ML19347B248

Submits Addl SEP Topics to Be Added to NRC 791116 List for Deletion from Plant Review.Items Removed Are Not Applicable to Facility or Are Being Reviewed as Generic Issue.Revised Listing of DBE Accident & Transient Groups Encl

ML19347B248
Person / Time
Site:	Dresden
Issue date:	09/11/1980
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Abel J COMMONWEALTH EDISON CO.
References
TASK-02-02.B, TASK-02-02.D, TASK-03-08.B, TASK-05-11.B, TASK-06-08, TASK-06-09.A, TASK-15-08, TASK-15-14, TASK-15-8, TASK-2-2.B, TASK-2-2.D, TASK-3-8.B, TASK-5-11.B, TASK-6-8, TASK-6-9.A, TASK-RR NUDOCS 8010140126
Download: ML19347B248 (5)

Text

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NUCLEAR REGULATORY COMMISSION 3

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e September 11, 1980 Docket No. 50-10 1

Mr. J. S. Abel I

Director of Nuclear Licensing l

Comonwealth Edison Company Post Office Sox 767 Chicago, Illinois 60690

Dear Mr. Abel:

By letter dated November 16, 1979, we sent you the list of topics which would not be reviewed by your plant in the Systematic Evaluation Program (SEP). These topics were deleted from the SEP review because they were not applicable to your plant or they were being reviewed as part of an ongoing generic issue outside the SEP. The following topics should be added to the November 16 listing.

Removal of these additional topics from the SEP review results from (1) related generic NRC activities, and (2) non-applicability of topics to certain facilities.

The folicwing is a list of such topics and indicates their disposition:

Tooic Catecorization Discositien II-2.B Generic Ccmpliance with Appendix E i

l is being evaluated under the Emergency Preparedness Prog. m Office (EPPO) effort. Compli-ance with Appendix I is being evaluated as part of th2 NRC Appendix I review effort, t

II-2.D Generic Compliance is being evaluated under the EPPO effort.

l III-8.B Completed The review published as NUREG l

0479, " Report on SWR Control l

Rod Drive Failures" fulfills the intent of this topic.

VI-8 Generic Will be reviewed by NRC as part of TMI Task Action Plan (NUREG 0660) as specified in May 7, 1980 letter to all operating reactor licensees.

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Mr. J. S. Abel September 11, 1980 Topic Catecorization Discosition V-ll.B Not applicable Topic not applicable to this plant design.

VI-9.A Not applicable Topic not applicable to this plant design.

Those parts of Topic II-1.B " Population Distribution" relating to emergency plans will be evaluated by EPPO.

In addition, the original DBE review list indicated that DBE group VI events " Uncontrolled Rod Assembly Withdrawal at Power" and " Uncontrolled Rod Assembly Withdrawal - Low Power Startup" are a part of Topic XI-13. However, the topic of reference should be Topic XV-8, " Control Rod Misoperation" and accordingly the references for Topic XV-8 should include Standard Review Plans 15.4.1 and 15.4.2.

Also, the November 16, 1979 'etter states that DBE Group X, " Inadvertent Operation of ECCS or CVCS Mal-function that Causes an Increase in Reactor Coolant Inventory" should be deleted as it applies only to PWRs. However, Group X will be included in the SEP review since inadvertent operation of ECCS should be evaluated for BWRs. to this letter includes a revised listing of the DBE Accident and Transient Groups applicable to BWRs. Of note should be the inclusion of Group XI, " Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position", revision to Group III to include " Radiological Consequences of a Main Steam Line Failure Outside Containment," and the Inclusion of Fuel Handling Accidents in Group VIII.

Sir.cerely, M d/uA Dennis M. Crutenfield,72hief Operating Reactors Branch #5 Division of Licensing

_nclosure:

As stated cc w/ enclosure:

See next page 9

Mr. J. S. Abel September 11, 1980 l

l cc :

1 Isham, Lincoln & Beale Diractor, Technical Assessment Counselors at Law Division l

One First National Plaza, 42nd Floor Of fice of Radiation Programs Chicago, Illinois 60603 (AW-459)

U. S. Environmental Protection Mr. B. B. Stephenson Agency Plant Superintencent Crystal Mall 42 Dresden Nuclear Power Station Arlington, Virginia 20460 Rural Route #1 Morris, Illinois 60450 U. S. Environmental Protection Agency U. S. Nuclear Regulatory Commission Federal Activities Branch Resicent Inspectors Of fice Region V Office Dresden Station ATTN: EIS COORDINATOR RR 71 230 South Dearborn Street Morris, Illinois 60450 Chicago, Illinois 60604 Susan N. Sekuler Resident Inspector Assistant Attorney General Dresden Nuclear Power Station Environmental Centrol Division c/o V. S. NRC 188 W. Randolph Street Rural Route fl Suite 2315 Morris, Illinois 60450 Chicago, Illinois 60601 Morris Public Library 604 Liberty Street Morris, Illinois 60451 Chairman Board of Supervisors of Grunay County Grundy County Courthouse Morris, Illinois 50450 Department of Public Health ATTN: Chief, Division of Nuclear Safety 535 West Jefferson Springfield, Illinois 62761 I

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ENCLOSURE BWR OBE TOPIC LIST Accident and Transient Groucs RELATED TOPIC DESIG?! 9 ASIS EVE!!T SRP Group I XV-1 Decrease in feedwater temperature 15.1.1 (BWR)

XV-1 Increase in feedwater flow 13.1.2 XV-1 Increase in stear. riow 15.1.3 XV-9 Start-up of inactive laop and flow 15.4.4, 5 controller malfunction XV-3 Inadvertent closure of main steam 15.2.4 isolation valve Group II XV-3 Loss of external load 15.2.1 XV-3 Turtine trip 15.2.2 XV-3 Loss of co.det.ser vacuum 15.2.3 XV-3 Steam pressure regulatury failure 15.2.5 XV-5 Loss of feecwater flow 15.2.7 i

Grouc III XV-18 Radiological Consequences of a 15.5.4 Main Steam Line Failure Outside Containment Grouc IV XV-4 Loss of AC power to station 15.2.5 auxiliaries XV-24 Loss of all AC power I

Grouc V XV-7 Loss of forced coolant flew 15.3.1 i

XV-7 Primary pump rotor sei:ure 15.3.3 j

XV-7 Primary pump shaft break 15.3.4 Grouc VI XV-8 Uncontrolled rot' assemely wiedrawal 15.4.2 at power XV-8 Uncontrolled rod ass sbly withdrawal 15.4.1 Icw power start-up XV-8 Control rod miscoeration 15.4.3 XV-13 Spectrum of rod drop accidents 15.4.9 i

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Grouc VII XV-19 Spectrum of loss of coolant accidents 15.5.5 Grouc VIII XV-21 Orop of cask or heavy' equipment 15.7.5 XV-20 Radiological Consequences of Fuel 15.7.4 Damaging Accidents (inside and outside containment)

Grouc IX XV-15 Inadvertent opening of SWR safety /

15.5.1 relief valve grouc X XV-14 Inadvertent operation of ECCS 15.5.1 l

Grouc XI XV-11 Inadvertent loading and oceration of 15.4.7 a fuel assembly in an improper position Grouc XII Not applicable to BWRs i

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_z-BWR OBE LIST (continued)

SRP RELATED GROUP SEP TOPIC DESIGN BASIS EVENT SECTION 3

VI XV-8 Uncontrolled rod assemoly withdrawal 15.4.2 at pcwer XV-d Uncontrolled rod assemoly withdrawal 15.4.1 low power start-up XV-8 Control rod misoperation 15.4.3 XV-13 Spectrum of rod crop accidents 15.4.9 VII XV-19 Spectrum of red crop accicents 15.5.5 VIII XV-20 Radiological consecuences of fuel 15.7.4 camaging accicents (insice ano outsice containment)

XV-21 Orop of cast or neavy equipment 15.7.5 IX XV-15 Inaevertent o;ening of SSR safety /

15.5.1 relief valve X

X(-14 Inadvertent operatien of ECCS 15.5.1 XI XV-11 Inacvertent loa:ing and operatica of 15.4.7 a fuel assem:iy in an improper pcsitien Not appli:scle to swr's X11 PWR CBE LIST 3R009 RELATED sRp SEP TCP!C DES!GN BASIS EVENT SECTION I

XV-1 Decrease in feedwater temoerature 15.1.1 XV-1 Increase in feecwater flow 15.1.2 XV-1 Increase in steam flow 15.1.3 XV-1 Inadvertent coening of steam 15.1.4 j

generator relief / safety valve XV-9 Start-up of inactive loco 15.4.4 t

XV-10 System malfunction causing a 15.4.5

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II XV-3 Loss of external load 15.2.1 XV-3 Turoine trio 15.2.2 l

XV-3 Loss of condenser vacuam 15.2.3 XV-3 Steam cressure regulatory failure 15.2.5 XV-5 Loss of feedwater flow 15.2.7 g

XV-6 Feedwater system oipe break 15.2.8 i

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