05000285/LER-2007-001, Re. Inoperability of a Post Accident Main Steam Line Radiation Monitor Due to Procedural Error
| ML071020167 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/29/2007 |
| From: | Reinhart J Omaha Public Power District |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| LIC-07-0021 LER 07-001-00 | |
| Download: ML071020167 (5) | |
| 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 |
| 2852007001R00 - NRC Website | |
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Omaha Public Power District 444 South 16th Street Mall Omaha NE 68102-2247 LIC-07-0021 March 29, 2007 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, DC 20555
Reference:
Subject:
Docket No. 50-285 Licensee Event Report 2007-001 Revision 0 for the Fort Calhoun Station Please find attached Licensee Event Report 2007-001, Revision 0, dated March 29, 2007. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B). If you should have any questions, please contact me. The attached LER includes the following regulatory commitment:
Appropriate procedures will be revised to ensure that MS-100, MS-101, MS-102 and MS-103 remain open to so that RM-064 is not isolated during plant startup activities. The procedure revisions will be completed by Nyf,31, 2007.
JAR/epm Attachment c:
B. S. Mallett, NRC Regional Administrator, Region IV A. B. Wang, NRC Project Manager J. D. Hanna, NRC Senior Resident Inspector INPO Records Center j~6J49~
Employment with Equal Opportunity
NRC FORM 366 U.S. NUCLEAR REGULATORY COMI APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
Estimated burden per response to comply with this mandatory collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-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, Washington, DC 20555-0001, or by internet e-mail LICENSEE EVENT REPORT (LER) to infocollects@nrc.gov, and to the Desk Officer, Office of Information and RegulatoryAffairs, 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 number, the NRC may not conduct or sponsor, and a person is not required to respond to, the (See reverse for required number of information collection.
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- 3. PAGE Fort Calhoun Station 05000285 1 OF 4
- 4. TITLE Inoperability of a Post Accident Main Steam Line Radiation Monitor Due to Procedural Error
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR 05000 NUMBER NO.
50 FACILITY NAME DOCKET NUMBER 02
.01 2007 2007
- - 001 00 03 29 2007 05000
- 9. OPERATING
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
MODE [1 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 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) 1 [E
20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
[] 50.73(a)(2)(viii)(B)
El 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)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
[E 50.36(c)(2)
[E 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 100 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) 2 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) 9-T 99 1*0, 99T-1-1 MS-275 MS-276 MS-291 MS-277 MS-278 MS-102S HCV-921 MS -103 r
,STEAM TO TURBINE VENT TO ATMOSPHERE A
L MS-181 MS-182
- - jV rI-I PI FRE-064 L
v J v 1 I MS-100 MS-101 HCV-922 999-
--T-T DRAIN OSTEAM TO TURBINE 9--9--
MS-279 MS-280 MS-292.MS-281 MS-282 Figure 1 (Main Steam Line Radiation Monitor)