
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Approved by:
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C. Jf Anderson, Chief date Plant Systems Section, EB/DRS Inspection Summary:
Inspection on June 3-7, 1985 (IE Report No. 50-423/85-28)
l, Areas Inspected:
Routine, unannounced inspection by one regional based inspector of licensee work activities and documentation pertaining to the
installation of safety-related instrumentation systems / components and
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associated control circuits.
The inspection involved 34 inspection hours on j
site by one region based inspector.
f Results: No violations or deviations were identified.
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DETAILS 1.0 Persons Contacted 1.1 Northeast Utilities Company (NUSCO)
L. Chiarizia, Instrument Engineer
- J. Crockett, MP-3 Superintendent
- K.
Gray, Staff Assistant J. Chiloyan, Project Engineer R. McGuinness, Licensing Supervisor
- D. Miller, Jr., Startup Manager
- L. Nadeau, Assistant Project Engineer J. Nicosia, EQ Engineer G. Olson, Electrical Engineer
- S. Orefice, Project Engineer 1.2 Stone and Webster Engineering Company D. Aube, Logic Engineer R. Burnham, Engineer W. Emerson, Lead Licensing & EQ Engineer D. Evans, QC Inspection Supervisor
- R. Scannell, QA Program Administrator M. Sinha, Lead Structural Engineer K. Snyder, Records Supervisor R. Stone, Principle Instrument Application Engineer
- W. Vos, Senior Engineer L. Waldron, Principle Engineer 1.3 U.S. Nuclear Regulatory Commission
- T. Rebelowski, Senior Resident Inspector
- denotes personnel present at exit meeting 2.0 Facility Tour 2.1 The inspector observed work activities in progress, completed work and plant status in several areas during a general inspection of the site.
The inspector examined work items for obvious defects or noncompliance with NRC requirements or licensee commitments.
Parti-cular note was taken regarding the presence of quality control inspectors and indications of quality control activities through visual evidence such as inspection records, material identifications, nonconformance and acceptance tags.
In addition, the inspector interviewed craft and supervisory personnel encountered in the work area.
2.2 During the facility inspection, the inspector noted that the licensee was using a bayonet type (Litton-Veam CIR Series) electrical connector to achieve the environmental seal at the connector inter-face with control instrumentation. Upon close examination the
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inspector identified varying degree of tightness between the connectors.
Two connectors used in the feedwater level transmitter installation No. 3FWS*LT352 and the component cooling pipe level switch installation No. 3CCP*LS25B were visibly loose.
2.3 The inspector questioned the licensee representative, who was with the inspector at the time of discovery, regarding the effect of the LOCA environment on this type of connection.
The licensee indicated the connectors were used in Millstone 2 and had been qualified.
The licensee also indicated that Millstone-3 has a qualification program (No. 558-1657) to qualify the Litton-Veam CIR Series connector. Testing is scheduled to be completed in September, 1985.
2.4 Environmental Qualification of the Litton-Veam CIR Series connector is unresolved pending NRC review of qualifying test data.
(423/85-28-01)
3.0 Status of Previously Identified Items 3.1 (Closed) CDR Nos. 840014, 850004 & 850006 Licensee Identification Nos. SD-45, 50-71 & SD-73 respectively 3.1.1 Pertaining to the omission of reset from Auto Test feature of the Emergency Diesel Generator load sequences discovered during performance of test No. T-3405-I-101.
Close out is based on work observation involving modification of auto test to include reset feature of Emergency Diesel Generator load sequence, and review of following documents.
Engineering Design Change Request (E&DCR)
Nos. T-E-03725, & T-E-03698,
- Design Deficiency Report (DDR) Nos. 251, 255 & 267.
Vendor Modification Procurement Document No. 2424.600-427
- April,1985 retest of 3RPS*PNL-ESCA & 3RPS*PNL-ESCB per Test procedures No. T-3405-I-101, Appendix G, steps 4.4.3.3.18 thru 4.4.3.3.21 and 4.4.5.2
- Letters to the NRC Nos. F-0436A(SD-45), F-0700A (50-71) &
F-0716A(SD-73)
3.1.2 These items are closed.
4.0 Instrumentation (Systems / Components)--Work Observation 4.1 The inspector examined work performance, partially completed work and completed work pertaining to the installation of safety-related pressure and flow transmitters, safety related flow switches, associated instrument tubing and instrument valves to determine whether the requirements of applicable specifications, NRC require-ments and licensee commitments were met in the areas of receipt inspection material qualification, procurement, installation and quality control inspectio *
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4.2 Items examined for this determination include:
- Steam Generator 3RCS*SG1B Steam Line Pressure Instrument Nos. 3 MSS *PY52481 and 3 MSS *PY52482
- Steam Generator 3RCS*SG1B level transmitter 3FWS*LT552
- Component Cooling Water System Isolation Control Instrument No. 3CCP*LS25A
- Refueling Water Storage Tank No. 3QSS*TK1 level transmitter and indicator 30SS*LT932 & 3QSS*LI932
- Main Control Board No. 3CES*MCB-MB5
- Instrument Panel No. CES*1PNL122
- Specification for Instrumentation Installation, piping and tubing No. I-943 Revision 10 dated February 12, 1985
- Level Transmitter Nos. 3FWS*LT527(BY), 3FWS*LT528(BB),
3FWS*LT529(BB) & 3FWS*LT552(BW) located in Containment Structure, Area 1.
- Pressure Transmitter Nos. 3 MSS *PT524(BR), 3 MSS *DT525(BW) &
EMSS*PT526(BB) located in Main Steam Valve Building, Area 4.
- Procurement Document No. 2472.510-626
- Drawing Nos. EK-501109, EK-501110, EK-501111, EO-501112, EK-508027, EK-508028 & EK-508029
- Inspection Report Nos. IR-M3106260005 & IR-M3106620009
- Certificate of Compliance for Purchase Order No. 2472.510-662 4.3 In addition to the above as-built verification, the inspector verified instrument line slope by measurement and calculations, assuring compliance with construction drawing requirements.
4.4 No violations were identified.
5.0 Instrumentation (Cable and Termination)--Work Observations 5.1 The inspector observed work activities in progress, partially completed work and completed work pertaining to the installation and termination of electrical circuits associated with the instruments identified in Section 4 of this report.
The inspection involved tracing of electrical cable from the instrument to the control console and to the controlled function. Areas examined include cable type, size, routing, separation, termination, inspection and docu-mentation.
5.2 Items examined for this determination include:
- Instrumentation Cable No. 3RPS30X800 from Primary Plant Process 3RPS*RAK SET 3 to Main Control Board 3CES*MCB-MB2
- Elementary Diagram No. 8756026
- Wiring Diagram No. 3HC-3AED
- Conductor Termination and attribute list per IR-M301017ML-3-4114
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- Instrumentation Cable No.3CES10C124 from Main Control Board 3CES*MCB-MB1 to Main Control Board Termination Cabinet 3CES*TB_MB10
- Wiring Diagram No. E-3
- Conductor termination and attribute list per IR-010-17-3-1136
- Instrumentation Cable No. 3MSSBOX204 from Reactor Containment Penetration 3RCP*F11P to local Instrument Panel No. 3CES*IPNL122
- Wiring Diagram No. 36Q
- Instrumentation Cable No. 3FWS2WX818 from Instrument panel No.
3RPS*RAKSE12 to Reactor Containment Penetration No. 3RCP*G1P
- Wiring Diagram No. 3HB-36R
- Elementary Diagram No. 8756026
- Crimp tool No. 04621
- Specification No. E-350 Revision 7 dated November 13, 1984, for Electrical Installation 5.3 No violations were identified.
6.0 Instrumentation Quality Assurance Record Review 6.1 The inspector reviewed pertinent work and quality records for activities relating to the installations of safety related instru-mentation systems / components and associated electrical circuits to ascertain whether the records meet established procedure and whether the records reflect work accomplished consistent with NRC require-ments and FSAR commitments. Areas examined include receipt inspection, storage, nonconformances, qualification documents and inprocess inspection reports.
6.2 Items examined for this determination include:
- Nonconformance & Disposition (N&D) Report Nos. 4285, 4867, 5253, 5499, 5654 & 6236
- Conduct Support Log-Reel No S-1015 Frame Nos. 000169 & 000336
- ASC0 Test Report No. AQR-020184 Revision 0
- Inspection Report Nos. 1-4A01975, I-4A02356 & I-4A02261
- Cable Pull tickets for Cable Nos. 3FWS2WX818, 3FWS2WX819, 3MSSB0X203, 3MSSBOX204, 3CESN0X576, 3CES10C124, 3CCPN0C004, 3QSS3BX801 & 3QSS3BX802
- Conductor Termination sheets for above Itsted cables 6.3 The above documents, reviewed by the inspector, were accurate, current, legible, easily retrievable and signed by authorized cognizant personnel.
6.4 No violations were identified.
7.0 Unresolved Items 7.1 Unresolved items are matters about which more information is needed to determine whether it is acceptable or a violation. Unresolved item (s) are discussed in paragraph *
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8.0 Exit Meeting 8.1 The inspector met with the 1!censee and construction representatives (denoted in Detail, paragraph 1.0) at the conclusion of the inspec-tion on June 7, 1985, at the construction site.
The inspector summarized the findings of the inspection and the licensee acknow-1 edged the inspectors comments.
8.2 The licensee was informed that the paragraph on proprietary infor-mation would no longer appear in the cover letter and that it is the licensee's responsibility to inform the inspector of proprietary information.
There was none.
8.3 At no time during the inspection was written material provided to the licensee by the inspector.