05000237/LER-2016-004, Regarding Reactor Building Differential Pressure Less than Technical Specification Requirement
| ML17010A281 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/09/2017 |
| From: | Karaba P Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 17-0001 LER 16-004-00 | |
| Download: ML17010A281 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 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)(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) |
| 2372016004R00 - NRC Website | |
text
Exelon Generation SVPLTR # 17-0001 January 9, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 2 Renewed Facility Operating License Nos. DPR-19 NRG Docket No. 50-237 Dresden Generating Station 6500 North Dresden Road Morris, IL 60450 www.exeloncorp.com 10 CFR 50.73
Subject:
Licensee Event Report 237/2016-004-00, Reactor Building Differential Pressure Less than Technical Specification Requirement Enclosed is Licensee Event Report 237/2016-004-00, "Reactor Building Differential Pressure Less than Technical Specification Requirement." This report describes events which are being reported in accordance with 1 O CFR 50.73(a)(2)(v)(C), "Any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material."
There are no regulatory commitments contained in this submittal.
Should you have any questions concerning this letter, please contact Mr. Bruce Franzen at (815) 416-2800.
Respectfully, Peter J Karaba Site Vice President Dresden Nuclear Power Station Enclosure Licensee Event Report 237/2016-004-00 cc:
Regional Administrator - NRG Region Ill NRG Senior Resident Inspector-Dresden Nuclear Power Station
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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Reported lessons learned are incorporated into the licensing process and fed back to industry.
f LICENSEE EVENT REPORT (LER)
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
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- 3. PAGE Dresden Nuclear Power Station, Unit 2 05000237 1 OF 3
- 4. TITLE Reactor Building Differential Pressure Less than Technical Specification Requirement
- 5. EVENT DATE
- 6. LEA 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 08 2016 2016 - 004
- - 00 01 09 17 05000
- 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)(i)
D 50.73(a)(2)(ii)(A)
D 50.7S(a)(2)(viii)(A) 1 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 l D 20.2203(a)(4)
D so.13(a)(2)(iii)
D 50.73(a)(2)(ix)(A)
D 20.2203(a)(2)(i)
D 50.36(c)(1)(i)(A)
D 50.73(a)(2)(iv)(A)
D ?0.73(a)(2)(x) 1 O. POWER LEVEL D 20.2203(a)(2)(ii)
D 50.36(c)(1)(ii)(A)
D 50.73(a)(2)(v)(A)
D 13.11(a)(4)
D 20.2203(a)(2)(iii)
D so.36(c)(2)
D 50.73(a)(2)(v)(B)
D 13.11 (a)(s>
D 20.2203(a)(2)(iv)
D so.46(a)(3)(ii) 1:8] 50.73(a)(2)(v)(C)
D 13.77(a)(1) 100 D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
D 50.73(a)(2)(v)(D)
D 13.77(a)(2)(i)
D 20.2203(a)(2)(vi)
D 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 13.11(a)(2)(ii)
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D 50.73(a)(2)(i)(C)
D OTHER Specify in Abstract below or in D.
Safety Analysis
YEAR 2016 -
- 3. LEA NUMBER SEQUENTIAL NUMBER 004 The safety significance of this event was low as it did not adversely impact the health and safety of the public. During the evolution, the differential pressure of the RB remained negative relative to the outside at all times. Additionally, there was no release, or potential for release, of radioactive material during the 22 minutes in TS LCO 3.6.4.1 Condition A.
E.
Corrective Actions
The Unit 2 RB Equipment Access Outer door seals were replaced, and work has been scheduled to improve door operation. This issue will be reviewed to determine if changes to the surveillance testing procedures are appropriate given the potential impact of the open interlock door. Additionally, procedures will be revised to require communication of seal inspection results for documentation in Operator Logs.
F.
Previous Occurrences
On 1"2/15/15, Operations secured RB Ventilation for Unit 2 and RB differential pressure degraded rapidly due to the 3C exhaust fan vortex damper failing to open as expected which impacted secondary containment.
On 9/5/15, a failure of the latches on an access hatch resulted in reduction of RB Ventilation exhaust flow and subsequent loss of secondary containment.
G.
Component Failure Data
Manufacturer Model S/N Type N/A N/A N/A Door REV NO.
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