05000318/LER-2007-001, Re Channel C Linear Range Nuclear Instrument Inoperable During Startup
| ML071510204 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/29/2007 |
| From: | Joseph E Pollock Calvert Cliffs, Constellation Energy Group |
| To: | Document Control Desk, Plant Licensing Branch III-2 |
| References | |
| LER 07-001-00 | |
| Download: ML071510204 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3182007001R00 - NRC Website | |
text
Calvert Cliffs Nuclear Power Plant Constellation Generation Group, LLC 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 0
Constellation Energy May 29, 2007 U.S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
SUBJECT:
Document Control Desk Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket Nos. 50-318; License Nos. DPR 69 Licensee Event Report 2007-001-00 Channel C Linear Range Nuclear Instrument Inoperable During Startup The attached report is being sent to you as required by 10 CFR 50.73.
Should you have questions regarding this report, please contact Mr. Jay S. Gaines at (410) 495-5219.
Very truly yours, for Joseph E. Pollock Plant General Manager JEP/MJY/bjd
Attachment:
As stated cc:
D. V. Pickett, NRC S. J. Collins, NRC Resident Inspector, NRC R. I. McLean, DNR
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may dig its/characters for each block)inot conduct or sponsor, and a person is not required to respond to, the digits/characters_________for
___each___block)__
information collection.
- 3. PAGE Calvert Cliffs Nuclear Power Plant 05000318 1 OF 005
- 4. TITLE Channel C Linear Range Nuclear Instrument Inoperable During Startup
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE 1
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR 05000 NUMBER NO.05 0
FACILITY NAME DOCKET NUMBER 04 02 2007 2007 -
001 -
00 05 29 2007 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[] 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)
[I 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
[I 20.2203(a)(2)(i)
[I 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
[I 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)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iv)
E] 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 006.7 El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
[E 50.73(a)(2)(v)(C)
E] OTHER El 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 (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)
V.
ADDITIONAL INFORMATION
A.
Component Identification IEEE 803 IEEE 805 Component EIIS Function System ID Reactor Protection System (RPS)
Linear Range Nuclear Instrument Channel CHA JD RPS LRNI Quad Isolator Card EB JD RPS LRNI Power Supply RJX JD B.
Previous Occurrences
A review of Calvert Cliffs' licensee event reports and other events over the past three years was performed. The review identified the following similar events:
- 1.
LER 2006-01: IA Diesel Generator Feeder Breaker Tripped Due to Low Design Setpoint The causal analysis performed to address this event identified system post-modification testing as a potential barrier that could have identified the inadequate short-time setting of the 1 A Diesel Generator Amptector. However, the post-modification test did not verify operation under all design bases conditions. Specifically, the system was not tested with all four ventilation fans starting simultaneously simulating a maximum temperature condition. Had the post-modification test simulated a maximum temperature condition, the breaker would have tripped and the error would have been detected and corrected.
Corrective actions for this event included additional training for engineering personnel on adequacy of post-modification test procedures; however maintenance personnel were not included in the target population.
- 2.
LER 2005-001: Main Feedwater Isolation Valve Inoperability Due to Handswitch Wiring The initial error in the wiring was not detected because the Post-Maintenance Operational Test did not verify the containment spray actuation signal/steam generator isolation signal isolation function prior to returning the valve to service after the 2002 refueling outage.
Corrective actions included a site wide initiative to improve human performance through specific procedures with tools and verification practices to reverse the declining trend.
Although site performance has improved in this area, the current condition is an example where continued focus is needed.