05000440/LER-1917-003, Regarding Annulus Exhaust Gas Treatment System Loss of Safety Function
| ML17177A350 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/26/2017 |
| From: | Hamilton D FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-17-204 LER 17-003-00 | |
| Download: ML17177A350 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(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) |
| 4401917003R00 - NRC Website | |
text
FENOC FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant P.O. Box 97 10 Center Road Perry, Ohio 44081 David B. Hamilton Vice President 440-280-5382 June 26, 2017 L-17-204 10CFR50.73(a)(2)(v)
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) 2017-003, "Annulus Exhaust Gas Treatment System Loss of Safety Function".
If there are any questions or if additional information is required, please contact Mr. Nicola F.
Conicella, Manager - Regulatory Compliance, at 440-280-5415.
David B. Hamilton
Enclosure:
LER 2017-003 cc:
NRC Project Manager NRC Resident Inspector NRC Region III
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/
APPROVED BY OMB:
NO. 3150-0104 EXPIRES:
3/31/2020 Estimated burden per response to comply with this mandatory collection request:
80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the Information Services Branch (T-2 F43),
U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.
Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503.
If a means used to impose an information collection does not display a currently valid OMB control
- number, 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 3
- 4. TITLE:
Annulus Exhaust Gas Treatment System Loss of Safety Function
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR SEQUENTIAL NUMBER REV NO.
MONTH DAY FACILITY NAME YEAR DOCKET NUMBER 05000 04 27 2017 2017 003 00 06 26 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 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) 100 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C)
D73.77(a)(1)
D 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)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii)
D 50.73(a)(2)(i)(C)
[I] OTHER Specify in Abstract below or in
CAUSE OF EVENT
The cause for the AEGTS sub-system A recirculation damper failure was a failure to follow procedure by electrical, and instrument and controls technicians which resulted in the split coupling that connects the actuator to the damper not being properly tightened.
ANALYSIS OF EVENT
Since AEGTS is not a core damage mitigation system and does not mitigate large and early containment releases, the inoperability of the AEGTS is determined to be of small safety significance. This event is being reported in accordance with 10CFR50.73(a)(2)(v)(C) and 10CFR50.73(a)(2)(v)(D) as an event or condition that could have prevented the fulfilment of a safety function.
CORRECTIVE ACTIONS
The failure to follow procedure was addressed by the FENOC performance management process.
PREVIOUS SIMILAR EVENTS
A review of LERs and the corrective action database for the past three years identified that no previous similar events occurred involving AEGTS.
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)