05000354/LER-2012-003, Regarding Operation with the Potential to Drain the Reactor Vessel
| ML12151A409 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/14/2012 |
| From: | Doris Lewis Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N12-0150 LER 12-003-00 | |
| Download: ML12151A409 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 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)(v), Loss of Safety Function |
| 3542012003R00 - NRC Website | |
text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC MAY 1 42012 LR-N 12-0150 1 0CFR50.73 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 2012-003 In accordance with 10 CFR 50.73(a)(2)(i)(B), PSEG Nuclear LLC is submitting Licensee Event Report (LER) Number 2012-003.
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, David P. Lewis Plant Manager Hope Creek Generating Station Attachment: Licensee Event Report 2012-003
Page 2 LR-N12-0150 Document Control Desk cc:
Mr. W. Dean, Regional Administrator - Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 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)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013
, the NRC may nfor each block)inot conduct or sponsor, and a person is not required to respond to, the digits/characters
)information collection.
- 3. PAGE Hope Creek Generating Station 05000354 1 OF3
- 4. TITLE Operation with the Potential to Drain the Reactor Vessel
- 5. EVENT DATE
- 6. LER NUMBER__
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL REV ONTH FACILITY NAME DOCKET NUMBER NUMBER NO.
MN/A FACILITY NAME DOCKET NUMBER 04 22 2012 2012 - 003 - 000 05 14 2012 N/A
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
El 20.2201(b)
El 20.2203(a)(3)(i)
[I 50.73(a)(2)(i)(C)
[E 50.73(a)(2)(vii) 5 20.2201(d)
El 20.2203(a)(3)(ii)
E] 50.73(a)(2)(ii)(A)
El 50.73(a)(2)(viii)(A)
El 20.2203(a)(1)
[] 20.2203(a)(4)
C] 50.73(a)(2)(ii)(B)
El 50.73(a)(2)(viii)(B)
_ 20.2203(a)(2)(i)
[] 50.36(c)(1)(i)(A)
[I 50.73(a)(2)(iii)
[] 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL
[: 20.2203(a)(2)(ii)
[E 50.36(c)(1)(ii)(A)
E] 50.73(a)(2)(iv)(A)
E] 50.73(a)(2)(x)
[1 20.2203(a)(2)(iii)
[:l 50.36(c)(2)
[I 50.73(a)(2)(v)(A)
El73.71 (a)(4)
E] 20.2203(a)(2)(iv)
[] 50.46(a)(3)(ii)
[I 50.73(a)(2)(v)(B)
El 73.71(a)(5) 000 [E
20.2203(a)(2)(v)
El 50.73(a)(2)(i)(A)
[E 50.73(a)(2)(v)(C)
[] OTHER [E 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)
[E 50.73(a)(2)(v)(D)
Specify in Abstract below or in siphoning the RPV water level below the top of the fuel, without taking credit for mitigating measures, would be an OPDRV activity.
In order to utilize the EGM and be eligible for enforcement discretion, the licensee is required to:
(1) adhere to the NRC plain language meaning of OPDRV activities, (2) meet the requirements which specify the minimum makeup flow rate and water inventory based on OPDRV activities with long drain down times, (3) ensure that adequate defense in depth is maintained to minimize the potential for the release of fission products by monitoring RPV level to identify the onset of a loss of inventory event, by maintaining the capability to isolate the potential leakage paths, by prohibiting Mode 4 (cold shutdown) OPDRV activities and by prohibiting movement of irradiated fuel, and (4) ensure that licensees follow all other Mode 5 TS requirements for OPDRV activities.
CAUSE OF EVENT
Outage Management, Operations, and Outage Coordinators responsible for evaluating outage work activities determined that the scheduled replacement of eight LPRM strings without setting secondary containment was within the acceptance criteria of the EGM.
SAFETY CONSEQUENCES AND IMPLICATIONS
There were no safety consequences during this OPDRV activity. The OPDRV activity was evaluated and determined the extended time to drain down the RPV to the top of the RPV flange was calculated to be 102.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, which is greater than the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> stated in the EGM. Hope Creek met all EGM criteria to be eligible for enforcement discretion. Irradiated fuel movements were prohibited. The 'C' residual heat removal (RHR) pump was the standby source of makeup designated for this evolution. The contingency plan was to use an incore housing plug to seal the opening (LPRM) should difficulty arise in replacement activities. This plug was staged on the refuel bridge with directions for installation. The refuel bridge crew was briefed on its use.
Procedure OP-HC-1 08-102, "Management of Operations with the Potential to Drain the Reactor Vessel" was in use. Secondary containment was not operable, but was able to be made vapor tight within 30 minutes.
A review of this event determined that a Safety System Functional Failure (SSFF) did not occur 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.
CORRECTIVE ACTIONS
None
COMMITMENTS
This LER contains no regulatory commitments.
NRC FORM 366 (10-2010)
PRINTED ON RECYCLED PAPER