05000219/LER-2017-001, Regarding Automatic Scram Due to APRM High Flux During Turbine Value Testing
| ML17024A062 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/18/2017 |
| From: | Gillin M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-17-002 LER 17-001-00 | |
| Download: ML17024A062 (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)(ii)(B), Unanalyzed Condition 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)(v), Loss of Safety Function 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) 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
| 2192017001R00 - NRC Website | |
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7 ::~':f::7 Exelon Generation RA-17-002 January 18, 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 Oyster Creek Route 9 South P.O. Box388 Forked River, NJ 08731 10 CFR 50.73
Subject:
Licensee Event Report (LER) 2017-001-00, "Automatic SCRAM due to APRM High Flux during Turbine Valve Testing."
Enclosed is LER 2017-001-00, "Automatic SCRAM due to APRM High Flux during Turbine Valve Testing." 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 Mike McKenna, Regulatory Assurance Manager, at {609) 971-4389.
Respectfully, Michael Gillin Plant Manager Oyster Creek Nuclear Generating Station Enclosure: NRC Form 366, LER 2017-001-00 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
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... J Branch {T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail
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(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 currenijy valid OMB control httQ://www.nrc.gov/reading-rm/doc-collections/nureas/staff/sr1022/r3[J number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Oyster Creek, Unit 1 05000219 1 OF 3
- 4. TITLE
~SCRAM due ro APRM High Aux during Turbine Valve Testing
- 5. EVENT DATE
- 6. LER 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 NIA FACILITY NAME DOCKET NUMBER 11 20 16 2017 - 001
- - 00 01 18 17 N/A NIA
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
D 20.2201 (b)
D 20.2203(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A)
N D 20.2201 (d)
D 20.2203(a)(3)(iil 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 50.13(a)(2)<m>
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(il D 50.36(c)(1)(i)(A)
!ZI 50. 73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL D 20.2203(a)(2)(iil D 50.36(c)(1)(ii)(A)
D 50.73(a)(2)(v)(A)
D 13.11<al<4l D 20.2203(a)(2)(iiil D 5o.3a(c)(2)
D 50.73(a)(2)(v)(B)
D 13. 11 (a)(5) 0 20.2203{a)(2)(1v)
D so.4a(a)(3l(lll D 50.73(a)(2)(v)(C)
D 1a.77{a)(1) 92%
D 20.2203(a)(2)(v)
D 50. 73(a)(2)(i)(A)
D 50.73(a)(2)(v)(D)
D 13. n(a)(2)(il D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 13.11(a)(2)(iil
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D 50.73(a)(2)(i)(C)
D OTHER Specify in Abstract below or in SEQUENTIAL NUMBER 001 REV NO.
00 There were no safety consequences impacting the plant or public safety as a result of this event. All control rods fully inserted and plant response was as expected. This event is being reported pursuant to 10CFR50.73(a)(2)(iv)(A) due to an actuation of the Reactor Protection System (RPS).
Corrective Actions
The hydraulic feedback linkage for the number 2 and number 4 control valves were repaired prior to restart of the unit. The Turbine Master Trip Solenoid Valve test will no longer be performed online to prevent initiating an oscillation of the MHC system. A root cause investigation is currently in progress to determine if additional corrective actions are required.
Previous Occurrences
Oyster Creek Nuclear Generating Station experienced a similar event on December 14, 2013. During quarterly turbine valve testing with reactor power at 100% of rated thermal power, the plant experienced reactor pressure control abnormalities. The hydraulic feedback linkage for the number 2 and number 3 control valves failed, thereby requiring a scram. Operators initiated a manual reactor scram due to reactor pressure rising to 1042 psig which approached the automatic scram set point. That event was reported under LER 2013-004-00 in February 2014.
Component Data Component IEEE 805 System ID IEEE 803A Component Control Valve Hydraulic Enclosure TG xc Page _3_ of _3_