IR 05000133/2010003

IR 05000133-10-003, on 04/12-16/2010, Humboldt Bay Power Plant, Unit 3

ML101320074
Person / Time
Site:	Humboldt Bay
Issue date:	05/12/2010
From:	Spitzberg D Division of Nuclear Materials Safety IV
To:	Conway J Pacific Gas & Electric Co
References
IR-10-003
Download: ML101320074 (12)

Text

UNITED STATES NUC LEAR RE G ULATO RY CO M M I SSI O N May 12, 2010

SUBJECT:

NRC INSPECTION REPORT 050-00133/10-003

Dear Mr. Conway:

This refers to the inspection conducted on April 12-15, 2010, at the Humboldt Bay Power Plant, Unit 3 facility, in Eureka, California. The enclosed report presents the results of this inspection.

This inspection was an examination of activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license. Within these areas, the inspection consisted of selected examination of procedures and representative records, observations of activities, and interviews with personnel. In summary, the inspector determined that you were conducting decommissioning activities in accordance with license and regulatory requirements.

In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter, its enclosure, and your response, if you choose to provide one, will be made available electronically for public inspection in the NRC Public Document Room or for the NRCs documents system (ADAMS), accessible from the NRCs Web site at HTTP://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the public without redaction.

Should you have any questions concerning this inspection, please contact Mr. Gerald Schlapper, Radiation Specialist at (817) 860-8273 or the undersigned at (817) 860-8191.

Sincerely,

/RA/

D. Blair Spitzberg, PhD, Chief Repository & Spent Fuel Safety Branch Docket: 050-00133 License: DPR-7

Enclosure:

NRC Inspection Report 050-00133/10-003

Pacific Gas and Electric Company -2-

REGION IV==

Docket: 050-00133 License: DPR-7 Report: 050-00133/10-003 Licensee: Pacific Gas and Electric Company Facility: Humboldt Bay Power Plant, Unit 3 Location: 1000 King Salmon Avenue Eureka, California 95503 Dates: April 12-16, 2010 Inspector: Gerald Schlapper, PhD, PE, CHP, Radiation Specialist Repository & Spent Fuel Safety Branch Approved by: D. Blair Spitzberg, PhD, Chief Repository & Spent Fuel Safety Branch Attachment: Supplemental Inspection Information ENCLOSURE

EXECUTIVE SUMMARY Humboldt Bay Power Plant, Unit 3 NRC Inspection Report 050-00133/10-003 This inspection was a routine, announced inspection of decommissioning activities being conducted at the Humboldt Bay Power Plant, Unit 3 facility. In summary, the licensee was conducting site activities in compliance with regulatory and license requirements.

Decommissioning Performance and Status Review

• The licensee conducted decommissioning activities in accordance with license and regulatory requirements. Radioactive postings and boundaries were maintained in accordance with regulatory requirements. Contaminated piping characterization and removal work was conducted in accordance with procedure requirements. The licensee noted concerns with the continuous alpha stack monitor system and took corrective actions to ensure operability of this system (Section 1).

Solid Radioactive Waste Management and Transportation of Radioactive Materials

• The licensee conducted radwaste handling activities and transportation activities in accordance with procedure and regulatory requirements. The licensee continues negotiation with the California Department of Transportation for route approval for shipments (Section 2).

Radioactive Waste Treatment, Effluent and Environmental Monitoring

• The licensee conducted radwaste treatment and effluent and environmental monitoring activities in accordance with regulatory requirements (Section 3).

-2- ENCLOSURE

Report Details Summary of Plant Status-Unit 3 During the inspection, the Humboldt Bay Power Plant, Unit 3, was being decommissioned by the licensee in accordance with commitments made in its Post Shutdown Decommissioning Activities Report dated June 30,2009. The licensee initiated decommissioning during May 2009.

At the time of this inspection the licensee commenced removal of the reactor vessel pressure relief valves with subsequent placement of the valves in an interim storage container. In the week following removal of the relief valves, the licensee plans to disconnect the main steam line. The reactor pressure vessel head is next to be removed in order to permit reactor pressure vessel characterization work that is required in order to determine how to dispose of the reactor vessel.

Other work in progress during the inspection included preparation and foaming of a contaminated pipe in the reactor feed pump area. The inspector also observed preparation for removal of the main steam line. The new access control point is operational and actions are underway to complete movement of equipment from the old access control area into the new access control point. During the inspection, movement of a second small part monitor detector and shield assembly was noted. The licensee continued work on the new count room building which is essentially complete. After acceptance from the contractor, transfer of the count rooms equipment will commence.

The licensee continued to construct a new natural-gas fired power generation plant on site property. Following the construction of the new power plant, the licensee plans to commence with the decommissioning of fossil plants Unit 1 and 2 by removing all of the hazardous materials from the structures. The shutdown and decommissioning of Units 1 and 2 are scheduled to begin in the September 2010 time frame and will be done concurrent with the Unit 3 decommissioning activities.

The licensee submitted on March 31, 2010 an exemption request to the NRC for alternate disposal of the building rubble and soil collected during the demolition of Units 1 and 2, and a small portion, the non-impacted areas, of Unit 3. NRC approval would allow the licensee to dispose of this waste material at a facility authorized to accept hazardous material with low levels of radioactive contamination.

1 Decommissioning Performance and Status Review (71801)

1.1 Inspection Scope The inspector evaluated whether the licensee and its contracted workforce were conducting decommissioning activities in accordance with license and regulatory requirements.

1.2 Observations and Findings The inspector toured the radiologically unrestricted areas of the facility. Radiological postings on fences and at entrances to the restricted area were clearly visible, and postings met the requirements of 10 CFR Part 20. During site tours, the inspector-3- ENCLOSURE

conducted radiological surveys to verify the accuracy of radiation boundary postings using a Ludlum Model 2401-EC2 survey meter (NRC No. 257896, calibration due date of 9/26/10). The inspector did not identify any location that was incorrectly posted by the licensee.

During the inspection, the licensee was continuing radiological characterizations of materials in the Spent Fuel Pool. This activity was underway to determine the waste classifications of the materials. The work was conducted in accordance with site instructions. The inspector observed doffing of personal protective equipment and noted that the increased emphasis during training of individuals was improving the ability of the workers to prevent unnecessary exposure due to airborne contamination.

Preparation for the first cut of contaminated pipe continued during the inspection. The inspector attended the pre-job briefing for the action of drilling and foaming of the pipe.

This activity followed procedures applicable when a foam fixative is utilized and pipe cuts are made utilizing a WACHs cutter assembly. During the pre-job briefing, prerequisites were outlined and work hold points discussed. Management confirmed that job performance measures were completed and that workers were confident that they were prepared for the safe completion of the task. The inspector also reviewed a licensee supplied DVD of a dry run conducted on a foamed pipe with low or no contamination which confirmed the level of training and confidence of workers. A remote video feed of this operation allowed for viewing of the foaming activity.

At the time of the inspection, foam as a fixative was approved for piping in the six to eight inch range. For larger pipes, the licensee was investigating the use of an epoxy like spray paint to fix contamination. Initial results were promising but other factors like waste acceptance criteria impact the final choice of a fixative. Other commercial fixatives are under review.

During the week of the inspection the licensee was in the process of removing relief valves on the reactor pressure vessel. Prior to this effort, the reactor vessel had been filled with demineralized water in order to reduce exposures. Removal of the valves was conducted following appropriate procedures and following accepted radiation protection techniques. Management oversight of this activity was noted. Placement of remote video cameras with real-time feed allowed for close observation of the workers without unnecessary risk of potential exposure to airborne radioactive material. Continuous monitoring of levels of airborne activity was observed and no alarms were noted.

Following removal, the relief valves were placed in storage in an approved temporary storage container.

1.3 Conclusions The licensee conducted decommissioning activities in accordance with license and regulatory requirements. Radioactive postings and boundaries were maintained in accordance with regulatory requirements. Radiological work in the spent fuel pool and reactor vessel areas was conducted in accordance with procedure requirements.

-4- ENCLOSURE

2 Solid Radioactive Waste Management and Transportation of Radioactive Materials (86750)

2.1 Inspection Scope The inspector reviewed the licensees programs for characterizing and shipping the radioactive wastes that will be generated during site decommissioning.

2.2 Observations and Findings The HBPP developed a position paper for low level waste disposal that identified waste disposal options by expected radiation levels. The plant was partitioned into areas and/or systems per the category of waste. The licensee utilized a flow path tool based on measured radiation levels that guides movement of material from removal from a system to interim storage, if required, to final packaging for transport to a waste disposal site. Although most system removal activities are conducted by the Day and Zimmerman contractor workforce, each team has a PG&E employee that provides oversight.

The inspector reviewed a conformance file for the DOT 7A package that will be used for shipment of the spent fuel rack and found it to conform with requirements. The training package presented to on-site personnel that related to waste processing was reviewed.

The inspector attended a pre-job brief that outlined the approach for loading a DOT package containing the spent fuel rack onto a trailer for transport. The briefing reviewed the work to be done and emphasized the need to pause for safety. Though the shipping container was loaded onto a trailer for transport, shipment was delayed as HBPP currently has limitations that are unique due to the location of the site and requirements of the California Department of Transportation.

2.3 Conclusions The licensee conducted radwaste handling and transportation activities in accordance with procedure and regulatory requirements.

3 Radwaste Treatment, Effluent and Environmental Monitoring (84750)

3.1 Inspection Scope The inspector reviewed the licensees programs for effluent and environmental monitoring that will continue during the period of decommissioning.

3.2 Observations and Findings Twelve monitoring wells ring the reactor caisson and refueling pool. There has been no indication of tritium significantly above detection limits since 1998. A hydrogeologic assessment of the site was conducted in March 2010 that assessed adequacy of the current groundwater monitoring system and made recommendations as to additional monitoring wells that should be installed to better assess groundwater post decommissioning.

-5- ENCLOSURE

The condition report and corrective actions for the continuous alpha stack monitoring system were reviewed. The continuous alpha monitor system had been non-operational for approximately three months due to an incorrect setting of a software switch. The software had been inadvertently changed during initial installation and testing. During this time any alpha particulate releases would have been detected in analysis of the weekly fixed filter sample. There was only limited work in areas of high alpha contamination during this time period and the weekly samples showed no indication of a release. The inspector noted when attending the pre-job brief for the pipe foaming and cutting that the continuous alpha particle stack monitor system must be checked to ensure operability prior to initiation of cutting of contaminated piping.

3.3 Conclusions The licensee conducted effluent and environmental monitoring in accordance with procedure and regulatory requirements.

4 Exit Meeting The inspector reviewed the scope and findings of the inspection during an exit meeting that was conducted at the conclusion of the onsite inspection on April 15, 2010. The licensee did not identify as proprietary any information provided to, or reviewed, by the inspector.

-6- ENCLOSURE

SUPPLEMENTAL INSPECTION INFORMATION PARTIAL LIST OF PERSONS CONTACTED J. Albers, Radiation Protection Manager R. Arroyo, Site Services Manager P. Barringer, Radwaste Shipping J. Chadwick, Radiation Protection Operations Supervisor A. Cordone, Decommissioning Projects Superintendent J. Davis, Radiation Protection Engineer S. Davis, Day-Zimmerman Site Manager L. Pulley, Deputy Decommissioning Manager K. Rod, Decommissioning Manager P. Roller, Director and Nuclear Plant Manager S. Schlerf, Radiation Protection Forman B. Sicotti, Quality Control Supervisor M. Smith, Engineering Manager R. Snyder, Radwaste Supervisor D. Sokolsky, Licensing Supervisor M. Stein, Radiation Protection Supervisor INSPECTION PROCEDURES USED IP 71801 Decommissioning Performance and Status Review IP 84750 Radioactive Waste Treatment and Effluent and Environmental Monitoring IP 86750 Solid Radioactive Waste Management and Transportation of Radioactive Materials ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed None Discussed None ATTACHMENT

LIST OF ACRONYMS CFR Code of Federal Regulations IP NRC Inspection Procedure HBPP Humboldt Bay Power Plant PSRC Plant Staff Review Committee QA quality assurance RFI Request for Information form SFP spent fuel pool TLD thermoluminescent dosimeters-2- ATTACHMENT