05000416/LER-2017-003-02, Reactor Shutdown Because of Condensate System Inventory Depletion and a Manual Reactor Core Isolation Cooling (RCIC) Initiation Because of a Feedwater System Shutdown
| ML18275A416 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  (NPF-029) |
| Issue date: | 10/02/2018 |
| From: | Emily Larson Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GNR0-2018/00036 LER 2017-003-02 | |
| Download: ML18275A416 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 4162017003R02 - NRC Website | |
text
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"-'P... n ergy GNR0-2018/00036 October 2, 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:
Supplemental Licensee Event Report 2017-003-02, Reactor Shutdown Because of Condensate System Inventory Depletion and a Manual Reactor Core Isolation Cooling (RCIC) Initiation Because of a Feedwater System Shutdown Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
Dear Sir or Madam:
Attached is Supplemental Licensee Event Report 2017-003-02. This supplement provides additional information related to the cause and corrective actions for this event.
This letter contains no new commitments. If you have any questions or require additional information, please contact Douglas Neve at 601-437-2103.
Sincerely, rc/4----
Eric A. Larson Site Vice President Grand Gulf Nuclear Station
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Attachment:
Supplemental Licensee Event Report 2017-003-02 cc: see next page
GNR0-2018/00036 Page 2 of 2 cc:
NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATTN: Ms. Lisa M. Re*gner Mail Stop OWFN 8 81 Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission ATTN: Mr: Kriss Kennedy, NRR/DORL (w2)
Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511
GNR0-2018/00036 Attachment Supplemental Licensee Event Report 2017-003-02
_(02~2018)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-;0104 EXPIRES: 03/31/2020
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- 1. Facility Name. :
.Grand Gulf Nuclear Static>n, -Unit 1 4;Title person is.not reouired io respond to. the information.collection:
- 2~ Docket Number 05000416.
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.Reactqr Shutdqwn Because of Conc;lensate Syst~m Inventory *oepletio11 and a :Manual Heac_tor Core: Isolation Cooling.(RCIC) lnitiatipn :E3~cause of FeedwatE3r\\System Shutdown :..
- :s. Event Date*.
Month :
Day:
- Year
- : : 6. LER Number Year
.Sequential Nuinber
- Rev No.
- 7. Report Dat~ *
- 8. Other Facilities l_nvolved Month D_ay Facility Name :
Year
- . NIA
- Docket Number 05000N/A :.: **
04 2cl°11.: :2011
- - 003
- - 02 *::
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. 05000N/A 9; dperaiii,g Mode
- 11. Thi~ Report is Submitted Pursua~t to the Requiremen~ of 10.CFR §: (Check all that apply).:
D 20.2201 (b) *
- 0 20.22oa(a)(~)(i) ti :so.fa(a)(2)(ii)(A)
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- * * * : D 20.22o~(a)(2)(iii)
D 20.22oa(a)(2)(iv)
... 20.2203(a)(2)(v)
- :[] 20.2203(a)(3)(ii)
D 20.2203(a)(4) 0 50.36(6):(:f )(i)(A)
. Q 50.36(c)(1 )(ii)(A).
- D 50.36(c)(2)..
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. IJ 50.73(a)(2)(i)(B) 0 50.73(a)(2)(ii)(B):.
- D 50.73(a}(2)(viii)(B)
D 50.73(a)(2)(iil)
- D 50.73(a)(2)(ix)(A)
- 181 :sci.73(a)(2)(iv)(A)
- * : 0 50.73(a)(2)(x)
D 50.73(a)(2)(v)(J.\\).
D *13.71 (a)(4)
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. _D 73.71 (a)(5)
- D 73.77{a)(1f *
- 0 73.77(a)(2)(ii) * * *
- q 1s.1?(a)(2)(iii) 0 50. 73(a)(2)(i)(C)
- . D Other (Specify in Abstract below or in C. REPORTABLE OCCURRENCE YEAR 2017
- 3. LER NUNIBER SEQUENTIAL NUMBER
- - 003 T-his licensee event-report (LER) *is-being *submitted *pursuant to Title 1-0 Code of Federal Regulations (10 CFR) 50.73(a)(2)(iv)(A) for a manual actuation of the reactor protection system (RPS) and the manual initiation of RCIC.
Telephonic notification was made via the U.S. Nuclear Regulatory Commission (NRC) Emergency Notification System 05:57 on April 4, 2017, pursuant to 10 CFR 50.72(b)(3)(iv)(A) and 10 CFR 50.72 (b )(2)(iv)(B).
The-notification to the NRC was performed 1 *hour and 47-minutes *beyond the-required 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> time required for NRC notification.
D.
CAUSE
I The lowering CST level was caused by a condensate system leak. Excessive vibration on an under-torqued pipe flange resulted in a failed pipe connection. The vibration was caused by cycling water
- injection valves, which -wer-e -receiving -faulty -signals from a -failing Turbine -Control-Card.
E.
CORRECTIVE ACTIONS
Immediate Actions:
The plant was placed in cold shutdown. Plant walkdowns were performed by Operations,
- Maintenance, and Engineering, which identified the damaged condensate piping.
Completed Actions:
The piping and flange connection were repaired, and the Turbine Control Card was replaced.
Planned Actions:
The Turbine Controls System is planned to be replaced in Refueling Outage 22 in 2020.
F.
SAFETY ASSESSM\\ENT There were no actual nuclear safety consequences or radiological consequences during the event. All systems operated ~s designed and there was no release of radioactivity.
REV NO.
- - 02 NRC FORM 3668 (02-2018)
Page 3 of 4 (04-2017)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 3/31/2020 LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET (See NUREG-1022, R.3 for instruction and guidance for completing this forn, http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3D
, the NRC may not conduct or sponsor, and a person is not required to respond to,. the information collection.
- 3. LER NUMBER Grand Gulf Nuclear Station, Unit 1 05000-416 YEAR 2017 G.
PREVIOUS SIMILAR EVENTS
SEQUENTIAL NUMBER
- - 003 REV NO.
- - 02 On June 25, 2016, an Automatic Reactor SCRAM (LER 2016-005-01) occurred due to a failed operational amplifier installed on a circuit card that provided input to the Turbine Control System. The corrective action to preclude repetition for this event is the same as that for LER 2017-003-02 (replace Turbine Control System with digital control system). The replacement is planned for Refueling Outage 22 in 2020 and therefore does not constitute an ineffective corrective action.
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