05000440/LER-2017-007, For Perry Nuclear Power Plant Regarding High Pressure Core Spray Inoperability Due to System Leak
| ML18045A057 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 02/13/2018 |
| From: | Hamilton D FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-18-019 LER 2017-007-00 | |
| Download: ML18045A057 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(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)(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) |
| 4402017007R00 - NRC Website | |
text
FENOC' FirstEnergy Nuclear Operating Company David B. Hamilton Vice President February 13, 2018 L-18-019 A TIN: 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 Perry Nuclear Power Plant PO. Box 97 10 Center Road Perry, Ohio 44081 440-280-5382 1 0CFR50. 73(a)(2)(v)(D)
Enclosed is Licensee Event Report (LER) 2017-007, "High Pressure Core Spray lnoperability due to System Leak." 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.
Sincerely, David 8. Hamilton Vice President
Enclosure:
LER 2017-007 cc:
NRC Region Ill Administrator NRC Resident Inspector NRR Project Manager
Enclosure L-18-019 LER 2017-007
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150--0104 EXPIRES: 3/31/2020 (04-2017)
, the httQ://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/
NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE I
Perrv Nuclear Power Plant 05000-440 1 OF 3
- 4. TITLE:
High Pressure Core Spray lnoperability due to System Leak
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED i
SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 12 22 2017 2017 -
007 -
00 02 13 2018 05000
- 9. OPERA TING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
D 20.2201(b>
D 20.2203(a)(3)(i>
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A) 1 D 20.2201 (d>
D 20.2203(a)(3)(ii)
D 50. 73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
D 20.2203(a)(1)
D 20.2203(a)(4>
D 50.73(a)(2)(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(i)
D 50.36(c)(1)(i)(A)
D 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL D 20.2203(a)(2)(ii)
D 50.36(c)(1)(ii)(A)
D 50.73(a)(2)(v)(A)
D 13.11(a)(4>
D 20.2203(a)(2)(iii)
D 50.36(c)(2>
D 50.73(a)(2)(v)(B)
D 13.11(a)(5>
D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 73.77(aH1>
100 D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
~
- 50. 73(a)(2)(v)(D)
D 73. 77(a)(2)(i>
D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73. 77(a)(2)(ii)
D 50.73(a)(2)(iHC>
D OTHER Specify in Abstract below or in
CORRECTIVE ACTIONS
YEAR 2017 SEQUENTIAL NUMBER 007 The permanent repair will be implemented by the end of the next refueling outage. Ultrasonic testing (UT) thickness readings will be performed on the HPCS minimum flow line first elbow downstream of restricting orifice at an initial periodicity of four years. For extent of condition, UT readings will be performed on similar elbow configurations for the minimum flow lines in the Reactor Core Isolation Cooling (RCIC) [BN],
Low Pressure Core Spray (LPCS) [BM] systems, and an additional elbow in the HPCS minimum flow line.
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.
REV NO.
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