05000341/LER-2012-006, Regarding Manual Reactor Scram Due to Hydrogen Leakage Into the Stator Water Cooling System
| ML13002A020 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 12/21/2012 |
| From: | Conner J DTE Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC-12-0081 LER 12-006-00 | |
| Download: ML13002A020 (4) | |
| 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) 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3412012006R00 - NRC Website | |
text
J. Todd Conner Site Vice President DTE Energy Company 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.4849 Fax: 734.586.5295 Email: connerj@dteenergy.com DTE Energy, 10 CFR 50.73 December 21, 2012 NRC-12-0081 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555-0001
Reference:
Subject:
Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43 Licensee Event Report (LER) No. 2012-006 Pursuant to 10 CFR 50.73(a)(2)(iv)(A), Detroit Edison is submitting the enclosed LER No. 2012-006, Manual Reactor Scram Due to Hydrogen Leakage Into the Stator Water Cooling System.
No commitments are being made in this LER.
Should you have any questions or require additional information, please contact Mr. Zachary W. Rad of my staff at (734) 586-5076.
Sincerely, Enclosure cc: NRC Project Manager NRC Resident Office Reactor Projects Chief, Branch 4, Region III Regional Administrator, Region III Supervisor, Electric Operators, Michigan Public Service Commission
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: No. 3150-0104 Expires 10/31/2013 (10-2010)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Fermi 2 05000341 1 OF 3
- 4. TITLE Manual Reactor Scram Due to Hydrogen Leakage Into the Stator Water Cooling System
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEOUENTIAL REV MONTH DAY YEAR II NUMBER NO.
05000 II 07 2012 2012 006 00 12 21 2012 FACILITYNAME DOCKET NUMBER 05000
- 9. OPERATING MODE
- 11. THIS REPORT SUBMITTED PURSU ANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
El 20.2201 (b) 0 20.2203(a)(3)(i)
E] 50.73(a)(2)(i)(C) 0 50.73(a)(2)(vii)
EJ 20.2201( d) 0 20.2203(a)(3)(ii) jJ 50.73(a)(2)(ii)(A)
EJ 50.73(a)(2)(viii)(A)
EJ 20.2203(a)(1) 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
[J 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i) 050.36(c)(1)(i)(A) jJ 50.73(a)(2)(iii)
EJ 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii) 050.36(c)(1)(ii)(A) 950.73(a)(2)(iv)(A)
[
50.73(a)(2)(x)
EJ 20.2203(a)(2)(iii)
EJ 50.36(c)(2)
[] 50.73(a)(2)(v)(A)
EJ 73.71(a)(4) 68 Percent EJ 20.2203(a)(2)(iv) 50.46(a)(3)(i)
El 50.73(a)(2)(v)(B) 73.71(a)(5) 020.2203(a)(2)(v) 050.73(a)(2)(l)(A) 50.73(a)(2)(v)(C)
El OTHER EJ 20.2203(a)(2)(vi)
EJ 50.73(a)(2)(i)(B) iJ 50.73(a)(2)(v)(D)
Specify in abstract below or in NRC Form 366A
- 12. LICENSEE CONTACT FOR THS LER FACILITY NAME ELEPHONE NUMBER (Include Area Code)
Fermi 2 / Robert J. Salmon - Supervisor, Nuclear Compliance (734) 586 - 4273CAUSE SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX E
TB GEN E275 Y
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED SUBMISSION MONTH DAY YEAR E YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
El NO DATE I ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
At 09:21 EST 11/7/12, the reactor mode switch was taken to shutdown and the main turbine generator was manually tripped in response to excessive hydrogen gas leakage into the stator water cooling system from the main turbine generator. Two control rods did not respond as expected; however, both rods exhibited nonnal scram times up to position 02, and the scram was uncomplicated. The lowest reactor vessel water level reached was 125 inches above top of active fuel which is below reactor water Level 3 and above Level 2. As expected, the High Pressure Coolant Injection and Reactor Core Isolation Cooling did not actuate. Reactor pressure did not increase above normal operating pressure during the transient. No safety relief valves actuated, and all isolations and actuations associated with reactor water Level 3 occurred as expected. Water level was restored during the transient and maintained at 196 inches by the post scram feedwater logic and the North Reactor Feed Pump. Decay heat was removed via steam to the main condenser using the turbine bypass valves. Two control rod drive mechanisms have been replaced for the control rods that did not respond as expected. A leak in the generator stator water cooling system was located and repaired.
NRC FORM 366 (10-2010)
Initial Plant Conditions
Mode 1
Reactor Power 68 percent Description of the Event At 09:21 EST 11/7/12, the reactor mode switch [HS] was taken to shutdown and the main turbine generator [TA]
was manually tripped in response to excessive hydrogen gas leakage into the stator water cooling system [TJ]
from the main generator [TB].. The scram was uncomplicated. Two control rods [JD] did not respond as expected; however, both rods exhibited normal scram times up to position 02. One control rod fully inserted into the core within the next two minutes with no additional operator action. One control rod stopped at position 02 and was manually inserted by the control room operator.
The lowest reactor vessel water level reached was 125 inches above top of active fuel which is below reactor water Level 3 and above Level 2. As expected, the High Pressure Coolant Injection [BJ] and Reactor Core Isolation Cooling (RCIC) [BN] did not actuate. There was no transient increase in reactor dome pressure and no safety relief valves actuated. All isolations [JM] and actuations [JE] associated with reactor water Level 3 occurred as expected. Water level was restored during the transient and maintained at 196 inches by the post scram feedwater logic and the north reactor feed pump [SJ]. Decay heat was removed via steam to the main condenser using the turbine bypass valves [JI].
At the time of the manual scram, all Emergency Diesel Generators [EK] were operable. All Emergency Core Cooling Systems were available and no significant safety related equipment was out of service.
The two control rod issues were investigated and attributed to problems within their control rod drive mechanisms. Both of those control rod drive mechanisms have been replaced. The main generator has been disassembled and the leak was located and repaired.
Si2nificant Safety Consequences and Implications This event posed no significant safety implications because, as discussed above, the reactor protection and safety related systems functioned as designed following the trip. Important safety-related and non-safety related equipment performed as discussed in the description of the event, and plant response was as expected. There was no increase in reactor pressure, and the reactor core was adequately covered and cooled throughout the event.
Therefore, the health and safety of the public were not affected by this event.
This event is being reported under 10 CFR 50.73(a)(2)(iv)(A), as an event or condition that resulted in the automatic or manual actuation of the Reactor Protection System and a reactor scram. A 4-hour non-emergency notification was made to the NRC Operations Center at 12:39 EST on November 7, 2012 (EN 48487) in accordance with I 0CFR50.72(b)(2)(iv)(B) for any event that results in actuation of the reactor protection system (RPS) when the reactor is critical.U.S. NUCLEAR REGULATORY COMMISSION (10-2010)
LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET
- 1. FACILITY NAME
- 2. DOCKET
- 6. LER NUMBER
- 3. PAGE YEAR SEQUENTIAL REVISION Fermi 2 05000341 E
NUMBER NUMBER 3 OF 3 2012 006 00
Cause of the Event
The cause of the event was a manual scram in response to hydrogen leakage into the stator water cooling system.
Preliminary analysis indicates the hydrogen leak was caused by the presence of a small metallic particle that was magnetized and oscillated with the four-pole rotor field. However, the actual piece of foreign material was not located. Indications are that the oscillation of the small particle, in conjunction with a magnetic attraction towards the stator bar, damaged end winding insulation laminates over time, eventually reaching the copper stator water bar and continuing until a hole was worn allowing hydrogen gas to leak into the generator stator water.
Corrective Actions
The leak was located and repaired. A thorough cleaning by vacuuming and magnetic sweeping of the generator internals was performed during the outage. An additional action taken was to apply a flooding varnish to the end winding areas. The varnish is intended to immobilize any existing material not previously removed to prevent it from causing additional damage. This event has been entered into the Fermi 2 Corrective Actions Program. The associated root cause evaluation is still in progress and may result in additional corrective actions.
Additional Information
A. Failed Component: Main Turbine Generator Component: Stator Water Cooling System Function: Generator Stator Cooling Manufacturer: English Electric (Alstom)
Model Number: N/A Failure Cause: Foreign Material (preliminary)
B.
Previous LERs on Similar Problems: LER 2009-002 reported a similar condition where a manual scram was performed in response to increased hydrogen leakage into the Stator Water Cooling System. The leak was attributed to a piece of foreign material that worked its way into a stator water bar. At that time, the leak was located and repaired in accordance with the generator manufacturer's recommendations. An improved Foreign Material Exclusion program was subsequently put in place with emphasis placed on maintaining generator cleanliness, and programmatic clean area barrier improvements were made to exclude particulates from generator end winding areas. The root cause evaluation for the current event is still in progress and is expected to address the effectiveness of past corrective actions.