IR 05000029/1993002

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Insp Rept 50-029/93-02 on 930202-0320.No Violations Noted. Major Areas Inspected:Plant Operations,Radiological Controls,Emergency Preparedness & Quality Verification
ML20035C706
Person / Time
Site: Yankee Rowe
Issue date: 03/30/1993
From: Eugene Kelly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20035C704 List:
References
50-029-93-02, 50-29-93-2, NUDOCS 9304090021
Download: ML20035C706 (7)


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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Repon No:

50-29/93-02 i

Docket No.

50-29

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Licensee No:

DPR-3 Licensee:

Yankee Atomic Electric Company 580 Main Street Bolton, Massachusetts 01740-1398 Facility Name:

Yankee Nuclear Power Station t

Inspection at:

Rowe, Massachusetts Dates:

February 2 - March 20,1993 Inspector:

Neil Perry, Senior Resi - Inspector

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. Approved by:

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Eug'ene

. Kelly, Chief eactor Projects Section 3A Date Summary:

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Areas Insoected: Plant operations, radiological controls, emergency preparedness, engineering j

and technical support, and safety assessment and quality verification.

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Results: See Executive Summary

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9304090021 930331 PDR ADOCK 05000029 G

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EXECUTIVE SUMMARY i

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Yankee Nuclear Power Station i

Report No. 50-29/93 42

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Plant Operations

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Plant equipment, housekeeping, and response to a fire protection system pipe break were good.

Radiological Controls j

Activities associated with the shipment of the control rod follower pieces were conducted well.

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Improved performance was noted in health physics practices.

Emergency Preparedness The first practice emergency drill using the Defueled Emergency Plan was successfully conducted, and training goals were met.

i Engineering and Technical Support

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The initial operation of an auxiliary service water pump was acceptable.

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Safety Assessment and Quality Verification i

An improved trend in the use of safety devices was observed in response to weaknesses previously identified with safety practices for activities around the spent fuel pit.

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TABLE OF CONTENTS EXECUTIVE SUMMARY......................................ii

TABLE OF CONTENTS.......................................iii

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1.0 FACILITY STATUS

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2.0 PLANT OPER ATIONS (71707)............................... 1

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2.1 Plant Housekeeping................................... I 2.2 Fire Protection System Pipe Break......................... 2 3.0 RADIOLOGICAL CONTROLS (71707).......................... 2 3.1 Control Rod Shipment

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3.2 Health Physics Practices............................... 2

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4.0 EMERGENCY PREPAREDNESS (71707)........................ 3 4.1 Emergency Drill.................................... 3

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t 5.0 ENGINEERING AND TECHNICAL SUPPORT (71707)............... 3 5.1 Auxiliary Service Water Pump........................... 3

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6.0 SAFETY ASSESSMENT AND QUALITY VERIFICATION (71707)........ 3

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6.1 Safety Practices

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7.0 MANAGEMENT MEETINGS (30702)

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7.1 Preliminary Inspections Findings..........................

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7.2 NRC Inspections.................................... 4

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7.3 Other Meetings..................................... 4

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DETAIIS 1.0 FACILITY STATUS The Yankee Nuclear Power Station has been shut down since October 1,1991, and the reactor vessel defueled since February 15, 1992. The plant has operated under a Possession Only License (POL) since August 5,1992. Under the terms of the POL, YAEC may perform additional decontamination work, disassemble components and store and ship spent fuel as long as the activities do not foreclose decommissioning options or substantially increase the cost of decommissioning. An NRC approved Certified Fuel Handler program replaced the Licensed Openator program and was implemented in July 1992. The Defueled Security Plan was approved on November 24, 1992. YAEC implemented the Defueled Security Plan and the Defueled Emergency Plan on December 19,1992, after appropriate procedures were approved and implemented, and after completion of required training.

On January 1,1993, plant staffing at the Yankee Nuclear Power Station was reduced to 59 full time, permanent, employees. Approximately 65 employees had their employment severed on December 31, 1992.

Since announcement of the permanent shutdown of the facility, approximately 61 employees found employment with other companies,9 employees retired, and 25 employees were relocated to Yankee Nuclear Services Division (YNSD). No funher staff reductions are anticipated by YAEC throughout 1993.

On March 12, 1993, the YAEC Board of Directors decided to proceed with the removal of certain components (4 steam generators, pressurizer, and reactor vessel internals) for disposal in South Carolina by June 1994. Asbestos insulation removal is expected to begin in April, and continue for approximately 2 months. Component shipments could begin as early as the Fall of 1993.

2.0 PLANT OPERATIONS (71707)

j The inspector ensured by direct observation that plant equipment was operated and maintained safely and in conformance with license and regulatory requirements. Control Room staffing met all requirements.

Operators were found to be alert, attentive and responded properly to

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annunciators and plant conditions. Operators adhered to approved procedures and understood the reasons for lighted annunciators. The inspector reviewed control room log books for trends and activities, observed control room instrumentation for abnormalities, and verified compliance with Technical Specifications. Accessible areas of the plant were toured; plant conditions,

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I activities in progress, and housekeeping conditions were observed. Additionally, selected valves and breakers were verified to be aligned correctly.

I 2.1 Plant Housekeeping i

During this inspation period, the inspector periodically toured the facility to verify that plant equipment was being maintained as required, and that general housekeeping was commensurate with activities being conducted in the area. Plant equipment and houseke ping were found good in all areas of the plant. Nu weaknesses were observed.

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2.2 Fire Protection System Pipe Brrak

On March 19,1993, a 10 inch fire protection system pipe broke. The break occurred on the

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discharge of the electric fire pumps, where the piping comes out of the screen well house. The j

diesel fire pump started, as designed, due to low pressure in the system. The fire protection

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technical requirements manual describes the required actions to be taken for various fire system components out of service, and plant personnel reviewed the requirements to ensure that all

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requirements were met. The piping, where the break occurred, is approximately 5 feet

underground, so the area was excavated in order to inspect the damage. The piping was completely broken apart such that a small section of piping needed to be replaced. Plant

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personnel suspect that the recent cold weather brought temperatures low enough so that the line

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and/or surrounding ground froze, causing the pipe break. At the close of the inspection period,

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the break was isolated, dug up, and awaiting pipe replacement. The inspector reviewed the

overall response to the pipe break, observed the break, and concluded that the response to the t

break was timely and in comphance with applicable requirements.

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J 3.0 RADIOLOGICAL CONTROLS (71707)

Radiological controls were periodically reviewed to confirm that radiation work permits were effectively implemented, dosimetry was worn properly, protective clothing was used as required,

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and radiation areas were properly posted. Selected work evolutions principally associated with

spent fuel pit activities were observed. In general, these were found to be adequate with respect

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to program implementation, and commensurate with the radiological hazards.

3.1 Control Rod Shipment

On February 18, 1993, the inspector observed the preparations of a shipping cask for the shipment of 3 pieces of control rod follower to GE for testing purposes. The inspector observed good coordination of the activities between security, health physics, maintenance, and

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operations. Additionally, good supervisory oversight was noted. All observed activities were

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i conducted well with no deficiencies identified.

3.2 IIcalth Physics Practices

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During the prior inspection period, the inspector had observed weaknesses in various health physics practices. Through periodic tours of the facility and through observation of ongoing

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activities, the inspector noted good health physics practices during this inspection period.

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Postings were as required, dressing requirements were properly met, radiation protection signs were not obscured by snow after storms, and there was more involvement by supervision during

activities. Overall, improved performance was observed with no deficiencies identified.

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4.0 EMERGENCY PREPAREDNESS (71707)

i 4.1 Emergency Drill On March 18, 1993, plant personnel conducted the first practice emergency drill under the defueled emergency plan. This drill was intended as a practice for the first emergency exercise, currently planned for the first week in April. The inspector reviewed portions of the drill and concluded that it adequately met the goal of training plant personnel for the exercise and l

potential plant events.

l 5.0 ENGINEERING AND TECHNICAL SUPPORT (71707)

5.1 Auxiliary Service Water Pump i

During this inspection period, plant pctsonnel completed a modificatien w install a smaller service water pump in parallel with the existing service water pumps, txcause of the reduced i

heat load on the service water system. The existing service water pumps y rovide a much larger i

flow than is necessary, due to fewer systems in operation. One of the existing two vapor container service water booster pumps was removed from the primary auxiliary building and was

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installed in parallel with the existing service water pumps in the screen house At the conclusion l

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of the inspection period, the pump was tested and in operatica. The inspector observed operation of the pump and identified no deficiencies.

6.0 SAFETY ASSESSMENT AND QUALITY VERIFICATION (71707)

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6.1 Safety Practices During the last inspec' ion period, the inspector observed weaknesses in the safety practices of

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personnel involved in activities associated with the spent fuel pit. During this inspection period,

the inspector observed good awareness by plant personnel in the routine use of safety devices.

This was especially noted during work around the spent fuel pit for the activities associated with

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the shipment of the control rod follower pieces.

i 7.0 MANAGEMENT MEETINGS (30702)

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7.1 Preliminary Inspections Findings j

i At periodic intervals during this inspection, meetings were held with senior plant management to discuss the findings. A summary of findings for the repon period was also discussed at the

conclusion of the inspection period on March 19,1903 and prior to report issuance.

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7.2 NRC Inspection 3 One Region-based inspection was conducted during this inspection period. Inspection results-

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were discussed with senior plant management at the conclusion of the inspection.

Dates Subiect Insoection No.

Imd IDspector

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3/8-11 Safeguards 93-03 A. Della Ratta i

7.3 Other Meetings l

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On February 10,1993, and March 11,1993 meetings were held between the NRC and YAEC, in Rockville, Maryland, to discuss the current plans for decommissioning the Yankee Nuclear

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Power Station. The Decommissioning Plan is due to be submitted to the NRC in February 1994, although YAEC expects to submit it in October 1993. The meeting was informational in nature.

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