05000316/LER-2020-003, Manual Reactor Trip and Automatic Safety Injection Due to Failed Open Pressurizer Spray Valve
| ML20311A129 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/02/2020 |
| From: | Ferneau K Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP-NRC-2020-63 LER 2020-003-00 | |
| Download: ML20311A129 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) 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)(1) 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 3162020003R00 - NRC Website | |
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A umt of Amencan Electnc PoWBr November 2, 2020 Docket No.: 50-316 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Donald C. Cook Nuclear Plant Unit 2 LICENSEE EVENT REPORT 316/2020-003-00 Indiana Midiigan Power Cook Nuclear Plant Ona Cook Place Bndgman, Ml 49106 lnd1anaM1ch1ganPowar com AEP-NRC-2020-63 10 CFR 50.73 Manual Reactor Trip and Automatic Safety Injection Due to Failed Open Pressurizer Spray Valve In accordance with 10 CFR 50.73, Licensee Event Report (LER) System, Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant Unit 2, is submitting as an enclosure to this letter the following report:
LER 316/2020-003-00: Manual Reactor Trip and Automatic Safety Injection Due to Failed Open Pressurizer Spray Valve There are no commitments contained in this submittal.
Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Director, at (269) 466-2649.
Sincerely,
- ~!)~
K. J. Femeau Plant Manager SJM/mll
Enclosure:
Licensee Event Report 316/2020-003-00: Manual Reactor Trip and Automatic Safety Injection due to Fa~ed Open Pressurizer Spray Valve
U.S. Nuclear Regulatory Commission Page 2" c:
R. J. Ancona - MPSC EGLE - RMD/RPS J. B. Giessner - NRC Region Ill
. D. L. Hille - AEP Fl Wayne, w/o enclosures NRC Resident Inspector R. M. Sistevaris - AEP Fl Wayne, w/o enclosures S. P. WaU - NRC, Washington D.C.
A. J. Williamson - AEP Ft. Wayne AEP-NRC-2020-63
Enclosure to AEP-NRC-2020-63 Licensee Event Report 316/2020-003-00: Manual Reactor Trip and Automatic Safety Injection Due to Failed Open Pressurizer Spray Valve
NRCFORM368 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 31II0-0104 EXPIRES: 08/31/2023 (06-2020)
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- 1. FACILITY NAME
- 12. DOCKET NUIIEER
- 13. PAGE Donald C. Cook Nuclear Plant Unit 2 05000316 1 OF4
- 4. TITLE Manual Reactor Trip and Automatic Safety Injection Due to Failed Open Pressurizer Spray Valve
- 6. EVENT DATE
- 8. LER NUMBER
- 7. REPORT DATE
- 8. OTI-IER FACILITIES INVOLVED YEAR~~
REV FACILITY NAME
~*NUIVBER MONTH DAY YEAR NO.
MONTH DAY YEAR NIA 05000 FACILITY NAME LJV\\,1\\1:: I NUt.t3ER 9
4 2020 2020 003 00 11 02 2020 NIA 05000
- 9. CJIERAlltG MOOE 11.THISREPORTISSUEIMIT1EDPURSWWT1011-E REQURB1ENT8 OF 10 CFR §: (Check al that BfJPly) 0 20.2201(b)
D 20.2203(a)(3)(1)
D 50. 73(a)(2){1i)(A) 50.73(a)(2Xvll)CA) 1 0 20.2201(d)
D 20.2203(a)(3)(H)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vll)(B)
D 20.2203(a)(1)
D 20.2203(a)(4)
D 50.73(a)(2)(&t)
D 50.73(a)(2){1x)(A)
D 20.2203(a)(2)(1)
D 50.36(c)(1)(1)(A)
[8] ~0.73{a)(2)(rv)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL D 20.2203(a)(2XI) 50.36(cX1)(D)(A)
D 50.73(a)(2)(v)(A) 73.71(aX4)
D 20.2203(a)(2)(HI)
D 50.36(c)(2)
D 50.73(a)(2)(v)(B)
D 73.71(a)(5)
D 20.2203(a)(2)(1v)
D 50.46(a)(3)(ll)
D 50.73{a)(2)(v)(C)
O73.n(a)(1) 92 D 20.2203(a)(2)(v)
D ~.73(a)(2)(i)(A)
D ~.73(a)(2){v)(D)
D 73.n(a)(2){1)
D 20.2203(a)(2)(vt)
D 50.73(a){2)(1)(8)
D 50.73(a)(2)(vl)
D 73.n(a)(2)(1t) 0 50.73(a)(2)(1)(C)
OTHER Spealy In~ below or III IR: Fam 368,\\
- 12. LICENSEE CONTACT FOR THIS LER UCe46EECONTACT r~7e~~=~
Michael K. Scarpello, Regulatory Affairs Director 13.COMPLE1caELN: FOR EACH COMPOt&TFAI..UREDESCi&DN lllSREPORT
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FAClURER TOICES FAClURER TOICES B
AB PC MOORE y
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR 0 YES (~ yes, complet,9 15. EXPECTED SUBMISSION DA TE) 1:8] NO SUBlll88ION DATE iABSTRACT (l.mtlo 1400apsces, UJ., 11f..4)1~ 14~~Jhes)
On Septermer 4, 2020, at 22:04, Unit 2 control room operators completed a planned power reduction from 100 percent to 92 percent reactor power in preparation to perfonn Main Turbine Stop and Control Valve testing. As Reactor Coolant System (RCS) pressure reached 2235 psig, one of two Pressurizer Spray Valves began to dose as expected and the other valve traveled unexpectedly to the fully open position. The operators were unable to close the failed open valve.and manually tripped the reactor at 22:42 due to lowering RCS pressure. RCS pressure continued to lower below the safety injection (SI) actuation setpoint and an automatic SI occurred. All safety systems responded as expected and RCS pressure recovered to normal.
The cause of the failed open valve was due to foreign material from the control air supply lodged in the positioner spool valve.
The valve positioner and electro-pneumatic transmitter were replaced which returned the valve back into service. Planned corrective actions indude installing point of use filtration upstream of susceptible valve positioners or replace associated regulating valves to include a filter.
This event was reported via Event Notification 54885 in accordance with 10 CFR 50.72(b)(2)(iv)(A), 10 CFR 50.72(b)(2Xiv)(B), and 10 CFR 50.72(b)(3)(rv)(A). This event is reportable as a Licensee Event Report in accordance with 10 CFR 50.73(a)(2)(lv)(A).
NRC FORM 366 (04-2018)
NRC FORM 36&A
('1)8-2020)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 08/31/2023
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LICENSEE EVENT REPORT (LE R)
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at: 0MB Office of 1---------------------1 Tnfurmation md R.egulabxy Af&irs. (31.50-0104), Attn: Deak Officer fer the Nuclear RquJatmy C'-001D1inion. 725 171h Strl:lc:t NW, Wahioglm, OC 20503; c-matl.
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- 1. FACLITY NAME Donald C. Cook Nuclear Plant Unit 2
NARRATIVE
EVENT DESCRIPTION
- 2. DOCKET NUMBER
- 3. LERNJIIEER YEAR SEQUeITw..
05000316 NUMBER 2020
- - 003 REV NO.
- - 00 On September 4, 2020, Unit 2 was operating at 100 percent power. The Unit 2 control room operators were preparing to perform Main Turbine Stop and Control Valve [T AJM testing.
At 16:06, the operators placed the initial set of Pressurizer Backup Heaters [PZR][EHTR] into service in preparation for a planned power reduction to support testing. After the heaters energized, the Pressurizer Spray Valve(s) [AB][FCV] 2-NRV-163 "Reactor Coolant Loop '#3 to Pressurizer Spray Control Valve" and 2-NRV-164 "Reactor Coolant Loop #4 to Pressurizer Spray Control Valve" were modulating to control pressurizer pressure.
At 20:35, the operators began to lower reactor power in accordance with 2-OHP-4021-011-001,, Power Reductions Between 89 percent and 100 percent At 22:04, operators reported completing the planned power reduction and Unit 2 was stable at 92 percent reactor power.
At 22:37, Pressurizer Spray Valves 2-NRV-163 and 2-NRV-164 closed together as expected in response to a lowering pressurizer pressure.
At 22:38, both Pressurizer Spray Valves began to open upon a valid open signal.
At 22:39, Reactor Coolant System (RCS) pressure reached 2235 psig and 2-NRV-163 began to close, as 2-NRV-164 continued to travel fully open.
At 22:42, the control room received an annunciator, "Pressurizer Pressure Low Deviation Backup Heaters On" and discovered that 2-NRV-164 was fully open with zero percent demand. The operators entered procedure 2-0HP-4022-IFR-001, Instrument FaUure Response and determined that 2-NRV-164 could not be closed using control board or digital controls Alarm Log Panel controls. In accordance with procedure immediate actions, operators performed a manual trip of the Unit 2 Reactor [RCT]. The operators entered procedure 2-0HP-4023-E-O, Reactor Trip or Safety Injection. Reactor Coolant Pump(s) (RCP) [AB][P] 23 and 24 were removed from service following verification of E-0 immediate actions. Safety Injection (SI) automatically actuated after RCS pressure lowered below the setpoinl All automatic actions in response to the SI signal occurred as expected.
Following the trip, Unit 2 was supplied by offsite power. AJI control rods fully inserted. The Auxiliary Feedwater Pumps [BA][P] started and operated, as expected. All Emergency Core Cooling System (ECCS)
[BQ] components and Containment Isolation [8D] operated as required. Both Emergency Diesel Generators (EDG) [EK][DG] automatically started and remained in standby. Decay heat was removed by the Condenser Steam Dump Valves [SGJM and ECCS was secured.
NRC FORM 386A (04-2018)
Page 2 of 4 (0e-2020)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMS: NO. 3150-0104 EXPRE8: 08/31/2023 F.atimati:d burden per rc!lpODSC' to comply widi tbil IIUllldatocy coBcdioo request 80 bouo.
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LICENSEE EVENT REPORT (LER) ~~=~=::c:'~~~S:~~=-
Brmcb (T-6 AIOM), US. Nuclear Rqu1atcxy Commiaion, Wllllmgton. DC 2()j55-0001, or by o-mail to Inilcolleds.Rcsoarcc@gov, and the 0MB ~
at: 0MB Office of 1--------------------I JnbJDation and Rcgulatoty Af&ira, (3150-0104). Attn: Desk Officer fir 1hc ~
CONTINUATION SHEET R.eanJatmy Corornismo, 725 17th Street NW, Wubingtoo, DC 20503; e-mail:
(See NUREG-1022, R3 for helruc:tk:m and gtjdence for completing this form ojra mt,mmjnn@nmh coo.goy _ The NRC may not conduct oc aponsca-, llod a person is not httD:/lwww.,v:c.goy/reacfing-rmnyregslstafflm1022Jr3/l required to rcopond to, a collcctioo of iofnrmation un1ea 1hc document rcqtWtiog oc ~
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- 1. FACD..ITY NAME
- 2. DOCKETNl-.B:R
- 3. ~NM:IER YEAR Donald C. Cook Nuclear Plant Unit 2 05000316 2020 SEQUENTw.
NUMBER
- - 003 REV NO.
- - 00 During SI termination, RCP 22 was removed from service due to continued lowering RCS pressure caused by the failed open pressurizer spray valve 2-NRV-164. Afterward, RCS pressure recovered to normal pressure and remained stable.
The event was reported via Event Notification 54885 in accordance with 10 CFR 50.72(b)(2)(iv)(A), 10 CFR 50.72(b)(2)(iv)(B), and 10 CFR 50.72(b)(3)(ivXA). The event is reportable as a Licensee Event Report (LER) in accordance with 10 CFR 50.73(a)(2)(iv)(A), for systems that resulted in a manual or automatic actuation of the R~ctor Protection System (RPS), Containment Isolation, Emergency Core Cooling (ECCS), Auxiliary Feec:twater System (AFW), and Emergency AC Electrical Power Systems.
COMPONENT 2-NRV-164-PU, Reactor Coolant Loop #4 to Pressurizer Spray Control Valve 2-NRV-164 Pneumatic Positioner [AB][PC]
CAUSE OF THE EVENT
Pressurizer spray valve 2-NRV-164 failed open due to debris lodged In the positioner spool valve. No point of use filtration was installed upstream of the spray valve positioner to protect from debris generation downstream of the control air after filter [LF][FL l].
A Root Cause Evaluation (RCE) was in progress at the time this LER was submitted. Any additional insights or causes found to be substantively different as descnbed in this LER will be reported in a supplement at that time.
CORRECTIVE ACTIONS
Completed Corrective Actions The valve positioner and electro-pneumatic transmitter for 2-NRV-164 was replaced.
Satisfactory diagnostic testing of 2-NRV-164 was completed which returned the valve back into service.
Planned Corrective Actions
Install point of use control air filtration or associated regulating valve with a filter upstream of single point vulnerable valve positioners susceptible to binding caused by small particulate.
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FORM 386A (04-20111)
Page 3 of 4 (08-2020)
U.S. NUCLEAR REGULATORY COMIWSSION APPROVED BY 0MB: NO. 3160-0104 EXPIRES: 08/31/2023
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F.atimated burden per rCipOmC to comply wi1h tlm mmdalooy collectioo request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
LICENSEE EVENT REPORT (LER) ~~,==~~~-~~1:;!~~
Bnmch (f-6 Al OM), US. Nuclear Roplaby Coounimm, Wulmpm, DC 20SSS--0001. oc by c-mm1 10 Inwcolloctl ~.
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.Rqiulaic.y ComnriKion 725 17th Su= NW, Wahinaloo. DC 20S03; e-mail.
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- 1. FACILITY NAME
- 2. DOa<ET NUMBER
- 3. Lm NJll:IER Donald C. Cook Nuclear Plant Unit 2 05000316
ASSESSMENT OF SAFETY CONSEQUENCES
NUCLEAR SAFETY YEAR 2020 SEQUENTIAL NUMBER
- - 003 REV NO.
- - 00 There was no actual nuclear safety hazards resulting from 2-NRV-164 failing open, as an safeguard features performed as expected. The potential nuclear safety significance and consequences could have been more severe had the operators not responded as they did or if any of the safety features had not functioned property.
INDUSTRIAL SAFETY There was no actual or potential industrial safety hazard resulting from 2-NRV-164 failing open.
RADIOLOGICAL SAFETY There was no actual or potential radiological safety hazard resulting from 2-NRV-164 failing open.
PROBABILISTIC RISK ASSESSMENT A Probabilistic Risk Assessment (PRA) was completed. The safety significance of the event was derived by calculating the Conditional Core Damage Probability (CCDP) and the Conditional Large Earty Release Probability (CLERP) of the transient initiating event, with the current site Full-Power Internal Events PRA Model of Record. The assessment concluded that the event was of very low safety significance.
PREVIOUS SIMILAR EVENTS
A review of Licensee Event Reports for the past five years found no events due to similar causes.
NRC FORM 386A(04-2019)