IR 05000259/1991005

Insp Repts 50-259/91-05,50-260/91-05 & 50-296/91-05 on 910129-0201.No Violations Noted.Major Areas Inspected: External Exposure,Dose Reduction Initiatives,Alara & Contamination Control

ML18057B508
Person / Time
Site:	Browns Ferry
Issue date:	02/22/1991
From:	Hughey C, Potter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML18057B507	List: IR 05000259/1991005 ML18057B506
References
50-259-91-05, 50-259-91-5, 50-260-91-05, 50-260-91-5, 50-296-91-05, 50-296-91-5, NUDOCS 9103120228
Download: ML18057B508 (8)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTA STREET, ATLANTA, GEORGIA 30323*

FEB 2 2 1991 Report Nos.:

50-259/91-05, 50-260/91-05 and 50-296/91-05 Licensee: Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Docket Nos.:

50-259, 50-260, and 50-296 Facility Name:

Browns Ferry i, 2, and 3 Inspe~c Approved by:

.

J

. Pott,

License Nos.: DPR-33, DPR-52, *

. and DPR-68 1, 1991 Facilities Radiation Prot~ction Settion Radiqlogical Protection and Emergency Preparedness Branch

Division of Radiation Safety and Safeguards SUMMARY Scope:

This routine, unannounced inspection of the radiation protection program was conducted in the areas of external exposure, dose reduction initiatives, ALARA and contamination contro Results:

In the areas inspected, no violations or deviations were identifie The original fiscal year* 1990 exposure goals were exceeded by over 500 *person-re Personnel contamination reports and radiological incidents reports for fiscal year 1990 were significantly below the goal The amount of contaminated square footage had been significantly reduced over the past year (Paragraph 2).

Self reading pocket dosimeters will be required in restricted areas b~ginning February 15, 199 The installation of lockable barriers around the fuel pool heat exchangers had been completed (Paragraph 3) *

~A~3120220 910222 G

ADOCK 05000259 PDR

Several initiatives for the reduction of individual and collective radiation exposures had been implemented or were planned for-future implementation (Paragraph 5).

' ; *

REPORT DETAILS Persons Contacted Licensee Employees:

• S. Bugg, Radwaste Manager

• R. Coleman, Radiological Protection Supervisor

• J. Corey, Radiological Control Manager

• E. Mastich, Health Physics Field Operations Supervisor

• L. Myers, Plant Manager

• J. Wallace, Compliance Licensing Engineer Other licensee employees contacted during this inspection included craftsmen, engineers, operators, security force members, technicians, and administrative personne NRC Resident Inspectors

• E. Christnot, Resident Inspector *

• C. Patterson, Senior Resident Inspector

• Attended exit interview Person-Rem, Personnel Contamination Events, Radiological Incident Reports, and Contaminated Square Footage (83750)

10 CFR 20. l(c) states that persons engaged in activities under 1 icenses issued by the NRC should make every reasonable effort to maintain radiation exposures as low as is reasonably achievabl Person-Rem Status The inspector reviewed site collective doses for 1990 and discussed past and current trends, and future goals with cognizant plant personne The original fiscal year 1990 (October -

September) goal was 710 person-re Actual exposure by the end of fiscal year (FY) 1990 was 1213 person-rem which exceeded the goa 1 by 503 person-re Licensee representatives indicated that the original FY 1990 goal was based on work being finished on Unit 2 then being started up in mid 1990 ~ and Unit 3 wa 1 kdown wor Unit 2 did not start up in 1990; however, due to an increase in work scop This increased work scope resulted in a significant increase in collective exposure for the Modifications Organization. This additional work included environmental qualification, piping support, electrical cabling and drywell steel modification wor The original FY 1990 goal for this group was 315 person-re Actual exposure was 959 person-re Because Unit 2 did

\\ *

not start up; however, during FY 1990 other plant groups were considerably under their goa *The collective exposure goal for FY 1991 was 650 person-re As of the end of January 29, 1991, 4 months into the new fiscal year, collective site exposure was about 2~8 person-re Personnel Contamination Reports (PCRs) The licensee's FY 1990 goal for PCRs was less than 250. They had stayed well under this goal for the year with 94 total PCRs. Because of this relatively low number of PCRs the FY 1991 goal was much more aggressive at 85 total PCR As of January 29, 1991 there had been 33 PCRs so far during the current fiscal yea The trigger level for reporting a PCR was greater than 100 counts per minute surface contaminatio In an effort to further reduce PCRs, the licensee planned the use of green scrub modesty undergarments under anti-contamination clothing within about two month Radiological Incident Reports (RIRs)

As with PCRs, the licensee had stayed well under the FY 1990 RIR goal of less than 13 Total RIRs for that period was 74. * The FY 1991 goal for RIRs was decreased to a total of 7 As of January 29, 1991, there had been 17 RIRs so far during the current fiscal yea Contaminated Square Footage The amount of contaminated areas around the plant had been significantly reduced. During the beginning of FY 1990 (October 1989),

temporary contaminated zone square footage was at 11 percent of the total plant area (924,973 square feet).

As of the end of December 1990, this amount had been reduced to 5.3 percen The original goal for FY 1990 was less than 10 percen The goal for FY 1~91 was reduced to less than 5 percen To help facilitate the future reduction of contaminated area the licensee planned to purchase a sophisticated high pressure water jet system (

11wet/vac 11 ).

No violations or deviations were identifie.

External Exposure Control (83750) Self Reading Pocket Dosimeters 10 CFR 20.202 requires each licensee to supply appropriate monitoring equipment to specific individuals and requires the use of such equipmen **

-*

During a previous inspection in this area (90-21, June 1990), the inspector noted that self reading pocket dosimeters (SRDs) were not required for general entry into the radio.logically controlled area (RCA).

The licensee indicated that this policy would change at least two weeks pr.ior to Unit 2 startu During this inspection, the

.licensee indicated that SRDs would be issue~ to all personnel entering the RCA beginning February 15, 199 Unit 2 fuel load was planned for March 199 Fuel Pool Heat Exchangers and Pumps Access During a previous inspection in this area (90-12, June 1990), "the licensee was installing lockable fencing around the fuel pool heat exchangers and pumps in all 3 Units in order to limits access to these areas which had approached and possibly exceeded 1,000 millirem per hour (prohibitive high radiation area), especially the un*i.t 2 heat exchanger which had become highly contaminated during the Unit 2 fuel reconstitutio During the present. inspection, the inspector noted that the installation of these barricades ~round the*heat exchangers in all three units had been complete.

.

No violations or deviations were identified. Unit 2 Post Startup Radiological Conditions Training (83750) CFR 19.12 requires the licensee to instruct all individuals working or frequenting any portion of the restricted areas in health protection aspects*

associated with exposure to radioactive materials or radiation and in precautions and ~rocedures to minimize exposur The inspector attended one of several training sessions.presented to plant personnel on Unit 2 post startup radiological condition The purpose o this training was to emphasize that plant radiological conditions would change significantly during and after startup. The instructor discussed radiological conditions in specific areas of the plant as they were presently and how they would change d~ring and after startu The areas emphasized during training were specific areas in the turbine, reactor, offgas and radwaste building A booklet summarizing the presentation was distributed during the training sessio The inspector considered the training to be adequat No violations or deviations were identifie As Low As Is Reasonaoly Achievable (ALARA) (83750)

10 CFR 20.l(c) states that persons engaged in activities under licenses issued by the NRC should make every reasonable effort to maintain radiation exposures as low as is reasonably achievabl. '

• • * *

Administrative Dose Limits As of January 1, 1991, new administrative dose limits became effective at all TVA nucl~ar site The highest administrative radiation dose limits were set at 1.0 Rem per quarter and 1.0 Rem per year with a graded authorization process up to the current Federal limits. These new limits were implemented to reflect the latest industry information concerning health effects from ionizing radiation. The following table is extracted from a TVA document distributed to radiation worker DOSE (REM)

1. O/qtr or yr 2.0/qtr or yr 2.5/yr 2.5/qtr or 3.0/yr 5.0/yr or lN (N=age in years)

AUTHORIZATION TO EXCEED Senior Line Manager and Radcon Manager Plant Manager and above Site Director and above VP Nuclear Ops and above Senior VP Nuclear Power or above Nori-TVA workers would have to provide a letter of authorization from their employer prior to exceeding an exposure of Rem per quarter and 1.0 Rem per yea Unit 3 Chemical Decontamination During the inspection, licensee management indicated that a chemical decontamination was being planned for the Unit 3 recirculation, core spray, residua 1 heat remova 1 and reactor water cleanup systems ("outside vesseP) to reduce general area dose rates and therefore reduce collective dose during upcoming work on Unit The licensee planned to use a l ow-oxidation state metal ion process (LOMI) to accomplish this decontaminatio No firm date for the decontamination had been established as ye ALARA Improvement Action Plan The inspector reviewed a memorandum date January 31, 1991, that established the Browns Ferry Plant ALARA Improvement Action Pla This plan was concurred upon by key site and plant managemen This plan established several aggressive goals, the actions required for implementing these goals, funding requirements and completion date This plan included but certainly was not limited to the following items:

. '

• ..

4.-. Establishing an aggressive ALARA goal setting proces Clearly define site management/supervisory responsib.ility and*

accountability for AL.ARA program implementatio Provide ALARA awareness training to appropriate levels of managemen Define and established aggressive administrative dose control This item has been completed and is discussed in Paragraph 5~ Establish a source term reduction progra Schedule and sequence work activities to incorporate ALJl.RJ!.

considerations and reduce dose impact Develop a Contamination Control and Decontamination Improvement.

• Program. *

Other Dose Reduction Initiatives The inspector and licensee representatives discussed several other dose reducti~n initiatives: Several remote video camera systems were on order for use in Unit 2 after startup to reduce number of routine entries into radiation areas by-plant personne * Several shielded security booths were being used to re.duce exposure of security guards who were required to be posted. for long periods of time in and near radiation area The licensee estimated a dose savings of approximately 7 person-rem* per yea.

An extensive mock-up facility had been constructed at' the site training cente The licensee planned to expand the use of mock-up facilities in the futur No violations or deviations were identifie.

Organization and Management Controls (83750)

The inspector briefly reviewed the Radiological Control Organization staffing level At the time of inspection, the staff included six managers, nine professional health physicists, 13 line supervisors, and *83 technician There were no vendor technicians on staff and the licensee indicated that ~one would be needed in the foreseeable future..

No violations or deviations were identified. *

Exit Interview The inspection scope and results were summarized on February 1, 1991, with those persons indicated in Paragraph The inspector described the areas inspected and discussed the inspection finding Proprietary information is not contained in thfs repor No violations or deviations were identified *