05000400/LER-2019-003, Both Source Range Nuclear Instruments Inoperable
| ML19346D060 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/12/2019 |
| From: | Dills J Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-19-0438 LER 2019-003-00 | |
| Download: ML19346D060 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(i) 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)(iii) 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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x) |
| 4002019003R00 - NRC Website | |
text
(. DUKE ENERGY.,
John R. Dills Plant Manager Shearon Harris Nuclear Power Plant 5413 Shearon Harris Road New Hill, NC 27562-9300 984.229.2000 10 CFR 50.73 December 12, 2019 Serial: RA-19-0438 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63 Subject: Licensee Event Report 2019-003-00 Ladies and Gentlemen:
Duke Energy Progress, LLC, submits the enclosed Licensee Event Report 2019-003-00 in accordance with 10 CFR 50.73 for Shearon Harris Nuclear Power Plant, Unit 1 (HNP). This report describes a series of events resulting in periods in which both source range nuclear instruments were inoperable simultaneously. These instruments have since been restored. This event had no significance with respect to the health and safety of the public.
There are no regulatory commitments contained within this report.
Please refer any questions regarding this submittal to Chuck Yarley at (984) 229-2477.
Sincerely, Enclosure: Licensee Event Report 2019-003-00 cc:
J. Zeiler, NRC Senior Resident Inspector, HNP T. Hood, NRC Project Manager, HNP NRC Regional Administrator, Region II
John R. Dills Plant Manager Shearon Harris Nuclear Power Plant 5413 Shearon Harris Road New Hill, NC 27562-9300 984.229.2000 10 CFR 50.73 December 12, 2019 Serial: RA-19-0438 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63 Subject: Licensee Event Report 2019-003-00 Ladies and Gentlemen:
Duke Energy Progress, LLC, submits the enclosed Licensee Event Report 2019-003-00 in accordance with 10 CFR 50.73 for Shearon Harris Nuclear Power Plant, Unit 1 (HNP). This report describes a series of events resulting in periods in which both source range nuclear instruments were inoperable simultaneously. These instruments have since been restored. This event had no significance with respect to the health and safety of the public.
There are no regulatory commitments contained within this report.
Please refer any questions regarding this submittal to Chuck Yarley at (984) 229-2477.
Sincerely, John R. Dills Enclosure: Licensee Event Report 2019-003-00 cc:
J. Zeiler, NRC Senior Resident Inspector, HNP T. Hood, NRC Project Manager, HNP NRC Regional Administrator, Region II
NRC FORM 366 (04-2018)
U.S. NUCLEAR REGULATORY COMMISSION 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/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
NRC FORM 366 (04-2018) 05000
- 3. Page 1
OF
- 4. Title
- 5. Event Date Month Day Year
- 6. LER Number Year Sequential Number Rev No.
- 7. Report Date Month Day Year
- 8. Other Facilities Involved Facility Name Docket Number 05000 Facility Name Docket Number 05000
- 9. Operating Mode
- 10. Power Level
- 11. This Report is Submitted Pursuant to the Requirements of 10 CFR §: (Check all that apply) 20.2201(b) 20.2201(d) 20.2203(a)(1) 20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(2)(v) 20.2203(a)(2)(vi) 20.2203(a)(3)(i) 20.2203(a)(3)(ii) 20.2203(a)(4) 50.36(c)(1)(i)(A) 50.36(c)(1)(ii)(A) 50.36(c)(2) 50.46(a)(3)(ii) 50.73(a)(2)(i)(A) 50.73(a)(2)(i)(B) 50.73(a)(2)(i)(C) 50.73(a)(2)(ii)(A) 50.73(a)(2)(ii)(B) 50.73(a)(2)(iii) 50.73(a)(2)(iv)(A) 50.73(a)(2)(v)(A) 50.73(a)(2)(v)(B) 50.73(a)(2)(v)(C) 50.73(a)(2)(v)(D) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(ix)(A) 50.73(a)(2)(x) 73.71(a)(4) 73.71(a)(5) 73.77(a)(1) 73.77(a)(2)(i) 73.77(a)(2)(ii)
Other (Specify in Abstract below or in Page of 05000-
- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
E. Safety Analysis
The SR instruments provide an anticipatory trip to the RPS on high neutron flux to mitigate impact of inadvertent rod [ROD] withdrawal. However, during the duration of the event, the RPS breakers were open and in their tripped (safety) configuration, or the reactor head was off and rods were unlatched, preventing rod withdrawal. Further, HNP accident analysis does not take credit for the anticipatory trip signal generated by SR instrumentation.
The SR instruments provide an audible indication to the control room that can alert an operator to an inadvertent dilution event. However, administrative controls to isolate unborated water sources, as described per HNP TS Surveillance Requirement 4.9.1.2, were in place for the duration of the events described. Accident analysis specifically credits administrative controls for preventing an inadvertent dilution event from occurring.
The SR instruments provide visual indication to the control room of unexpected changes in core reactivity. However, visual indication is also provided by the Wide Range NFMS, which provides the same level of quality assurance, redundancy, and the necessary display range as the SR instruments. Both sets of instruments are credited per TS 3.9.2, Refueling Operations Instrumentation, and are both considered components within the same system. The Wide Range NFMS was operable and provided visual indication of core reactivity during the event.
The overall safety function performed by the SR detectors was preserved for the duration of the event. There was no significant impact to the health and safety of the public. Based on this evaluation, this condition will not be counted as a safety system functional failure against Performance Indicator MS05, Safety System Functional Failure.
F. Additional Information
There have been no Licensee Event Reports submitted in the past three years by HNP due to a similar event.
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Shearon Harris Nuclear Power Plant, Unit 1 400 2019 003 00