text
~Entergy.
GNR0-2019/00035 August 7,.2019 U.S. Nuclear Regulatory Commiss.ion Attn: Document Control Desk Washington, DC 20555-0001 Entergy Operations, Inc.
P. 0. Box756 Port Gibson, MS 39150 Eric A. Larson Site Vice Presid~nt Grand Gulf Nuclear Station Tel. (601) 437-7500 10CFR50.73
SUBJECT:
Supplemental Licensee Event Report 201'8-001-01, Reactor Manual Shutdown due to Turbine Pressure ControlValve Position Changes Grand Gulf. Nuclear Station, Unit 1 Docket No.. 50-416 License No. NPF-29
Dear Sir or Madam:
Attached is Supplemental Licensee E.vent Report 2018-001-01, Reactor Manual Shutdown due to Turbi'ne Pressure Control Valve Changes. This report is being: submitted in accordance with 10CFR50.73(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 Jim Shaw at 601-437-2103.
Sincerely, r0L Eric A. Larson EAL/rtw At~achment:
cc:
Supplemental Licensee Event Report 2018-001-01 NRC Region IV - Regional Administrator NRC Senior Resident Inspector, Grand Gulf Nuclear Station NRR Project Manager
GNR0-2019/00035 Attachment Supplemental Licensee Event Report 2018-001-01
NRC FORM 366
{04-2018)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 LICENSEE EVENT REPORT (LER)
(See Page 2 for required number of digits/characters for each block)
(See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/readinq-rm/doc-collections/nuregs/staff/sr1022/r3l)
, the NRG may not conduct or sponsor, and a person is not reauired to resoond to the information collection.
~.Page Grand Gulf Nuclear Station, Unit 1 05000416 1 OF3
- 4. Title Reactor Manual Shutdown Due to Turbine Pressure Control Valve Position Chanaes
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved Docket Number Sequential Rev Facility Name Month Day Year Year Number No.
Month Day Year N/A 05000 N/A 01 30 2018 2018 001 01 08 07 2019 Facility Name N/A Docket Number 05000 N/A
- 9. Operating Mode
- 11. This Report is Submitted Pursuant to the Requirements of 1 O CFR §: (Check all that apply)
MODE1 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(g}(2)(iii)
D 50. 73(a)(2)(ix)(A)
D 20.2203(a)(2)(i)
D 50.36(c)(1 )(i)(A)
[8] 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. 11 (a)(5) 91 °k 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
CORRECTIVE ACTIONS
The. following corrective actions are completed or planned.
Completed:
The main.steam line resonance compensator circuit was recalibrated.
YEAR 2018
- 3. LER NUMBER SEQUENTIAL NUMBER
- - 001 Work instructions to setup steam line compensator were revised to provide corrected work steps.
F.
SAFETY SIGNIFICANCE
The safety significance of this event is low because*au systems operated as designed and the TCV changes did not challenge any safety parameters. The manual scram was performed as a conservative measure. There w'ere no actual nuclear safety consequences or radiological consequences during the event.
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 was an incorrect potentiometer setting. Therefore, the corrective actions for the previous event would not have prevented this event. Page 3 of 3 REV NO.
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| 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 |
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