05000272/LER-2005-003, Regarding ECCS Leakage Outside Containment Exceeds Dose Analysis Limits (Seal Injection Filter Replacement)

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Regarding ECCS Leakage Outside Containment Exceeds Dose Analysis Limits (Seal Injection Filter Replacement)
ML051940204
Person / Time
Site: Salem PSEG icon.png
Issue date: 07/05/2005
From: Joyce T
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N05-0310 LER 05-003-00
Download: ML051940204 (6)
v • d • e


LER-2005-003, Regarding ECCS Leakage Outside Containment Exceeds Dose Analysis Limits (Seal Injection Filter Replacement)
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)(iii)
10 CFR 50.73(a)(2)(iv)(A), System Actuation
2722005003R00 - NRC Website
v • d • e

text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 LR-N05-031 0 JUL 0 5 2005 o PSEG Mutclear LLC U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LER 272/05 - 003 - 00 Salem Generating Station Unit 1 Facility Operating License DPR-70 Docket No. 50-272 This Licensee Event Report (LER) entitled "ECCS Leakage Outside Containment Exceeds Dose Analysis Limits (Seal Injection Filter Replacement)," is being submitted pursuant to the requirements of 1 OCFR 50.73(a)(2)(v).

The attached LER contains no commitments.

Should there be any questions regarding this 856-339-5456.

matter please contact Enrique Villar at Sincerely, Thomas P. Joyc Site Vice President - Salem Attachment EHV C

Distribution LER File 3.7 11L

95-2168 REV. 7/99

FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 0613012007 (6-2004)

, the NRC may digits/characters for each block) or nsor, and a person Is not required to respond to, the

3. PAGE Salem Generating Station Unit 1 05000272 1 OF 5
4. TITLE ECCS Leakage Outside Containment Exceeds Dose Analysis Limits (Seal Injection Filter Replacement)
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILMES INVOLVED SEUNTA RVFACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER N

LR MONTH DAY YEAR FACILfTY NAME DOCKET NUMBER 05 03 2005 2005 - 003 -

00 07 05 2005

9. OPERATING MODE THIS REPORTIS SUBMITTEDPURSUANT TO THE REQUIREMENTSOF CFR§: (Checkallithatapply) oJ 20.2201(b) 03 20.2203(aX3)(i) 0] 50.73(a)(2X(i)C) 0 50.73(aX2)(vii) 1 0

20.2201(d) 0 20.2203(aX3)(ii) 0 50.73(a)(2Xii)(A) 0 50.73(a)(2)(viiiXA) o 20.2203(a)(1) 0 20.2203(aX4) 0 50.73(a)(2Xii)(B) 0 50.73(a)(2)(viiiXB) 0o 20.2203(a)(2Xi) 0 50.36(cXl)(iXA) 0 50.73(a)(2)(iii) 0 50.73(aX2)(ix)(A)

10. POWER LEVEL 0

20.2203(a)(2Xii) 0 50.36(cXI)(ii)(A) 0 50.73(a)(2)(iv)(A) 0 50.73(aX2)(x) 0 20.2203(aX2Xiii) 0 50.36(cX2) 0 50.73(a)(2XvXA) 0 73.71(aX4) oI 20.2203(a)(2Xiv) 0 50.46(a)(3Xii) 0 50.73(a)(2)(vXB) 0 73.71(aX5) 100%/

0 20.2203(aX2Xv) 0 50.73(a)(2XiXA) 0 50.73(a)(2)(vXC) 0 OTHER o 20.2203(aX2Xvi) 0 50.73(aX2XIXB) 0 50.73(a)(2)(vXD)

Specify In Abstract below nr In NR(' Fnrm.VAA

12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Indude Area Code)

E. H. Villar, Licensing Engineer 856-339-5456

13. COMPLETE ONE UNE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT

CAUSE

SYSTEM COMPONENT MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT MANU-REPORTABLE

.1_____FACTURER TO EPIX FACTURER TO EPIX X

GB

_ISV

_ _j No

14. SUPPLEMENTAL REPORT EXPECTED
15. EXPECTED MONTH DAY YEAR SUBMISSION o YES (If yes, complete 15. EXPECTED SUBMISSION DATE) 0 NO DATE ABSTRACT (Umit to 1400 spaces, I.e., approximately 15 single-spaced typewritten lines)

On May 3, 2005, the 11 seal water injection filter was removed from service in preparation for filter replacement.

A local leak rate was performed following the tag out and determined that the leakage was well within the acceptable administrative limit for Emergency Core Cooling System (ECCS) leakage outside the containment. Subsequent Reactor Coolant System (RCS) water inventory surveillances completed at 0900 and 2318 hours0.0268 days <br />0.644 hours <br />0.00383 weeks <br />8.81999e-4 months <br /> on May 3 indicated an unidentified RCS leakrate of 0.3 gallons per minute (gpm). On May 4 at approximately 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> the seal water injection filter work was completed and the filter returned to standby mode. A third RCS water inventory was completed on May 4 showing an unidentified leak rate of 0.055 gpm. At this point it was determined that the increased leakage was associated with the seal replacement work. This leakage (approximately 68,000 cubic centimeters/hour (cc/hr)) exceeded the 3800 cc/hr limit stated in the Final Safety Analysis Report (FSAR) Section 6.3.2.11 for ECCS leakage outside the containment. The apparent cause for the excessive leakage was inadequate isolation of the seal injection filter. Some of the corrective actions taken are: The seal water injection filter isolation valves are scheduled to be repaired in the next refueling outage, the human performance deficiencies have been documented in the corrective action program, Operations procedures will be revised to provide enhanced guidance on anomalous RCS leakrate trends, and the ownership for the leakage monitoring and reduction program will be transferred from Engineering to Operations.

This event is reportable in accordance with 1 OCFR50.73(a)(2)(v), many 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."

NRC FORM 306(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 (If more space Is required, use additional copies of NRC Form 366A)

CORRECTIVE ACTIONS

1. The seal water injection filter isolation valves are scheduled to be repaired in the next refueling outage.
2. The human performance deficiencies have been documented in the corrective action program and corrective actions are being developed.
3. Operations procedures will be revised to provide enhanced guidance on investigating anomalous trends of RCS leak rates.

1

4. The ownership for the leakage monitoring and reduction program will be transferred from Engineering to Operations.
5. The events as described in this LER will be submitted to the PSEG Operations Training Review Group for incorporation into the formal training program for operations personnel.

COMMITMENTS

This LER contains no commitments.

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