05000219/LER-1917-002, Regarding Manual Scram Due to Degraded Main Condenser Vacuum
| ML17249A124 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/31/2017 |
| From: | Gillin M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-17-052 LER 17-002-00 | |
| Download: ML17249A124 (4) | |
| 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)(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)(i) |
| 2191917002R00 - NRC Website | |
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~- Exelon Generation Oyster Creek Route 9 South P.O. Box388 Forked River, NJ 08731 RA-17-052 August 31, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk or 0-881 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRC Docket No. 50-219 10 CFR 50.73
Subject:
Licensee Event Report (LEA) 2017-002-00, "Manual Scram due to Degraded Main Condenser Vacuum."
Enclosed is LER 2017-002-00 reporting the manual reactor scram due to degraded main condenser vacuum, which occurred on July 3, 2017.
This event did not affect the health and safety of the public or plant personnel. This event did not result in a safety system functional failure. There are no regulatory commitments made in this LER submittal.
Should you have any questions concerning this report, please contact Gary Flesher, Regulatory Assurance Manager, at (609) 971-4232.
Respectfully, Michael F. Gillin Plant Manager Oyster Creek Nuclear Generating Station Enclosure: NRC Form 366, LEA 2017-002-00 cc:
Administrator, NRC Region I NRC Senior Resident Inspector - Oyster Creek Nuclear Generating Station NRC Project Manager - Oyster Creek Nuclear Generating Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (06-2016)
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 />.
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Reported lessons learned are incorporated into the licensing process and fed back to industry.
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LICENSEE EVENT REPORT (LER)
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections f
i Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail (See Page 2 for required number of digits/characters for each block) to lnfocollects.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 (See NUREG-1022, R.3 for instruction and guidance for completing this form means used to impose an information collection does not display a currently valid OMB control httQ://www.nrc.gov/reading-rm/doc-collections/nureas/staff/sr1022/r3l) number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Oyster Creek Nuclear Generating Station 05000219 1 OF 3
- 4. TITLE Manual Reactor Scram due to Degrading Main Condenser Vacuum
- 5. EVENT DATE
- 6. LEA NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED YEAR I SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.
MONTH DAY YEAR N/A 05000 FACILITY NAME DOCKET NUMBER 07 03 2017 2017 - 002
- - 00 08 31 2017 N/A 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: {Check all that apply)
D 20.2201(b)
D 20.22os(a)(3)(i) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A)
N D 20.2201(d)
D 20.22os(a)(3)(ii) 0 50. 73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B)
D 20.22os(a><1>
D 20.22os(a)(4)
D 50.1s<a><2><m>
0 50.73(a)(2)(ix)(A)
D 20.22os(a)(2)(i) 0 50.36(c)(1)(i)(A)
IZ! 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x)
- 10. POWER LEVEL D 20.22os(a)(2)(ii) 0 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(v)(A)
D 1s.11ca)(4)
D 20.22osca>(2)(iii)
D 50.s6(c)(2>
0 50.73(a)(2)(v)(B)
D 1s.11ca><5>
D 20.2203(a)(2)(iv)
D so.4a(a)(3J(iiJ D 50.73(a)(2)(v)(C)
D n.n<aJ<1J 100 0 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(D)
D 1s.11(a)(2)(i) 0 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 50.73(a)(2)(vii)
D 1s.n<a>(2)(ii)
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0 50.73(a)(2)(i)(C)
D OTHER Specify in Abstract below or in
Corrective Actions
Exelon took the following corrective actions:
- 1.
Immediate procedure changes to alarm response and operating procedures were performed to provide clear direction for a trip of the AOG system.
- 2.
Industry Benchmarking was completed and the Operations department has implemented an integrated decision-making model.
- 3.
Reinforcement of key operations fundamentals and human performance boards with each operator.
Previous Occurrences
A previous event occurred on July 26, 2012 during startup from Forced Outage 1 F29. The delay pipe filled with water prior to or during plant startup resulting in a six-hour delay in establishing condenser vacuum. A procedure change was put in place to verify the delay pipe is draining correctly prior to every plant start up.
Component Data Component IEEE 805 System ID IEEE 803A Component N/A N/A N/A
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