RA-15-042, Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Reports - January 1, 2013 Through December 31, 2014

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

Subject:

Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Reports -

January 1, 2013 through December 31, 2014 Enclosed are the Oyster Creek Nuclear Generating Station 10 CFR 50.59 and 10 CFR 72.48 Change 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 is needed.

Sincerely, Ll tas

amyPresident (Vice Oyster Creek Nuclear Generating Station Enclosure cc: Administrator, USNRC Region I USNRC Senior Project Manager, Oyster Creek USNRC Senior Resident Inspector, Oyster Creek

Enclosure - RA- 15-xx Page 1 of 5 Exelon Generation Company, LLC Oyster Creek Nuclear Generating Station Enclosumre to RA-15-42 Docket No. 50-219 2013- 2014 Biennial 10 CFP 60.6t and -10CFR 72A9 Chang Summary Reports These summary reports are issued pursuant to reporting requirements for Oyster Creek Nuclear Generating Station (OCNGS). These reports address tests, experiments, and changes to the facility and/or procedures as they are described In the Final Safety Analysis Report for the OCNGS station and the Final Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System (TN-618T Spent Fuel Cask at OCNGS). These reports summarize the three (3) tests, experiments, and changes that were implemented between January 1, 2013 and December 31, 2014 under 10 CFR 50.59. There were no tests, experiments, or changes Implemented by OCNGS under 10 CFR 72.48.

. .. J

Enclosure - RA-15.xx Page 2 of 5 Item # 1 Evaluation Number: OC-2013-E-0001, Rev.0 PORC Review Meeting No. (Date):. 13-08(08/30/13)

Activity/Document No.: Temporary Modification / ECR # 13-00378, Rev.0

Title:

Trunnion Room Temperature Main Steam Une Isolation Description of Actlvfty ECR OC 13-00378 allows Operations to install a jumper across three of the four temperature switches in any one of four Reactor Protection System (RPS) high temperature isolation circuits. This Is a temporary jumper that is Installed as a compensatory measure to reduce the challenges with regard to spurious Isolations. This temporary jumper Is to be removed after repairs have been made to restore the system to its design condition no later than 1R25.

Reason for Activity:

RPS 1 and 2 have been experiencing spurious half scram isolations due to an Intermittent ground Inone of the main steam line temperature sensors which are located Inthe Condenser Bay. Steam leaks inthe Condenser Bay.are beleved to be the cause of the intermittent grounding. Therefore, the purpose of the jumper Is to prevent spurious initiation of the affected RPS sub-channel.

Effe*t of Activity:

Implementing ECR OC 13-00378 protects against a full reactor scram due to simultaneous spurious half Isolations InRPS I and RPS 2 Trunnion Room high temperature isolation circuits. Im ECR OC 13-00378 does not prevent a full reactor scram Ifvalid trip signals are received on the Trunnion Room high temperature circuits. Implementing ECR OC 13-00378 does not have any Impact on any plant design basis or safety analysis as described inthe UFSAR.

Summary of Conclusion for the Activity's 0.S9 Review:

Implementing ECR OC 13-00378 does not result Inmore than a minimal Increase Inthe frequency of an occurrence of an accident previously evaluated Inthe UFSAR, nor does it result Inmore than a minimal increase Inthe 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 Inthe consequences of an accident previously evaluated Inthe UFSAR, nor does itresult Inmore than a minimal increase. Inthe consequences of a malfunction of an SSC important to safety previously evaluated inthe UFSAR. Implementing ECR OC 13-00378 does not create the popsibllity for an accident of a different type than any previously evaluated Inthe UFSAR, nor does it create a possibility for a malfunction of an SSC important to safety with a different result than any previously evaluated inthe UFSAR. Implementing ECR OC 13-00378 does not result in a design basis limit for a fission product barrier as described Inthe UFSAR being exceeded or altered. Implementing ECR OC 13-00378

Ernclosure -. RA-15-xx Page 3 of 5 does not result in a departure from a method of evaluation described inthe UFSAR used inestablishing the design bases or inthe safety analyses for Oyster Creek.

Therefore, NRC approval Isnot required prior to Implementing ECR OC 13-00378.

Iftem # 2 Evaluation Number:. OC-2013-EO0002' Rev.0 PORC Review Meeting No. (Dale): 13-10 (0023/13)

Actlvlty/lDocument No.: Temporary Modification I ECR # 13-00378, Rev.2

Title:

TCCP to Jumper Out TS-IBOO1OE and TS.IB001OF Description of AetW.y This activity Is a Temporary Configuration Change Package (TCCP) to jumper out temperature switches TS IB001OE, MSL TUNNEL HI TEMPERATURE SWITCH CLOSES MSIV'S, and TS-IBOO1OF, MSL TUNNEL HI TEMPERATURE SWITCH CLOSES MSIV'S. The field wires inthe switch housings will be lifted and connected together, effectively jumpering out each temperature switch.

TS-IBO01DE and T&-IBOO1OF are described Inthe UFSAR, inthe attached 50.59 Screening, and inthe attached $0.59 Evaluation as *Trunnion Room High Temperature" switches. Both switches are located Inthe Main Steam Line Tunnel Inthe Condenser Bay.

Reason tor Activity:

RPS System I has been experiencing spurious hall Isolations. Troubleshooting Isolated TS-IBOOIOE and TS-IBOO1OF. This TCCP Is to keep the switches Isolated until repairs can be performed ina plant outage.

Effect of Aethfty.

This TCCP does not affect plant operations. It does reduce the number of temperature switches for high Trunnion Room temperature inRPS System I from 8 to 6. It reduces the TSs Ineach RPS sub-channel from 4 to 3. This Is acceptable per Technical Specification, which requires only one TS Ineach sub-channel. However, the TCCP does 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 itinvolves a change to an SSC that adversely affects a UFSAR described function.

Enclosure - RA- 15-xx Page 4 of 5 This activiky does not result Inmore than a minimal Indre9se inthe frequency of occurrence of an accident previously evaluated Inthe UFSAR. It does not result in more than a minimal increase inthe likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated Inthe UFSAR. Itdoes not result inmore than a minimal increase Inthe consequences of an accident previously evaluated Inthe UFSAR. Itdoes not result Inmore than a minimal Increase Inthe consequences of a malfunction of an SSC important to safety previously evaluated inthe UFSAR. It does not create a possibility for an accident of a different type than any previously evaluated in the UFSAR. Itdoes not create a possibility for a malfunction of an SSC important to safety with a different result than any previously evaluated InUFSAR. It does not result in a design basis limit for a fissionproduct barrier as described inthe UFSAR being exceeded or altered. It does not result ina departure from a method of evaluation described in the UFSAR usedin establishing the design bases or Inthe safety analyses.

Therefore, prior NRC approval before Implementation of ECR 13-00378 Rev 2 is not required.

ftmn#3 Evaluation Number:. OC-2014-E-0002, Rev.0 PORC Review Meeting No.(Dte): 1407 (07/09/14)

ActlvltylDocument No.: Temporary Modification / ECR # 14-00340, Rev.0 TMe: Gag for Damper M-838- 11 ECA OC 14-00340 installs a gag to maintain Damper DM-838-11 inthe open position during normal plant operation. Damper DM438-11. is the iower inlet damper to Drywell Recirculation Fan RF-1-4.

Reason fW A~rt":

During a recent inspection of the drywell recirculatlon fans, Itwas observed that Damper DM438-1l was found closed and not functioning. See IR 1679878. Aclosed damper to a drywell recirculation fan reduces the fan's ability 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 fan operation and improves cooling of the drywell during plant operation. Installing this gag also prevents Damper DM-838-11 from closing should Drywefl Recirculation Fan RF-1-4 trp.

Enclosure - RA-15-xx Page 5 of 5 Summary of Conclusion for the Activity's 50.59 Review:

Ifa 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 inmore than a minimal Increase inthe frequency of an accident previously evaluated Inthe UFSAR, nor does it does not result inmore than a minimal increase inthe likelihood of occurrence of a malfunction of an SSC Important to safety previously evaluated inthe UFSAR. Implementing ECR OC 14-00340 does not result inmore than a minimal Increase Inthe consequences of an accident previously evaluated inthe UFSAR, nor does result Inmore than a minimal increase inthe consequences of a malfunction of an SSC important to safety previously evaluated inthe UFSAR. Implementing ECR OC 14-00340 does not create a possibility for an accident of a different type than any previously evaluated inthe UFSAR, nor does it create a possibilty for a malfunction of an SSC important to safety with a different result than any previously evaluated in UFSAR. Implementing ECR OC 14-00340 does not result ina design basis limit fission product barrier (DBLFPB) as described in the UFSAR being exceeded or altered, nor does it result ina departure from a method of evaluation described inthe UFSAR used Inestablishing the design bases or inthe safety analyses.

ECR OC 14-00340 does not impact the Oyster Creek Technical Specifications and Operating License.

Therefore, ECR OC 14-00340 can be implemented without obtaining previous NRC approval.

Note: Evaluation # OC-2014-E-0001 was never issued. The proposed activity (Temporary modification / ECR # 14-00323) was voided (cancelled) before ever being approved for installation. As such, this Evaluation was not required.