LER-2018-001, Reactor Manual Shutdown Due to Turbine Pressure Control Valve Position Changes |
| Event date: |
|
|---|
| Report date: |
|
|---|
| Reporting criterion: |
10 CFR 50.73(a)(2)(iv)(B), System Actuation |
|---|
| 4162018001R00 - NRC Website |
|
text
- ~=':r* Entergy GNR0-2018/00010 March 29, 2018 U.S. Nu9lear 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 2018-001-00, Reactor.Manual Shutdown due to Turbine Pressure Control Valve Position Changes Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
Dear Sir or Madam:
Attached is Licensee Event Report 2018-001-00, Reactor Manual Shutdown due to Turbine Pressure Control Valve Changes. This report is being submitted in accordance with 1 OCFR50. 73(a)(2)(iv)(A) for any event or condition that resulted in a manual or automatic actuation of any of the systems listed in 1 OCFR50.73(a)(2)(iv)(B).
This letter contains no new commitments. If you have any questions or require additional information, please contact Dougla$ Neve at 601-437-2103.
Sincerely, rct_
Eric A. Larson Site Vice President Grand Gulf Nuclear Station
Attachment:
Licensee Event Report 2018-001-00 cc: see next page
GNR0-2018/00010 Page 2 of 2 U.S. Nuclear Regulatory Commission A TIN: Mr. Siva Ling am*
Mail Stop OWFN 8 81 Rockville, MD 20852-2738
.NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U. S. Nuclear Regulatory Commission ATTN: Mr. Kriss Kennedy, NRR/DORL (w/2)
Mail Stop OWFN 8 81 Washington, DC 20555-0001 r
GNR0-2018/00010 Attachment Licensee Event Report 2018-001-00
NRC FORM 366 U.S; NUCLEAR REGULATORY COMMISSION APPROVED. BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (06-2016)
, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection..
- 1. FACILITY NAME
- 2. DOCKET Grand Gulf Nuclear Station, Unit 1 05000 416
E. CORRECTIVE ACTIONS
The following corrective actions are completed or planned.
Completed:
YEAR
- 3. LEA NUMBER SEQUENTIAL NUMBER 2018-001-00 Control circuit card has been replaced and adjusted to correct tolerances and retested satisfactorily.
REV.
NO.
Planned actions included in the corrective action program which may be changed in accordance with the program:
Revise procedure to set up TCV circuitry to reflect appropriate test report F.
SAFETY SIGNIFICANCE
The safety significance of this event is low because all systems operated as designed and the TCV changes did not challenge any safety parameters. The manual scram was performed as a conservative measure. There were no actual nuclear safety consequences or radiological consequences during the eve~t.
G. PREVIOUS SIMILAR EVENTS
Entergy conducted a three-year review of the relevant licensee event reports and determined that there was one similar known event reported as GGNS Licensee Event Report 2016-05-00 "Automatic Reactor SCRAM." The failure in that event was a failed amplifier card, which is different from this event which is an incorrect potentiometer setting. Therefore, the corrective actions for the previous event would not have prevented this event.
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000416/LER-2018-001-01, Grand Gulf. Nuclear Station, Unit 1, Reactor Manual Shutdown Due to Turbine Pressure Control Valve Position Changes | Grand Gulf. Nuclear Station, Unit 1, Reactor Manual Shutdown Due to Turbine Pressure Control Valve Position Changes | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000416/LER-2018-001, Reactor Manual Shutdown Due to Turbine Pressure Control Valve Position Changes | Reactor Manual Shutdown Due to Turbine Pressure Control Valve Position Changes | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000416/LER-2018-002, Both 208 Containment Air Lock Doors Simultaneously Inoperable | Both 208 Containment Air Lock Doors Simultaneously Inoperable | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System | | 05000416/LER-2018-003, Inoperable Reactor Protection Functions During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests Due to Use of a Test Box | Inoperable Reactor Protection Functions During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests Due to Use of a Test Box | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000416/LER-2018-004, Potential Loss of Safety Function Due to Concurrent Inoperability of Two Diesel Generators | Potential Loss of Safety Function Due to Concurrent Inoperability of Two Diesel Generators | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000416/LER-2018-005, Secondary Containment Door Misaligned, Due to 1nadequate Criteria, Could Have Prevented Fulfillment of a Safety Function | Secondary Containment Door Misaligned, Due to 1nadequate Criteria, Could Have Prevented Fulfillment of a Safety Function | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000416/LER-2018-006, Secondary Containment Roof Hatch Left Open Due to Inadequate Corrective Actions | Secondary Containment Roof Hatch Left Open Due to Inadequate Corrective Actions | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
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)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(B) | | 05000416/LER-2018-007, Potential Loss of Safety Function (Residual Heat Removal) and System Actuation Caused by Inadvertent Valve Opening | Potential Loss of Safety Function (Residual Heat Removal) and System Actuation Caused by Inadvertent Valve Opening | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(viii)(A) | | 05000416/LER-2018-008, Unplanned System Actuation (Diesel Generator) Caused by Inadvertently Opening the Wrong Fuse Drawer | Unplanned System Actuation (Diesel Generator) Caused by Inadvertently Opening the Wrong Fuse Drawer | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000416/LER-2018-009-01, Reactor Manual Shutdown Due to Feedwater Level Control Changes | Reactor Manual Shutdown Due to Feedwater Level Control Changes | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000416/LER-2018-009, Reactor Manual Shutdown Due to Feedwater Level Control Changes | Reactor Manual Shutdown Due to Feedwater Level Control Changes | 10 CFR 50.73(a)(2)(iv)(A), System Actuation
10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
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)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000416/LER-2018-010-01, Reactor Manual Scram Due to Main Steam Bypass Stop and Control Valve Drifting Open | Reactor Manual Scram Due to Main Steam Bypass Stop and Control Valve Drifting Open | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000416/LER-2018-010, Reactor Manual Scram Due to Main Turbine Bypass Valve Drifting Open | Reactor Manual Scram Due to Main Turbine Bypass Valve Drifting Open | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
|
