IR 05000213/1992025

Insp Rept 50-213/92-25 on 921214-17.No Violations Noted. Major Areas Inspected:Mgt Organization,Training & Assurance of Quality

ML20126H332
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	12/22/1992
From:	Joseph Furia, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20126H297	List: IR 05000213/1992025 ML20126H293
References
50-213-92-25, NUDOCS 9301050144
Download: ML20126H332 (6)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /92-25 Docket N License N DPR-61 Licensce: Connecticut Yankee Atomic Power Comoany Post Office Box 22Q Hartford. Connecticut 06141-0270 Facility Name: Haddam Neck Plant inspection At: lladdam Neck. Connecticut ,

inspection Conducted: December 14-17. 1992 Inspector:

W () J. Furi), Seaior Radiation Specialist, i

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date d Facilities Radiation Protection Section (FRPS),

Facilities Radiological Safety and Safeguards Branch (FRSSB), Division of Radiation Safety

. Safeguards (DRSS)

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, O Approved by:

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67 L^ \ l2 '2 S 91 V7. Pasciak, Chief, FRPS, FRSSB, DRSS date Areas Inspected: Management organization, training, assurance of quality, radiation control during normal operations, ALARA, and implementation of the above program Eclulls: Continued strong performance in the radiation protection program was note Training of radiation protection technicians, including continuing training and training for contractor radiation protection personnel was a notable strength. No radiological safety concerns or violations of regulatory requirements were identifie i PDR ADOCK 0S000213 l l

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- DETAILS

- 1. L'enomel Contackd 1.I' Liernsee Personnel

• R. Aft, Training Coordinator G. Bouchard, Unit Director T. Burns, Supervisor, Technical 'i' raining

• W. Gates, Radiation Protection Supervisor E. Gugallis, Station Technician

• hl. Hadfield, Operations Assistant

' R. Haight, Radioactive hiaterials Handling Supervisor

• J. Hawkins, Senior Station Technician

• T. hicDonald, hiaintenance hianager -

• R hicGrath, Radiological Engineering Supervisor

• W. Nevelos, Health Physics hianager f J. Powell, Senior Radiation Protection Technician

• D. Ray, Director, Nuclear Services

• ht. Sweeney, Radiation Protection Supervisor - Services 1,2 NRC Personngl P. Habighorst, Resident Inspector

• W. Raymond_, Senior Resident Inspector o * Denotes those present at the exit interview on December 17, 1992,-

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The purpose of this safety and health inspection was to review the licensee's programs for radiation safety during normal operations. Inspection areas included radiological t work control and housekeeping, ALARA, dosimetry and trainin , Previously identified items (Closed) Inspector Follow Up Item (50-213/92-1101) Posting _of radiation area'.

boundaries. The licensee conducted an evahiation of the current posting practices y '

utilized in the outside yard area, which represents the bulk of the Radiologically Controlled Area (RCA) during normal power operations, and concluded that ti'e posting of discrete radiation area boundaries was impractical due to the need for the a

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movement and storage of materials, both radioactive and non-radioactive, throughout -

the yard area. As'part of its preparations for implementation of the "new" 10 CFR y- Part 20,'the licensee was preparing to evaluate all radiological postings at both J

.Haddam Neck and hiillstone, and would implement any necessary changes on January -

1,1994. This item is closed.

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(Open) Violation (50-213/92-16-01) Failure to perform Technical Specification required audit of the Process Control Program (PCP) every 24 months. The licensee conducted audit A60299 (Radwaste/PCP, Conaceticut Yankee) to meet the Technical Specification requirement, in August 1992. Additional corrective actions involving the development of a computerized matrix to track audit requirements were scheduled for completion by January 31,1993. This item remains open pending licensee completion and NRC review of Inis long term corrective actio . Radiation Prettqtion Program As mentioned in earlier inspection reports, the licensee developed and has now implemented a llealth Physics Department reorganization. The new structure has three supervisors; Radiological Engineering, Radiation Protection and Radiation Protection Services. These supervisors report directly to the Health Physics Manager. The Radiological Engineering section is responsible for: engineering evaluations; ALARA planning, reviews, controls and monitoring; radwaste systems; program effectiveness evaluations; regulatory standards review and complihnce; the Whole Body Counter and count room program; internal dose assessment; outage planning; and special projects. All support positions within this organization, with the exception of the ALARA Coordinator, were filled at the time of this inspectio IW te ALARA Coordinator position could be filled, the previous ALARA coordinator was detailed to provide continuing support to this program area. The Radiation Protection vetien is responsible for: Personnel monitoring; job coverage;

~-r.t a,om operations; fire brigade; unconditional release of materials; radioactive material handling and processing; radwaste shimnent and disposal, tool and area decontamination; and procedures review and rmslon. The Radiation Protection Services section is responsible for: dosimetry; health physics records; whole body counting; respirator qualificion; instrument calibration; the 10 CFR 20 revision project; and the internal audit progra .1 As Low As Reasonably Achievable (ALARA) Progra As noted above, responsibility for the development of the ALARA program rests with the ALARA Coordinator, who reports to the Radiological Ngineering Supervisor. At the time of this inspection, the licensee was waluating applicants for this open position, and planned to have the position Gled by the end of January 1993. For 1992, the licensee had established an ALARA goal of not more than 193.4 Person. Rem. Due to the extended length and scope of the 16th refueling outage, which was not completed until March 16, 1992, the licensee exceeded its budget of 119.7 Person-Rem for the outage in 1992 by 46.7%. Since the close of the outage, the licensee has been well within its budget of 73.7 Person-Rem for non-outage operations for the remainder of 1992, and it appears that the licensee will finish the year only 10% over its initial goal, i

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As part of its llealth Physics Department reorganization, the licensee had l recently created a position of Station Technician to support the computer generation of surveys, reports and graphics. _ The Station Technician attended the morning meetings of the Maintenance Department in order to better coordinate the efforts of the licalth Physics Department in supporting work being conducted in the RCA, in addition, the scope and depth of data being ;

maintained by the Station Technician, and its availability and use by the station ,

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staff, was a notable licensee strengt l The lleensee had developed a Radiation 11xposure Reduction program for the years 1992 through 1996, with the emphasis on dose rate reduction in the

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containment. As the data above indicates, the licensec's exposures during normal power operations are comparable to other pWRs in the United State ;

liowever, during outages the licensee experiences higher exposure rates due to signincant radiation levels in the pump bays of the containment. The _

l licensee's goal by 1996 is to be at the Institute for Nuclear Power Operation (INPO) established three year average of 185 Person Rem per year. In order to meet this goal, the licensee's ALARA staff identl0cd twenty dose reduction techniques, some of which have already been implemented at lladdam Nec !

Included in this listing was: liigh 11 oration Shutdown for use at the end of-eycle 17 operations; ultrafine filters, which the licensee had installed in the Chemical and Volume Control System (CVCS), down to 0.2 micron porosity; and Zircalloy Puel Cladding, with the first batch of Zircalloy clad fuel placed

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in the reactor as part of the sixteenth refueling outage. Also proposed were zine injection and full system decontaminations, lloth would require significant engineering studies and major outlays of capit2d in order 30 be institute .2 Work Control and flousekeeping As part of this inspection, tours of many of the accessible areas of the RCA were conducted in general, the RCA was found to be well maintained with no significant housekeeping, posting or contamination problems noted. Since the inspector's last visit to the site in July 1992; a significant reduction in the size and number of contaminated areas was noted. - This reduction in contaminated areas reduces radwaste generation, improves the case with which workers can accomplish their jobs, and reduces the chances for personnel l

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contamination During the evening prior to the start of this inspection, the licensee identlSed a problem with the control over one of its locked liigh Radiation Areas (LilRA). This represents the third LilRA event at the facility in 1992i In this instance, an Auxiliary Operator (AO), while performing his shift rounds,

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entered the Spent Resin Iluilding from the RCA yard. ' This building had been

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posted one week earlier as a LilRA. A hasp and LliRA padlock were attached to the door leading to this area with appropriate postings placed on the door. The AO unlocked the door to enter the area, remained for less than one minute in the Spent Resin llullding, and then exited the lluilding. Upon exit, the AO failed to secure the LilRA padlock. A second kick, permanently attached as part of the door, engaged when the door was closed, The AO recalled verifying that the door was locked, but did not remember that the ,

LilRA padlock also needed to be secured. Although the licensee's procedure for maintaining the LilRA control required use of the LilRA padlock, the area was never accessible to an inadvertent intruder and was clearly posted as a LilRA. In response to previous LilRA problems, the licensee had installed

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audible and visual alarms on the permanent LilRA doors, llowever, such an -

alarm was not present at the Spent Resin lluilding entrance because it was only a temporary LilR The licensee, upon discovering the LilRA problem, began an investigation to identify the cause of the event and notined this inspector upon his arrival at the site. The licensee interviewed the AO, requested a iluman Performance

!! valuation, and in general took the event very seriously. Suggested corrective ,

actions were viewed from both a short and long term plant-wide perspectiv "

Discussions with licensee personnel indicated that an aggressive LilRA control program was in place at 11addam Neck. Key control, which had been identined by the NRC as a concern several years earlier, had been significantly improved. Access control for the RCA was observed to be a licensee strength. This event appears to be isolated and not reDective of a i

breakdown or significant weakness in the licensee's Locked liigh Radiation Area control progra ,

4.3 Dosimetry  ;

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The lleensee's dosimetry program was under the direction of the Radiatio Protection Services supervisor and included respiratory protection, external and internal dosimetry and all radiation protection records. As part of this inspection, a review of randomly selected dosimetry records was conducte .

All files were for current plant employees or contractors, and were found t contain, where appropriate, NRC Forms 4 and 51 of6cial verineation of ,

previous dose received at other facilities and licensecs; medical approvals for the wearing of respirators, along with respirator 6t testing data; internal dose-assessments; and approvals for dose extensions. No discrepancies were noted in these records, s

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4,4 Training The license had developed three training programs for radiation protection  ;

technicians including initial training, continuing training, and contractor technician training. Both initial and continuing training included significant ,

systems training. - The continuing training program stressed the radiological conditions associated with plant systems at normal power operations, during -

outages, and during emergency situation _

Continuing training for 1993 was scheduled to include two training sessions-totaling 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />, plus an additional 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> available for industry updates, revisions to procedures (especially for the implementation of the new 10 CFR -

Part 20), and other instruction as deemed appropriate by the Training and licalth Physics Department managers. Discussions with Ilealth Physics -;

Department managers indicated that there was, in general, good responsiveness on the part of the Training Department to llP training needs. There were frequent communications between the departments regarding the training-progra The licensec's Training Department has led the way in the development of a  ;

national registry of contractor health physics technicians, including training' i qualifications. The licensee developed a basic knowledge training manual and examination for incoming contractor technicians, and was developing a similar program for basic job skills. This program has promoted better utilization of *

the limited iraining time available for preparing contractor technicians for work during outages by allowing more time (9 be spent on site specific training issues. The national registry of contractor technicians contains -

information concerning who has taken the examh:ation, their examination score, and the date of testing. This registry allows the licensee to pre-approve contractor technicians for work at Ifaddam Neck, and to waive the testing if the contractor took the examination within the past two years and passed the examination with a score that is acceptable to the licensee. This is a notable achievement for the licensee. -The registry represents a significant expenditure of manpower and fmancial resources that has led to significant improvement in the licensee's contractor technician training progra . Exit . interview

~ The inspector met with the licensee representatives denoted in Section 1 at the conclusion of the inspection on December 17, 1992. The inspector summarized the purpose, scope and rmdings of the inspectio ;

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