05000237/LER-2005-002, Regarding Unit 2 Group 1 Isolation and Resulting Scram

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Regarding Unit 2 Group 1 Isolation and Resulting Scram
ML051430346
Person / Time
Site: Dresden Constellation icon.png
Issue date: 05/23/2005
From: Bost D
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
SVPLTR # 05-0024 LER 05-002-00
Download: ML051430346 (5)


LER-2005-002, Regarding Unit 2 Group 1 Isolation and Resulting Scram
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
2372005002R00 - NRC Website

text

10 CFR 50.73 May 23, 2005 SVPLTR # 05-0024 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 2 Renewed Facility Operating License No. DRP-19 NRC Docket No. 50-237

Subject:

Licensee Event Report 237/2005-002, Unit 2 Group 1 Isolation and Resulting Scram Enclosed is Licensee Event Report 237/2005-002, Unit 2 Group 1 Isolation and Resulting Scram, for Dresden Nuclear Power Station. 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 systems listed in paragraph (a)(2)(iv)(B).

Should you have any questions concerning this report, please contact Mr. Pedro Salas, Regulatory Assurance Manager, at (815) 416-2800.

Respectfully, Original Signed By Danny G. Bost 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 (6-2004)

LICENSEE EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007

, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

1. FACILITY NAME Dresden Nuclear Power Station Unit 2
2. DOCKET NUMBER 05000237
3. PAGE 1 OF 4
4. TITLE Unit 2 Group 1 Isolation and Resulting Scram
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO.

MONTH DAY YEAR FACILITY NAME N/A DOCKET NUMBER N/A 03 24 2005 2005 - 002 - 00 05 23 2005 FACILITY NAME N/A DOCKET NUMBER N/A

9. OPERATING MODE 1
10. POWER LEVEL 096
11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)

OTHER 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 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)

E.

Corrective Actions

The A EHC Pressure Regulator A45, A54 and C46 cards were replaced.

The A EHC Pressure Regulator A54 card backplane connector was replaced and the all termipoints on the connector were remade.

The remaining connectors to the A EHC Pressure Regulator A54 card will be reworked during the next Unit 2 refueling outage.

F.

Previous Occurrences

A review of DNPS Licensee Event Reports (LERs) for the last five years did not identify any similar events.

G.

Component Failure Data

NA