05000219/LER-2018-001, EMRV Pressure Sensor As-Found Setting Exceeded Limiting Safety System Settings
| ML18220A877 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/31/2018 |
| From: | Gillin M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-18-074 LER 2018-001-00 | |
| Download: ML18220A877 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 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)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) |
| 2192018001R00 - NRC Website | |
text
RA-18-074 July 31, 2018 U.S. Nuclear Regulatory Commission Attn: Document Control Desk or 0-8B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 NRG Docket No. 50-219 Oyster Creek 741 Route 9 South Forked River, NJ 08731 10 CFR 50.73
Subject:
Licensee Event Report (LEA) 2018-001-00, "EMRV Pressure Sensor As-Found Setting Exceeded Limiting Safety System Settings" Enclosed Is LER ~018-001-00 reporting the as-found calibration setting of me 11A" EMRV Pressure Sensor exceeding the Limiting Safety System Settings setpoint requirement.
This event did not affect the health and safety of the public or plant personnel. This event did not result in a safety system functional failure. There are no regulatory commitments made in this LER submittal.
Should you have any questions concerning this report, please contact Gary Flesher, Regulatory Assurance Manager, at (609} 971-4232.
Respectfully, Michael F. Gillin Plant Manager Oyster Creek Nuclear Generating Station Enclosure: NRG Form 366, LEA 2018-001-00 cc:
Administrator, NRG Region I NRG Senior Resident Inspector - Oyster Creek Nuclear Generating Station NRG Project Manager - Oyster Creek Nuclear Generating Station
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- 1. Facility Name
- 2. Docket Number 3.Page Oyster Creek Nuclear Generating Station 05000.;.219,.
1 OF 3
- 4. Title EMRV Pressure Sensor As-Found Setting Exc::eeded Limiting Safety System Settings
_5._Elient Date
- 6. LER Number
- 7. Report Date,
- 8. Olher FaclUties Involved.
I Sequentilll I Rev FaclrltyName DockGINwnbor Month Day
- .. Year
- . Year Mon111 Dlly Year NIA
- 05000 N.ilmber No.
06 05 2018
.2018 31 2018 Faclf~Name Dookol Numbor 001 *,
- - 00 07 NIA
- -05000
- 9. Operating Mode
- 11. This Report is Submitted Pursuantto the Requirements of 10 CFR §: (Checkall thst apply}
D 20.2201
D
- 20.220aca1<a>ci>
0 50.73(a)(2)(ii)(A)
D 5().73(a><2>C~iiil(Al N
D 20,2201<d)
D 20:2203(a)<3>(ii}.
- D
- 5!).73(a)(2)(ii1(B),
D so.1acai<21(vru}(B>
D 20.22oa<aic1i -
D 20.2203(a)<4>
0 50;73(a)(2)(iii) 0 50.73(a)(2)(ix)(A) 0 20.2203(a)(2)(i) 0 50.36(c)(1}(i)(A)
, 0 50.73(a)(2)(iv)(A)
D 50.73(a)(2)(x)
- 10. Power.Level D 20.22oa<a112>(ii>
18J. 50.36(c)(1)(ii)(A).
0 50.73(a)(2)(v)(A)
D 1a.11ca><4>
r 0 20.2203(a)(2)(iii)
D so.as<c1c21 O* 50.73(a)(2)(v)(B) 0 73.71(a)(5) 0 20.22Q3(a)(2)(iv)
D
- so_4sca><a1<ii).
0 50.7a(a)(2)(v)(C) 0 7a,i7(a)(1) ---
100 0 20.ffll3(a)(2iM.
0 50,7'J(s)(2}(i)<A)
D S0.73(n)(2)(v){D)
D n.n,a)la)ti}
D 20.22oa(a1c2><vi>
~
50.73(a)(2)(i)(B).
- [] 50.73(a)~)(vii)
D. ia'.n(a)(2)(iil D 50.73(a)(2)(i)(C) 0 Other (Specify in Abstract below or in.
~
- 2. DOCKET NUMBER
. 05000-219
. YEAR.
2018 -
- 3. LER NUMBER.
SEQUENTIAL.
- NUMBER**
001 REV NO.
00
Cause of Event
The cause *otthis occurrence is instrument drift above theLSSS limit. This has notoccurred since the last LEA on.
EMRV seitpoirit drift in 1994.. A review of sun,eiflance trend data shows no degrading trend in performance of the.**
. switch beyond normal drift in band. _A review of surveill_ance data since.installation of the subject switchqn 10/27/15 shows.that no as-found setpoint*adjustments have been*requlred during any of the tests...
Corrective Actions
The subject instrument setpoint was adjusted*within the as-left surveillance tolerance band, and successfully tested;
Assessment of Safety Consequences
- Th.is occurrence is considered to have minimal safety significance as: 1) Staggered EM RV initiation is conservative.
After implementation of the modifications related to the Mark 1 Containment Long Term Program,.EMRV staggering was no longer necessary since the supporting*stnictural analyses assumed that all five EMRVs opened at 1105psig..
- The subject "A" EMRVpressure switch as-found setpoint (1095 psig) ls bounded by these analyses; 2) the ADS. *
- function of the EM RVs is not affected by this pressure switch, therefore, all five EM RVs would have actuated to relieve pressure; 3)the Isolation Condenser System and turbine bypass valves were fully operable; 4) rnanual.
. operation of the EMRVs was not affected; an.d 5) the reactor safety valves are designed to prevent reaching the*.
Reactor Coolant System pressure safety limitof 1375_ psig on a complete loss of EMRV relief capability~
Previous Occurrences
LER 81-40
- LER 81-57 Reactor High Pressure Switch "B".EMRV...*.
LER 82-24
.. EMRY Switch out of Technical Specification Limit
. LER 90-1 o EMRV High Pressure Relief Setpoints Exceed Technical Specification Limit Due to.Drift
.. LER 92-12 EMRV High Pressu.re Relief Setpoints Exceed Technical Specification Limit Pue* to. Pritt
- LER 9+08.
EMRV Setpoints Exceed Tech Spec limits Due to Drift LEA 9+ 12 -EMRVHigh -Pressure Relief Setpoints Exceed Technical Specification Limit Due to Driff.
Component Data Component
. Pressure Switch IEEE 805 System ID SB IEEE.803A Comporierit PS Page...L. of _3_