05000237/LER-2009-007, Regarding Reactor Protection System Nonconformance to a Design Standard

Regarding Reactor Protection System Nonconformance to a Design Standard

ML100330292
Person / Time
Site:	Dresden
Issue date:	01/22/2010
From:	Hanley T Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SVPLTR # 10-0004 LER 09-007-00
Download: ML100330292 (4)

LER-2009-007, Regarding Reactor Protection System Nonconformance to a Design Standard

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 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)(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
2372009007R00 - NRC Website

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Exelon Generation Company, LLC www.exeloncorp.com Nuclear Dresden Nuclear Power Station 6500 North Dresden Road Morris, IL 60450-9765 10 CFR 50.73 SVPLTR # 10-0004 January 22, 2010 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249

Subject:

Licensee Event Report 237/2009-007-00, "Reactor Protection System Nonconformance to a Design Standard" Enclosed is Licensee Event Report 237/2009-007-00, "Reactor Protection System Nonconformance to a Design Standard," for Dresden Nuclear Power Station. This event is being reported in accordance with 10 CFR 50.73(a)(2)(v)(A), "Any event or condition that could have prevented the fulfillment of a safety function of structures or systems that are needed to shut down the reactor and maintain it in a safe shutdown condition."

There are no regulatory commitments contained in this submittal.

Should you have any questions concerning this letter, please contact Ms. Marri Marchionda 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: 08/31/2010 (9-2007)

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 Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, LICENSEE EVENT REPORT (LER)

Washington, DC 20555-0001, or by internet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control (See reverse for required number of number, the NRC may not conduct or sponsor, and a person is not required to respond digits/characters for each block) to, the information collection.

3. PAGE Dresden Nuclear Power Station, Unit 2 05000237 1 OF 3

4. TITLE Reactor Protection System Nonconformance to a Design Standard

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

[

8. OTHER FACILITIES INVOLVED M ~

FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR Dresden Unit 3 05000249 NUBR N.

_II_

I_

I_ NUMBER N

tFACILITY NAME DOCKET NUMBER 11 27 2009 2009 007 00 01 22 2010 jN/A N/A

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) 0l 50.73(a)(2)(i)(C)

E] 50.73(a)(2)(vii) 5 [E

20.2201(d)

El 20.2203(a)(3)(ii)

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

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

El 20.2203(a)(1)

El 20.2203(a)(4)

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

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

El 20.2203(a)(2)(i) 0l 50.36(c)(1)(i)(A)

El 50.73(a)(2)(iii) 0l 50.73(a)(2)(ix)(A)

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

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

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

El 50.73(a)(2)(x)

El 20.2203(a)(2)(iii)

El 50.36(c)(2) 0 50.73(a)(2)(v)(A)

El 73.71(a)(4) 000 0

20.2203(a)(2)(iv) 0l 50.46(a)(3)(ii)

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

El 73.71(a)(5) 0] 20.2203(a)(2)(v)

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

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

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

[E 50.73(a)(2)(i)(B)

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

Specify in Abstract below or in compensatory actions within one hour or reduce power to below 38.5 percent within four hours.

Therefore, the safety significance is minor.

E.

Corrective Actions

This discrepancy existed for both DNPS Unit 2 and Unit 3 RPS pressure switches for the Turbine Stop Valve - Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure - Low trip bypass functions. For Unit 2, DNPS took actions to restore compliance to the referenced design standard prior to the return to service of the unit when two of the pressure switches were connected to a second independent sensing line. For Unit 3, DNPS has performed an operability determination, and the safety function remains operable. The Unit 3 discrepancy will be resolved during its 2010 refueling outage.

DNPS reviewed the other RPS operating bypasses on both Units and found no discrepancies.

F.

Previous Occurrences

A review of DNPS Licensee Event Reports (LERs) was performed and no recent RPS design nonconformance was identified.

G.

Component Failure Data

N/APRINTED ON RECYCLED PAPERPRINTED ON RECYCLED PAPER