05000440/LER-2019-004, Loss of Feedwater Heating Results in Loss of Safety Function
| ML19277G666 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 10/04/2019 |
| From: | Payne F FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-19-202 LER 2019-004-00 | |
| Download: ML19277G666 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(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) 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 4402019004R00 - NRC Website | |
text
FENOC FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant P.O. Box 97 10 Center Road
- Perry, Ohio 44081 Frank Payne 440-280-5382 Vice President October 4, 2019 L-19-202 10 CFR 50.73(a)(2)(v)(A) 10CFR50.73(a)(2)(v)(D)
ATTN:
Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 Licensee Event Report Submittal Enclosed is Licensee Event Report (LER) 2019-004, "Loss of Feedwater Heating Results in Loss of Safety Function".
There are no regulatory commitments contained in this submittal.
If there are any questions or if additional information is required, please contact Mr. Glendon Burnham, Manager - Regulatory Compliance, at (440) 280-7538.
Frank R. Payne
Enclosure:
LER 2019-004 cc:
NRC Project Manager NRC Resident Inspector NRC Region III Regional Administrator
Enclosure L-19-202 LER 2019-004
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.qov/readinq-rm/doc-collections/nureqs/staff/sr1022/r3/
APPROVED BY OMB:
NO. 3150-0104 EXPIRES:
3/31/2020
, the NRC may not conduct or sponsor, and a
person is not required to respond to, the information collection.
- 1. Facility Name Perry Nuclear Power Plant
- 2. Docket Number 05000-440
- 3. Page 1
OF
- 4. Title:
Loss of Feedwater Heating Results in Loss of Safety Function
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved Month Day Year Year Sequential Number Rev No.
Month Day Year Facility Name Docket Number 05000 08 06 2019 2019 004 00 10 04 2019 Facility Name Docket Number 05000
- 9. Operating Mode
- 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)(3)(i) 20.2203(a)(3)(ii)
20.2203(a)(4)
D 50.36(c)(1)(i)(A)
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)(viii)(A)
50.73(a)(2)(viii)(B)
Q 50.73(a)(2)(ix)(A)
50.73(a)(2)(x)
- 10. Power Level
20.2203(a)(2)(ii) 50.36(c)(1 )(ii)(A) 50.73(a)(2)(v)(A)
73.71 (a)(4)
20.2203(a)(2)(iii) 50.36(c)(2)
50.73(a)(2)(v)(B)
73.71 (a)(5)
20.2203(a)(2)(iv)
50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
73.77(a)(1) 65 O
20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(D)
73.77(a)(2)(i)
20.2203(a)(2)(vi)
50.73(a)(2)(i)(B)
50.73(a)(2)(vii)
73.77(a)(2)(ii) 50.73(a)(2)(i)(C)
Other (Specify in Abstract below or in 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation; and TS 3.3.2.1, Control Rod Block Instrumentation for Rod Withdrawal Limiter (RWL).
According to procedure ONI-N36, Loss of Feedwater Heating, Revision 18, compliance with one of the following four actions is specified for unplanned reductions in feedwater temperature:
Restore the feedwater temperature within the TS action time(s)
Disable the bypass by removing the four trip units (C71-N652A, B, C, D) for RPS and EOC-RPT.
Implement setpoint changes for the trip units within the TS action time(s)
Reduce power to </= 38 percent within the TS Action Time(s)
At 1422 hours0.0165 days <br />0.395 hours <br />0.00235 weeks <br />5.41071e-4 months <br />, the four trip units were removed to disable the bypass function and obtain compliance with the TS action time to restore Operability.
At 1631 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.205955e-4 months <br /> feedwater heaters 5A and 6A were restored to service, and at 1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br /> the trip units were reinstalled to re-enable the bypass function.
CAUSE OF EVENT
The Direct Cause was determined to be the continued rise of water level in the heater, after the emergency drain valve reached 100% demand, actuating the high-high isolation level switch.
The apparent cause is still under investigation, as the cause evaluation is not complete.
EVENT ANALYSIS
A Probabilistic Risk Assessment (PRA) evaluation was performed for the August 6, 2019 loss of feedwater heating. A conservative analysis of this event results in delta Core Damage Frequency (CDF) and delta Large Early Release Frequency (LERF) values that are well below the acceptable thresholds discussed in Regulatory Guide 1.174 The increase in risk for this event is therefore considered very small in accordance with the Regulatory Guidance.
This event is being reported in accordance with 10 CFR 50.73(a)(2)(v)(A) and 10 CFR 50.73(a)(2)(v)(D) as an event or condition that could have prevented the fulfillment of a safety function.
CORRECTIVE ACTIONS
Corrective action included restoration of the feedwater heaters to back in-service.
Further corrective actions will be developed based upon the apparent cause, once the investigation is completed.
Previous Similar Events
A review of LERs and the corrective action database for the past three years identified no similar events.(04-2018)