ML20141F804

Forwards Insp Rept 50-213/97-01 on 970106-0407 & Nov. Insp Identified Weaknesses in Contamination Controls & ALARA Program

ML20141F804
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/08/1997
From:	Rogge J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Feigenbaum T CONNECTICUT YANKEE ATOMIC POWER CO.
Shared Package
ML20141F808	List: ML20141F804 ML20141F818 ML20141F830
References
50-213-97-01, 50-213-97-1, NUDOCS 9705220056
Download: ML20141F804 (4)

See also: IR 05000213/1997001

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May 8, 1997

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Mr. Ted C. Feigenbaum

Executive Vice President and Chief Nuclear Officer

clo R. A. Mellor, Director

Site Operations and Decommissioning

Connecticut Yankee Atomic Power Company

362 Injun Hollow Road

' East Hampton, CT 06424-3099

. SUBJECT: NRC INTEGRATED INSPECTION REPORT 50-213/97-01

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Dear Mr. Feigenbaum:

On April 7,1997, the NRC completed an inspection at Connecticat Yankee Atomic Power

Compan'y The enclosed report presents the results of that inspection. During the three

month period covered by this inspection period, the conduct of activities at Haddam Neck

focused on maintaining spent fuel pool cooling with the plant in the defueled condition.

The period was marked by a transition to the reduced staffing and organization established

following the cessation of power operations, and the development plans and projects to

decommission the plant. Our review of the radiological environmental monitoring program

(REMP) incorporated selective examinations of procedures and representative records,

interviews with personnel, and observations by the inspector. The REMP at the Haddam

Neck Station was considered overall to be well performed and effective.

Several significant deficiencies occurred during the period. Inadequacies in the procedures

used to calibrate certain radiation mcenitors resulted in the declaration of all gaseous and

liquid effluent monitors required by the technical specifications to be inoperable. A design

deficiency and corrosion induced degradation in the service water piping resulted in

potential challenges to spent fuel pool cooling. The plant staff responded appropriately to

these issues, but had to rely on compensatory sampling and fire hoses for spent fuel

cooling while actions to address these issues were implemented. When viewed together,

the events of this period appear as a continuation of plant material and design

discrepancies that cause continued concern regarding plant operations.

The inspection of radiation protection activiti es identified that as a result of the

November 2,1996, fuel transfer canal event, all radiological work activities that could

challenge the radiological controls program were suspended. We also noted that a number

of program improvements, in response to the fuel transfer canal event were completed and

that no radiologically significant work activities will be performed except as outlined in your

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correspondence dated December 9,1996. Our inspection identified weaknesses in

contamination controls and the ALARA program, which should be addressed to preclude

problems during decommissioning. We expect that your ongoing radiation protection

program review and subsequent actions, taken in response to our March 4,1997,

Confirmatory Action Letter will address our concerns in these areas. We acknowledge

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Mr. Ted C. Feigenbaum 2

your efforts to improve the capabilities of the quality assurance organization through the

addition of individuals with extensive radiological controls experience and experience in

decommissioning. We have not completed our review of your contractor's dose

assessment for the two workers who sustained intakes of radioactive material during the

November 2,1996, event. Consequently, the unresolved item associated with this matter

remains open. In addition, unresolved items were identified concerning release of

contaminated material on February 19,1997, and training of personnel on use of

contamination monitorir;g equipment. Interim actions were taken to restrict the release of

material from the radiological controlled and protected areas pending evaluation of the

event and development and implementation of long term corrective actions. The details of

the NRC review of this matter will be included in a future inspection report.

Several examples of failure to meet license requirements were identified during this

inspection, as described in the enclosed Notice of Violation. The circumstances

surrounding the violations are described in detailin the enclosed report. The violations

concern the f ailure by plant personnel to follow procedures, the failure to adequate

complete technical specification surveillance tests, and the failure correct conditions

adverse to quality. The findings represent a recurrence of concerns the NRC has  !

previously addressed to you, most recently in our letter dated Februery 4,1997 forwarding 1

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Inspection Report 96-13 and a Notice of Violation concerning personnel errors. in our

February 4 letter, you were requested to address your plans to enhance performance

standards along with the actions that will be taken to improve procedural adherence by all

station workers. Your response to us dated February 25,1997 did not address the

broader problem of personnel performance errors. Please give this matter particular

attention in your response to the enclosed Notice. Please note that you are required to

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respond to this letter and should follow the instructions specified in the enclosed Notice

when preparing your response. The NRC will use your response, in part, to determine

whether further enforcement action is necessary to ensure compliance with regulatory

requirements.

In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter l

and its enclosures will be placed in the NRC Public Document Room (PDR),

Sincerely,

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Original Signed By:

John F. Rogge, Chief

Projects Branch No. 8

Division of Reactor Proiects

Docket No. 50-213

License No. DPR-61

Enclosures:

1. Notice of Violation

2. NRC Inspection Report No. 50-213/97-01

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Mr. Ted C. Feigenbaum 3

cc w/ encl:

B. D. Kenyon, President - Nuclear Group

D. M. Goebel Vice President - Nuciear Oversight

J. K. Thayer, Vice President - Recovery Officer, Nuclear Engineering and Support

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F. C. Rothen, Vice President - Work Services

J. J. LaPlatney, Haddam Neck Unit Director

i L. M. Cuoco, Senior Nuclear Counsel

G. P. Van Noordennen, Manager, Nuclear Licensing

H. F. Haynes, Director - Nuclear Training

) J. F. Smith, Manager, Operator Training

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W. D. Meinert, Nuclear Engineer

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State of Connecticut SLO

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Mr. Ted C. Feigenbaum 4

Distribution w/ench

Region l Docket Room (with concurrences)

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PUBLIC

Nuclear Safety Information Center (NSIC)

NRC Resident inspector  ;

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D. Screnci, PAO -

J. Rogge, DRP

M. Conner, DRP

C. O'Daniell, DRP ,.

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Distribution w/enci (VIA E-MAIL):

W. Dean, OEDO - l

S. Weiss, NRR, DRPM, PDND

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M. Fairtile, PM, NRR

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R. Jones, NRR

j M. Callahan, OCA i

W. Travers, SPO

R. Correia, NRR

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D. Taylor, NRR j

s D. Screnci, PAO, ORA

DOCDESK

Inspection Program Branch, NRR (IPAS) r

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DOCUMENT NAME: G:\ BRANCH 8\HN\HN9701.RPT )

To receive a copy of this document, indicate in the box: "C" = Copy without

attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy

OFFICE Rl/DRP 4 l Rl/DRP l j

NAME RAYMONP/// ROGGFf)/ l

DATE ;P;/97 (/f'/97 l

OFFICIAL RECORD COPY

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