05000261/LER-2012-001, Regarding Technical Specification Required Plant Shutdown Due to Missed Surveillance and Operation Prohibited by Technical Specifications
| ML12081A280 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/14/2012 |
| From: | Cosgrove T Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RNP-RA/12-0012 LER 12-001-00 | |
| Download: ML12081A280 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(8) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 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)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
| 2612012001R00 - NRC Website | |
text
10 CFR 50.73
&jjý Progress Energy Serial: RNP-RA/12-0012 MAR 1 4 2012 Attn: Document Control Desk United States Nuclear Regulatory Commission Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 LICENSEE EVENT REPORT NO. 2012-001-00 TECHNICAL SPECIFICATION REQUIRED PLANT SHUTDOWN DUE TO MISSED SURVEILLANCE AND OPERATION PROHIBITED BY TECHNICAL SPECIFICATIONS Ladies and Gentlemen:
The attached Licensee Event Report is submitted in accordance with the requirements of 10 CFR 50.73. Should you have any questions regarding this matter, please contact William R. Hightower at (843) 857-1329.
This document contains no new Regulatory Commitments.
7 1in y,
oma SS. Cos Plant General Manager H. B. Robinson Steam Electric Plant, Unit No. 2 PSF Attachment c:
Mr. Victor McCree, NRC, Region I1 A. Billoch, NRC, NRR NRC Resident Inspector Progress Energy Carolinas, Inc.
Robinson Nuclear Plantk 3
D 3581 West Entrance Road Hartsville, SC 29550
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES 10/31/2013 (10-2010)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE H. B. Robinson Steam Electric Plant, Unit No. 2 05000261 1 OF 3
- 4. TITLE Technical Specification Required Plant Shutdown Due to Missed Surveillance and Operation Prohibited bV Technical Specifications
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR NUMBER NO 05000 FACILITY NAME DOCKET NUMBER 01 17 2012 2012 001 00 03 19 2012 1
05000
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
- 9. OPERATING MODE 20.2201(b) 20.2203(a)(3)(i)
[E 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 1 Fl 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(8) 50.73(a)(2)(viii)(B)
M--_
20.2203(a)(2)(i)
E]
50.36(c)(1)(i)(A)
[3 50.73(a)(2)(iii) f-50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A) f-50.73(a)(2)(x) f-20.2203(a)(2)(iii)
El 50.36(c)(2)
[E 50.73(a)(2)(v)(A) f-73.71(a)(4) 85.5%
20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B) f-73.71(a)(5) fl 20.2203(a)(2)(v)
ED 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C) f-OTHER Specid in Abstract below E
20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D) or i The condition described in this Licensee Event Report is reportable in accordance with 10 CFR 50.73(a)(2)(i)(A), the completion of any nuclear plant shutdown required by the plant's Technical Specifications, 10 CFR 50.73(a)(2)(i)(B), any operation or condition which was prohibited by the plant's Technical Specifications, and 10 CFR 50.73(a)(2)(iv)(A), any event or condition that resulted in manual or automatic actuation of the Reactor Protection System including a reactor trip.
IV. SAFETY SIGNIFICANCE
Following the discovery of the missed SR, the Performance Capacity Test of Station-B Battery was satisfactorily performed on January 28, 2012, with a recorded capacity of 116.4%, indicating the subject equipment was capable of performing its required safety function during the delinquent surveillance interval. Therefore, based on the above, the event had no adverse impact on the health and safety of the public.
V. CORRECTIVE ACTIONS
Completed Corrective Actions:
The Performance Capacity Test of Station-B Battery was successfully completed on January 2 8th, 2012, following a Technical Specification required shutdown.
An interim method of reporting and reviewing ITS SRs was implemented until a more robust method could be developed.
Planned Corrective Actions
Revise frequency codes and calculation methods to provide due dates and late dates that are aligned with or conservative to ITS frequencies, due dates and overdue dates.
Develop and implement a set of site specific procedures to provide implementing guidance for the coordination of SRs at HBRSEP, Unit No. 2.
VI. PREVIOUS SIMILAR EVENTS
Licensee Event Reports (LERs) for HBRSEP, Unit No. 2, were reviewed from the past 5 years. No similar events were identified.