05000424/LER-2019-001, Engineered Safety Feature Chiller Inoperability Causes Operation in a Condition Prohibited by Tech Specs

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Engineered Safety Feature Chiller Inoperability Causes Operation in a Condition Prohibited by Tech Specs
ML19100A447
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 04/08/2019
From: Taber B
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-19-0351 LER 2019-001-00
Download: ML19100A447 (4)


LER-2019-001, Engineered Safety Feature Chiller Inoperability Causes Operation in a Condition Prohibited by Tech Specs
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications

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)(x)

10 CFR 50.73(a)(2)(v), Loss of Safety Function

10 CFR 50.73(a)(2)

10 CFR 50.73(a)(2)(i)
4242019001R00 - NRC Website

text

-~ Southern Nuclear April 8, 2019 Docket No:

50-424 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 B. Keith Taber Vice President Fleet Operations Vogtle Electric Generating Plant-Unit 1 Licensee Event Report 2019-001-00 3535 Colonnade Parkway Birmingham, AL 35243 205*992*5859 tel NL-19-0351 Engineered Safety Feature Chiller inoperabilitv causes operation in a Condition Prohibited by Tech Specs Ladies and Gentlemen:

In accordance with the requirements of 10 CFR 50.73(a)(2)(i)(B), Southern Nuclear Operating Company is submitting the enclosed Licensee Event Report, 2019-001-00 for Vogtle Electric Generating Plant Unit 1. This letter contains no NRC commitments. If you have any questions, please contact Matthew Horn at (706) 848-1544.

Respectfully submitted, b

B. Keith Taber Vice President Fleet Operations BKT/KCW Enclosure: Unit 1 Licensee Event Report 2019-001-00 Cc: Regional Administrator NRR Project Manager-Vogtle 1 & 2 Senior Resident Inspector-Vogtle 1 & 2 RType: CVC7000

Vogtle Electric Generating Plant-Unit 1 Licensee Event Report 2019*001*00 Engineered Safety Feature Chiller inoperabilitv causes operation in a Condition Prohibited by Tech Specs Enclosure Unit 1 Licensee Event Report 2019-001-00

NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 104-2018)

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

  • Page Vogtle Electric Generating Plant, Unit 1 05000424 1 OF2
4. Title Engineered Safety Feature Chiller inoperability causes Operation in a Condition Prohibited by TS.
5. Event Date
6. LER Number
7. Report Date
8. Other Facilities Involved Sequential Rev Facility Name Docket Number Month Day Year Year Month Day Year N/A Number No.

05000 02 10 2019 2019

- 001
- 00 OJ../ Jo ~019 Facility Name Docket Number N/A 05000
9. Operating Mode
11. This Report Is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply) 1 0 20.2201 (b) 0 20.2203(a)(3)(i) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) 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) 0 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}

100 0 20.2203(a}(2)(iii) 0 50.36(c}(2) 0 50.73(a)(2)(v}(B) 0 73.71(a)(5}

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)(ii) 0 20.2203(a)(2)(vi) 1:8] 50. 73(a)(2)(i)(B) 0 50.73(a)(2)(vii}

0 73.77(a)(2)(iii) 0 50.73(a)(2)(i)(C) 0 Other (Specify in Abstract below or in NRC Form 366A

12. Licensee Contact for this LER

~censee Contad

~:lephone Number (lndude Area Code)

~ogtle Electric Generating Plant, Matthew Horn, Regulatory Affairs Manager 06-848-1544

13. Complete One Une for each Con ~nent Failure Described in this~_

Cause

System Component Manufacturer Reportable To ICES

Cause

System Component Manufacturer Reportable To ICES X

KM CHU T265 y

N/A

14. Supplemental Report Expected Month Day Year 0 Yes (If yes, complete 15. Expected Submission Date) 121 No
15. Expected Submission Date N/A N/A N/A f'\\bstract (Limit to 1400 spaces, i e. approximately 14 single-spaced typewritten lines}

~t approximately 0317 EST on February 7, 2019 while the unit was in Mode 1 and 100 percent power, the Unit 1 A-train Engineered Safety Feature Chiller was stopped after a post maintenance run. When the chiller was restarted on February 12, 2019 at 0026 EST it immediately tripped on high condenser pressure. During post-event analysis, it was determined hat the chiller was inoperable immediately after being shut down from the post-maintenance run until it was repaired and declared operable on February 14, 2019 at 0436 EST. This resulted in the chiller being inoperable for approximately 169.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, which is longer than the Technical Specification allowed out of service time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. This resulted in the unit operating in a Condition Prohibited by Technical Specifications which is reportable under 10 CFR 50.73(a)(2)(i)(B).

ifhis event had no adverse effects on the health and safety of the public and is of very low safety significance.

NRC FORM 366 (02-2018)

A. Event Description

3. LER NUMBER SEQUENTIAL NUMBER
- 001 REV NO
- 00 On Feb 4, 2019, with Unit 1 in Mode 1 and 100 percent power, the Unit 1 A-train Engineered Safety Feature (ESF) Chiller was taken out of service for planned maintenance. On Feb 6, 2019 it was started for the 1 0-hour post-maintenance run at maximum loading. The chiller ran satisfactorily for the duration of the test and was shut down at 0317 EST on Feb 7, 2019.

Immediately after the test run, the pump out compressor, which removes non-condensable gases from the chiller automatically started and ran for 1345 minutes of the 1440 minutes in a 24-hour period. The continuous running of the pump out compressor indicates that significant air in leakage was present. This air in leakage caused the condenser vacuum to degrade and the chiller was not able to perform it's required function. When the chiller was restarted on Feb 12 at 0026 EST, it tripped on high condenser pressure. The chiller was declared inoperable and repair work began. The chiller was evacuated and purged with nitrogen gas to facilitate leak checks. Leaks were identified and sealed, and the chiller was declared operable on February 14 at 0436. The total time that the chiller was inoperable was 169.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> or 7 days, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and 19 minutes. The Technical Specification allowed outage time for this chiller is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Because the chiller was inoperable for longer than the time allowed by Technical Specifications, this event is reportable under 10 CFR 50.73(a)(2)(i)(B).

During the time while the Unit 1 A-train ESF chiller was inoperable due to air in leakage, the Unit 1 S-train ESF chiller was taken out of service on Feb 10, 2019 for 3 minutes when the Control Room handswitch was taken to stop for planned surveillance testing. The S-train chiller was available, but not Operable. During this time there were no ESF chillers Operable on Unit 1, however both chillers were not out of service for longer than the 1-hour completion time in Technical Specification 3.7.14 Condition B.

B. Cause of Event

The cause of the event was inadequate sealing of the ESF chiller which allowed air in leakage that degraded the condenser vacuum. This allowed air into the condenser, which is normally operated below atmospheric pressure, and caused the chiller to trip.

C. Safety Assessment

The safety significance of this event is very low. No system actuations occurred due to this failure and the reactor was maintained at 100 percent power. During the time the chiller was inoperable, it's critical attribute to maintain the Nuclear Service Cooling Water pressure boundary, as defined in the ESF chiller 10 CFR 50.69 categorization, was maintained. Also, during this time, the other chiller was operable and able to provide its safety function except during the 3 minutes when it was taken out of service on February 10. However, the chiller was only inoperable because of the handswitch position in the Control Room and could have been started manually in the event it was needed.

D. Corrective Actions

The chiller was purged with nitrogen and sniffed to find areas were leaks were present. Once these leaks were discovered they were sealed. The other train chiller on Unit 1 and the other two chillers on Unit 2 were monitored and no leakage points were identified.

E. Previous Similar Events

None