05000348/LER-2016-006, Regarding Manual Reactor Trip Due to Loss of Speed Control on 1A Steam Generator Feed Pump
| ML16354B547 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/19/2016 |
| From: | Gayheart C Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-16-2480 LER 16-006-00 | |
| Download: ML16354B547 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(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 10 CFR 50.73(a)(2)(i) |
| LER closed by | |
| IR 05000348/2017001 (1 May 2017) | |
| 3482016006R00 - NRC Website | |
text
A Southern Nuclear December 19, 2016 Cheryl A. Gayheart VICe President - Farley Farley Nuclear Plant Post OffiCe Box 4 70 Ashford, AL 36312 334 814.4511 tel 334.814.4575 fax cagayhea@ southemco.com Docket No.:
50-348 NL-16-2480 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Unit 1 Licensee Event Report 2016-006-00 Manual Reactor Trip due to Loss of Speed Control on 1 A Steam Generator Feed Pump Ladies and Gentlemen:
This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations, 10 CFR 50. 73(a)(2)(iv)(A), for a manual actuation of the Reactor Protection System and an automatic start of the Auxiliary Feedwater system.
This letter contains no NRC commitments. If you have any questions, please contact Julie Collier at 334.814.4639.
Respectfully submitted, Ms. C. A. ~
art Vice Presi~nt - Farley GAG/EGA Enclosure: Unit 1 Licensee Event Report 2016-006-00
U. S. Nuclear Regulatory Commission NL-16-2480 Page2 cc:
Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, Executive Vice President & Chief Nuclear Officer Ms. C. A. Gayheart, Vice President-Farley Mr. M. D. Meier, Vice President-Regulatory Affairs Mr. D. R. Madison, Vice President-Fleet Operations Mr. B. J. Adams, Vice President-Engineering Ms. B. L. Taylor, Regulatory Affairs Manager-Farley Mr. K. D. Miller, OE Coordinator-Farley RTYPE: CFA04.054 U. S. Nuclear Requlatorv Commission Ms. C. Haney, Regional Administrator Mr. S. A. Williams, NRR Project Manager-Farley Mr. P. K. Niebaum, Senior Resident Inspector-Farley
Joseph M. Farley Nuclear Plant Unit 1 Unit 1 Licensee Event Report 2016-006-00 Manual Reactor Trip due to Loss of Speed Control on 1 A Steam Generator Feed Pump
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION jAPPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (11*2015)
, the NRC may not conduct or sponsor, and a person is no
~u lred to respond to, the information collection.
- 1. FACILITY NAME
~* DOCKET NUMBER
~.PAGE Joseph M. Farley Nuclear Plant, Unit 1 05000 I 348 1 OF 3
~.TITLE Manual Reactor Trip due to Loss of Speed Control on 1A Steam Generator Feed Pump
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED I
SEQUENTIAL I REV NO ACIUTYNAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER MONTH DAY YEAR 19 ACIUTYNAME DOCKET NUMBER 11 08 2016 2016 006 -
00 12 2016
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 0 20.2201 (b) 0 20.2203(a)(3)(i) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) 1 0 20.2201(d) 0 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B) 0 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A) 0 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A) 181 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 50.36(c)(1 )(ii)(A) 0 50.73(a)(2)(v)(A) 0 73.71(a)(4) 0 20.2203(a)(2)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(B) 0 73.71(a)(5) 32%
0 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(C) 0 73.77(a)(1) 0 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(D) 0 73.77(a)(2)(i) 0 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 50.73(a)(2)(vii) 0 73.77(a)(2)(ii) 0 50.73(a)(2)(i)(C) 0 OTHER Specify in Abstract below or in =
A. PLANT AND SYSTEM IDENTIFICATION
Westinghouse-Pressurized Water Reactor
B. DESCRIPTION OF EVENT
- 2. DOCKET NUMBER osooo-348
- 3. LEA NUMBER YEAR 2016 SEQUENTIAL NUMBER 006 At 1326, on November 8, 2016, reactor power was at 34 percent in Mode 1 and power was being reduced to remove the main generator from service. The recirculating flow control valve [FCV] for the 1A Steam Generator Feed Pump (SGFP) [P] was opened in accordance with unit shutdown procedure. All steam generator (SG) [SG] levels began to trend down, as expected and as described in the unit operating procedure. The unit operator attempted to raise speed for the 1A SGFP using the SGFP master speed controller [SC]. The SGFP speed rose to approximately 3700 rpm but would not rise further. The demand on the SGFP master speed controller was greater than 65 percent, which corresponded to a speed greater than 3700 rpm.
Due to the inadequate response from the SGFP master speed controller, the Shift Supervisor directed raising speed on the 1A SGFP using the slave controller. Demand on the slave controller was raised to approximately 80 percent, which corresponded to a speed higher than 3700 rpm. The 1A SGFP speed was observed to not have changed and remained at 3700 rpm.
The Shift Supervisor then established trip criteria. Due to the inability to raise 1 A SGFP speed and feedwater flow to the SGs, all SG levels continued to lower. At 32 percent reactor power, the Shift Supervisor directed a manual reactor trip to prevent reaching the low SG level automatic reactor trip setpoint. At 1331, a manual reactor trip was performed due to lowering SG levels and an inability to raise speed and feedwater flow because the 1 A SG FP speed control circuitry failed. The motor driven auxiliary feed pumps also started automatically, as expected, with the manual reactor trip. The main steam isolation valves were closed to limit the unit cool down because the isolation valves [ISV] on the 2AI28 moisture separator reheater [MSR] second stage had excessive leakby. Decay heat removal was accomplished with the atmospheric relief valves, and the unit was maintained in mode 3 to continue with the previously scheduled main generator repairs.
C. UNIT STATUS AT TIME OF EVENT Unit 1, Mode 1, 32 percent power with a unit shutdown in progress
D. CAUSE OF EVENT
The speed reference adjust and speed controller (C2) card was found to have an out of tolerance output voltage due to an A2 operational amplifier on the card that failed because of infant mortality.
E. REPORTABILITY ANALYSIS AND SAFETY ASSESSMENT This event is reportable as required by 10 CFR 50. 73(a)(2)(iv)(A) due to a manual actuation of the reactor protection system and automatic actuation of the auxiliary feedwater system. The reactor was shut down at 1331 and mode 3 was entered. There was no loss of safety function REV NO 00 Page 2 of 3
Estimated btrden per response to cOIIllllv with Ills mandatory colecbon request eo ho\\n.
Reported lessons learned are P;orporalild into lhe li::ar&slng process and led back to imuslly.
Send coomen:s regardng bmlen eslinate to tle FOtA. Pnrq end fn!annalion CcllociDis Blanch (T-5 F53), U.S. NIElear RegUatory Conmsslon, Was/wlg!on, DC 20555-0001, or by internet e-mail to lnlocollects.ResourceOm:.gov, and to lhe Desk Olficer, 01!i:e ollnlamation and Regulat!ll)' Affairs, NEOB-1!W!, (315(H)104), Oflice of ~ent 2nd 8cJd9el, Waslington, DC 20500. 11 a means used to impose an lllorma!Jon calediln does 11011ispiay a anenlfy vaHd OMS control rumber, the NRC may 1101 conduct or sponsor, and a person is 1101
~quAd to respond to, the information colection.
- 2. DOCKET NUMBER 0500Q-348
- 3. LER NUMBER 2016 SEQUENTIAL NUMBER 006 REV NO 00 and no radioactive release associated with this event. All required safety systems were available and responded as expected. There were no actual consequences detrimental to the health and safety of the public and the event is considered to be of very low safety significance.
F. CORRECTIVE ACTION
A new C2 card was installed, and the 1A SGFP high pressure and low pressure governor valves were stroked satisfactorily as the functional test.
G. ADDITIONAL INFORMATION
- 1) Previous Similar Events: none
- 2) Commitment Information: No commitments are made in this correspondence.