IR 05000220/1987008
| ML17055D139 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point |
| Issue date: | 08/06/1987 |
| From: | Bicehouse H, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17055D138 | List: |
| References | |
| 50-220-87-08-EC, 50-220-87-8-EC, NUDOCS 8708200224 | |
| Download: ML17055D139 (6) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Inspection No.
87-08 Oocket No.
50-220 License No.
OPR-63 Licensee:
Nia ara Mohawk Power Cor oration P ann se oa S racuse NY 132 Facility Name:
Nine Mile Point - Unit
Meeting At:
NRC Re ion I Kin of Prussia PA N
i C
d d: ~7 Prepared by:
.
U8 H. J.
icehouse, Radiation Specialist date Approved by:
W. J.
sci
, Chief, Effluents Radiation Protec
'on Section te Meetin Summar:
Enforcement Conference at NRC Region I, King of Prussia, Pennsylvania on July 7, 1987, to discuss the findings of Special Inspection 50-220/87-08.
The topics discussed at the meeting were the events associated with licensee's shipment No.
1 WS-0697, the licensee's investigation findings and the licensee's corrective actions.
The meeting was attended by NRC and licensee management and lasted about
hour.
8'7o 5000220 708i 2 PDR PDOCH, 0
@DR Q
Details Partici ants Nia ara Mohawk Com an C.
V. Mangan, Senior Vice President T.
E.
Lempges, Vice President, Nuclear Generation C.
L. Stuart, Superintendent, Chemistry
& Radiation Management A. F. Zallwick, Manager, Nuclear Licensing E.
W. Leach, Radiation Protection Manager G.
D. Wilson, Attorney M. Watterhahn, Attorney (Conner
& Wetterhahn)
M. J.
Hauf, Manager, Field Services (Waste Chem. Corporation)
Nuclear Re ulator Commission J.
M. Allan, Deputy Regional Administrator R.
R. Bellamy, Chief, Emergency Preparedness
& Radiological Protection Branch H. J.
Bicehouse, Radiation Specialist W. A. Cook, Senior Resident Inspector B. S. Davidson, Radiation Specialist R.
M. Gallo, Chief, Projects Branch
J.
M. Gutierrez, Regional Counsel D. J.
Holody, Jr.,
Enforcement Officer J. J. Kottan, Radiation Laboratory Specialist T. T. Martin, Director, Division of Radiation Safety
& Safeguards N.
S. Perry, Reactor Engineer
~Per ose The Enforcement Conference was held at the request 'of NRC Region I to discuss the problems identified during a special reactive inspection-conducted following a report of unusually high. radiation levels on two radioactive materials transport packages sent by the licensee to the Brunswick Steam Electric Plant on May 15-16, 1987.
The discussions at the meeting focused on the events from April 1, 1987, through May 16, 1987 related to the equipment shipped in the two packages, the deficiencies identified during NRC Inspection 50-220/87-08, their significance and causes, and the licensee's planned and completed corrective actions.
Discussions NRC management stated that this enforcement conference was requested to discuss the findings from the special safety inspection conducted May 26-27, 1987 (Report No. 50-220/87-08).
The licensee was asked to provide his perception of the findings presented in Report No.
50-220/87-08, additional qualifying information and 'his planned and
0'
completed corrective actions.
The licensee indicated that the facts (as presented in Report No. 50-220/87-08)
were in agreement with the facts found in the licensee's investigation.
4.
Licensee's Presentation Licensee management presented the findings from their review of the events associated with the shipment (including inhouse and onsite reviews at Brunswick Steam Electric Plant)
~
I
~
Licensee management described the corrective actions implemented and planned as a result of their investigation of the events described in Report No. 50-220/87-08.
These actions included:
~
An opening for technical specialist in radiation protection was filled on June 1,
1987, and that individual will provide additional professional oversight to shipping activities;
~
additional procedural guidance for surveying, packaging and shipping nonroutine material is being drafted;
~
appropriate personnel wi 11 be trained in the revised procedures; and
~
planned technical improvements to limit component dose rates, improve procedural guidance for making LSA determinations and improve non-fixed activity control.
Concludin Statements Licensee management concluded by stating their belief that the events described in Report No. 50-220/87-08 had been adequately reviewed and evaluated and that adequate corrections would be made to address the safety issues identified.
Licensee management requested reconsideration of apparent violations Nos.
50-220/87-08-02 and 87-08-03 by the NRC.
NRC Region I management acknowledged the licensee's request for reconsideration of the two apparent violations.
NRC Region I management stated that the licence would be informed of the need for and nature of appropriate enforcement action relative to the apparent violations at a
later tim '