ML20217P762
| ML20217P762 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/18/1997 |
| From: | Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Cross J DUQUESNE LIGHT CO. |
| Shared Package | |
| ML20217P765 | List: |
| References | |
| 50-334-97-05, 50-334-97-5, 50-412-97-05, 50-412-97-5, EA-97-375, NUDOCS 9708280226 | |
| Download: ML20217P762 (4) | |
See also: IR 05000334/1997005
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August 18, 1997
EA No. 97 376
Mr. J. E. Cross
President
Generation Group
Duquesne Light Company (DLC)
Post Office Box 4
Shippingport, Pennsylvania 15077
SUBJECT:
NRC INTEGRATED INSPECTION REPORT 50 334/97 05, 50 412/97 05,
NOTICE OF VIOLATION AND EXERCISE OF ENFORCEMENT DISCRETION
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Dear Mr. Cross:
The NRC conducted an inspection of the Beaver Valley Power Station (BVPS) facilities from
June 8 to July 19,1997. The enclosed report presents the results of that inspection.
During the 6 week period covered by this inspection period, your conduct of activities at
the Beaver Valley Power Station fac'lities was generally characterized by sound
conservative decisions with regard to plant operations. The decision to shutdown Unit 1
on June 27 and to extent the shutdown to perform additional repairs demonstrated a
conservative safety perspective. The Unit 2 shutdown on July 10 was effectively
managed by operators.
Notwithstanding the above, certain performance weaknesses were evident.- Operators on
Unit 1 failed to prevent the inadvertent actuation of the overpressure protection system
due to inattention to slowly rising reactor coolant system pressure. Also, inadequate work
Instructions and poor communications during maintenance troubleshooting e two separate
occasions resulted in an inadvertent actuation of an engineered safety feature and an
emergency shutdown of the emergency response facility diesel generator. These types of
occurences warrant continued management attention to reducing human errors.
Based on the results of this inspection, the NRC hae determined that a violation of NRC
requirements occurred. This violation is cited in the enclosed Notice of Violation, and the
circumstances surrounding the violation are described in detailin the enclosed report. The
violation indicates that troubleshooting activities need increased review and management
attention. Please note that you are required to respond to this letter and should follow the
instructions specified in the enclosed Notice when picparing your response. The NRC will
use your response, in part, to determine whether further enforcement action is necessary
to ensure compliance with regulatory requirements.
.The NRC also reviewed three issues involving past design deficiencies. The first issue
involved reactor protection system trip functions which failed to meet design requirements
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specified in IEEE 2791971. The second issue involved non-seismic emergency diesel
generator fire suppression system actuation relays. The third issue involved containment
isolation check valves which did not meet their design basis requirements. The three
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J. E. Cross
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issues were identified by your staff through voluntary initiatives. The NRC considers your
Initiatives to identify longstanding practices and design issues a strength. Corrective
actions taken and planned were comprehensive and should prevent recurrence. The design
deficiencies were subtle in nature and were not likely to be identified by routine
surveillance or quality assurance activities.
These three design issues are apparent violations of NRC requirements which could be
considered for escalated enforcement and subject to a civil penalty. However, after
consultation with the Director, Office of Enforcement, I have been authorized to not issue a
Notice of Violation and not propose a civil penalty in this case in accordance with the
provisions provided in Section Vll.B.3 of the NRC's Enforcement Policy. This decision was
made after consideration that: (1) the violations were identified by your staff's good
questioning attitudes during voluntary Initiatives; (2) corrective actions, both taken and
planned, were comprehensive and timely; (3) the conditions were subtle in nature and not
likely to be disclosed through routine surveillance or quality assurance activities; and (4)
the violations are not reasonably linked to current performance. The exercise of discretion
acknowledges your good effort to identify and correct subtle violations, that would not be
identified by routine efforts, before_the degraded safety systems are called upon.
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,
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Hubert J. Miller
Regional Administrator
Docket Nos. :- 50 334, 50 412
License Nos.: DPR 66, NPF 73
Enclosures:
2.- Inspection Report 50-334/07 05, 50 412/97-05
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J. E. Cross
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cc w/encts:
S. Jam, Vice President, Nuclear Services
R. LeGrand, Vice President, Nuclear Operations
B. Kline, Manager, Nuclear Engineering Department
B. Tulte, General Manager, Nuclear Operations Unit
K. Ostrowski, Manager, Quality Services Unit
J. Arias, Director, Safety & Licensing Department
M. Clancy, Mayor
Commonwealth of Pennsylvania
State of Ohio
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J. E. Cross
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Distribution w/encis:
Region I Docket Room (with concurrences)
PUBLIC
Nuclear Safety Information Center (NSIC)
NRC Resident inspector
H. Miller, ORA
D. Screnci, PAO (2)
W. Axelson, DRA
D. Holody, ORA
B. Fewell, ORA
J. Lieberman, OE
P. Eselgroth, DRP
D. Haverkamp, DRP
A. Keatley, DRP
Distribution w/encle (VIA E MAIL):
J. Stolz, NRR
D. Brinkman, NRR
W. Dean, OEDO
Inspection Program Branch, NRR (IPAS)
R. Correla, NRR
F. Talbot, NRR
DOCDESK
Inspection Program Branch, NRR (IPAS)
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