05000261/LER-2003-001, For H. B. Robinson Unit 2 Regarding Failure to Complete Technical Specifications Required Action within the Allowed Completion Time
| ML031150031 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 04/23/2003 |
| From: | Cleary T Progress Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RNP-RA/03-0052 LER 03-001-00 | |
| Download: ML031150031 (7) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor |
| 2612003001R00 - NRC Website | |
text
10 CFR 50.73 Progress Energy Serial: RNP-RA/03-0052 APR 2 3 2003 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 LICENSEE EVENT REPORT NO. 2003-001-00 FAILURE TO COMPLETE TECHNICAL SPECIFICATIONS REQUIRED ACTION WITHIN THE ALLOWED COMPLETION TIME 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 Mr. C. T. Baucom.
Sincerely,
/~
C Timothy P. Cleary Plant General Manager CAC/cac Attachment C:
Mr. L. A. Reyes, NRC, Region II Mr. C. P. Patel, NRC, NRR NRC Resident Inspector, HBRSEP
- - s,,-Z Progress Energy Carolinas. Inc.
3581 West Entrance Road Hartsville, SC 29550
NAC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB NO. 3150-0104 EXPIRES 6-30-2001 (1-2001)
COMMISSION
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
FACILITY NAME (1)
DOCKET NUMBER (2)
PAGE (3)
H. B. Robinson Steam Electric Plant, Unit No. 2 05000261 1 OF 6 TITLE (4)
Failure to Complete Technical Specifications Required Action within the Allowed Completion Time EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
_Q A
[
FACILITY NAME DOCKET NUMBER MO DAY YEAR YEAR SENQUMENTA MO DAY YEAR 05000 l
FACILITY NAME DOCKET NUMBER 02 24 2003 2003 - 001
- - 00 04 24 2003 _
05000 OPERATING THIS REPORT IS SUBMITTED PURSUANTTO THE REQUIREMENTS OF 10 CFR § (Check all that apply) (11)
MODE (9) 1
=
20.2201 (b)
_ 20 2203(a)(3)(ii) 150.73(a)(2)(ii)(B) 50.73(a)(2)(ix)(A)
POWER 20.2201(d) 20 2203(a)(4) 50.73(a)(2)(i^i) 50.73(a)(2)(x)
LEVEL (10) 100%
1 20 2203(a)(1)
_ 50 36(c)(1)(i)(A) 50.73(a)(2)(iv)(A) 73 71 (a)(4) 20 2203(a)(2)(1)
_ 50 36(c)(1)(fi)(A) 50.73(a)(2)(v)(A)
_ 73.71 (a) (5) 20 2203(a)(2)(ii) 50 36(c)(2) 50 73(a)(2)(v)(B)
OTHER
- - Specify in Abstract below or in 20 2203(a)(2)(iii) 50 46(a)(3)(ii) 50 73(a)(2)(v)(C)
(If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (if more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A) (17)
IV.
CORRECTIVE ACTIONS
The corrective actions for this event that have been completed include the following:
- - discussion of this event with each shift at turnover as an interim action,
- - a caution tag was placed on the chart recorder warning operators that opening the cover on the recorder will halt the recorder and that pressing the RUN/HALT button will restart the recorder after the cover is closed,
- - a night order (03-004) was issued, which clarifies the operation of the recorder,
- - a signoff was added to the auxiliary operator log for the review and proper operation of the chart recorder, and
- - additional training information was distributed to the operations crews that includes photographs of the recorder and specific details of the different displays.
V.
ADDITIONAL INFORMATION
A. Failed Component Information:
There were no failed components associated with this event.
B. Previous Similar Events
A review of recent (past 3 years) events at HBRSEP, Unit No. 2, for conditions prohibited by the TS was conducted. Licensee Event Report 2002-001-00 identifies steam generator safety valve inoperability discovered during testing that resulted in a condition prohibited by the TS. This event occurred due to equipment malfunction and is not relatable to this event.
Licensee Event Report 2001-001-00 identifies a condition where a reactor core protection channel for detection of low reactor coolant system flow was found out-of-tolerance. This event was attributed to human error and lack of procedural guidance. The instrument and control system calibrations are performed by maintenance personnel and use different procedures than those used by the operators in
, conducting activities associated with the Control Rod H-10 verifications.
Therefore, the cause and corrective actions identified by Licensee Event Report 2001-001-00 would not have been expected to prevent the failure to meet the required actions for Control Rod H-10 ARPI inoperability.