05000423/LER-2019-001, Regarding Plant Shutdown Required by Technical Specifications, Emergency Diesel Generator Exceeded Allowed Outage Time

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Regarding Plant Shutdown Required by Technical Specifications, Emergency Diesel Generator Exceeded Allowed Outage Time
ML20055D320
Person / Time
Site: Millstone Dominion icon.png
Issue date: 02/13/2020
From: Daugherty J
Dominion Energy Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
20-002 LER 2019-001-00
Download: ML20055D320 (6)


LER-2019-001, Regarding Plant Shutdown Required by Technical Specifications, Emergency Diesel Generator Exceeded Allowed Outage Time
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown

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)(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)

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)
4232019001R00 - NRC Website

text

Dominion Energy Nuclear Connecticut, Inc.

Rt 1 56, Rope Ferry Road, Waterford, CT 06385 Dominion Energy.com U. S. Nuclear Regulatory Commission

MILLSTONE POWER STATION UNIT 3 LICENSEE EVENT REPORT 2019-001-00

~

Dominion P' Energy Serial No.

MPS Lie/DCB Docket No.

License No.20-002 RO 50-423 NPF-49 FEB 1 3 2020 PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS, EMERGENCY DIESEL GENERATOR EXCEEDED ALLOWABLE OUTAGE TIME This letter forwards Licensee Event Report (LER) 2019-001-00 documenting a condition at Millstone Power Station Unit 3, on December 18, 2019. This LER is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(A), the completion of any plant shutdown required by the plant's Technical Specifications.

If you have any questions or require additional information, please contact Mr. Jeffry A.

Langan at (860) 444-5544.

Sincerely, Jo 1. Daugherty Sir ::ce President - Millstone Attachments: 1 Commitments made in this letter: None

cc:

U.S. Nuclear Regulatory Commission Region 1.

2100 Renaissance Blvd.

Suite 100 King of Prussia, PA 19406-2713 RV. Guzman Serial No.20-002 Docket No. 50-423 Licensee Event Report 2019-001-00 Page 2 of 2 NRG Senior Project Manager Millstone Units 2 and 3 U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08 C-2 Rockville, MD 20852-2738 NRG Senior Resident Inspector Millstone Power Station

ATTACHMENT Serial No.20-002 Docket No. 50-423 Licensee Event Report 2019-001-00 LICENSEE EVENT REPORT 2019-001-00 PLANT SHUTDOWN REQUIRED BY TECHNICAL SPECIFICATIONS, EMERGENCY DIESEL GENERATOR EXCEEDED ALLOWABLE OUTAGE TIME MILLSTONE POWER STATION UNIT 3 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES:

03/31/2020 NRG FORM 366 (04-2018)

.::,C..,J.t-flREGt,(.,_.

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'. J LICENSEE EVENT REPORT (LER)

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, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.

3.Page Millstone Power Station Unit 3 05000423 1 OF 3

4. Title Plant Shutdown Required by Technical Specifications, Emergency Diesel Generator Exceeded Allowed Outage Time
5. Event Date
6. LER Number
7. Report Date
8. Other Facilities Involved Month Year Year I Sequential I Rev Month Facility Name Docket Number Day Number No.

Day Year 05000 Docket Number 12 18 2019 2019 -

001

- 00 02 13 2020 05000
9. Operating Mode
11. This Report is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply)

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) 1 D 20.2203(a)(1)

D 20.2203(a)(4)

D 50.73(a)(2)(iii)

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

D 20.2203(a)(2)(i)

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

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

D 50.73(a)(2)(x)

10. Power Level D

20.2203(a)(2)(ii)

D 50.36(c)(1 )(ii)(A)

D 50. 73(a)(2)(v)(A)

D 73.71 (a)(4)

D 20.2203(a)(2)(iii)

D 50.36(c)(2)

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

D 73.71(a)(5)

D 20.2203(a)(2)(iv)

D 50.46(a)(3)(ii)

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

D 73.77(a)(1) 100 D

20.2203(a)(2)(v) 5a 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)

D Other (Specify in Abstract below or in

3. ASSESSMENT OF SAFETY CONSEQUENCES

, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.

2. DOCKET YEAR 05000423 2019
3. LER NUMBER SEQUENTIAL NUMBER 001 REV NO.

00 All requirements of Technical Specifications were met while the 'A' EOG was out of service. The risk profile was managed in accordance with 10 CFR 50.65(a)(4). The shutdown of MPS3 in accordance with TSAS 3.8.1.1 action b was conducted in an orderly and controlled manner. No other risk significant equipment was out of service during the time that the 'A' EOG was out of service or during the controlled shutdown evolution. The safety consequences of this condition were low. No safety systems actuated. Although the 'A' EOG was out of service, MPS3 was in a normal electrical configuration. All equipment powered from offsite sources and the 'B' EOG, the steam-driven auxiliary feedwater pump, the Unit 3 SBO diesel generator and the two Unit 2 EDGs remained operable throughout. There was no loss of decay heat removal capability, because main and auxiliary feedwater pumps remained operable and available to feed the steam generators.

4. CORRECTIVE ACTION

The signal generator for the speed input to the 'A'EOG tachometer relay was replaced with a magnetic pick up speed signal. The spread exhaust system modification was removed, and the original exhaust system was re-installed.

The EOG was balanced and retested in accordance with its post maintenance test plan and satisfactorily passed the required TS surveillance tests to return the EOG to operability.

Extent of condition was evaluated and addressed for the 'B' EOG.

Additional corrective actions are being taken in accordance with the station's corrective acUon program.

5. PREVIOUS OCCURRENCES

No previous similar events were identified in the last three years in which the condition of an EOG resulted in a plant shutdown required by Technical Specifications.

6. Energy Industry Identification System (EIIS) codes EK, Emergency Diesel Generator Page 3 of 3