05000316/LER-2006-001, Re Failure to Comply with Technical Specification 3.6.2, Containment Air Locks
| ML061430345 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/11/2006 |
| From: | Weber L Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:2573-29 LER 06-001-00 | |
| Download: ML061430345 (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) 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 |
| LER closed by | |
| IR 05000315/2006010 (10 August 2006) | |
| 3162006001R00 - NRC Website | |
text
7.
Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place
~VIER~Bridgman, Ml 49106 POWER AERcom A unit ofAmerican Electric Power May 11, 2006 AEP:NRC:2573-29 Docket No. 50-316 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 2 LICENSEE EVENT REPORT 316/2006-001-00 FAILURE TO COMPLY WITH TECHNICAL SPECIFICATION 3.6.2, CONTAINMENT AIR LOCKS In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Report System, the following report is being submitted:
LER 316/2006-001-00: "Failure to Comply withTechnical Specification 3.6.2, ContaimentAirLocks"' contains the regulatory conmnitment identified in this submittal.
Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Supervisor, at (269) 466-2649.
Sincerely, Lawrence J. Weber Plant Manager RAM/jen Attachments
U. S. Nuclear Regulatory Conmnission AEP:NRC:2573-29 Page 2 c:
J. L. Caldwell, NRC Region III K. D. Curry - AEP Ft. Wayne, w/o attachnent J. T. King, MPSC - w/o attachment MDEQ - WHMD/RPMWS - w/o attachment NRC Resident Inspector P. S. Tam, NRC Washington DC
ATTACHMENT 1 TO AEP:NRC:2573-29 REGULATORY COMMITMENTS The following table identifies those actions committed to by Indiana Michigan Power Company (I&M) in this document. Any other actions discussed in this submittal represent intended or planned actions by I&M. They are described to the Nuclear Regulatory Commission (NRC) for the NRC's information and are not regulatory commitments.
Commitment
Date I&M will add the information contained in Lessons Learned #40 06/09/06 to the Indoctrination Training given to contractors as they come on site.
NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES 613012007 (6-2004)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Donald C. Cook Nuclear Plant Unit 2 05000-316 1 of 3
- 4. TITLE Failure to Comply with Technical Specification 3.6.2, Containment Air Locks
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED T
SEQUENTIAL I REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR I NUMBER lINUMBER MONTH DAY YEAR V
1 FACILITY NAME DOCKET NUMBER 03 13 2006 2006 001 00 05 11 2006
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 0 20.2201(b) 0 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C) 0 50.73(a)(2)(vii) 1 0 20.2201(d) 0 20.2203(a)(3)(ii) 0 50.73(a)(2)(0i)(A) 0 50.73(a)(2)(viii)(A) o 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B) 0 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A) 0 50.73(a)(2&iv)(A) 0 50.73(a)(2)(x) o 20.2203(a)(2)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71 (a)(4) 100%
0 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B)
D 73.71 (a)(5) 0 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
OTHER Speify in Abstract below
_0 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D) or in' (If more space is required, use additional copies of NRC Form (366A)
Conditions Prior to Event
Unit 2-Mode I at 100% power.
Description of Event
On March 14, 2006, at approximately 0941 hours0.0109 days <br />0.261 hours <br />0.00156 weeks <br />3.580505e-4 months <br />, with Donald C. Cook Nuclear Plant (CNP) Unit 2 in MODE 1, Maintenance test technicians conducted routine operability testing of the inner and outer airlock doors for the Unit 2 Lower Containment Airlock (2-AIRLOCK-C612) [AL]. The inner airlock door was tested first and successfully passed its operability test. The outer airlock door was subsequently tested and audible leakage was detected by test personnel. Indiana Michigan Power Company (I&M) immediately investigated the cause of the excessive leakage and determined that the airlock door latching mechanism was not fully engaged. The lack of full engagement resulted in insufficient seating of the equalizing air valve. Upon discovery, the outer airlock door was immediately sealed dosed. Upon obtaining proper closure of the outer airlock door, the outer airlock door was re-tested, resulting in a successful leak rate of 0.0 SCCM.
I&M performed a review of the usage for 2-AIRLOCK-C612 and determined that contract Maintenance personnel last used 2-AIRLOCK-C612 on March 13, 2006, at approximately 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />.
I&M reviewed Technical Specification 3.6.2, Containment Air Locks, and determined that the requirement of Required Action A.1, which for this event required the inner airlock door be verified closed within one hour, was not met. Therefore, this event is reportable in accordance with 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by the plant's technical specifications. During the time period of this event the inner airlock door was closed and operable and 2-AIRLOCK-C612 was capable of performing its design function.
Cause of Event
The cause of this error has been determined to be improper operation of the airlock doors associated with 2-AIRLOCK-C612 by contract maintenance personnel.
Analysis of Event
The configuration of the partially closed outer airlock door meant that the outer airlock door for 2-AIRLOCK-C612 may not have been able to perform its design function. However, the inner airlock door was operable and properly closed and capable of performing its designed safety function. The period of inoperability for the outer airlock door includes the time from the previous opening of the outer door on March 13, 2006, at approximately 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />, and continuing to the successful completion of the operability surveillance test on March 14, 2006, at 1010 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.84305e-4 months <br />.
Each air lock door has been designed and tested to certify its ability to withstand pressure in excess of the maximum expected pressure following a Design Basis Accident in containment. As such, closure of a single door supports containment operability. Each of the doors contains double-gasketed seals and local leakage rate (if more space is required, use additional copies of NRC Form (366A) testing capability to ensure pressure integrity. To affect a leak-tight seal, the air lock design uses pressure-seated doors (i.e., an increase in containment internal pressure results in increased sealing force on each door).
Consequently, it is judged that this event would not have resulted in any airlock leakage from containment during an accident, and the airlock remained fully functional during this time because the inner door was in the proper closed position.
Corrective Actions
Actions Taken:
The outer airlock door of 2-AIRLOCK-C612 was immediately sealed dosed and successfully leak tested.
The inner airlock door for 2-AIRLOCKC612 and the inner and outer airlock doors for the Unit 2 upper airlock were satisfactorily tested.
Both the inner and outer airlock doors for the upper and lower Unit I airlocks were satisfactorily tested.
The individuals who failed to correctly seal closed the outer door of 2-AIRLOCK-C612 were instructed on the proper method of dosing and verifying dosed the doors associated with 2-AIRLOCK-C612.
I&M issued a lessons learned (required reading) to all Maintenance personnel to alert them of the error and to refresh their knowledge of the proper operation of the airlock doors associated with 2-AIRLOCK-C612.
I&M verified that placards are in place at each airlock door for both the upper and lower airlocks in both Unit 1 and Unit 2 to provide guidance on the proper operation of the airlock doors.
I&M has expanded the distribution of the lessons learned to include all Operations, Radiation Protection, and Engineering personnel.
I&M has provided copies of Lessons Learned #40 to the Work Control Center Senior Reactor Operator and incorporated them into the Unit 1 and Unit 2 Containment Entry Logbooks.
Action To Be Taken:
I&M will add the information contained in Lessons Learned #40 to the Indoctrination Training given to contractors as they come on site.
Previous Similar Events
None.