ML20056G976
| ML20056G976 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/31/1993 |
| From: | Bettenhausen L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Denton R BALTIMORE GAS & ELECTRIC CO. |
| Shared Package | |
| ML20056G977 | List: |
| References | |
| NUDOCS 9309080023 | |
| Download: ML20056G976 (3) | |
See also: IR 05000317/1993023
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AUG 311993
Docket Nos. 50-317
50-318
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Mr. Robert E. Denton
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Vice President - Nuclear Energy
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Baltimore Gas and Electric Company
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Calvert Cliffs Nuclear Power Plant
1650 Calvert Cliffs Parkway
Lusby, Maryland 20657 - 4702
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Dear Mr. Denton:
SUBJECT: SPECIAL INSPECTION REPORT NOS. 50-317/93-23 AND 50-318/93-23
During the period of July 6 through 9,1993, a special inspection was conducted at the
Calvert Cliffs Power Plant, Units 1 and 2. Subsequent to the on site inspection, an in-office
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review of the gathered information was performed between July 12 and July 30,1993. The
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onsite inspection and subsequent review was conducted to address Region I concerns that a
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number of recent operational events represented an adverse trend in performance and a
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decline in your ability to address and correct problems within your operational activities.
Specifically, between June 8 and July 1,1993, four Reactor Protection System (RPS)
actuations occurred, and one event involving improper restoration of a service water heat
exchanger almost resulted in a complete loss of the service water system. Based on this
inspection, we have concluded that there was no common root cause for these events and that
your reviews and proposed corrective actions are appropriate. We do note that one primary
root cause, inadequate job preparation, was a strong contributor in three of the five evente.
We will continue to review your operational activities; however, we do not believe that
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increased NRC inspection emphasis is needed at this time.
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The inspection was conducted using the guidance contained in NUREG/CR-5455 Volumes 1
and II, Human Performance Investigation Process (HPIP). To limit the scope of the
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inspection, the last two events - a reactor trip due to low steam generator later level and
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improper restoration of a service water (SRW) heat exchanger - were reviewed i.7 <iepth.
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The NRC review detennined the root cause(s) and contributing factors of tnese ments
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independent of the facility review. NRC results were then compared with the results of the
facility review. The results of the facility and NRC reviews closely paralleled each other.
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OFFICIAL RECORD COPY
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9309080023 930831
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Mr. Robert E. Denton
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AUG 311993
The results of the facility reviews of the other three events were also reviewed by the NRC
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subsequent to the site inspection to evaluate the level of detail, facility assignment of root
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cause(s), and any commonality between all five of the events. Based on our review, three of
the five events had a primary root cause of failure to prepare adequately, either by thorough
preevolution briefings or a questioning attitude of personnel involved, for the evolutions that
were to take place during the operations shift.
The inspectors briefed the plant general manager and other plant personnel on July 9,1993,
on the status of the inspection. During the briefing, the inspectors presented preliminary
information gathered during the inspection and discussed further NRC evaluation to be
conducted prior to discussion of final inspection results.
On July 30,1993, a final exit meeting was conducted by Mr. Briggs with Mr. Cruse and
other members of your staff identified in Attachment 3. During the meeting, the details and
findings of the inspection were discussed and compared with those from your staff's analysis.
In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter and
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its enclosure will be placed in the NRC Public Document Room.
No reply to this letter is required; but, should you have any questions regarding this
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examination, please contact the undersigned.
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Sincerely,
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g(iginal SIEUBd OY
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Lee H. ggeham
Im H. Bettenhausen, Chief
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Operations Branch
Division of Reactor Safety
Enclosure:
Special Inspection Report Nos. 50-317/93-23 and 50-318/93-23
with Attachments 1,2, and 3
Attachments:
1. HPIP Events and Casual Factor (E&CF) Chart,
Low Steam Generator Level Reactor trip
2. HPIP E&CF Chart, SRW Heat Exchanger Return to Service
3. Partial Listing of Personnel Contacted
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OFFICIAL RECORD COPY
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Mr. Robert E. Denton
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Aug 3 y
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cc w/ encl and attachments:
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G. Detter, Director, Nuclear Regulatory Matters (CCNPP)
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R. McIzan, Administrator, Nuclear Evaluations
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J. Walter, Engineering Division, Public Service Commission of Maryland
K. Burger, Esquire, Maryland People's Counsel
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R. Ochs, Maryland Safe Energy Coalition
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K. Abraham, PAO (2)
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Public Document Room (PDR)
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I_ocal Public Document Room (LPDR)
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Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
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State of Maryland (2)
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bec w/ encl and attachments
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Region I Docket Room (with concurrences)
C. Cowgill, DRP
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L. Nicholson, DRP
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D. Weaver, DRP
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P. Wilson - Calvert Cliffs
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V. McCree, OEDO
R. Capra, NRR
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D. Mcdonald, NRR
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L. Briggs, DRS
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Greg S. Galletti, HFAB/NRR
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NOTIFY VIA E-MAIL AND NO ATTACIIED FILE:
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L. Bettenhausen, DRS
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G. Meyer, DRS
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RI:DRS
RI:DRS
RI:DRS
Briggs
Meyer
ausen
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08/26/93
08/}#93)
089y/93
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OFFICIAL RECORD COPY
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