IR 05000146/1999202

Insp Rept 50-146/99-202 on 990830-0902.No Violations Noted. Major Areas Inspected:Onsite Review of Selected Aspects of Organizational Structure & Functions Program,Emergency Preparedness,Fire Protection Program & Facility Inspections

ML20216J988
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	10/04/1999
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20216J985	List: IR 05000146/1999202 ML20216J981
References
50-146-99-202, NUDOCS 9910070083
Download: ML20216J988 (7)

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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NilCLEAR REACTOR REGULATION

- Docke't No: '50-146 ~

License No: DPR-4 Report No: 1999202'

Licensees: GPU Nuclear Corporation and Saxton Nuclear Experimental Corporation Facility: Saxton Nuclear Experimental Facility Location: Saxton, Pennsylvania Dates: August 30 - September 2,1999 Inspector Thomas F. Dragoun Approved by: Ledyard B. Marsh, Chief Events Assessment, Generic Communications and Non-Power Reactors Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation f

9910070083 991004 "

PDR ADOCK 05000146

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EXECUTIVE SUMMARY

This routine, announced inspection included onsite review of selected aspects of the orgaaizational structure and functions program, emergency preparedness, fire protection program, facility inspections, and the control of work since the last NRC inspection of this progra ORGANIZATIONAL STRUCTURE AND FUNCTIONS The organizational structure and functions were consistent with Technical Specification requirement EMERGENCY PREPAREDNESS The emergency plan was properly implemente FIRE PR'.;TECTION The fire protection plan was properly implemente ~ FACILITY INSPECTIONS Facility inspections were completed as required by Technical Specification 3. CONTROL OF WORK Work was performed in accordance with regulatory requirements and licensee commitment l

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REPORT DETAILS

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b Summartofflant S4tus

' Concrete surfaces in the reactor cavity and primary compartment were being scabbled to remove surface contamination. Most pipes remaining in penetrations between compartments i

were removed by core boring the concrete surrounding the pipes: A large'section of the reactor

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cavity wall containing hard-to-remove piping was cut and removed. Plans were in progress to pump water from the con alament vessel (CV) Pipe Tunnel and the Stearn Plant Condenser

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- Outibw into storage tanks prior to disposal.

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. QBGANIZATIONAL STRUCTURE AND FUNCTION;

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-a: Scope (IP 36801)

L The' inspector reviewed selected aspects ofi e- organization and staffing-e ; qualifications and training a staff retention e- audits e- _ AMERGEN ' support *

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b.- . Qhservations and Findinas The site organization, staff responsibilities, and key personnel were unchanged

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since the last inspection. Training records were up-to-date. Staff tumover was -

low with only a few radiation protection technicians requiring replacemen Although there is no program to encourage personnel retention, morale was high and interviewed personnel stated an intention to remain until project completio A comprehensive biennial Quality Assurance audit was completed in April and

May 1999 with three minor discrepancies reported and entered into the Corrective Action Program for follow u Most support for the environmental monitoring program, radiological engineering, measuring and test instrument calibration and repair, record keeping, drawing services, technical engineering, medical exams, drug screening, fire training, fire

' fighting equipment, industrial safety and hygiene programs, and general employee training at Saxton is provided by the Three Mile Island (TMI)

organization. The sale of TMI to AMERGEN is expected to be consummated at

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the end of the current TMl refueling outage. Approximately 12 "GPU/AMERGEN Reciprocal Service Contracts" have been put in place to ensure continuity of TMI support for e ssential Saxton programs.

! Conclusions .

The organizatior.al structure and functions wee censioent with Technical Specification requirements.- '

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I 2. EMERGENCY PREPAREDNESS Scope (IP 40755)

The inspector reviewed selected aspects of: {

• Emergency Plan and procedure changes emergency notifications -

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e contaminated / injured person emergency response kit Observations and Findinas -

q Several minor changes were recently made to the Emergency Response  !

Procedure and Emergency Plan which did not decrease the effectiveness of the plan. The licensee will submit the revised plan to the NRC for information. This

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matter will be reviewed in a future inspection (Inspector Follow up item 50-146/1999202-01).

An emergency notification list was posted on the main bulletin board and the telephone, cell phone, and pager numbers are verified quarterly. The inspector obscrved a successful notification test to the Program Director while he was off sit The emergency response kit was opened, inventoried, and found to contain the required equipment in operable condition, Conclusions i

The emergency plan was properly implemente j 3. FIRE PROTECTION l

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a, - Scope (IP 40755) 1 The inspector reviewed selected aspects of: fire watch training e location and maintenance of fire fighting equipment a self-contained breathing apparatus (SCBA) packs and turn-out gear ! Observations and Findinas

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- The fire protection program is based on the noncombustible structure of the CV and negligible fire loading of the contents. Introduction of combustibles is controlled. An item on the daily closeout checklist for the CV verifies that combustible materials were removed.

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I Fire watch annual requalification training records were up to date. Many of the l extingui::hers on site are discharged and replaced during this training as part of 1 the operability check on the equipmen ,

The number, location, rating, routine inspection, and maintenance of portable fire fighting equipment appeared reasonable. Two sets of SCBA packs and turn-out l gear were available as specified in the Fire Protection Plan. The sets included a 1 sensor worn by the firefighter that sounds a loud audible alarm if the firefighter is motionless for a predetermined period. This helps to locate the firefighter if rescue is required.' Conclusions l

The fire protection plan was properly implemente '

4. ' FACILITY INSPECTIONS -l Scoce (IP 40755)

The inspector reviewed selected aspects of:

e inspeciten and calibration procedures e inspection and calibration data sheets and records Ocservations and Findinos  !

l Facility inspections and equipment calibration were completed on schedule and !

in accordance with licensee procedures. All the recorded results were within the technical specifications and procedurally prescribed parameters. The records and logs were complete and were being maintained as require Conclusions Facility inspections were completed as requiced by Technical Specification 3. ! SCABBLING AND CORE BORING Scope (IP 37801)

The inspector reviewed selected aspects of:

o 50.59 and 50.82 change reviews e specific work procedures a worker training a health physics (HP) practices

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4 Observations and Findinos Change reviews were detailed and documented as required. Earlier reviews consisted of a broad work scope document with change review information provided in the instructions for parts of the work. Now, the broad scope document is eliminated and all details are provided in each job specific work instruction (SWI).

Commercial pneumatic tools were modified by site personnel for scabbling mastic coated surfaces and to improve performance over the equipment provided by the scabbling system vendor. The original and modified scabbling tools and core boring equipment were acceptance tested by radiological engineering prior to use. Records indicated that workers were trained in SWI requirements and use of the scabbling equipment. Core boring was done by a vendor (Bluegrass).

HP practices, radiation work permit requirements, and job coverage by HP technicians were appropriate. As low as reasonable achievable practices included removal of hot spots to reduce general area dose rates before initiating the slow scabbling process. No bloassay for alpha emitters or whole body counting for beta-gamma emitters has been required since breathing zone air sampling indicated all committed effective dose equivalent doses were below administrative limits (50 mrem / week).

The conventional safety program was acceptably implemented and the program remains the responsibility of the radiation safety officer. Housekeeping was adequate. A portable generator was available as a backup electrical suppl Conclusions Work was performed in accordance with regulatory requirements and licensee commitment . EXIT MEETING The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on September 2,1999. The licensee acknowledged the findings presente ,

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R# 1 PARTIAL LIST OF PERSONS CONTACTED

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Licens,ee

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R. Case, SNEC Group Radiological. Controls Supervisor

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i P.ECarmel; SNEC Site Supervisor .

-: G. A. Kuehn, SNEC Program Director A. Paynter, SNEC Radiation Safety Officer -

A Rone' GPU Vice President of Engineering

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L. Sharnenek, SNEC Site Foreman '

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INSPECTION PROCEDURES USED

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~ IP 36801' ORGANIZATION, MANAGEMENT, AND COST CONTROLS AT -

PERMANENTLY SHUTDOWN REACTORS IP 37801' l SAFETY REVIEWS, DESIGN CHANGES, AND MODIFICATIONS AT PERMANENTLY SHUTDOWN REACTORS

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IP 40755 . CLASS Ill REACTORS ITEMS OPENED. CLOSED AND DISCUSSED OPENED:

50-146/1999202-01. IFl - Submit Emergency Plan changes to NRC for infom1ation -

CLOSED: None LIST OF ACRONYMS USED CV Containment Vessel --

CFR Code of Federal Regulations HP. . ~ Health Physics -

SCB ;-Self Contained Breathing Apparatus -

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-;SWI Specific Work Instruction i.TMI Three Mile Island power plant

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