ML20154R877
| ML20154R877 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/19/1986 |
| From: | Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20154R875 | List: |
| References | |
| 50-423-86-05-MM, 50-423-86-5-MM, NUDOCS 8603310233 | |
| Download: ML20154R877 (4) | |
See also: IR 05000423/1986005
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-423/86-05
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Docket No.
50-423
Licensee:
Northeast Nuclear Energy Company
P. O. Box 270
Hartford, Connecticut
06101
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Facility Name: Millstone Unit 3
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Meeting at:
Region I Office, King of Prussia, Pennsylvania
Date:
March 13, 1986
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Prepared by:
R. J. Summers, Project Engineer
Approved by:
de b02A
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E. C. McCabe, Chief, Reactor Projects Section 3B
Date
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Meeting Summary
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The meeting was held at licensee request.
The licensee presented their findings
on-events that have occurred since January 31, 1986, and the corrective actions
taken.
NRC Region I noted that the licensee was addressing problems and stated
that the frequency and causes of trips and other events were receiving ongoing NRC
review.
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ADOCK 05000423
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DETAILS
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Licensee Attendees
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E. Mroczka, Vice President, Nuclear Operations
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W. Romberg, Station Superintendent, Millstone
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R. Laudenat, Manager, Licensing
J. Crockett, Superintendent, Millstone Unit 3
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2.
NRC Attendees
T. Murley, Regional Administrator
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R. Starostecki, Director, Division of Reactor Projects (DRP)
S. Ebneter, Director, Division of Reactor Safety (DRS)
W. Kane, Deputy Director, DRP
E. Wenzinger, Chief, Projects Branch No. 3, DRP
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L. Bettenhausen, Chief, Operations Branch, DRS
E. McCabe, Chief, Reactor Projects Section 3B, DRP
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J. Shedlosky, Senior Resident Inspector
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J. Prell, Reactor Engineer, DRS
C. Rossi, Assistant Director, PWR-A, NRR
L. Crocker, Section Leader, NRR
E. Doolittle, Licensing Project Manager, NRR
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Licensee Presentation
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The licensee presented a review of plant incidents and reportable events that
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have occurred during the startup program.
Actions taken have included im-
proving procedures and also operating shift review of the events for training
purposes to try to prevent recurrence.
The licensee's presentation outline
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is attached to this report as Enclosure 1.
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4.
Meeting Results
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The licensee presented their approach to self evaluation based upon the events
and performance to date.
The NRC will continue to monitor the startup program
closely to determine if the licensee's analysis and corrective actions for
these events have been effective.
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ENCLOSURE 1
LICENSEE EVENT REPORTS / PLANT INCIDENT REPORTS SINCE 1/31/86
1
EVENT
DESCRIPTION
CAUSE
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LER 86-9
Feedwater Isolation (FWI) signal was generated due to Equipment
high levels in Steam Generators 1 and 4, at 6% power.
Failure
at 6% power.
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LER 86-11
Control Building Isolation (CBI) signal was generated Equipment
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due to a noise spike, in Mode, 3, at normal operating Failure
temperature and pressure.
LER 86-13
FWI signal was generated due to a high level in Steam Equipment
Steam Generator 2, at 15% power.
Failure
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PIR 66-86
Reactor Trip occurred due to two simultaneous Solid
Equipment
State Protection System (SSPS) General Warning Alarms, Failure
at 15% power.
LER 86-10
Reactor Trip occurred due to a low level in Steam
PATP Related
Generator 2, at 15% power.
PIR 57-86
FWI was generated due to high level in Steam Generator PATP Related
3, at 15% power.
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PIR 65-86
Reactor Trip occurred during a low steam generator
Personnel
level, at 29% power.
Error
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PIR 67-86
FWI signal generated due to high level in Steam
Personnel
Generator 1, in Mode 3, at normal operating tempera-
Error
ture and pressure.
LER 86-7
Determined that the LC0 for Technical Specification
Administrative
3/4.8.4.1 was not met, at 3% power.
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LER 86-8
Determined that the LC0 for Technical Specification
Administrative
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3/4.3.3.10 was not met, at 3% power.
PIR 63-86
Reactor Trip occurred due to a low level in Steam
Personnel
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Generator 1, at 15% power.
Error
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PIR 74-86
A Safety Injection Signal was received from a low
Personnel
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pressure condition in all four steam generators, in
Error
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Mode 3.
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Enclosure 1
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EVENT
DESCRIPTION
CAUSE
PIR 75-86
RCS loop 2 hot leg injection valve, 3SIL*V932, found
Administrative
to be danger tagged shut instead of locked open, in
Mode 3, at normal operating temperature and pressure.
PIR 76-86
Safety Injection Signal was received from the rate
Personnel
compensated low steam generator pressure actuation
Error
logic, in Mode 3, at normal operating temperature
and pressure.
The following incidents, while still a cause for concern, do not represent a pro-
grammatic breakdown.
Four are directly attributable to equipment failures.
Two
are personnel error resulting from the extenuating circumstances of the Power As-
cension Test Program (PATP).
Two are personnel error of the type that can be ex-
pected during the startup of any new plant.
Equipment Failure
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LER 86-9
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LER 86-11
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LER 86-13
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PIR 66-86
PATP Related
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LER 86-10
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PIR 57-86
Personnel Error
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PIR 65-86
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PIR 67-86
The following incidents represent programmatic problems.
Two are due to inade-
quacies in the tracking of surveillances required by LC0 Action Statements.
Action
to prevent recurrence is being aggressively pursued.
One is the result of not
completing the action to prevent recurrence from another incident.
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LER 86-7
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LER 86-8
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PIR 63-86
The following incidents are the result of the events on February 28/ March 1, 1986.
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PIR 74-86
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PIR 75-86
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PIR 76-86
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