05000354/LER-2012-006, High Pressure Coolant Injection System Inoperable
| ML12319A412 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/31/2012 |
| From: | Carr E Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N12-0315 LER 12-006-00 | |
| Download: ML12319A412 (5) | |
| 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)(viii)(B) 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 |
| 3542012006R00 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC OCT3 3 2012 1 OCFR50.73 LR-N12-0315 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Hope Creek Generating Station Unit 1 Facility Operating License No. NPF-57 Docket No. 50-354
Subject:
Licensee Event Report 2012-006-00 In accordance with 10 CFR 50.73(a)(2)(v)(D), PSEG Nuclear LLC is submitting Licensee Event Report (LER) Number 2012-006-00, High Pressure Coolant Injection System Inoperable.
Should you have any questions concerning this letter, please contact Mr. Paul Bonnett at (856) 339-1923.
No regulatory commitments are contained in the LER.
Sincerely, Eric S. Carr Plant Manager Hope Creek Generating Station Attachment: Licensee Event Report 2012-006-00
Document Control Desk LR-N12-0315 Page 2 cc:
Mr. W. Dean, Regional Administrator - Region 1 U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Mr. J. Hughey, Project Manager U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 B1A 11555 Rockville Pike Rockville, MD 20852 USNRC Senior Resident Inspector - Hope Creek (X24)
P. Mulligan, Manager Bureau of Nuclear Engineering\\
New Jersey Department of Environmental Protection PO Box 420 Trenton, NJ 08625 Hope Creek Commitment Tracking Coordinator (H02)
INPO - LEREvents@lNPO.org
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013 (10-2010)
, the NRC may sfor each block)inot conduct or sponsor, and a person is not required to respond to, the digits/characters frecblk)information collection.
- 3. PAGE Hope Creek Generating Station 05000354 1 OF3
- 4. TITLE High Pressure Coolant Injection System Inoperable
- 5. EVENT DATE
- 6. LER NUMBER__
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MNH DY YA YERSEQUENTI AL REV MOT A
ER FACILITY NAME DOCKET NUMBER YEAR NUMBER NO.
MONTH DAY YEAR N/A FACILITY NAME DOCKET NUMBER 09 4
2012 2012 - 006 -
000 11 2012 N/A
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
[1 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C)
El 50.73(a)(2)(vii)
El 20.2201(d)
El 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
[I 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
[I 50.73(a)(2)(viii)(B)
El 20.2203(a)(2)(i)
El 50.36(c)(1)(i)(A)
El 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
El 50.36(c)(1)(ii)(A)
El 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x)
El 20.2203(a)(2)(iii)
[] 50.36(c)(2)
[] 50.73(a)(2)(v)(A)
El 73.71(a)(4)
El 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii)
El 50.73(a)(2)(v)(B)
El 73.71(a)(5) 100 [3 20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
El 50.73(a)(2)(v)(C)
[] OTHER [E
20.2203(a)(2)(vi)
El 50.73(a)(2)(i)(B)
Z 50.73(a)(2)(v)(D)
Specify in Abstract below or in
CAUSE OF EVENT
The cause of the event was dirty contacts on the 1 FD-HV-FOO1 motor operator LS-1 1 limit switch that prevented continuity through the contactors. The contacts were cleaned and continuity restored and the HPCI steam admission valve was retested satisfactory.
SAFETY CONSEQUENCES AND IMPLICATIONS
HPCI was declared inoperable because of the failure of the 1 FD-HV-F001 steam admission valve to open on demand. This is a condition that could prevent the fulfillment of a safety function. No other safety systems were inoperable during the HPCI inoperability. Based on the engineering review a Safety System Functional Failure (SSFF) occurred as defined in Nuclear Energy Institute (NEI) 99-02.
PREVIOUS OCCURRENCES
A review of Licensee Event Reports for the past three years at Hope Creek was performed to determine if a similar event had occurred. No similar events were noted for the HPCI steam admission valve.
CORRECTIVE ACTIONS
- 1. A root cause evaluation is being conducted.
- 2. The contacts were cleaned and continuity restored.
- 3. The HPCI steam admission valve (HV-FO01) was retested satisfactorily.
COMMITMENTS
This LER contains no regulatory commitments.
NRC FORM 366 (10-2010)
PRINTED ON RECYCLED PAPER NRC FORM 366 (10-2010)
PRINTED ON RECYCLED PAPER