05000311/LER-2018-002, Automatic Reactor Trip Due to High 23 Steam Generator Water Level
| ML18316A010 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/12/2018 |
| From: | Martino P Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N18-0111 LER 2018-002-00 | |
| Download: ML18316A010 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2) 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)(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 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
| 3112018002R00 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 NOV 12 2018 LR-N18-0111 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Nuclear Generating Station Unit 2 Renewed Facility Operating License No. DPR-75 NRC Docket No. 50-311
SUBJECT:
LER 311/2018-002-00 OPSEG Nuclita:r I.LC 10 CFR 50.73 Automatic Reactor Trip Due to High 23 Steam Generator Water Level This Licensee Event Report, "Automatic Reactor Trip Due to High 23 Steam Generator Water Level," is being submitted pursuant to the requirements of the Code of Federal Regulations 1 OCFR50. 73(a)(2)(iv)(A), "any event or condition that resulted in manual or automatic actuation of any of the systems listed in paragraph (a)(2)(iv)(B)."
Should you have any questions or comments regarding the submittal, please contact Mr. Harry Balian of Regulatory Affairs at 856-339-2173.
There are no regulatory commitments contained in this letter.
Sincerely, Patrick A Martino Salem Plant Manager Enclosure-LER 311/2018-002-00 cc:
USNRC Regional Administrator-Region 1 USNRC NRR Project Manager-Salem US NRC Senior Resident Inspector-Salem NJ Department of Environmental Protection, Bureau of Nuclear Engineering Commitment Coordinator, Salem Generating Station Corporate Commitment Coordinator, PSEG Nuclear, LLC
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (04-2018)
LICENSEE EVENT REPORT (LER)
(See Page 2 for required number of digits/characters for each block)
(See NUREG-1 022, R3 for instruction and guidance for completing this form htt1;2:/lwww.nrc.gov/reading-rm/doc-collections/nu[§Qs/staff/sr1022/@
- 1. FACILITY NAME Salem Generating Station - Unit 2
- 4. TITLE APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 2. DOCKET NUMBER
- 3. PAGE 05000311 1 of 3 Automatic Reactor Trip Due to High 23 steam Generator Water-Level
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED I
SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER
__ 09 14 ---
2018
.2018
--- 002 --- _-:_00 11 12 2018 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
Mode 1
- 10. POWER LEVEL 090 0 20.22o1(b)
D 20.2201 <d) 0 20.2203(a)(1)
D 20.2203(a)(2)(i)
D 20.2203(a)(2)(ii) 0 20.2203(a)(2)(iiQ 0 20.2203(a)(2)(iv)
D 20.2203(a)(2)(v)
D 20.2203(a)(2)(vQ 0 20.2203(a)(3)(i) 0 50.73(a)(2)(iQ(A)
D 50.73(a)(2)(viii)(A) 0 20.2203(a)(3)(iQ 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B) 0 20.2203(a)(4)
D 50.73(a)(2)(iii)
D 50. 73( a)(2)(ix)(A) 0 50.36(c)(1)(i)(A)
(;71 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x) 0 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(v)(A) 0 73.71(a)(4) 0 50.36(c)(2) 0 50.73(a)(2)(v)(B) 0 73.71(a)(5)
D 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(C) 0 73.77(a)(1) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i)
[j 50. 73( a)(2)(i)(B)
D 50.73(a)(2)(vii) 0 73.77(a)(2)(ii) 0 50.73(a)(2)(Q(C)
[j OTHER Specify in Abstract below or in
CAUSE OF THE EVENT
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. LERNUMBER YEAR I SEQUENTIAL I REVISION NUMBER NUMBER 2018
- - 002
- - 00 The direct cause of the positioner feedback arm failure was fatigue due to cyclic stresses. Cyclic stresses were caused by vibration of the feedback arm. A recent design change to the feedwater control system resulted in a resonance frequency being created in the positioner feedback arm at certain power levels. The vibrations were sustained during the Unit 2 coast-down because the plant was maintained in the resonance region for longer periods of time than during normal plant operations, or during startup or shutdown.
SAFETY CONSEQUENCE AND IMPLICATIONS No safety consequences are associated with this event. Operators responded appropriately to the failure of 23BF19 and subsequent automatic reactor trip. Plant response was as expected and designed. Failure of the 23BF19 valve positioner did not prevent automatic closure of 23BF19 in response to a main feedwater isolation signal. The feedwater isolation stopped the main feedwater flow and prevented excessive heat removal.
SAFETY SYSTEM FUNCTIONAL FAILURE This condition did not result in a safety system functional failure as defined in NEI 99-02, Regulatory Assessment Performance Indicator Guidelines. This event did not result in a condition that would have prevented the fulfillment of a safety function of a system needed to shut down the reactor and maintain it in a safe shutdown condition, remove residual heat, control the release of radioactive material, or mitigate the consequences of an accident.
PREVIOUS EVENTS A review of previous events for the past three years did not identify similar events.
CORRECTIVE ACTIONS
The positioner feedback arm was replaced and the station returned to operation at a reduced power level that did not induce the resonance. The feedwater control valve or feedwater control system will be modified to adjust system parameters to reduce vibration.
COMMITMENTS
There are no regulatory commitments contained in this LER. Page 3 of 3