ML20129E550
| ML20129E550 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/25/1996 |
| From: | Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Cross J DUQUESNE LIGHT CO. |
| References | |
| EA-96-244, NUDOCS 9610010106 | |
| Download: ML20129E550 (19) | |
See also: IR 05000334/1996005
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September 25, 1996
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EA 96-244
Mr. J. E. Cross
President
Generation Group
Duquesne Light Company
Post Office Box 4
Shippingport, Pennsylvania 15077
SUBJECT: NRC ENFORCEMENT CONFERENCE MEETING SUMMARY
Dear Mr. Cross:
This refers to the predecisional enforcement conference held between your staff and NRC
representatives on August 28,1996, at the NRC Region I office. The purpose of this
enforcement conference was to discuss the apparent violation identified in NRC Inspection
Report Nos. 50-334/96-05 and 50-412/96-05, being considered for escalated enforcement
action in accordance with the " General Statement of Policy and Procedures for NRC
Enforcement Actions" (Enforcement Policy), NUREG-1600. The apparent violation was the
failure to comply with 10 CFR 50.62 which requires a reliable system to provide an
alternate means of tripping the turbine and actuating auxiliary feedwater under conditions
indicative of an Anticipated Transient Without Scram (ATWS).
During the meeting, your staff presented the details of the event during which the ATWS
Mitigating System Actuation Circuitry (AMSAC) failed to respond as expected. New
information, not available during the inspection, was presented regarding the lifting of a
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feedwater relief valve and its correspondence to the fluctuations observed in feedwater
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flow during the event. In addition, your staff described the identification of the AMSAC -
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problem, the root cause, and the corrective actions taken to prevent recurrence. The
status of efforts of a focused design review being' performed on AMSAC and three other
systems was discussed.
In concluding remarks, Mr. Miller emphasized the importance of an on-going engineering
sensitivity for potential design issues.
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A copy of the handout material used by your staff in this predecisional enforcement
conference is attached.
By separate correspondence, dated September 11,1996, you have been advised of the
results of our deliberations on this matter.
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QLQ
9610010106 960925
s
ADOCK 05000334.
G
PDR a
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J. E. Cross
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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.
Sincerely,
James T. Wiggins, Director
Division of Reactor Safety
Docket Nos. 50-334
50-412
Enclosures:
1. Attendance List
2. Handout Material
cc w/encis:
Sushil C. Jain, Vice President, Nuclear Services
T. P. Noonan, Vice President, Nuclear Operations
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L. R. Freeland, Manager, Nuclear Engineering Department
B. Tuite, General Manager, Nuclear Operations Unit
K. L. Ostrowski, Manager, Quality Services Unit
R. Brosi, Manager, Nuclear Safety Department
M. Clancy, Mayor
Commonwealth of Pennsylvania
State of Ohio
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J. E. Cross
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Distribution w/encts:
Region I Docket Room (with concurrences)
PUBLIC
Nuclear Safety Information Center (NSIC)
D. Screnci, PAO
NRC Resident inspector
P. Eselgroth, DRP
D. Haverkamp, DRP
J. Shannon, DRS
W. Ruland, DRS
M. Kalamon, DRP
D. Kern, Surry Site, Ril
J. Stolz, NRR
D. Brinkman, NRR
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W. Dean, OEDO
R. Zimmerman, ADPR, NRR
J. Goldberg, OGC
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J. Lieberman, OE (OEMAIL)
D. Holody, EO, RI
Inspection Program Branch, NRR (IPAS)
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R. Correia, NRR
R. Frahm, Jr., NRR
DRS File
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DOCUMENT NAME: A:\\ECSUMARY.BV
Ta receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure
'E' = Copy with attachment / enclosure
'N' = No copy
0FFICE
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NAME
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DATE
09/24/96
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0FFICIAL RECORD COPY
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MEETING ATTENDEES
Beaver Vallev Power Station
J. Arias
Director, Licensing
R. Brosi
Manager, Nuclear Safety
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J. Cross
Senior Vice President
R. Fedin
Supervisor, independent Safety Engineering Group
K. Halliday
Director, Electrical Engineering
U. S. Nuclear Reaulatory Commission
A. Blough
Deputy Director, Division of Reactor Safety
P. Eselgroth
Chief, Branch 7, Division of Reactor Projects
J. Ganiere
Electrical Engineer, Office of Nuclear Reactor Regulation
D. Holody
Manager, Office of the Regional Administrator
H. Miller
Regional Administrator
W. Ruland
Chief, Electrical Engineering Branch, DRS
J.Shannon
Reactor Engineer, Electrical Engineering Branch, DRS
K. Smith
Regional Counsel
K. Young
Reactor Engineer, Electrical Engineering Branch, DRS
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Pennsvivania Deoartment of Environmental Resources
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M. Murphy
Bureau of Radiation Protection
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Predecisional Enforcement
Conference
Beaver Valley Power Station
August 28,1996
King of Prussia, PA
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Predecisional Enforcement Conference
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Duquesne Light Participants
+ J. E. cross
Sr. V.P. and ChiefNuclear Officer
+ R. K. BroSi
Manager, Nuclear Safety
+ J. Arias
Director, Licensing
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+ K. E. Halliday
Director, Electrical Engineering
+ R. W. Fedin
Supervisor, ISEG
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Agenda
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+ OpeningRemarks
+ AMSAC Background
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+ Problem Identification & Immediate Corrective Actions
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+ Preliminary Reviews & Industry Notifications
+ Root Cause Analysis
+ Additional Corrective Actions
+ Comarehensive Actions to Prevent Recurrence
+ Focused Design Reviews
Safety Significance and Closing Remarks
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AMSAC Background
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+ Designed in response to 10 CFR 50.62
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+ Provide protection against a total loss of
+ Unit 1 1988 (IR7) Unit 21989 (2R4)
+ Foxboro design using Westinghouse
Owners Group generic approved design
+ Initiates on 2/3 Low FW flow signal
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Problem Identification
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+ Unit 1 Turbine / Reactor trip May 31,1996
(LER 1-96-008)
+ Post trip follow-up ISEG Overview
+ Initial assessment: expected respont e to a
unit trip
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Problem Identification (Cont'd)
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+ Multiple timer resets prevented actuation
+ AMSAC timer fluctuations correlates with
FW flow alarms
+ Notified NSS, AMSAC declared inoperable
+ "A" FW flow instrument signal suspected,
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FW system interaction with AMSAC
+ Also applicable to Unit 2
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Immediate Corrective Actions
+ Basis for Continued Operation (BCO)
+ Time limit applied (Admin. LCO) to restore
in 7 days or reduce power to < 40%
+ FW flow instrument calibration identified
"C" instrument
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Preliminary Reviews and
Industry Notification
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+ Reviewed Industry Information available on
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+ Reviewed BVPS availability information
+ Reviewed past BVPS post trip data
+ Initiated Xuclear Network entry to notify
the industry
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Root Cause Analysis
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+ Prior trips with data, AMSAC initiated
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when expected
+ Root cause determined to be design
incompatible with FW pressure pulsations
+ Previous identified design deficiencies
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would not have prevented actuations
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Additional Corrective Actions
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+ Modification to lower setpoint for a flow
instrument failure
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+ Incorporated AMSAC modifications at both
units within the seven day limits
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Comprehensive Actions to
Prevent Recurrence
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+ Conducted a focused design review of both
unit's AMSAC systems
+ Focused design reviews of 3 other systems
+ Basis for the selection of the 3 systems:
-Installed after initiallicensing
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- Customized generic designs
-Include T/S and non-T/S systems
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AMSAC Focused Design
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Review
+ Current design
+ Additional enhancements to improve
reliability:
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- Computer power supply annunciator
- Test matrix development
- Jumper configuration
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Focused Design Review of Other
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+ Inadequate Core Cooling Monitor
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+ Post Accident Sampling System
+ High Energy Line Break Isolation System
+ Results will be reviewed for generic
conclusions with additional corrective
actions as appropriate
+ Schedule for completion
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Safety Significance
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+ Required by 10 CFR 50.62
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+ Low Core Damage Frequency Impact of
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+ If AMSAC was required and did not
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actuate, procedures and training are in place
to ensure manual actions are taken
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Closing Remarks
+ Insightful identification of a subtle initial
design deficiency not likely to be found
through routine efforts or past reviews
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+ Appropriate immediate corrective actions
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+ Comprehensive long term corrective actions
to prevent recurrence
+ Expanded actions to identify similar generic
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