05000346/LER-2004-002, Regarding Notification of an Unplanned Reactor Trip During Reactor Trip Breaker Testing
| ML042800252 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/04/2004 |
| From: | Bezilla M FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NP-33-04-002-00 LER 04-002-00 | |
| Download: ML042800252 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii) 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 |
| 3462004002R00 - NRC Website | |
text
FENOC FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor. Ohio 43449 Mark B. Bezilla Vice President - Nuclear 419-321-7676 Fax: 419-321-7582 NP-33-04-002-00 Docket No. 50-346 License No. NPF-3 October 4, 2004 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001 Ladies and Gentlemen:
LER 2004-002-00 Davis-Besse Nuclear Power Station, Unit No. 1 Date of Occurrence - August 4. 2004 Enclosed please find Licensee Event Report 2004-002-00, which is being submitted to provide written notification of an unplanned reactor trip during Reactor Trip Breaker Testing. This trip occurred due to the presence of a failed fuse in Reactor Trip Breaker "A" circuitry, such that when Reactor Trip Breaker "B" was opened per the test procedure, Reactor Trip Breaker "A" also opened, tripping the reactor. This event is being reported pursuant to 10 CFR 50.73(a)(2)(iv)(A), an event that resulted in actuation of the Reactor Protection System. A 4-hour immediate notification of this event was made to the NRC on August 4, 2004 (Event No.
40921). Commitments associated with this LER are listed in the Attachment.
Very truly yours,
/Z1 /"U4t/
GMW
/I Enclosure Attachment cc:
Regional Administrator, USNRC Region III DB-1 Senior Project Manager, USNRC DB-I NRC Senior Resident Inspector Utility Radiological Safety Board 2-,
Docket Number 50-346 License Number NPF-3 NP-33-04-002-00 Attachment Page 1 of I COMMITMENT IST The following list identifies those actions committed to by the Davis-Besse Nuclear Powver Station in this document. Any other actions discussed in the submittal represent intended or planned actions by Davis-Besse. They are described only as information and are not regulatory
commitments
Please notify the Director - Performance Improvement (419-321-7181) at Davis-Besse of any questions regarding this document or associated regulatory commitments.
COMMITMENTS
DUE DATE
- 1. The Surveillance Test procedures that perform the Channel Functional Test of all four Reactor Trip Breakers were revised to require verification of fuse indication prior to performing the test.
- 2. Additional procedures that may open the Reactor Trip Breakers will be identified and revised as applicable to require verification of acceptable fuse status prior to opening the Reactor Trip Breakers.
- 3. Preventive maintenance activities will be developed to replace the fuses associated with the Control Rod Drive System Source Interruption Devices on a periodic basis to preclude failure due to age and/or weakening due to long term cycling.
- 1. Completed August 17, 2004
- 2. December 5, 2004
- 3. November 15, 2004
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 315040104 EXPIRES 613012007 (6-2004)
, the NRC may (See reverse for required number of not conduct or sponsor, and a person Is riot required to respond to. the digits/characters for each block)
Informationcollection.
- 3. PAGE Davis-Besse Unit Number 1 05000346 1 OF4
- 4. TITLE Reactor Trip During Reactor Trip Breaker Testing Due To Fuse Failure
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED M SEQUENTAL l
REV I Y
l FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR 05000 08 04 2004 2004 002 00 10 04 2004 FACILITY NAME DOCKET NUMBER 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
El 20.2201(b)
Ea 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C)
E 50.73(a)(2)(vii) 1 E 20.2201(d)
D 20.2203(a)(3)(ii)
E 50.73(a)(2)(ii)(a)
D 50.73(a)(2)(viii)(A)
D 20.2203(a)(1)
D 20.2203(a)(4) al 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
D_ _ 20.2203(a)(2)(i) a 50.36(c)(1)(i)(A)
D 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL E 20.2203(a)(2)(ii)
E 50.36(c)(1)(ii)(A) 3 50.73(a)(2)(iv)(A)
E 50.73(a)(2)(x)
D 20.2203(a)(2)(iii)
E 50.36(c)(2) 0 50.73(a)(2)(v)(A)
E 73.71(a)(4) 100 El 20.2203(a)(2)(iv)
E 50.46(a)(3)(ii)
E 50.73(a)(2)(v)(B)
D 73.71(a)(5)
El 20.2203(a)(2)(v) a 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
D OTHER Specify In Abstract below 0_E 20.2203(a)(2)(vi)
E 50.73(a)(2)(i)(B)
E 50.73(a)(2)(v)(D) 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 NRC Form 366A)
FIGURE 1 Simplified Functional Diagram of the CRD Circuitry BREAKER INTENTIONALLY OPENED BY DB.MI.03011