05000423/LER-2020-001, Technical Specification Allowed Outage Time Exceeded by Accident Monitoring Instrument

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Technical Specification Allowed Outage Time Exceeded by Accident Monitoring Instrument
ML20070H650
Person / Time
Site: Millstone Dominion icon.png
Issue date: 03/05/2020
From: Daugherty J
Dominion Energy Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
20-072 LER 2020-001-00
Download: ML20070H650 (6)


LER-2020-001, Technical Specification Allowed Outage Time Exceeded by Accident Monitoring Instrument
Event date:
Report date:
Reporting criterion: 10 CFR 50.73(a)(2)(ii)

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)

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)(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)
4232020001R00 - 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 Attention: Document Control Desk Washington, DC 20555 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 LICENSEE EVENT REPORT 2020-001-00

~

Dominion

~

Energy Serial No.

MPS Lie/DCB Docket No.

License No.20-072 RO 50-423 NPF-49 MARO.5 2020 TECHNICAL SPECIFICATION ALLOWED OUTAGE TIME EXCEEDED BY ACCIDENT MONITORING INSTRUMENT This letter forwards Licensee Event Report (LER) 2020-001-00 documenting a condition discovered at Millstone Power Station Unit 3, on January 15, 2020. This LER is being submitted pursuant to 10 CFR 50. 73(a)(2)(i)(B) as an operation prohibited by plant technical specifications.

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

Langan at (860) 444-5544.

Sincerely,

//) ~

JoM R. Daugherty Site Vice President - Millstone Attachments: 1 Commitments made in this letter: None

cc:

U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd.

Suite 100 King of Prussia, PA 19406-2713 RV. Guzman Serial No.20-072 Docket No. 50-423 Licensee Event Report 2020-001-00 Page 2 of 2 NRC 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 NRC Senior Resident Inspector Millstone Power Station

ATTACHMENT Serial No.20-072 Docket No. 50-423 Licensee Event Report 2020-001-00 LICENSEE EVENT REPORT 2020-001-00 TECHNICAL SPECIFICATION ALLOWED OUTAGE TIME EXCEEDED BY ACCIDENT MONITORING INSTRUMENT MILLSTONE POWER STATION UNIT 3 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES:

03/31/2020 (04-2018)

, the NRC may not htt[l:i/www.nrc.gov/reading-rm/doc-<::ollections/nuregs/staff/sr1022/r3/}

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 Technical Specification Allowed Outage Time Exceeded by Accident Monitoring Instrument
5. Event Date
6. LER Number
7. Report Date
8. Other Facilities Involved I

Sequential I Rev Facility Name Docket Number Month Day Year Year Number No.

Month Day Year 05000 Docket Number 01 15 2020 2020 -

001

- 00 03 05 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

D D

D 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(iii) 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)

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)

[xi 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 consequences of this condition were not safety significant. If AFW flow indication was required during the time that computer point 3FWA-F51B3 was inoperable, there was indication of AFW flow to the 'B' Steam Generator by another channel, 3FWA*Fl33B1, which was operable. If this redundant channel was not available, operators would use diverse indications such as auxiliary feedwater pump status, auxiliary feedwater discharge pressure, control valve position and multiple channels of both narrow range and wide range steam generator level indication to maintain decay heat removal from this steam generator. The affected channel offlow indication would have responded to flow although it would have indicated higher flow than actual.

While 3FWA-F51B3 was inoperable, 3FWA*FT33B was operable and providing indication of 'B' Steam Generator AFW flow to both the main board indicator, 3FWA*Fl33B1, and to a computer point, 3FWA-F33B3. The Safety Parameter Display System Heat Sink Critical Safety Function Status Tree uses 3FWA-F33B3 for AFW flow to the 'B' Steam Generator and therefore was not affected.

4. CORRECTIVE ACTION

\\

The transmitter was calibrated and restored to operable status.

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

5. PREVIOUS OCCURRENCES

There are no previous occurrences over the past three years.

6. Energy Industry Identification System (EIIS) codes BA: Auxiliary Feedwater PDT: Transmitter, Differential, Pressure Page 3 of 3