05000400/LER-2016-007, Regarding Containment Spray System Valve Actuation
| ML16355A325 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/20/2016 |
| From: | Hamilton T Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| HNP-16-118 LER 16-007-00 | |
| Download: ML16355A325 (5) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x) |
| 4002016007R00 - NRC Website | |
text
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December 20, 2016 Serial: HNP-16-118 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63 Subject: Licensee Event Report 2016-007-00 Ladies and Gentlemen:
Tanya M. Hamilton Vice President Harris Nuclear Plant 5413 Shearon Harris Road New Hill, NC 27562-9300 919.362.2502 10 CFR 50.73 Duke Energy Progress, LLC, submits the enclosed Licensee Event Report 2016-007-00 in accordance with 1 O CFR 50. 73 for Shearon Harris Nuclear Power Plant, Unit 1. This report details the actuation of a containment spray system valve that occurred on October 26, 2016, while the site was in a planned refueling outage. The corrective action program evaluation is ongoing and this report will be supplemented following completion of the evaluation.
This document contains no regulatory commitments. Please refer any questions regarding this submittal to Jeff Robertson, Manager - Regulatory Affairs, at (919) 362-3137.
Sincerely, Tanya M. Hamilton Enclosure: Licensee Event Report 2016-007-00 cc:
Mr. C. D. Jones, NRC Sr. Resident Inspector, HNP Ms. M. Barillas, NRC Project Manager, HNP NRC Regional Administrator, Region II
Tanya M. Hamilton Vice President Harris Nuclear Plant 5413 Shearon Harris Road New Hill, NC 27562-9300 919.362.2502 10 CFR 50.73 December 20, 2016 Serial: HNP-16-118 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63 Subject: Licensee Event Report 2016-007-00 Ladies and Gentlemen:
Duke Energy Progress, LLC, submits the enclosed Licensee Event Report 2016-007-00 in accordance with 10 CFR 50.73 for Shearon Harris Nuclear Power Plant, Unit 1. This report details the actuation of a containment spray system valve that occurred on October 26, 2016, while the site was in a planned refueling outage. The corrective action program evaluation is ongoing and this report will be supplemented following completion of the evaluation.
This document contains no regulatory commitments. Please refer any questions regarding this submittal to Jeff Robertson, Manager - Regulatory Affairs, at (919) 362-3137.
Sincerely, Tanya M. Hamilton Enclosure: Licensee Event Report 2016-007-00 cc:
Mr. C. D. Jones, NRC Sr. Resident Inspector, HNP Ms. M. Barillas, NRC Project Manager, HNP NRC Regional Administrator, Region II
LICENSEE EVENT REPORT (LER)
NRC FORM 366 (06-2016)
U.S. NUCLEAR REGULATORY COMMISSION 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 />.
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 Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory 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 number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (See Page 2 for required number of digits/characters for each block) 1 OF
- 3. PAGE 05000
- 4. TITLE
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR SEQUENTIAL NUMBER REV NO.
FACILITY NAME 05000 DOCKET NUMBER FACILITY NAME 05000 DOCKET NUMBER
- 9. OPERATING MODE
- 10. POWER LEVEL
- 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)
- 12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT TELEPHONE NUMBER (Include Area Code) CAUSE SYSTEM COMPONENT MANU-FACTURER REPORTABLE TO EPIX
CAUSE
SYSTEM COMPONENT MANU-FACTURER REPORTABLE TO EPIX
- 14. SUPPLEMENTAL REPORT EXPECTED YES (If yes, complete 15. EXPECTED SUBMISSION DATE)
NO
- 15. EXPECTED SUBMISSION DATE YEAR DAY MONTH ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)
NRC FORM 366 (06-2016)
YEAR YEAR DAY MONTH 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(vii) 20.2203(a)(2)(ii) 20.2203(a)(2)(i) 20.2203(a)(1) 20.2201(d) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(2)(v) 20.2203(a)(2)(vi) 20.2203(a)(3)(ii) 20.2203(a)(4) 50.36(c)(1)(i)(A) 50.36(c)(1)(ii)(A) 50.36(c)(2) 50.46(a)(3)(ii) 50.73(a)(2)(i)(A) 50.73(a)(2)(i)(B) 50.73(a)(2)(ii)(A) 50.73(a)(2)(ii)(B) 50.73(a)(2)(iii) 50.73(a)(2)(iv)(A) 50.73(a)(2)(v)(A) 50.73(a)(2)(v)(B) 50.73(a)(2)(v)(C) 50.73(a)(2)(v)(D) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(ix)(A) 50.73(a)(2)(x) 73.71(a)(4) 73.71(a)(5)
OTHER Specify in Abstract below or in Note: Energy Industry Identification System (EIIS) codes are identified in the text within brackets [ ].
A. Background Event Date: October 26, 2016 Mode: 6 Reactor Power: 0 percent Event Time: 1142 EDT No systems, structures, or components were inoperable at the start of this event that contributed to the event. No change in plant mode or in reactor power occurred as a result of this event. The plant was in mode 6, refueling, with the reactor vessel head removed, reactor cavity water level greater than 23 feet, core reload complete, and the residual heat removal system in operation.
This event is reportable per 10 CFR 50.73(a)(2)(iv)(A) as an event or condition that results in valid actuation of any of the systems listed in paragraph (a)(2)(iv)(B) of [10 CFR 50.73] due to actuation of a valve in the containment spray (CT) system [BE].
The purpose of the CT system is to spray borated sodium hydroxide solution into Containment [NH] to cool the atmosphere and to remove the fission products that may be released into the containment atmosphere following a loss of coolant accident (LOCA) or main steam line break (MSLB). It has two principal modes of operation: 1) the initial injection mode, during which time the system sprays borated water taken from the refueling water storage tank (RWST) [TK], and
- 2) the recirculation mode, which is initiated when low-low level is reached in the RWST. During recirculation mode, the pump suction is transferred from the RWST to the containment sump by opening the containment sump suction valves and closing the valves at the outlet of the RWST. This switchover is accomplished automatically.
B. Event Description
On October 26, 2016, at 1142 EDT, the Shearon Harris Nuclear Power Plant (Harris) was in a planned refueling outage.
Operations was in the process of restoring the CT system following maintenance, with the reactor cavity filled with water and the RWST level less than 23.4 percent. During the CT system restoration, Operations started the 'B' CT pump [P],
which was aligned to the RWST. With RWST level less than 23.4 percent, the logic was satisfied to initiate CT switchover to the containment sump. This caused the containment sump suction valve, 1CT-102 [ISV], to open, establishing a flow-path which allowed water to be transferred from the RWST to the containment sump.
Immediate action was taken by Operations to restore the desired plant configuration. This was achieved by securing the CT pump and re-closing 1CT-102. During the event, the CT system was aligned for recirculation of 'B' CT pump discharge back to the RWST, so no water flowed through the spray header.
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- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
C. Causal Factors The corrective action program evaluation of the event is not yet complete, so final determination of causal factors is still in progress. Once the evaluation is complete, a supplemental report will be issued containing these items. The direct cause of the event was starting the 'B' CT pump with RWST level less than 23.4 percent.
D. Corrective Actions
Completed Actions:
Immediate corrective action to provide just-in-time training for Operations as a refresher on the operation of the spray system switchover actuation logic.
Planned Actions:
Planned actions will be determined following completion of the ongoing corrective action program evaluation. Once the evaluation is complete, a supplemental report will be issued containing these actions.
E. Safety Analysis
The safety significance of this event was minimal, as the condition had no impact on decay heat removal. The event did not affect water inventory in the reactor cavity, and there was no impact on core cooling, which was being performed by the residual heat removal system [BP] at the time of the event. This event did not impact the health and safety of the public.
F. Additional Information
There have been no related events at Harris within the past three years.
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