05000302/LER-2006-002, Regarding Emergency Diesel Generator in a Condition Prohibited by Technical Specifications Due to Mispositioning
| ML070030513 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/14/2006 |
| From: | Franke J Progress Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 3F1206-03 LER 06-002-00 | |
| Download: ML070030513 (9) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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 |
| 3022006002R00 - NRC Website | |
text
Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10 CFR 50.73 December 14, 2006 3F1206-03 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
CRYSTAL RIVER UNIT 3 - LICENSEE EVENT REPORT 50-30212006-002-00
Dear Sir:
Florida Power Corporation, currently doing business as Progress Energy Florida, Inc., hereby submits Licensee Event Report (LER) 50-30212006-002-00. The LER discusses Emergency Diesel Generator EGDG-1A being inoperable for a period of time greater than allowed by the CR-3 Improved Technical Specifications (ITS). The EGDG-1A output breaker closing coil was not charged due to mispositioning of the charging motor direct current power control switch.
During this time, EGDG-1 B was removed from service for scheduled maintenance and testing, rendering both trains of the onsite Emergency Alternating Current System inoperable. This report is being submitted pursuant to 1 OCFR50.73(a)(2)(i)(B) and 1 OCFR50.73(a)(2)(v)(D).
No new regulatory commitments are made in this letter.
If you have any questions regarding this submittal, please contact Mr. Paul Infanger, Supervisor, Licensing and Regulatory Programs at (352) 563-4796.
o66n A. Franke Plant General Manager Crystal River Nuclear Plant JAF/dwh Enclosure xc:
Regional Administrator, Region II Senior Resident Inspector NRR Project Manager Progress Energy Florida, Inc.
Crystal River Nuclear Plant 15760 W. Powerline Street Crystal River, FL 34428 jj7~22~
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/3V02007 (6-2004)
, the NRC digitscharacters for each block) may not conduct or sponsor, and a person is not required to respond to, the Information collection.
- 3. PAGE CRYSTAL RIVER UNIT 3 05000302 1 OF 8
- 4. TnILE Emergency Diesel Generator In A Condition Prohibited By Technical Specifications Due To Mispositioning
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR NACLAT 05000CETNUBE NUMBER NO.
N/A 0
FACILITY NAME DOCKET NUMBER 11 01 2006 2006 -
002 -
00 12 14 2006 N/A 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITFED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[o 20.2201(b)
[I 20.2203(a)(3)(i)
C0 50.73(a)(2)(i)(C)
[I 50.73(a)(2)(vii)
[1 20.2201(d)
[3 20.2203(a)(3)(ii)
[
50.73(a)(2)(ii)(A) 13 50.73(a)(2)(viii)(A)
[3 20.2203(a)(1)
[3 20.2203(a)(4)
[3 50.73(a)(2)(ii)(B)
[3 50.73(a)(2)(viii)(B) 1o 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A)
[3 50.73(a)(2)(iii)
[] 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL [3 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
[I 50.73(a)(2)(iv)(A)
[3 50.73(a)(2)(x)
[3 20.2203(a)(2)(iii)
[3 50.36(c)(2)
[0 50.73(a)(2)(v)(A)
[3 73.71(a)(4)
El 20.2203(a)(2)(Iv)
El 50.46(a)(3)(ii) 13 50.73(a)(2)(v)(B)
[] 73.71 (a)(5) 100%
[3 20.2203(a)(2)(v)
E3 50.73(a)(2)(i)(A)
[3 50.73(a)(2)(v)(C)
[3 OTHER [o 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 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 (If more space is required, use additional copies of (If more space Is required, use additional copies of NRC Form 366W)
ATTACHMENT 1 ABBREVIATIONS, DEFINITIONS AND ACRONYMS ABB Asea Brown Boveri AC Alternating Current BTS Breaker Test Shop CFR Code of Federal Regulations CP Compliance Procedure CR-3 Crystal River Unit 3 DC Direct Current EGDG Emergency Diesel Generator ES Engineered Safeguards ICDP Incremental Core Damage Probability ITS Improved Technical Specifications KV Kilovolt NCR Nuclear Condition Report NEI Nuclear Energy Institute NRC Nuclear Regulatory Commission OP Operating Procedure PEF Progress Energy Florida, Inc.
PM Preventive Maintenance Procedure SP Surveillance Procedure V
Volt NOTES:
Improved Technical Specifications defined terms appear capitalized in LER text {e.g.,
MODE 1)
Defined terms/acronyms/abbreviations appear in parenthesis when first used {e.g.,
Reactor Building (RB)).
EIIS codes appear in square brackets {e.g., reactor building penetration [NH, PEN]).
(If more space Is required, use additional copies of NRC Fonn 366A)
ATTACHMENT 2 LIST OF COMMITMENTS The following table identifies those actions committed to by PEF in this document. Any other actions discussed in the submittal represent intended or planned actions by PEF. They are described for the NRC's information and are not regulatory commitments. Please notify the Supervisor, Licensing & Regulatory Programs, of any questions regarding this document or any associated regulatory commitments.
RESPONSE
COMMITMENT
DUE DATE SECTION No regulatory commitments are being made in this submittal.