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MONTHYEARML20213F1241986-11-0707 November 1986
Concurs W/Intent of Amend 108 to License DPR-16,revising Radiological Effluent Tech Specs,Per 10CFR50,App I.Exception Taken to Basis 3.6.A (SEP Topic XV-16) Re Radiological Consequences
Project stage: Other
ML20211M3851986-11-28028 November 1986
Forwards SER Re Util 850726 Request for Deferment of Eight NRC Required Mods from Cycle 11 Refueling Outage to Either Cycle 11 or 12R Outage.Request Acceptable for Deferral to Cycle 11,but No Later than Restart from Cycle 12R
Project stage: Approval
ML20148G4931988-01-19019 January 1988
Requests Addl Info Re Implementation of ATWS Rule Requirements,Including Provision of Electrical Functional Diagrams for ARI & RPT Sys from Sensors to Final Actuated Devices,By 880210
Project stage: Other
ML20195K0201988-01-22022 January 1988
Requests Addl Info Re Util 831114 & 851023 Submittals for Generic Ltr 83-28,Item 2.2 (Part 1) Re Equipment Classification Program (Programs for All Other safety- Related Components).Response Requested by 880229
Project stage: Other
ML20149L6291988-02-18018 February 1988
Forwards Safety Evaluation Supporting Proposed Design for Standby Liquid Control Sys.Tech Spec Change Request Needed by 880331
Project stage: Approval
ML20205L0091988-07-31031 July 1988
Conformance to Generic Ltr 83-28,Item 2.2.1-Equipment Classification for All Other Safety-Related Components: Oyster Creek, Technical Evaluation Rept
Project stage: Other
ML20205K9921988-10-21021 October 1988
Forwards EGG-NTA-7293, Conformance to Generic Ltr 83-28, Item 2.2.1-Equipment Classification for All Other Safety- Related Components:Oyster Creek, Accepting Util 831111, 851023 & 880518 Responses
Project stage: Other
ML20205P5231988-11-0404 November 1988
Forwards Safety Evaluation Supporting Util Submittal Re Compliance W/Atws Rule 10CFR50.62 Concerning Alternate Rod Injection & Recirculation Pump Trip Sys.Design Does Not Meet Requirements of ATWS Rule & Not Acceptable
Project stage: Approval
ML20235H7431989-02-16016 February 1989
Advises That Util 890120,23 & 31 Ltrs Re IGSCC Insp & Repairs Performed During 12R Refueling Outage Meet Generic Ltr 88-01 Requirements.Safety Evaluation Will Be Sent Under Separate Conver
Project stage: Approval
ML20246M5871989-08-29029 August 1989
Summary of 890802 Meeting W/Util in Rockville,Md Re full-term OL & Other Licensing Activities.List of Attendees & marked-up Regulatory Info Tracking Sys List of Unresolved SEP Topics & TAC Numbers Encl
Project stage: Meeting
ML20058K5061990-06-28028 June 1990
Forwards Supplemental Safety Evaluation for Plant Dcrdr. NRC Concludes That Licensee Submittal Meets NUREG-0737, Suppl 1 Dcrdr Requirements & Therefore,Issue Considered Resolved
Project stage: Approval
ML20058A6381990-10-18018 October 1990
Forwards SE Conditionally Accepting Util Insp & Repairs for Igscc,Per Generic Ltr 88-01
Project stage: Approval
ML20073H5581991-04-24024 April 1991
Discusses Alternative Method of Monitoring Containment high- Range Radiation Monitors,Per Amend 116 to License DPR-16. Justification Provided to Support Conclusions That Addl Preplanned Monitoring of Monitors Unwarranted
Project stage: Other
RA-09-017, Letter from Exelon, Subj: Request for Exemption from 10 CFR 50, Fire Protection of Safe Shutdown Capability2009-03-0303 March 2009
Letter from Exelon, Subj: Request for Exemption from 10 CFR 50, Fire Protection of Safe Shutdown Capability
Project stage: Request
1988-02-18
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.e GPU Nuclear Corporation
<1 Nuclear
- = gf r 388 Forked River, New Jersey 08731-0388 609 971-4000 Wnter's Direct Dial Number:
April 24,1991 C321-91-2060 U.S. Nuclear Regulatory Commission Att: Document Control Desk Washington, DC 20555 Gentlemen:
Subjects Oyster Creek Nuclear Oenerating Station (OCNGS)
Docket No. 50-219 License No. DPR-16 Containment High Range Radiation Monitors - Alternative Monitoring References (1) NRC Letter, March 31, 1987,'" Oyster Creek Nuclear Generating Station - Containment High Range Radiation Monitors (TSCR 152, TAC 64381 and 64015)."
i The Reference (1) letter provided approval of Amendment No. 116 to Provisional Operating License No. DPR-16 for the Oyster Creek Nuclear Generating Station.
The safety Evaluation, sections 2.1 and.2.3, enclosed with the Reference (1) letter requested a technical specification be proposed for a proplanned alternative method of monitoring containment radiation to be initiated if both containment high range radiation monitors are inoperable for more than 7 days or to provide justification for not needing this technical specification for Oyster Creek.=
GPU Nuclear has evaluated existing plant features and procedures, and concluded
.that based on the following justification an additional preplanned method of monitoring' containment radiation is not warranted.
The containment high range radiation monitors are redundant and therefore can tolerate single failure.
Currently, the containment high range radiation monitors function to observs release of radioactive materials into the drywell during and following an accident. During and following an accident, any exhaust through the main stack would be monitored by the high range RAGEMS
- noble gas monitor (Technical Specification 3.13.G.3).
In addition, the existing Oyster Creek Nuclear Generating Station post-accident sampling and analysis procedure for the PASS addresses isotopic analyses of iodine and particulate cartridges for drywell dome and ring header samples.
9105070174 910424 PDR ADOCK 05000219 g
P PDR R2:C3212060 r 3( 0%
In summary, independent plant features currently exist to replace the functions of the containment high range radiation monitors in the unlikely event of oosh high range monitore being inoperable for more than 7 days.
If you have any questions on this submittal, please contact Mr. Michael W.
Laggart, Manager, corporate Nuclear Licensing at (201)3'.6-7968 Si cerely, f? a J.,J.yor ikee
, Oyster Creek JJE/RZ/ pip j
cc: Administrator, Region I Senior NRC Resident Inspector oyster creek Project Manager RZ C3212060
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