05000316/LER-2019-001, Manual Reactor Trip Due to Non-Essential Service Water System Degraded Condition
| ML19259A022 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/12/2019 |
| From: | Lies Q Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP-NRC-2019-44 LER 2019-001-00 | |
| Download: ML19259A022 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 3162019001R00 - NRC Website | |
text
m INOIAHA MICHIGAN POWEil*
A unit of Amencan E/ectnc Power September 12, 2019 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 316/2019-001-00 Indiana Michigan Power Cook Nuclear Plant One Cook Place Bndgman, Ml 49100 lnd1anaM1ch1ganPower com AEP-NRC-2019-44 10 CFR 50.73 Manual Reactor Trip Due to Non-Essential Service Water System Degraded Condition 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 316/2019-001-00: Manual Reactor Trip Due to Non-Essential Service Water System Degraded Condition 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, Ql~~
Site Vice President MPH/mll
Enclosure:
Licensee Event Report 316/2019-001-00: Manual Reactor Trip Due to Non-Essential
_Service Water System Degraded Condition
U.S. Nuclear Regulatory Commission Page 2 c:
R. J. Ancona - MPSC R. F. Kuntz-NRC Washington DC EGLE - RMD/RPS NRC Resident Inspector D. J. Roberts - NRC Region Ill A. J. Williamson - AEP Ft. Wayne AEP-NRC-2019-44
Enclosure to AEP-NRC-2019-44 Licensee Event Report 316/2019--001-00 Manual Reactor Trip Due to Non-Essential Service Water System Degraded Condition
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
Estrnatad burden per raoponse 1o ~y wrth this rnancletory coJ1ectlon ~
BO hours
{~
LICENSEE EVENT REPORT (LER)
Reported IMSOllll 1981Tl9d are ncorpomled into the K:80SU1Q process end fed back to lldustry Send COIT1TTl8/M regarding tx.rden estrnate to the lrlormabon SBMC89 Branch (T-2 F43), US
'{....
(See Page 2 for req1a'8d number of dlgrtM::ha"acle b" each block)
Hue!-
RagU8lofy CorrrnlSS!Oll, Washngton, DC 20655-0:Xl1, or by e--ma,J lo 1n1ocoOects Resou"ce@m: gov, and to the D98k Officer, Office of lnformaba, and ~
(See NUREG-1022, R3 for lnstrudion and guidance for completing this form Maa~. NEOB--10202, (3150--0104 ), Office of Mllnagament end Bt.dget, Waalmgton, DC 20503 If e moons used to llllp09B en 1nfoonallon collecbon does not ~J,iy e currentty vel,d 0MB control htto* / twww n ffi g<N/read1no-m,/goc--collectiQns/n ureos/staff/sr1 022/r31) rurber, the NRC may not conduct or oponoor, and a p,,rson 18 not requred to r85p0!1d to, the l1formalJon coUecbon
- 1. FACILITY NAME
- 12. DOCKET NUMBER
.PAGE Donald C. Cook Nuclear Plant Unit 2 05000316 1 OF3
- 4. TITLE Manual Reactor Trip Due to Non-Essential Service Water System Degraded Condition
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACIUllES INVOLVED YEAR ~QU::i REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NO MONTH DAY YEAR NIA
!05000 NUMBER FACILITY NAME IDOCKET NUMBER 07 21 2019 2019 001 00 09 12 2019 N/A 05000
- 9. OPffiA1N3 MODE
- 11. THIS REPORT IS SUBMTTED PURSUANT TO THE~
OF 10 CFR §: (Check aU that apply) 1 D 20.2201 (b)
D 20.2203(a)(3)(1)
D 50 73(a)(2)(!l)(A)
D 50 73(a)(2)(vm)(A)
D 20 2201(d)
D 20 2203(a)(3){ii)
D 50 73(a)(2)(1i)(B)
D 50 73(a)(2)(vrn)(B)
D 20.2203(a)(1 >
D 20 2203(aX4)
D so.73(a)(2)(iii)
D so 73(a)(2)(1X){A)
D 20.2203(a)(2)(1)
D 50 36(c)(1)(1)(A)
~
50 73(a)(2)("w)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL D 20 2203(a)(2)(11)
D 50.36(c)(1)(11)(A)
D 50 73(a)(2)(v)(A)
D 73.71(a)(4)
D 20.2203(a)(2)(ii1)
D so.36(c)(2)
D 50 73(a)(2)(v)(B)
D 73.71(a)(5) 17 D 20.2203(a)(2){lv)
D 50 46(a)(3)(li)
D 50.73(a)(2)(v)(C)
D 73 77(a)(1)
D 20 2203(a)(2)(v)
D 50.73(a)(2)(1)(A)
D 50.73(a)(2)(v)(D)
D 73.77(a)(2)(1)
D 20 2203(a)(2)(v1)
D 50.73(a)(2)(1)(B)
D 50 73(a)(2)(vu)
D 73.77(a)(2)M D so 73(a)(2)(1)(C) 00THER Speafy n Abstract below or IJl NRC Fam 366A
- 12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT rLEPHONE NumER (/nclixie Arna Cooo)
Michael K. Scarpello, Regulatory Affairs Director (269) 466-2649
- 13. COMPLETE ONE UE FOR EACH COMPONeIT FAILURE DESCRl3ED IN THIS REPORT
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANlJ..
REPORTABLE FACTURER TO ICES FACTURER TO ICES
- 14. SUPPLEMENTAL REPORT EXPECTED
[8J NO SUBMISSION DATE v,.BSTRACT (Lmt to 1400 spaces, I e, approximately 14 S/T1gkrspaced typewntten lines)
On July 19, 2019, Donald C. Cook Nuclear Plant (CNP) Unit 2 started experiencing degraded performance on the Unit 2 Non-Essential Service Water System (NESW), which *affected one (1) NESW pump. On July 21, 2019, a second NESW pump on Unit 2 was affected. On July 21, 2019, a rapid downpower over approximately 40 minutes was conducted on Unit 2, and a manual reactor trip was initiated from 17 percent power to allow for investigation and repair of the degraded NESW System, before any thresholds were exceeded. The manual reactor trip was completed at 0826 EDT on July 21, 2019.
The manual Reactor Protection System (RPS) actuation was reported via Event Notification 54176 in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). This manual RPS actuation is reportable pursuant to 10 CFR 50.73(a)(2)(iv)(A) as, "Any event or condition that resulted in manual or automatic actuation of the RPS."
The direct cause of the degraded NESW system performance was a high differential pressure on both Unit 2 NESW strainers, due to excessive loading of small mussels and plugged backwash lines. Both strainers were cleaned, backwashed lines flushed, and returned to service.
NRG FORM 366 (04--2018)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020
EVENT DESCRIPTION
- 3. Lffi NlNBER SEQUENTIAL NUMBER
- - 001 REV NO
- - 00 On July 19, 2019, Donald C. Cook Unit 2 was operating in MODE 1 at approximately 100 percent power, when Unit 2 started experiencing degraded performance on the Non-Essential Service Water System (NESW) [KG], which affected one (1) NESW pump.
On July 21, 2019, a second NESW pump on Unit 2 was affected by degraded NESW system perfonnance, and as a result, a rapid downpower was performed over the course of approximately 40 minutes, in accordance with 2-0HP-4022-001-006, Rapid Power Reduction Response.
On July 21, 2019, at 0826 EDT a manual reactor [RCT] trip was perfonned at 17 percent power, to allow for further investigation and repair of the degraded NESW System.
During this event, Unit 2 was being supplied by offsite power, and all control rods fully inserted. The Auxiliary Feedwater [BA] Pumps were started as required and operated properly. Decay heat removal was via the Steam Generator Power Operated Relief Valves (PORVs) [SB][RV] following breaking Main Condenser [COND] Vacuum for expedited cooldown of the Main Turbine. All plant systems functioned normally following the reactor trip, and no radioactive release resulted from this event.
The NESW system is not considered an engineered safeguards system since it is not required to transfer heat from structures, systems or components (SSC) important to safety during accident conditions.
However, it is required to operate during all phases of nonnal plant operation to supply cooling and*
makeup water to numerous plant systems and components.
The manual Reactor Protection System (RPS) [JC] actuation was reported via Event Notification 54176 in accordance with 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). This manual RPS actuation is reportable pursuant to 10 CFR 50.73(a)(2)(iv)(A) as, "Any event or condition that resulted in manual or automatic actuation of the RPS.~
COMPONENTS 2-0ME-35S - SOUTH NESW PUMP DISCHARGE STRAINER 2-0ME-35N - NORTH NESW PUMP DISCHARGE STRAINER Page 2 of 3 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150--0104 EXPIRES: 03/31/2020 (04-2018)
Eslimaled txmlen per response to comply Vlrth tins mandatory collecbon request 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />
- C~
\\¥}
L Repo,1ed lessons learned a-e mCO!lX)fB!oo l1lo the lcenmg process !lld fed ba:k lo lldustry.
ICE NS EE EVENT REPORT (LE R)
Send comments regardulg burden es1ma1e kl the 1ntomaion Servrces Branch fT-2 F43J, u s Ntd8!I' CONTINUATION SHEET Regtia!oly Coomsston, Waslwlglon, DC 20555-0001, or by s-ma!I kl lnforolec!s Resource@nrc gov, and to the Desk Officel', Office of I nformatloo ood Regulfilxy
>-----------------------1 Affairs, NEOB-10202, (3150--0104), Office of Mm~ement and Budget. Washmgton, DC 20503 If a (See NUREG-1 022, R 3 for instruc!Jon and gu id anc:e for completing th is form rooms used to 1~ oo ll1formabon colecboo does not displrr, a currently v~d 0MB control httpJ/www.nrc.gov/reading-rm/doc-collections/nuregs/stafffsd 0;22/r3/l oornber, !he NRG may not conduct or sponsor, !lld a person rn no1 requrred lo respood to, the l1lfamaoon collec!loo YEAR Donald C. Cook Nuclear Plant Unit 2 05000316 2019
CAUSE OF THE EVENT
- 3. LERNLIMBER SEQUENTIAL NI..MBER
- - 001 REV NO
- - 00 A preliminary analysis was performed and determined that the direct cause for the Unit 2 NESW degraded condition was a high differential pressure in both Unit 2 NESW pump discharge strainers, due to the excessive loading of small mussels and plugged backwash lines. Both strainers were cleaned, backwash lines flushed, and returned to service. A Root Cause Evaluation (RCE) is in progress at the time of this report. If the RCE reveals insights or causes different than described in this LER, a supplement will be provided.
ASSESSMENT OF SAFETY CONSEQUENCES
NUCLEAR SAFETY There was no actual or potential nuclear safety hazard resulting from the Manual Reactor Trip.
INDUSTRIAL SAFETY There was no actual or potential industrial safety hazard resulting from the Manual Reactor Trip.
RADIOLOGICAL SAFETY There was no actual or potential radiological safety hazard resulting from the Manual Reactor Trip.
PROBABILISTIC RISK ASSESSMENT Probabilistic Risk Assessment of the event determined it to have very low safety significance
PREVIOUS SIMILAR EVENTS
A review of Licensee Event Reports for the past three years found no similar events. Page 3 of 3