05000266/LER-2019-002, Operation Not Maintained within Pressure and Temperature Limit Report (PTLR) as Required by Technical Specification 3.4.3
| ML19161A083 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/08/2019 |
| From: | Craven R Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2019-0017 LER 2019-002-00 | |
| Download: ML19161A083 (3) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2662019002R00 - NRC Website | |
text
June 08, 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Licensee Event Report 266/2019-002-00 NRC 2019-0017 10 CFR 50.73 Enclosed is Licensee Event Report (LER) 266/2019-002-00 for Point Beach Nuclear Plant, Pressure Temperature Limits Report.
This letter contains no new regulatory commitments.
If you have any questions please contact Mr. Eric Schultz, Licensing Manager, at (920) 755-7854.
Sincerely, NextEra Energy Point Beach, LLC Robert Craven Site Director Enclosure cc:
Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241 Description of the Event:
SEQUENTIAL NUMBER 002 REV NO.
00 On April 9, 2019, following the Unit 1 RCS [AB] cooldown for refueling (U1 R38), PBNP identified where cold leg temperature was not maintained within the limits specified in the PTLR. An extent of condition review identified time intervals where both units had operated outside of the PTLR temperature limit. During these intervals, the technical specification required action completion times were not satisfied.
Technical Specification 3.4.3, RCS [AB] Pressure and Temperature Limits Limiting Condition for Operation (LCO),
requires that RCS [AB] pressure, temperature, and heat-up and cooldown rates be maintained within the limits specified in the PTLR. The LCO is applicable at all times and requires that if a limit is exceeded, initiate action to restore parameters and determine RCS [AB] is acceptable for continued operation prior to entering Mode 4. The RCS [AB]
heat-up and cooldown rates have been maintained within the limits of the PTLR. However, the RCS [AB] was not maintained greater than the minimum temperature specified in the PTLR and the required action to determine the RCS [AB] acceptable for continued operation was not completed prior to entering Mode 4.
This event is being reported pursuant to 10 CFR 50.73(a)(2)(i)(B), Operation or Condition Prohibited by Technical Specifications.
Cause of the Event
PTLR requirements were not properly integrated into plant processes.
Analysis of the Event
The PTLR is contained in Section 2.2 of the PBNP Technical Requirements Manual (TRM). PBNP utilizes Operating Instruction, RCS [AB] Heat-up/Cooldown Plotting for plotting and controlling plant heat-up and cooldown trends to satisfy the PTLR documented in the TRM. The operating instruction does not contain the explicit numerical limits specified in the PTLR for the heat-up rate, cooldown rate, or minimum temperature for pressurization or bolt up.
Corrective Actions
The Unit 1 RCS [AB] condition was evaluated for continued operation with acceptable results prior to entry in Mode 4.
Additionally, the prior occurrences of exceeding the minimum temperature specified in the PTLR were also evaluated and determined to be acceptable utilizing the guidance of ASME Code Appendix E. These evaluations were made available to NRC staff. Activities to properly integrate PTLR requirements into plant processes are being controlled in the corrective action program.
Safety Significance
During the events and subsequent operations, there was no loss of any safety systems, structures or components, as the excursions beyond the PTLR limits did not result in degradation of the reactor pressure vessel structural integrity.
There were no challenges to any design or safety limit. All plant systems functioned as required during the events.
The reactivity effects during these events had no impact on the safety of the core. Since the evaluation results determined the RCS [AB] to be acceptable, the events were determined to be of very low safety significance and there was no impact on the health and safety of the public as a result of these events.
Similar Events
There have not been similar events reported with the same cause of not maintaining operations within the PTLR in the past three years.
Component Failure Data
None NRC FORM 3668 (02-2018)
NRC FORM 366 (04-2018)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 LICENSEE EVENT REPORT (LER)
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- 13. Page Point Beach Nuclear Plant (PBNP) Unit 1 05000266 I
1 OF 2
- 4. Title Operation not maintained within Pressure and Temperature Limit Report (PTLR) as required by Technical Specification 3.4.3.
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved Facility Name Docket Number Month Day Year Year Sequential Number Rev No.
Month Day Year PBNP Unit 2 05000301 06 08 2019 Facility Name Docket Number NA OSOOONA 002 2019 2019 04 09 00
- 9. Operating Mode NA NA NA
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On April 9, 2019, following the Unit 1 Reactor Coolant System (RCS) cooldown for refueling (U1 R38), PBNP identified where cold leg temperature was not maintained within the limits specified in the PTLR. An extent of condition review identified time intervals where both units had operated outside of the PTLR temperature limit. During these intervals, the technical specification required action completion times were not satisfied.
Technical Specification 3.4.3, RCS Pressure and Temperature Limits Limiting Condition for Operation (LCO), requires that RCS pressure, temperature, and heat-up and cooldown rates be maintained within the limits specified in the PTLR. The LCO is applicable at all times and requires that if a limit is exceeded, initiate action to restore parameters and determine RCS is acceptable for continued operation prior to entering Mode 4. The RCS heat-up and cooldown rates have been maintained within the limits specified in the PTLR. However, the RCS was not maintained greater than the minimum temperature specified in the PTLR and the required action to determine the RCS acceptable for continued operation was not completed prior to entering Mode 4.
This event is being reported pursuant to 10 CFR 50.73(a)(2)(i)(B), Operation or Condition Prohibited by Technical Specifications.
NRC FORM 366 (04-2018)