05000388/LER-2009-001, Multiple Test Failures of Main Steam Safety Relief Valves
| ML092960277 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/12/2009 |
| From: | Rausch T Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-6552 LER 09-001-00 | |
| Download: ML092960277 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(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 |
| 3882009001R00 - NRC Website | |
text
Timothy S. Rausch Sr. Vice President & Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3445 Fax 570.542.1504 tsrausch@pplweb.com DO-ppN OCT 12 2D09 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OP 1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 50-388/2009-001-00 LICENSE NO, NPF-22 PLA-6552 Docket No 50-388 Attached is Licensee Event Report (LER) 50-388/2009-001-00. This event was determined to be a Common-Cause Inoperability of Independent Trains or Channels and reportable under 10 CFR 50.73(a)(2)(vii) in that three (3) safety relief valves (SRVs) failed to meet their setpoint criteria in Technical Specification 3.4.3.
There were no actual consequences to the health and safety of the public as a result of this event.
No regulatory commitments are associated with this LER.
T. S. Rausch Senior Vice -President and Chief Nuclear Officer Attachment Copy:
NRC Region I Mr. R. R. Janati, DEP/BRP Mr. F. W. Jaxheimer, NRC Sr. Resident Inspector Mr. B. K. Vaidya, NRC Project Manager ru
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2010 (9-2007)
, the NRC may digits/characters for each block) not conduct or sponsor, and a person is not required to respond to, the information collection.
l3. PAGE Susquehanna Steam Electric Station Unit 2 05000388 1 OF 3
- 4. TITLE Multiple Test Failures of Main Steam Safety Relief Valves
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEQUENTIAL REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 04 29 2009 2009 - 001 -
00 10 12 2009 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
El 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
ED 50.73(a)(2)(vii) 5 El 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
[I 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL E] 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
El 73.71(a)(4)
[3 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 0%
El 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER E
20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below or in
CORRECTIVE ACTIONS
The following corrective action has been completed:
& The SRVs were replaced with SRVs having a setpoint tolerance of +/- 1%.
The following corrective action is planned:
Revise reportability procedure to clarify that multiple test failures should also be evaluated for common cause under 10 CFR 50.73(a)(2)(vii) and that setpoint drift is a common cause.
Evaluate the existing test procedure, valve performance, appropriateness of maintaining the current TS limit, and take actions accordingly.
No regulatory commitments are associated with this report.
ADDITIONAL INFORMATION
Failed Component Information: None
Previous Similar Events
LER 2000-003-00, Docket No. 387/License No. NPF-14, "Multiple Test Failures of Suppression Chamber-to-Drywell Vacuum Breakers" LER 2000-007-00, Docket No. 387/License No. NPF-14, "Multiple Test Failures of Main Steam Safety Relief Valves" LER 2001-005-00, Docket No. 388/License No. NPF-22, "Multiple Test Failures of Main Steam Safety Relief Valves."
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