IR 05000336/1980018
| ML19351E984 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/09/1980 |
| From: | Ebneter S, Paolino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19351E983 | List: |
| References | |
| 50-336-80-18, NUDOCS 8012190655 | |
| Download: ML19351E984 (3) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-336/80-18 Docket No.
50-336 License No.
DPR-65 Priority Category C
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Licensee:
Northeast Nuclear Energy Company p.0. Box 270
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Hartford, Connecticut 06101 Facility Name: Millstone Nuclear Power Station, Unit 2 Inspection at: Waterford, Connecticut
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Inspection conducted: September 23-26, 1980 Inspectors:
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/4-7- [O R. J.
o' lino, Reactor Inspector date signed
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date signed date signed
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Approved by:
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S. D. Ebneter, Chief, Engineering Support dats signed Section No. 2, RC&ES Inspection Summary:
Inspection on September 23-26, 1980 (Report No. 50-336/80-18)
Areas Inspected:
Routine, announced inspection by a regional based inspector of. the fuel handling fan associated with the Auxiliary Building Ventilation System; Reactor Coolant Pumps associated with the RBCCW and the Boric Acid Tank heaters associated with the Chemical Volume and Control System to verify component installation as iden-tified and reported by the licensee in response to NRC Bulletin No.79-01B.
The inspec-tion involved 26 inspection hours onsite by one NRC regional based inspector.
Resul ts:
No items of noncompliance were identified.
Region I Form 12 (Rev. April 77)
8012190 N E
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DETAILS 1.
Persons Contacted Northeast Nuclear Energy Company R. Bates, Plant Engineer J. Kelley, Unit 2 - Superintendent E. Mroczka, Station Superintendent J. Opeka, System Superintendent - Nuclear Operations U.S. Nuclear Regulatory Commission J..Shedlosky, Senior Resident Inspector 2.
NRC Bulletin 79-01B Installation Verification The inspector reviewed Piping and Instrumentation Diagrams (P&ID's) and Wiring Diagrams pertaining to select systems outside the containment to determine by visual observation whether all active components associated with these systems have been identified by the licensee.
Systems / Components examined for this determination were selected from the licensee's submittal dated July 7,1980 containing Master Listing of Environmental Qualification of Electrical Equipment for Millstone Unit 2 which included the following:
Auxiliary Building Ventilation System:
Fuel Handling Fan MF-20 and
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Fuel Handling Dampers No's. HV-8141, 8275 and 8326.
Reference drawing No. 32021 sh.5.8.9 and 10 P&ID. No. 26029 Revision 2 Reactor Building Component Cooling Water System:
Pumps No's MPIIA,
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B, and C Reference drawing Nos. 30044 and 32015 sh.1, 2, and 3 P&ID No. 26022 sh. 1 of 2, Revision 7.
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Chemical Volume and Control System:
Boric Acid Tank Heaters No's
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141, 142, 143 and 144.
Reference drawing No. 32009 sh.15,16,17 and 18.
P&ID No. 26017 Revision 5 Area location dwg. No. SK-77-597-34036 sh 1-9
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The inspector verified that the components, cables, raceways, junction boxes and terminal boxes associated with.the systems referenced above were as identified in the licensee response to IE Bulletin No.79-01B.
The following exceptions were noted:
the electrical motors (2) used to actuate Fuel Handling Damper
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No's HV-8275 and HV-8326 were not identified.
the flow switch FS-8141 appeared to be an integral part of the
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Foxboro type 70 flow controller (S/N-2727885) and not the Foxboro type 50 listed by the licensee.
Conduit containing safety-related electrical wire leads from
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solenoid valve HY8141 to J-Box (Fire Zone Area 45) identified as 20741, a non-safety-related designation.
The discrepancy between the reported system / component identification and the actual installation is unresolved pending NRC review of licensee re-evaluation and submittal of corrected data in accordance with IE Bulletin 79-01B (050-336/80-18-01).
3.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable or items of noncompliance or deviations.
Unresolved item (s) identified in this report (paragraph 2) will be included in the licensee's final submittal due November 1,1980.
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Safety Evaluation Report The acceptability of the action taken by the licensee to correct the unresolved item (s) listed in paragraph 2 will be documented in the safety evaluation report (SER) that is to be written for Millstone 2.
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Exit Interview The inspector met with licensee representatives (listed in Detail, Para-l graph 1) at the conclusion of the inspection on September 26, 1980.
The inspector summarized the purpose and scope of the inspection and the inspection findings.
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