05000354/LER-2016-005, Regarding Reactor Protection System Actuation While the Reactor Was Shutdown
| ML17004A310 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 01/04/2017 |
| From: | Casulli E Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N16-0239 LER 16-005-00 | |
| Download: ML17004A310 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 3542016005R00 - NRC Website | |
text
PSEG Nuclear LLC P.0. Box 236, Hancocks Bridge, New Jersey 08038-0236 LR-N 16-0239 JAN 0 4 2017 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Hope Creek Generating Station Unit 1 I>SEG Nu,cleaT LLC 10CFR50.73 Renewed Facility Operating License No. NPF-57 Docket No. 50-354
Subject:
Licensee Event Report 2016-005-00, Reactor Protection System Actuation While the Reactor Was Shutdown In accordance with the requirements of 10 CFR 50.73(a)(2)(iv)(A), PSEG Nuclear LLC is submitting the enclosed Licensee Event Report (LER) Number 2016-005-00, "Reactor Protection System Actuation While the Reactor Was Shutdown."
If you have any questions or require additional information, please contact Mr. Thomas MacEwen at (856) 339-1097.
There are no regulatory commitments contained in this letter.
Sincerely, Edward T. Casulli Plant Manager Hope Creek Generating Station ttm Attachment: Licensee Event Report 2016-005-00
LR-N16-0239 Page 2 Document Control Desk cc:
Mr. Daniel Dorman, Regional Administrator-Region I, NRC Ms. Carleen Parker, Project Manager-US NRC 10CFR50.73 Mr. Justin Hawkins, NRC Senior Resident Inspector-Hope Creek (X24)
Mr. Patrick Mulligan, Manager IV, NJBNE Mr. Thomas MacEwen, Hope Creek Commitment Tracking Coordinator (H02)
Mr. Lee Marabella-Corporate Commitment Tracking Coordinator (N21)
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (06-2016)
Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
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LICENSEE EVENT REPORT (LER)
Reported lessons learned are incorporated into the licensing process and fed back to industry.
Send comments regarding burden estimate to the FOIA, Privacy and Information Collections (See Page 2 for required number of digits/characters for each block)
Branch (T*5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail
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to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory (See NUREG-1 022, R.3 for instruction and guidance for completing this form Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control httg :/ /www. nrc. gov/readi ng-rm/doc-collections/nu regs/staff/sr1 022/r3/)
number, the NRC may not conduct or sponsor, and a person Is not required to respond to, the information collection,
- 13. PAGE Hope Creek Generating Station 05000354 1 OF 3
- 4. TITLE Reactor Protection S stem Actuation While the Reactor Was Shutdown
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED YEAR I SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.
MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 11 5
2016 2016
- - 005
- - 00 1
~
2017 05000
- 9. OPERATING MODE
- 11. THIS REPORT IS SUBMITIED PURSUANT TO THE REQUIREMENTS OF 10 CFR §:(Check all that apply) 4-Cold Shutdown D 20.2201(b)
D 20.2203(a)(3)(i)
D 50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A)
D 20.2201(d)
D 20.2203(a)(3)(ii)
D 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B)
D 20.2203(a)(1)
D 20.2203(a)(4)
D 50.73(a)(2)(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(i)
D 50.36(c)(1)(i)(A) 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. POWER LEVEL D 20.2203(a)(2)(ii)
D 50.36(c)(1)(ii)(A)
D 50.73(a)(2)(v)(A)
D 73.71(a)(4)
D 20.2203(a)(2)(iii)
D 50.36(c)(2)
D 50.73(a)(2)(v)(B)
D 73.71(a)(5) 0%
D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 73.77(a)(1)
D 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B) 0 50.73(a)(2)(vii)
D 73.77(a)(2)(ii) 0 50.73(a)(2)(i)(C) 0 OTHER Specify in Abstract below or in
CAUSE OF EVENT
The cause the event was personnel error associated with partial procedure use. A causal evaluation is in progress. A supplement to this LER will be submitted to provide the results of the investigation.
SAFETY CONSEQUENCES AND IMPLICATIONS
There were no adverse safety consequences as a result of this event. The RRCS/ARI and RPS actuation did not cause any required systems to become inoperable or any design limits to be exceeded. The RRCS is not required to be operable in Operational Condition 4. The SDV high level trip is not required to be operable in Operational Condition 4.
All plant systems responded as designed. The reactor water cleanup (RWCU) {CE} system remained in service, providing decay heat removal, as planned, during the pressure test window.
SAFETY SYSTEM FUNCTIONAL FAILURE A review of this condition and the associated evaluations determined that a Safety System Functional Failure (SSFF) as defined in Nuclear Energy Institute (NEI) 99-02, "Regulatory Assessment Performance Indicator Guideline," did not occur.
PREVIOUS EVENTS A review of events for the past three years at Hope Creek was performed to determine if similar events had occurred.
On September 28, 2015, a human error resulted in an RRCS/ARI actuation and subsequent RPS actuation with the reactor at 100 percent power. This was reported in LER 2015-005. That event involved a personnel error that was associated with incorrect keypad entries during testing on the RRCS system. The causal evaluation will review similarities to that event.
CORRECTIVE ACTIONS
The individual involved in the event was disqualified from performing this and similar duties pending remediation.
Other corrective actions will be determined following the completion of the causal evaluation.
COMMITMENTS
There are no regulatory commitments contained in this LER. Page 3 of 3