05000389/LER-1917-001, Regarding Delay in Initiating Immediate Technical Specification Required Action During Fuel Movements
| ML17143A224 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/27/2017 |
| From: | Deboer D Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2017-067 LER 17-001-00 | |
| Download: ML17143A224 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 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)(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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| LER closed by | |
| IR 05000335/2017002 (2 August 2017) | |
| 3891917001R00 - NRC Website | |
text
~.... l April 27,; 2017 U.S. Nuclear Regulatory Commission Attn: Docume.nt Control Desk Washington, D.C. 20555 Re: St. Lucie Unit 2 Docket No. 50-389 L-2017-067 10 CFR 50.73 Reportable Event: 2017-001-00 Date of Event: March 1, 2017 Delay in Initiating Immediate Technical Specification Required Action During Fuel Movements The attached Licensee Event Report 2017-001-00 is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.
Sincerely,
{)~()~
Daniel DeBoer Site Director *,
St. LuCie Plant BO/res Attachment cc:
NRC Region II Administrator.
- ~) _.:. r St. Lucie Plant NRC Senior Resident Inspector Florida Power & Lig~t Company 6501 S. Ocean Drive, Jensen Beach, FL 34957
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ii 11 ii
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (06-2016)
- ~(I'.:
, the NRG may not conduct or sponsor, and a person is not required to I
respond to, the information collection.
- 1. FACILITY NAME I
- 2. DOCKET NUMBER
- 13. PAGE St. Lucie Unit 2 05000389 1OF3
- 4. TITLE Delay in Initiating Immediate Technical Specification Required Action During Fuel Movements
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR I SEQUENTIAL I REV MONTH DAY YEAR FACILITY NAME DOCKET NUMBER NUMBER NO.
NA 03 01 2017 2017 -
001 - 00 04 27 2017 FACILITY NAME DOCKET NUMBER NA
- 9. OPERATING MODE 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply)
D 20.2201 (b)
D 20.2203(a)(3)(il D
50.73(a)(2)(ii)(A)
D 50.73(a)(2)(viii)(A)
Defueled 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 5o.73(a)(2)(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(il D
50.36(c)(1 )(i)(A)
D 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
D 20.2203(a)(2)(iil D
50.36(c)(1)(ii)(A)
D 50.73(a)(2)(v)(A)
D 13.11 (a)(4)
- 10. POWER LEVEL D
20.2203(a)(2)(iiil D
5o.3s(c)(2l D
50.73(a)(2)(v)(B)
D 13.11(a)(5l 0%
D 20.2203(a)(2)(iv)
D 50.46(a)(3)(iil D
50.73(a)(2)(v)(C)
D 13.77(aJ<1>
D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
D 50.73(a)(2)(v)(D)
D
- 73. ncaJ(2l<il D
20.2403(a)(2)(vi)
!XI 50. 73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(al<2l<iil D
50.73(a)(2)(i)(C)
D OTHER Specify in Abstract below or in LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET
- 1. FACILITY NAME St. Lucie Unft 2 I
Safety Significance
. 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 OMS control number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 2. DOCKET
- 6. LER NUMBER 05000389 20~7 -
001 This condition was mitigated by the operator actions implemented immediately upon discovery of the prohibited condition by placing control room ventilation on recirculation. During this period, if there had been a postulated fuel handling accident (FHA) that required isolation of the control room and actuation of filtered recirculation, a concurrent loss of offsite power with a single failure of the 2A Emergency Diesel Generator would have delayed the control room isolation for approximately 25 minutes while alternate power was restored to the motor operated dampers. Operations would also have the option to manually close specific control room ventilation dampers to isolate the control room envelope if appropriate for the priorities of the hypothetical scenario.
The analyses-that limit the radiation exposure to operators in the control room are very conservative for the postulated FHA and assume the radioactive release has no dilution as it is transported from the fuel handling building (FHB) to the control room. Additionally, the control room personnel have protection from factors that are not credited in the analyses that limit the radiation exposure to operators in the control room. These are:
The FHB is maintained at negative pressure. This would slow radioactive release from the FHB during the postulated FHA.
The control room is maintained at a positive pressure. If the control room is unable to go on recirculation, it will take additional time for the positive pressure to escape the control room envelope before a release from the FHB could be transported into the control room by atmospheric winds.
The release from the FHA is assumed to have no dilution as it is transported to the control room. However; atmospheric winds that could overcome the negative pressure of the FHB in order to draw out the release and to force it into the control room, would provide significant dilution.
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This event included no automatic actuations or equipment performance issues. This event had no impact to onsite personnel, and the health and safety of the public were not affected by this event.
Corrective Actions
- 1. Procedure instructions were revised to provide additional instructions for the coordination of fuel handling activities to check each shift to ensure specific prerequisites are met and to confirm permission has been obtained frorn_,the Unit Supervisor to move irradiated fuel.
I Previous Occurrence A review of previous events for the past three years identified no similar events.
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