05000220/LER-2006-002, Re HPCI Logic Actuation Due to Turbine Trip
| ML062340053 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/11/2006 |
| From: | Hutton J Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 06-002-00 | |
| Download: ML062340053 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(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)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2202006002R00 - NRC Website | |
text
James A. Hutton Plant General Manager P.O. Box 63 Lycoming, New York 13093 315.349.2061 315.349.4308 Fax Constellation Energy, Nine Mile Point Nuclear Station August 11, 2006 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:
SUBJECT:
Document Control Desk Nine Mile Point Nuclear Station Unit No. 1; Docket No. 50-220 Licensee Event Report 06-002. "HPCI Logic Actuation due to Turbine Trip" In accordance with 10 CFR 50.73(a)(2)(iv)(A), we are submitting Licensee Event Report 06-002, "HPCI Logic Actuation due to Turbine Trip."
Should you have questions regarding the information in this submittal, please contact M. H. Miller, Licensing Director, at (315) 349-1510.
Very truly yours, JAH/KSE/sac
Attachment:
(1)
Licensee Event Report cc:
S. J. Collins, NRC Regional Administrator, Region I L. M. Cline, NRC Senior Resident Inspector el 21
ATTACHMENT (1)
LICENSEE EVENT REPORT (LER)
Nine Mile Point Nuclear Station, LLC August 11, 2006
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may not conduct digits/characters for each block) or sponsor, and a person is not required to respond to, the information digis/carater foreac blck)collection.
- 3. PAGE Nine Mile Point Unit 1 05000220 1 OF 4
- 4. TITLE HPCI Logic Actuation Due To Turbine Trip
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE A
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FAILIYNMOKTNME NUMBER NO.I________________
IFACILITY NAME DOCKET NUMBER 06 12 2006 2006 - 002 -
00 08 11 20061
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
El 20.2201(b)
[I 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
N El 20.2201(d)
El 20.2203(a)(3)(ii)
[E 50.73(a)(2)(ii)(A)
[I 50.73(a)(2)(viii)(A)
[I 20.2203(a)(1)
[I 20.2203(a)(4)
[3 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
[E 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [I 20.2203(a)(2)(ii)
[I 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
[I 20.2203(a)(2)(iii)
[I 50.36(c)(2)
[3 50.73(a)(2)(v)(A) 0l 73.71(a)(4)
[I 20.2203(a)(2)(iv)
[I 50.46(a)(3)(ii)
[I 50.73(a)(2)(v)(B)
El 73.71(a)(5) 000 [E 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
[3 50.73(a)(2)(v)(C)
El OTHER El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
[E 50.73(a)(2)(v)(D)
Specify in Abstract below or in (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)
V. Additional Information
A. Failed Components:
None
B. Previous similar events
Similar level control events with the plant in cold shutdown and the reactor vented to atmosphere have occurred without resulting in a turbine trip (reactor water level did not rise excessively or the turbine trip was not reset) and therefore did not actuate HPCI logic. For these events operators failed to incorporate lessons learned into operating procedures to warn operators of possible consequences.
In 1997, two similar events occurred where HPCI logic was actuated when unplanned reactor water level increases initiated a turbine trip and actuated HPCI logic. The cause of the first event on July 11, 1997, was attributed to component failure of valves not involved in this recent event. The cause of the second event on December 7, 1997, was attributed to operator error in that operating parameters were not adequately monitored, allowing reactor water level to increase to the high level trip point. Because the specific causes of the three events are different, previous corrective actions were not designed to prevent this recent event.
C. Identification of components referred to in this Licensee Event Report:
Components Feedwater System/Booster Pump Feedwater Isolation Valve Feedwater Flow Control Valve High Pressure Coolant Injection (HPCI) System HPCI Initiation Logic Reactor Vessel Main Turbine/Supervisory Control IEEE 805 System ID SJ SJ SJ BJ JG IEEE 803A Function P