IR 05000220/1983019
| ML20024F444 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/16/1983 |
| From: | Sharon Hudson, Lazarus W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20024F437 | List: |
| References | |
| 50-220-83-19, NUDOCS 8309090388 | |
| Download: ML20024F444 (3) | |
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U.S. NUCLEAR REGtJLATORY COMMISSION
REGION I
Report No. 83-19 Docket No. 50-220 License No. DPR-63 Priority Category Licensee: Niagara Mohawk Power Corporation 300 Erie Boulevard West Syracuse, New York 13202 Facility Name: Nine Mile Point Nuclear Station, Unit 1 Meeting at: USNRC Region I, King of Prussia, PA Meeting Conducted August 10, 1983 Inspectors: [
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Approved by: ~Chie4( Reghor Projects Seftion 2C date'
Div. of Project and Resident Programs Meeting Summary:
Enforcement Conference on August 10, 1983 (Report No. 50-220/83-19)
Summary:
Special Enforcement Conference convened by NRC Region I management to discuss NRC concerns regarding failure to perform a piping analysis for a modification to the containment spray system (Report No. 50-220/83-16), failure to follow procedures for maintaining Reactor Building integrity, and failure to trip a reactor scram and main steam isolation trip system as required by Technical Specifications (Report No. 50-220/83-17). Senior licensee and NRC Region I management attended the meeting held in the Region I office.
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DETAILS 1.
Attendees Niagara Mohawk Power Corporation T. Lempges, Vice President, Nuclear Generation C. Mangan, Vice President, Nuclear Engineering T. Perkins, General Superintendent, Nuclear Generation T. Roman, Station Superintendent USNRC T. Murley, Regional Administrator R. Starostecki, Director, Division of Project and Resident Programs (DPRP)
H. Kister, Chief, Projects Branch No. 2, DPRP L. Bettenhausen, Chief, Test Programs Section, EPB L. Briggs, Senior Reactor Inspector, Test Programs Section W. Lazarus, Project Engineer, Reactor Projects Section 2C S. Hudson, Senior Resident Inspector, Nine Mile Point, Unit 1 D. Holody, Enforcement Specialist J. Craig, Enforcement Specialist, IE 2.
Discussions NRC Region-I management opened the meeting by discussing their concerns regarding three recent violations of NRC requirements, including failure to perform a piping re-analysis to determine the effects on the piping of the addition of four large air operators to valves in the containment spray test / bypass lines; failure to maintain required Reactor Building integrity in accordance with procedures; and failure to trip a reactor trip / main steam isolation valve trip system as required by Technical Specifications, when both detectors were inoperable.
The licensee representatives acknowledged the NRC's concerns and provided the following-information regarding corrective actions taken or planned to improve performance.
A piping re-analysis of the affected containment spray piping is
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being performea to determine if system integrity.may have been compromised during a seismic event. Additional corrective actions as described in Inspection Report 50-220/83-16 and CAL 83-07 are still in progress.
Information related to this action will be provided upon completion of the action.
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In the case of failing to replace the seal on the Reactor Building track bay outer door, before re-opening the inner door, the licensee stated that the procedural violation had been discussed with the auxiliary operator involved in the incident, and that signs had been
' stenciled on the outer track bay door to ensure that the requirement for replacing the seal is clearly brought to the attention of per-sonnel. A modification to the door or seal area is being considered, to make the removal of the seal unnecessary during periods of access.
The licensee reviewed the circumstances associated with the failure
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to identify the malfunction of main steam line high radiation detec-tors in one of the reactor trip / main steam stop closure system. It was stated that the incident had been reviewed with all shifts by the Operations Supervisor, to ensure that operator; are more alert in detecting instrument trends which may be indicative of a problem, and to ensure that conservative action is taken to comply with Technical Specifications when malfunction of a required instrument is sus-pected.
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Results The NRC acknowledged the licensee's comments and stated that they would be considered in determination of appropriate enforcement action. The meetiag was then closed.
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