05000416/LER-2019-001-01, Automatic Reactor Shutdown Due to Activation of Generator Lockout
| ML19234A071 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 08/22/2019 |
| From: | Emily Larson Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GNR0-2019/00029 LER 2019-001-01 | |
| Download: ML19234A071 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(B), System Actuation 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 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 10 CFR 50.73(a)(2)(i) |
| 4162019001R01 - NRC Website | |
text
~Entergy GNR0-2019/00029 August 22, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Entergy Operations, Inc.
P.O. Box 756 Port Gibson, Mississippi 39150 Eric A. Larson Site Vice President Grand Gulf Nuclear Station
- Tel: 601-437-7500 10 CFR 50.73
SUBJECT:
Supplemental Licensee Event Report 2019-001-01, Automatic Reactor Shutdown Due To Activation Of Generator Lockout Grand Gulf Nuclear Station, Unit 1 NRC DocketNo. 50-416 Renewed Facility Operating License No. NPF-29
Dear Sir or Madam:
Attached is Licensee Event Report 2019-001-01, Automatic Reactor Shutdown Due To Activation Of Generator Lockout. Thfs report is being submitted in accordance with 10 CFR 50. 73(a)(2)(iv)(A) for an event or condition that resulted in an automatic actuation of the reactor protection system, as specified by 1 O CFR 50.73(a)(2)(iv)(B).
This letter contains no new commitments.
- If you have any questions or require additional information, please contact Jim Shaw at 601-437-2103.
. Sincerely, z;:a~-
Eric A. Larson EA Uram
Attachment:
Licensee Event Report 2019-001 ~p1 (See Next Page)
G N R0-2019/00029 Page 2 of 2 cc:
NRC Region IV - Regional Administrator
.NRC Senior Resident Inspector, Grand Gulf Nuclear Station NRR Project Manager
GNR0-2019/00029 Attachment Licensee Event Report 2019-001-01
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
, the NRC may not conduct or sponsor, and a nerson is not reauired to resoond to the information collection.
- 1. Facility Name*
- 12. Docket Number S.Page Grand Gulf Nuclear Station, Unit 1 05000416 1 OF3
- 4. Title A11i,.. 11r1 ;,
~ -
-- ~h11~1:,-rn*,;, n11A To Aci.:.,,..,tl,-1n of~.....,,...., ;.ii111 I n~kn11t
- 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.
OSOOON/A
_J; Facility Name Docket Number 02 23 2019 2019
- - 001
- - 01 8
22 2019 N/A OSOOON/A*
- 9. Operating Mode
- 11. This Report is Submitted Pursuantto the Requirements of 10 CFR §: (Check all that apply) 1 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)
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) 181 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 73.7-1 (a)(5) 100 D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 73.77(a)(1)
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)(ii)
D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73. 77(a)(2)(iii)
D 50.73(a)(2)(i)(C)
D Other (Specify in Abstract below or in YEAR 2019
- 3. LER NUMBER SEQUENTIAL NUMBER
- - 001 Grand Gulf Design Engineering and key stakeholders reviewed critical components and safety related engineering changes completed during the time period between September 2016 and February 2019 along with pending modifications for extent of cause in the execution of standards.
Planned:
REV NO.
- - 01 Develop a permanent engineering change to approve negative phase sequence relay set-point was adjusted back to 9 percent.
Develop and implement a workshop to communicate standards for detail quality review for preparation development of an Engineering Change in accordance with EN-OC-115 Attachment 9.19 Standard Design process. Incorporate examples of acceptable products and contrast with examples of poor quality products and incorporate learning activities for quality review of products to demonstrate understanding specifically targeted at Topic note development, Use of Internal-OE, Calculation reviews and Owner's acceptance of vendor products in accordance with.site procedures.
Develop and implement a standard for performing Engineering Design Review for Engineering changes. Establish in the standard critical attributes for review, requirements for organizational engagement at key milestones, and requirements for risk ranking for prioritization for review of engineering changes.
(
Develop a detailed quality review checklist with attributes required for preparation of an Engineering Change in accordance with site procedures.
Develop and implement job aids for performing Owner's Acceptance of Vendor products and incorporate into the Engineering Change Process in accordance with site procedures.
Develop a detailed critical attributes list for third party review for engineering changes using criteria for each phase of a modification in accordance with site procedures.
Safety Significance
The incorrect set-point resulted in an automatic unplanned Reactor SCRAM as a result of Generator Lockout and Turbine Trip signals. All safety systems responded as designed. There were no other actual consequences to safety of the general public, nuclear safety, industrial safety and radicflogical safety for this event.
The actual consequences were an automatic, unplanned Reactor SCRAM as a result of Generator Lockout and Turbine Trip signals. There were no other actual consequences to safety of the general public, nuclear safety, industrial safety and radiological safety for this event.
There was no challenge to protecting the health and safety of the general public because all Emergency Core Cooling Systems (ECCS) and Engineered Safety Features (ESF) equipment were operable and available prior to the automatic Reactor SCRAM. Operators followed the appropriate off-normal procedures and responded appropriately to the automatic SCRAM.
Previous Similar Events
Enter conducted a three ear review, as described in NUREG-1022 uidance, and no similar events were revealed.