05000331/LER-2009-003, Regarding Unplanned Manual Scram Due to Increasing Reactor Water Level
| ML091540244 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 06/02/2009 |
| From: | Richard Anderson NextEra Energy Duane Arnold |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NG-09-0430 LER 09-003-00 | |
| Download: ML091540244 (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)(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 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3312009003R00 - NRC Website | |
text
NExTera ENERGY DUANE ARNOLD June 2, 2009 NG-09-0430 10 CFR 50.73 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001 Duane Arnold Energy Center Docket 50-331 License No. DPR-49 Licensee Event Report #2009-003-00 Please find attached the subject report submitted in accordance with 10 CFR 50.73. This letter makes no new commitments or changes to any existing
commitments
Richard L. nesoL
ý Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC cc:
Administrator, Region Ill, USNRC Project Manager, DAEC, USNRC Resident Inspector, DAEC, USNRC NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSIO APPROVED BY OMB NO. 3150-0104 EXPIRES: 8/31/2010 (9-2007)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Duane Arnold Energy Center 05000 331 1 OF 5
- 4. TITLE Unplanned Manual Scram due to Increasing Reactor Water Level
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME DOCUMENT NUMBER I
NUMBER NO.
05000 04 03 09 2009 003 0
06 02 09 FACILITY NAME DOCUMENT NUMBER 1
05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
Fi 20.2201(b)
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20.2203(a)(3)(i)
E]
50.73(a)(2)(i)(C)
Li 50.73(a)(2)(vii) 1 Li 20.2201(d)
Li 20.2203(a)(3)(ii)
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50.73(a)(2)(ii)(A)
E] 50.73(a)(2)(viii)(A)
Li 20.2203(a)(1)
Li 20.2203(a)(4)
L]
50.73(a)(2)(ii)(B)
Li 50.73(a)(2)(viii)(B)
Li 20.2203(a)(2)(i)
Li 50.36(c)(1)(i)(A)
LI 50.73(a)(2)(iii)
[
50.73(a)(2)(ix)(A)
- 10. POWER LEVEL Li 20.2203(a)(2)(ii)
Li 50.36(c)(1)(ii)(A)
[
50.73(a)(2)(iv)(A)
[] 50.73(a)(2)(x)
Li 20.2203(a)(2)(iii)
Li 50.36(c)(2)
Li 50.73(a)(2)(v)(A)
Li 73.71(a)(4) 100%
Li 20.2203(a)(2)(iv)
[
50.46(a)(3)(ii)
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50.73(a)(2)(v)(B)
L] 73.71(a)(5)
Li 20.2203(a)(2)(v)
Ej 50.73(a)(2)(i)(A)
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50.73(a)(2)(v)(C)
E] OTHER E] 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)
Fi 50.73(a)(2)(v)(D)
VOLUNTARY LER
- 12. LICENSEE CONTACT FOR THIS LER NAME TELEPHONE NUMBER (Include Area Code)
Bob Murrell, Engineering Analyst 319-851-7900CAUSE SYSTEM COMPONENT MANU-REPORTABLE L
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
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NO DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On April 3, 2009, while operating at 100% power, with no Technical Specification (TS) Required Actions in affect, instrument and controls (I&C) technicians were performing Surveillance Test Procedure (STP) 3.3.3.2-09, Reactor Water Level and Pressure Instruments Calibration. This STP was performed for the first time since the recorder had been replacedduring Refueling Outage (RFO) 21 in February 2009. Step 7.1.20 directed lifting a lead on the positive terminal of channel 2 on Level Recorder Switch (LRS) 4559/4560. When the lead was lifted, the control loop for reactor vessel level control was opened, and indicated vessel level pegged low. The plant response, as designed, was to increase feed water flow to the reactor to compensate for the indicated lowering vessel level. This caused actual reactor vessel level to increase. As a result of the increasing reactor water level, operators inserted a manual scram at 0028. All safety systems responded as designed. Containment isolations signals were received for groups 2, 3, and 4 due to reactor level dropping below 170 inches. All isolations went to completion. This reactor level response is normal following a reactor scram.
The cause of this event was an inadequate procedure change.
There were no actual safety consequences and no effect on public health and safety as a result of this event.
NRC FORM 366 (9-2007)
PRINTED ON RECYCLED PAPER (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)
Reporting Requirements
This event is reportable under 10 CFR 50.73(a)(2)(iv)(A).PRINTED ON RECYCLED PAPER