ML19309E737
| ML19309E737 | |
| Person / Time | |
|---|---|
| Site: | 07001308 |
| Issue date: | 01/31/1980 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19309E724 | List: |
| References | |
| 15326, NEDO-21326C2, NEDO-21326C2-V1-2, NUDOCS 8004240294 | |
| Download: ML19309E737 (11) | |
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NEDO-21326C2 Janunry 1980 Consolidated Safety Analysis Report - Morris Operation NEDO-21326, Volumes 1 and 2 RE7ISION
'INDEX for Revision C2, January 1980 Incorporation of new text.
Pages to be Re=cved New Pages to be Inserted Chapter Page Number Date Chapter Page Nu=ber Date Volume 1 Volume 1 Revision Su==ary 11/79 Revisien Se--=ry 1/80 Table of Contents viii 11/79 Table of Centents viii 1/30 7
7-34 11/79 7
7-34 1/80 Volume 2 Volume 2 Revision Su==ary 11/79 Revision Snemary 1/80 Table of Centents viii 11/79 Table of Contents viii 1/80 10 10-9a,10-9b 1/80
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.uu:w< o 80042do g C[,L 1 of 1
t Following :::aterial to be inserted in Volume 1 G
EDO-21326c2 January 1980 CONSOLIDATED SAFETY ANALYSIS REPORT r
FOR MORRIS OPERATION REVISION
SUMMARY
Revision & Amendment Date Sumnnry NEDO-21326C 1/79 Reissue and update filed with !icense renewal acclication.
Incorpcrates all"A" senes revisions of onginal cated 1/77.
NEDO-21326C1 11/79 incorporates demograohic data through the year 2000, radiological men'tonng update, and expanded tacie of contents.
NEDO-21326C2 1/80 Incorporates new Chapter 10 specification and revised radiation data.
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Revision Coding Key: New cr changed information is indicated by vertcal bars in the nght-hand margin opposite the new or enanged information:"N" indicates new information; "E" indicates editorial charges or correctons.
Document Numoer Key:
NED0 213 2 6 C1 ev sien Prefix Senal sien Amencment gg, f
5
NEDO-21326C2 January 1980 TABLE OF CONTENTS (Continued)
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 Co=ponents 9-3 9.2.3 Morris operation organization 9 -4 9.3 Training Programs 9-7 9.4 Normal 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 9-13 9.5.4 Activation of Emergency organization 9-19 9.6 Deccmmissioning 9-21 9.7 References 9-21
- 10. OPERATION SPECIFICATIONS 10-1 10.1 Introduction 10-1 10.1.1 Definitions 10-1 10.1.2 Authorized Place of Use 10-2 10.1 3 Quality Assurance 10-2 10.1.4 General Considerations 10-3 10.2 Safety Limits 10-3 i
10.2.1 Authorized Materials 10-3 10.2.2 Fuel Storage Provisions 10-3 10.2 3 Changes, Tests and Experiments 10-9a 10 3 Limiting Conditions 10-10 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 Sampling 10-14 10.4.2 Effluent Water 10-14 viii
NEDO-21326C2 January 1980 For comparisen, the guideline value for 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 estimated annual thyroid exposure because it is the maximum dese. Averages of thyroid exposures were calculated for concentric circles with radii of multiples of 10 miles. These average values were multiplied by the population within each area which gives an average annual man-thyroid-Rec. The sum of these values for each area out to a radius of 50 miles gives a total of less than four man-thyroid-Rem /yr for the period frem 1970 to the year 2000.
For ccmparison, the population exposure from normal background radiation (taken at 100 mR/yr) in the same area is about 665,000 man-Rem for 1970, to 750,000 man-Rem for the year 2000. The radiological impact fecm the Morris Operation is insignificant.
7.7 3 Liquid Releases There are no planned releases of liquid wastes from the site. Furthermore, there is no mechanism under normal operating conditions for injection of contaminaued water into the waste water treatment system.
7.8 REFERENCES
1.
RESSAR-41 Reference Safety Analysis Report, Vol. 6, Westinghouse, December 1973 and A=endments.
2.
K. J. Eger, Operating Experience - Irradiated Fuel Storage - Morris Operation, Morris, Illinois, General Electric Company, May 1978 (NEDO-209698).
2a. State of Illinois, Department of Public Health, Monitoring and Regulation of Nuclear Facilities in Illinois, Springfield, Illinois (1977).
The report shows slightly higher levels of radioactivity in the control counties.
3 A proprietary prcduct of the Norton Co.
7-34
d Following material to be inserted in Volu:ne 2
NEDC-21326C2 Januacy 1980 CONSOLIDATED SAFETY ANALYSIS REPORT FOR MORRIS OPERATION REVISION
SUMMARY
Revision & Amencment Date Summary NECC 2'32SC 1 79 Ae:ssue and uccate Nec.vtr 'icease renewat acclication.
'ncer;; orates a.i ' A *-seres rev s ens of iriginal dated 1/77.
NEDO-21326C1 1 t,79 incercerates cemcgra::me cata :nre"gn the year 2000.
racicieg: cal moniter:rg.ccate. anc excandec tacle of contents.
NECO 2132sC2
- 20 incer;: crates new Chacter 10 s::ecification and revised rad:atcn data.
Revision Coding Key: New er changed information is indicated cy vertical ::ars in tne ognt nand marg!n oc;:osite the new or enanged informat.on: N" ndicates new information; "E" incicates edit 0nal changes or ccrrectons.
Occument Numcer Key:
NEOO 21326C1 e <isicn Prefix Senat P sien Amendment Senes
NEDO-21326C2 January 1980 TABLE OF CONTENTS (Continued)
Page 9.
CONDUCT OF OPERATIONS 9 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 Conponents 9-3 9.2 3 Morris Operation Organisation 9-4 93 Training Programs 9-7 9.4 Normal 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 Responsibiljties 9-18 9.5 3 Action Procedures 9-18 9.5.4 Activation of Emergency Organisation 9-19 9.6 Decommissioning 9-21 9.7 References
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9-21
- 10. OPERATION SPECIFICATIONS 10-1 10.1 Introduction 10-1 10.1.1 Definitions 10-1 10.1.2 Authorized Place of Use 10-2 10.1 3 Quality Assurance 10-2 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 Provisiens 10-3 10.2.3 Changes, Tests and Experiments 1 -9a 10 3 Limiting conditions 10-10 10 3 1 Limiting Conditiens - Water Shield 10-10 10.3.2 Limiting condition - Criticality 10-10 10.4 Surveillance Requirements 10-11 10.4.1 Effluent Air Sampling 10-14 10.4.2 Effluent Water 10-14 viii
NEDO-21326C2 January 1980 10.2 3 Changes, Tests and Experiments N
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10.2 3 1 Specification Changes in the facility and procedures described in this report, as well as tests and experiments not described in this report, =ay be perforced without prior approval by the U.S. Nuclear Regulatory Cocsission, provided that a pro-posed change, test or experi=ent does not require a change in the Operation Specifications of this chapter, involve unreviewed safety or environmental issues (including occupational radiation exposure exceeding regulatory limita-tions), or decrease the effectiveness of the physical security plan.
A change, test or experiment that does involve unreviewed safety or environmen-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 for the facility.
10.2.3.1.1 Unreviewed Safety Issues Criteria Changes in the facility or procedures or tests and experiments (hereinafter referred to as " actions") shall be reviewed for safety and envirencental issues previously unreviewed by the U.S. Nuclear Regulatory Commission under the follow-ing criteria:
The proposed action shall be deemed to involve an unreviewed safety a.
issue if the probability or consequences of an accident or malfunction of equipment important to safety would exceed limitations established in this report or established by regulations.
b.
The proposed action shall be deemed to involve an unresolved safety issue if the' margin of safety where defined in any specificatice in this chapter is significantly reduced.
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NEDO-21326C2 January 1980 10.2 3 1.2 special Records and Reports N i The following special records and reports are required regarding changes, tests and experiments:
Records of facility changes shall be made and maintained during the a.
life of the facility (e.g., until termination of license), including the bases for determining that the changes did not involve unreviewed safety issues. Facility changes of a long-ters or permanent nature will be recorded by issuing revisions to appropriate chapters of this report.
b.
Records of temporary facility changes and tests and experiments shall be prepared and mainta'ined 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.
An annual report of actions under Subsection 10.2.3.1 shall be furnished c.
to the Nuclear Regulatory Commission: Wegional Office and other addressees as required by applicable regulations. The annual report shall contain a brief description of changes, tests and experiments and shall include a summary of the safety evaluation of each action.
10.2.3.2 Basis This specificati0n provides the flexibility to make changes in the facility and procedures and to conduct tests and experiments that utilize the unique features of Morris Operation while maintaining these actions within the safety limits previously reviewed and approved by the U.S. Nuclear Regulatory Commission.
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