05000440/LER-1917-006, Regarding Loss of Safety Function Due to the Inoperability of Both Trains of Motor Control Center Ventilation
| ML17335A065 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 12/01/2017 |
| From: | Hamilton D FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-17-0318 LER 17-006-00 | |
| Download: ML17335A065 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(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)(A), Loss of Safety Function - Shutdown the Reactor 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) |
| 4401917006R00 - NRC Website | |
text
FENOC Perry Nuclear Power Plant P.O. Box97 10 Center Road FirstEnergy Nuclear Operating Company Peny' Ohio 44081 David B. Hamilton 440-280-5382 Vice President December 1, 2017 L-17-0318 10CFR50.73(a)(2)(v)(B) 10CFR50.73(a)(2)(v)(C) 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) 2017-006, "Loss of Safety Function due to the Inoperability of Both Trains of Motor Control Center Ventilation."
There are no regulatory commitments contained in this submittal.
If there are any questions or if additional information is required, please contact Mr. Nicola Conicella, Manager - Regulatory Compliance, at (440) 280-5415.
David B. Hamilton Vice President
Enclosure:
LER 2017-006 cc:
NRC Region III Administrator NRC Resident Inspector NRR Project Manager
Enclosure L-17-318 LER 2017-006
NRC FORM 366 (04-2017)
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/
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- 1. FACILITY NAME Perry Nuclear Power Plant
- 2. DOCKET NUMBER 05000-440
- 3. PAGE 1
OF 3
- 4. TITLE:
Loss of Safety Function due to the Inoperability of Both Trains of Motor Control Center Ventilation
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO.
MONTH DAY FACILITY NAME YEAR DOCKET NUMBER 05000 10 04 2017 2017 006 00 12 01 2017 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) 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) 50.73(a)(2)(ix)(A) 50.73(a)(2)(x)
- 10. POWER LEVEL 100 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) 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
EVENT ANALYSIS
A Probabilistic Risk Assessment (PRA) evaluation was performed. The analysis indicates that the event resulted in a very small change to overall plant risk with a change (delta) in core damage frequency (CDF) of 1.78E-09/yr, and a change (delta) in the large early release frequency (LERF) of 1.11E-09/yr.
The delta CDF and delta LERF values are well below the acceptable thresholds of 1.0E-06/yr and 1.0E-07/yr, respectively, as discussed in Regulatory Guide 1.174.
Therefore, the safety significance of this event is considered to be very small.
CORRECTIVE ACTIONS
Corrective actions in response to the event include: revising the maintenance procedure to use the Force Deflection Method for tensioning of the belts; replacing the M23 A supply fan drive belts and restoring M23/24 to operable; and performing an additional check of belt tension on the same train exhaust fan along with the opposite train supply and exhaust fans.
Additionally, the belts for the Auxiliary Building ventilation [VF] exhaust fans will be checked.
PREVIOUS SIMILAR EVENTS
A review of LERs and the Corrective Action database for the past three years identified no similar events.
COMMITMENTS
There are no regulatory commitments contained in this report. Actions described in this document represent intended or planned actions, are described for the NRC's information, and are not regulatory commitments.(06-2016)