05000219/LER-2003-003, Regarding Actuation of Reactor Protection System Due to Grid Transient
| ML032810189 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/26/2003 |
| From: | Harkness E AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2130-03-20249 LER 03-003-00 | |
| Download: ML032810189 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(x)(A) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)()(B) 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 2192003003R00 - NRC Website | |
text
AmerGen SM AmerGen Energy Company, LLC An Exelon/British Energy Company Oyster Creek US Route 9 South RO. Box 388 Forked River, NJ 08731-0388 10 CFR 50.73 September 26, 2003 2130-03-20249 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Oyster Creek Generating Station Facility Operating Ucense No. DPR-16 NRC Docket No. 50-219
Subject:
Licensee Event Report 2003-003-00:
Actuation of Reactor Protection System due to Grid Transient Enclosed is Licensee Event Report 2003-003, Revision 0. This event did not affect the health and safety of the public or plant personnel.
If any further information or assistance is needed, please contact Mr. William Stewart, of my staff, at 609.971.4775.
Very truly yours, Ernest J Harkness P.E., Vice President Oyster Creek Generating Station EJHIRAM Enclosure cc:
Regional Administrator, USNRC Region I USNRC Senior Project Manager, Oyster Creek USNRC Senior Resident Inspector, Oyster Creek File No. 03081
NRC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 6-30-2001 (1-2001)
COMMISSION Estimated burden per response to comply wth this mandatory infbrmaton collection request:
50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Reported lessons learned are corporated into the licensing process and fed back to riustry. Send comments regarding burden estimate to e Records Manaement Branch (T-E6. US.
uclarReglatry ommssinWashington, DC 20555-0001, or by nternet LICENSEE EVENT REPORT (LER)
Ofto is@nrlgov, ad otheOffier Otfice of Information and Re ulato Affairs.
NEOB-10202 (3150-0104). Office o Manapement and Budget Washington C 20503. H a (See reverse for required number of used to impose formation collecton does not display a currently valid OMB control digits/characters or each block) number the NRC may not conduct or sponsor. and a person l not required to respond to. the information collection.
FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
Oyster Creek, Unit 1 05000 219 1 OF 4
TITLE (4)
Actuation of Reactor Protection System due to Grid Transient EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED(S)
FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR NUMBR NO MO DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 08 14 2003 2003 - 003 - 00 09 26 2003 __05000 OPERATING THIS REPORT IS SUBMITTED PURSUANTTOTH REOUIREMENTS OFIOC (Check all that a2dv (11)
MODE (9)
N
_ 20.2201) 20.2203a)(3)0i) 50.73(a)(2)(l1)(B)
_150.73(a)(2)(x)(A)
POWER 20.2201(d) 20.2203(a)(4)
_ 50.73(a)(2)(ilD 50.73(a)(2)(x)
LEVEL (10) 100 202203(a)(1)
_ 50.36(c)(1)()(A)
X 50.73(a)(2)(v)(A) 73.71(a)(4) 202203(a)(2)()
50.36(c)(1)(iA) 50.73(a)(2)(v)(A)
C_.7 1
66A 202203(a)(2)0i)
_ 50.36(c)(2)
_ 50.73(a)(2)(v))
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_ 20.2203(a)(2)(Ii)
_ 50.46(a)(3)(i)
_ 50.73(a)(2)(v)
N C Fom 36 2002203(a)(2)(v)) -
50.73(a)(2)()(B) 50.73(a)(2)(v2i)
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20.2203(a)(3)(_)
50.73(a)(2)(fl)(A) 50.73(a)(2)(vlX)(B)
LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Area Code)
William Stewart I
609.971.4775 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
MAN-1EIORT1B1EMANLU-REPORTABLE
CAUSE
SYSTEM COMPONENT FACTURERE TO EW
CAUSE
SYSTEM COMPONENT FA CTURER TO EPIX SUPPLEMENTAL REPORT EXPECTED (14)
EXPECTED NTH DAY YEAR SUBMISSION YES (ifyes,cmomplete EXPECTED SUBMISSION DATE).
X NO l
DATE (15) 1 I_
l ABSTRACT (Limit to 1400 spaces. i.e.. approxImately 15 sinceo-spaced typewritten Hnes) (16)
On August 14, 2003, an electrical disturbance in the off-site electrical power grid caused an overexcitation condition in the main generator. This resulted in a main generator lockout, turbine trip, and reactor scram from 100% power. The reactor shut down as designed. Plant cooldown to cold shutdown was required due to the trip of all five recirculation pumps (three auto trip and two manual trip). Off-site power was available throughout the event.
The safety significance of this event is considered minimal. The plant responded as designed for this type of event. Technical Specification limits were maintained. There was no radioactive release. Off-site power was not lost. Operator response was appropriate.
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DATE OF DISCOVERY This event occurred on August 14,2003.
IDENTIFICATION OF OCCURRENCE Note: System Identification codes from IEEE 805-1984 are indicated with Si. Component Function Identifiers from ANSI/IEEE 803A-1983 are indicated by CFI.
An electrical disturbance in the off-site electrical power grid (S - FK) caused an overexcitation condition in the main generator (S - TB, CF - GEN & TG). In response to the overexcitation condition, protective relaying (CFI - 86) locked out the main generator which tripped the main turbine (SI - TA, CFI - TRB) and scrammed the reactor (S - AC, CFI - RCT). Off-site power was not lost. Actuation of the Reactor Protection System is reportable under 10 CFR 50.73(a)(2)(iv)(A).
CONDmONS PRIOR TO DISCOVERY The plant was operating at approximately 100% power with all reactor plant pressures and temperatures normal for full power operation. All safety-related equipment was operable.
DESCRIPTION OF OCCURRENCE On August 14,2003, at 1610 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.12605e-4 months <br />, annunciators (CFI - ANN) in the Main Control Room indicated a voltage transient and Main Generator Overexcitation. The sequence of alarms (SI -
IQ) shows that the initial condition was a low voltage and low VAR condition on the main generator. Within seconds, the low voltage alarm (CFI - EA) cleared and over-voltage and over excitation alarms (CFI - IA) were received. About nine seconds later protective relaying locked out the Main Generator which tripped the main turbine and resulted in a reactor scram.
(If more space Is required, use additional copies of (It more space Is required, use addiional copies of NRC FoRm 366A) (7)
CORRECTIVE ACTIONS
Evaluated generator-related electrical components for damage from the transient and determined no repair was needed.
Investigated the problem with the reactor mode switch and determined the locking mechanism was operating properly and no repair was needed.
Training on Mode Switch operating technique will be provided to Operations personnel.
SIMILAR EVENTS
LER 1992-005, Reactor Scram & Engineered Safety Features Actuation caused by Offsite Fire LER 1994-007, Reactor Scram due to Personnel Error while Performing Switchyard Work