ML15159B052

Oyster Creek - Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Reports - January 1, 2013 Through December 31, 2014

ML15159B052
Person / Time
Site:	Oyster Creek
Issue date:	05/26/2015
From:	Stathes G L Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-15-042
Download: ML15159B052 (6)

Text

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S10 CFR 50.59S10 CFR 72.48RA-15-042 May 26, 2015U.S. Nuclear Regulatory Commission Attn: Document Control DeskWashington, DC 20555-0001 Oyster Creek Nuclear Generating StationRenewed Facility Operating Ucense No. DPR-16NRC Docket No. 50-219

Subject:

Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Reports -January 1, 2013 through December 31, 2014Enclosed are the Oyster Creek Nuclear Generating Station 10 CFR 50.59 and 10 CFR 72.48Change Summary Reports for regulatory commitments changed during the period of January 1,2013 through December 31, 2014.There are no regulatory commitments contained In this submittal.

Please contact Thomas Cappuccino at (609) 971-4430 if any further Information or assistance isneeded.Sincerely,

amy Ll tas(Vice President Oyster Creek Nuclear Generating StationEnclosure cc: Administrator, USNRC Region IUSNRC Senior Project Manager, Oyster CreekUSNRC Senior Resident Inspector, Oyster Creek Enclosure

-RA- 15-xxPage 1 of 5Exelon Generation

Company, LLCOyster Creek Nuclear Generating StationEnclosumre to RA-15-42Docket No. 50-2192013- 2014Biennial 10 CFP 60.6t and -10 CFR 72A9 Chang Summary ReportsThese summary reports are issued pursuant to reporting requirements for Oyster CreekNuclear Generating Station (OCNGS).

These reports address tests, experiments, andchanges to the facility and/or procedures as they are described In the Final SafetyAnalysis Report for the OCNGS station and the Final Safety Analysis Report for theStandardized NUHOMS Horizontal Modular Storage System (TN-618T Spent Fuel Caskat OCNGS). These reports summarize the three (3) tests, experiments, and changesthat were implemented between January 1, 2013 and December 31, 2014 under 10 CFR50.59. There were no tests, experiments, or changes Implemented by OCNGS under 10CFR 72.48.... J Enclosure

-RA-15.xxPage 2 of 5Item # 1Evaluation Number: OC-2013-E-0001, Rev.0PORC Review Meeting No. (Date):.

13-08(08/30/13)

Activity/Document No.: Temporary Modification

/ ECR # 13-00378, Rev.0Title: Trunnion Room Temperature Main Steam Une Isolation Description of ActlvftyECR OC 13-00378 allows Operations to install a jumper across three of the fourtemperature switches in any one of four Reactor Protection System (RPS) hightemperature isolation circuits.

This Is a temporary jumper that is Installed as acompensatory measure to reduce the challenges with regard to spurious Isolations.

Thistemporary jumper Is to be removed after repairs have been made to restore the systemto its design condition no later than 1 R25.Reason for Activity:

RPS 1 and 2 have been experiencing spurious half scram isolations due to anIntermittent ground In one of the main steam line temperature sensors which are locatedIn the Condenser Bay. Steam leaks in the Condenser Bay. are beleved to be the causeof the intermittent grounding.

Therefore, the purpose of the jumper Is to prevent spuriousinitiation of the affected RPS sub-channel.of Activity:

Implementing ECR OC 13-00378 protects against a full reactor scram dueto simultaneous spurious half Isolations In RPS I and RPS 2 TrunnionRoom high temperature isolation circuits.

Im ECR OC 13-00378does not prevent a full reactor scram If valid trip signals are received on theTrunnion Room high temperature circuits.

Implementing ECR OC 13-00378does not have any Impact on any plant design basis or safety analysis asdescribed in the UFSAR.Summary of Conclusion for the Activity's 0.S9 Review:Implementing ECR OC 13-00378 does not result In more than a minimal Increase In thefrequency of an occurrence of an accident previously evaluated In the UFSAR, nor doesit result In more than a minimal increase In the likelihood of occurrence of a malfunction of an SSC Important to safety previously evaluated in-the UFSAR. Implementing ECR OC 13-00378 does not result in more than a minimal increase In the consequences of an accident previously evaluated In the UFSAR, nor does it result In more than aminimal increase.

In the consequences of a malfunction of an SSC important to safetypreviously evaluated in the UFSAR. Implementing ECR OC 13-00378 does not createthe popsibllity for an accident of a different type than any previously evaluated In theUFSAR, nor does it create a possibility for a malfunction of an SSC important to safetywith a different result than any previously evaluated in the UFSAR. Implementing ECROC 13-00378 does not result in a design basis limit for a fission product barrier asdescribed In the UFSAR being exceeded or altered.

Implementing ECR OC 13-00378 Ernclosure

-. RA-15-xxPage 3 of 5does not result in a departure from a method of evaluation described in the UFSAR usedin establishing the design bases or in the safety analyses for Oyster Creek.Therefore, NRC approval Is not required prior to Implementing ECR OC 13-00378.

Iftem # 2Evaluation Number:.

OC-2013-EO0002' Rev.0PORC Review Meeting No. (Dale): 13-10 (0023/13)

Actlvlty/lDocument No.: Temporary Modification I ECR # 13-00378, Rev.2Title: TCCP to Jumper Out TS-IBOO1OE and TS.IB001OF Description of AetW.yThis activity Is a Temporary Configuration Change Package (TCCP) to jumper outtemperature switches TS IB001OE, MSL TUNNEL HI TEMPERATURE SWITCHCLOSES MSIV'S, and TS-IBOO1OF, MSL TUNNEL HI TEMPERATURE SWITCHCLOSES MSIV'S. The field wires in the switch housings will be lifted and connected

together, effectively jumpering out each temperature switch.TS-IBO01DE and T&-IBOO1OF are described In the UFSAR, in the attached 50.59Screening, and in the attached

$0.59 Evaluation as *Trunnion Room High Temperature" switches.

Both switches are located In the Main Steam Line Tunnel In the Condenser Bay.Reason tor Activity:

RPS System I has been experiencing spurious hall Isolations.

Troubleshooting IsolatedTS-IBOOIOE and TS-IBOO1OF.

This TCCP Is to keep the switches Isolated until repairscan be performed in a plant outage.Ef fect of Aethfty.This TCCP does not affect plant operations.

It does reduce the number of temperature switches for high Trunnion Room temperature in RPS System I from 8 to 6. It reducesthe TSs In each RPS sub-channel from 4 to 3. This Is acceptable per Technical Specification, which requires only one TS In each sub-channel.

However, the TCCPdoes require a 50.59 Evaluation because Rt involves a change to an SSC that adversely affects a UFSAR described function.

Summary of Conclusion for the Activity'e 50.$5 Review:This activity requires a 50.59 Evaluation because it involves a change to an SSC thatadversely affects a UFSAR described function.

Enclosure

-RA- 15-xxPage 4 of 5This activiky does not result In more than a minimal Indre9se in the frequency ofoccurrence of an accident previously evaluated In the UFSAR. It does not result in morethan a minimal increase in the likelihood of occurrence of a malfunction of an SSCimportant to safety previously evaluated In the UFSAR. It does not result in more than aminimal increase In the consequences of an accident previously evaluated In theUFSAR. It does not result In more than a minimal Increase In the consequences of amalfunction of an SSC important to safety previously evaluated in the UFSAR. It doesnot create a possibility for an accident of a different type than any previously evaluated in the UFSAR. It does not create a possibility for a malfunction of an SSC important tosafety with a different result than any previously evaluated In UFSAR. It does not resultin a design basis limit for a fissionproduct barrier as described in the UFSAR beingexceeded or altered.

It does not result in a departure from a method of evaluation described in the UFSAR usedin establishing the design bases or In the safety analyses.

Therefore, prior NRC approval before Implementation of ECR 13-00378 Rev 2 is notrequired.

ftmn#3Evaluation Number:.

OC-2014-E-0002, Rev.0PORC Review Meeting No.(Dte):

1407 (07/09/14)

ActlvltylDocument No.: Temporary Modification

/ ECR # 14-00340, Rev.0TMe: Gag for Damper M-838- 11ECA OC 14-00340 installs a gag to maintain Damper DM-838-11 in the open positionduring normal plant operation.

Damper DM438-11.

is the iower inlet damper to DrywellRecirculation Fan RF-1-4.Reason fW A~rt":During a recent inspection of the drywell recirculatlon fans, It was observedthat Damper DM438-1l was found closed and not functioning.

See IR1679878.

A closed damper to a drywell recirculation fan reduces the fan'sability to cool the drywell effectively.

Effet of AdtWv.ty-Installing a gag on Damper DM-838-1 1 ensures that the damper is open fully during fanoperation and improves cooling of the drywell during plant operation.

Installing this gagalso prevents Damper DM-838-11 from closing should Drywefl Recirculation Fan RF-1-4trp.

Enclosure

-RA-15-xxPage 5 of 5Summary of Conclusion for the Activity's 50.59 Review:If a 50.59 Screening was performed, Questions I and 2 would have been answered'Yes' since ECR OC 14-00340 does remove an automatic function to close Damper DM-838-11 resulting from a trip of Drywell Recirculation Fan RF-1-4.Implementing ECR OC 14-00340 does not result in more than a minimal Increase in thefrequency of an accident previously evaluated In the UFSAR, nor does it does not resultin more than a minimal increase in the likelihood of occurrence of a malfunction of anSSC Important to safety previously evaluated in the UFSAR. Implementing ECR OC 14-00340 does not result in more than a minimal Increase In the consequences of anaccident previously evaluated in the UFSAR, nor does result In more than a minimalincrease in the consequences of a malfunction of an SSC important to safety previously evaluated in the UFSAR. Implementing ECR OC 14-00340 does not create apossibility for an accident of a different type than any previously evaluated in theUFSAR, nor does it create a possibilty for a malfunction of an SSC important to safetywith a different result than any previously evaluated in UFSAR. Implementing ECR OC14-00340 does not result in a design basis limit fission product barrier (DBLFPB) asdescribed in the UFSAR being exceeded or altered, nor does it result in a departure froma method of evaluation described in the UFSAR used In establishing the design bases orin the safety analyses.

ECR OC 14-00340 does not impact the Oyster Creek Technical Specifications andOperating License.Therefore, ECR OC 14-00340 can be implemented without obtaining previous NRCapproval.

Note: Evaluation

1. OC-2014-E-0001 was never issued. The proposed activity(Temporary modification

/ ECR # 14-00323) was voided (cancelled) before ever beingapproved for installation.

As such, this Evaluation was not required.