05000458/LER-2016-007, Regarding Operations Prohibited by Technical Specifications Due to Failure to Implement Required Actions within Completion Time
| ML16222A349 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 07/25/2016 |
| From: | Chase M Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RBG-47694 LER 16-007-00 | |
| Download: ML16222A349 (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)(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)(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) |
| 4582016007R00 - NRC Website | |
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RBG-47694 July 25, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
RBF1-16-0084 Licensee Event Reporf 50-458 I 2016-007-00 River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47
Dear Sir or Madam:
Entergy Operations, Inc.
River Bend Station 5485 U.S. Highway 61 N St. Francisville, LA 70775 Tel 225-381-4157 Marvin L. Chase Director - Regulatory & Performance Improvement In accordance with 10 CFR 50.73, enclosed is the subject Licensee Event Report. This document contains no commitments. If you have any questions, please contact Ms. Kristi Huffstatler at 225-378-3305.
Enclosure cc:
U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Blvd.
Arlington, TX 76011-4511 NRG Sr. Resident Inspector P. 0. Box 1050 St. Francisville, LA 70775 INPO (via ICES reporting)
Licensee Event Report 50-458 I 2016-007-00 July25, 2016 RBG-47694 Page 2 of 2 Central Records Clerk Public Utility Commission of Texas 1701 N. Congress Ave.
Austin, TX 78711-3326 Department of Environmental Quality Office of Environmental Compliance Radiological Emergency Planning and Response Section Ji Young Wiley P.O. Box 4312 Baton Rouge, LA 70821-4312
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.
l LICENSEE EVENT REPORT (LER)
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail
,._....,... *"fl" (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 http://www.nrc.gQv/reaging-rm/dQc-collec!iQns/nuregs/staff/sr1022/r31) number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE River Bend Station - Unit 1 05000 458 1 OF 3
- 4. TITLE Operations Prohibited by Technical Specifications Due to Failure to Implement Required Actions Within Completion Time
- 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 05 25 2016 2016 -
007 - 00 07 25 2016 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) 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 so.73(a)(2)(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(i) 0 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) 0 50.73(a)(2)(v)(A)
D 73.71(a)(4)
D 20.2203(a)(2)(iii) o so.3a(c)(2) 0 50.73(a)(2)(v)(B)
D 73.71(a)(5)
D 20.2203(a)(2)(iv)
D so.4a(a)(3)(ii) 0 50.73(a)(2)(v)(C)
D 73.77(a)(1) 100 D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 20.2203(a)(2)(vi)
[{] 50.73(a)(2)(i)(B) 0 50.73(a)(2)(vii)
D 73.77(a)(2)(ii) l>':,f.'.<f;
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D 50.73(a)(2)(i)(C)
D OTHER Specify in Abstract below or in PREVIOUS OCCURRENCE EVALUATION In the last three years, River Bend Station has reported the following incidents of operations prohibited by Technical Specifications:
- LER 050-458 I 2016-03-00 (report date 3/17/16)- This event involved a postulated malfunction in a reactor control rod drive mechanism, not a human performance deficiency. The investigation of this event will be completed during the next refueling outage.
- LER 050-458 I 2015-06-00 (report date 9/14/2015) - This event involved the use of superseded vendor manual data in the initial troubleshooting of an abnormal system response during surveillance testing. Later analysis confirmed that the affected subcomponent should have been declared inoperable at the time of discovery.
- LER 050-458 I 2015-03-00 (report date 7/9/2015) - This event involved the mis-positioning of a manual valve in the Division 2 containment penetration leakage control system. The investigation found that operators failed to adequately apply configuration control requirements regarding that valve.
- LER 050-458 I 2015-01-00 (report date 4/16/2015) - This event involved a deficient surveillance test procedure.
- LER 050-458 I 2014-03~00 (report date 8/11/2014) - This event involved the concurrent inop.erability of redundant channels of an RPS trip function due to a common cause malfunction in channels containing a certain type of relay.
While the second and third items above were related to human performance deficiencies, neither of them were attributed to a root cause involving errors in the application of Technical Specifications requirements.
SAFETY SIGNIFICANCE
Approximately four days following the discovery of the air leaks and the governor drive coupling configuration, DG system engineers documented operability evaluations which concluded that none of these conditions posed any potential challenge to the ability of the DG to fulfill its safety function. It was confirmed that no similar conditions were present on the Division 2 DG. The air leaks were repaired and the governor drive coupling assembly was corrected prior to restoration of the Division 1 DG to an operable status. This event had no significance with respect to the health and safety of the public.
(NOTE: Energy Industry Identification System component function identifier and system name of each component or system referred to in the LER are annotated as (**XX**) and [XX], respectively.) Page 3
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