05000261/LER-1917-001, Regarding Auxiliary Feedwater System Actuation During Surveillance Testing
| ML17152A326 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 06/01/2017 |
| From: | Kapopoulos E Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RNP-RA/17-0040 LER 17-001-00 | |
| Download: ML17152A326 (5) | |
| 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)(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)(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) |
| 2611917001R00 - NRC Website | |
text
(_~ DUKE ENERGY Serial: RNP-RA/17-0040 JUN 01 2017 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 H. 8. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 LICENSEE EVENT REPORT NO. 2017-001-00:
Ernest J. Kapopoulos, Jr.
H. B. Robinson Steam Electric Plant, Unit 2 Site Vice President Duke Energy 3581 West Entrance Road Hartsville, SC 29550 0 : 843 857 1701 F: 843 857 1319 Ernie.Kapopoulos@duke-energy.com 10 CFR 50.73 AUXILIARY FEEDWATER SYSTEM ACTUATION DURING SURVEILLANCE TESTING Ladies and Gentlemen:
Pursuant to 10 CFR 50.73, Duke Energy is submitting the attached Licensee Event Report.
Please direct any questions regarding this submittal to Mr. Tony Pila, Manager - Nuclear Regulatory Affairs at (843) 857-1409.
This document contains no new regulatory commitments.
Ernest J. Kapopoulos, Jr.
Site Vice President EJK/jmw Attachment c:
Region Administrator, NRC, Region II NRC Resident Inspector, HBRSEP D. Galvin, NRA
United States Nuclear Regulatory Commission Attachment to Serial: RNP-RA/17-0040 4 Pages (including this page)
H.B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AUXILIARY FEEDWATER SYSTEM ACTUATION DURING SURVEILLANCE TESTING
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3160-0104 EXPIRES: 03/31/2020 (04-2017)
!ll!J;!://www.nrc.gov/re,ading-rm/doc-colle,ctionl!/nure.gs/s!;.1ff/sr1 Q221r3{)
the NRG may not conduct or sponsor, and a person is not required to respond ID, the information collection.
- 3. PAGE H. B. Robinson Steam Electric Plant, Unit No. 2 05000 261 1 OF 3
- 4. TITLE Auxiliary Feedwater System Actuation During Surveillance Testing
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED I
SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NO.
MONTH DAY YEAR NA 05000 FACILITY NAME DOCKET NUMBER 04 03 2017 2017 -
001 -
00 06 02 2017 NA 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 50.73(a)(2)(viii)(A) 3 D 20.2201(d)
D 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B)
D 20.2203(a)(1)
D 20.2203(a)(4>
D so.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) 0 50.73(a)(2)(x)
- 10. POWER LEVEL D 20.2203(a)(2)(ii>
D 50.36(c)(1)(ii)(A) 0 50.73(a)(2)(v)(A)
D 73.71(a)(4>
D 20.2203(a)(2)(iii)
D so.3s(c)(2>
D 50.73(a)(2)(v)(B)
D 73.71(a)(s)
D 20.2203(a)(2)(iv)
D so.4s(a)(3)(ii) 0 50.73(a)(2)(v)(C)
D 73.77(a)(1) 000 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) 0 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)
D OTHER Specify In Abstract below or in
CORRECTIVE ACTIONS
Completed:
- 1. MST-551 was suspended.
- 2. 'B' MFW pump was restarted.
- 3. AFW pumps were secured.
- 4. BOP operator was relieved of his licensed operator duties and submitted to post-event testing.
- 5. The BOP operator received a formal remedial training package on procedure adherence.
SAFETY ANALYSIS
The actuation of the AFW system during surveillance testing was valid, and the system responded to plant conditions as designed. There is no safety consequence as a result of this event. The cause was attributed to inadequate procedure adherence and not due to any equipment failures. This event resulted in no impact to the health and safety of the public.
ADDITIONAL INFORMATION
An operating experience (OE) search was conducted and there is one prior event at HBRSEP2 involving inadvertent actuation of the AFW system within the past three years. This actuation was due to inadequate procedural guidance rather than inadequate procedure adherence, and was reported via LER 2016-005-01.
Energy Industry Identification System (EllS) codes for systems and components relevant to this event are identified in the text of this document within brackets [ ]. Page 3
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