05000416/LER-2016-009, Regarding Entry Into Mode of Applicability with the OPRM Upscale Settings Incorrectly Set
| ML17005A335 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/05/2017 |
| From: | Nadeau J Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GNRO-2016/00063 LER 16-009-00 | |
| Download: ML17005A335 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 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)(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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 4162016009R00 - NRC Website | |
text
--==-Entergy GNRO-2016/00063 January 5, 2017 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150 James Nadeau Manager, Regulatory Assurance Grand Gulf Nuclear Station Tel. (601) 437-2103
SUBJECT:
Dear Sir or Madam:
Licensee Event Report LER 2016-009-00, Entry into Mode of Applicability with the OPRM Upscale Settings Incorrectly Set Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29 Attached is Licensee Event Report LER 2016-009-00, Entry into Mode of Applicability with the Oscillation Power Range Monitor (OPRM) Upscale Settings incorrectly set. This report is being submitted in accordance with Title 10 Code of Federal Regulations 50.73(a)(2)(i)(B) and 10CFR50.73(a)(2)(v)(A).
This letter contains no new commitments. If you have any questions or require additional information, please contact James Nadeau at 601-437-2103.
SinCereIY'/f~~
JJN/ram
Attachment:
Licensee Event Report (LER) 2016-009-00 cc: see next page
GNRO-2016/00063 Page 2 of 2 u.s. Nuclear Regulatory Commission ATTN: Mr. Siva Lingam Mail Stop OWFN 8 B1 Rockville, MD 20852-2738 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 u. S. Nuclear Regulatory Commission ATTN: Marc L. Dapas (w/2)
Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511
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.;,~""Glt,('f" LICENSEE EVENT REPORT (LER)
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- 1. FACILITY NAME
~. DOCKET NUMBER
. PAGE Grand Gulf Nuclear Station Unit 1 05000416 10F2
- 4. TITLE Entry into Mode of Applicability with the Oscillation Power Range Monitor Upscale Settings Incorrectly Set
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED YEAR ISEQUENTIALI REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.
MONTH DAY YEAR N/A 05000N/A FACILITY NAME DOCKET NUMBER 03 27 2016 2016
- - 009
- - 00 01 05 2017 N/A
~5000N/A 9.OPERATING MODE 11.THIS REPORTISSUBMITTEDPURSUANTTO THE REQUIREMENTSOF 10 CFR§: 'Check all that apply)
MODE 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)
D 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) 181 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) 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)(i)
D 20.2203(a)(2)(vi) 181 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii)
D 50.73(a)(2)(i)(C)
D OTHER Specify inAbstract below orinNRC Form 366A
- 12. LICENSEE CONTACT FOR THIS LER ICENSEE CONTACT rELEPHONE NUMBER (Include Area Code)
James Nadeau, Manager Regulatory Assurance 601-437-2103 13.COMPLETEONE UNE FOR EACH COMPONENTFAILUREDESCRIBEDINTHISREPORT
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX A
N/A N/A N/A N/A N/A N/A N/A N/A N/A
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR [gj YES (Ifyes, complete 15. EXPECTED SUBMISSION DATE)
D NO SUBMISSION 5
31 2017 DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15single-spaced typewritten lines)
On March 27, 2016, the Entergy, while returning the GGNS Unit 1 to power operations at the conclusion of Refueling Outage 21, reactor thermal power was allowed to exceed 16.8 percent without first fully calibrating the Oscillation Power Range Monitor (OPRM) to include the new limits required by the adoption and implementation of the Maximum Extended Load Limit Line Plus (MELLLA+) operating range. Specifically, the OPRM Upscale setting requirements specified in Technical Specification 3.3.1.1, Reactor Protection System (RPS) Instrumentation, Table 3.3.1.1-1, Reactor Protection System Instrumentation, Function 2, Average Power Range Monitors, Sub-Function f. OPRM Upscale were not fully met. The direct cause of this event was the failure to ensure the required procedure changes were incorporated and performed prior to the unit entering the mode of applicability. Corrective actions included the addition of the condition to Limiting Condition for Operation tracking system to ensure resolution prior to a mode of applicability. This event is reportable as a licensee event report (LER) in accordance with 10CFR50.73(a)(2)(i)(B) as an operation or condition prohibited by Technical Specifications and 10CFR50.73(a)(2)(v)(A) for the loss of safety function.
2016
- - 009
- - 00 On March 27, 2016, the Entergy, while returning the GGNS Unit 1 to power operations at the conclusion of Refueling Outage 21, reactor thermal power was allowed to exceed 16.8 percent without first fully calibrating the Oscillation Power Range Monitor (OPRM) to include the new limits required by the adoption and implementation of the Maximum Extended Load Limit Line Plus (MELLLA+) operating range. Specifically, the OPRM Upscale setting requirements specified in Technical Specification 3.3.1.1, Reactor Protection System (RPS) Instrumentation, Table 3.3.1.1-1, Reactor Protection System Instrumentation, Function 2, Average Power Range Monitors, Sub-Function f. OPRM Upscale were not fully met.
This error was subsequently discovered on November 17, 2016 during a review of General Electric Hitachi (GEH)
Report 0000-0158-7807, Revision 0000, PRNM System DSS-CD Settings against the settings in GGNS Procedures 06-IC-1C51-R-0077A/B/C/D, Average Power Range Monitor Calibration.
REPORTABILITY
This event is reportable as a licensee event report (LER) in accordance with 10CFR50.73(a)(2)(i)(B) as an operation or condition prohibited by Technical Specifications and 10CFR50.73(a)(2)(v)(A) for the loss of safety function.
CAUSE
The causal evaluation for this event is ongoing and this LER will be supplemented upon completion of the causal analysis.
The direct cause of this event was the failure to ensure the required procedure changes were incorporated and performed prior to the unit entering the mode of applicability.
CORRECTIVE ACTIONS
Corrective actions included the addition of the condition to Limiting Condition for Operation tracking system to ensure resolution prior to a mode of applicability.
The condition has been added to Limiting Condition for Operation for tracking ensure resolution prior to restart.
SAFETY SIGNIFICANCE
There were no actual nuclear safety consequences or radiological consequences as a result of this calibration error.
No Technical Specification Safety Limits were violated.
PREVIOUSLY SIMILAR EVENTS LER 2013-006-00, Primary Containment Inoperable Due to an Inadequate Surveillance Procedure Resulting in a Loss of Safety Function The causes and corrective actions implemented as a result of LER 2013-006-00 were reviewed and it has been determined that the corrective actions were acceptable and could not have prevented the event documented in this LER.Page 2 of 2