05000316/LER-2018-001, Valid Actuation of the Unit 2 Cd Emergency Diesel Generator During Testing

From kanterella
(Redirected from 05000316/LER-2018-001)
Jump to navigation Jump to search
Valid Actuation of the Unit 2 Cd Emergency Diesel Generator During Testing
ML18157A065
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 06/04/2018
From: Lies Q
American Electric Power, Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2018-38 LER 2018-001-00
Download: ML18157A065 (6)
v • d • e


LER-2018-001, Valid Actuation of the Unit 2 Cd Emergency Diesel Generator During Testing
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)(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)
3162018001R00 - NRC Website
v • d • e

text

m INDIANA MICHIGAN POWER A unit of American Electric Power June 4, 2018 Docket No.: 50-316 U. S. Nu9lear Regulatory Commission A TIN: Document Control Desk 11555 Rockville Pike Rockville, _MD 20852 Donald C. Cook Nuclear Plant Unit 2

. LICENSEE EVENT REPORT 316/2018-001-00 Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 lndianaMichiganPower.com AEP-NRC-2018-38 10 CFR 50.73 Valid Actuation of the Unit 2 CD Emergency Diesel Generator During Testing 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 316/2018-001-00: Valid Actuation of the Unit 2 CD Emergency Diesel Generator During Testing 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,

?_u:LJ: ~

a/sh~ne Lies Site Vice President MPH/mll

Enclosure:

Licensee Event Report 316/2018-001-00: Valid Actuation of the Unit 2 CD Emergency Diesel Generator During Testing

U.S. Nuclear Regulatory Commission Page 2 c:

R. J. Ancona - MPSC A.W: Dietrich, NRC Washington DC MDEQ - RMD/RPS NRC Resident Inspector K. S. West, NRC Region Ill A. J. Williamson - AEP Ft. Wayne AEP-NRC-2018-38

Enclosure to AEP-NRC-2018-38 Licensee Event Report 316/2018-001-00 Valid Actuation of the Unit 2 CD Emergency Diesel Generator During Testing

NRG FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)

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 />.

  • .~1.*"J,~~~..

LICENSEE EVENT REPORT (LER)

Reported lessons learned are incorporated into the licensing process and fed back to industry.

f Send comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S.

'f 1

Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail

.~

~

... 4 (See Page 2 for required number of digits/characters for each block) to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a (See NUREGa 1022, R.3 for instruction and guidance for completing this form means used to impose an information collection does not display a currently valid 0MB control number, the NRG may not conduct or sponsor, and a person is not required to respond to, the htt12://www.nrc.gov/reading-rm/doc-collections/nur~s/staff/sr1022lr3D information collection.

3. PAGE Donald C. Cook Nuclear Plant Unit 2 05000316 1 OF3

!4. TITLE Valid Actuation of the Unit 2 CD Emergency Diesel Generator During Testing

5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED YEAR ISEQUENTIAi REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NO.

MONTH DAY YEAR 05000 NUMBER FACILITY NAME DOCKET NUMBER 04 13 2018 2018 001 00 06 04 2018 05000

9. OPERATING MODE
11. TI-flS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check ail that apply)

Defueled D 20.2201(b)

D 20.2203(a)(3)(i)

D 50.73(a)(2)(ii)(A)

D 50.73(a)(2)(viii)(A)

D 20.2201(d)

D 20.2203(a)(3)(ii)

D 50.73(a)(2)(ii)(B)

. D 50.73(a)(2)(viii)(B)

D 20.2203(a)(1)

D 20.2203(a)(4)

D so.73(a)(2)(iii)

D 50.73(a)(2)(ix)(A)

D 20.2203(a)(2)(i)

D 50.36(c)(1)(i)(A)

~

50.73(a)(2)(iv)(A)

D 50.73(a)(2)(x)

10. POWER LEVEL D 20.2203(a)(2)(ii)

D so.36(c)(1)(ii)(A)

D 50.73(a)(2)(v)(A)

D 73.71(a)(4)

D 20.2203(a)(2)(iii)

D so.36(c)(2)

D 50.73(a)(2)(v)(B)

D 73.71 (a)(S) 0 D 20.2203(a)(2)(iv)

D so.46(a)(3)(ii)

D 50.73(a)(2)(v)(C)

D 73.77(a)(1)

D 20.2203(a)(2)(v)

D 50.73(a)(2)(i)(A)

D 50.73(a)(2)(v)(D)

D 73.77(a)(2)(i)

D 20.2203(a)(2)(vi)

D 50.73(a)(2)(i)(B)

D 50.73(a)(2)(vii)

D 73.77(a)(2)(ii)

D 50.73(a)(2)(i)(C) 00THER Specify in Abstract below or in NRG Form 366A

12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT rELEPHONE ~;M~;t;;~~;~

Michael K. Scarpello, Regulatory Affairs Director CAUSE SYSTEM COMPONENT MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPJX FACTURER TO EPJX

14. SUPPLEMENTAL REPORT EXPECTED
15. EXPECTED MONTH DAY YEAR D YES (If yes, complete 15. EXPECTED SUBMISSION DATE)

~ NO SUBMISSION DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 14 single--spaced typewritten lines)

On April 13, 2018, with Unit 2 defueled, at approximately 1555 Eastern Daylight Time (EDT), during performance of procedure 12-EHP-4030-056-218 (Automatic Operation of Auxiliary Feedwater Pumps), the Unit 2 CD Emergency Diesel Generator (EOG) automatically started unexpectedly and loaded to 4kV Safeguards bus T21 C when test switches were closed before the technician performing the surveillance recognized that he had mistakenly skipped a page that would have prevented the CD EOG from starting.

The South Spent Fuel Pit (SFP) Cooling Train lost power due to the expected load shed, and was restarted on the Unit2 CD EOG at 1614 EDT. The North SFP Cooling Train remained in-service for the duration of the event. There was no observable change in Spent Fuel Pool Temperature.

The valid actuation of the Unit 2 CD EOG is reportable pursuant to 1 OCFR50. 73 (a)(2)(iv)(A) as an event or condition that resulted in the manual or automatic actuation of Emergency AC Electrical Power Systems, including Emergency Diesel Generators (EDGs).

NRG FORM 366 (04-2018)

INTRODUCTION

YEAR 2018

3. LERNUMBER SEQUENTIAL NUMBER
- 001 On April 13, 2018, with Unit 2 defueled, at approximately 1555 Eastern Daylight Time (EDT), during performance of procedure 12-EHP-4030-056-218 (Automatic Operation of Auxiliary Feedwater Pumps), the Unit 2 CD Emergency Diesel Generator (EDG) [EKJ[DGJ automatically started unexpectedly and loaded to 4kV Safeguards bus T21 C [EAJ[BUJ when test switches were closed before the technician performing the surveillance recognized that a page had been mistakenly skipped that would have prevented the CD EDG from starting.

EVENT DESCRIPTION

REV NO.

- 00 Procedure steps within 12-EHP-4030-056-218, provide instruction to manually actuate and hold relays 2-5x5-T21D (4KV BUS T21D MASTER LOAD SHEDDING RELAY #5) and 2-5x2-T21C (4KV BUS T21 MASTER LOAD SHEDDING RELAY #2). These relays are held closed while various valve positions are verified. Once valve positions are verified, these relays are released. Valve positions are then verified again followed by steps to remove blocks from the test switches. However, the procedure steps that direct releasing the relays were inadvertently skipped. As a result, when the test switches were closed, the load shedding relays were still closed resulting in the unexpected start of 2 CD EDG. All associated equipment and auxiliaries responded as expected.

The South Spent Fuel Pit (SFP) Cooling Pump [PJ lost power due to the expected load shed, and was restarted on the Unit 2 CD EDG at 1614 EDT. The North SFP Cooling Pump remained in-service for the duration of the event.

There was no observable change in Spent Fuel Pool Temperature.

COMPONENT 2-0ME-150-CD (Unit 2 CD EDG)

ASSESSMENT OF SAFETY CONSEQUENCES

NUCLEAR SAFETY The North SFP Cooling Pump remained in-service, and Spent Fuel Pool Temperature remained unchanged for the duration of the event. The South SFP Cooling Train was re-established within 19 minutes of the event. Due to maintaining SFP cooling throughout the duration of this event, and the timely restoration of the South SFP Cooling Train, there was no nuclear safety significance to this event.

INDUSTRIAL SAFETY There was no actual or potential industrial safety hazard resulting from the 2 CD EDG Auto Start.

RADIOLOGICAL SAFETY There was no actual or potential radiological safety hazard resulting from the 2 CD EDG Auto Start. Page 2 of 3 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)

LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET 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 Information Services Branch (T-2 F43), U.S. Nuclear Regulator/

Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory 1---------------------------l Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a (See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r30 means used to impose an information collection does not display a currently valid 0MB control number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.

Donald C. Cook Nuclear Plant Unit 2 05000316

CAUSE OF EVENT

YEAR 2018

3. LER NUMBER SEQUENTIAL NUMBER
- 001 The cause for this event is personnel error. The procedure reader did not adequately follow an approved procedure by skipping a page of the procedure that included steps that would have directed the performer to release the relays, prior to closing the test switches.

CORRECTIVE ACTIONS

Completed Corrective Actions A mandatory meeting was held for Supervisors/Managers to address human performance.

A briefing occurred with the work group involved in this event to discuss the human performance elements and to commit themselves to more thorough procedure use and adherence and place keeping.

Planned Corrective Actions

A procedure enhancement to 12-EHP-4030-056-218 has been requested to include CAUTIONS prior to sections where inadvertent equipment actuations could occur as a result of skipping steps.

PREVIOUS SIMILAR EVENTS

LERs for CNP Unit 1 and Unit 2 were reviewed for the previous three years; no similar events were found.

REV NO.

- 00 Page 3 of 3

Retrieved from "https://kanterella.com/w/index.php?title=05000316/LER-2018-001,_Valid_Actuation_of_the_Unit_2_Cd_Emergency_Diesel_Generator_During_Testing&oldid=4982880"