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| {{Adams
| | #REDIRECT [[05000416/LER-2016-009, Regarding Entry Into Mode of Applicability with the OPRM Upscale Settings Incorrectly Set]] |
| | number = ML17228A275
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| | issue date = 08/16/2017
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| | title = Regarding Entry Into Mode of Applicability with the OPRM Upscale Settings Incorrectly Set
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| | author name = Neve D
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| | author affiliation = Entergy Operations, Inc
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| | addressee name =
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| | addressee affiliation = NRC/Document Control Desk, NRC/NRO
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| | docket = 05000416
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| | license number = NPF-029
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| | contact person =
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| | case reference number = GNRO-2017/00030
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| | document report number = LER 16-009-01
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| | document type = Letter, Licensee Event Report (LER)
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| | page count = 5
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| }}
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| {{LER
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| | Title = Regarding Entry Into Mode of Applicability with the OPRM Upscale Settings Incorrectly Set
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| | Plant =
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| | Reporting criterion = 10 CFR 50.73(a)(2)(ii)(A), 10 CFR 50.73(a)(2)(viii)(A), 10 CFR 50.73(a)(2)(ii)(B), 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), 10 CFR 50.73(a)(2)(x), 10 CFR 50.73(a)(2)(v)(A), 10 CFR 50.73(a)(2)(v)(B), 10 CFR 50.73(a)(2)(v), 10 CFR 50.73(a)(2)(i)(A), 10 CFR 50.73(a)(2)(i)(B), 10 CFR 50.73(a)(2)(vii), 10 CFR 50.73(a)(2)(i)
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| | Power level =
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| | Mode =
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| | Docket = 05000416
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| | LER year = 1916
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| | LER number = 9
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| | LER revision = 1
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| | Event date =
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| | Report date =
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| | ENS =
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| | abstract =
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| }}
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| =text=
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| {{#Wiki_filter:~
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| =.c?SEntergy GNRO-2017/00030 August 16, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Entergy Operations, Inc.
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| P. O. Box 756 Port Gibson, MS 39150 Douglas Neve Manager, Regulatory Assurance Grand Gulf Nuclear Station Tel. (601) 437-2103
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| ==SUBJECT:==
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| Dear Sir or Madam:
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| Supplemental Licensee Event Report LER 2016-009-01, 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 Supplemental Licensee Event Report LER 2016-009-01, Entry into Mode of Applicability with the Oscillation Power Range Monitor (OPRM) Upscale Settings incorrectly set.
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| This letter contains no new commitments. If you have any questions or require additional information, please contact Douglas Neve at 601-437-2103.
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| Sincerely,
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| ~~
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| Manager Regulatory Assurance Grand Gulf Nuclear Station DAN/ram
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| ==Attachment:==
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| Licensee Event Report (LER) 2016-009-01 cc: see next page
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| GNRO-2017/00030 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: Mr. Kriss Kennedy, NRR/DORL (w/2)
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| Mail Stop OWFN 8 B1 Washington, DC 20555-0001
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| , the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
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| NRC FORM 366 (04-2017)
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| U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
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| (See Page 2 for required number of digits/characters for each block)
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| (See NUREG-1022, R3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collectionslnuregs/staff/sr1 022/r3/)
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| APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2020
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| : 1. FACILITY NAME Grand Gulf Nuclear Station, Unit 1
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| : 2. DOCKET NUMBER 05000416 1
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| : 3. PAGE 1 OF 3
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| : 4. TITLE Entry into Mode of Applicability with the Oscillation Power Range Monitor Upscale Settings Incorrectly Set
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| : 5. EVENT DATE
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| : 6. LER NUMBER
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| : 7. REPORT DATE
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| : 8. OTHER FACILITIES INVOLVED I
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| SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER.
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| NO.
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| MONTH DAY YEAR N/A 05000 N/A 03 27 2016 2016 - 009 - 01 8
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| 16 2017 FACILITY NAME N/A DOCKET NUMBER 05000 N/A 11.THISREPORT ISSUBMITTED PURSUANT TOTHEREQUIREMENTS OF10CFR§: (Check all that apply)
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| : 9. OPERATING MODE o 20.2201(b)
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| D20.2203(a)(3)(i)
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| D50.73(a)(2)(ii)(A)
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| D50.73(a)(2)(viii)(A)
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| MODE 1 o 20.2201(d)
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| D20.2203(a)(3)(ii)
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| D50.73(a)(2)(ii)(B)
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| D50.73(a)(2)(viii)(B) o 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A) o 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A)
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| D50.73(a)(2)(iv)(A)
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| D50.73(a)(2)(x) o 20.2203(a)(2)(ii)
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| D50.36(c)(1)(ii)(A)
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| D50.73(a)(2)(v)(A)
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| D73.71(a)(4)
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| : 10. POWER LEVEL o 20.2203(a)(2)(iii)
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| D50.36(c)(2)
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| D50.73(a)(2)(v)(B)
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| D73.71(a)(5) 100%
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| o 20.2203(a)(2)(iv)
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| D50.46(a)(3)(ii)
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| D50.73(a)(2)(v)(C)
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| D73.77(a)(1) o 20.2203(a)(2)(v)
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| D50.73(a)(2)(i)(A)
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| D50.73(a)(2)(v)(D)
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| D73.77(a)(2)(i) o 20.2203(a)(2)(vi)
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| ~ 50.73(a)(2)(i)(B)
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| D50.73(a)(2)(vii)
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| D73.77(a)(2)(ii) o 50.73(a)(2)(i)(C) 0 OTHER Specify in Abstract below or in =
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| : 2. DOCKET 05000416 YEAR I
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| : 3. LER NUMBER SEQUENTIAL NUMBER 2016 - 009 - 01 I
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| REV.
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| NO.
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| On March 27,2016, Entergy, while returning the GGNS Unit 1 to power operations at the conclusion of Refueling Outage 20, 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.
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| 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.
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| 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-0077A1B/C/D, Average Power Range Monitor Calibration. Based on GE analysis GGNS-NE-16-00007 Revision 001 performed for this issue, the deviation in TMIN and TMAX values did not affect the system's ability to safely perform its function. A new TMIN value of 1.05 seconds has been recommended.
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| REPORTABIL1TY 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.
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| An analysis was performed for this issue, the deviation in time minimum (TMIN) and time maximum (TMAX) values did not affect the system's ability to safely perform its function. Therefore, Entergy is retracting the reporting of this LER against 10CFR50.73(a)(2)(v)(A). Based on this re-analysis and a review of the performance indicator reporting criterial this condition does not count against the performance indicator MS05, Safety System Functional Failure. This performance indicator will be supplemented at the end of the second quarter 2017 to remove the reporting of this event.
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| ==CAUSE==
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| Direct Cause:
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| 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.
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| Apparent Cause:
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| Cause 1:
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| Entergy failed to maintain an adequate line of sight for this modification. Due to the time required to complete the modification a number of different individuals were assigned as owner of the modification, resulting a loss of important information between owners.
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| Cause2:
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| The personnel involved did not communicate efficiently to allow adequate traceability, document important information accordingly, or follow up and assure that changes were completed correctly.
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| Page 20f3
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| , the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
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| NRC FORM (6-2016) 366A U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)
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| CONTINUATION SHEET (See NUREG-1022, R.3 for instructionand guidance for completing this form http://www.nrc.gov/reading-rm/doc-collectionslnuregs/staff/sr1 0221r3D APPROVED BY OMB: NO. 3150-0104 EXPIRES: 3/31/2020
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| : 1. FACILITY NAME Grand Gulf Nuclear Station, Unit 1 NARRATIVE
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| : 2. DOCKET 05000416 YEAR I
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| : 3. LER NUMBER SEQUENTIAL NUMBER 2016 - 009 - 01 I
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| REV.
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| NO.
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| ==CORRECTIVE ACTIONS==
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| Completed:
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| Updating the procedure and correctly setting and fully testing the OPRM upscale settings.
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| Perform a brief with personnel qualified to perform a Design Change on the importance of understanding the full scope of a Mod and what a lack of rigor will result in. Also address the importance of effective communication and documentation.
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| Perform a brief with applicable personnel to address the importance of effective communication and documentation for obtaining cross-discipline inputs, reviews and comments.
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| Perform a follow up action 6 months later to review 6 modifications done after the briefing to ensure the issue was corrected and all applicable personnel fully understood the importance of obtaining reviews and comments.
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| Scheduled Perform a follow up action 6 months later to review 6 modifications done after the briefing to ensure the issue was corrected and all applicable personnel fully understood the importance of obtaining reviews and comments.
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| ==SAFETY SIGNIFICANCE==
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| There were no actual nuclear safety consequences or radiological consequences as a result of this calibration error. No Technical Specification Safety Limits were violated.
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| 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.
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| }}
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| {{LER-Nav}}
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