Event Notification Report for March 09, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/08/2002 - 03/09/2002
EVENT NUMBERS
38758
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 38758
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GORDON ROBINSON
HQ OPS Officer: JOHN MacKINNON
Notification Date: 03/09/2002
Notification Time: 05:32 [ET]
Event Date: 03/09/2002
Event Time: 01:00 [EST]
Last Update Date: 04/03/2002
Notification Time: 05:32 [ET]
Event Date: 03/09/2002
Event Time: 01:00 [EST]
Last Update Date: 04/03/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
MOHAMED SHANBAKY (R1)
MOHAMED SHANBAKY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
LOCAL LEAK RATE TEST FAILURE
Appendix J Local Leak Rate Testing of Containment Penetration for Drywell Sprays failed Tech Spec Acceptance Criteria for Secondary Containment Bypass Leakage. The leakage limit is 9 standard cubic feet per hour and the test results were 10.5 standard cubic feet per hour. The identified degraded condition is reportable as a condition of the nuclear power plant, including its principle safety barriers being seriously degraded per 10CFR50.72(b)(3)(ii)
The NRC Resident Inspector will be notified of this event by the licensee.
***UPDATE (RETRACTION) ON 4/3/02 at 1147 EST FROM ROBERT BOESCH TO RICH LAURA***
"On 03/09/02, Appendix J Local Leak Rate Testing (LLRT) of a primary containment penetration for Drywell Sprays failed Tech Spec Acceptance Criteria for Secondary Containment Bypass Leakage. The test results were attributed to the tested Containment Isolation Valve (CIV), HV151F016A. The identified condition was reported in EN#38758 as a Degraded Condition per 10 CFR 50.72(b)(3)(ii)(A).
"As a result of observations made during the testing, one of the test boundary valves, HV151F021A, was refurbished. Significant valve seat degradation was noted after the test boundary valve was disassembled. After the refurbishment of the test boundary valve, the Appendix J LLRT was repeated for the tested CIV, HV151F016A, with acceptable results. Since no significant maintenance was performed on the tested CIV that would affect its leak-tightness, the subsequent test results are valid for as-found leakage of the tested CIV. The total As-Found Secondary Containment Bypass Leakage was less than the Tech Spec limit. Based on this evaluation, ENS Notification EN#38758 is retracted."
The NRC Resident Inspector was notified. The R1DO (G. Meyer) was notified.
Appendix J Local Leak Rate Testing of Containment Penetration for Drywell Sprays failed Tech Spec Acceptance Criteria for Secondary Containment Bypass Leakage. The leakage limit is 9 standard cubic feet per hour and the test results were 10.5 standard cubic feet per hour. The identified degraded condition is reportable as a condition of the nuclear power plant, including its principle safety barriers being seriously degraded per 10CFR50.72(b)(3)(ii)
The NRC Resident Inspector will be notified of this event by the licensee.
***UPDATE (RETRACTION) ON 4/3/02 at 1147 EST FROM ROBERT BOESCH TO RICH LAURA***
"On 03/09/02, Appendix J Local Leak Rate Testing (LLRT) of a primary containment penetration for Drywell Sprays failed Tech Spec Acceptance Criteria for Secondary Containment Bypass Leakage. The test results were attributed to the tested Containment Isolation Valve (CIV), HV151F016A. The identified condition was reported in EN#38758 as a Degraded Condition per 10 CFR 50.72(b)(3)(ii)(A).
"As a result of observations made during the testing, one of the test boundary valves, HV151F021A, was refurbished. Significant valve seat degradation was noted after the test boundary valve was disassembled. After the refurbishment of the test boundary valve, the Appendix J LLRT was repeated for the tested CIV, HV151F016A, with acceptable results. Since no significant maintenance was performed on the tested CIV that would affect its leak-tightness, the subsequent test results are valid for as-found leakage of the tested CIV. The total As-Found Secondary Containment Bypass Leakage was less than the Tech Spec limit. Based on this evaluation, ENS Notification EN#38758 is retracted."
The NRC Resident Inspector was notified. The R1DO (G. Meyer) was notified.