IR 05000146/1998203

Insp Rept 50-146/98-203 on 980914-17.No Violations Noted. Major Areas Inspected:Decommissioning Activities at Facility

ML20154K137
Person / Time
Site:	Saxton File:GPU Nuclear icon.png
Issue date:	10/13/1998
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20154K121	List: IR 05000146/1998203 ML20154K118
References
50-146-98-203, NUDOCS 9810160125
Download: ML20154K137 (10)

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U.S. NUCLEAR REGULATORY COMMISSION

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Docket No: 50-146 License' No: ' DPR-4 ' -

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- Report No: 1998203 Licensee. : 'GPU Nuclear Corporatio!1 and f

Saxton Nuclear Experimental Corporation j

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f Facility: Saxton Nuclear Experimental Facility !

Location: Saxton, Pennsylvania

, Dates: September 14-17,1998 l

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I inspector: : Thomas F. Dragoun, Senior Reactor Inspector F

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• i Approved by: Seymour H. Weiss, Director  ;

Non-Power Reactors and Decommissioning .;

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Project Directorate  !

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EXECUTIVE SUMMARY The monthly meeting with the Citizens Task Force continued to be an effective forum for ,

public participation and information exchange. Preparations for removal and shipment of i large components were well coordinated. Cold weather protection for equipment and workers was appropriate increased emphasis on the fitness for duty program for contractor personnel was appropriate. Conduct of work in the controlled area was found to :

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be in compliance with NRC requirements. No safety concerns or violations of regulatory '

requirements wera idct.tifie '

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Report Details Summarv of Plant Status l

A large fabric and metal frame tent had been erected on site for temporary storage of large ,

components removed from the containment building. Scaffolding around the exterior of '

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containment was being erected to support cutting of access openings. Plugging and welding of penetrations in the steam generator and pressurizer vessels was underwa Approximately 100,000 pounds of contaminated rnetal scrap was packaged for shipment i and stored on sit l l . Transportation of Radioactive Material Insoection Seone (Insoection Procedure 86750)

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• Procedures, e Route to be used to transport large components, e Railroad siding arrangements, and

• Documentation for a shipment of used respirator Observations and Findinos 1 '

. TS 1.0.11 states, in part, that the process control program (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensura l that processing and packagiag of solid waste is accomplished in accordance with l applicable regulations. The document titled "SNEC Facility Prow Control {

Program" (#6575-PLN-4542.09) was submitted to the NRC on September 16, k 1997, but did not contain this information. During this inspection, the licensee i stated that shipments were controlled in accordance with Standing Order SOM-  ;

6575-97-01. In addition, waste characterization and shipping papers were prepared l in accordance with TMl procedure OS-22. The inspector was able to locate the '

required information in these document The inspector accompanied a tour of the roadway and rail siding that will be used for shipment of large components. The licensee indicated that the heavy load contractor (Hake) was experienced and was using lessons learned from similar projects. Planning appeared to be thorough. Coordination with the local municipalities along the route, Penn DOT, State Police, railroad companies, insurance providers, and the waste burial site was discussed. Arrangements to use private property adjacent to the rail siding for staging and transferring loads to the rail cars will allow for enhanced safety and security precaution The characterization and classification of a shipment of used respirators being sent to TMI was completed using the "RAMSHIP" computer program. Shipping ,

documents were completed in accordance with licensee procedures and regulatory )

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c,- Conclusions Shipment of radioactive material was conducted in accordance with regulatory ,

requirement , Cold Wea'ther Preparations

, inpoection Scoce (Insoection Procedure 71714)

The inspector reviewed:

e completion of the cold weather checklist, e protection of the exhaust monitoring system, and e protection of personnel and susceptible system Observations and Findinos

. A cold weather checklist was available. Some of the checks were complete but not all. Capacity and placement of heaters for freeze protection of buildings, safety equipment, water, and electrical utilities appeared adequat The airborne radioactivity mon - for the exhaust stack was located in a insulet 1, heatcd enclosure equipped with a low temperature alarm that sounds in the '

' Decommissioning Support Facility. However, the small bore air sampling and return lines for the monitor were not heat traced. Moisture in the heated air being exhausted from the CV could condense, freeze, and plug the sample line. The RSO stated that the lines would be heat traced and insulated before cold weather and steps added to the daily check procedure to verify proper operation of the heat tracing.- This matter will be reviewed in a future inspection, Conclusions The licensee has effectivel, implemented a program to protect safety-related

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systems against extreme cold weathe .0 Fitness for Duty

' insoection Scone (Insoection Procedure 71801)

The inspector reviewed:

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• ' implementation of a fitness for duty program, e staff adjustments, and e termination briefing informatio +

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, Observations and Findinas l The fitness for duty program is descrhd in the GPU Nuclear Corporate Policy and Procedure Manual Number 1000-ADM-2002.06 revision 12. This program is applicable at the Saxton site with some of the nuclear power plant requirements described as " optional." The Saxton Program Director stated that, of ten randomly selected personnel who provided c'.-mples at various times since July, three tested positive for alcohol or drugs. Dieciphnary action taken for all three was immediate termination. The Director also staied that representatives from GPU Human Resources and the GPU medical staff held special discussions with site contractor personnel during the week of September 28,1998. All long-term contractor personnel with unescorted access were also tested as part of pre-job screenin GPU personnel continue to be randomly teste The inspector reviewed the staff realignments taken to replace terminated

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personnel. Replacement personnel were qualified and no safety concerns were identifie The inspector observed the termination briefing of one individual. Information provided regarding rights and responsibilities appeared to be in conformance with the GPU polic Conclusions

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The GPU fitness for duty program was satisfactorily implemente .0 Radiation Protection insoection Scoce (Insoection Procedure 83750)

The inspector reviewed the radic'ogical controls for plugging and welding penetrations in the pressurizer includit:g:

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e access training, e a radiation work permit, e radiation surveys, e respiratory protection program, and e control of exposure to alpha emitter Observations and Findinas The inspector reviewed the training provided to workers prior to being granted access to the controlled area. Information required by 10 CFR 19.12 was provided.

l The radiological conditions and protective measures for the pressurizer plugging work were described in Radiation Work Permit #41, " Preparation and Support for Steam Generator and Pressurizer Removal." The inspector noted that the area dose rates indicated on the RWP were different from dose rates recorded during the l

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referenced surveys. The HP technician who issued the RWP explained that a section of steam generator cold leg piping was removed after the surveys were completed. This pipe section was a major contributor to the radiation field and he adjusted conditions on the RWP to account for its removal. This demonstrated good attention to changing conditions as the facility is dismantle Observation of work in the primary compartment indicated that workers were complying with RWP requirements, continuous HP coverage was provided, and a fire watch was statione The licensee used local blowers with HEPA filters to provide engineered control of airborne radioactivity created during welding and heat treatment on the contaminated metal. Since respirators were required, the inspector verified that the workers on the job were qualified for respirator use. This included completion of a physical evaluation, fit testing for the type of respirator issued, and trainin Issuance of respirators was properly controlled by HP technicians at the personnel access point. No deficiencies were noted. A low oxygen concentration alarm (set at 19.5%) in the primary compartment caused a work stoppage and evacuatio The problem was attributed to air stratification during welding and was resolved by changing the orientation of blower supply outlet location Breathing zone air samples were used to assess worker uptakes of radioactive material. The inspector reviewed the maintenance and calibration of alpha and beta-gamma laboratory counting equipment used to analyze air samples. Equipment is l calibrated and maintained by personnel from TMI. An adequate supply of

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instruments was on hand to allow timely analysis of samples. Daily quality control checks of the courting equipment were performed and recorded by on-site HP .

technicians using generally accepted techniques. The predominant nuclides present )

on most air samples were naturally occurring radon daughters. Samples were j allowed to decay to reduce the prasence of radon daughters and were re-analyze j Selected samples are also ser'+ to the GPU environmental laboratory for alpha -

spectroscopy analysis to verify that the assumed isotopic mix has not change i These are acceptable technique l The derived air concentration (DAC) limit for airborne alpha emitting nu'.iides was reviewed. GPU Calculatiu Sheet 6575-97-011 calculated the DAC limit for the l isotopic mix found in each of the six zones identified during the site characterization I study. A gross DAC value of 4.0 E-12 Ci/ml for alpha emitters was adopted. This l value was reasonable and was used to calculate and record DAC-hour dose for the '

workers. The protection factor allowed by 10 CFR 20 Appendix A for respirator usage was appropriately included in the calculations. Records of sample analysis and dose calculations were well kept and readily retrievable. Within the scope of this review, the CEDE dose assigned to workers in alpSa contamination zones was found to be ALARA and within NRC limit The inspector noted that all aspects of the respirator and sample analysis laboratory programs reli3d heavily on support provided from TMI. Continuation of this support l

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[ was not guaranteed due to the proposed sale of TMI. The Site Supervisor stated

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that some support could be obtained from contractors. Difficult to replace and other

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critical support from TMI had been identified to GPU upper management. A similar concern was expressed in a recent letter to the President of GPU from the Citizens >

' Task Force but no reply was received yet. This matter will be reviewed in a future inspectio *

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~ Conclusione The radiological controls applied during welding of openings in the pressurizer -

satisfied regulatory requirement , Changes and Modifications

, Insoection Scone (Insoection Procedure 37801)

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For the closure welding of the pressurizer openings, the inspector reviewed:

e welder training and certifications, a work instruction, and e the 50.59 revie Observations and Findinas All welders were contract workers. Welders were tested and certified on site in accordance with the GPU welding program. This involved welding test coupons to pipe sections on site which were sent off site for testing and inspection. The record of welder certifications, documented in a GPU letter dated September 8,1998, listed the procedures that each welder was authorized to perform. All welders who signed in on RWP 41 for work on the pressurizer were certified for GPU Welding '

Procedure 111, dissimilar metal welds. This was required since many of the welds ,

involved carbon steel to stainless steel. The contractor (Raytheon) site l superintendent stated that all completed welds would be inspected in accordance with the GPU progra The specific work instruction for the pressurizer closure welding (SWl-98-056, rev. ) was clear, detailed and comprehensive. This procedure had beer, reviewed and )

l approved as required by TS 3.6. Nonradiological safety precautions included 1 l controls for hot work, monitoring for gases, and handling of removed component l l . The gas-tech monitor (oxygen and explosive gas monitor) used by the industrial i hygienist alarmed on low oxygen concentration as discussed in Section 4.0 above.

Control of industrial hazards seemed proper.

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The 50.59 review of the work (facility change) was attached to the SWI It l provided detailed job specific analysis of potential accidents associated with the l work. The justification and rationale for each conclusion of no unreviewed safety l question was thorough and technica!Iy sound.

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6 Conclusions

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Closure welding of pressurizer penetrations was done in accordance with regulatory requirements and licensee commitments.

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' Exit interview (Inspection Procedure 30703)

l The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on September 17,1998. The licensee

- acknowledged the findings presented.

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O PARTIAL LIST OF PERSONS CONTACTED l

LiCPJ1Ssift James Byrne, Manager, DD&E Perry Carmel, Site Supervisor Rod Case, GRCS William Heysek, Licensing Department '

Robert Holmes, Technical Consultant Robert Lewis, Raytheon Site Superintendent Sylvia Morris, Sr. Public Affairs Representative Arthur Paynter, Radiation Safety Officer Gordon Powers, Raytheon Engineer L'ouis Shamanek, GPU Site Superintendent Lawrence Simon, Radwaste Shipping Supervisor  ;

G. A. Kuehn, Program Director Saxton Citizens Task Force Roger Granlund, independent Assessor (Penn. State University)

r INSPECTION PROCEDURES USED IP 30703: ENTRANCE AND EXIT INTERVIEWS IP 37801 SAFETY REVIEWS, DESIGN CHANGES, AND MODIFICATIONS IP 71714 COLD WEATHER PREPARATIONS IP 71801 DECOMMISSIONING PERFORMANCE AND STATUS REVIEW IP 83750 OCCUPATIONAL RADIATION EXPOSURE IP 86750 SOLID RADIOACTIVE WASTE MANAGEMENT ITEMS OPENEO, CLOSED, AND DISCUSSED Ooened None Closed None C

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4-LIST OF ACRONYMS USED j CEDE Committed Effective Dose Equivalent CFR: Code of Federal Regulations CV Containment Vessel DAC Derived air concentration DD& Decontamination and Decommissioning Engineering DOT Department of Transportation GP General Public Utilities Corporation GRCS Group Radio;ogical Controls Supervisor

<HP Health Physicist HEPA High Efficiency Particulate Air filter-IP . . Inspection procedure NRC . Nuclear Regulatory Commission RWP- Radiation Work Permit TMl Three Mile Island power station TS Technical Specifications -

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