05000301/LER-2018-001, Operation or Condition Prohibited by Technical Specifications, Less than Minimum Refueling Cavity Water Level
| ML18347B033 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/13/2018 |
| From: | Craven R Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2018-0054 LER 2018-001-00 | |
| Download: ML18347B033 (3) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 3012018001R00 - NRC Website | |
text
December 13, 2018 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Unit 2 Docket 50-301 Renewed License No. DPR-27 Licensee Event Report 301/2018-001-00 NRC 2018-0054 10 CFR 50.73 Enclosed is Licensee Event Report (LER) 301/2018-001-00 for Point Beach Nuclear Plant, Unit 2. NextEra Energy Point Beach, LLC is providing this LER related to Less Than Minimum Refueling Cavity Water Level.
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 PSCW NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241
NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
, the NRC may not conduct or sponsor, and a person is not required to respond to the information collection.
- 13. Page Point Beach Nuclear Plant Unit 2 05000301 1 OF2
- 4. Title Operation or Condition Prohibited by Technical Specifications, Less than Minimum Refueling Cavity Water Level
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved Sequential Rev Facility Name Docket Number Month Day Year Year Month Day Year NA Number No.
OSOOONA 10 15 2018 2018 001 00 12 13 2018 Facility Name Docket Number NA OSOOONA
- 9. Operating Mode
) IS] No NA NA NA Abstract (Limit to 1400 spaces, i.e., approximately 14 single-spaced typewritten lines)
Jon October 15, 2018 at 1405, with Unit 2 in MODE 6 for refueling activities, it was identified that the refueling cavity level did not satisfy Technical Specification (TS) Limiting Condition for Operation (LCO)s. Technical Specification Action Condition (TSAC) 3.9.6.A, for refueling cavity water level not within limit, and TSAC 3.9.5.A, for less than the required number of RHR loops OPERABLE were entered.
During the evaluation of the issue there was evidence that the condition existed longer than the time allowed by TS.
Therefore, this event is being reported pursuant to 10 CFR 50.36(c)(2) and 10 CFR 50.73(a)(2)(i)(B).
NRC FORM 366 (04-2018)
Description of the Event:
SEQUENTIAL NUMBER 001 REV NO.
00 On October 15, 2018 at 1402, with Unit 2 in MODE 6 performing refueling activities, a Control Operator identified that the board indication for 2L T-433, Pressurizer Level, was 1% lower than on the prior Unit 2 shift log. The Control Operator notified the Core Load Supervisor to check the refueling cavity and spent fuel pool levels. At 1405 The Unit 2 refueling cavity level and spent fuel pool levels were noted to be 63 feet 4 inches. As this level is below the required 63'8", the site entered Technical Specification Action Condition (TSAC} 3.9.6.A for refueling cwvity watet~vel not within limits, and TSAC 3.9.5.A for less than the required number of residual heat removal (RHR) loops OPERABLt:.
Operations immediately suspended fuel movement and initiated action to establish water level in the refueling cavity to satisfy the LCO.
When evaluating the event it was identified at 1432 that there was inter-system leakage from the refueling cavity going to the Unit 2 refueling water storage tank (RWST). The inter-system leaked was determined to be from valve 2SI-857 A, Residual Heat Removal Heat Exchanger Outlet to Safety Injection Pump Suction. The valve was indicating closed, but was found off its seat by approximately% inch.
Further review determined that the cavity level began lowering at approximately 0315 on October 15, 2018. It is determined that there was firm evidence the condition existed prior to the time of discovery for a time longer than permitted by the TS. Therefore, this event is being reported pursuant to 10 CFR 50.36(c)(2) and 10 CFR 50. 73(a)(2)(i)(B).
Cause of the Event
Valve 2SI-857 A indicated closed when it was off its seat by % inch.
Analysis of the Event
When the low level in the refueling cavity was identified, Operations immediately suspended fuel motion and began troubleshooting. The site concluded that the 2SI-857 A valve was approximately % inch off its seat with a closed indication in the control room. The valve was closed, and verified. The Unit 2 RWST level was noted to be stable.
Operations aligned the "A" holdup tank to the refueling cavity and began filling the refueling cavity.
Corrective Actions
An adverse condition monitoring plan was developed. Operations is reviewing the event to determine if procedural enhancements and or training are needed.
Safety Significance
The event was determined to be very low safety significance. The minimal deviation from the LCO required water level did not challenge the safety analysis described in the FSAR. It is therefore concluded that the event did not result in a safety significant risk greater than that associated with normal refueling activities. There was no impact on the health and safety of the public as a result of this event.
Similar Events
There have not been similar events in the past three years.
Component Failure Data
None NRC FORM 3668 (02-2018)