ML20212H356
| ML20212H356 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 04/15/1998 |
| From: | Doerflein L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Cruse C BALTIMORE GAS & ELECTRIC CO. |
| Shared Package | |
| ML20212H360 | List: |
| References | |
| 50-317-98-01, 50-317-98-1, 50-318-98-01, 50-318-98-1, EA-98-173, NUDOCS 9804210354 | |
| Download: ML20212H356 (5) | |
See also: IR 05000317/1998001
Text
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April 15, 1998
EA 98-173
Mr. Charles H. Cruse
Vice President - Nuclear Energy
Baltimore Gas and Electric Company (BGE)
Calvert Cliffs Nuclear Power Plant
1650 Calvert Cliffs Parkway
Lusby, MD 20657- 4702
.
SUBJECT:
NRC REGION 11.'dTEGRATED INSPECTION REPORT NOS. 50-317/98-01
AND 50-318/98-01 AND NOTICE OF VIOLATION
'
Dear Mr. Cruse:
This report transmits the findings of the safety inspection conducted by NRC inspectors at
the Calvert Cliffs Nuclear Power Plant from February 8,1998 to March 14,1998. The
enclosed report presents the results of that inspection. At the conclusion of the
'
inspection, the::e findings were discussed with Mr. Katz and others of your staff.
Overall, the NRC has concluded that your facility was operated in a safe manner. During
the period, we observed continued good control of plant operations. Your efforts to reduce
the number of control room deficiencies and the number of valve, switch, and breaker
mispositionings have been positive. Excellent coordination between operations,
maintenance and systems engineering personnel resulted in prompt and effective
replacement of a power supply in the control element drive system and precluded an
unnecessary plant transient. We also fcund that a good radioactive waste processing,
.
handline, storage, and transportation program was in place. However, technical
weaknesses were identified in the areas of waste concentration averaging, scaling factor
determination, and determination of curie content.
We also found that your staff developed and followed a comprehensiv) process to ensure
all design and quality assurance issues which might have affected the NUTECH Horizontal
Modular Storage System dry shielded canister were resolved. However, your resolution of
the design issues did not identify an unreviewed safety question involving an equipment
'
malfunction of a different r,p than any evaluated previously in the Updated Safety
Analysis Report. Further, your oplication for a license for the independent spent fuel
storage installation did not provide complete and securate information regarding the
behavior of the dry shielded canister during a vertical top end drop accident.
Based on the results of this i.1spection, the NRC has determined that violations of NRC
requirement:, occurred. These vic,lations are cited in the enclosed Notice of Violation
(Notice) and the circumstances surrounding them are described in detail in the subject
inspection report. All of the violations were identified by the NRC, and included: (1) the
failuro to provide complete and accurate information regarding the behavior of the dry
9804210354 980415
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shielded canister in the license application for the independent spent fuel storage
installation; and, (2) failure to identify a that an unreviewed safety question resulted from a
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change in the evaluation of the dry shielded canister vertical top end drop accident.
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You are required to 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,
its enclosure (s), and your response will be placed in the NRC Public Document Room
(PDR).
Sincerely,
Original Signed by:
Lawrence T. Doerflein, Chief
Projects Branch 1
Division of Reactor Projects
Docket / License Nos.:
50-317/DPR-53
50-318/DPR-69
72-8/SNM-2505
Enclosures:
1.
2.
NRC Region 1 Integrated inspection Report Nos. 50-317/9tbO1 and 50-318/98-01
cc w/encis:
T. Pritchett, Director, Nuclear Regulatory Matters (CCNPP)
'
R. McLean, Administrator, Nuclear Evaluations
J. Walter, Engineering Division, Public Service Commission of Ma.yland
K. Burger, Esquire, Marylu.d People's Counsel
R. Ochs, Maryland Safe Er.;rgy Coalition
State of Maryland (2)
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Distribution w/encis:
B. Boger, ADPR, NRR
J. Goldberg, OGC
J. Lieberman, OE (OEMAIL) (2)
H. Miller, RA/W. Axelson, DRA (i)
D. Holody, EO, RI
T. Walker, SES
Nuclear Safety Information Center (NSIC)
PUBLIC
NRC Resident inspector
Region i Docket Room (with concurrences)
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L. Doerflein, DRP
R. Junod, DRP
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Distribution w/ encl: (VIA E-MAIL)
B. McCabe, RI EDO Coordinator
S. Stowart - Calvert Cliffs
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S. Bajwa, NRR
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A. Dromerick, NRR
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M. Campion, RI
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inspection Program Branch, NRR (IPAS)
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R. Correia, NRR
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F. Talbot, NRR
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DOCUMENT NAME: G:\\ BRANCH 1\\CC980101. INS
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
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DATE
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April 15, 1998
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EA 98173
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Mr. Charles H. Cruse
Vice President - Nuclear Energy
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Baltimore Gas and Electric Company (BGE)
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Calvert Cliffs Nuclear Power Plant
1650 Calvert Cliffs Parkway
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Lusby, MD 20657- 4702
SUBJECT:
NRC REGION 1 INTEGRATED INSPECTION REPORT NOS. 50-317/9P 01
AND 50-318/98 01 AND NOTICE OF VIOLATION
Dear Mr. Cruse:
This report transmits the findings of the safety ins, ection conducted by NRC inspectors at
the Calvert Cliffs Nuclear Power Plant from February 8,1998 to March 14,1998. The
enclosed report presents the results of that inspection. At the conclusion of the
inspection, these findings were discussed with Mr. Katz and others of your staff.
Overall, the NRC has concluded that your facility was operated in a safe manner. During
the period, we observed continued good control of plant operations. Your efforts to reduce
the number of control room deficiencies and the number of valve, switch, and breaker
mispositionings have been positive. Excellent coordination between operations,
maintenance and systems engineering personnel resulted in prompt and effective
replacement of a power supply in the control element drive system and precluded an
unnecessary plant transient. We also found that a good radioactive waste processing,
handling, storage, and transportation program was in place. However, technical
weaknesses were identified in the areas of waste concentration averaging, scaling f actor
determination, and determination of curie content.
We also found that your staff developed and followed a comprehensive procers to ensure
all design and quality assurance issues which might have affected the NUTECH Horizontal
Modular Storage System dry shielded canister were resolved. However, your resolution of
the design issues did not identify an unreviewed safety question involving an equipment
malfunction of a different type than any evaluated previously in the Updated Safety
Analysis Report. Further, your application for a license for the independent spent fuel
storage installation did not provide complete and accurate information regarding the
behavior of the dry shielded canister during a vertical top end drop accident.
Based on the results of this inspection, the NRC has determined that violations of NRC
requirements occurred. These violations are cited in the enclosed Notice of Violation
(Notice) and the circumstances surrounding them are described in detail in the subject
inspection report. All of the violations were identified by the NRC, and included: (1) the
failure to provide complete and accurate information regarding the behavior of the dry