05000354/LER-2004-008, Re Potential for Uncontrolled Radiological Release - Reactor Water Clean-up Isolation
| ML043090536 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/28/2004 |
| From: | Hutton J Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N04-0489 LER 04-008-00 | |
| Download: ML043090536 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(i)(B), Prohibited by Technical Specifications |
| 3542004008R00 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 OCT 2 8 2004 LR-N04-0489 O PSEG Nuclear LLC U.S. Regulatory Commission Document Control Desk Washington, DC 20555 LER 354104-008-00 HOPE CREEK GENERATING STATION - UNIT I FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 This Licensee Event Report entitled, Potential For Uncontrolled Radiological Release -
Reactor Water Clean-up Isolation, submitted pursuant to the requirements of 1 OCFR50.73(a)(2)(v)(C).
Sincerely, Lames Mun
/lant Manager - Hope Creek Attachment RFY C
Distribution LER File 3.7
- k
- also 95-2168 REV. 7/99
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSIO APPROVED BY OMB: NO. 3150-0104 EXPIRES: 0613012007 6-2004)
, the NRC may digits/chlaracters for each block) not conduct or sponsor, and a person Is not required to respond to, the
- 3. PAGE Hope Creek Generating Station 05000 354 1 OF 3
- 4. TITLE Potential For Uncontrolled Radiological Release - Reactor Water Clean-up Isolation
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED D
FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR S
EQUENTIAL R
MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 8
29 2004 2004 - 008 -
00 10 27 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(a)(3)(i) 0 50.73(a)(2)(i)(C) 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)(viii)(A)
O 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(vli)(B) 0 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x) o 20.2203(a)(2)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71(a)(4) o 20.2203(a)(2)(iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 98 0 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A)
E 50.73(a)(2)(v)(C) 0 OTHER 0 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B) 0 50.73(a)(2)(v)(D)
Specify In Abstract below nr In NRC. Fnrm RAAA
- 12. LICENSEE CONTACT FOR THIS LER FACILITY NAME TELEPHONE NUMBER (Inchide Area Code)
R. Yewdall, Licensing Engineer 1856-339-2469
- 13. COMPLETE ONE UNE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE
CAUSE
SYSTEM COMPONENT MANU-REPORTABLE FACTUJRER TO EPIX FACTURER TO EPIX X
IJ DET G080 No
- 14. SUPPLEMENTAL REPORT EXPECTED
- 15. EXPECTED MONTH DAY YEAR SUBMISSION 0 YES (If yes, complete 15. EXPECTED SUBMISSION DATE) 0 NO DATE ABSTRACT (Umit to 1400 spaces, Le., approximately 15 single-spaced typewritten lines)
On 08129/04 at 1928 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.33604e-4 months <br />, an alarm was received in the control room indicating the Reactor Water Cleanup (RWCU) high differential flow isolation channel for the outboard RWCU supply isolation valve was inoperable. The alarm was the result of the Leak Detection System (LDS) initiating a system failure signal. At the time, the functional test for the inboard RWCU high differential flow isolation channel was being performed. During the channel functional test, power to the inboard isolation valve was removed to permit continued RWCU system operation while the isolation function was tested. With the outboard isolation actuation channel inoperable and the inboard isolation valve deenergized in the open position, the required isolation function may not have been completed in the event of a break in the RWCU system.
The condition was caused by the coincidental failure of a Nuclear Measurement and Control (NUMAC) analog card and the channel functional test being performed on the other isolation valve. The cause of the NUMAC analog card failure was due to a random component failure. Immediate corrective actions were taken to isolate the RWCU system and restore power to the inboard isolation valve. The NUMAC analog card was replaced. The LDS was successfully tested and declared operable.
This event is being reported in accordance with 1 OCFR50.73 (a) (2) (v) (C), any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.
NRC FORM 366 (6-2004)
- :-U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
FACILITY NAME (1)
DOCKET (2),
LER NUMBER (6)
PAGE (3)
Y SEQUENTAL I REVISION YER NUMBER NUMBER Hope Creek Generating Station 05000354 NU2 OF 3
___1_
2004 008 00 l
TEXT (If more space is required, use additional copies of NRC Form 366A) (17)
PLANT AND SYSTEM IDENTIFICATION
General Electric - Boiling Water Reactor (BWR/4)
Leak Monitoring System {IJ/DET)*
- Energy Industry Identification System {EIIS} codes and component function identifier codes appear as {SS/CCC}
IDENTIFICATION OF OCCURRENCE Event Date: August 29, 2004 Discovery Date: August 29, 2004 CONDITIONS PRIOR TO OCCURRENCE Hope Creek was in Operating Condition 1 (Power Operation), at the time of discovery. At the time of the Nuclear Measurement and Control (NUMAC) analog card failure, the inboard isolation valve was in an open condition with power removed to perform a channel functional test. All required structures, systems or components were operable at the start of this event.
DESCRIPTION OF OCCURRENCE On 08/29/04 at 1928 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.33604e-4 months <br />, an alarm was received in the control room indicating the Reactor Water Cleanup (RWCU) high differential flow isolation channel for the outboard RWCU supply isolation valve was inoperable. The alarm was the result of the Leak Detection System (LDS) {IJ/DET} initiating a system failure signal. At the time, the functional test for the inboard RWCU high differential flow isolation channel was being performed. During the channel functional test, power to the inboard isolation valve was removed to permit continued RWCU system operation while the isolation function was tested. With the outboard isolation actuation channel inoperable and the inboard isolation valve deenergized in the open position, a break in the RWCU system may not have resulted in a required isolation. This condition could have resulted in the unintended release of radioactive material.
The condition was caused by the coincidental failure of a NUMAC analog card and the channel functional test being performed on the other isolation valve. The NUMAC system performs a continuous diagnostic. The cycle of the self-test is approximately one minute. Upon receiving the leak detection system trouble alarm, the RWCU system was removed from service to comply with Technical Specification 3.3.2-1, action 23, which requires closure of the affected isolation valves within one hour.
Corrective maintenance included removal and replacement of the NUMAC card. The system was tested successfully and declared operable. The failure of the component was due to a random failure event.
The Technical Specification was entered as required and the system was returned to operable condition within the allowed outage time.
This event is being reported in accordance with 1 OCFR50.73 (a) (2) (v) (C), any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material.U.S. NUCLEAR REGULATORY COMMISSION (1-2001)
LICENSEE EVENT REPORT (LER)
FACILITY NAME (1)
DOCKET (2)
LER NUMBER (6)
PAGE (3)
SEQUENTIAL REVISION YEAR NUMBER NUMBER Hope Creek Generating Station 05000354 3 OF 3
_1 2004 008 00 lOJ CAUSE Ut-UOCCUKRENC The inability to isolate the RWCU system was caused by the coincidental failure of the NUMAC analog circuit card and the system functional test being performed on the other isolation valve. The cause of the failure of the NUMAC analog card was due to a random component failure on the card.
PREVIOUS OCCURRENCES
A review of LERs for the two prior years at Hope Creek and Salem was performed to determine if similar event had occurred. There were no previous occurrences of this type report during that period.
SAFETY CONSEQUENCES AND IMPLICATIONS
There were no safety consequences associated with this event since there was no unmonitored or unplanned radiological effluent release associated with this event. Operations isolated the RWCU system within one hour from the failure of the NUMAC circuit card.
A review of this event determined that a Safety System Functional Failure (SSFF) as defined in Nuclear Energy Institute (NEI) 99-02 has occurred. With the outboard isolation actuation channel inoperable and the inboard isolation valve deenergized in the open position, a break in the RWCU system may not have resulted in a required isolation. This condition could have resulted in the unintended release of radioactive material.
CORRECTIVE ACTION
Corrective actions included:
Isolated the RWCU system within one hour; Determined that a component in the differential flow monitoring system had failed; Replaced the failed component and performed a system retest; Preventive maintenance for the NUMAC drawers will be established.
COMMITMENTS
This LER contains no commitments.