05000373/LER-2010-003, Regarding Standby Liquid Control Test Tank Seismic Analysis
| ML103560658 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/21/2010 |
| From: | Karaba P Exelon Nuclear |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| RA10-086 LER 10-003-00 | |
| Download: ML103560658 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 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) 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)(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 |
| 3732010003R00 - NRC Website | |
text
Nuclear LaSalle Generating Station www.exeloncorp.com 2601 North 21st Road Marseilles, IL 61341-9757 10 CFR 50.73 RA1 0-086 December 21, 2010 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 LaSalle County Station, Unit 1 and Unit 2 Facility Operating License No. NPF-1 1 and NPF-1 8 NRC Docket No. 50-373/50-374
Subject:
Licensee Event Report 2010-003-00 In accordance with 10 CFR 50.73(a)(2)(v)(A)/(C), 10 CFR 50.73(a)(2)(i)(B), and 10 CFR 50.73(a)(2)(vii) Exelon Generation Company (EGC), LLC, is submitting Licensee Event Report Number 2010-003-00.
There are no regulatory commitments in this report. Should you have any questions concerning this report, please contact Mr. Terrence W. Simpkin, Regulatory Assurance Manager at (815) 415-2800.
Peter J. Karaba Plant Manager LaSalle County Station
Enclosure:
Licensee Event Report Cc:
Regional Administrator - NRC Region III NRC Senior Resident Inspector - LaSalle County Station
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (10-2010)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the i
information collect on.
- 3. PAGE LaSalle County Station, Unit 1 05000373 1
OF 3
- 4. TITLE Standby Liquid Control Test Tank Seismic Analysis
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR FACILITY NAME LaSalle County Station, Unit 2 DOCKET NUMBER 05000374 NUMBER NO.
FACILITY NAME DOCKET NUMBER 10 28 2010 2010 003 00 12 17 2010
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) q 20.2201(b) q 20.2203(a)(3)(i) q 50.73(a)(2)(i)(C)
Z 50.73(a)(2)(vii) 1 q 20.2201(d) q 20.2203(a)(3)(ii) q 50.73(a)(2)(ii)(A) q 50.73(a)(2)(viii)(A) q 20.2203(a)(1) q 20.2203(a)(4) q 50.73(a)(2)(ii)(B) q 50.73(a)(2)(viii)(B) q 20.2203(a)(2)(i) q 50.36(c)(1)(i)(A) q 50.73(a)(2)(iii) q 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL q 20.2203(a)(2)(ii) q 50.36(c)(1)(ii)(A) q 50.73(a)(2)(iv)(A) q 50.73(a)(2)(x) q 20.2203(a)(2)(iii) q 50.36(c)(2) 50.73(a)(2)(v)(A) q 73.71(a)(4) 100 q 20.2203(a)(2)(iv) q 50.46(a)(3)(ii) q 50.73(a)(2)(v)(B) q 73.71(a)(5) q 20.2203(a)(2)(v) q 50.73(a)(2)(i)(A)
Z 50.73(a)(2)(v)(C) q OTHER q 20.2203(a)(2)(vi)
Z 50.73(a)(2)(i)(B) q 50.73(a)(2)(v)(D)
Specify in Abstract below or in
D. SAFETY ANALYSIS
The safety significance of this event is minimal. The safety function of the SBLC system is to provide the capability of bringing the reactor, at any time in a fuel cycle, from full power and minimum control rod inventory to a subcritical condition. The probability of a design basis earthquake concurrent with an anticipated transient without scram (ATWS) condition is low. Additionally there is procedural guidance for injecting sodium pentaborate solution using the Reactor Water Clean-up (RWCU) system with the SBLC system unavailable.
E.
CORRECTIVE ACTIONS
This event occurred in 1981 and therefore is historical. An Engineering evaluation was performed to support seismic analysis of the SBLC test tank mounting with the test tank drained. Procedural controls have been put in place to direct the operator to drain the SBLC test tank following surveillance testing that requires use of the test tank.
F.
PREVIOUS OCCURRENCES
A review of LSCS Licensee Event Reports (LERs) for the last three years did not identify any LERs associated with seismic analysis of the SBLC system.
G. COMPONENT FAILURE DATA
Component failures were not involved with this event.