IR 05000220/1986002

Mgt Meeting Rept 50-220/86-02 on 860211.Major Areas Discussed:Licensee Outage Schedule for Refueling & Mod Outage Expected to Begin on 860308

ML17055B308
Person / Time
Site:	Nine Mile Point
Issue date:	02/21/1986
From:	Linville J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML17055B307	List: IR 05000220/1986002 ML17055B304
References
50-220-86-02-MM, 50-220-86-2-MM, NUDOCS 8603030343
Download: ML17055B308 (14)

Text

U.S.

NUCLEAR REGULATORY COMMISSION

REGION I

Report No.

86-02 Docket No.

50-220 License No.

DPR-63 Priority Category C

Licensee:

Nia ara Mohawk Power Cor oration 300 Erie Boulevard S racuse New York 13202 Facility Name:

Nine Mile Point Nuclear Station Unit

Meeting At:

US NRC Re ion I Kin of Prussia Pa.

Meeting Conducted:

Februar

1986 (

Approved by:

.

C.

nville,

, Chief, Projects S ction 2C, Divi ion of Reactor Projects II e50-220/86-06.

dat

~Summar:

A management meeting was convened by NRC, Region I management to discuss the licensee's outage schedule for the refueling and modification outage scheduled to begin on March 8, 1986.

This meeting was scheduled as a

result of a Systematic Assessment of Licensee Performance (SALP) Report No.

50-220/85-99 recommendation to enhance NRC understanding of licensee outage plans and controls, and to improve licensee/NRC communications.

8603030343 860225 PDR, ADOCK 05000220

PDR

DETAILS Attendees Nia ara Mohawk Power Cor oration P. Francisco, Lead Licensing Engineer G. Gresock, Manager Nuclear Design E.

Leach, Superintendent Chemistry/Radiation Management T.

Roman, Station Superintendent R.

T. Essier, Planning Coordinator B. Wolken, Lead Modifications Engineer U.S. Nuclear Re ulator Commission W. Kane, Deputy Director, Division of Reactor Projects S. Collins, Chief, Projects Branch No. 2, DRP J. Durr, Chief Engineering Branch, Division of Reactor Safety (ORS)

P.

K. Eapen, Chief, Quality Assurance Section, DRS J. Wiggins, Chief, Materials and Processes Section, DRS R. Nimitz, Senior Radiation Specialist, Division of Radiation Safety and Safeguards (DRSS)

J.

McFadden, Radiation Specialist, ORSS J. Linvilie, Chief, Projects Section No.

2C, DRP C. Marschall, Resident Inspector, NMP-Unit

Discussions The licensee discussed the critical path for the fourteen week refueling outage scheduled to begin March 8, 1986 and the modifications scheduled for completion as shown in the Enclosure 2.

Discussions initially focused on work control measures such as the daily morning meeting to determine outage status, the establishment of engineer-ing and site drywell coordinators to control work in the drywell, radiation protection staffing and controls, and modification package status and controls.

Modifications of interest included the licensee's first attempt at Induc-tion Heating Stress Improvement, Emergency Condenser piping and valve re-placement, replacement of Intermediate Range and Source Range Monitoring Instrument dry tubes and replacement of the Containment Spray Heat Ex-changer s (CSHXs).

The licensee indicated that material procurement delays for the CSHXs could necessitate a weld repair contingency.

Other work items of interest to the NRC included the 10 year Inservice Inspections and the installation of an electrochemical potential device in the Reactor Vessel to measure hydrogen concentration in the upper vessel.

Before closing, di scussion moved to training for modification implementation and the implementation of the new Emergency Operating Procedures scheduled for

P C

I I

the startup from the outage, the benefits of the Management Analysis Cor-poration (MAC) review of Unit 1 management performance and the resulting action plan, the licensee's integrated living schedule and licensee ef-forts to reduce the number of reactor trips and safety system challenges.

3.

. Conclusion The meeting enhanced the NRC understanding of licensee outage planning and control activities and provided a means for NRC Region I to express their interests and concerns in these areas for licensee consideration.

It also served as a feedback device to get the licensee impressions of the benefits of the MAC Management review and action pla I

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Drywell Penetration Modification for Jet Thrust Encapsulated Vessel Samples ADS:

Master Inhibit Switch/Modify Confirmatory Logic

.

Containment Isolation un High Radiation Replace HFA Relays Diesel Generator Modifications Replace SRM/IRM Dry Tubes Reactor Vessel Hydrotest Heatup Appendix J Cleanup Isolation Valves Appendix J - Emergency Condenser Drain Line Test-Point Replace Emergency Condenser Steam Drain Line Control Room Emergency Vent System Upgrade Replace Containment Spray Heat Exchangers Equipment Qualification Relocate Technical Support Center (TSC)

RPS Component Supply Voltage Safety Parameter Display System Fire Protection Modifications Fire Dampers Fire Protection Sprinkler System Turbine Building Smoke Purge Fire Protection - Penetration Repairs Control Room Design Review Reroute 4160 Volt Feeder

/r'101-11 Reroute Core Spray System Control Cables Reroute Containment Spray Raw Water Control Cables 101*'02*

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107 108 111*

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118*

121 122*

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Replace Condenser Tubes 201 27.

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Emergency Condenser Line Modifications Service Water Radiation Monitor 202*

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Stub Tubes Long Range Fix 205 30.

Additional Station Service Transformer 206 31.

Scriba Sub Station Phase III 207 32.

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41.

44.

45.

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Steam Dryer Repair Turbine Test Valve Control Circuit Addition of Generator Step Up Transformer Replace 24 Volt Batteries Feedwater Pump Control Cicuitry ATWS Level Transmitters Motor Generator Set Reliability Hain Steam Line Radiation Monitor Cable Replacement Energy Management System (WS)

Containment Coating Induction Heating Stress Improvement (IHSI)

Continuous Air Monitor (CAH) System Upgrade Appendix J - Raw Water Intertie Control Circuit Changes Moisture Separator Shroud Bolts Reactor Recirculation Pump Monitoring Addition of Seventh Demineralizer In-Reactor Stress Corrosion Monitoring 214 215 217 218 219 220 222 227 228 302 304 306, 307 311 312 316 401 600

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