05000277/LER-2005-003, Regarding E-2 Emergency Diesel Generator Technical Specification Required Actions Not Performed
| ML060470546 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 02/10/2006 |
| From: | Grimes J Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CCN 06-14002 LER 05-003-00 | |
| Download: ML060470546 (5) | |
| 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)(v), Loss of Safety Function |
| 2772005003R00 - NRC Website | |
text
Exe1e n M Exelon Nuclear Telephone 717.456.7014 Nuclear Peach Bottom Atomic Power Station www.exeloncorp.corn 1848 Lay Road Delta, PA 17314-9032 10CFR 50.73 February 10, 2006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station (PBAPS) Units 2 & 3 Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 & 50-278
Subject:
Licensee Event Report (LER) 2-05-03 This LER reports a condition prohibited by Technical Specifications involving an inoperability of the E-2 Emergency Dies el Generator In accordance with NEI 99-04, the regulatory commitment contained in this correspondence is to restore compliance with the regulations. The specific methods that are planned to restore and maintain compliance are discussed in the LER. If you have any questions or require additional information, please do not hesitate to contact us.
Sincerely, Joseph P. Grimes Plant Manager Peach Bottom Atomic Power Station JPG/djf/IR 437007 Attachment cc:
PSE&G, Financial Controls and Co-owner Affairs R. R. Janati, Commonwealth of Pennsylvania INPO Records Center S. Collins, US NRC, Administrator, Region I R. I. McLean, State of Maryland US NRC, Senior Resident Inspector CCN 06-14002
NRC FORM 366 U.S. NUCLEAR REGULATORY CCOMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007
- 6-2004)
, the NRC maynotconduct or sponsor, and a person is not required to respond to, the information digits/characters for each block) collection.
- 3. PAGE Peach Bottom Atomic Power Station Units 2 and 3 05000 277 1 OF 4
- 4. TITLE E-2 Emergency Diesel Generator Technical Specification Required Actions not Performed
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT D ATE8.
OTHER FACILITIES INVOLVED SEUNILRVFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQuENTIAL REV MONTH DAY YEAR PBAPS Unit 3 05000 278 FACILITY NAME DOCKET NUMBER 12 22 2005 05 03 0
2 10 2006 05000 D. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201(b) 0 20.2203(a)(3)(;)
[0 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii) 1 E 20.2201(d) 0 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A)
El 20.2203(a)(1) 0 20.2203(a)(4)
[E 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
E 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL
[
20.2203(a)(2)(ii)
I 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x) o 20.2203(a)(2)(iii)
El 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71 (a)(4)
El 20.2203(a)(2)(iv)
El 50.461a)(3)(ii)
El 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 100 Cl 20.2203(a)(2)(v)
El 50.731a)(2)(i)(A)
El 50.73(a)(2)(v)(C) 0 OTHER El 20.2203(a)(2)(vi) 0 50.731:a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in NRIC (If more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (1 7)
Cause of the Event
The unknown inoperability of the E-2 EDG between 12/22/05 and 12/27/05 was the result of a less than adequate PMT when the Air Coolant Auxiliary Pump was returned to service on 12/22/05. The PMT that was performed consisted of running the pump without the EDG in operation. This PMT was not adequate since additional seal water pressure is applied to the packing area when the EDG is in operation. The seal water pressure is provided by the E-2 EDG engine-driven Jacket Coolant Pump. This engine-driven pump is not in operation unless the EDG is operating. Had the EDG being running during the PMT, appropriate packing adjustments / repairs could have been promptly initiated.
The human performance aspects of not ensuring an appropriate PMT for the Air Coolant Auxiliary Pump maintenance are being reviewed in accordance with the Corrective Action Program.
Corrective Actions
The associated Technical Specification Condition B Required Actions were appropriately completed during the 12/27-28/05 time period when the E-2 EDG was declared inoperable.
The Air Coolant Auxiliary Pump was removed from service and the E-2 EDG was declared operable on 12/28/05 at approximately 1815 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.906075e-4 months <br />.
Appropriate PMT testing will be developed and performed prior to returning the Air Coolant Auxiliary Pump to service.
Additional assessment and appropriate corrective actions concerning human performance work practices will be further assessed as part of the Corrective Action Program.
Previous Similar Occurrences There were no previous LERs identified involving a condition prohibited by Technical Specifications caused by less than adequate post-maintenance testing.