05000443/LER-1917-001, Regarding Manual Reactor Trip in Response to a Feedwater Isolation Due to High Level in Steam Generator B
| ML17178A359 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/27/2017 |
| From: | Browne K NextEra Energy Seabrook |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| SBK-L-17106 LER 17-001-00 | |
| Download: ML17178A359 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(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) |
| 4431917001R00 - NRC Website | |
text
June 27, 2017 10 CPR 50.73 Docket No. 50-443 SBK-L-17106 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 NEXTeraM EN~~~~
Seabrook Station Licensee Event Report (LER) 2017-001-00 Manual Reactor Trip in Response to a Peedwater Isolation due to High Level in Steam Generator
'B' Enclosed is Licensee Event Report (LER) 2017-001-00. This LER reports an event that occurred at Seabrook Station on April 29, 201 7. This event is being reported pursuant to the requirements of 10 CPR 50.73(a)(2)(iv)(A).
Should you require further information regarding this matter, please contact me at (603) 773-7932.
Sincerely, cc:
D. Dorman, NRC Region I Administrator J. Poole, NRC Project Manager P. Cataldo, NRC Senior Resident Inspector NextEra Energy Seabrook, LLC P.O. Box 300, Seabrook, NH 03874
Enclosure to SBK-L-17106
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2017) htti;i://www.nrc.gov/reading-rm/doc-QolleQjiQns/ou[egs/staff/s[1022/[3/)
the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Seabrook Station 05000 443 1 OF 3
- 4. TITLE Manual Reactor Trip in Response to a Feedwater Isolation due to High Level in Steam Generator 'B'
- 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 MONTH DAY YEAR NUMBER NO.
05000 FACILITY NAME DOCKET NUMBER 04 29 2017 2017 -
001 -
00 06 28 2017 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) 1 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 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)
[{] 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 13.71(a)(4)
D 202203(a)(2)(iii)
D 5o.36(c)(2)
D 50.73(a)(2)(v)(B)
D 13.71(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) 12 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 13.77(a)(2)(ii)
D 50.73(a)(2)(i)(C)
D OTHER Specify in Abstract below or in An EFW actuation also results in a SG blowdown isolation, and this function was performed within five seconds. Due to a lack of decay heat, the RCS temperature cooled to approximately 535 deg. F and a subsequent automatic letdown isolation occurred due to low pressurizer level at 17%. The crew then successfully stabilized the plant in Mode 3 at normal operating pressure and temperature and normal letdown and SG levels were restored. The event posed no actual or potential hazard to public health or safety.
The event resulted in a valid actuation of the reactor protection system and met the reporting criteria of 10 CFR 50.72(b)
(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). A four hour report was made to the NRC at approximately 2119 on April 29, 2017 (event number 52718). Plant operators responded to the plant trip in accordance with approved procedures, and safety systems functioned as expected. No adverse consequences resulted from this event and this incident had no adverse impact on health and safety of the public or the plant and its personnel. This event did not involve a safety system functional failure.
Corrective Actions
Completed Corrective Actions
- 1. Individual performance was corrected.
- 2. All similar transmitter valve positions were verified. All valves were found in their correct position.
Planned Corrective Actions
- 1. Develop and present a case study on this event to l&C technicians that captures the specific details of this event and lessons learned.
- 2. Develop a maintenance procedure that provides specific step-by-step instructions to perform SG level channel backfilling operations.
Similar Events
There have been no previous licensee event reports at Seabrook for a similar event.
Additional Information
The Energy Industry Identification System (EllS) codes are included in this LER in the following format: [EllS system identifier, EllS component identifier]. Page 3
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