05000311/LER-2005-002, Regarding Reactor Coolant Instrument Line Through-Wall Leak
| ML051650342 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/03/2005 |
| From: | Fricker C Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N05-0308 LER 05-002-00 | |
| Download: ML051650342 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(ii) |
| 3112005002R00 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 JUN 0 3 2005 LR-N05-0308 oI PSEG Nu clearLLC U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LER 311 / 05-002 - 00 Salem Generating Station Unit 2 Facility Operating License DPR-75 Docket No. 50-311 This Licensee Event Report (LER) entitled "Reactor Coolant Instrument Line Through-Wall Leak' is being submitted pursuant to the requirements of 10CFR 50.73(a)(2)(ii)(A).
The attached LER contains no commitments.
Should there be any questions regarding this matter please contact Howard Berrick at 856-339-1862.
Sincerely, C. Frick Salem Plant Manager Attachment HGB C
Distribution LER File 3.7 Q--
95-2168 REV. 7/99
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06130/2007
, the NRC may digits/characters for each block) sponsor, and a person Is not required to respond to, the
- 3. PAGE Salem Generating Station - Unit 2 0500031 1 OF 4
- 4. TITLE Reactor Coolant Instrument Line Throuch-Wall Leak
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MSEQUENTIALl REV OINTY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMERU NO.
MONTH DAY YEAR FACILrTY NAME DOCKET NUMBER 4
4 2005 2005 002 00 6
3 2005
- 9. OPERATING MODE 11.THIS REPORT IS SUBMITTED PURSUANTTOTHEREQUIREMENTS OF 10CFR§: (Check aelthat apply) o 20.2201(b) 0 20.2203(aX3Xi) 0 50.73(a)(2XiXC)
D 50.73(a)(2Xvli) 1 0 20.2201(d) 0 20.2203(aX3)(ii) 0i 50.73(a)(2Xii)(A) 0 50.73(a)(2Xvlii)(A) o 20.2203(a)(1) 0 20.2203(aX4) 0 50.73(a)(2Xii)(B) 0 50.73(a)(2Xviii)(B) 0 20.2203(a)(2Xi) 0 50.36(cXl)(1)(A) 0 50.73(a)(2Xiii) 0 50.73(a)(2Xix)(A)
- 10. POWER LEVEL 0 20.2203(a)(2Xii) 0 50.36(cX1)(iiXA) 0 50.73(a)(2Xiv)(A) 0 50.73(a)(2Xx) 0 20.2203(a)(2Xiii) 0 50.36(cX2) 0 50.73(a)(2XvXA) 0 73.71(a)(4) o 20.2203(a)(2Xiv) 0 50.46(a)(3Xii) 0 50.73(aX2)(v)(B) 0 73.71(a)(5) 100 0 20.2203(aX2Xv) 0 50.73(a)(2XiXA) 0 50.73(a)(2)(v)(C) 0 OTHER o 20.2203(aX2Xvi) 0 50.73(a)(2XiXB) 0 50.73(a)(2)(v)(D)
Specify In Abstract below nr In NW(' F~nrm ArAA
- 12. UCENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)
Howard G. Berrick, Senior Licensing Engineer 856-339-1862CAUSE SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COPNNT MANU-REPORTABLE J
FACTURER TO EPIX FACTURER TO EPIX A
AB TBG No
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION 0 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 April 4, 2005, during a Boric Acid program field walkdown, an accumulation of boric acid was identified on %-inch instrument tubing, low-pressure side, associated with 21 Reactor Coolant Pump (RCP) flow transmitter 2FT416. The 2FT416 instrument tubing line was field examined in an effort to assess structural integrity of the tube. The low-pressure tubing was found to possess an accumulation of crystallized dried boric acid, which indicates that the leak was relatively new. The boric acid was removed. A tubing tray pressure plate restraint was then removed, revealing a corrosion point spot.
The removed pressure plate had evidence of corrosion at the same location as the corroded point spot on the tubing. Extensive walkdowns of instrumentation tubing in containment revealed evidence of additional instrumentation tube leakage. Corrective actions included replacement of instrumentation tubing, tightening loose fittings, swiping, sampling and cleaning, as necessary.
This event is reportable in accordance with IOCFR50.73(a)(2)(ii), 'Any event or condition that resulted in: (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded".
NRC~~~~~~~
FOR 36 620)PITD NRCCE A
NRC FORM 366 (6-2004)
PRINTED ON RECYCLED PAPER
t11 1, :, i I I,,"
I.
I I t
- - 1':
11, . I V.11, :,
. e. -,
., I,. I..:..
(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)
SAFETY CONSEQUENCES AND IMPLICATIONS (contd)
The RCS flow instruments are designed with a common high-pressure tap and individual low pressure taps. A failure of a low-pressure tap would cause the affected channel to fail high, leaving two channels available for the reactor protection function. No indications of RCS flow anomalies were noted. The safety function of providing a reactor trip on a low RCS flow condition was not impacted by this event.
Based on the above, there was no impact to the health and safety of the public.
A review of this event determined that a Safety System Functional Failure (SSFF) as defined in the Nuclear Energy Institute (NEI) 99-02 did not occur.
CORRECTIVE ACTIONS
- 1. All tubing sections identified to have through wall leakage were replaced during the Salem 2R14 refueling outage.
- 2. The RC flow transmitter tubing from the instrument root valves to the transmitters, and all drain piping associated with the accumulator drain valves were cleaned to acceptable chloride levels.
- 3. A chloride contamination control program will be established to preclude events of this nature.
- 4. An evaluation of the structural integrity assessment and its impact on reporting requirements is in progress. Additional corrective actions will be taken at the completion of the evaluation.
COMMITMENTS
This LER contains no commitments.