05000237/LER-2007-002, Unit 2 Reactor Scram Due to Loss of Feedwater
| ML072780585 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/03/2007 |
| From: | Bost D Exelon Generation Co, Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| SVPLTR # 07-0031 LER 07-002-00 | |
| Download: ML072780585 (5) | |
| 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) 10 CFR 50.73(a)(2)(iii) 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 |
| 2372007002R00 - NRC Website | |
text
Exelon Generation Company LLC DTesden NucleaT PoweT Station 650o North Dresden Road MorTis, IL 60450-9765 wwAw.exe ionccrP'c0-r 10 CFR 50.73 SVPLTR # 07-0031 July 3, 2007 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit No. 2 Renewed Facility Operating License No. DRP-19 NRC Docket No. 50-237
Subject:
Licensee Event Report 237/2007-002-00, "Unit 2 Reactor Scram due to Loss of Feedwater" Enclosed is Licensee Event Report 237/2007-002-00, "Unit 2 Reactor Scram due to Loss of Feedwater," for Dresden Nuclear Power Station, Unit 2. 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. James Ellis, Regulatory Assurance Manager, at (815) 416-2800.
Respectfully, 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 w'dl175/
NRC FORM 366 U.S, NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the digls/harctes or achblok)infnrm~qtinm cllAc.tinn.
- 3. PAGE Dresden Nuclear Power Station, Unit 2 05000237 1 OF 4
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED I
FACILITY NAME DOCKET NUMBER MONTH DAY YEAR SEQUENTIAL REV D
DAY YEA R NUMBER NO.
MONTH DR N/A N/A FACILITY NAME DOCKET NUMBER 05 04 2007 2007
- - 002 00 07 03 2007 N/A N/A
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
C3 20.2201(b)
[I 20.2203(a)(3)(i) 13 50.73(a)(2)(i)(C)
Dl 50.73(a)(2)(vii)
El 20.2201(d) 0l 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A) 0l 20,2203(a)(1)
[I 20.2203(a)(4)
[E 50.73(a)(2)(ii)(B) 17 50.73(a)(2)(vili)(B)
_3 20.2203(a)(2)(i) 0l 50,36(c)(1)(i)(A)
[-
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)
Z 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
E 50.36(c)(2) 0l 50.73(a)(2)(v)(A)
El 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)
[I 20.2203(a)(2)(v)
[E 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 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)
DNPS will develop a design specification for the Condensate Prefilter valve CPU software.
DNPS will evaluate a configuration change to the Condensate Prefilter System software that opens the bypass valves on low feedwater flow.
F.
Previous Occurrences
A review of DNPS Licensee Event Reports (LERs) for the last three years did not identified any LERs associated with latent software deficiency.
G.
Component Failure Data
NA NRC FORM 366,A (1-2001)