05000311/LER-2004-009, Re ECCS Leakage Outside Containment Exceeds Dose Analysis Limits (23 Charging Pump)
| ML043570456 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/13/2004 |
| From: | Fricker C Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N04-0565 LER 04-009-00 | |
| Download: ML043570456 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) 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)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iii) |
| 3112004009R00 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 o PSEG ANuclear LLC DEC 1 3 2004 LR-N04-0565 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LER 311104-009-00 SALEM - UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 This Licensee Event Report, 'ECCS Leakage Outside Containment Exceeds Dose Analysis Limits (23 Charging Pump)," is being submitted pursuant to the requirements of the Code of Federal Regulations 1 OCFR50.73(a)(2)(v).
The attached LER contains no commitments.
Sincere~l7Pl a
C cker S'lem Plant Manager Attachment
/EHV C
Distribution LER File 3.7 k--) 1--)
"Ir' e5:e:'112 ';:;"-
95-2168 REV. 7/99
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06130/2007 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.
LICENSEE EVENT REPORT (LER)
Nuclear Regulatory Commission. Washington. DC 20555-0001, or by Internet
..and Regulatory Affairs, NE8 B-0202 (3150.0104), Office of Management and Budget. Washington, DC 20503. i a means used to Impose an Information (See reverse for required number of collectiondoesnotdisplayacurrentlyvalidMB control number, the NRC may digits/characters for each block) and a person Is not required to respond to, the
- 3. PAGE Salem Generating Station Unit 2 05000311 I OF 4 4, TITLE.
. a.
ECCS Leakage Outside Containment Exceeds Dose Analysis Limits (23 Charging Pump)
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SENUENTIAL REO. MONTH DAY YEAR FACILrTY NAME DOCKET NUMBER 10 13 2004 2004 - 009 -
00 12 13 2004
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) 0 20.2201(b) 0 20.2203(aX3)(i) 0 50.73(a)(2)(iXC) 0 50.73(a)(2)(vii) 1 0 20.2201(d) 0 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viiiXA) 0 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viiiXB) o 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iii) 0 50.73(aX2)(ix)(A)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 50.36(c)(1 Xii)(A) 0 50.73(aX2)(ivXA) 0 50.73(aX2)(x) 0 20.2203(aX2)(iii) 0 50.36(c)(2) 0 50.73(aX2)(v)(A) 0 73.71(aX4) o 20.2203(aX2)(iv) 0 50.46(aX3)(ii) 0 50.73(aX2)(v)(B) 0 73.71(a)(5) 100%
0 20.2203(aX2)(v) 0 50.73(aX2)(1)(A) 0 50.73(aX2)(v)(C) 0 OTHER o 20.2203(aX2)(vi) 0 50.73(a)(2Xi)(B) 0 50.73(a)(2)(v)(D)
Specify In Abstract below nr in NRC. Fnrm rnRA
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Include Area Code)
E. H. Villar, Licensing Engineer 856-339-5456CAUSE SYSTEM COMPONENT MANU REPORTABLE l
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTE COMPNENTFACTURER TO EPIX FCUE OEI X
CB V
No
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION 0 YES (If yes, complete 15. EXPECTED SUBMISSION DATE) 0D NO DATE ABSTRACT (Umit to 1400 spaces, Le., approximately 15 single-spaced typewritten lines)
This event is reportable in accordance with 1 OCFR50.73(a)(2)(v), Zany event or condition that could have prevented the fulfillment of the safety function of structures or system that are needed to:....(C) control the release of radioactive material; or (D) mitigate the consequences of an accident."
On October 13, 2004, at approximately 14:06 the 23 Positive Displacement Charging Pump (PDP) was removed from service to perform scheduled maintenance. The maintenance involved the removal of the suction stabilizer and placing a flange on the suction side piping where the suction stabilizer was removed. Following the tagging evolution, operations personnel noted a 0.55 gpm (125,000 cc/hr) leak back through the suction flange for the PDP.
The leakage exceeded the administrative limit (2200 cclhr) and 3800 cc/hr limit stated in the Final Safety Analysis Report (FSAR) Section 6.3.2.11 for emergency core cooling system (ECCS) leakage outside the containment.
Because this leakage could not have been isolated from the recirculation flow path during the recirculation phase of the design basis LOCA, the assumptions made in the dose analysis calculations were violated. The apparent cause for the excessive leakage has been determined to be the failure of the 2CV64 to provide full isolation of the pump.
Immediate actions were taken to restore system integrity by removing the blind flange and re-installing the suction stabilizer, thus containing any leakage within the system pressure boundary. Additionally, a corrective action work order has been initiated to repair the discharge valve (2CV64) during the next outage.
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 Forrn 366A)
SAFETY CONSEQUENCES AND IMPLICATIONS (cont'd)
In accordance with Technical Specification 6.8.4.a, "Primary Coolant Sources Outside Containment,"
Salem station has a program to monitor leakage outside the containment and take action to reduce the leakage within the assumption of the LOCA dose analysis. Through implementation of this program the increase in Reactor Coolant System (RCS) unidentified leakage was determined to be outside containment and actions were expeditiously taken to minimize the leakage.
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 NEI 99-02 occurred.
CORRECTIVE ACTIONS
- 1. Immediate actions were taken to restore system integrity by removing the blind flange and re-installing the suction stabilizer, thus containing any leakage within the system pressure boundary.
- 2. A corrective action work order has been initiated to repair the discharge valve (2CV64) during the next outage.
COMMITMENTS
This LER contains no Commitments.