05000461/LER-2019-004-01, Safety Relief Valve Wiring Issue Results in Condition Prohibited by Technical Specifications
| ML20031D058 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 01/29/2020 |
| From: | Chalmers T Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| SRRS 5A.108, U-604530 LER 2019-004-01 | |
| Download: ML20031D058 (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)(viii)(B) 10 CFR 50.73(a)(2)(iii) 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) |
| 4612019004R01 - NRC Website | |
text
Clinton Power Station 8401 Power Road Clinton, IL 61727 U-604530 January 29, 2020 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Clinton Power Station, Unit 1 Facility Opemting License No. NPF-62 NRC Docket No. 50-461 Subject: Licensee Event Report 2019-004-01 10 CFR 50.73 SRRS 5A.108 Enclosed is Licensee Event Report (LER) 2019-004-01: Safety Relief Valve Wiring Issue Results in Condition Prohibited by Technical Specifications. This report is being submitted in accordance with the requirements of 1 O CFR 50.73.
There are no regulatory commitments contained in this report.
Should you have any questions concerning this report, please contact Mr. Dale Shelton, Regulatory Assurance Manager, at (217) 937-2800.
Respectfully, Thomas D. C mers Site Vice President Clinton Power Station
Attachment:
Licensee Event Report 2019-004-01 cc:
Regional Administrator - Region Ill NRC Senior Resident Inspector - Clinton Power Station NRC Project Manager, NRR - Clinton Power Station Office of Nuclear Facility Safety - Illinois Emergency Management Agency
NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
, the NRG may not conduct or sponsor, and a person
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is not required to respond to, the information collection.
3.Page Clinton Power Station, Unit 1 05000461 1
OF 3
- 4. Title Safety Relief Valve Wiring Issue Results in Condition Prohibited by Technical Specifications
- 5. Event Date
- 6. LEA Number
- 7. Report Date
- 8. Other Facilities Involved I
Sequential I Rev Facility Name Docket Number Month Day Vear Vear Number No.
Month Day Vear 05000 Facility Name Docket Number 10 02 2019 2019 -
004 01 01 29 2020 05000
- 9. Operating Mode
- 11. This Report is Submitted Pursuant to the Requirements of 1 O 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)
D 20.2201(d)
D 20.2203(a)(3)(ii)
D 50.73(a)(2)(ii)(B)
D 50.73(a)(2)(viii)(B) 5 D
D D
D 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(iii) 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 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)
D 20.2203(a)(2)(iv)
D 50.46(a)(3)(ii)
D 50.73(a)(2)(v)(C)
D 13.77(a)(1J 000 D 20.2203(a)(2)(v)
D 50.73(a)(2)(i)(A)
D 50.73(a)(2)(v)(D)
D 73.77(a)(2)(i)
D 20.2203(a)(2)(vi)
~ 50.73(a)(2)(i)(B)
D 50.73(a)(2)(vii)
D 73.77(a)(2)(ii)
-*: /*~:r. :
- , /J °;l'
" D 50.73(a)(2)(i)(C)
D Other (Specify in Abstract below or in D.
"Safety Consequences SRV 1 B21-F051 B has a Safety/Relief (S/R) function and a Low-Low Set (LLS) function. SRV 1 B21-F041 B has an S/R function and an Automatic Depressurization System (ADS) function. The LLS Relief Function is armed upon relief actuation of an S/R valve and will cause a greater magnitude blowdown (in the relief mode) for specified S/R valves and a subsequent cycling of a single LLS valve. The LLS and S/R functions were not affected by this condition. However, due to accumulator volume design requirements for the ADS SRV, this condition rendered the ADS function for SRV 1 B21-F041 B inoperable since May 2017. As a result, Technical Specifications Limiting Condition for Operation 3.5.1, Emergency Core Cooling System - Operating, Action E (One ADS valve inoperable), which requires an inoperable ADS valve be restored within 14 days, was not met.
Therefore, the condition described in this Licensee Event Report (LER) is reportable under 1 O CFR 50.73(a)(2)(i)(B), any operation or condition which was prohibited by the plant's Technical Specifications.
E.
Corrective Actions
(1) The Division 1 SRV 1 B21-F041 Band SRV 1 B21-F051 B wiring was corrected and a post-maintenance test completed.
(2) Work orders instructions will be revised to add this event as operating experience and for SRV de-termination/re-termination steps to incorporate more robust verificp.tion practices, including defined scope on wiring designators.
(3) Operations personnel will create and place SRV Equipment Identification Number (EIN) signage during the next refueling outage to eliminate the need for craft and operators to rely on conduit numbers to identify SRVs.
F.
Previous Similar Occurrences There were no previous events identified involving miswiring of components similar to the condition described in this LER.
G.
Component Failure Data
Not applicable. Page _3_ of _3_