IR 05000266/1979017
| ML19211D087 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/20/1979 |
| From: | Naker K, Streeter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19211D082 | List: |
| References | |
| 50-266-79-17, NUDOCS 8001160327 | |
| Download: ML19211D087 (4) | |
Text
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U.S. NUCLEAR 1EGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-266/79-17 Docket No. 50-266 License No. DPR-24 Licensee: Wisconsin Electric Power Company 231 West Michigan Milwaukee, WI 53201 Facility Name: Point Beach Nuclear Power Plant, Unit 1 Inspection At: Point Beach Site, Two Creeks, Wisconsin Inspection Conducted: October 15-19, 1979 f/k
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Inspector:
K. R. Baker
///8/71 N
h Approved By:
J. F. Streeter, Chief ti! W 79 Nuclear Support Section 1 Inspection Summary Inspection on October 15-19, 1979 (Report No. 50-266/79-17)
Areas Inspected: Routine, announced inspection of refueling activities.
The inspection involved 32 inspector-hours on site by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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- DETAILS 1.
Persons Contacted
- G. Reed, Manager, Nuclear Power Division
- J. Greenwood, Assistant to the Manager F. Rhodes, Operations Superintendent T. Deddins, Maintenance Superintendent J. Reisenbuechler, Instrument and Control Engineer J. Zach, Reactor Engineer R. Weedon, Health Physicist The inspector also held discussions with other members of the staff.
- Denotes those attending the exit interview on October 19, 1979.
2.
Preparations for Refueling The inspector verified the licensee had approved procedures for new fuel receipt, new fuel inspections, fuel transfer, refueling, and core verification. The inspector reviewed the content of these procedures against Technical Specification requirements, ANSI N18.7, and general accepted practices.
The inspector reviewed the quality releases and site inspection re-cords of the fuel used in this refueling. All deficiencies were resolved by the licensee prior to loading the assemblies.
The following records and procedures were reviewed:
RP-2A, Revision 6, 1/19/77, " Receipt of New Fuel Assemblies" RP-2B, Revicion 3, 10/30/75, " Fuel Assembly Visual Inspection" EP-2C, Revision 3, 9/18/78, "New Fuel Inspections" RP-3B, Revision 0, 10/13/75, " Fuel Shipping" WMTP1-2.1, Revision 0, 9/11/79, " Core Refuelin;, - 7" RP-1A, Revision 10, 1/23/79, " Preparation for Refueling" RP-1C, Revision 7, 1/4/79, " Refueling" New Fuel Inspection Records and Westinghouse Fuel Revision Qual-ity Release forms for fuel assemblies L-1 through 28, H-83 through 86.
No items of noncompliance or deviations were identified.
3.
Refueling Activities The following records were reviewed to determine if prerefueling activities and refueling activities were conducted as specified in the Technical Specifications and approved procedures:
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RP-1C, WMTP1-2.1, ORT-15, RP-1A, Control Room Logs and Unit 1
Log for October 11-14, 1979.
Observations c,f refueling related activities were made by the in-spector during the period of October 15-18, 1979. No direct obser-vations we e made of fuel handling activities.
No items of noncompliance or deviations were identified.
4.
Maintenance Activit;7s_
The inspector reviewed records of and observed maintenance activities to dete:mine if they were being conducted by qualified personnel and in accordance with approved procedures during the refueling outage.
The following procedures and records were reviewed:
PT R-1, Revision 3, 9/25/79, "Maia Steam and Pressurizer Safety Valve Setpoint Test" ICP 11.9, 10/17/79, " Reactor Protection System D. C. Relay Re-placement" Maintenance Request 22405, A SI Accumulator Level Transmitter LT-938 The inspector observed a portion of the activities associated with Maintenance Reque n 22405 and Procedure PT R-1.
No items of noncompliance or deviations were identified.
5.
High Radiation Areas The inspector observed work in high radiation areas.
From these ob-servations and discussions with the licensee it is not clear how the licensee is complying with the Technical Specification Section 15.6.11 requirement that for high radiation areas "A person or per-sons permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area."
Discussions indicate the licensee sometimes uses integrating alarming dosemeters, prior surveys with frequent update and stay times with continuous H.P. coverage to satisfy the provisions of Section 15.6.11.
This practice is consistent with the present version of the Standard Technical Specifications. The item was discussed with the licensee and the licensee stated he would assure that his practices are consistent with the exact wording of Section 15.6.11 or he would request a Technical Specification change. The inspector observed no specific instance where the licensee was in noncompliance with the exact words of the Technical Specification.
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The item is considered unresolved pending actions by the licensee and review by RIII personnel (266/79-17-01).
6.
Unresolved Items Unresolved Items are matters about which more information is required in order to ascertain whether they are acceptable items, Items of Noncompliance, or Deviations. An Unresolved Item disclosed during the inspection is discussed in Paragraph 5.
7.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on October 19, 1979. The inspector summarized the purpose and the scope of the inspection and the findings.
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