ML20092P562

Forwards Current Status of NUREG-0737 Items.Table 1 Includes Listing of NUREG-0737 Items NRC Considers Acceptable & Resolved.Table 2 Provides Target Dates of Planned Mods

ML20092P562
Person / Time
Site:	Oyster Creek
Issue date:	06/27/1984
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NUDOCS 8407090098
Download: ML20092P562 (6)

Text

l GPU Nuclear Corporation Nuclear

= = = 388 Forked River, New Jersey 08731-0338 609 971-4000 Writer's Direct Dial Number:

Mr. Dennis !!. Crutchfield Operating Reactors Branch #5 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 NUREG 0737 Status Re: Full Term Operating License The purpose of this submittal is to provide you with the current status of NUREG-0737 items for the Oyster Creek plant.

Attached is Table 1, which includes a listing of 0737 items the NRC considers acceptable and resolved.

In addition, Table 2 provides you with the status or target dates of planned modifications.

Should you require any further information on this topic please contact Mr. Michael Laggart, BWR Licensing Manager at (201)299-2341.

Very truly yours, Petef 8. Fiedler Vice President and Director Oyster Creek PBF:BH: dam Attachments cc: Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 h

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e-0737 ITEMS COMPLETED Table 1 0737 Item Title NRC Closeout Date 1.A 1.1.

Shift Technical Advisor 1/15/82

1. A 1.2 Shift Supervisor Responsibilites 5/8/80 l. A 1.3 Shift Manning 2/1/82 1.A 2.1 Upgrading of R0 and SRO Training 11/30/82 1.A 2.3 Instructor Complete SR0 Exam 1.A 3.1 Revise Scope and Criteria for

-Licensing Exams L

1.C.2 Shift Turnover Procedures 5/8/80 1.C.3 Shift Supervisor Responsibilities 5/8/80 j.

1.C.4 Control Room Access 5/8/80 1.C.5 Feedback of Operating Experience 2/1/82 i

1.C.6 Correct Perfomance of Operating 2/1/82 Activities II.B.4 Training for Mitigating Core Damage 11/30/82 II.D.1 Safety and Relief Valve Testing 6/19/84 II.E.4.2(6)

Containment Vent & Purge Valves 8/31/83 II.E.4.2(7)

Containment Isolation on High Radiation 8/31/83 II.F.1.4 Containment Pressure-Monitor 9/29/83-p II.F.1.5 Containment Water Level Monitor 9/29/83 II.F.1.6 Containment Hydrogen Monitor ~

9/29/83 II.K.3.3 Reporting Reifef a Safety ' Valve.

6/10/82 Failing and Challenges II.K. 3.14 Isolation Condenser Isolation

12/18/81 Modification L II.K.3.16 Reduction of.-Challenges and Failures 5/8/80 to Relief Valves 1

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0737 Item Title NRC Closeout Date II.K.3.17 Report on Outages of ECC Systems 8/4/83 II.K.3. 21 Core Spray Modifications 5/27/83 II.K.3.25 Effects of Loss of A-C Power on Pump 10/22/82 Seals 1

II.K.3.29 Study to Demonstrate Performance of 8/1 5/81 Isolation Condensers with Noncondensibles II.K.3.30 Small Break LOCA Model 12/21/83 II.K. 3. 31 Plant Spectfic Calculations 12/21/83 II.K.3.44 Evaluation of Anticipated Transients 6/18/82 Combined with Single Failure II.K.3.45 Depressurization with systems other 5/17/83 than ADS III.A.1.1 Emergency Preparedness-Short Term 5/8/80 III.A.2.1 Emergency Preparedness-Upgrade 5/9/83 Emergency Plans III.D.1.1 Primary Coolant Outside Containment 5/8/80 Leak Reduction Program f

III.D.3.3 Inplant Radiation Monitoring 5/8/80

• These programs are implemented by the NRC.

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Table 2 THE FOLLOWING IS A STATUS OF OUR REMAINING OPEN ITEMS:

I.C.1 Guidance for the Evaluation and Development of Procedures for Transients and Accidents (EOPs)

Status:

As stated in our most recent correspondence dated April 15, 1983, our E0Ps will be implemented in two phases.

The phase 1 E0Ps were in place by November,1983.

These did not include ATWS events. Phase 2 will be implemented prior to the restart from our Cycle 11 refueling outage and will include all of the items omitted in phase 1.

I.D.1 Control Room Design Reviews (CRDR)

Status:

The CRDR for Oyster Creek was essentially completed in September 1982. Further integration of E0Ps are necessary. A summary report of the completed CRDR for all items required by Generic Letter 82-33 was submitted to tne NRC by letter dated April 30, 1984.

I.D.2 Safety Parameter Display System Status:

A formal Safety Evaluation was completed in April 1984.

The implementation plan will be submitted in June 1984, and the SPDS is projected to be operational prior to restart from our Cycle 11 outage.

II.B.1 Reactor Coolant System Vents Status:

By letter dated September 2,1983, the NRC requested additional information including our detailed isolation condsnser high point vent modification design.- We plan to provide this information by December 1,1984.

II.B.2 Plant Shielding Status:'

This item is complete with the exception of change out of filters for the Standby Gas Treatment System.

By letter dated April 15,1983,' GPUN requested cancellation of this requirement based on NRC staff evaluation of SEP Topic XV-19. The results

.of that analyses demonstrated that a single STBGS filter train was capable of handling an entire accident. Additional infomation regarding the adequacy of our plant shielding design review has been requested by the NRC.

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II.B.3. Post Accident Sampling Status:

By correspondence dated February 10, 1984 we provided the following dates for the implementation of our PASS System:

4 1)

Completion of Hardware Installation - Mid August 2)

Completion of Startup and Test - Mid Saptember 3)

Turnover to Plant - Mid September /End of October

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II.D.3 Valve Position Indication

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Status:

Positive indication of Relief and Safety Valve Position has been j

installed and the Oyster Creek Technical Specifications reflect their operability.

Environmental qualification will be i

accomplished in accordance with 10 CFR 50.49.

II.E.4.1 Dedicated Hydrogen Penetrations l

Status:

By letter dated January 17, 1983, the NRC stated that the requirements of 10 CFR 50.44 are appropriate in order to confonn to this action item.

II.F.1.1 Noble Gas Monitor f

J Status:

This is scheduled to be completed during our present refueling outage.

4 II.F.1.2 Iodine / Particulate Sampling i

Status:

This is scheduled to be completed during our present refueling j

outage.

II.F.1.3 Containment High Range Monitor-Status:

This will be installed during our Cycle 11 refueling outage.

II.F.2 Instrumentation for Detection of Inadequate Core Cooling Status:

By letter dated April 4,1980 and February 10, 1981, we stated

"... the existing safety grade multiple water level

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. instrumentation is a-direct and unambiguous indication of

. inadequate core cooling." We are still in agreement with this position and no new modifications are planned.

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II.K. 3.18 ADS Logic Status:

A plant specific risk analysis has been completed. No ADS Logic Modifications are recommended for Oyster Creek.

II.K.3.19 Interlock for Recirc Pump Modification Status:

By NRC correspondence dated March 14, 1983 the NRC has confirmed our deferral of this modification to Cycle 11.

II.K.3.27 Common Reference Level Status:

By GPUN correspondence dated April 8,1983.

The final phase of implementation for this modification which involves the deletion of all references to old scales, procedure revisions, and conducting the necessary training, will be completed during our current refueling outage.

II.K.3.46 Michelson Concerns Status:

By GPUN correspondence dated March 10, 1982, we stated that the design of the new overhead grid core spray sparger system has taken water hammer effects into consideration. We are awaiting further NRC evaluation of this topic.

III.A.l.2 Upgrade Emergency Support Facilities Status:

As discussed in our response to 0737 Supplement 1, our OSC is operational. The new TSC building should be completed in June 1984, and operational (without Data System) in August 1984. Our E0F has been relocated to our former FE0F in Lakewood, NJ.

III.A.2.2 Meteorological Collection System Status:

The Met Tower at Oyster Creek has no independent power supply as yet. Further study is on-going in this area.

III.D.3.4 Control Room Habitability Status:

As stated in correspondence dated April 8,1983 interim modifications are scheduled for completion during our Cycle 11 refueling outage. Final modifications will be completed at a later date. The NRC has requested further information on this item.

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