05000400/LER-2010-005, For Harris Nuclear Plant, Unit 1 Regarding Emergency Core Cooling System (ECCS) Inoperable for Greater than Time Allowed by Technical Specifications
| ML110050078 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/30/2010 |
| From: | Henderson K Progress Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| HNP-10-134 LER 10-005-00 | |
| Download: ML110050078 (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)(B), Unanalyzed Condition 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 |
| 4002010005R00 - NRC Website | |
text
pTagess Enavgy DEC 3 0 2010 Serial: HNP-10-134 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 LICENSEE EVENT REPORT 2010-005-00 Ladies and Gentlemen:
The enclosed Licensee Event Report (LER) 2010-005-00 is submitted in accordance with 10 CFR 50.73, paragraph (a)(2)(i)(B) as a condition prohibited by the plant Technical Specifications and paragraph (a)(2)(v)(D) as a condition that could have prevented the fulfillment of a safety function needed to mitigate the consequences of an accident. This report describes an event in which an inadequate operating procedure resulted in the required number of Operable Emergency Core Cooling System Trains being less than that required by Technical Specifications due to two Residual Heat Removal header isolation valves being de-energized. In accordance with 10 CFR 50.73(a) requirements, this LER is submitted within 60 days following discovery of the event.
This document contains no Regulatory Commitments.
Please refer any questions regarding this submittal to Mr. John Caves, Supervisor -
Licensing/Regulatory Programs, at (919) 362-3137.
Sincere 7x-Kelvin Henderson Plant General Manager Harris Nuclear Plant KH/kab Enclosure cc:
Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mrs. B. L. Mozafari, NRC Project Manager, HNP Mr. L. A. Reyes, NRC Regional Administrator, Region II Progress Energy Carolinas, Inc.
Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562 GL)
- ,,4 il 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 digits/characters for each block) information collection.
- 3. PAGE Harris Nuclear Plant - Unit 1
- - i05000 0400 1
OF
- 4. TITLE Emergency Core Cooling System (ECCS) Inoperable for Greater than Time Allowed by Technical Specifications
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR N/A 05000 NUMBER NO.
FACILITY NAME DOCKET NUMBER 11 9
10 2010 005 -
00 12 30 10 N/A 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
[]20.2201(b)
[
20.2203(a)(3)(i)
]
50.73(a)(2)(i)(C) 5 50.73(a)(2)(vii) 4 20.2201(d) 5 20.2203(a)(3)(ii) 5] 50.73(a)(2)(ii)(A)
[
50.73(a)(2)(viii)(A)
[] 20.2203(a)(1)
I]
20.2203(a)(4)
[] 50.73(a)(2)(ii)(B)
.i 50.73(a)(2)(viii)(B)
[]
20.2203(a)(2)(i)
E] 50.36(c)(1)(i)(A)
[] 50.73(a)(2)(iii) 5 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 20.2203(a)(2)(ii)
[j 50.36(c)(1)(ii)(A) 5 50.73(a)(2)(iv)(A) 5 50.73(a)(2)(x) 5 20.2203(a)(2)(iii) 5 50.36(c)(2)
[] 50.73(a)(2)(v)(A)
El 73.71(a)(4)
[] 20.2203(a)(2)(iv)
E] 50.46(a)(3)(ii)
[]
50.73(a)(2)(v)(B) 5 73.71(a)(5) 0%
El 20.2203(a)(2)(v)
E] 50.73(a)(2)(i)(A)
E] 50.73(a)(2)(v)(C) 5 OTHER 1=
20.2203(a)(2)(vi)
[
50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)
Specify in Abstract below or in
PREVIOUS SIMILAR EVENTS
LER-2006-02-00, During Refueling Outage 13 (RFO-13), a rebuilt York Compressor was installed on the A Chiller for the
'A Essential Services Chilled Water (ESCW) system. To connect the rebuilt compressor, personnel reinstalled and reconnected the linkage between the compressor pre-rotation vane (PRV) shaft and the PRV motor. The root cause of this event was a technically inadequate maintenance procedure. This did not prevent the recurrence because the current issue involved an operating procedure rather than the conduct of maintenance.
CORRECTIVE ACTIONS
Immediate Corrective Actions
- - 1RH-25 and 1RH-63 circuit breakers were promptly closed and the entry into Technical Specification 3.0.3 was exited.
(11/9/2010)
- - Operating Procedure "OP" lineup checks were performed. (11/10/2010)
- - OP-111 was revised to remove the error that caused the breakers to be opened. (11/10/2010)
Planned Corrective Actions
- - Complete Operations training on Human Performance