05000260/LER-2004-001, Regarding Reactor Scram from Sensed Power Load Unbalance Condition
| ML042520218 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/07/2004 |
| From: | Skaggs M Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LER 04-001-00 | |
| Download: ML042520218 (10) | |
| 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)(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)(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 |
| 2602004001R00 - NRC Website | |
text
September 7, 2004 U.S. Nuclear Regulatory Commission 10 CFR 50.73 ATTN: Document Control Desk Mail Stop OWFN, P1-35 Washington, D. C. 20555-0001
Dear Sir:
TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT (BFN) -
UNIT 2 - DOCKET 50-260 - FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT (LER) 50-260/2004-001-00 The enclosed report provides details of an automatic scram which occurred on Unit 2. A main generator load reject condition was spuriously sensed by the main turbine electro-hydraulic control (EHC) system. The systems designed response then resulted in a reactor scram.
In accordance with 10 CFR 50.73(a)(2)(iv)(A), TVA is reporting this event as the valid actuation of the reactor protection system and of containment isolation valves in more than one system. There are no commitments contained in this letter.
Sincerely, Original signed by:
M. D. Skaggs cc: See page 2
U.S. Nuclear Regulatory Commission Page 2 September 7, 2004 Enclosure cc (Enclosure):
(Via NRC Electronic Distribution)
Ms. Eva Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970
U.S. Nuclear Regulatory Commission Page 3 TEA:PSH:BAB Enclosure cc (Enclosure):
M. D. Skaggs, PAB 1B-BFN J. C. Fornicola, LP 6A-C K. L. Krueger, POB 2C-BFN F. C. Mashburn, BR 4X-C D. F. Helms, LP 6A-C P. W. Wilson, PAB 1G-BFN A. S. Bhatnagar, LP 6A-C E. J. Vigluicci, ET 11A-K LEREvents@inpo.org NSRB Support, LP 5M-C EDMS-K S:lic/submit/LERs/U2 LER 2004 01 EHC.doc
NRC FORM 366 (7-2001)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (6-2004)
LICENSEE EVENT REPORT (LER)
(See reverse for required number of digits/characters for each block)
APPROVED BY OMB NO. 3150-0104 EXPIRES 06/30/2007
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILITY NAME Browns Ferry Unit 2
- 2. DOCKET NUMBER 05000260
- 3. PAGE 1 OF 7
- 4. TITLE Reactor Scram from Sensed Power Load Unbalance Condition
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO.
MONTH DAY YEAR FACILITY NAME none DOCKET NUMBER N/A 07 08 2004 2004-001-00 09 07 2004 FACILITY NAME none DOCKET NUMBER N/A
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §:(Check all that apply)
- 9. OPERATING MODE 1
20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A)
X 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)
OTHER
- 10. POWER LEVEL 100 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 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 NRC Form 366A) (17)
D.
Safety System Functional Failure Consideration:
This event does not involve a safety system functional failure which would be reported in accordance with NEI 99-02. The scram was caused by a malfunction of non-safety related equipment. All safety-related equipment performed in accordance with design in response to the event.
E.
Loss of Normal Heat Removal Consideration:
The main condenser was retained as the heat sink during this event, and the condensate/feedwater systems continued to provide reactor vessel inventory make-up. Neither HPCI nor RCIC operated during this event. A momentary lift of seven SRVs occurred at the time of the event to control the initial pressure transient, but the valves properly reseated. Other than quenching the discharge from the short-term opening of the SRVs, the suppression pool was not used as a heat sink following this event. This event does not constitute a scram with a loss of normal heat removal which would be reported in accordance with NEI 99-02.
VIII. COMMITMENTS
None