05000311/LER-2006-003, Re Manual Reactor Trip Due to Elevated Reactor Coolant Pump Seal Leak-off
| ML063410224 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/27/2006 |
| From: | Fricker C Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N06-0442 LER 06-003-00 | |
| Download: ML063410224 (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 |
| 3112006003R00 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 O PSEG Nuclear LLC NOV 27 2006 1 OCFR50.73 LR-N06-0442 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555-001 LER 311/06-003 Salem Nuclear Generating Station Unit 2 Facility Operating License No. DPR-75 NRC Docket No. 50-311
SUBJECT:
Manual Reactor Trip Due to Elevated Reactor Coolant Pump Seal Leakoff This Licensee Event Report, "Manual Reactor Trip due to Elevated Reactor Coolant Pump Seal Leakoff," 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 Justin Wearne at 856-339-5081.
Salem Plant Manager Attachments (1) 95-21 95-2168 REV. 7/99
NovS7 2 Page 2 Document Control Desk LR-N06-0442 C
Mr. Samuel Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission Attn: Mr. S. Bailey, Licensing Project Manager - Salem Mail Stop 08B1 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Salem (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P.O. Box 415 Trenton, NJ 08625
FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
Estimated burden per response to comply with this mandatory collection request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records and FOIA/Privacy Service Branch (T-5 F52), U.S. Nuclear Regulatory Commission, LICENSEE EVENT REPORT (LER)
Washington, DC 20555-0001, or by internet e-mail to infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104),
Office of Management and Budget, Washington, DC 20503. if a means used to impose an information collection does not display a currently valid OMB control (See reverse for required number of number, the NRC may not conduct or sponsor, and a person is not required to digits/characters for each block) respond to, the information collection.
j3. PAGE Salem Generating Station - Unit 2 05000311 1 of 4
- 4. TITLE Manual Reactor Trip Due to Elevated Reactor Coolant Pump Seal Leak-off
- 6. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REVFAITYNMDOKTUBE NUMBER NO.
MONTH DAY YEAR 09 6 0 20 6-0 3-0
______ I FACILITY NAME DOCKET NUMBER
- 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)
El 50.73(a)(2)(vii) 1
]
20.2201(d)
C3 20.2203(a)(3)(ii)
C] 50.73(a)(2)(ii)(A)
E] 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 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 El 20.2203(a)(2)(ii) 0l 50.36(c)(1)(ii)(A)
[9 50.73(a)(2)(iv)(A) 0l 50.73(a)(2)(x)
C3 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A) 0l 73.71(a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
[] 50.73(a)(2)(v)(B) 0l 73.71(a)(5) 094 [1 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
[3 50.73(a)(2)(v)(C)
El 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 nr in N*. F:nrm *RRA
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (include Area Code)
Justin Wearne, Licensing Engineer t856-339-5081MANU-REPORTABLE MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT FACTURER TO EPIX
CAUSE
SYSTEM COMPONENT TO EPIX X
AB P
W351 Y
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION El YES (Ifyes, complete 15. EXPECTED SUBMISSION DATE) 0 NO DATE ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
On September 26, 2006 at 1513, with Salem Unit 2 in an end of cycle (EOC) coast down at 94% power, a manual reactor trip was performed due to elevated seal leak-off flows on 21 Reactor Coolant Pump (RCP). The 21 RCP number one seal leak-off flow exceeded the pump trip criteria of greater than 6 gpm. The reactor trip actions and plant recovery were performed without complications.
A root cause team determined that the most probable cause is the combination of dissolved oxygen being introduced into a low boron and low lithium Reactor Coolant System which caused corrosion products to become dislodged from the system and deposited onto the RCP seals. Corrective actions are to improve procedures to better cope with EOC chemistry conditions.
This report is being made 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)."
NRC FORM 366 (6-2004)
PRINTED ON RECYCLED PAPER NRC FORM 366 (6-2004)
PRINTED ON RECYCLED PAPER
(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. Immediate corrective actions were taken to increase sensitivity to and minimize activities that could potentially cause a perturbation in RCS chemistry while at low boron (<100 ppm) concentrations for the remaining operating cycle until the refueling outage.
- 2.
An adverse condition monitoring plan was established that provided for increased monitoring of RCS chemistry and RCP pump parameters for the remainder of the EOC coastdown.
- 3.
Actions are being taken to identify activities that can impact RCS pH and to better accommodate EOC chemistry including procedure revisions for Reactor Coolant filter replacement.
- 4. Training will be conducted for various station departments regarding implications of end-of-cycle chemistry conditions associated with coastdown.
COMMITMENTS
This LER contains no commitments