05000311/LER-2007-002, Re Reactor Trip Due to a Breach in the Condensate System
| ML072120588 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/20/2007 |
| From: | Braun R Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N07-0161 LER 07-002-00 | |
| Download: ML072120588 (6) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(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 |
| 3112007002R00 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 Z le, Lk 0 Nuclear LLC JUL 3 0 2007 1 OCFR50.73 LR-N07-0161 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555-001 LER 311/07-002 Salem Nuclear Generating Station Unit 2 Facility Operating License No. DPR-75 NRC Docket No. 50-311
SUBJECT:
Reactor Trip Due To A Breach In The Condensate System This Licensee Event Report, "Reactor Trip Due To A Breach In The Condensate System" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50.73(a)(2)(iv)(A).
The attached LER contains no commitments. Should you have any questions or comments regarding this submittal, please contact Mr. H. Berrick at 856-339-1862.
Sincerely, Robert Braun Site Vice President Salem Generating Station Attachments (1) 95-2168 REV. 7/99
JUL 2 0 2007 Document Control Desk Page 2 LR-N07- 0161 cc Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Salem (X24)
Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSIOI APPROVED BY OMB: NO. 3150-0104 EXPIRES: 0613012007
(-2004)
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. PAGE Salem Generating Station - Unit 2 05000311 1 OF 4
- 4. TITLE Reactor Trip Due to a Breach in the Condensate System
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR None FACILITY NAME DOCKET NUMBER 05 24 2007 2007 002 00 07 23 2007 None
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) 0] 20.2201(b)
El 20.2203(a)(3)(i)
[I 50.73(a)(2)(i)(C)
Cl 50.73(a)(2)(vii)
El 20.2201(d) 0l 20.2203(a)(3)(ii)
[I 50.73(a)(2)(ii)(A)
EL 50.73(a)(2)(viii)(A)
[I 20.2203(a)(1) 0I 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
[I 50.73(a)(2)(viii)(B) 0[ 20.2203(a)(2)(i)
[I 50.36(c)(1)(i)(A)
[l 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
[] 50.36(c)(1)(ii)(A)
N 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)
El 20.2203(a)(2)(iv)
[] 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B) 0l 73.71(a)(5) 100%
El 20.2203(a)(2)(v)
[I 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C) 0l OTHER El 20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify in Abstract below
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (include Area Code)
Howard Berrick, Senior Licensing Engineer 1 856-339-1862MANU-REPORTABLE
CAUSE
COMPONENT RATUR REPORTABLE CAUSEFACTURER TO EPIX FACTURER TO EPIX E
SF LG 004J Y
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION [E YES (If yes, complete 15. EXPECTED SUBMISSiON DATE) 0 NO DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On May 24, 2007 at 0232, Salem Unit 2 tripped due to 22 Steam Generator (SG) low-low level. The cause of the low SG level trip was the failure of the 24 Demineralizer Vessel (DMV) upper sight glass, which resulted in a loss of condensate inventory and suction pressure and ultimately the trip of 21 Steam Generator Feedwater Pump (SGFP).
The 21 SGFP trip resulted in a turbine runback signal and level decrease in the 22 SG. An automatic reactor trip occurred when 2 of 3 channels reached the low-low level set point on the 22 SG. The root cause for failure of the 24 DMV upper sight glass is attributed to the latent failure to control vendor documents pertaining to the installation and maintenance of these sight glass windows. Corrective actions included replacing all Unit 2 sight glass windows prior to placing the DMV's back into service and the replacement of Unit 1 sight glass windows as the DMV's were removed from service during routine operation. All DMV sight glasses have been replaced.
This event is reportable in accordance with 10CFR50.73 (a)(2)(iv)(A), "any event or condition that resulted in manual or automatic actuation of any of the systems listed in paragraph (a)(2)(iv)(B) of this section."
(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)
CORRECTIVE ACTIONS
- 1. Completed a prompt investigation of event and subsequent root cause evaluation.
- 2. All DMV sight glass windows were replaced using the latest vendor guidance. The Unit 2 sight glasses were replaced prior to placing the DMV's in-service. The Unit 1 DMV sight glasses were replaced as the DMV's were removed from service during routine operation.
- 3. The applicable vendor manual will be updated to include the appropriate installation instructions and maintenance procedures for the sight glasses.
COMMITMENTS
No commitments are made in this LER.