05000219/LER-2017-004-01, 1 for Oyster Creek Nuclear Generating Station Regarding Reactor Protection System Channel Disabled During Test Box Use
| ML18046A076 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/16/2018 |
| From: | Gillin M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-17-082 LER 2017-004-001 | |
| Download: ML18046A076 (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)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 2192017004R01 - NRC Website | |
text
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~, Exelon Generation Oyster Creek 741 Route 9 South Forked River, NJ 08731 RA-17-082 February 16, 2018 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 (LER) 2017-004-01, "Reactor Protection System Channel Disabled during Test Box Use."
Enclosed is LER 2017-004-01 reporting the failure to implement the required action statement as described by Technical Specifications when performing the Turbine Trip and Generator Load Rejection surveillance testing. The LER has been revised to add supplemental information as required by Revision 00 of the document.
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, LER 2017-004-01 cc:
Administrator, NRC Region I NRC Senior Resident Inspector - Oyster Creek Nuclear Generating Station NRC Project Manager - Oyster Creek Nuclear Generating Station
NRCFORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: 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.
LICENSEE EVENT REPORT (LER)
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections
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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 0MB control http://www.nrc.Qov/readin!l-rm/doc-collections/nureQs/staff/sr1022/r3/)
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- 3. PAGE Oyster Creek Nuclear Generating Station 05000219 1 OF 3
- 4. TITLE Reactor Protection System Channel Disabled During Test Box Use
- 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 05000 FACILITY NAME DOCKET NUMBER 08 31 2017 2017 - 004
- - 01 02 16 2018 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 20.2203(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A)
N D 20.2201 (dl D 20.2203(a)(3l(iil D 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
D 20.2203(a)c1)
D 20.2203(al(4l D 50.13(a)(2)(iiil D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2l(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)(iil D 50.36(c)(1 )(ii)(A)
D 50. 73(a)(2)(v)(A)
D 13.11(a)(4l D 20.2203(a)(2)(iiil D 5o.3a(c)(2)
D 50. 73(a)(2)(v)(B)
D 13.11(a)(5l D 20.2203(a)(2)(iv)
D sOAa(a)(3){ii)
D 50.73{a)(2){v)(C)
D 13.77{a){1) 100 D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
D 50.73(a)(2)(v)(D)
D 13.11(a)(2)(i)
D 20.2203(a)(2)(vi)
[8J 50. 73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 13.11(a)(2)(ii)
~~};1t1L:/1if D 50.73(a)(2)(i)(C)
D OTHER Specify in Abstract below or in
Assessment of Safety Consequences
SEQUENTIAL NUMBER 004 REV NO.
01 The RPS has two independent trip systems with two logic channels in each trip system. The use of the RPS test box only impacts one channel in the RPS division being tested. The ability to receive a full scram due to a turbine stop valve closure when the RPS test box was installed for testing was not inhibited since the other channel in the RPS division being tested was unaffected by the installation of the RPS test box.
Corrective Actions
- 1.
All operating procedures using the test box, including the Turbine Stop Valve Anticipatory Scram and Turbine Load Rejection Scram surveillance tests, will be revised to reflect the TS Section 3.1.1. note (nn) requirement prior to next use. The procedures direct sufficient channels remain operable and a log entry made verifying the total amount of time the channel has been bypassed during test box installation is less than,the time limit specified in the TS.
- 2. All station surveillances which implemented test boxes for Station Qualified Reviewer errors were reviewed as part of the extent of condition with no other deficiencies noted.
Previous Occurrences
There have been no similar, previous events resulting from the installation of a test box during surveillance testing at Oyster Creek.
Component Data Component N/A IEEE 805 System ID N/A IEEE 803A Component N/A Page _3_ of _3_