ML020910616
| ML020910616 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire  |
| Issue date: | 03/20/2002 |
| From: | Uttal S NRC/OGC |
| To: | Olson M - No Known Affiliation |
| Byrdsong A | |
| References | |
| +adjud/rulemjr200506, 50-369-LR, 50-370-LR, 50-414-LR, ASLBP 02-794-01-LR, RAS 4137 | |
| Download: ML020910616 (5) | |
Text
÷*oV egs REG4
'I"UNITED STATES 0,
NUCLEAR REGULATORY COMMISSION IS
,WASHINGTON, D.C. 20555-0001 March 20, 2002 OFFICE OF THE GENERAL COUNSEL Mary Olson Southeast Director of NIRS P.O. Box 7586 Asheville, NC 20882
Dear Ms. Olson:
Pursuant to the Staff's agreement to forward Daily Event Reports (DERs) relating to McGuire Nuclear Station, Units 1 & 2, and Catawba Nuclear Station, Units 1 & 2, enclosed please find three DERs.
Sincerely,
/
Susan L. Uttal Counsel for NRC Staff cc w/encls: J. Zeller D. Repka cc w/o encls: Service list
POWER REACTOR I
FACILITY: CATAWBA UNIT:
[ 1 [2]
[ ]
RX TYPE:
[1] W-4-LP, [2] W-4-LP REGION:
2 STATE: SC NRC NOTIFIED BY: ED BREWER HQ OPS OFFICER:
LEIGH TROCINE EMERGENCY CLASS: NON EMERGENCY 10 CFR SECTION:
AINV INVALID SPECIF SYSTEM ACTUATION NOTIFICATION DATE:
NOTIFICATION TIME:
EVENT DATE:
EVENT TIME:
LAST UPDATE DATE:
12/11/01 17:16
[ET]
10/17/01 10:39 [EST]
12/11/01 NOTIFICATIONS LEONARD WERT R2 UNIT SCRAM CODE RX CRIT INIT PWR[
INIT RX MODE CURR PWR CURR RX MODE 2
A N
0 Cold Shutdown 0
Cold Shutdown EVENT TEXT INVALID ACTUATION OF THE REACTOR PROTECTION SYSTEM WHILE THE UNIT WAS IN COLD SHUTDOWN (60-Day Report)
The following text is a portion of a facsimile received from the licensee:
"This 60-day optional report, as allowed by 10CFR50.73(a) (1),
is being made under the reporting requirement in 10CFR50.73(a) (2) (iv)
(A) to describe an invalid actuation of a specified system, specifically the reactor protection system (RPS).
On October 17, 2001, at 1039 with Unit 2 in MODE 5 with a boron concentration of 2531 ppm, an invalid reactor trip signal was generated from 2 out of 4 logic for overtemperature delta-T.
The reactor trip breakers opened as designed upon receipt of the invalid reactor trip signal.
All control rods and shutdown rods were already fully inserted before the invalid reactor trip signal trip signal was generated.
At the time of the invalid reactor trip signal, reactor protection channel III had been properly removed from service for maintenance testing.
Other maintenance technicians were in the process of setting up test equipment in reactor protection channel I for upcoming resistance temperature detector cross calibrations.
The technicians thought that the place where they were connecting the test equipment was isolated from the circuit and would have no effect on the plant.
During the connections, a momentary spike occurred on reactor protection channel I.
This completed the 2 out of 4 logic for an overtemperature delta-T reactor trip, and a reactor trip occurred.
The control room operators entered appropriate procedures and verified proper equipment operation for the existing plant conditions. Both trains A [and]
B of the reactor protection system actuated.
This was a complete actuation, and the system performed as designed for the existing plant conditions.
This event has been entered into the site-specific corrective (Continued on next page)
EVENT NUMBER:
38557
FACILITY:
CATAWBA PAGE # 2 OF EVENT NUMBER: 38557 action program for resolution."
The licensee notified the NRC resident inspector and plans to notify applicable state, county, and local agencies.
POWER REACTOR I
FACILITY: MCGUIRE UNIT:
[ ]
[2]
[ I RX TYPE:
[E] W-4-LP, [2] W-4-LP REGION:
2 STATE: NC NRC NOTIFIED BY: WAYNE HOYLE HQ OPS OFFICER:
BOB STRANSKY EMERGENCY CLASS: UNUSUAL EVENT 10 CFR SECTION:
AAEC EMERGENCY DECLARED NOTIFICATION DATE:
NOTIFICATION TIME:
EVENT DATE:
EVENT TIME:
LAST UPDATE DATE:
01/15/02 10:14 [ET]
01/15/02 09:55 [EST]
01/15/02 NOTIFICATIONS BRIAN BONSER ROBERT DENNIG TONY CEGIELSKI R2 NRR FEMA UNIT SCRAM CODE RX CRIT INIT PWR INIT RX MODE CURR PWR CURR RX MODE 2
N Y
100 Power Operation 100 Power Operation EVENT TEXT UNUSUAL EVENT DECLARED AND EXITED The licensee entered and exited an Unusual Event due to a leak from the Chemical and Volume Control System (CVCS) that was caused by the lifting of a relief valve. During valve maintenance on a line tagged out as isolated, the opening of a valve caused pressure in the line to exceed that of a relief valve, causing flow to the Unit 1 Boric Acid Storage Tank (BAST).
The licensee is sampling the tank to ensure operability of the tank. The NRC resident inspector has been informed of this event by the licensee.
IVfN:T:MUBR 38630 I
POWER REACTOR E
FACILITY: MCGUIRE UNIT:
[I]
[ ]
[ I RX TYPE:
[1] W-4-LP, [2] W-4-LP REGION:
2 STATE: NC NRC NOTIFIED BY: PHILLIP THOMPSON HQ OPS OFFICER:
MIKE NORRIS EMERGENCY CLASS: NON EMERGENCY 10 CFR SECTION:
ARPS RPS ACTUATION -
CRITICAL AESF VALID SPECIF SYS ACTUATION NOTIFICATION DATE:
NOTIFICATION TIME:
EVENT DATE:
EVENT TIME:
LAST UPDATE DATE:
03/04/02 10:13
[ET]
03/04/02 08:41 [EST]
03/04/02 NOTIFICATIONS CAUDLE JULIAN R2 UNIT SCRAM CODE RX CRIT INIT PWR INIT RX MODE CURR PWR CURR RX MODE 1
M/R Y
100 Power Operation 0
Hot Standby EVENT TEXT MANUAL REACTOR TRIP DUE TO LOSS OF FEEDWATER "Manual reactor trip due to falling level in 1A Steam Generator (S/G),
(RPS Activation).
Level decrease occurred after the Feedwater Regulating Valve (FRV) for the 1A S/G failed closed upon loss of the normal and backup electrical power to the valve solenoid. After the reactor trip, the 1A S/G experienced a LO-LO Level Alarm which auto started both motor driven Auxiliary Feedwater pumps, (ESF Actuation).
All S/G levels are now at normal levels and Unit 1 is stable.
An investigation is in progress to determine the loss of electrical power to the FRV solenoid for the 1A SIG."
The plant is dumping steam to the Main Condenser with no known Primary/Secondary leakage.
There was no actuation of primary safety valves.
All safety systems are operable and normal electrical distribution is available.
The NRC Resident Inspector has been notified.
EVENT NUMBER:
38748 I