05000311/LER-2019-002, Manual Reactor Trip and Auxiliary Feed Water System Actuation
| ML19283A003 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/10/2019 |
| From: | Martino P Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N19-0097 LER 2019-002-00 | |
| Download: ML19283A003 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 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), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
| 3112019002R00 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236
'trCT l U 2019, LR-N19-0097 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Salem Nuclear Generating Station Unit 2 Renewed Facility Operating License No. DPR-75 NRC Docket No. 50-311 LER 311/2019-002-00 Salem Unit 2 Manual Reactor Trip and Auxiliary Feed Water System Actuation PSEG 10 CFR 50.73 This Licensee Event Report, "Salem Unit 2 Manual Reactor Trip and Auxiliary Feed Water System Actuation," is submitted pursuant to 10 CFR 50.73(a)(2)(iv)(A).
Should you have any questions or comments regarding the submittal, please contact Mr. Thomas Cachaza of Regulatory Affairs at 856-339-5038.
There are no regulatory commitments contained in this letter.
Sincerely,
~
Patrick A Martino Salem Plant Manager Enclosure - LER 311 /2019-002-00 cc:
USNRC Regional Administrator - Region 1 USNRC NRR Project Manager - Salem USNRC 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 APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
, the NRG may not conduct or sponsor, and a person is not required to htto://www.nrc.gov/readiD9-rm/doc-collections/nu!:§9s/staff/sr1022/rM respond to, the information collection.
- 3. PAGE Salem Generating Station -Unit 2 05000311 1 OF 3
- 4. TITLE Salem Unit 2 Manual Reactor Trip and Auxiliary Feed Water System Actuation
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED I
SEQUENTIAL I REV FACILITY NAME DOCKET NUMB.ER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 08 11 2019 2019 -
002
- - 00 10 10 2019 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 0 20.2201(b)
D 20.2203(a)(3)(il C 50.73(a)(2)(ii)(A)
C 50. 73( a)(2)(viii)(A) 0 20.2201(d)
C 20.2203(a)(3)(ii) 0 50. 73(a)(2)(ii)(B)
C 50.73(a)(2)(viii)(B) 1 D 20.2203(aJ(1l D 20.2203(a)(4)
D 50.73(a)(2)(iii)
C 50.73(a)(2)(ix)(A) 0 20.2203(a)(2)(i) 0 50.36(c)(1 )(i)(A)
I?] 50. 73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL fJ 20.2203(a)(2)(ii) 0 50.36(c)(1 )(ii)(A)
C 50.73(a)(2)(v)(A)
- 73.71(a)(4)
D 20.2203(aJ(2)(iii)
D 50.36(c)(2)
[J 50. 73( a)(2)(v)(B)
D 73.71(a)(5) 083 D 20.2203(a)(2)(iv)
D 5o.4s(al(3)(ii)
C 50.73(a)(2)(v)(C)
D 73.77(a)(1l D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
L 50.73(a)(2)(v)(D)
C 73.77(al(2)(il D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
C 50.73(a)(2)(vii)
D 73.77(aJ(2l(iil D 50. 73( a)(2)(i)(C)
D OTHER Specify In Abstract below or in NRC Fonn 366A
- 12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT TELEPHONE NUMBER (Include Araa Code)
Thomas J. Cachaza, Senior Regulatory Compliance Engineer 856-339-5038 CAUSE SYSTEM COMPONENT.
MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TOEPIX FACTURER TOEPIX X
SJ LCV 308D y
- 14. SUPPLEMENT AL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR [7 YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
RJ NO SUBMISSION DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
At 0814 on 8/11/19, with Unit 2 at 83 percent power during a planned load reduction, the reactor was manually tripped due to degraded feedwater flow control to the 23 Steam Generator caused by a malfunction of the associated Feedwater Regulating Valve, 23BF19. All systems responded normally post-trip. An actuation of the Auxiliary Feedwater system occurred following the manual reactor trip as expected due to low level in the steam generators. The unit was stabilized in Mode 3.
The failed equipment was repaired.
This event is reportable in accordance with 10 CFR 50.73(a){2)(iv)(A).
NRC FORM 366 (04-2018)
PLANT AND SYSTEM IDENTIFICATION
Westinghouse-Pressurized Water Reactor (PWR/4)
Main Feedwater System Level Control Valve (SJ/LCV)
Auxiliary Feedwater system (BA)
IDENTIFICATION OF OCCURRENCE Event Date: August 11, 2019 Discovery Date: August 11, 2019 CONDITIONS PRIOR TO OCCURRENCE Mode 1, operating at 83 percent power DESCRIPTION OF OCCURRRENCE
- 2. DOCKET 05000311 APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020
, the NRG 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 2019 002 00 At 0814 on 8/11/19, with Unit 2 at 83 percent power during a planned load reduction, the reactor was manually tripped due to degraded feedwater flow control to the 23 Steam Generator (SG) caused by a malfunction of the associated Feedwater Regulating Valve, 23BF19 (LCV). All systems responded normally post-trip. An actuation of the Auxiliary Feedwater system (BA) occurred following the manual reactor trip as expected due to low level in the steam generators. The unit was stabilized in Mode 3.
This event is reportable pursuant to 10CFR50.73(a)(2)(iv)(A).
The valve positioner manufacturer is Dresser Masoneilan and the model number is SVI II AP.
CAUSE OF THE EVENT
The direct cause of the failure was the loosening of the positioner lever arm screw and subsequent disengagement of the spring roll pin from the rotating magnet on the assembly due to vibration.
SAFETY CONSEQUENCE AND IMPLICATIONS No safety consequences are associated with this event. Operators responded appropriately to the degraded feedwater flow control to the 23 steam generator and the subsequent manual reactor trip in accordance with plant procedures. Plant response to the manual reactor trip was normal. All safety systems operated as required.
CORRECTIVE ACTIONS
Corrective actions include:
Repair of the 23BF19 valve positioner (complete).
Replacing the positioner mounting kits to an upgraded model on the feed regulating and feed regulating bypass valves (planned).
NRC FORM :366A (04-2018)
(cont.)
PREVIOUS EVENTS APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
Reported lessons learned are Incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of lnfonnation and Regulatory Affairs, NEOB-10202, (3150.0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an infonnation collection does not display a currently valid 0MB control n_umber, the NRG 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 2019 002 00 On 9/14/18, a Salem Unit 2 automatic reactor trip occurred due to high/low steam generator water level caused by failure of the 23BF19 positioner (LER number 311/2018-002-00). The 23BF19 positioner failure was caused by acute, high magnitude vibrations due to changes to the Feed Water Control System. The corrective actions taken were specific to the 2018 event and would not have prevented this event.
Commitments
There are no regulatory commitments contained in this LER. Page 3 of 3