05000237/LER-2014-002, Regarding Reactor Scram Due to Main Power Transformer Failure

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Regarding Reactor Scram Due to Main Power Transformer Failure
ML14188B456
Person / Time
Site: Dresden Constellation icon.png
Issue date: 06/06/2014
From: Marik S
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
SVPLTR 14-0031 LER 14-002-00
Download: ML14188B456 (5)


LER-2014-002, Regarding Reactor Scram Due to Main Power Transformer Failure
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
2372014002R00 - NRC Website

text

Exe!lon Generation.

Dresden Nuclear Power Station 6500 North Dresden Road Morris. IL 60450 815 942 2920 Telephone www.exeloncorp.com 10 CFR 50.73 SVPLTR # 14-0031 June 6, 2014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 2 Renewed Facility Operating License No. DPR-19 NRC Docket No. 50-237

Subject:

Licensee Event Report 237/2014-002-00, Unit 2 Reactor Scram due to Main Power Transformer Failure Enclosed is Licensee Event Report 237/2014-002-00, Unit 2 Reactor Scram due to Main Power Transformer Failure. This is an interim report which describes an event which is being reported in accordance with 10 CFR 50.73(a)(2)(iv)(A), any event or condition that resulted in manual or automatic actuation of any of the system listed in paragraph (a)(2)(iv)(B).

There are no regulatory commitments contained in this submittal.

Should you have any questions concerning this letter, please contact Mr. Glen Morrow at (815) 416-2800.

Respectfully, Site Vice President Dresden Nuclear Power Station Enclosure Licensee Event Report 237/2014-002-00 cc:

Regional Administrator - NRC Region III NRC Senior Resident Inspector - Dresden Nuclear Power Station LIL"

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2017 (02-2014)

Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.

,Reported lessons learned are incorporated into the licensing process and fed back to industry.

Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to tnfocoltects.Resource@nrc.gov, and to the Desk Officer, Office of Information and (See Page 2 for required number of Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC digits/characters for each block) 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

3. PAGE Dresden Nuclear Power Station, Unit 2 05000237 1 OF 4
4. TITLE Unit 2 Reactor Scram due to Main Power Transformer Failure
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME NTHDAYNUMBE NO.

FACILITY NAME DOCKET NUMBER

9. OPERATING MODE
11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)

E] 20.2201(b)

El 20.2203(a)(3)(i)

[] 50.73(a)(2)(i)(C)

E] 50.73(a)(2)(vii)

El 20.2201(d)

El 20.2203(a)(3)(ii)

El 50.73(a)(2)(ii)(A)

El 50.73(a)(2)(viii)(A)

El 20.2203(a)(1)

El 20.2203(a)(4)

El 50.73(a)(2)(ii)(B)

El 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i)

El 50.36(c)(1)(i)(A)

El 50.73(a)(2)(iii)

El 50.73(a)(2)(ix)(A)

10. POWER LEVEL El 20.2203(a)(2)(ii)

El 50.36(c)(1)(ii)(A)

[

50.73(a)(2)(iv)(A)

El 50.73(a)(2)(x)

El 20.2203(a)(2)(iii)

El 50.36(c)(2)

El 50.73(a)(2)(v)(A)

El 73.71 (a)(4) 100 20.2203(a)(2)(iv)

E] 50.46(a)(3)(ii)

El 50.73(a)(2)(v)(B)

El 73.71 (a)(5)

El 20.2203(a)(2)(v)

El 50.73(a)(2)(i)(A)

El 50.73(a)(2)(v)(C)

El OTHER El 20.2203(a)(2)(vi)

El 50.73(a)(2)(i)(B)

El 50.73(a)(2)(v)(D)

Specify in Abstract beiow or in

PLANT AND SYSTEM IDENTIFICATION

Dresden Nuclear Power Station (DNPS), Unit 2, is a General Electric Company Boiling Water Reactor with a licensed maximum power level of 2957 megawatts thermal. The Energy Industry Identification System codes used in the text are identified as [XX].

A.

Plant Conditions Prior to Event:

Unit: 02 Reactor Mode: 1 Event Date: 04-12-2014 Mode Name: Power Operation Event Time: 1012 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.85066e-4 months <br /> CDT Power Level: 100 percent B.

Description of Event

On April 12 th, 2014 at 1012 CDR, an automatic reactor protection system [JC] actuation due to failure of the main power transformer [EL]. All control rods [AA] inserted to their full-in position.

Following the reactor trip, all systems operated as expected.

This event is being reported in accordance with 10 CFR 50.73(a)(2)(iv)(A), any event or condition that resulted in manual or automatic actuation of any of the system listed in paragraph (a)(2)(iv)(B).

C.

Cause of Event

The cause of this event is under investigation and will be reported in a supplemental notification.

D.

Safety Analysis

Following the actuation, all other systems responded as expected, therefore, this event is of low

safety significance

E.

Corrective Actions

Corrective actions will be developed during the ongoing root cause investigation.

F.

Previous Occurrences

Previous occurrences will be identified through the root cause investigation.

G.

Component Failure Data

Manufacturer Model S/N Type Siemens ELIN 1731658 TDQ-A27D9K-99