ML20141F804
| 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: |
| 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
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. 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'
The enclosed report presents the results of that inspection. During the three
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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 activit es identified that as a result of the
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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
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that no radiologically significant work activities will be performed except as outlined in your
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
9705220056 97050s
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Mr. Ted C. Feigenbaum
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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
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
respond to this letter and should follow the instructions specified in the enclosed Notice
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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.
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In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter
and its enclosures will be placed in the NRC Public Document Room (PDR),
Sincerely,
Original Signed By:
John F. Rogge, Chief
Projects Branch No. 8
Division of Reactor Proiects
Docket No. 50-213
License No. DPR-61
Enclosures:
2. NRC Inspection Report No. 50-213/97-01
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Mr. Ted C. Feigenbaum
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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
F. C. Rothen, Vice President - Work Services
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J. J. LaPlatney, Haddam Neck Unit Director
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L. M. Cuoco, Senior Nuclear Counsel
G. P. Van Noordennen, Manager, Nuclear Licensing
H. F. Haynes, Director - Nuclear Training
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J. F. Smith, Manager, Operator Training
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W. D. Meinert, Nuclear Engineer
State of Connecticut SLO
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Mr. Ted C. Feigenbaum
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Distribution w/ench
Region l Docket Room (with concurrences)
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Nuclear Safety Information Center (NSIC)
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NRC Resident inspector
D. Screnci, PAO
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J. Rogge, DRP
M. Conner, DRP
C. O'Daniell, DRP
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Distribution w/enci (VIA E-MAIL):
W. Dean, OEDO -
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S. Weiss, NRR, DRPM, PDND
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R. Jones, NRR
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M. Callahan, OCA
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W. Travers, SPO
R. Correia, NRR
D. Taylor, NRR
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D. Screnci, PAO, ORA
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DOCDESK
Inspection Program Branch, NRR (IPAS)
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DOCUMENT NAME: G:\\ BRANCH 8\\HN\\HN9701.RPT
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To receive a copy of this document, indicate in the box:
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OFFICE
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