IR 05000266/1979016
| ML19211D334 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/14/1979 |
| From: | James Smith, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19211D332 | List: |
| References | |
| 50-266-79-16, 50-301-79-18, NUDOCS 8001170566 | |
| Download: ML19211D334 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-266/79-16; 50-301/79-18 License No. DPR-24; DPR-27 Docket No. 50-266; 50-301 Wisconsin Electric Power Company Licensee:
231 West Michigan Milwaukee, WI 53201 Point Beach Nuclear Power Plant, Units 1 and 2 Facility Name:
Point Beach Site, Two Creeks, WI Inspection At:
Inspection Conducted: September 24-28, 1979
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// -/ 3 - 77 Inspector: J/ J. D. Smith R Fidwik
//-N-If Approved By:
R. F. Warnick, Chief Reactor Projects Section 2 Inspection Summary Inspection on September 24-28, 1979 (Report No. 50-266/79-16; 50-301/79-18)
24-28, 1979 to Routine, announced inspection on September review design changes and modifications, bulletin action, circular action and Areas Inspected:
The inspection involved 33 inspector-hours onsite by independent inspection.
one NRC inspector.
No items of noncompliance or deviations were identified.
Results:
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DETAILS 1.
Persons Contacted
- G. A. Reed, Manager, Nuclear Power Division
- J. Greenwood, Assistant to the Manager F. T. Rhodes, Operations Superintendent T. F. Deddins, Maintenance Superintendent C. H. Harris, Radiochemical Engineer J. Reisenbuechler, Instrument and Control Engineer
- F. Zeman, Office Supervisor The inspector also talked with and interviewed members of the oper-ations and maintenance section.
- Denotes those attending the exit interview on September 28, 1979.
2.
Bulletin 79-06 Interim Action Followup The majority of the licensee's response to Bulletin 79-06 and 79-06A (Revision 1) item 2, will be submitted to NRC by December 31, a.
1979 when the Westinghouse Owner's Group expects to complete its review of this bulletin item.
In the interim the licensee committed to implement interim administrative actions to address This commitment was reviewed by and has the concurrence this item.
Due to of the NRC Office of Nuclear Reactor Regulation (NRR).
the imminent re-testing of operators the inspector visited the plant primarily to ensure that these interim administrative actions had been imp'emented and fully promulgated to the The licensee had implemented this bulletin item by operators.
Following issuing Speccial Order PBNP 79-18, Revision O.
discussions with NRR and with Mr. F. Rhodes, Point Beach Oper-the Special Order was revised to the ations Superintendent, inspector's and NRR's satisf action and promulgated to the This operations staff as Special Order PBNP 79-18, Revision 1.
fulfilled the licensee's interim committment to item 2 of Bulletin 79-06, the inspector notified NRR and operator license examinations were scheduled for the following week.
The inspector, at the request of NRR, discussed the licensee's b.
response to item 11 of the subject bulletin concerning notifi-NRR's cation of the NRC if an event occurs at the plant.
concern was that a definitive threshold had not been established I discussed the licensee'n policy in the licensee's responre.
This policy was promulgated via memorandum titled with NRR.
24, 1979 and was distributed to
" Incident Reporting" on May duty and call superintendents, group heads and duty management, shift supervisors.
In light of this memorandum and the past-2-1763 256
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history of the licensee's reporting practice to IE, NRR was satisfied that the procedures in place satisfy item 11 of the bulletin.
3.
IE Circular Followup The inspector reviewed the licensee's management evaluation and imple-The licensee's mentation of IE Circulars through circular 79-17.
evaluation and implementation of the circular information applicable to the Point Beach facility through circular 79-17 was acceptable.
4.
IE Bulletin Followup The inspector on a continuing basis, is reviewing the licensee's During the inspection evaluation and implementation of IE bulletins.
the inspector reviewed the licensee's evaluation and implementation of Work 79-09, 79-10 and 79-11, and were found acceptable.
IE Bulletin is continuing on the remaining bulletins by the plant staff, corporate The licensee activities in this area can be staff and outside vendors.
best categorized as a " maximum effort."
5.
Design Changes and Plant Modifications The following design changes and plant modifications, and internal review and approval procedures were revieved to ascertain compliance with the requirement of 10 CFR 50.59, PBNP Technical Specifications No items of concern and Administrative Procedures as applicable.
were identified.
Vent Sample Probe Fan Fila and B Stack (Unit 1 Purge M-552 Exhaust)
Pressurizer Relief Valve Discharge Line, Snubber Support, M-554 Mechanical Stiffening Replacement of Solenoid Valves for Main Steam Isolation E-200 Valves IC-192 Safeguards Logic Modifications IC-194 Safeguards Instrumentation Power Supply Modification IC-199 Safeguards Reset Circuitry Modification 6.
Spent Fuel Pit The spent fuel pit leak-off collection system and collection analysis records were ir. cected.
No items of concern were identified.
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7.
Exit Interview The inspector met with the licensee's representatives (denoted in para-graph 1) at the conclusion of the inspection on September 28, 1979.
The inspector summarized the scope and findings of the inspection.
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