ML19294B186

Revision C2 to Consolidated SAR for Morris Operation,Vols 1 & 2.Related Correspondence

ML19294B186
Person / Time
Site:	07001308
Issue date:	01/31/1980
From:	GENERAL ELECTRIC CO.
To:
Shared Package
ML19294B178	List: ML19294B177 ML19294B184 ML19294B186
References
NEDO-21326-RC2, NUDOCS 8002270495
Download: ML19294B186 (10)

Text

NEDO-21326C2 January 1980 t

i Consolidated Safety Analysis Report - V. orris Operation c.

NEDo-21326, volu=es 1 and 2 RE7ISION INDEX for Revision C2, January 1980 Incorporation of new text.

1 Pages to be Re=oved New Pages to be Inserted Chapter Page Nu=ber Date Chapter Page Nu=ber Date Volu=e 1 Volume 1 Revision S-"ry 11/79 Revision Su==ary 1/80 Table of Contents viii 11/79 Table of Contents viii 1/80 7

7-34 11/79 7

7-34 1/80 Volume 2 Volume 2 Revision S"-m ry 11/79 Revision Sn-~ ry 1/80 Table of Contents viii 11/79 Table of Contents viii 1/80 10 10-9a,10-9b 1/80 G

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NEDC-21326C2 Jant.:ary 1980 CONSOLIDATED SAFETY ANALYSIS REPORT J'

FOR MORRIS OPERATION REVISION

SUMMARY

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Revision & Amendment Date Summary E

NEDO-2132SC 1/79 Reissue and ucdate fiied witn license rene ' acclicat:en.

Incorecretes all"A"-senes revisions of enginal dated 1/77.

NEDO-21326C1 11/79 incorparates demogracnic cata tnrcugn the year 2000, radiological monitonng update, and excanded tacie of centents.

NEDO-2132SC2 1/80 incorporates new Chapter 10 scecificatien and revised radiation data.

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Revision Coding Key: New or enanged information is indicated by vertical bars in the nght-hand margin ecposite the new or changed informat:cn:"N" indicates new infcrmation:

'E" indicates editonal enanges er correct: ens.

Occument Numcer Key:

NEOO 213 2 6 C1 i

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[nevis;cn Revis:en Prefix Sanal Amendment Senes

NEDO-21326C2 January 1980 TABLE OF CONTENTS (Continued)

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Q[g Page 9.

CONDUCT OF OPERATIONS 9-1 9.1 Introduction 9-1 9.2 Corporate organization 9-1 9.2.1 Corporate Functions, Responsibilities, and Authorities 9-1 9.2.2 Spent Fuel Services Operation Components 9-3 9.2.3 Morris Operation Organization 9-4 9.3 Training Programs 9-7 9.4 Nor=al Operations 9 -8 9.4.1 Plant Procedures 9-8 9.4.2 Records and Reports 9-11 9.4.3 Facility Modifications 9-11 9.5 Emergency Plans 9-15 9.

5.1 Purpose and Scope

9-15 9.5.2 Responsibilities 9-18 9.5 3 Action Procedures 9-18 f

9.5.4 Activation of Emergency Organization 9-19 1

z 9.6 Decommissioning 9-21 i

9.7 References 9-21

10. OPERATION SPECIFICATIONS 10-1 10.1 Introduction 10-1 10.1.1 De finitions 10-1 l

10.1.2 Authorized Place of Use 10-2 10.1 3 Quality Assurance 10-2 r

10.1.4 General Considerations 10-3 10'.2 Safety Limits 10-3 10.2.1 Authorized Materials 10-3 10.2.2 Fuel Storage Provisions 10-3 10.2.3 Changes, Tests and 7xperiments 10-9a 10 3 Limiting Conditions 10 10 3.1 Limiting Conditions - Water Shield 10-10 10.3.2 Limiting condition - Criticality 10-10 10.4 Surveillance Requirements 10-11 10.4.1 Effluent Air Sa=pling 10-14 10.4.2 Effluent Water 10-14 i

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NEDO-21326C2 January 1980 For eccparison, the guideline value fer compliance to Appendix I of 10 CFR Part 50 is 15 = Rem /yr to any organ (Regulatory Guide 1.109).

7.7.2 3 Man-Rem Calculations Man-Rem calculations were done only for the esti=ated annual thyroid exposure because it is the =aximum dose. Averages of thyroid exposures were calculated for concentric circles with radii of rultiples of 10 =iles.

These average values were multiplied by the population within each area which gives an average annual can-thyroid-Rec. The su= of these values for each area out to a radius of 50 t

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=iles gives a total of less than four nan-thyroid-Re /yr for the period from 1970 to the year 2000.

For co=parison, the population exposure from normal background radiation (taken

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at 100 =R/yr) in the sa:e area is about 665,000 =an-Rem for 1970, to 750,000 5

san-Rem for the year 2000.

The radiological i= pact from 'the Morris Operation is insignificant.

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7.7 3 Licuid Releases There are no planned releases of liquid wastes frem th,e site.

Furtherscre, there is 'no mechanism under non al operating conditions for injection of centa=inated water into the waste water treatment system.

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4 7.8 REFEFINCES

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1.

RESSAR-41 Reference Safety Analysis Report, Vol. 6, Westinghouse, Dece=ber 1973 and Amendments.

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2.

K. J. Eger, Operating Experience - Irradiated Fuel Storage - Morris Operation, l

Morris, Illinois, General Electric Cc=pany, May 1978 (NED0-20969B).

2a. State of Illinois, Depart =ent of Public Health, Monitoring and Regulation of Nuclear Facilities in Illinois, Springfield, Illinois (1977).

The report shows slightly higher levels of radicactivity in the control counties.

3 A proprietary pecduct of the Norton Co.

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NEDO-21326C2 January 1980 CONSOLIDATED SAFETY ANALYSIS REPORT FOR M

MORRIS OPERATION REVISION

SUMMARY

Revision & Amendment Date Summary

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NEDC-21326C 1/79 Re ssue and u::date filed w:tn heense renewat accircat'en.

Incerecrates all A" senes revisions of onginal cated 1/77 NEDO 21325C1 11/79 incorporates demogracnic data tnrcugn the year 2000.

raciclogical men;tenng ucdate and excanded tat:ie of l

centents.

NEDO 2132SC2 1780 Incorporates new Chacter 10 spec:fication and revised radiation data.

Revision Coding Key: New cr changed informat:cn 's 'nc.ated oy vert: cal acrs in the egnt nand marg:n ecocsite the new or enanged informat;en: "N" incicates new infor:9ation:

'E",ndicates ec;t0nai cnanges er correct: ens Occument Numcer <ey.

NEOO 29 325~~

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REDO-21326C2 January 1980 TABLE OF CONTENTS (Continued) r Page

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9.

CONDUCT OF OPERATIONS 9-1 9.1 Introduction 9-1 9.2 Corporate Organization 9-1 9.2.1 Corporate Functions, Responsibilities., and Authorities 9-1.

9.2.2 Spent Fuel Services Operation Co:penents 9-3 9.2.3 Morris Operation OrEanization 94

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93 Training Progra=s 9-7 9.4 Nor=al Operations 9 -8

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9.4.1 Plant Procedures 9-8 9.4.2 Records and Reports 9-11 9.4.3 Facility Modifications 9-11 9.5 Energency Plans 9-15 9.

5.1 Purpose and Scope

9-15 9.5.2 Responsibilities 9-18 i

9.5.3 Action Procedures 9-18 j:

i 9.5.u Activatien of E=ergency Organization 9-19 E

9.6 Decct=issi:ning 9-21 9.7 References 9-21

10. OPERATION SPECIFICATIONS 10-1 10.1 Introduction 10-1

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10.1.1 De finitiens 10-1 10.1.2 Authorized Place of Use 10-2 10.1.3 Quality Assurance 10-2 f.

10.1.4 General Ccnsideratiens 10-3 i

10.'2 Safety Li=its 10-3 10.2.1 Authorized Materials 10-3 L

10.2.2 Fuel Storage Provisions 10-3

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10.2.3 Changes, Tests and Experi=ents 10-9a 10.3 Li=iting Conditions 10-10 10.3.1 Li=iting Conditions - Water Shield 10-10 10.3.2 L1=iting Condition - Criticality 10-10 10.2 Surveillance Require =ents 10-11 10.4.1 Effluent Air Sa:pling 10-13 10.3.2 Effluent Water 10-13 viii

I NEOo-21326C2 January 1980 10.2.3 Changes, Tests and Exceriments N

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10.2.3.1 Specification Changes in the facility and procedure 3 described in this report, as well as tests and experiments not described in this report, =ay be perfor=ed without prior approval by the U.S. Nuclear Regulatory Co=sissien, provided that a pro-posed change, test or experiment does not require a change in the Operation Specifications of this chapter, involve unreviewed safety or environ = ental issues (including occupational radiation exposure exceeding regulatory li=ita-tions), or decrease the effectiveness of the physical security plan.

A change, test or experiment that does involve unreviewed safety or environ =en-tal issues, a change in these Operation Specifications, or that would decrease the effectiveness of the physical security plan, requires prior approval by the U.S. Nuclear Regulatory Commission. Matters involving physical security shall be considered and processed as specified in the approved physical security plan fer the facility.

10.2 3 1.1 Unreviewed Safety Issues Criteria Changes in the facility or procedures or tests and experiments (hereinaf ter referred to as " actions") shall be reviewed for safety and environmental issues previously unreviewed by the U.S. Nuclear Regulatory Co= mission under the follow-ing criteria:

a '.

The proposed action shall be deemed to involve an unreviewed safety issue if the probability or consequences of an accident or. =alfunction of equipment i=portant to safety would exceed li=itations established in this report or established by regulations.

b.

The preposed action shall be deemed to involve an unresolved safety issue if the =argin of safety where defined in an9 specification in this chapter is significantly reduced.

N 10-9a

NEDO-21326C2 January 1980 10.2 3.1.2 Special Records and Reports N

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The following special records and reports are required regarding changes, tests and experiments:

Records of facility changes shall be =ade and maintained during the a.

life of the facility (e.g., until termination of license), including the bases for deter =ining that the changes did not involve unreviewed E

safety issues. Facility changes of a long-ters er per:anent nature will be recorded by issuing revisiens to appropriate chapters of this E

report.

b.

Records of temporary facility changes and tests and experiments shall be prepared and =aintained for 5 years.

These records shall include safety evaluations to document the bases for determining that the subject changes, tests and experiments did not involve unreviewed safety issues.

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An annual report of actions under Subsection 10.2.3.1 shall be furnished

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c.

to the Nuclear Regulatory Cctrission Regional Office and other addressees as required by applicable regulatiens.

The annual report shall contain a brief description of changes, tests and experi=ents and shall include a su==ary of the safety evaluation of each action.

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10.2.3.2 Basis This specification provides the flexibility to =ake changes in the facility and procedures and to conduct tests and experiments that utilize the unique features of Morris Uperation while =aintaining these actions within the safety limits previously reviewed and approved by the U.S. Nuclear Regulatory Commission.

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10-9b

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