05000249/LER-2011-001, Regarding Control Rod Block Instrumentation Failure

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Regarding Control Rod Block Instrumentation Failure
ML110810616
Person / Time
Site: Dresden Constellation icon.png
Issue date: 03/16/2011
From: Hanley T
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
SVPLTR # 11-0012 LER 11-001-00
Download: ML110810616 (4)


LER-2011-001, Regarding Control Rod Block Instrumentation Failure
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications

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)(iv)(A), System Actuation

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
2492011001R00 - NRC Website

text

Exelkn,.

Exelon Generation Company, LLC Dresden Nuclear Power Station 6500 North Dresden Road Morris, IL 60450-9765 www.exeloncorp.coni Nuclear 10 CFR 50.73 SVPLTR # 11-0012 March 16, 2011 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 3 Renewed Facility Operating License No. DPR-25 NRC Docket No. 50-249

Subject:

Licensee Event Report 249/2011-001-00, Control Rod Block Instrumentation Failure Enclosed is Licensee Event Report 249/2011-001-00, Control Rod Block Instrumentation Failure. This event is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B), Any operation or condition which was prohibited the plant's Technical Specifications.

There are no regulatory commitments contained in this submittal.

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

Respectfully, Tim Hanley Site Vice President Dresden Nuclear Power Station Enclosure cc:

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

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 Dresden Nuclear Power Station, Unit 3 05000249 1 OF 3
4. TITLE Control Rod Block Instrumentation Failure
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR N/A 05000 NUMBER NO.

FACILITY NAME DOCKET NUMBER 01 15 2011 2011 001 00 03 16 2011 N/A 05000

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

El 20.2201(b)

El 20.2203(a)(3)(i)

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

El 50.73(a)(2)(vii) 1 [1 20.2201(d)

El 20.2203(a)(3)(ii)

E] 50.73(a)(2)(ii)(A)

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

[I 20.2203(a)(1)

El 20.2203(a)(4)

E] 50.73(a)(2)(ii)(B)

[I 50.73(a)(2)(viii)(B)

__ 20.2203(a)(2)(i)

[I 50.36(c)(1)(i)(A)

El 50.73(a)(2)(iii)

[1 50.73(a)(2)(ix)(A)

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

[I 50.36(c)(1)(ii)(A)

[I 50.73(a)(2)(iv)(A)

[I 50.73(a)(2)(x)

El 20.2203(a)(2)(iii)

[: 50.36(c)(2)

[I 50.73(a)(2)(v)(A)

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

El 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)

[

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

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

Specify in Abstract below or in D.

Safety Analysis

The design of the RBM system is to block CRD withdrawal during a RWE to prevent exceeding the MCPR safety limit. Since the RBM upscale rod block is not credited in the analysis of a rod withdrawal error, the safety significance of the failure of the relay card is minimal. Therefore, health and safety of the public was not compromised as a result of this condition.

E.

Corrective Actions

The failed relay card was replaced.

A causal investigation will be performed to determine why operations personnel did not identify that the RBM was inoperable.

F.

Previous Occurrences

A review of DNPS Licensee Event Reports (LERs) for the last three years did not identify any LERs associated with control rod block inoperabilities or failures.

G.

Component Failure Data

Not Applicable