05000416/LER-2017-007-01, Engineered Safety Features System Actuations Due to the Loss of Engineered Safety Features Transformer 11
| ML18346A393 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  (NPF-029) |
| Issue date: | 12/12/2018 |
| From: | Emily Larson Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GNRO-2018/00056 LER 2017-007-01 | |
| Download: ML18346A393 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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 |
| 4162017007R01 - NRC Website | |
text
'!!:~ Entergy I
GNR0-2018/00056 December 12, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Entergy Operations, Inc.
P. 0. Box756 Port Gibson, MS 39150 Eric A. Larson Site Vice President Grand Gulf Nuclear Station Tel. (601) 437-7500 10CFR50.73
SUBJECT:
Licensee Event Report 2017-007-01, Engineered Safety Features System Actuations due to the loss of Engineered Safety Features Transformer 11 Grand Gulf Nuclear Station, Unit 1 Docket No. 50-410 License No. NPF-29
Dear Sir or Madam:
Attached is Supplemental Licensee Event Report 2017-007-01, Engineered Safety Features System Actuations due to the loss of Engineered Safety Features Transformer 11.
n This letter contains no new commitments. If you have any questions or require additional information, please contact Douglas Neve at 601-437-2103.
Sincerely, Eric A. Larson EAL/dre
Attachment:
Licensee Event Report 2017-007-01 cc: see next page
G N R0-2018/00056 Page 2 of 2 cc:
NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATTN: Mr. Siva Lingam Mail Stop OWFN 8 B 1 Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission ATTN: Mr. Kriss Kennedy Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511
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GNR0-2018/00056 Attachment Licensee Event Report 2017 -007-01
NRCFORM366 U.S. NUCLEAij REGULATORY COMMISSION APPROVED '3Y OMS: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
, the NRG may not conduct or sponsor, and a oerson is not reauired to resoond to the information collection.
i.Page Grand Gulf Nuclear Station, Unit 1 05000416 1 OF3
- 4. Title
- -...,;.. ~*..... : ~-&-'-;; '=A~h m:::.~ ~.. --:~ *
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1:0. rh IA to th?- In~~ 1,f ;.,.. ;,,~r~....,-* ~;:;,7,;:.;!*v Fi:::.~h IrP~ T. "11 -~~-,..,,.~, 11
- 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 NIA Number No.,
OSOOONIA 12 12 2017 2017
- - 007
- - 01 12 12 2018 Facility Name Docket Number NIA OSOOONIA
- 9. Operating Mode
- 11. This Report is Submitted Pursuant to the Requirements of 1 O CFR §: (Check all that apply) 1 D 20.2201(b)
D 20.2203(a)(3)(i)
D 50.73(a)(2)(il)(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 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)
IZI 50.73(a)(2)(iv)(A)
D 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)
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) 18%
D 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(C)
D 73.77(a)(1)
D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(D) 0 73.77(a)(2)(ii)
D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii) 0 73.77(a)(2)(iii)
D 50. 73(a)(2)(i)(C)
D Other (Specify in Abstract below or in
CORRECTIVE ACTIONS
YEAR 2017
- 3. LER NUMBER SEQUENTIAL NUMBER
- - 007 Spare Essential Transformer 21 was placed into service and normal power was restored. The new cable that was pulled has a copper shield that is not a susceptible to degrading in moist condition as the zinc shield. The new cable that is now in service had a megger, Tan Delta, and a Hi-Pot test performed.
SAFETY SIGNIFICANCE
There were no nuclear safety consequences or radiological consequences as a result of this event. No Technical Specification Safety Limits we.re violated. Upon the loss of Engineered Safety Feature Transformer 11 all required accident mitigation ESF components responded as designed. The isolation of the Reactor Core lsqlation Cooling System, although unexpected, did not adverse.ly impact the plant's ability to respond to the event.
PREVIOUSLY SIMILAR EVENTS LER 2015-001, Automatic Actuation of the Reactor Protection System (RPS) due to a Fault in the Protective Relaying Circuitry on the "B" Main Transformer LER 2016-002, Automatic Actuation of the Reactor Protection System due to "B" Main Transformer Wiring LER 2016-006, Multiple Valid Engineered Safety Feature Actuations Entergy has reviewed the events listed in the licensee event reports (LER) documented above to determine if the corrective actions should have prevented the event documented in this LER. Based on a preliminary evaluation it has been concluded the established corrective actions would not have prevent this event.
Entergy's investigation into the cause of this event and the development of corrective actions to preclude recurrence are ongoing. This section will be supplemented at the conclusion of this effort.
REV NO.
- - 01 NRG FORM 3668 (02-2018)