ML20148Q534
| ML20148Q534 | |
| Person / Time | |
|---|---|
| Site: | 07001308 |
| Issue date: | 12/31/1980 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20148Q526 | List: |
| References | |
| NUDOCS 8101230043 | |
| Download: ML20148Q534 (154) | |
Text
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O Effective Date:
December 31, 1980 ATTACHitENT A APPLICATION FOR RENEWAL OF MATERIALS LICENSE SNil-1265 APPLICANT'S PRINCIPAL OFFICERS Chairman of the Board and Chief E'xecutive Officer Reginald H.' Jones - - - - -
John F. Burlingame - - - - - Vice Chairman of the Board and Executive Officer Vice Chairman of the Board and Executive Officer Edward E. Hood, Jr. - - - -
John F. Welch, Jr. - - - - - Vice Chairman of the Board and Executive Officer James A. Baker - - - - - - - Executive Vice President, Sector Executive -
Industrial Products and Components Sector Executive Vice President, Sector Executive - Inter-Robert R. Frederick - - - -
r.ational Sector Herman R. Hill - - - - - - - Executive Vice President, Sector Executive - Power Systems Sector Christopher T. Xastner - - - Executive Vice President, Sector Executive - Technical Systems and Materials Sector Executiva Vice President, Sector Executive - Con-Paul W. Van Orden - - - - -
sitmer Pr* ducts and Services Sector Arthur M. Bueche - - - - - - Senior Vice President, Corporate Technology Daniel J. Fink - - - - - - - Senior Vice President, Corporate Planning & Development
- - - Senior Vice President, Corporate Production and Robert B. Xurtz - - -
Operating Services Leonard C. Maier, Jr. - - - Senior Vice. President, Corporate Relations Senior Vice President, General Counsel and Secretary l
Walter A. Schlotterbeck Thomas 0. Thorsen - - - - - Senior Vice President, Finance l
I All principal corporate officers are citizens of the United States of America.
The address for these officers is:
General Electric Company Fairfield, Connecticut 06431 Additional information regarding Ceneral Electric Company may be obtained from its Annual Report, Attachment E.
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810 128.004+
ATTACHMENT B RESPONSE TO SPECIFIC SECTIONS OF 10CFR72 Reeconse to specific secticna Lia:ed in 2:use 2e: er of 3cuember ::, :380 as ' amended by te::er of 3cuember 23, 1980.
Section
Response
72.11(b)
Refer to application letter 72.14(e)(2)
Refer to application letter 72.14(e)(3)
Shutdown and decommissioning costs, and financici provisions are described in CSAR Revision C3, Appendix A.7, Section A.7.5-series, including i
Figure A.7-1.
72.17(d)
A commitment to have and maintain an adequate compliment of trained and certified personnel is contained in CSAR Revision C3, Section 9.2.3.8.
72.20 Information on file and previously submitted; see Attachment D.
72.33(b)(4)
The training and certification program is contained in Attachment F; also, see CSAR Revision C3, Section 9.3.1.
72.33(b)(5)
Provisions for use of uncertified personnel are contained in CSAR Revision C3, Section 9.4.1.
72.72(e)
Proximity of sites is discussed in the CSAR, Revision C3, Sections 3.3.1 and 8.1.2.
72.76 Criteria for decommissioning are included in the CSAR, Section 4.5.
Subpart I Refer to response to,Part 72.33(4) and (5) 6
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ATTACHMENT C COMPARISON OF PART 72 REQUIREMENTS VERSUS APPLICANT'S DOCUMENTATION AS REQUESTED IN ROUSE LETTER OF NOVEMSER 12, 1980 j
Documensa referenced herein are identified under " Notes" on page References are to chaters or sections of the CSA? (note 2)
C-6.
excep: uhere noted otheruise. A.<ection reference foltouei by :he symbol (*) indicates material contained in the CSAR proposed Revision C3; see Attachmen: G.
A section refdrence not folloued by the syrbol refers :o :he current CSAR, including Revision C:; Revision C2 has been ui:hdraun.
Yne acron;m: NER means, "no response recuired".
- ocumen:
references indicate principal respenses; h:vever, :hese references are v.at in: ended tv 3 e:haustive.
Part 72 Apolicants Documentation References Subpart A
- NRR Subpart B 72.11(a),(b) -
- See request for amendment (note 1).
(c)
- See request for amendment; copies of CSAR proposed Revision C3 furnished in same qt.antity as original submission (February 1979).
(d)
- Furnished with original submission (February 1979) 72.12
- NRR 72.13
- NRR 72.14(a)(b)
- See request for amendment (c)
- 1.1.1 (*)
(d)(1)
- NRR (2)
- NRR (3)(1)
- 1.1.1 (ii)
- See request for amendment (4)
- NRR (e)
- See request for amendment 72.15(a)
- CSAR (note 2)
(1)
- 1.1. 2, 1.1. 3 ; 1.2 through 1.2.2.3 including 1.2.1.5(*);
Chapter 3 including sections in the proposed Revisien C3,
f especially Sections 3.7.5, and 3.9(*) through 3.9.1.3(*).
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C-2 (2)
- 1.2; 1.2.2 through 1.2.2.3; 1.3 through 1.3.5 (3)(i)ii)
- Refer to Subpart F
{iii) t (iv)
- 4.6(*)
(4)
- 5.3 through 5.8, including 5.5.l(*), 5.5.3.2(*),
S'. 5.4. 3(*), 5. 5. 5. 4(*), 5. 7.1( *), and 5. 7. 2. 3(*).
(i)
- see above (ii)
- Chapter 8, and Appendix A.8, A.9, A.12 and A.13 (5)
- Chapter 7; especially 7.2 and 7.6. Also, see Operating Experience Report (note 3)~, Sections 4.5 and 5.2, (6)
- 1.3.5.1; 4.3.8.3 and 4.3.8.4; 5.4.2.3, 5.5.5.8.
Also see Operating Experience Report Section 3.5 and 3.6.
(7)
- See Attachment H (8)
- Chapter 9 (9)
- NRR (10)
- See response to Part 72.17 (11)
- See response to Part 72.19 (12)
- Chapter 6 (i)
- Operating Experience Report, Sections 4 and 5 (ii)
- 4.3.8.4; 5.4.2.3, 5. 5.2 through 5.5.2.4, 5.5.4 through 5.5.4.2, 5.5.4.4, 5.5.5.7 and 5.5.5.8.
Also, see Operating Experience Report, Sections 3.3 through 3.6.
(iii)
- 5.4.2.3 and Operating Experience Report Section 3.6 (13)
- 8.7.1, 8.7.2.1, 8.8.3, 8.9.1, 8.*10.3.1 and Appendix A.13 (14)
- Chapter 11 and Appendix B.8 (15)
- See response to Subpart H (16)
- NRR (17)
- See response to 72.18 72.16
- See response to 72.33 72.17(a)
- 1.1.l(*)
(b)
- Attachment F (c)
- 9.2.3 l
(d)
- 9.2.3.8 i
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~ -..
_. =.
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Appendix A.7 72.18(a) 3 (b)
- Appendix A.7, Section A7.5.3 f
- See Radiological Emergency Plan (note 4) 72.19 72.20
- See Attachment 0 72.21
- NRR Note: Copies of revised documents are furnished in l
the same quantity as with the original application.
)
Subcart C
- NRR Suboart 0
- General requirements under 9.4.2 and 9.4.2.1; see Attachment H i'
Suboart E
[
72.61(a)
- Chapter 3 - all sections, and referenced appendixes.
- t (b)
- 3.3, 3.4, 3.7 series (c)
- 3.8 (d)
- NRR (e)
- See Attachment 0; also, Operating Experience Report f
1 (f)
- 3.5.2 72.62(a) i l
I
- 3.4, 3.5, and 3.7; also 3.8 (b)
(
(c) l 72.63(a)
'l (b) h
- 3.3, 8.1.2'(*)
(c) t 72.64(a)
- 3.4, 3.5, and 3.7; also 3.8 (b)
- Attachment 0; Operating Experience Report; CSAR Appendix A.7.
(c)(i)
- 3.2.3 i
(ii)
- 3.2.4 through 3.2.4.5 l
(iii)
- 3.4.3, 3.4.4, 3.6.1 through 3.6.3, and referenced f
I appendixes.
(d)
- NRR I
72.65(a)
- Operating Experience Report; CSAR S.1.1 through S.1.1.3 (b)
- Operating Experience Report; CSAR-Appendix A.7 f
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72.66(a)(1)
- NRR (2)
- NRR (3)
- NRR (4)
- Appendix 8.1 and B.2 (5)
- NRR (6)
- 4.2 through 4.2.5.2.3 (b)
- NRR 72.67(a)
- NRR (b)
- See Attachment H (c)
J 72.68(a)
-1.2.1.5(*),3.2.2.4(*)
(b)
- 4.3.6.1(*)
l (c)
- NRR l
72.69(a)
- 3.2.2.4(*)
l
- * '3 (b)
')
j 72.70 Suboart F 72.71
- NRR i
72.72(a)
- 4.4(*) and Chapter 11(*)
l (b)(1)
{
- 4.2(*) through 4.2.6.2 l
i (2)
)
t (3)
-4.4.2(*)
(4)
-4.3.2.l(*)
l (c)
- 4.3.7 through 4.3.7.2(*)
(d)
- NRR (e)
- 4.3.1(*)
f l
(f)
- 4.2(*), 4.3.4.1(*) through 4.3.4.3
[
(g)
- 4.2.(*)
(h)(i)
- 4.1.2, 4.2(*), 4.3.2(*), 4.3.5, 4.3.7, 4.3.8 ( includ-ing subsections of these principal sections).
f i
(2)
- 4.3.2.1(*)
j (3)
- 4.3.3.1(*)
t (i)
- 4.3.4.l(*)
(j)
- 4.3.4.l(*)
i (k)
- 4.3.9.1(*)
= _ - -.
~
i C-5 72.73(a)
- 4.3.5.1 and Appendix A.10 (b)
- Appendix A.10 an-d 8.5 72.74(a)
- 4.3.6.l(*)
(1)
I (2)
(3) i
- 4.3.6.2 and 4.3.6.2.1(*)
s (4)
(5) j (6)
.4.3.6.2.2-(b)
- 4.3.6.2.3 (c)(1)
- 4.3.6.2.4(*)
^
I (2)
- 4.3.6.2.3 (d)
- 4.3.3.l(*)
72.75(a)
- 4.3.8.1 and 4.3.8.3 l
(1)
- 4.3.4.1 l
(2)
- 4.3.6.2.2 1
(3)
- 4.3.2.1 (4)
- 4.2.7.1(*)
(5)
- 4.3.8.3 l
(b) 4.3.8.3 5
72.76
- 4.5(*)
Suboart G 72.80
- Chapter 11(*) and Appendix B 8 Suobart H
{
- See Physical Security Plan (note 5) 72.81 72.82
)
72.83
- Part of Physical Security Plan l
72.84
- NRR Subcart I l
72.91 72.92
- See Attachment.F l
72.93
)
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C-6 Nctes:
1.
" Request for amendment" refers to attached letter to R. Cunningham (NRC), dated 1/12/31.
2.
"CSAR" refers to Consolidated Safety Analysis Report for Merris Operation, NE00-21326C, including Revisions C1 ano proposed C3 (proposed Revision C3 is attached; Revision C2 was withdrawn).
3.
" Operating Experience Report" refers to "Orena:ina E:verienos Reoort -
Irradiated Fuel Storage at Morris Operation January 1972 to December 1979, NEDO-209698, including revisions through Revision B4, September 1980.
4.
" Radiological Emergency Plan" refers to Radiologioc! Icergency ?!an f
for Ndrris Opera: ion, NEDO-21894, including revisions through Revision
-3, September 1980.
5.
" Physical Security Plan" refers to ?hysiccI Securi:p ?!an - Merris i
Cperation, NE05-14507C4, including revisions through Revision C4, December 1979. This plan includes a contingency plan and security l
I force qualification and training plan.
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4 ATTACHMENT 0
)
SUMMARY
OF ENVIRONMENTAL REPORT INFORMATION
01.0 INTRODUCTION
This document contains the environmental report information related to the renewal of Materials License SNM-1265 for General Electric's Morris Operation, required by Title 10, Code of Federal Regulations, Part 72.20 (10CFR72.20).
01.1 Scoce, Content and Summary This document consolidates and summarizes environmental information ralated to the irradiated (spent) fuel storage activities at Morris Operation that has been previously documented by General Electric, the U.S. Atomic Energy Commission (USAEC), the U.S. Nuclear Regulatory Commission (USNRC), and the U.S. Depart-ment of Energy (US00E). These documents are listed in Table 0-1, and include documents specifically related to the Morris Operation and documents concerned with the generic aspects of scent fuel transport and storage.
01.1.1 Method of Referencing Information In accordance with crovisions of 10CFR72.12, this document incorporates pre-viously published information by saecific references to the documents listed in Table 0-1.
References.are made by Table 0-1 item number and specific reference (s) to paragraph or section, or as otherwise appropriate.
For example,
... refer to (13), 3.2.2 for site description..." references item (13) of Table 0-1, Section 3.2.2 of the CSAR. Likewise, "... refer to (5), II, A-F for site description..." references Item 5 of Table 0-1 Section II, Subsections A through F of the Final Environmental Statement for the Midwest Fuel Recovery Plant (MFRP).
01.2 Content Information in this document summarizes the environmental impacts of past activity at Morris Operation and forecasts impacts from activity authori:ed by the proposed license renewal in the period of 1980 - 2000.
01.3 Summary of Exoerience Since 1972, more than 1000 bundles of irradiated (spent) fuel from commercial nuclear power plants using light water reactors - - Boiling Water Reactors
l 0-2 (BWR) or Pressuri:ed Water Reactors (PWR) - - have been received and stored at the Morris Operation facility.
Effective control of radioactive material in the basin water, water temoerature, cask contamination, airborne radic-active materials and effluents has been demonstrated. Methods of cask and fJel handling and storage have also been demonstrated to be safe and effec-tive. There has been no appreciable leakage from fuel in storage as measured by radioactive materials in the basin water and fuel shipments have been com-pleted safely and efficiently.
Experience in water basin storage of spent fuel from light water reactors, both in the United states and abroad, has demonstrated that this storage method is a technically uncomplicated and cassive operation. There are no sources of energy involved in fuel storage at Morris Operation with the potential for causing dispersal of radioactive material in a form that could be car'ried, in any biologically significant amount, to an off-site location to pose a threat j
to public health and safety or to cause environmental damage.
The nine years of spent fuel :torage at Morris have resulted in an almost un-detectable environmental impac+
01.3.1 Additional Background Information Background information regarding the Morris Operation may be found in (1) through'(5) for MFRP history and in (7) through (9) for fuel storage.
Reference l
(9) I.B contains a concise discussion of Morrds history through the time of the fuel storage capacity expansion to about 700 TeV in 1975.
t 01.4 Status of Licenses A list of licenses and permits required for Morris Operation is contained in Table 0-2.
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0-3 TABLE 0-1 APPLICABLE ENVIRONMENTAL 00:L'MENTS These documents are d.scussed beginning in Section 01.1 Identification Item Source and Title Number Date (1)
GE; Applicants Environmental Report - Nid-NEDO-14504 June ;971 ass: Tuel ?ecovery ?im :, Morris, :::incia l
(2)
GE; Response Oc AIC Staff Questions Regard-NE00-14504-1 October 1971 ing Applican:a Envircr.u n:at Repor:-Mi6.:es-Fuel Recovery ?lm :, Mern a, :: incia.
i (3)
GE; Applicanes Invirmmen:at Recorc Sur:Le-NE00-14504-2 Novemoer 1971 i
L - Mibas: het Recoveru ' lan:, ~~
=en:
?
~
Morris, Z;iincia.
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(4)
GE; Response :o AIC 5:aff A ss dens Regard-NE00-14504-3 August 1972 l
ing Applican:a Envircr. men:at Repor: -
i Mibes: Fuel Re::very ? tan:, Morns, : ;inois
\\l (5)
USAEC; Final Invircnmen:a?. 5:a:emen: Rela:ed (None)
Decemoer 1972 i
- Cpera:icn of :he :he Nibes: Fuel Re-i covery ? tan: by :he Ceneral E;ec:ric Company; Docket 50-258.
(6)
USAEC; Invironmen:at 5arvey of Transpor-WASH-1238 Decemoer 1972 l
- a:icn of Radioactive Matericta :o and From Nuclear ?xer Plan:a.
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( 7)
USAEC; Ltr., Chitwood to Rouse, subject (None)
Au9ust 1974 I
Envitcr.~en:ci Ccnsidera:icns-Easuance of l
Eccili:y License for ? ssessim Cnty; i
Docket No's. 50-268 and 70-1308.
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(8)
GE; Safety Iva!uation Repor for Morris NE00-20825 Maren 1975
)
Cpem:icn Fuel 5tcrage Eapansion.
l (9)
USNRC; Invironmental Impac: Appraisat by NR-FM-002 December 1975 l
the Division of het cycle and Ma:edat Safe:y Related to License imen6nent for i
Ma:ericia License No. SNM-l265 - Morns l
Operation Tacility... ; Cocket No. 70-1308.
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(10)
GE; Samary Invirceen:al. Repcre - Fast NE00-21624-April 1977
(
5torage Facili:y Eapansion fx Mc.Ms l
Cpera:icn...
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l D-4 TABLE D Cont'd (11)
USNRC; Finct Invircre en:c: Sea:e en: en :he NUREG-0170 Cecem er 1977 Trcnsper:ction of R:dicactive Mc:eMc! by (Vols. 1 & 2)
Air and C:har Mcdes; Docket No. PR-71, 73
.(40 FR 23768).
(12)
USNRC; Fina; Generic Invironmen:c; I.-cac:
NUREG-0575 August 1979 sta:emen: :n HandMn; and stcrage of (Vols. 1-3) spen: Ligh: Wa:er ?:ver Recc:cr Fuel.
(13)
GE; Censolida:ed Sciety AncIysis Reper:
NEDO-21326C January 1981 for Nords Cpera-:icn; througn Revision C3, January 1981; referred to as CSAR.
s (14)
USNRC (by Pacific Northwest Laboratory, NUREG/CR-0956 July 1979 1
USDOE - Battelle Memorial Institute);
PNL-3065 Cc=en:ary cn spen: Fue; 5:crcge a:
Morne C: era:icn.
(15)
USNRC; Envirent en:c! Irpcc: Appraisa; Re-(None)
June 1980 ic:ed :o :he Remuci of Mc:encie License 524-i265 for :he Receip:, Storage and i
Transfer of Spen: Fuel; Docket No. 70-1 1308 i
I (16)
GE; Cperating IcpeMance Reper: -
NED0-209698 Novem';er 1930 i
Irradic:ed Fuet sacrage a: Morde Opera:icn - <ianuary id72 c Decembe" LJ30; including revisions through B4.
i (17)
US00E; Finc! Invircr. :en:c; Irpac: 5:::emen:
00E/EIS-0015 May 1980
- U.5. 5 pen: Tuei Policy, Vol. 2 l
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0-5 TABLE 0-2 LICE'ISE AND PERMITS REQUIRED FROM FEDERAL AND STATE AGENCIES Issuance Expiration Action _
License No.
Date Date Registration Radiation In-None 8/6/ 71 None stallation, State of Illinois, Department of Public Health State of Illinois, Environ-063-806-AAC 4/25/78 4/18/81 mental Protection Agency, Division of Air Pollution Control Illinois Environmental Pro-1979-E0-440 5/11/79 5/1/84 tection Agency Water Pollution Control Permit; Evaporation Pond Permit U.S. Nuclear Regulatory SNM-1255 12/3/75 S/31/79(a)
Commission, Materials License Revised and Reissued for In-creased Capacity of Facility State of Illinois IL-00329-01 8/14/80 S/31/84 Department of Public Health Radioactive Material License Amendment No. 5 Illinois Environmental Pro-1976-ES-408-1 9/17/76 None tection Agency Water Pollution Control Permit, Land Disposal System Permit (a) Pursuant to 10CFR70.33(b) the apolicant made a timely filing for renewal of i ts license.
Therefore, in accordance with 10CFR70.33(b), the license shall not expire until the application for renewal has been finally determined by the Commission.
9 0-6 02.0 NEED FOR SPENT FUEL STORAGE The need for storage of spent fuel both at reactor sites and at ISFSI's has bean analyted in (12) Vol.1, 2.0 and 3.0 series; and Vol. 2, Accendix I.
t 02.1 Need for Continuina Ooeration at Morris
- General Electric needs to continue operation of its spent fuel storage facility l
at Morris in order to store: (1) GE-owned fuel, (2) utility-owned fuel either l
presently in storage or to be received pursuant to existing contracts, and (3) f otner utility-owned fuel if necessary to fulfill existing limited comitments l
to certain utilities-in the event of an emergency situation or lack of full core
' discharge capability at their plant sitas.
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.In addition, the ownership of and responsibility for additional fuel bundlas l
originally supplied by GE to four utilities are in dispute.
The resolution of l
the dispute with three of these utilities has been postponed. GE is in liti-gation with the fourth utility.
It is GE's position that it does not own and f
has no responsibility for any of this fuel.
Continued operation will also have the advantage cf providing a storage place j
which could be used to alleviate temocrary, emergency storage needs of utilities, f
such as Dairyland Power, as requested by the Copartment of Energy.
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Others foresee specific needs in the near future for continuing fuel storage coerations at Morris.
These forecasts are supported by the broad base es-tablished in generic studies (12) and (17).
03.0 SITE AND REGION ENVIRONMENTAL DESCRIPTIONS The site and region are described in (1) III, 1.0 - 8.4; (5) III, A-F and j
Appendix 3; (13) 3.1 - 3.9 and Appendices A.5 and A.6, and Appendix 3.1-B.4 l
r and 8.9 - B.14.
Subjec: of le:ter, :auson, GE :o Cunningham, liRC, iaced April 25, :380 Cn Dece :ber 3,1990, cver the vero of :he Gove:~1er of I;;incia, :he T*incis l
l General Assembly ence:ed in:o I,cu a ataru:e :ha: bans :he impct:a:icn for 3:orage i
\\
in:o :llinois of any apen: nuclear fuel which vas used in any nuclear rea::cr l
l Loca:Ji :utside of Zi?,incia.
Tnis 3:a:u:e is aubjec: to Li: iga:icn :::acking its l
(f:o:noce con:inued :n ne:: page)
\\
Some added : ments are con:ained in (3), (3) and '1)
- -. -,. ~....- - -. -,,, _, - - - - _., _. - -. - - -.,. -
- -. -. _ -... _ - - -, _ - - - - - - _. ~.. -,
D-7 04.0 FACILITY DESCRIPTION The facility is described in (13) Chapters 1 and 5.
05.0 OPERATIONAL HISTORY Operational history of Morris Operation fuel storage activity is centained in (14) all sections, and (16) all sections.
Item (16) is revised periodically to incorporate significant data from recent operations, including environmental monitoring reports.
06.0 ENVIRONMENTAL AND RADIATION MONITORING PROGRAMS Monitoring programs for Morris Operation are described in (13) 3.2.2.4, 3.4.3, 3.5.3, 7.a.4, and 7.7
- and (16) all secticns.
07.0 ENVIRONMENTAL IMFACTS OF PROPOSED ACTION The proposed continued operation of the Morris facility through the year 2000, the subject of the current licensing action, involves a possible continuing receipt of scent fuel until the present storage cacacity (about 700 TeU) is reached.
Non-radiological imoacts, including use of water and effluents would continue on about the same unit-time basis.
- For example, see (13) 3.5.3 and 5.8.A through 5.8.d.5 and (15) 5.2 and Appendices A and B-3.
07.1 Radiological Imcacts The radiological imoacts of the Morris Operation from ' January 1972 through December 1979 are presented in (16), Chapters 2-5 and Appendices.
Under 10CFR72, fuel received at Morris Operation will normally have been coolec at least one year prior to receipt.
Stmmarized data for fuel in storage at Morris Operation as of August 20, 1980 is contained in Table 0-3.
- cnsci:u:icnati:y for, =cng ::her re acns, i: posir; n unconsci:u:icn: burden wcn in:ers:::e ocmerce.
See Generat 5;ac:ric c==ny :nd Ecu:hern Cali':mic Edison ::many v. :yrene C. ?:hner (A::cmeu kner:L, 3:cre c ' lLiincia) 2: :L, 60 : ds:s G.:. :%incia :ece :cer 24, :350).
.~ne 3:a:e of Z %incia has also lCed an enf:rcer en: :::icn under he 3:::u:e.
See.=ectie of : %incia v. Scu:hern ::~.i-fornia Edison Car-cnu, 3C-12-543-C5 (*3:h Judi:mb Ccur:, Grundy ::un:y, :%incia, Cace".'cer 24, 1360.
- ha: fa, :ha =cun: of va:er used per year er :he =0un ef ef.-Tuen: frc-t :he bo** ar per ?eCr.
0-8 Radiological source information is provided in (13) 7.3 - 7.3.3, and off-site dose assessment is contained in (13) 7.7 - 7.7.2.3.
These analyses assume 750 TeV of spent fuel and only 90 days cooling; therefore, these analyses. are very conservative when compared to fuel cooled for about three years, typical of the newest fuel in storage.. Based on the experience data contained in (16), occupational exposure during receipt of fuel to reach storage capacity, during routine operations while at capacity and during transfer of fuel should be about the same as previously experienced.
Continued efforts to reduce occupational exposures - - see (16) 4.5 and Table 4 - should reduce exposure incurred on specific tasks as nell as overall coerations.
The proximity of Dresden Nuclear Power Station (ONPS) has been considered in relation to coerations at Morris. The measured and calculated dose commit-ments from Morris are a small fraction of the ONPS dose commitments under either reatine or accident conditions (or both).
See (13) 8.1.2.
l 750 Teu xs uaed :s a ncdnal : paci:y 2. wing Licensing ::ivioy, bu: 13-cui::
capaci:y is n ou: 700 Teu.
l-
0-9 TABLE 0-3 DATA
SUMMARY
FUEL STORED AT MORRIS OPERATION August 20, 1980 Item pWR BWR Average Surnup 26,700 mwd /Te 3,600 mwd /Te Average Age 6.9 years 8.7. years Oldest bundles 51 bundles 29 bundles Discharge date Acril 1970 July 1970 Plant Connecticut Yankee Dresden Youngest bundles 13 bundles 5 bundles Discharge date Septemoer 1978 May 1975 Plant San Onofre Lacrosse Maximum burnup 40,550 mwd /Te*
18,990 mwd /Te#
Minimum burnup 10,760 mwd /Te**
196 mwd /Te##
Point Beach C-64 discharged March 1977
- i Connecticut Yankee C-52 discharged April 1970 j
Lacrosse I-22 discharged May 1975 Dresden CN-506 discharged July 1970 07.2 Transportation of Radioactive Materials The environmental impacts of transporting spent fuel and other radioactive materials have been reported in (6) and (12).
As summarized in (6) Summary and Conclusions, the risks to the environment due to the radiological effects of transportation, including accidents or from cermon causes are very small; i
also, see (11) Volume 1, 5.9 and (17) Appencix C.
These small impacts are quantified in Summary Table S-4, 10CFRbl.
I i
0-10 08.0 ENVIRONMENTAL IMPACTS OF POSTULATED ACCIDENTS The environmental imoacts of accidents at an ISFSI have been analy:ed in j
(12) 4.2.3-series and 4.2.4-series for related transoortation accidents.
f Analyses of accidents is also contained in (13) Chaoter 8.
i In all of these analyses, the dose. commitments are extremely small and well within the requirements of 10CFR72.68.
f 09.0 SAFEGUARDS S'afeguards have been placed in effect at Morris Operation in accordance with j
a physical. security. plan approved by NRC. This plan includes a contingency j
plan and a plan for the selection and trainir' of security personnel.
These l
Plans and cperations comply with requ4rements s.
- 10CFR73, i
010.0 DECOMMISSIONING A decommissioning plan is contained in (13) Appendix A.7.
This plan has the l
princioal objective of decontaminating the site to permit future unrestricted I
t use.
i 011.0 ALTERNATIVES **
Alternatives to the continued operation of the Morris facility whien have f
been considered, include the following: Close the facility as it stands; j
replace the Morris facility by constructing and licensing a new facility; j
transfer stored fuel to a private or Government-owned facility; return stored l
fuel to the nuclear power plant where it was used; transfer stored fuel to any i
nuclear power plant that has storage space available; reprocess the stored l
fuel; or dispose of the stored fuel as waste material.
None of these are feasible alternatives to continued ooeration of the Morris j
facility for the following reasons:
f o Closing the facility with stored fuel in place is a j
violation of regulations.
l Also, see (.11) and (17)
~
Subject of letter, Dawson (.GE) to Cunningham (.NRC), dated April 23, 1980 l
l J
.=
i 0-11
]
i o Reclacing the existing facility with a new facility is j
inconsistent with the current energy and environmental
{
policies of Federal, State, and local governments, such as those to reduce the use of oil and protect the environ-l ment from unjustified construction projects.
o There are no other licensed, private away-from-reactor facil-i ities with sufficient capacity to store the spent fuel presently j
stored at Marris, j
o There are no known government fac,ities for storing the spent fuel presently stored at Morris, f
o Returning spent fuel to the source power plants may be impossible due to lack of sufficient storage soace or in-l advisable due to storage congestion and loss of the 3,lant's f
core reserve.
It is also inadvisable because of additional handling and transport of fuel whicn would be required.
o Transferring stored fuel to power plants with space available will create future storage problecs at those facilities, j
o Reprocessing the stored fuel is contrary to current governmental policies. Comercial reprocessing facilities are not available j
in the United States.
o Disposing of the stored fuel as waste is not ;.ossible due to lacP l
i of Federal facilities.
i Of the alternatives considered, continued operation of the Morris facility
{
represents the least environmental impact. Closing the facility with fuel i
still in storage is not considered a viable alternative because it violater l
regulations. The stored fuel must be removed or the facility must continue operation.
Replacing the facility requires additional land and resource
[
i utilization and eventual transportation of the fuel and its associated environ-mental imoact, small as it is (.shown in 10CFR51, Summary Table S-tl.
Moving the fuel to any other site involves transoortation and if moved to power plant sites its presence may, in addition, necessitate plant shutdown and the conse-quent loss of electrical power generation.
Reprocessing of the fuel requires
[
cransportation to a commercial recrocessing facility - - none exist in the l
l
.,,,,,.,_..-,_._,.y.
- - ~
s 0-12 United States - - and the additional environmental imcact due ta the process (shown in 10CFR51, Table S-3),
Discarding the fuel as waste requires trans-portation, land and resource utili:ation to construct facilities for such disposal and results in loss of tne energy value of the fuel thus disposed.
The latter two alternatives cannot be accomplished because Federal policy prohibits reprocessing and Federal policy for waste management and disposal has not been implemented.
l 1
012.0 COST-BENEFIT CONSIDERATIONS The renewal of Materials License SNM-1265 will permit the continued operation i
of the Morris facilit/ to provide interim stcrage of spent fuel pending im-j piementation of the Federal waste management and disposal program.
The continued operation at Morris provides storage for about 315 Teu of fuel currently in clace and an additional, capacity of about 385 TeV that could accommodate future needs of General Electric or emergency needs within the nuclear industry.
The costs incurred to obtain those benefits are nominal, consisting of a small, j
almost unmeasurable dose commitment to the regional population (15) and those j
along transportation routes (11)(12) - - a total of under 300 person-rem over
{
the next 20 years,' including occupational exposures - - operational costs of i
about 53 million per year, and decommissioning costs of about 56 million l
(1978 estimate).
[
The costs of not renewing the Morris Operation license involve radiological dose commitments equal to or greater than those incurred in continuing operations.
as well as significant costs that would be incurred in any alternative con-
}
sidered, including potential loss of electric power generating capacity and
(
increased importation of oil.
i 0
13.0 CONCLUSION
j The fuel storage activities at Morris Operation have been shown to have an i
environmental impact that is so low is to be almost unmeasurable (16).
Pro-jected imoacts over the next 20 years are essntially no greater than those in l
the past. The benefits of continued operation are much greater than the cost l
in terms of environmental impact, even when accidents at the site or in trans-I
?uel :rans cr:c:icn ucata are no: included because :ranacct ta:icn e::ense is no:
I an in:egral cos: of facili:y opera:icn and ucuid be ine. bred in any \\>iable at:e..azive.
l
~
Opera:icnal acs:a include tcu-level caste n.icmen: ::d dia:cs"
)
l t
b l
0-13 Portation of spent fuel are Considered.
Therefore, General Electric has recuested that Materials License llo. SilM-1255 be renewed for a period of 20 years, 4
e l
i
l 0,14 COMPARISON APPLICANT'S
SUMMARY
OF ENVIRONMENTAL REPORT INFORMATION VERSUS REQUIREMENTS OF 10CFR51.20 References are by section designation and - - where noted - - by reference to Table 0-1 in the attached summary.
Part Summary Reference 51.20(a) 01.0 through D1. 3; 03.0, 03.1 (1)
D7.0 througn 07.2 (2) 07.0 through 07.2 (3)
(4) 011.0 (5)
~
(b) 012.0 (c) 05.0, D6.0, and 07.0; escecially Table 0-1 (16) all sections.
(d)
Adverse data included, e.g., Table 0-1 (13),
7.7 - - 7.7.2.3 s
ATTACHMENT E GENERAL ELECTRIC COMPANY ANNUAL REPORT 1979 Copies of General Electric's Annual Report for 1979 are furnished as follows:
o U.S. Nuclear Regulatory Commission:
One copy with each of three signed and notarized originals of the amended application.
o Service List: One copy to each addressee of record as of December 31, 1980.
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The Chairman comments i
The Generd Electric that entes the decade of the Genergt Flectrk s pertormanre h 195 ringed m.t a dec-l The cottook for the first hn't of 1990 reflects rediwwt Inv-profRs shipped nf tricer inflationary Inreemarws - have ch of ecnnomic activity.tml GE econnmhts do ret Irwo-taihd m beep pace wnh the vtsing ro,ts os mrtarbg hisad-i 1960s is thorpty dtttarent from the Cmrpany that went arte of pr - Titabte growth in ymn intarest ag sha.e owners foto the tT70s. Todny we t*= rive worne 53% of our earn-Salog of $?2 5 Nttion weep to 9 4% from the 19 TR see a contract 6nn as severe a9 in 1974-75. They ewpect a ings martwnrwy and ery:Igwnent, mnednining inverwnries.
I grmhial acortnmic tgdurn bepmting in the inter months of and sn[porhng research and J.
W ; Thhterksctinn Ings not froat tradttional electrient equtpment bust-tev*l and contenetect with the $9 5 btHirm rentired a dec-9 riesees but from snotertots, rinhwsi resources, services, ode ene#er t 990, titA rio fessening of infrarion for the year.
In rent etypnrate retninerf earnings has wankenert capant and transportetten equipment compared with esdy 20%
Farnint t of $ f 4 bitfien were t5*.nhove the 1978 At Indicatatt by the nppenting reviews that follow in investment, with residting lowevert levels of prorhwesvity M 1968. and Internationet operations now contribute entaf Fnenings gawn ene the ten yr ar pmirwt endenrt the 4
this Anment Ikport. some of new twestne=ses wm tm at newt intee national rompetiftvaness about 3*% of earnings. eempered with ItP.back then.
Increa<e in entes g nwing from a <te* e deptasmed $ 14 i forted by the redtsrtirws in pronomer activity. bul nur tt H a 98tuation that enRM Int thmsp changes in national The r9ae General Electric for the '80s thers has a f ar pm sharein 1%9 to $6 20 pee store in 1979
- hmThs in fMMe*934 s that n's retnHvely imatterted by deactinn Bellevmg that the tirtl *tep towned this gnniis morJdtverse earning
- bs**. is more Internationne in Annmer a soitional mengewe of tmw yme ng them ttm rycks shoulet heep us o fset ttwsa negattve fartrws greatm p+he e./
J ;
,of inRatinn s mpact on the outlook, and te lest vulnerable to U.S. economic cycI*s.*
ownnes have benehted fenm thk darnata of sirresttut par-Genarmt Electric has onor grant =trengths as N enters witnf prorets nt rapesat fewenhnn. ynew enen.=gement wet formance h rettacted in your evidrwwts Ftw the fourth con-this new yent and new decnt'e come it,imtlahva twen in Is79 by ttw Financial Ac-g.
sacutive year. yUsw Direttms in 19 79 inrepated the dwi-f
- A n9w k9 managnment kam has been pigt in pinCe.
Counting Stanttards (he 9 CR) tJnder TA$H tender-
- e A. g y.g{;
}g g
's denet.twing6ng ttm year g totat tn $? 75 pm whea - morn gwov6Snq $ne nn ordmty k nnsition to young but twnedy step,snme 1.20t)tJ S rne nnies wilinchsde,in their
'/.
l than doesb'e the $1 1t) darkred a dor ade agn
}
ewpador cod tendmship With the retirement of two truty 1979 nntent ecpwis. mfintinn n tpmtad siapplementary
.j1 But tiene fleinnetal re=tstts me hamed rm trattitional entstemhng conhihutors to your Conpany s pecqress.
ttata that wlR shne hne entiniton escatales repmted snies
-'N[
d 4
).Y Iy morexmtmo mr-tteds wh6ch fail to eatbrI tha== tent to Vire Chairmen Dave Dance and Jark Pmber, three mm amt enenmgt. tainet shnrttn% Ire depeedntirm prownlons, d"
whk h U S Industr y and the puNor cenpratty have been l
Vire Chattenen have teen elected and have joined ynew and boostt eits tive tas intes to crwmterprorbreve tavets Bon'd of Ol'ectms in add 6hort, mw depth of management Our GF nisppicmenemy data are onpages 7tt 30 humi nort des ded t*y the ravages of entisten whir h 69tnet l
u I
has provided tresh managerint tatent M head 16ve of cew Becaine we hava 6mg usert t.trO {tast in test out) reportad financid results ihat k why theta comments CWlurte with a ef'trutsion (.1 the entlahnn issue. and why sin Sectors amt to filt other key fasitions. repswfing out the arenunting t<w drwneshc inventories. GE hat minimized I
team who welllead ymn Company intn this new decartg the "phantrwn" inventru y ps ofits thq retult from F ff'O we have made inftstiort the ttwma rif thH Armuni tiegm,t I
. TNs team wMI have the sigridicant nrfwenMga of a tmte-(flegt in, t.rst rnet) mernwitmg Hnwavar. Itm Crwnpany h t** tad 5t'nten c planning system that reatty works. Wten te se, lou =4y n'tected by tte Nghar ettertive ta= rates that a
For the '80s. a new GE: Over tha past dwnda. yamor man-i n
4 wnewes into oew 2 ens Of @wdt tmve h b*99n.In N* #Ad) IOII)s. our system was an ewperintan-gpqqtt fygyn unrtWherbthn M hhhg UnM GE emesaeow enr darMa* Charsaaa riacia.ed H.pnaag teranterigt, esih gy y wow.= ti.=i raawn no.4 s.,
proved Genms Electric's nNiity to enpc wtm tte ettacts nf talirke Hut it has t*ronw e aay of ble kw us et GE.
You wm nnia onen est supplements.y data that, altar inflation and have grentty #versiflart arvt strenother*ed tt*
ennbling gn to idatWfy those bassinawes with the greatest pre-taw emnings n.a adpsstert int the impart ofinRation P"'an""n' **'"i"P 9'o*N' ""d b ""noa4 M *** **
and #*n eadncerTy in=as e*t d*>nds.yme Company Company s earninos bea IM in the rre sh ** yaas of f
resmwres needarlInt their fuH J
' 6... /
retained Inr tamvestment and growth oniy 16% ne pa tow 1MR.Our 1r n<tetinnat electsIcaf e pr4pment twrsme*weg ne j
- Wa en ar 19R9 wNh substantint herkingg ol unhlted rw-Barningt over the t475 79 partnrt The comparable e
coemted for some lt0% ct earnants h 1970. they penvkkd
'i atmut 47% That 11 st!!1 a gubstaittial tigtwo. Imt the de a dars. ewpanded by a stmnq instom of awport ordar*
smount trw eN t) S nnntenanriat rarpornMons was even Tha paw t'onkart1 negntiritert with unenns in mirt-1979 lower, et Ift% iles tomawb.it more tamratele tituat6rm frw matic charwya M eepeegents comes trewri a combinatirwt of stratagic puning of certa.n bershiattas nrwt iha *perf ace.
give tts a peaceful start on Hwee yamrs of prorbsrteve reta-yois Cnmpany provietet hitta sathtmiinn, hnwever, when teoriships with GE employees we see hrew rior irstiatirin adFr= tert data e.cata drven new las growth of other bestinetsas.
. Materials inchwfing thennt il anet metani,rgirnt p.yg.
. With cash and marketable securitias ammmting to $2 6 saias and enenings nrut shnw that mw regwwlatt deprecin-pets as wall as the naturnt resnam e added t*y new mbing bitslon. plug a triple A credit rating.we befieve we have the tinn awrentes unrtare.ta'a oest teat eng4tal verovary peerts e miata. Utah inte+nationit Inc. - rwnwided ? 7% of *arn-8h*ncina s**mr* to sea vs #wough the economic down-by sorne $ns mminnin I979 shna
~
r hen amt17 t tance a new wave of growth e#inveshnent IndustrywMe et=1a ganerate% this F ASR initiateve w
ingt in 1974, compared with 6% irt torift
. services hinine==es inctu tino hnanciat. intmmaton, orpadun*es world*i(>
wm unrimscore the rnaa tor rastn ' wino u s corpnenm tvroadcasting. Irwtattation. maintenance antt repals tarv-
- Our 1979 plant and aginipmant ewpamfitures of $ t.3 bil-inenme taw provisions and posicw o as to mitigate the ices mrtved up from 10% in t %n en tfm.of 1979 enenhgg lion Inp oft a dacada in which we invested $7 9 hitton to impact of inflation o, the rapitar.mntice sworweg Tha t
Yrarmprwtation erpsipment, mret'y aircraft engines and twovide an espandad. mortarnirad prorhntmn ha*#
results of the mnte ren8khc rapitat recovery allowanr*9 hcomoHvet, vote to 10% of eatnings in i919. rompared
. And, perhaps most critical of alt 10 th* luture, we have eru3 othee remmtial measures that tursinemmnen are nde the mamanhan of resentch and rfeveinement swogenms cating to nin tenmintn,s witt henchi rot only irwtustry but w th 4% n tus
. And iotat irternationat nemat.nng. mn.i of whird are that totsted s t 4 tutiton in 1979 gworbeing a verunNe We nation as a wtwile Py siteng'hening the Hnw of invett-includsed in the perterstage9 htova. penvirted only 86% of technological ranaissance for Sa Compney.
monts hat enhance inrtermtry's gworturMvtty, they win strike our emnina,in ius compa ed aith 37% in i979 u s The*a strengths rhm*t enua Geneen Electric in al or. ne innatinn s primary eno=es and wat thus hnip n ve e
puptwt sateg. atoria. vote from $ t(W1 mellion in neady $2 9 ste9f ain its Maritity as a geowth company. withInng term thk cmmtry a more stable fenwirtatinn for its ernemmec and (trowth rat *9 Wall nhand of thrMe of the If S prennmy sncjgl pengregs in then 1Of =ps billennIn j979 These generat mmparIsons refiert the r** Generaf Etertric that yrner mannaamant eteveinped in tha 19 ffM -
The impoet of InnaHon Of the challengas tactna tha u S a Ganent Flectric tar tarcar. mare (fivarse. vama prnhta.
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1 Industrial Products and Cornponents: ' * " ' ' ~ " " ~ ~ * ~ ~ ~ ' strengthin allmajor markets i om.,, .m e. mar,r,4,..t.m.a co,,,-s - _,,m.3,s,, Ga.,m al,,per._,, ,._mmt ,,,..., G ,,r., ,,,o. ,,r,,, c,,,,_r,,,,ct,c,,op,,,._ ertut metnes for ewaveforg and motortied wheets of +m et the tirst pe netienl inraewtasemit tamp. GE lighting Cow Henvirasting Corpruntion Aper req'd'ert diepnsition I
- t%if1*sses contemind to petgiha ;ipp Irmryvations t hate of fettnin Miatsom. ItM new GC og*tatinn wmstd inrturte buiNredrige
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- s.,2e suae swo smi ersigmages have. es an eaatT a. corittihisted to national Svp televhirm tfatww*s and tiu A*A Pnd teven FM wtio l
~ - ' ' - -~~if ^~ M ~ ~ ~ M ~M baUIage WehIrt*9. and comput. fired mnChine-toot con-i N[~ ' ' ~ tron;(ttattom) diesel-electriclocornettveg pred sannet I i electric motore es componente in nppfinntes. i ,argy-con =muntion efine ts with Itw4, high et'iciancy sisonns. pin ent*vkinn opmatem w P ,at s.qh me mity dkcharga inmps that ma. n worthwhite to "piare old II hthg syqtpfm with e,ew samps that save pn-Geneggt (tectric Ctedet Cgrpotpflon (GTCC) cat ned $90 Q tqy and teduce energy costs emninn in 19 79. repementing a sheng 17*. impmvemerd 3 for tha 3 80cmotive market, tha Company bfmehred o ese 19 78 rews. as highet in 3mm on an mcrea ed prwt-l ' g,;;t_{ tr.tw os eere vabios more than net ci heter inte.e t==- ,7 m t an n,*ym v r. inn or tha now h+ nan h.adtar ms. pan.. Te.e. .anies m this ohnity ownmt nnnenmna-a;- ) g. }4
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- rg *. 3 - ( .h-t wa ordy one it+d n nur h as mit gim inmps i r O*her paw prodexts inti + Circhea
- a circutar nu-dated ' antv e attinate waen mnee than $ 73 b.ittinn at tha
. O y,,. - i -w - oo,. i, 9...fiactino g.owth or nemty s t tetiirm L . f ' E,' 4.,c-iigt,t t tama tn cs.nd,.~r ine,,+,-. Pacement appiiratinm newt blat h16qht and decorator kw the yi, distributert almnat evedy tw tween GECC's .yy'... j j, ' 1, ', msions of the miott Stik
- uMt Consurw < nnd its Commarcial and leatustnal financmg
( s- - :- + .-,j't 1 4 Anirnpottant 19791nnovatinn withinng term signiti-twasinets * *gments pae page '19 he GFCC condanged g pp
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,mp. the n,=t high intamity di.ch=.n. tamp toe hnme moadp.*tecipatinnintugh growthenerny eeistad
=ghtinty The Ita' art lamp h scheduled to two maehMad in industrlas ron ibuted signitirantly to Cnmmercial and l
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'ona n, the n si of a fanaiy r.:inna e,taiamp, that me onty inim.wiat bu=inemearcivableg asim or s9%. wNtegaina m
y n4 tw d ng much **ct-irity in nenmata sto sama et 2ss in the Consumet wqman eenertmt c=parvimt par-b ' (ig ;,e smrpJns of tight as tha incantietcent tmeibs they rephce vicipation in britmo equity ele ariring aeed the impart of g
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- ,t non nie p.n nwimsurrese.c.egoneonet.
.'Qh w surem. General Fiactrie maintainod its itow ot naw tiona,Iy.tt* Credit Corpnentum temk an emport mt step in mndeiintro tuem m provide romum.c nnancing smvu a in J' pan -- -,* [' E ['. i .w -tuc, **iaN to mah
- l'onho lm5 l Hnt wennwe agremnent with T<.st iha C.ertit Cnepora6nn l
swasening-digitni ci.ctron.c a ru'dna it* GreM 3979 p io,en wa,..pm d t pa,n+ aim m.,'s Anniher impnetens piement nt the Ce.rtet Corporation l .n.rroproce99er technnioQy into tinck vadbs And the n.4 q g w.,, g Q.,,.,.,.,,'.~m
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,ars.,ro.c eoumminn ow oners tar,#,,e. wy. i ' T' ' i a.cuonie cemwon and en=y cienn.amovahie ran.8 e ategieaw twin s, as e,muit <a st ono raii na i roit-h p i i
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- w.. e Eng sinck and midolenwg artsvities. GE CC partes:ipation
- + Mr 13 x yt A I .p te vt. ion,eecivm opa,anons.cwevad go,,d s*, and in ma w h,owm.ruvny,nn e manicipie,t du,ina 1979-o i 6, 3 p>( - L :M. e g,1 z $ "0 h. NC 'L C *,, --nino,gningin 1979 signmcnnny h,o -pdom te n e- =sume andincreated retait,atm of or coto, TV sets The outtock renacts wvernt tartors that ewmiet enmNna ieA- +i ,,[.p 7-t 't ( od.otapar.enedars enet wet seeaen inno inme Tawvi-to p m*>r. gnna comumee ma.6af,in tha ionos. such n . g,.Q.:,, A,e g;j v p owm tinm in ta,ey iormanns and a m. yming n.us ,v y ,. g.. g. - r.gaa,nop wicomt+d.sih. - tm.isv.pu. cam mset 4a s nn ih. ,ets n,nt,%t-dio m,gws vg. / %y! - innovno m, inch, dad.1v e-t-noi sy+- that M. g n /j e. .ppiianc... t,em~n-,.nd i v,ets. idimm.~ .w, +wm, to rnor.en.,, m mt.ane s io in.n. P ;gnCg,g, Of@.. w .tannn sas.ctinn. and n pmerammawa vi<teo enswrie re-targa repincoment marhats for the<a pendnets ntfer nepor-3' - 4,. n0po,g.p0e. y, p%,, bx,..', t . ~. '. D < ceda, mat. ft...ch wa.nty parin<t per,niis recordmg tunni., to tmsinnse, that can meet com ' dm*,m 0J . - ~. z. 1 ..t., t ny. nv. dmm ni n,ng.a s a, datm.ni nme, on in. innovanve ene.oy amrt-ni.high nu,tity pe,et..rt, ,cJ - ,..c - t- -emet ch.nn, A ce,,,, ue m ies, enmny wut. shmi t m o. mu4 m..ed ~ s-rio, 0 c g, f G,g;y. C,.p. . yM g -} m ,c ' g r 'CgC Q-
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.aa,e,oegoino,c .s..,,,,on. -oy - evpa,t. in opttei,e e., ~,n-m -f,m s ne tt,- - r _gg 1 n w d cad,hy met *ing suono empha,a on pr~ met e a ero.de tiv, no camevi,+,,pno d..ewr., wn inrirmam,n nno emd. mi, imp.omnmnt. m,ri by h.rpe g ( ,kg p#y y, p [v, 1 .t Y, .+md of the peior y nt on o.ind =*s increatm GE eur-evpamionatng rvire,tiusin gsm t.=tain Ioto.tha .. - 4, b/ e .g ..nety op=ntas thrae vtw telavisinn statinm and itwee sarior tauncted an intansive m=h-tino anet netvartking d4' 5 c, ar y 1_.,-.-.,,__ -.ga n-,e, g _ e<._mt_. < {. }, y\\. o... .nc ,y m or,da.oru,nos,an,inemm ct - pro,.nn.on th h -ce hono,-m.m.,ini.e,= w. arnmaness eumrwmas to comuna the rwondentwg and comummeotthe remos i Z,n 5 r. npme,w.s i3 ystems ser.ngmaning enhar c_omrinen as et tha GE h'and c n n ri . i 9 Ariement ns.girist 997, e o --.~---=.,.,-,*.,-meu. w-wm--,w.----m.ww-., .m- .-u-- -...-..-w-* u
F m eveer t%wtw+= a.e c_ = two.w.9 Services eftered by the inreustrisi prodoets and Compe-The erwkrsWW perwt,rts arwt Ceenp=ww=M Sertar ach* vat Ivan*portation sys* ems twssinassas wrwinuert to grow m Service enr1 distrehutinn twirestas entwasried tiv thk ownts Sactor inchsde (top) a waridwide netwmh of appe-a sheng M*% eave ings improvamard on a erwt ItW m-gopplying $ae i ataoirlocomnevestrantit prendsinn Sarms inckwie rehstservlee shers handtbg surts prefacts es the re-cr==*a h revenuas Asof th ';artnr 4 map w twametses l ewyulpment and molnetiad wheels for large off highway 4pm abe9 *arvera shres. crimp 6 sing a woridekta reatwor* of taevnt6.s pover ng maadananre knpactirm_ a vehet es, ggc,,sharpty Ngher egmengs achaved by tr.eme i d Tha bun $ng of hydroMectric genere* ors; and (bottoni) di9-sbarad in this growth. inrtatew GE ry aratinne pov@ng g,,,,, ,c p,,,g,,,, g,,979 pere kd by Inr;omo-repan erwt ietwatrvng N 6natustrW agsspment prortnrert 1 markets with captini arys p rent, con cnnant prorbres fr> trthuelon services of the CE Supply Company. a cewpnea+=rt tay manutarturers anr1 rnneactrws inen theer j teva opeenenne. whkh showed gmwing stranrdh ha ->= ries-t y Ganarat Elactric arwt athar marmstacht m9. W4h shase De markete senpa Newwwsmq thate poht qrow h m 1979. nie Company a pencbjets traneprwtatMn sy=irm*. atyw afne repair marv-Saews rd O*re rnt Fhertdc incomotrveg rearhed e invastad ture*r in Weer *epanginn. netdbrw3 asoht ewme 6 ret nors supply center 9 eng e cctrirat arvf sestartMad a a naw hagh in 1974 as tha remun of We evpanshwi os coat shnet during tha paae, twinging io I93 the eum+ar reaeni- ~f~ prtwfuctg The industrial pmrbrjs and Comennents " actor hauinge erwt ihn incesase in peqqvbar+ opmatines tav U S Ing wartrt==te 1-t j , I-A in adrt.twm to rww Iari# ties GE inva=ted in iha graw1h ]e ] K pretwsntad kw *'U% of Intal Gee ** 48 Ftnride revenung raeronds g Garmen F ><tdc connnuad to sigtwy high pedos-of its seevire enverage. inclurtng new capat*4ty &w
- in i979 anri19%of tre yeme 9 eaeamot h
see I ( a p/ i E" activa at the t ginning of t onn.tha S~ tor ns in.nre propu sinn equipermnt to the rmi iranse wwhany boorting maw *. intnenreve,==1 = ansa empn.nt. g 3 e twearse. mmmtaaanca sarv re trw s=4+gasr and *ub<t= r a c euch,*s in nenmera a nrannn os comrany e-sawrm ouring w.yaar. th. uassachusatts nay Tran= porta ion n \\ 47 [ ~ ~. -4
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io==fu om** oronttun> ties ihm reprwt w ha<ad an the l Authn Ny orda tre 190 prephon and contrat weg was tione, n== <arvice for inntreW cvone erwt twet ennwea-comr akt erws en ordar for 300.=nnar sets was veraeved nance. amt e panded wevice erw hyttoaleoie pames a +
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l tvm em ctdengo Transit Aumosey Transit cae oparstores wnhnrwyassof n.nai m sf3dre cap,ity no.6.ma g___ gb(* 7p g na org,neratmn $=,- , g.qL e,n enmpi.%d me nya,haue et as uawnanar e.s eers ont me,t ce saas hmad nppariunn.m for,eb.,* ting an.n. y cane,,e Etacide a motor teew =arve a twe.1 rac-4 dnnert c are anet.gwy areng e* capacity of a=m 8ng ne** e inwn nr m+r=wiat marm.tt many ot =hern =~e wannth-u e Mong me an+aast erwridnr t ' 3 Sams nt Ger=4 Eurin ennenetred wh~il drhres tar Ahn ew=q 1979 ma %i genamoinstonnantatma j c anad hy u s ihduery s inr.<ma<a<t cataat i wastmac ia c - w_ a p:.nt.nr, ~,,,,,,en, io bem. pree~ty - by etor t, io on hign..,,,tecies
- r. strong-in im.retincting ar=, erw,w.nea,.er, a,,,~r. wrma..,..pa,, dad te arh,a gramar -gy etnrwnry T haw twr+=wa ra-increswd.orm da damand lar haulaga vahietm kw inreurta eapau and cautwam e nt sp.9ahrmf iewohnna 1
opan pit cent onet enepar entnes arpsipment inn irvlapnndant contanos erwt ainior usars porverf gand increstas in carniewn in to79 on erwnemhat - D'***uhnn w'v'r ** pmvht=1 by ** G~*ent Elarkic high-saias The Cornpany *irst4 ned a >=+eship enia in senna kidustrial electronlee operatione had goe Ongs in-Supply Cormpar*y in rumenmar s in ihn enne actor. inrtm-h. l 5 S[1- -y, 5 4 e.,rtdc.nn.nts.4m.,cre.,edia7 we,ne - gy - crem, on < su high~ uw,
- W.come-
- tv n-ais n,. cE na w w+, y na.-nr* a m y rani-t onc*~t.fm ce per+e, imd Wa ang n.niers sor. a in cE pro + cts ami mn* er nm-apo -
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e s . ora and induWW manufFletreet ShmiQm W49 aNo in pmvkjlnq iarge dactricM tyskms tr9 pnwM inthtM*y Wmu of othar companwmq cag@nhypd on Wrangm9 m W9 m i - y .4 Q Wartwnin thee farm rngetaf $rw mnents Among the year s comen4rreants from customers Pvough-servert mnrhat be 1979 to arhave eno#wr yaar of im. t w cinhei ano.fs io e.p.ad e tmA.,4 , tira.9hi ouiiha -odd.as an nns-en. *ec*wm elve an.s.u o-ro ad re un, A --,tadr.rf ord., en=y.oricmg p ~ p p;y pW t oppnrionme, for inreen-1 s,*s ni n-ai rn-nir pend-mannn systa.m io equi, a na. hot crip swei mm in ar s invm ~y man,-n-,9,ysw.m is ha.ng; c [ ucts uch n mnine= tm e, m.n%nestey and r ww=s Taswan. e imerove s= vira in ceinmas Prodisrts inferiwir s'ing fieicmprocestor lachnology in and gartr Strars ior pil wa4 drstiertry rigg serve WidutFief cue mars naeds for ince*=wd perwturiev-The outlook is ice =eme tenmar*s of tha martets earvad vy rq I o ( )
- y inciurm e., uar* centory ioson ser*,n compu ~.
t,y maine.1* pemh.rt. mt cn,nonn c scant in a "t t cone,,eto, equipmene op--,nn, had anng==m.wt, -I ma+.t b, cemh.nmg etscia t m,r,p-teri,-,ondan the N weremseg on highae sales Onnthouad teghia els et tred numaricalcentrols ihee sww units tw shne sherw;m in 19AO whita othare may be nNectart t*y a jf v n r n-, .e,. o s om..,m, ,d ~ m
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e corttrois miO4 sena9 mprhir19 $nois . Crerr>ncecial erwt inrhesteisil conttructine9 rn Arkals n'a e4-nr.retirtantial heeJging t!4ris b 1479 GF rnarwft:lt'Itfr8's Strong starnantf Inr e actmnic power supphes enr ame pacted M vamam thong in 19R0. ntPiough eagwkntier 3 - n c anaf enartats a wwte eamla nf prnerts tnr ftds erachat, with a inrtrs on rpetr@utWe erwt citetM pre 4r fir;rt int ut*rs rif in electmnic replee, and Gaphratnes incer.asad vnhima ter structinn marhats nea intacn=t ln stN fore irt iha riaer farm elec1*ic power Iha Ganar:gt F try kic lina RMo incturies this GE predict kna The Company providadles r=1cus- . Dommtet marbets Irw Inenmouves shrmdd hokt at ecc-a &at purpo** con =oM. **mg dav'ces. anaf *tre amt bm ra=ar sure'y 'o a enarvit=ctur= of lawr-aquippat ord navais in 1Sa4 him a modama sirenamening M cahia praducts ma= ewout e+t-s pasad in o.=se=< puret,=se=. A,*t.rionas canarW riacner rir vairvenents rinring the %naret Ekctric s elec*ronic enmponenst twismess is. T he v=ert for enargv cmis-va' inn newt ter inreened ymse Inchysarl a two tatt cter 6ing FOO voit emby whirh ,soaltting tmm the electronws bnnm..fth stappad up tie-penttiertiv6ty otters innaar tem growm rytme somit%g as the ,i atta rts sata overat nn et punrh presa etripman'. news new rn=nd for samaranductrws capacones newt om. mactmnic cnmpany orks a speart riaveinproard ne na. wartermie snad =tah, phninamc>6e controm wherb peem t mtwe arn-davices supphed t*y the Company As a vasult of tha Onrm gwerksrig anff eyttares nnmiral arwt smobic tra ceara*.nn m matareat haartnng pany s ongning pneticipation m as ctnr automohaa re- . Iha need for modmn ow,ra erricient machir. inr44 and g,% arrhcaten* s**'ch. Geaaa' E* cide in'tod'* cad a 19 79 a a** tagh-awwe aart=shravat perwhenon emelemena skreg Amono many encay teamwd product, cammg cus-penw >=nc=en, mat is capabia ce wrecteng inega curfacts. The =rwiripates res pganca in mening shnu d =uttam r inmar arceptanre ert 1979 *4s ite nae rnrngwdm t'asad in tegs than a minienth et s sacorwf AMo during 1979. the mehats ter strives tew a=ravewwS. and mnterired whea8 C {(, pmgr nmmadia ughnnq enntent tydam that savat M*rgy Company enterarj We tet growing Squwt evyMal dMplay for haulmqa vahirks u1 t,y outom.ncany pmvhting tha rregramm-t amnunt os mar 6et Yba mniore ine ne*t oystni ampiw artw oinov g . cec.eh in.orwita ma niananra nrwe rep *, m=rnetg e o n hi.han news.twra r.adad in enmmard=t and hvbetrtat pmmesing. nnt= hey in ennsumar and instnimardahon
==vwt t3 tha nr ne+ work of =arvire shnps e, e,pacurt so 1, a twsilrtirigs Acphratmr:9 cnntinua itwmoghnert tha darnda t rw a.n w.aa ti to Aswissal nagirert 19*9 4 J
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k - an. l Technical Systems and Materials: e i strong growth for all major businesses t 9 I th-awisi vers vois soir isrs
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The diverse prodiscis of the Techedcol Systems ered me-Ces turbine rearations ghnwad twther ler.gwovement in inatntity to reenver instatinnar y emts through price Irs- --'~~ ~ F,e ~ ~ im~ M -~ ' F~ We genes for commercial strerott to elenutatoes for trniedng f*rtals Sector ennae from (top) the CF6 temity of )*t en-t ga re, 54 185 54 ses 53 eas $12%e marnogg hs 19 79, prirnarily nn the serength of the6e inter-crensas. nevt the decline in remi<teedial reinteurtirm. these ii.M.N,i~g,. national yWes Ganarsi EWtric o.n hat %as maintained Genaral Flectric bugincesn nra emphaecing progsams g ~ ~ ' ~ ~~ ttight crews;Sqd(bottom)fromproductionof 3 blCone [ 8 thew wasidwklet IPartatshtp in n f anga g4 ppptiggjinng ]$qq for cordtoffing cost % improving e8ew tenry Rrwt rnntohdat chemicots to Lenan' ptastica for a Yuttosta, stadlum, ,1 'eaenge me treturtas eteride estiHty paa6irin anst mid eanna pmver. nrwt Inn operations Genwth oppne tunitteg resulteria kom prodiert rtevainp-I j l rwn*rous Irviustrial applientions sur h as pipeline pinnp. ments a. t.sno purwed en tem me-, rhan =ondomas ing and othhorn en and gas plattarms pu.chawt Generni F iacteac time et u-a watthnur meiarg 7 _., m . gy ugh efficianes.,of enmrirned evciae,1Am (steen >r-newt gas turbirm) plante crwairmed to alteart potenttas eteg-rweigned to halp utihs6.s leves their dvfy tna f panlig mwt ,.p, wmarini.re.t.particuiareyine. eny etwn countrie, vn iayg Avsn. em company ma w tho fir <i commerciai c. - vj y;$ g
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, 3 i The s.rtor is deveinp.no arem qis h, rhine, to orve snip,r.md et
- Auiomane netm namhn, and contra ag t-international markets. In 1979, fl tirst twom was peacend
( AILtetAC*) had managamant syetsam whet h al8nes *e-wg) -- -. __ D $,8 4 v f p l prw the Company s advancad MSn0Fint 100 mw heavy. mote meter readinqgg ernt increamael utility letts*ance over demnews cycias i duty gn tuetWne I The outlook h for mngt pown synlems markets in temain j Nuclear systeme businegnat trases in 1979 were bwer Wugg%h I w the nest taw yants With rureent v hedutos e thanin prior waars. ag Genaral F Iertvic made fin ther sub-i stantint ewpandthweg on engineermo eiwt daveinpment in penectenq modest increnges in adiipmanri General Fiect,ic g enwar sy t.n= bee mess-n..Sterming un
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,,nort of nuciam penrtts in n he f *,, r h e e. their ettorH M sedura their crerr*ng retg lewer ovar-t i pendituen. In nddition in 15. cer rts ne desements nt ship-bend newt imptova tworturtivdy in ouim in get=n pe nino, p nants nno cancettatinns of =+9, nedag. are c=pected teven to reset in ennum.ing imse, em this emenms Concarred nbrust the ponibility of alertrir re-wer r.; The barkinq nt enters fne thesa twasinesses. incherfing shrwtinug in the late 1980s. Genee at t tertele managars nr4 r$ ci nuttent reactors.fuct asse mhfies and pined servir eg at orglng pggreisIvo eteveloptrworrt of alt prage,d enarcy hO yaer end i9 79 totsted $'s 't bithon, of erhit.h $2 5 billson is options.inrfudmo cons newf tw cwar pawar fr H their beliat geb.duigd ior shipmerd s iar i9e e ide comparatap bark-e j that erhna the tutge for enictear enaruy was mvfa mnra inq for 197s was ss i biman. nt wt*.h 52 4 bittinn ww omeurt by u aosant at ihrr u,* teand u,dt ?In 1979. 3: sctmiuwd for ssipmen. nets im rm ti.e o s utmty in-m_. du<try.canceit unn, of nnrum piants hava guhsta entry emcwar pown enn and siwmi.i con play a egnmcard. and sata. role in vedtK ng the pretant heavy devndente on N__ [ " - i f notetumbered snow Mder3 during tha tast leve yeMrs It is g ihe b net of banme occidc s msnyme nt me,e,ure.p-nn en,n,ts. it Power Systems Sertor hu nrqantied itsFnergy [1.
- tion ot neWar orders will req' pre mnra than senewed de-marwt for eiertrtrat ganet ating a+#vment tbare rrunt be Systems antf Technoingy Divininn specifica"y M grear-
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_ ^ nond n wid.enng.of efvanced nero, eieweinement ac- { -nments aconn in reinem tha n..rie= nemmino n,nc. fivirles Incharterf are developmenHin go.peallas hnolo-hsues ag e arfinertive waste 'stmaqa as well as not aar gies to usa cnalin mora etticient economirvd and cI*en g' 'g ' g egg. and to resnive ewkt.v.g uncas taanttas regarding mech i powas pinnts; advanced sortium suttur batterieg wNeh y j esptwt pnlicy. wnuld f acilitate increaw! control of peak energy leads by , {- q e Nuclene fuet antf p' ant servire neads nt tj S and for-9- ,J 1 j eign ut!!!!ias,ntfor the Sector rtenetemsttes Ine prahtable ennadnq possibia the glorzoe retImga navwmts of efectric- .'s-9 fr43 s, f '. v 3 grawth. ouring 1979. the nur4 ras tween.sg receivert fur-ity; arws =ntar cernral raceiver rewm p' ants thI n** he-3 32 p ,.4, %, -1#. '- 4 ther tarpe ordars kw emclear power plant teet. erwt wortred tlostats to ennvert the noen, eneruy in etaWir6ty e' -3... g e
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cinseiy wah ** scam s instw=m and savire en. ricer-me reported in neevious Annuat ricrorts. custceners have 'S a v t' N ir g business to o.veino cenmai narteie rwrwar service seguired that nuciaar fuet be soi f wei wanantw s enve" ,/.. _. i oppon tunite ing the ugehillita of tha tual. even ttwegh the eoperiance y4(, ,,<4- ,s . j inetsitatkm and wevice engineming hehieweg base toe piedicting the life of nurwas tuelundar power , ;y*- 's, J i5 f {e m S'. '. w. - t o ~ schwved acced eneninos in i9 79 an gnms,a es in-peantopuntingcm=1mnns19 sute intivety sman. As of -r,/..# V i s. -#' [ j. v t creases Growth ine thk tmsen.w k being ach6eved by pacembm 31.19 79. ttwa wm.. yon wan ardy commit- ,..s. n=nts on tuat with an or #aat saias vena of everonmntaty W,W' o. \\ .?9 j ewpanding utmey mamtenane. piant eqmpm.nt mndee ni-3 9 1 bimrin. anrf on funt in tha bm bing preseney vahied m; [ U. ',. ' 'I ~;3 7,;*.f f-s *Qt[ y { f T '.. {,7 6,. f 4 rgilon and marine services worbtwide $3 o bimon. cave ing deitversas thrrnenh the eaviy 1090s f .e ,e O. J.:y.. ( 4 '.i y E- , $.'. p ?;1 Also. gorne tuel ordagg inchde reptorecing. piertorteurn 1 -[~i Power deftvery businesses which penrture ttamtnemets, fit ** cation and anda dHpmd ac' vires in view o'cunant ir 6 power circuit fxenkers,warhen, ami metas repa'ted o s en nt pancies n as.9 y unemwn whether y-5 t, -u j 19 7s. in view of th...cen rapara, in uteht, systems th. mw h services enn tm providart 4 t ht ow.r mning,-s ghti, hiot-Sain un ato,. tor a Die omsinese r enrtpur immew is 14 Arumdf symet es79 2 h i l
w O tii,weenes, .igu winnen a.w.n i To he#p wndicat equipereed customero enntrol costs, For lhe nuny of high mchnoingy emsinesses ma61pg up ge,o,p.ce ope, nitres had sidntantiM earnings ga6ns Growth of abe elarvo mate iak hirstne s hog teen GE offers (tnp) e rettertdshtr+g service for motete n-rpy tha Tectmient Sys*ms arvf Matennis Sector. t979 was a that nutpaced um year's sales increa*.e. and new orders acreterated by appelcatums in ebr*untrs hw cammunica-amita #;nother fast-gprowing service: a ge bat infor mm. year ryt further substanttat inceeasas pr lh sevemses neuf wen ahead of 1978 Techrmingles in thh tmMness Hon,enmp Aers arwt consterier masheM n tion services network (bottom) enahting entstoners to earnings inreensed 28*. ateve their 197a > vets, with all I ,n,.nmpass space scient es. deseme electmnees avion-trse the mersed computer power et GE 'Supeecenters? of te, Sectne s majne busina=ses cemtriturttnq to the year s l ics.cornputer software and energy sysums. Medical oystes hutnesse=Jssos*ying diagnosHe bnng-en 1979, General Electric was saiected to deveine a 6ng and pahent mnndarbg mvuttwnen1 and ealated serv-strong gMm The Sector acemmted for M*.of total Generat new stdirl state. ftwee demenswwist eadar system for Ibe ices, had suttttasdial earnmgs inerenses on higher salas Doctric revenues and earnkwis en 1979 Ai, Force itws row genaration of air dafense radar ottees in 19 To notomatte operatann arwt redistad maintenance cmts T he Comparty er*oducert a new tdtrasnemd (fingem-Aircraft engine tminesses sesving aircraft marine arwt h spara sciences GE is rbveloping nei advanced tic sustam partiridarty arrhcable in fetal cuamenntions and inrfustrial markeN produced gnavi earnings inescasas on communientmn swellite system lor the Air Force screar'ing procadmas. Witt ttes rww system.Generat sharply tdgher saws, while conhouing a hoch lev *l et *"- In avanners, which inrhsdes the night control antf in-Electric nnw offers allimw diagemstic imaging terfmiques, j ",s penrliturcq for cormnercial engrew rievelryrrent Tim yaar ,,n,,,,gaginn 3y,,em, gn, ,ontt. General Ficctric inchwthq-onventenat u ray,mripar medicina and rom-d serveg tmth mihtary enti commercint marhats GE avinners puted tomography (C f) was nntahte for the high rate et new orrtorg fm Cnmme 74, D, cial nieceatt engines and contumed steength in militar V eqidpment k on an wide bodied airceatt, and important The yeat benu@t a cordinued high demand lov the new systems havn twan selected for ttn Roeing 757 newt Company s C f systams. wheth n nmbme n any with corn-inaskets 4 (;r, Airlines around the wasto rnnhm = to morternare and 767 airc. aft nowin develop <nent puner technntogy in peorfore cent sectional views of the suppharnant ttwas fleets with new arid te engine t aiecraft-For teth mi;itar y and commeecial cu=tomers. General terty Some3MCenaralilectricCT systemshavet'een lastalleefin 16 crnmeries Electric has sworfuced computar generated ininge dis-
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The GE f amily of commetrini engines servn this marhet g with powerplants that otter e!hciency. Inw fuel consump-pinys that ernin prints vta simulatad rather than artisar inghts Even erwwe highty advanrad s*nutators see being GE In*orrnathn services tmsiness maintainart its rapid t tion and low-colse desigm py 1979 year entf. 54 aidines hnet over 'ino Cf'6 pnw-j devennpert b further improve fllgtd tralning whHe reducing g owth le sMas and earnbgs Remnte stata processing aged narcraft in service on their twin. tri et anr1 truw engme costs and conseeving fuel serwires were fue thm espantted by enterwttng the avatts i t Gens rnpides".GE's comtuster genereterf graphec twidy el MARM ltt* *ervire Kress to Venaructa nnrf Saudl wide bndlad n#rrentt Highlichting new nrefr5ts rtiwim3 the o yaar were airlines specifyino the CF6 p0 encirw for now gghg,,,ynce, cc gi,m*C its tatt growth in 1979, drmbling Asahia T he network rwar serves ovae 6.000 customare tri ,e twin jet Poming 767 and Atet'ug inthr:tria A310 niereatt lin*h equipment sales and tte size of its nationwide net-24 rountries Fewthee novances were mada during ttw yane in infor-Sirmdtaneous certification ot the CF M56 turtelen enrir ot sarvice centers mation seewires tar;tmoWy. inchwtmg the introdur Ibrt of .a anginein both Franca and tiie tI S was nne*ber 1979 vmlestone A jnint development by Genmat Onctric anaf Engtrieered materials had sharpsy hiqher earnings ervt the M ARK 18! Oktrehuted Data Penregging service, anel the s SNFCMA of France, the engene has teen spiactad by me-snMs then in tio prpreding year. Itw Genm at Elactric MARK 3nnn* remre computino Saevice )or astunes to re-engtne their DC 8 nonatt It ennnnped its fammy of high paeformonte materlah inchwtes engineered Inght fast program with the sert t'sshd first fli'Jhl on a lour-pinstics, sihcone chamienM. tungston cartdde metats. CommuntenHone tmsinesses of Genern1 Flactetc Inchede Man Mada diamrwids. Bewaron* atw asives. arw1 electro-reir#M radio oppeptwwig and compester intmfare equip- - .%qy p yy engine 707 Jettiner Prospects in general aviatrem impeoved dusing the masertnis guch as laminates and recharganble battanes must The year's sutntantialearnings gnim anrf higher General Electric plastles contamw'd to panetrole auto-smie waen pared by mnhite radio Goodcisstome secapt-year when GE's CF 34 erwines w== spec.ed tof tha r** embHe markets tothin the U S. arwf nhread Sephing to ance of the Canha y fr* mobile radio line crw*ltMded to thm I twin-angine business stretatt, Canadair 1.td s Chnttanger 4 yl l E. and when Re% ncepter launctw'd its 214ST civii hall' improve foal efficiencies by rartucing weight, auto enakers improvart ressetts = ' ~ ~ "
- i copiar writh GE CT T tutteshaft engp*s-are increasingly specifying the Company, high parform.
Marine nnetinrfugtrialmarkeM for aircraf t derived en-nnre plastics to repince malais and grams. With the 1979 The oestinnk for the variad maetrets sarved by tt e Tet hnt. } gines remained 9tmng in 1979 1 he foret GE t M5000 g*9 introrksettori of Arrrox* resin. "the pencessable epowide? cal Systems anri WeanaM Sector 49 arrellent. Whue gale = ganaralor to enter regular envoca t= git manting peak ghe Gncewar Etertric litwt of plastics ew*w covers 32 nuto-of engineered materiaM may t a afterted by a stvle term 4: 4 a downturn in some onmeetic marhets, it tg e= parted that a4 eiertetrat demarwig frw Tok yo deing the yant ihe Com-annteve nopNr nHong j pany's oneIler development in rantina gat terrhees. tha trwestments in asparvtart maru stacturing facilities at there will he contmew d oenath in toreign ma. bets " q 7 1 t M2500. has toen chosen Irw over 130 ships in 11 pavie9 the Company's Mount Vernne. Inet.pinnt facNitatad the Machett Int new aiecraft engines antt for re antt ning i Meeting military reeds. GF s F 404 engste for the introductwm of Margasd
- sheet, a bugh glaring gworfuct aircraft mee nn n innq term growth cwve F!A.18 Hornet qualitiad for pen hsetinn in 1979 Atso. GE with ahrasinn ranistarw e comparnte to that of glass Governrnard maskets ine detema *quipment. serv-was spiected to deveinp arvt inght test an F ici or E General nectric tungsten-ra. hide tantals next Man-irn. ams resaaert and,tevetnpment are trwecast in Martn ind,,,d
.a ond, nm F.ndirig geowit, iue.ia, e.p. edin the Imio, ioed.Mive nghtm Eng.nent, a petm. t-ste p-b plant for 4 isch mitreeft n, the Navy F - t 4 nnet Air Ferra F.t 6 h inetustey's delve Irw higher pendurtivity in metalworkmq Informattnn servir** markets are conhmoing to en- & ( gj GE h., niso deveionad a suesiantiait >, mms in,up-near on, nnrtin.nttay siniensified mining,,pe,ations pon,f,.p.diy wortdwirte Wbetd markets for mnhile e,wrimunicatiores aquipmer'* ptying enititary helicoptm engines The i 700 fuehoshaft and drming few oil newt gas eng.no, strentfy in production en. Army haiacnetas. contin-Innewniinns ticipert the Company's aincones business are erreced to grow substantrany in tha nant sve yea a 1 eserfindeveinpment fnr the U S Navy I AMt'S helicot*ar maintainits growth As an euample,rmw GeneralFiertric Np=fs for improved medicar etiagnostic eTilpment je and competed thght qualificatwm tasts. rnecting or en - silirona sentants ottar greater duratdtsty and ange of connnon in holstar markets for gr pt.htiented enedicar .W h ccmfing an pa tormance renubemenis appncatinn .ysia, v.= rw a r m r Ir ts arwitseitlepfwl197s a
o E 2 Natural Resources: new highs in worldwide mining operations I te.wa i s tvs +9 7e i977 is rs 'ws Natural resources activittes et Utah InternatMnalin-GE's nahnat resmwres oparations. primarry Utah intman-sron ore arttvtt as Msn benetned frorn inevensed ship-ciude Dop) cokir q cent mining at new Norwich pmk tionalInc, set eww highs in ravenues amt estesings in mords and highm geice reallinhonslet t979 Entnings mine in Austealta, and production et enpper in Canada; 1979 Revenues wee Mtdghmmanin t978,whne gWres wee made by Amh alian and thw 7ealanet opeen-t===nu.e stage se ev smea sa re.) stans tone anet, nethemgh another Ims was recorded. Impeme-E_J_;;;;~mp F,4 ' _' ~ ine,~ ~ ~ n,C W we bonenW eM gm prort'ntion of Ladd i etrolenen, entningt, which ewc**ded $200 melt 6nn for the first time. erwne al=re we snarte by Sarnero. Itwi gr.no nwinnn BearB-e and a worldwide minerals ewploention pengearvt. g,.reMed th Thatebuswwsmwihided5%of tan venhore in widrh Utah owns 49% nt the vnhng stark intal Geneeat Flertric revemps enri t5% nt earnings and p ovides daht gitaranteet. 4 kw 1979 A sharp irnpeevement in earntrigs from Canartian rop-Steam cent mining operattom, sarvinty several etarhic par rTeratirms was the mapw factne enrd'ibuttng to the inittlies stwwrart a gewsd enmings gain. Imp ovemanM p'. '. ] d h- ~ N year try year emnings gain Approwimately tt2% of 1979 eeventms and 77% ne net were rentired al the Temppar mnw in Cotormio nnd ernrn [I !! earnings from nattrat regnurces originated imm nnn U S conteact mming at the San Juan m6ne in Ww Menico. I I while resmults tenm the Navnp> mme tre Ww Memiro were I coerettons The mineeat sales tsachIng at the end of 1979,inckwl-gnahtly inwer than thrine nrhiaved in 9978 l ing urnnhwn, was $5 6 bitHon.et wh6 h $4 5 bitionn was Ou and naturet gne nparattnns of whnely ownert t add re-t y f k; actedidad for shipment attm t9RO Allcontreets mnhing poteinn s'.orptwahon reprwted record revenues antt wasn n, [ up this turking nen payable tola S thftass wn, n.mm hem t ad knm imp,nvad p,nd..rt p te, and ' ',4' tg - E = p 4' Austrattan ecletng cent acHvities continuort to be the from the 1979 arquhfunn of the intilan Wells nahweigas I I 'f ( b, s ["h maint notwee nt earnings by LPnh heternationalin 1979. gwnpoetles in tavas. the ewparvied eug%ratinn drining N A mottest entr ings improvement was attehutable to fac-pmgr amconrherted by tadet empedanced a success entio g L ord shipments of 17,n trutimn metric tons. a 5% increwe that eas well above mitumb y avenges. I I over stdpments in 197tt, when deliveries were attactert by a ig e f' h. a miners' thine et neady seven ween s A negative rI* vel-Urannuen opeestions aee conducted bypattdindr'e Mines opment dewinry the yant was the Aust aNan fedarni goveen-CorprwnHon. a whntry owned nonrensatidated suttswilary, . 4 e' ' <h - e I w ment s dari= inn to retain itwt coat evorwt etuty, a levy it ett of whose(nmmnn stm3 is hetrl by in<tependant hus- ,s 0 4 5 N l Q toeg (saannte 12 to financiat statements) The smalt er,ss i' gweviousty was committed to eliminata. , p (({ lI! Newwich Pmk. Utah's litth st, fare cokirig cent m6ne in at these operattons eetter-lad relative *y low shipmeest tev-5- H, Austentin, came tnto prottuchon in November 1979 Tha els. increased emts. newi tha naed M dclivae renrerwe nte new mine will vench an anmsal capacity of 4 3 mittion met-g,nrte, low pice contenets enteeed into in the earty 19709 [ ric tons tiring 6ng total annual perxtuttirm cnpactly of the lhase ennt nets are geledidad to be fistfilled by 19tl t. 7 al Utah operated mines to over 21 mittina metric lont At OWwe scevittee inrkde ncran pansgwutaunnin suppmf of year end, ngprowlmately orw Wierd nt Norwicht'aek's nn- ??T T51 'I- .,' 7'.% y. J3 V'f 23 mmi produr*= capae y was erw*arted for i wice iang-enining nemaime. andiamt e .: comaunn= con-n g 0..: JJ^^ tmm.aates annncemmes Although adriittonal amounts durted masey in en*fornia AMn in a ydne venhwe wnh ?M. J tl. ..c 1 are e,pected to be commnted km cnnt, acts endy in ien0 or = tightmg cenup. t itah heqan developnwnt nt a t mg L .4 t .. < - 1:.] ; 4 ~ .(. % some pnriann et ow nanws capactly ng being smervat kw sten mine in t>varta t his mirw h ewported to rnnwnence ' ~[ M. g{, ',' i, i*'* ) 4. 4 - 4s.- sain on the spor market wt for great. sinihnny in p.orturtion in 19n2 nn.1 reorkere a s ondicare one una of i*,3. 3 @,.7- ; g y ,?* -A-y- ,,,,,,i, pro,,uc,, t,, r,ew cu,,r,,nce, at, nnm,n,,,mos,en,e,,,,,, men,, + i. y M;, 3 a. f 1 g Uimh own, ew ot newatm nene. net ss% ct W. 7.. othm utah opmnted cnking enat minesin Austeniin The cunonk i, em enn inu d strength anat increasert mm-e . ;. y i i f s t t stahi.shment in t979 of a sydney tendoimevers pahewn in it, worirtwid-markets toe nahwas eesnincea-
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j-office from which to manage tt* att.finte's Auste nlean nrHv-Investing toe tong term growth. Utah emphasites a g 'g e, n e:'c i-nie, renertg both a fuether comndement by Utah >> pertu vinneous ** pine ation progeam aimad at ma6ntaining and -M
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i ', I a 6-k.. h pate in Amtralia s economic growth arut a move to make strengthenmq its ente as a leadmgina cost pentbre, nt .j 'e 1 2 y', ^ i '.; $.,- D-Operanom at the totand Copper mine in pris4h Cohnn-tmne further sherveene Ut=h s posninn as it, nimine cr*- g-7 minarni re ninces **edad by the warta g econnmias i Utah more resonmive to tocat etevesopments Addinnnat capacity avapahle hom tte new Norwirh park ,.g. ., j* 1 '4 tiin. canada prorweat eecned earningg kw the year tha ing regt gepphm to micennhnnal maskets and shne*t en-j < i. ;; [e[l 9 ' avanoa rdce car om=wt ot terter eme 45% In 1979 h-hance t itah s rome phtwe nnsitinn en enking raat madreta -r 'd %.p-.. b ',. s x,- l J 3 nortation to the improvemant in coge-, maekees. by prort-Atvene end 8979.tfrahsniernationalenc sasedcer-e 1 . l
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- t t saie, nt,,,ntyhdenuen. gr*t. s-and et,ani. n. whirt, iain x. tuck y - p.-tie, im s 7 md.en te-Nnnonni t
$ g3 j y ' R ,.'y tngathee nerounted fos approuimately one thirdof estantt Steel corprwation and sigemet an mq,. 2 to gwstrhage j f. Copper'S revem9es, were 9 tit)starttially hlqher ni verord ndroittnnas coat penpe9 tieg hetd by National trt Kertturk y 4 9 a nart vwst w 4naa hw $tsn muunn a paces j therhe=msf tnrowhenawn 19 4 13 Anww.sg napnet 19 9 l i l 4 l
i l g ,= l l l l International: total GE business abroad l increases; U.S. exporis set record ~ TotalGE entmnahor at rewmees ware t?% highee 6n 1979 Genpeat E h=rev6r s t nem Ammtenn atminees e, pere.
- "h e*'"i"95 "P " '"'*'""'i"""'We'anons et ne Sec-enrM o=ceeany sewer sales grnwm aehem entnegs seremo to esrs
,s;g ,*7 F Ws Ws Generet Eteetric serves international customers with h a*wso ew u S-- -tr.n*o sims-ss v 3e s.g in s.e.re,s (top) consumer products from Canadian CE; htgh-ints accntmlmi kw abnut 31% of GE s 1979 total revenuas in 1979 Amitales h ttaty newf Span tiparatet at a lnst h way ghting.as in Atenandeln. Egypt 3bettom) delve Aust'aha and the phepp6,wsjnipemed pertammu e **- p i and 37% of nat earnings systems, e* foe Kenice's OH fletd development; and T hase int *rna6an#1 revemes w*re d*'twed l'om tour sunad hem wamtanbo Genmal Flerkic consumer pieds '~~ -' ~~ ~ - - N" medtest eystems produced by GE Fspnflota. ethneles b form larger operstkww in euchange for marww-twoad snurres maktwide
- - _ 3
_ _ S?"'" W"# s2 "7 _s?M sE'se - Operations oi nnndiversified foraign atti8iates. Includmg Wy ownership posst*=ss.
- '"*'O' j i,
,,M* _ F1 FsJa the foreign opar 41 tons of Utah hilernatirmat kic; internattamat cnnstnertion nperations provMe the
- E sporis of GE pmdew-ts erwt saevices from the U S. In 2 and tertwtical c pe,pse m take on very herge
'"""***-9=as'*****
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,f- }[ $ 71 unattiAntad sneenori cetomers and to GF offitantes; ineeenetionalpreserts Prohtab6Mty of these operattnra was L ? }~
- Tectmoingy Eri=rneng revenuesImmunatti#atert anrf improved in 1979 cm abnest the same sales lavel as t978
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,[SNYa-M_ T . Foreignmutit inttusteyarmeteorn Ewpert sales eetiert an part. the many services prev &ted , g, j[ 'I t e %r
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~. Results of the twst thece activities atnre are also in- % GE s dnenesisc nperat6nns by the InternnHemat Sector. 3 g-
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~, 0 o', g 3, g 94 ]' -E; cluded in the nopengwtate prodistt Sector data elsewheep These seevtces range fmm a woeldwida sa es organern-r t I,8N - -4_,.,,'. d a-j- Kg in th6s Raptwt I he lotsth arttvity. frweign munt industs y tion to est;itiaishment nt limson oftiras tn developing coure operstWps which nre undee the direct managemerit cf the trees RasuRs tre 1979 cemlinuert to be tod by high technot-n .s 3 -
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'A r-a p Inquirnationat Sector. accoupled for 12%of Inta* GE' ony produrfs surh as qu turtiines and aircenft engwies severmes and 5% of earnings in 1979 Ybe tuerhang nt orrlaes from es.affittatert cusinmas for .A ' :yqC$ f. - *f. w-A summary ot reventses teom outsida lhe RS. fonows: espewis hmn M U S increased sharply.fttwn S3 5 tdian f 7 f p' TP' f _.E f - v' at the end o819 rn h s a e huhon for 19 rs. r yo,,, h,t,,,,,, ten .e.,;,,,e, _,a s,c.,,, < y> e@ fa W .? s f 'f.- k5 N . h hi ' - ~ me isre The cottooli continues Infavor substantialgrowth kw irt- -~ p=waneet f ' - Al ,(- Fweegriesw==wvie end nr esat tornational markett served by GE. evan hough GE econ-s ^y,, d,. .?. N Y Z*,*, '*'2C"'" 'M 'M
- '*'* e=re" 9 math e='5 '" "* *ar'd 5 e"'an" "' S J
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== m-= p --+ .y 4.' t_ J; it S *=cet to - -- neeq3 te, wie h,ge, varimningy pentbcts and servires that ,g 3 f Gmwat Flechic provides Also, effneis by the inhtena- [ [ -f 1 g, tinnat Sortnr to strengthen the Company s sales suppr*1 j dR ca w wan,rd aw acrtl MO es, ,t t. N m mn swuchee. particularty in rw a gmeth eren 6n th* Midom r 1 5 E est. Ahics newt Semtheast AWm. hsve tegem to pay re-w ~ turns in Irwveased smies to these areas. I eJ~ g Operettons outsida the tis. Increasert revenues ham GE trwe6yn npeennems wist confirme to eetiert ** dif-S4 4 bill 6nn m 1978 to $51 bdImn in 1979 Yhis growth was teeing 0 L.,. ; eates and ecorwwnic costdit6nns in the 7 l*1 r primarDy attributable to nondiversified aM tiates. directly Counteles thay serve for instance. Upw4can mnekets i managed by the apperpriate Sectnes, and reRects GE's shoutriba lnnuanced sionifienneey as that cointe y's gov-emphasis on enroteraging Irvtividual product birsinesses ornment camveris its ceteegy sesnurres inen inckrstatal { ~ 'f {- to entenet thc6f arttvmes to ginbat mmhets. 44th suppor t growth Tha nuttonkine genethin kitarashimne markets. y i antf enordinatinn providert by the Internar6nt Nrint however. nwrst take into actmmt the enrre==*d wortdaide [\\ ( Forengn mutJ irwhsstry eterntenns inrter athese corripetHion from magne fore 6qn manuf achwees, freepsenny g amotmts enetsest principally of afhtiates marwhettwing var-with support of thew natumalgovernm=Ws gf e led lines of prorturts oriented lowent their host countey Pros:perts Inr U S companiesin internationalbin6-gg mnrh ets. newt international construr tion ngmentenns. Da-ness are improved by events of f 979.Indurhng Congres-j' suits were mlwad in 1979. In llne with contumed dimcult skmnt approvalof a vow enternat6onal erarte agreement moonnmic corwtitiorn In snany of the coamteleg served whrme terms enuto. wtth retipr atkwt by m we than 900 i 2, yg y Whne revenues increased 5%, earnmgs were oil by I 4%. nathms.verbre isade bardets for many U S Intfiestries in par t due to 1978's nneweeterring gain frorn the snie of The year also saw tow onve+rewnent tornoniferwe of the e i ' p GE sintarest in Oseam Ger61I t innad Statas reart. In the words of Presidant Cat fer. to Canadian General Etectelc Compariy ttd.. largest of "plam n hlghee pnnrity nn ewprwts In onter lo helpoffset s& the omdt! Inrhrsu y affiliates, with 1979 smies et $ e,339 mil-Increased oilimpents hnid downU S trade descits and Ilon in Canadtan donars. tus ned in a strorv; pee ttwmance strengthen the donar ine President's E xprwt Council wns Actions % eepositwm sevmni cornioner anci ennstructen eenrg1ntzed in 1979 General Electric's Hnard product tiraes were Instrumentalin ** L,.
- of Chaieman pest the Company s support Nhhtd the new ef-Stees.opernemq margins and eatnings Inrt by agremnq to seeve as the CoonrH s d*e6eman j
wrwnwneweer :. 21 SW Assesses Rapnet t975 k i
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O l Financialissues- '"rpiameni=y informan m ta ns=' Siemnent at r vn TaDIO 1: Supplementary.,iniormation - elfect of changing prices m mos use r4 th. t tr o meitw*t er.aase.d 19 74 amt to 8 theimpact of nfl' tion g,,,,6,,g co,,,3y S no 3 mm,nn a,,,1 $7,4, r.,,.linn pn i a 170.3 to 7 ni s1wm arwt $17.tW5 4 cmMwint e** par teva 8y with a ennespnrwtww) terhetNon nif *Tw
- ted P* #98 (""I'Is-thtortionately tI S law terrobtwms ime to prowwtp en
- """*"e"'t"""'*"""'W"~
i'""**'"'**'""'**'* erp4 valent in t.If'O tar the mip:%1 of a*D1hnn em a com-bRatwm k remmnray detmart e a bet in value ni morief party s costs t ' propa4y pW't anws erpsipment inctapt. n. ,n.w,= n,rp, e4 n ep eadi r g e
- ' mar im eam an to ar -* g-ira, riss= to an herente in the v -hera-of tr nnay and readit dechsrtons tne weat arwt >=, tw, the-, assets are b.v ad I"' b' I*
MW N-sataHva try evallahin goods arwt rmveres resuHeng m a nsa on twigermi psprrhase costs rather than gnrtay t regdara-m the tevet of priras initah.m m tha tt 3 m ganeralty rac-mant enets in opne* al. the setn't r=3 thrwita# met be I S9t*9 ofFo'brts and servicas m customerg $27.461 $22.46 t $72.46I rwynsf*d to be caissed by a corv*dnatwm ni tarinet. irw+sd turwied from atMr tan enmirwn f Co91 of gntwt9 *nid 15.991 16.043 16.074 mo rysvammani datieveg st a.p hrressam m enetgy r osts, Salling. generat and adminletrative enperne 3316 3Jt6 311ti .i anrt kiw prorhrlivity gairm wirhytnq the attort ni pentitesat The supplementary informattan shr>wn it Tahia i se Deprecentines, daplathre and amnettrattrm 624 RRO 9AO mg govamment ecquiatwes 51atos npara*mg emults to ehmm ve 11* matar abris nf Inserest nrid other tmancial charges 258 2%R 2%8 A!!hrwmh irms of purcha=irwt onwer nt Itw rfnMar wn-insatinn etkemed ahnve Tabla 1 rornparas 'TF <te'ahng Othar incorne j 519) _(5 t 9) (519) parts all erpas of the crewwwny. 4 se pas tietervly r,reemis en results as sepnetert on pena 32 wm <*suttt ar*tu tml m t** F emings batoreincome taum and mhwwpyinterest 2.391 2.031 _9.952 e sts effect rm sawmgs - el bnth mrtvWn;g en berm such as ways Ttyst,,peutts are resta451 M shr*ss tha etter's ed prov41rm for incnmaItzes 953
- 53 053 savmgi ae. counts. saciarth s *C panetres. arwt nf a nrpr>
geeweniinnaten - the inst tot the dnet#s purctMrvt geno,ity intere,t in namings of ransolidntad af'Ittah/s _ _29 __ M _ _t 3 earsons bi the form of retairiart menings pmer - on invenMems and 5vart asects Ihe aeron 1 re tant ownbgg apptirable M corvirnon 9br k $ t.409 $ t?64 9R6 statement shnes results resta ett tos thangas in eter6he For the hwtividual, with inttahne nt G% a year. the etnMae pttres - the curtant omt9 of rardacenq mma assat9 Yo'W E nr a par enmmm shnee $ 6 70 $ 4 68 $ 4 34 saved by a paesnn at aga *,0 wit have Inst theca fifths of iM managamant tack that the tast entumn m Tabla 1 is tem Shwe ownersWMy at yew and (net negats) M $LW $ 10.4 vs $1 W 3 valua by #m hme the per9nn M *te E5 W4h a 10%inf!n-rnrwa eneaningful anr1 hag thevattwo shr wri. in Tabb ? tm tirm enta, atmost four tetths of tt*= dn#* s va5sa k lost in 15 paga 3rt, tva years or we uns em stutt basis aMn a@marf Useof each doner of eernings yavs ihM problam afterts p!rm<t -varyn m 6nrnoding to erpsivalent t97e inlines bmMa the ya*?s cnmpReahpe '"=adenushwbasn es nem thosa peetently wort-ing arwt es s ridy thma atm mee on W99ta thin ter hniry med are rw4 prerke. M*y do two-fuert incomes dure tensonable atqws wimnHems The situa' inn b r**wievart even mme dithrutt 5y tha h these emeewngt stat *ments. <gmrenc ad o=Wr*'Ws
- a. p i=4 ady e vor ce i
hi neac8ac e'*eas progresstva lnrcene tav system. A rrw=rewwmai sistf me s made to t t ) rmf of oontfs te*f for tha rven ed rmt et "I etwiy raprirts that 4 family rif toe.es p,th an aernma nt $8. 8 32 septaring triverdone wwt (7) sterrarrafenn ene tha riweent m t964 wmsid nand e 1979 mr_ema nt $1n 999 m hma costs ot plant and eryse ment t ha vestat-mees tor even-r hapt pare with tha inereate in the Crmenmer l'nre hrten trwim new relatreety smatt herausa GT s estem6va u-e ni ovas tha ywars H-mavae.tha 18 Tqinrome rf $18.918 puts tiro acenuntmg nkendy hraciv eet'ar ts curver't rosM in s6 tha f amily inIn a twghav tan tirarket abw-h when cepspled the le aditiemat statements Howaves, a substantial ecstate-
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? unth Intransect Snctal 9erwrity taxes restures re=1 a' tar-enent is mada for the knpart of mt'atirm on Ruad asMcM. , [} j tan income $ LORN belnw tte erprivn'ent 1961 tr* val which beve re ntively irmg fives T he $R? t smetown ed degwe- , fj Q' 1 g., riatwm as traditkinalty repoeted. = ten rest = tert trw genergt ye 4 j~ Your Company and att U S. businesses fara a sime8=r hdtahon. Inc, casas In a Int $ of $RRO mil 4prt Ihsl the re-1 [ f88 g(,)' # t; ' per+ievvi ihminats saverws, z.cen tha intm nt veta$ned statemani naressary to refter t reydarement of these as evnengs - the earningt a reurpany keeps after pay,ng sett at curtant rmtg grows to $fH'o mitrinn ihn nat ettect .a empk yaes. suppliars and verwines. arwt after payment of of these rettatamentsInweeg regwwt=t enenma of $6 20 m j navos M Cowar"mant # net rter terwis m sbve owners It a shera to $4 f;R nn a oenevnt inthhrm adpe=f=1 hases aswt rembed tne gro*W were cut h twiM to t 6% of income remirares nf return commansurate wim the rkk9 invotved w crwnpany n to conhnue 6n huserw st. nww h h ss grow 41 $4 3 t on a specific rureont rmt hcM tetore tar, not 32% as *ttocted in 'he tradit6onal linancial Surh supplementet mesesrements can astkt in etw entire omrst be able en 9mra or retain unfin sent - mn6ngs, pher sente,nents over the parmet. share owners received a eagmstre nuorntwm gworess. Staritng with bittal prolatt no-provkfing a return M ik thwe nwemes. M ftmet p* cmt of a is sh,nenrenf to note that for the #=e years t979 979-measure of nrotactinn against intiat6rwis impact as abmst gwnval. Implemanfattrm entf subsequent review replac6ng - nt entfiy's in9 itadFr" *1 th* p""t"C h** "' *# "'T"d**"' '*' ""*~' '"'" C"'"P""e' *a*re* o**=r"a*a*rs twr> thirds of attar law ammings were resteitwsted - erpeva-assets used up Detantenn nt c.w,eqM m the<e 6nHatwmary W Cr**8' b e8"*'ge end a etench herrees an lant M en average annual generWe cata of shoest 8% in rent improving productivity to ottset innationary trwres k n 16me9 undar enesteg fan laws n i e h:stionna farm.3 all ,,[ dh,ldr nets primary anal estabhsbert by inp msnaqameed that 6s being 8 s**,smi the-pt-Gemi.ni oprieu, ~~ se- ~ bu- ,,,a cor.s,.r., s e. p.r ,.,,-,e r.fe r e.rMr U S tan raquintinn9 g=remt *erogeweine: of the unpart we9 7t% since f 975 est 8 % shre t975. This mesat thof tha An eres receiving tpecirl attenfton by managagewnt M both cov*e of thk Antwsal Deport, tie Cnmpviy bn1 com of intiation on a company s invenemy rmM by use of the pro tn m cr s eenibge hee been roer. norprir the twahrt of owpartmentation with sten ene of 6npatirm adprstert mens-fnittad eigmticent leveh of resources M research erwt da-asnpment pet *vihas M neralaraia ennnvalinn anrt ince===n ttTO (tast in, tir=1 out) mventnry mettwwt b r,e,* rat. wi-hermann. uren*nts at the inenvirtual t*,siness and popc1 tevet toe w der the lITO methort. a enmpviy r hvgas nft In opeeation9 cap 4mt hudoating Since 1973,=w Compmt, bag toen produrtiv#y In n idation.Genarat FterWir 9 proettwe the current cmt of 6nventons rnnwmad rhnww: tt= year Ari grriportant Insight t'om thme data M derk-tad in the evpeelmannna with vstmerg tecl#qope to menswa the Im. base remtwuses to bs* e=pandad newt modemired through with intiation averaging m er iimas, yese Pw negthva pear *s p* nght ihma show tbM, nym the five yems part of Innat+on. to incorpnente Wig persperHvas povktad inctensing invecmenM in pbni and equipment. For ewam-empact on operation 9 of using rwermt roets with respact to 1975 4979, tw tante of intiatinn tft% rnrwenf GE s earn-by seeth meagwements ento darkmn meking. and to stem-pfa. $ t.2r? mitterm a,wt $ f.05s smition weea st*est on a supply of goods n substanhat I inanrial ratu!M are pnr-ings ween tnmed away than plt *arert to have teen M* utste awarenast by nit laveh of manacamens of the need strategthenang GenerM Electetc's portuction base in 1979 cosa using trad6hnna Imanr*M shtanenM Mwla the ha tre deveenp constructrue busiewss strategle" to dam witti annt 1978. reqw ct6vety Irnag6 native and d Hgent couplhig s trayed more antwata8y when the t ITO rnettorf es med m par. ode of high inflatwm. newt GE has u=ed I tro for mnet of dilinnat camenos st:=lements inrticated an ettm twe innanon. Use oNective is to emura that investmanM of moduction ternnepses annt eq enpmant h evasral m W= lts U S. vnarastarturing wiventoties Sne a ereartar renkwy tan rata of 41% over thm per*wt the ' eeal ' taw rat * "' rwadad for new busmass geow'h, pedurevny impove-maintenance analmicrovemant of yrna Company's The Stamment el Earnmos on paa. 3? es em that b=<n As aced 51% of poh's tetrwa taves conseq tent'y. aarn6nos ,neng,n,1caparity e,,p mg,m cam appenpute pantahmty i The Giunsmil Florieer bewouww 39 20 Arweel napring ts's ,.. - - - ~,, ,. ~.
O Table 2: supplementary information - effect of changing prices o, Report of management th.wmew.e..= recs w e -wes e To the Share Ownees of General Flectric Company GE s accewmsewy arwt emants=t mitrok. anrt rewwturt sierh VM h== peepared the erw. ,L,; statenens ol knan-tests antt retMart peoredseret a9 bey fBreen sace,pssar y to Current cost Irvtornsation in clottms of 1979 purchasing power (b) clat potation of General flectric Company arwcennsoti-medve at an <riniim nn the %regs of Anancias statements IM - .=ru.va *====mrt9re+ia.$ 1g79 197g 1q77 t97s t9+5 dated att: Matas a9 0t December 31.1979 mart 1978. orwl The Atutd t'twesetteene the F4oard of flueectnet. SWe'l ot p'o'hsr19 arid terver es to rmtamers $22.461 $21867 $?O n94 $20 ilt5 $19 022 "'"'**d#****"'**'"'"#""9""""*""" "'"C'd'""P"'*4***'Y"'""*""''""e"""'*>'h* Onet Mgnorts goiri 16.074 15 518 14 791 14 Iis i3.914 W"" "*' Ch8"'" '" *"*""T "3""d"' Wws Cmnpany. mmnw an nnoning appr*at Setimg garmal and adm'nietahve erg n=e 37s 3 ss:s a nos 3.160 3.Di e ended. incIwtirig the nrdesAdostiy and geogragduc
- wen *9s of math anr1 the ir-r
' s of the puhhc ac- ""*I* "" I '" gao 30:10 gitq 97e g 006
- EP
"*"'*I DepreciaNnn, tiepint* wt newf artwvteratmes intarest antinther hnanctat c hegas 2r,8 249 21R "2 251 the etteet of changmg pesce The stataments hme baan puhNc accesneants management arwt internaf moristors to ,w w= M Mn 1%m menu w % _ 235) psred b mning wnh p ah ep><ww Othar income jsg) (466) 14 sit 1%0) { Eammns before incnme twas arwi r unnrity inte.est 1.952 1.970 t ft2m 1.659 1.06R gg gwps yg i,,,,,,,,ciwncances and b. aumsmem(we wrurw eecsad m provostrin trw encone tazeg 953 995 02R 1953 620 g.lwk amnewW9 Piat are breet on nur beM murnat*9 r. ist descun Win eWM nf wwdr e @ W poeir nphbns _20 __?G , _26 juttrynants Financistinformatwmotsewhereinttwo Ar mes' em the adaqiracy of witeenal tenanreal enntwo t and the r lAnnryity intetent en camongs of remanhdated athHatas _J Q P*t? TRO $ 422 Flapnet k conessent with that in the financial stateme.ds ersahty of Enancht repnehno thaCommittee aesprev*ws Not enmings applicat ia to enmmnn sinrli $ 9R6 I 98i2 Your Company maintaens a strong system of enhal the Company's acrmenting pnncies, wwmnal acemywing sinancial ennemia and procedinet wpported tiy a ccepo-contiott arwt tt+ Anmameprwt arwt pemy maineial E mnings per cewsnon shva 3 4 34 $ 4 22 S 3 aq $ 3 45 S 1 89 rata staff N l'avating aurtitors part sm 1. .as" by vest-Vrww managamant has trwig verngnised s scetwmsi-Shara owners' equity ait ya= cowl (net as. cts)(c),. _ _ _$ i1.153--111.020 _ ~$1ot:5G $ tt1526_ $ t0.056- "'"Ch '"h* '" " ***' '"Cr**"9 Ce*P'***v "' d**0"*N#""*"*h'* ""'""C* "' "PP' t'""" c
- MMW and Wud lean 9m pty Hws serwmvhMMy 4 sefterlad in key Company Avmnoe consumm reira inrW e t'w;7 - 100) 217 4 19s 4 t4i 5
? To 5 t 612 sen-uen arrorha wah==nagenwss mw pnwy unwn.nh,.nanong. anen ar ungs e e (to=Wgain in garmeM rwtha%io pmm of nat manat=ry it=rm t(200) st12a) S tstI s (2n) s 19 2ation amt recoe ed and reprwted gunpedy The my54m W tiapy ccmtlirt6ng r4sts=te bushess inteeasts of Company ""U"
- 8""P"
'"""*C Divirfor'ds dectated rev romman shma 2 75 2.78 2 52 2 17 2 16 Marttet prica por comnen charp af y.ar erwf 47% 50 % 5f9% fi4% 60". haps tha anost keportant safeguaed in Wus sy= tam t<w tmsinags newinas, and compnance wah anhtiu=1 inws shara owneea 6. the fact that W o Company hai long em-Educah*inal rnmmiinirasinn anr1reviaw progsams arede-pha96 edtheselachem temininganddevelopmerd of gignavt in enmue that theee policies are etearty emdee, t sFd*995 mal Snancial managms to imp 5pmerd erwl ovm-ntond antt Wml there k siwarenomq Mint deviahnn recat feed to% . y interm.iwa - y= tan i and 7 m p w.ng ma e.ct m. .pe ment y me. se.#* penom appheahnn of asinsanas rw*ois and n* wiam was ned t. Inw ated n e is tiii, >+,mamm ha. h a r.ec, t ai em.danr. me cmm=io - n. rim int mne. '.ema - v-=. -d ne-4 -- eenewting of ma,aoamant s siewardship of corporat as r-m~e ~*w =t a.-a.m t,== yen v. ~t==*d in on e.r rea e r *,an,w arr-e.n%$ st wtard,fwand terme ed Ih.conesd perhatwig te=.' ne th*' inh
- tm a savg need maintenance of accoutSts in confoemity with gaes-
/ (F ASD) INey.e new e.t thee ede=m: ten seensir.g an trid.e~ de*riamd iennd n m.d w h m miemene, nr.g.n=. ,,any acc,,.pte.1 m counung p.incipus-Js/ \\ s,.wmig or c.d.nn t awr em~m, and,t.nnenns m.na-e ma en.d renvaradim, we r**nm wm.e e v== u,, 4,,,,,,,,,,,,,,c,,n,,og,,,,,,,,,og a v p,,,,,,,se i d sti. fWad a wt Ctisd %eiv. Ossirer ihp h nn, a co d.i m. i.a.wm.d c.
- -*=ntman s =hn== ah= dor = *=m fra *a ** r. ands "9'**"'
w =,ininen matwin dem.n verer n, t.n. u ananrw,ev. ha-h n rece~t m==<i ~,.ev+ns nun *=' d <=* ant fhMqe of MS te4pnnshHties insolM as Dwy relMe to /J g e m-n. m nied m carr< v en u 1f inwmwna is n.. finMart of 1979 ami.tspi pserhaghig fariece,70$ () tggh) enefairr**sof reportadopmategreutts erwf ananrsat s/ o,, g par.d uging tha set ud 0.i** =a arr ept.cl arenspWinry p,ww 4 Sinr.=== nt N= mete.m.nM ** *"rm aHa tra en. v
- e. nome, muee
- ia.e9.d*-
iner-= t=na = a m. j conditina. it*y cheain and ma.niain an undmstanding nt +.,*. w. rr.< wd. r*> ant. r.hn y1swinn gang.hern r.arw, an s, re.m. q h=$at on e. .nt.e ct + wh + mn m w,,,d ,e.,trmior nm noe.cconman v sa,
- m..
wa w-d cai ai-* it=4 ~t.e-t ia t o w m. urt eiat n. mi.. a u na=,hamp,o.m re,imant dnum in u n.e ve-m.e ua,y) Reporl Of,ndependent Cerlih,ed p3DI,C accountants I t mm. - tw. m.a mi-e s nm temi a-t o w.ca.d*+ p.h sn, - a.,m t *,,, nmannna,wm,ei.e. m may b ar mw =r ** ="aeino * *o'=*a~. a' * * *ncrde h*=maann er.r-e s uung s mu-is arma=+ m a a-ao m.filary isJeweishon etwnwe its tableg i m.td 2 tinw.v.e, N 04 thfint it.welvkug iny.ntney wwt peip rty gdant anrieq.ppgipeg sama*Janical 9 nr*'.m tha' #* tinsic conr.ph th=cv==.4 agg.'t Unid.r thes pencerber. theeisent+e et einNart esvnew.vt P***we me. th. snet swywhranf w Wie e.ede e hav..ivnirwt j d >t.antartenrum al Mt.eces elv.m mee at e.<tated in enyavMent To the share o-ne. and somd or oirector of mants p.e-me t.+ty n. nn=ncie pasdion cmenm at m .u..~4 nom. min. i.*-i E leurtric Company and roesisitwtaled attihites at Deacember a in..i., *ii i, ed m mi r. rti.,,.iu,n .d. tbl Prkerhat tyges edir,f,irm# win ese < tin arvo Srw g hang.e ire Generat Dectytc Cgweiparty dnBar 39 3 6g ericame.d by the Oswesen.e Prere fiertes Iror all ar rar Firm erw'a* cmm a. m 'n' *-**v cce GF-a we hav. c. amin.d 18. stai. ment of sinanciat prisition of 31, io79 a.id t 91s. an,t the,e uets ne is.#, op,easir,,s n,v, atusitenna innet in 1W m<.ed t tm e.stve.1 mits t979 venRar o n.' ate-t sararea ofP.-. e hann.= Ins arw.rdic gymde newt Gan.'at Elerttic Comnany and consolidated attihat*g as tie changesin M*6e fer ancial pewittnn inr ite yemes then whanrews um rrt m s a..-nri. st onnin e.a w WM inWm@ e pq mWf MmW a."hnres amt l?) Ins swagerty gdvs: and.et.pgemed. evt.ma9y of De.mber R,, 1479 pH 191% ard Ww FNaW MW S8
- Pwthameng gwiesit psivawd nf 12.t 74 in yabe th. aevd arnet awt wwer
<d ew. cha. < tae m v= ria==a ce g
- cair, d.m -mh r, ham e idvi,197a..ths.es ce n
dmngeg in shm. nwnms' eqisily tm Wie years then mid.d a=saw r== tero =i. n=-y <* m *r9.n.+t he arennated *. e fr) At tler.nih.e 31,14'9 pe riereent rait at mv.rWrery.vas Om c=armnavirms were mada iri acrewdanre with genae-Wi.ir arywwal.nt ws wme ed 1979 tl.dt.ars, tathee thswi nit.n.ie $5 ?$t minion and nicearm.ty te*d and erftarment =en et the metrat rusmh., et ren te spent $7.ftfM emnwws F glimMed rgn.ed engh armhrahl.mIh.wan Ally arrepted aterblmq ttenrj ads, antj acreertigegly g [ g/ i 9 Itap headleg Afrittert ent rttarws.9 ire WHr [irer.1 et surh anw==ds he=t eturing sa <= pad d '979 wir'*a*=, hv enenriert such tests of it* aremeding recor.t, arvt si.rh q,w.esce s,wm in.dn,mminn c..pa..,,,ing v. annei appmestmise'y $I.t t 9 wdthon which w,s 5179 namnnI gs othew eisdalhag proc.theres as we considered tweesMary in ress m ire wri== a c. c appnerh to tran=artereg =ivedvewy wives.o ity amt peg, mve me si an.nininn uie.a,..d* h en +t t. n=rm,
- "'ll'tY 800?2 r
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- 3. (9(
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se lummarYof si nificant
- "**'*"e*pr* int savire een ovm a p~in., a',' " yam, NotesIo financial statements
""".*d ma,."et vmiu. nl inest asset,'*at ihm onet rd i,E sn P'C'"e*y """'"'d~"""*"* "d "* 79.as mat 9 $ 4 wn mne, nd $ un2 miairm at ih. e,wt et is7s ornic-iccounting pohc.ies .re e**n charo-f to np-aana c emm, nmmmy n w esi e.dihai emimenn in eia n =6nn otan ettartive Janne y 1.14ar). *9 rw9tde in meremmes of $90 Orsvestment ta e credtt ,iwtrinn in tha Plan
- unhewletO ItaDitiths The irivastniant trs= ctartit is reco.rtart by ttwe "etetanaf finannat tratement* rd the Pamson Triest appear methnd" nevt is amtwtired at a toew the,nt the gwtwh$o" Int lavet over Itw feves et the tvilst'as to which tbn e rodet 1, Sne,g
- beln,
- ha virtariChl Statar1*ents ennsntidate the aerriterits et the apphm. rather finan beNSQ "IlnWed threw,qh fn inrnmet M Aggiroiremalaty rine (*eghthof sales were10 aQanct8ts of th9 tssis of congatidation U S novanmerd. wt*-h M the Company s begast ssngh Ceewed Etmric romenn Trwet
==nt Ganern Electnc Company w,those et n't ma;ne-the year the esnat 6s autuhert i cu<tnmm Tha rmetp* *oure
- nt the** satm ana tha e-1979
- 79 e
~ ~ ey n.n=t end wnuotimier-epan q amriat-t ramre-1erhnir at Systm and Mmesin89 gegment of the Com-op,.nn,,,,,,, t invemort" .nt shwtm en shote of the fornnhdated germp M signdL Sehtantsalty all manutacteutnq wivent,r6m Int atmiin 19. pany's hteginesg ingas aggett at Jamnary a $1.328 9 $3.918 T am"), escoct finntw-e compimes whnte oporatenm are ~ carnpan, cr**hmm. 349 r 3is e
- me items reta*ina n tr amadinna amnno > parant and U.3 ara =Mir4 nn a tast in rest not m t ito. dam Mmt i
it%tiatad companias nre etwnina'eri tram tha ron=rdwtated manutactiesnainventnrMrnetofa ff= tt S are aanerP y i 2 Opereting coste rwgieny cred.hd6nm _ _94 3 83 3 H t on .nn, en,,, t., ,n,.- c,,,,,,,, h,r,, t n. _55o _p, ow tarw'a wia -t arwt s ir**vene r na __ 294 3 _ 23*
- vaw.mt on a ne,i in r,e m t.r= r ero h m vasint.em ar.
wi.monts ., me catem.nt of rmannt pae.hna urwim awestenevis innng ovmhea 1. and do not e= reed nat ieaniah* *aivas f,,s.,u,y,,,, r,,,,,p.,,,,,,,m. inri,,,% -i, r,- t,7n The nnnconsnrdat.d rinvir-comen+< me inchwtat bas f m te cme of matedat dir-et abnr vws mwao ce==noa =i-= apt atera i .rwt a e vatued af ery Aty phes advances In ad+tHn.rnm-cerIain Indirart manuWturing espemet ** (h* cart di-t n.se $ g. pas 4 $ y,4ot 3 thMirect 2t t 07 Ar" mart ___6 r e _ 75 9 oanseg in which GE anr1 rw ns conud. wad artgiatos own rect *y in operating ene:tg themq th* retirwt incierrert. rathat u.t.r*=is. sispr*** =a'vic** an't w='I-a9
- 2 75
- Penwies tions'ar=aad em-rea's "W
' 8"a 7 vre irsefurtad tander investments, v% sert at the ppprogwiato Mming irwentories, wherhinritute pdrw3,wtu mirted
- '***""'D""*":38
,_pM _pM vrt, w r.o. os th. voting onewu nnat~t remnan m 1 than betna inventnd-f Daprettanon dardannn and py2:3 se q3 v ..t are ct equity plus advanem Am r ta em aings et non-me pad ront metal corm ab ates and meng suW'e<. are .,,,,,,9,,.,,,,,,,,,, g,,,,,,g,7;,1 g,,,,,3, --~ ttatmt at the in. e of avaraoaemi nr m= Set t be rmt nt 1,,,,,,,,,,,,c,,,,,e ps, t pso e . nmnadeed annne.wmew.s mwt amnr.aws compa-n.es . incturwt in m. tai-ment os mnmns under ether min.nn inv ntewim mriod-s e eth +r-t and ir dnert rmn w m m
- n. w,6,nn, y3,,,,,,,,,,,,,,,,,,,,,,
ComMteriq of tabor.{$urtheted siapp ies amt setwk eg. and pie yeser j157 9) _J3rD9 9t p,,,,,,, g g 33 g g,ggi g l depracMttnrt. depletton erwt nmorgirahon of peng*rty, p8 ant - ~ ^ ~ c,pn,,s t,,,wtg aret newes 547 0 354 0 $20.330 F $1 Ff95
- stirpefte
-Z-ek.e egrate and aw=to sgas 919 0 7 FO O A nnnromotidp*ar1 uraneum minerwt erwginny (ep .wwte t?)ig hMointhsdarlunrfee bvoetmstritt anet es v=Iued anet eqesipmerd crem we etnr+s wat r==rw* s 29744 _2.7st 5 4 s.,ppi ni.t d.v.4. we inann 4.4734 4 on a ,,in.-r et cet or equoy. plii, advanccs ,,7, ,,7, prormty. plaat med equipment Ei4 s saiti Ch a"'I '"'t '"'* i"'"'"***5 371 5 ?** 2 unnotarsurinet pirent arid erreinmm't inraadm the twlo*al gm,,,,n e.p4 Oshar ma*** - not ,, _76 6 _ JT T we ebe Con peny and itg ennshrwbws at' 4 ate recmrt a ret nllanet. tinitdingt anri eqmpment lets etyachten. comaccon as a sain only won tm. to entucts p=<s-s to which k the m'imatart emt cone n~t by we=< wwi ch* cnisipseny sisrirtrd roseserch wert ici:d e-** si??L5 $1328 9 i .ti w.pn ni sao o s2e e ,,, eminmer of wh.n sm*.s me emtma mt in actned-teceara An arre'-ratad daprac%tian mathor' ha*ad snrint e,.evu, va. 471 3 vir o ri.newd nasan., g,drerig alty on e ettm M th* yea's digit
- Iormtda. h r*8'rtin Artweetning 741 9 24 F 4 t inNiity m pamtswipes St.PF4 5
$14189 7 abat ??t e ton 0 t i=Nady for remenns en mote wittwcontract terre. reemd tiaperlatirwt et the celqMat cost ne marudar betriq Minersaisoyaltiot amt eutwwt stidies 9t 5 7n g pedirigents wW M eeM ,1W p J%@ pi;gnt anst entripment ptttehaged asiditisMN in tha U 9 w a wndad me in'ias 54y15 5$3re_? nne empicy.seg earn cr.d.w d,winrt > runent yeae im =>d *~veant m two Arqukitinm tww= ta tra avt ramt jg,,;p, y,,;;,,,,g,,,,;,,,,,go,,g,;,,,,,q,,,,,,,,7 Wacitjon 9tperege ,xanom to t. iai..n in th-to ne..a r.m t h. e.neme manut,riu.w,a rdant and m' air.~niincawi nimida th-l wm,,co,,,,,,,, e.t. cts y,d,nton,,ty,,,0 .,1,,,n,. w,,,e cet<ts N tt= =ep,eet-sier r.iar t=, pp. s.nn peari..re n s3,, moi m in 1,7,,ces sas 3 mitr.on in 19 7ti. Unamor U S. me deprerlavd an a s* m9 t ane bask it manu'ac-i s t i e miri,nn in I979 mwl s t 21 mittann in i9 Til h for tNs yabmty > ncticed(funo th-v *== ntem me g carned rcther than inihm year vvateres am takan turmg pinnt arrt eqmpmant r4 cdt=rt in phone mal em q ftnmir Citrictitleiriq or obstdegrenef4, attrttthesat degastriM8on { g g,,,,9gg H provirfart. F uppewistures trw m1witanarire snel rapans et General Flertric prwills attihates have a number of pen- ,,,p,cyyppy pen., tone mv tments N n c-ni rtert,ic renman Trust which manuterturin9 piani and eq.einment ma rhma-1in np-n- ,;n, p,,,,_,n,,n,,, Comr'ay co*10t ab'r h
- as 5 412 9 Utah has sep:w ala pemann ptans which me <ishstari-g,p fury stFw1*'t anet the entM pl whirft are inchpded h turwis tha obligaf6nrog r=t the Gens *ral f k*rtrec Ieftonn tirtns Ms inr"Hrred tfdtthnin 1979 Rred $39t 4 melbrsnin 197R lhe meist sig y
plan, e,e cantad at amne ti7ed rmt p8'st renormemed ap-The co*t of minirig gwog m hes mrtudeg inithf evW-niticant of these plans is the Ganerat Flertetc pencion ,hn total Company onett repneted above b Md h se gp hgn w,p Qggmg T',gy g,MantW RR Qy n Fm U S me mag %g%%www practattran irt he enrrtmem time b por thtpo Raryngnderitt De $tRes afid cDs1 of ma,nt rebipeWrw];tenjariq Much sedvetan-pengenmmert appeettatirwi M eare.ad out t.n a systematic tialty incre=== tha motut five= N =i< ting as5ets t ha cet p g,,,gog,,,,,,y,npnena vndee pin baes whsch does not alve servtue wetqht to short term et mming prve vtes H deprersaie t depleted rw amnetired reminet pian totaled 7530r) anet 72.100 at Darcer.ber 31 evremos for incentive enenpansatmn wara l'Ji 0 mmeon erwriret fleartuatincts. Prnepmmed sprw aciaten will ont be over the us*NIlivas of the rela **d asseds by use ne und ot~ t 979 and 1979. reepar hvely, nr.d ohingsthms of ttwa Plan in 1979 and S47 el rremon M t4784 recognirad a avmana ten 6 vatoa c.ceads averaga mm. production. serpioht 86n* ne derhn*q hatanc-t'ww19 ,,, t,n,,d p,,,,,,q.,,ha or renenyt in,sv Ord v55tV8, ch ctfintarj On a rTvrtvletr) bath Over a tretettiyaar $.hrsteig ewptnr Atton efisl9 nr* erref'*ad ifnt.IIt N d*" Mn Mtheir $ brW q h p q W e I ter reined thmI tha d#VWInD'n8 wit nt "Ifnharal dP[*N%d '9 g9ggg g pp.gggg, gg g g g gggg, g,gg i giprtnd l The funding progenm int the tymirm Plan uses 8W as Wraly to be ernnomtrally taagilde Attee thH riewminMinn pie prwh were R R tor 1979 mid 7 8% for 1979 the egtimstert rata pt futura Trutt brorna ihn ente in-is made, att costs related to tur that davatnpment. inrttwt Med Wttes M the Pembn Phn wrma ed j chsdes ey*etamatic recognitwm nt appenrhtinn in the com-ing tmancing cmts or idanhtiab'e new twwroww'qs associ mfe be $R1r,nimbre W Nem% W979mpmmt neart anh the rtavainement N nae ndmna rent-ets. ore ,,n gm,nym,, p,,,d ot,,73,,,,,,,,,,,,,,,,,,q ennn stor> rorttono thu8 geded prinr servira tahaitees of the ptan are amar-rppital'7ert Amortiration of mais costs tecim uten enm-primasdy tenm a nentimente en tie rensien Plan which t elf #d ovb; 20 yenes Nat nrhemiat gains mwt irrstag are er stnrentemt ett girnductirwt aritt H nvm tsan yeast = We wme etter-teve in i979 Unturwtad veeed Eahnrier-iro pr.trturtive tiva of em proomty. wherhavm is ien j c,,,,,d in,3,,,,,,nn,,,,,,,, s 7p,i.,imirin and sm,,iii amortired ov.r is y=== i Costs of a s*parata. supWementar y pensinn pha, pre-Oil and gas propm ting nee ar eviengad tne by use ne the nerfly tttarting tong earvir = pen'**=innal arwt managasal tutt rogt enetted [ I n n.r r e
- r. n f
,,,,,,,n,,,,n,,,,,, l l l r
i 1 I gg pnventrWeg ende.al encesne te.'E #*rt et flunkg ttit eeenc*e en U 5-Centtermed criregnhrtated SnartriaYttst
- s inn the l "' k'C O**
- .'-iee
-. '.. _. _19_7q fise'maindem a,en,e Gnce,, i14y j jUwd 3 f m..wan sp gi., ,q 79 99 g IMM N"r OW NI'nr ahnn M*a prhropat nnnren. 19 Na ~ ~-~ ----- to *g Ig79 "#N -h WW
- I e-w.c A7 H30 E== nue' U
Tn) 5Ns 3"'"'**"aa " ***4*'* GaaarW*rhit Ca*4' 'H= mat *w=ars 252 1 75s t vbal=Nor ectytenee oweinre anpases "a e 340 4 005 5 C@
- M dN W LT N 9d N 'MV s
Sn.t t e.+cne pd n.,,, nt.mn-o, n _-J."= be eNa6nad by anting in Ganaeat flertdr Crarft Crwpne n- ,, g ,,,t,,,,,,,,,,,,,,,,,,, '"4 ***"ri**d f""Tanteg (7 y 89
- d '*'**
'*'"'"'4 C'**'*##"'U6"O# 49 r 44 ) w a ty enet nor+inerW oyeemsw.eg '#*9'* "" '"*'**nt tat ** (* 0) (*0 i) e s ~, asy,d criervandet end nnh P***""'"'**r*"** tlH t) Of s) N the M O nwPind of InvenMry accountmg had been g pg
- CU"P""Y-
'"'*"9**"'dh***D'*" b"' E3*chte CmfM Corporation creaanhet#erf tpantummining nM.fizie it ? 33 7 k(5 g) 5(13 5), Mewacter pnemen Other - noe trw t 70 g gg ~ _ _ _. -. -{ $ W 9 nHenn Ngtme than repor ed at Deeendier 3t, I6 31 .,,,,,,,,,yp,,,og ,,7, e t*19 (5 L5 *9 n en.n nn high., than r.po,,ed at occambar ,,,,,7. SU ted in a desferred tag aitat wherh es theen gpwipe etter -g - -- -gg p wl.mr, tg g ,o 5 it= cinnutativ. net en.ct et twnino,$tter.nr., das.e
- 33. IINI Qgg,4gg-g
- en.e,un., n.?,,,
.in, ,3, t ,t.,,,,,,,,,,, jf1j q gj gig g swet. I firns tales e et harm 7,quig 3 g pgy 7 1979 9978 b.e ,t e,,,,, gg,,74,) ,3 9, H*e# '******"h*V'0*"*c"'* i 4.*===e6 ~ ~~ 6 5585 5 'y,U8i 9 g Pr guttefry items leichade gamq ferim *.afag nf market. 5.? thdmIsa*50cconibar 31 ta wpaity eacurttes of $r,5 rna#enn m 197ft 9 9. g 9973 b"*9'**"I b lons*9 I 207 8 1 ft11 F SAanuf erturtng pt ent arwt ogsdperient S""M '******h8a5 , _ ]40 6 _ _79 9
- tt perf ottw, fmarecial thaeges y j Q,9,~ggg g -- - -
g4- ~yg 18""> $ 174 7 $ fM S I"38 r*****ahla9 T3039 6.11? 5 unepsis typter1thle to principal Memg nt t wig term bOr-flaductinri tre tavet epoeng fenne U"'h*"95 9'""'**9 #"wt A4"*nnre tnr en,s .yg g) ygg y, t vingi were $'t7 6 mittinn in 1979 and $49 0 malion 6n yer ywig ta= satse= of (nr,megated "Pa"at FW5 19438 A aftl#Ma*(hsrtm9 igDt9 3 DM 04) M*h*""V *"rf *rPdiwnant 5.394 2 4.717 o Nat rar**wpNas . F 4F2 7 A t t_st 3 r , 37, 3 ,yg g N aomsg br bienn nt ecmr.p ww
- 6' st reeg and manu ac.
ng P int up4pe mngerter1Inse 179 8 737 4 Yntss aggeog g('t4_ F_h
- h. k_.td.i.t_j l
3 CM Cnepwahna ln t' aloes taw gg,,,,,,",",p,,p,,,,,,,,,,,,,, Novklori for tricoev'e tas** M'P**M en aNar las bewg p 7) C 7) Md' '"'**'"*"'C'*d8 UM UD
- 'P'""*nd f.456 0 113I $
11*?t 0 19 951 0
===mt - 9978 fG71 Sk545i 55 555 E U"'""N"*""V""' tano term-emnerw I 741 0 1571 t setterat mrcrne tasas tav Wmg*31 g@s se = (O M "hrnestad amount payaNa tr/ast 9 $sgo 4 02 _Q $ Cnge nt.koneenry 1 Og 2 57 5ti g --
- d"**"d*4 3?48 3?$ 5
- M*ct oriknerag ettswanres 0111 (t3 5) 34 9 % 4' 5% Art %#nne t psy 3 g(ngg g N~"*' Wh** **NI*** 631 3 JI3 F wmosnes't era st desarrest - ew.t 45 4 24 9 ngeirieur g My pgm -66701 _53633 E8'"f*'*'**'*'* 413 6 '6@ G Cnet atDacomben 31 {9 3sf j jil 356 I ,6 0 -615 7 71 D****** t iruvia** tema= m~- = - - 33 3g Mau a ocione, depisuen p.sm,,4,,,,,,,,,,,,,,
- gri benme fases I I*'"I"9' P*' C"*'nOn ghare Car nttinre 1,f,6 4 441 7 e so matad amound payaNe 1M 2 77i t h#r* a'* DA**'t on ttw avmaga numbar of e
E "' "h 9 0*' S 4 51"5 et sha*Pe nutetanrfing Any tilbsten nhir h w wstd emetelt fenn, Mi 6 Dm4 A+#sirewdpaid mcapdas tt 5 tt 5 e 45 4 overi nt unung efte.eures n e d e t. 23e 5 27t 3 73 f*w pr tent'ai espert9a or etwwerthn r 3 turh itoews at sleick ((* jQ I[ *I Yn at en eeing etes ,t3 ~#t6 4 -676 5 E 9"#Y orar.a m conv nbi. dade nu =tarwerig e,insinnincent ~ $ ""[,*" "**" *
- e (tesg *han t *L in 1979 and 197H)
Ohar cha"O** 10 9 _ ft0 tt e s sn e7e ss sse r n, - - -,g, =---m __3,t 5"% 1' 4 $8J)9 M*'r* a' Da*a**r 14 $4,rs:4 s4.305 s sa-a and.,.ty -, ;7 - 9 Cath and mnetectable sectettlieg g ' t J S federailrirewee tan eet+ w rts have t mere ched Isina dppo*Hs 3rtd C*tleftrMP4 Of Wet agryaQM*f 19f9_ _ _t0fR strnorft 19 7 j, $t 8:75 t meinrm at Dacerv+ee 31. t9 79. setri SI.746 m mit- =S[ $N M*"9__f_* ** *=ar _, _ _, _ _ _ s'_ sor 4 s _ e,3 e I'envl41nr1 has been friirt. te fadrw a! wireme lavag 'o tise
- nn nt Deren+er 31.19?S Depneds ra%icted as tn
~ ~- F 5 a** ara"'a ut tm thal pnetern of tho unrtistnbedevi carnmodl of affeh,. u*a9" sad *' thora *e or uwd as p tN r twr'ran5atan far 8 as anet c=nrtateruneansa. rartad in ba eamm 4 hl Mnn Wmwing engngeenentt.me M mMcHas t2 trwettonenft W M 'h"M M2 347 the Darpnl Certipany Urtrbstretmetent est+vings irtlertried to b#t#4 SmCWhes (mtp Of.htch nem swgesHy wr7Bri-89 MF9 WS OP*'aNa0 and artamNra'iwe 145 6 3tS t Pm**ww' tm h*==* - wretvWilog M4
- ia 4 mffwattfid iridefenstely trl Mftflatet arwi musuMaterf Cem-16.%) ase raffled at the tower of nmrvr%7,wt enst ce ma, bet
'**"*"*"*d**'*"r*"fts#*** $_924 0 $_6416 -a*-'*"-* U et ao
- nics totalert $144 meltion at the end t,f T'3 74 anrf $A f $
va um C3rtving vakie ww tubstgottatly ti* sans at mar-sellion at tha end of 197R het va'oe et y ar mt t979 and i97a inr*,d-t at y.= enr1 q;;;,7 "'*""'"""**'9 _7g _g
- I
"'**'*""**' ara"*'a-* chang.s in estimat.d t.weiwr.ci m. tw.s payatore 19 79 -wa u s i..n., c+n anc.,s ni s4 rn 3 m.n.nn ,,,,,,,,,,,,,,y,,,,,, _g a ,,,,,,,,,,,,,,q, .a in n e.'veci ci mming er nrr., r.,,,n pr ncipe.y ts193 7 mennnin 197s> n,,,,,,,,,,,,,,,,,,,p,,,,,,,,,. g e 21$ t 244 4 g,, %g, .. ine,.m.d rarcign evoi,m anet tu.7.s. an,f from guasoneaed seenw ttag 4 4 Gh*' J47 5 _ p9 i mm, g wy, p3 gg 'engedring in 19 79 frw to miyme nt tappotet ttw tesuttg 9 Ct8er*nt refelvaM*9 _3eo e _3e0 5 n n.d m,,t, a, p.r,mh.,,I g 234 g g pii 3 n antertenog in Austealig recordmt frw finanreat repneting s e r, t97s
- n. -*
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- r$dah'* a *>*v san *'a.
_ 44 o __3r 4 __r__. -en=es in offwe perinrta - si7s4 6 - 6,77 i irwastmens er.dn nemone.1to s rs e m,nion in f 979. c- , E.4, note. ^"'***'ad "*"eaa*
- _ 30s 3
_25 M Investmani in th..wnnonartaiers..n*,m,n.ns, = coated ae se.o 7 tn mnn in th prior v., in 1979. A nse.d owy,s ip, _ 1t5 9 _ m et Menai-cr.ns,, nr an,,,tment in.tw,a g o n t setaimi. is n 2r s sm5 si.4ie 5 re,tatast.,,in ni.cc.,,w oe re,enin.ng a u n opp =te nt
- =ne na4m.d a mai.,
69 2e n lo s enmirm an netd-s to r-1 earn,ngs. enmpa,.rf.m. 's e rnimnn in 1978 Al p. end ne i979. th. amnurw se.a cria _ pn r _49 e i ne A,stice notin-n Artv*r= y cien ance rene. din. t n 3 73s o 3wo in fTttenpetton urith they }tl7ti {JtRh mentqstt)In qwh6rit 3R of a'ened and to ha incimtad n, not eatn ng, in futu. yey, A"I* "9 .b -_ N th,, hen eust,ng uranhan b. .n.e ne utnh he, bean M $206 7 milnort. s me s 51299 5 transfarred A8 cfwrimews etnrk 01 thtg aflitiate hM baen piared In a vonnq fneet crvdmse a e, ;,,,._ gyngng n hi+=ie** t%w to tha yr.c 2nno. Genewat f I wir and les
- = fL=
e r -ow m e. w $ Arw.sd Raymet et?g e -.., ~_- - - ~
et a n . a d a e t 4 l ,s t o b e eo.t r , p itar v m f s yef -.bm pe h a oct t ull h a e 7. 4 e. mihd i a r 3 tsvo - m,, i a y r 3 lomfhi r w-cd w k elt oos t c w i .f m=M'l r e a se p8 i e tmiid ir cns~eeewe p1 s r r c n .. ar mw w emt - m *' b a " p 3 m. foeia ipg - n I, n r " i n nr e rh p t g ,hs o t Ct v e 7 9 n a et n o o 9 t. pb i vt s pst c a wa*edd ni cmt F i e f e yesi h r het d t h Ms utsMi v c t,0, t r er M r e s oni n v i wh a r pvt n n a a< g nmt t se*w mr w G s m "* N a f tv e. da-:- "3fs' de n erfow. m a, d . tes sys ns e e t n e. m a cr in:.a vl e at we 6a e e o . v
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- s y n escore9et uf tsn r ede wnl aht ooM'Em e
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- f t
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- tnme tr e ee ewt i eett gd w tumt pn
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- n. n m t wEmwges hitwt da*e b F
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- lw'"a*'t n
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- nl n tss al s e er te*
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- r. 9 h a s ar a n o*dtwh9 a rb r r
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Industry segmentinformation I [ t.P31.45s shmes. ora mitabh.to a ardem mtirm b"N' wt P'e future Apprecialtrwt f wfits rel1tissg tra imespirent 2 _ _ - _..- - "**- _.. -. _ -. ! *"** "'"*._MN""*"L _.-~ _ _ _ felnns tne I.957,003 nrut 1 A52.494 shareg emee rm.d- -E-' -19nriIrig nt December 31.1979 wwt 1979. respec16vely '9 #9 'I#8 ---a_- '079 '9IO
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'9#I #I '9 ?' 8 """t""***' I 8 I# 0 I**' I NI I"" IWI I* 2 IW2 $4eetnemsanr;e gnits wtitt an sweenna ppe tswt mawwtiure srteevnble vahut of $29 01 reintaig im a one tr, cme 1 7 he of og InitsstruppedW newtceregww.eeds 48023 41239 3 See 1 507 9 east 5 411 5 42950 3 FS 3 32846 3 %64 4 3 49% 7 3 29 7 G 294 9 t 74 4 153 9 31%4 g 3 3gg 3 3 og3 y w kimble tnt grafdmg optinr'% at th* enr1 nf 1974 #39 penww eyesse m g e em0 e 4144 is 4 e448 2% 0 tas a 1en e 5 nom e 45% s 1 wwl a 2.'rE577. A surnmary of sinch ephrt i teangattmns tturing forfmers y.wwn-and m wme, " d I"'M*8'Sh"*"D'** Neheat egeweres 9140 3 30322
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Ieme rewmumer ywrwharts enet *arww'** go,,gyn,hartt erwi 2.329 9 2.t251 99?51 176 3 165 6 947 7 1,19 5 911 83a s hempia redwig and eswnpewoneg r serveregsocussrwners ss.OR16 s% 642 3 s% 8mH 9 59.127 9 2.835 0 2 *04 6 2.t52 9 10s t e4 3 at 6 91 6 ?# 7 73 2 t Grieraling y 4705 5979 510 7 5%08 pn.or =yete m tar 4 pamengo yt14 3a2 t 340A 3p2 5 tertmaral =ygumes newt snoteem's 34221 2.E62 7 2.1211 3 441 7 290 2 203 e ts3 4 g49 6 12'5 3 1.479 4 1.4R9 3 1. 3 84 # 0 201 2 212 5 1356 91 4 77 5 99 9 Nahw W eegrJewr** 9m enmengs po, ~ t 33 1 69 1 %ft t RR yp,,,,,e moshe sed,Mry riper wirwie 27599 2.099 6 t.949 0 100 9 199 9 815 9 9t4 R19 52 7 cnmmem shase Genersi 'crtware spans awt einnmannne _._!.846 3 j.838 9 ,,,,18637 23 5 15 6 _t4 9 f19 J5 _ t5 2 t s sJ9 Pit s 5.0)s 0 sp69s a 59.262 3 $9 0551 san s ss2n s5_7s 4 ssn t ,q 7g ~~ see.of ende rt,eries, se 4is 4 St.eni e s4 a42 9 s% 403 7 - esicco.enner t Twsppng marips ei3 4 %?3 3 464 0 560 1 _ le bresste,smenpnnenes i Het emmingg 247 p 319 4 2n8%9 3R3 S Corteurtier prortucM and e:erwiree ennen% ni evingne aggit1 w et. Ormoret Etertrtc Cre*Nt Corporatine, e e4wey nonest annr wi Inchestrial ptedeette ered C., I e W **"InO* Dar are erwwstbrung errupment Egheeneg pedstgg hneogeoveg ann) 9"31'taged knapre afreaum. enggges twwnmWy M crwetgeeww, eswn-Eggwierance ermern>l Sree# srw*wg prerY elmetterier enmprweents), EP8W480 SNt blhMirtat innenreng gwtrirgta# t inrtiseertste r eputal esgrepseient (retregnee #nst, miserpreallose erwt to arig. I I Guettn prtertur tg and garvires, tels'wt": ens 9 varmtwsteg newt twnsit pmenpape. In alegear stegree e,titeinse.9 rt pse U $ ll 2090 manr m and else and gwwtasenn). enewdensenr, angparterm, reper aswlretiostreng of eastei, senet cahtoweginre servireg # ake 6w esries servdre npers-erwig one sme6ne appilanres ase erwet>wierg GF 1W rereerers. CN988Ryin*'srar1r ermodes perdw toof rrwnpaniesnaher share peer tetr eter traner arwt nunctworitrat apparahrt erwe a newerwt cf GeneralFbetrar enrmtthse a matrw gwwterm of p..de.sg ananrewt geirp8y tweenee citeemg p nstnerts ed GooiseW tseriete and anice nrwt hrm pe, and niwen pn,6=-f, l'y GF CC ensrestarteers - the n-rerat Finecer tuseekw 41 42 Arapiessd Pharuwe tt14 4 i 9
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.tm .e. I,. ,ae.,..i--e,. test eerntnqyelor Indswtry osagmar.tg ire prior Aneursal naptwig (129 5 misurm in ta79. $"M emMwm in t974) 69 annratiid encpar-reguns.d from hlgher volinne. tioss ed wskbg capitat 1 hase improvements were partinpy trarbeteet e4rsenstem at empnrat=Inleepet ' wrwna e penge sewt sting compnnemfg having ettengibliny trw Imentmente in con Operating costs are gummnetred in the table ors offseg by the fart that sofE.g peret en cordencis taken at s ceww ansenriset raa'0*9 tr'r**'d rT'*Pa"T C"*r'**'wg tinged gnh,4=ted.munies pnges 46 and 47. Prinripal elements of npoenting onets for girm prires severa' years aqn were not adeqisate to rower ydnripesy rescae,nn. Cewne.nonring et t97* Se allacanraiof h,g=went, siin C.E s pnhr y Inter *Inlamat gnias so warty 1979 anr11979 nee h nnta 2 to the finanrtat stniements c,, rent tvisi initation Norient operat6cns continued In in-ghe,. Item, to parord rewnpany enenponerim has teen th:en,yad og yearerstilemorpstesalarec-. .W *anaqpeeret Despite grmrt prorhattivity gains. Increased matarlat and otp a in99, althrwach te=$ Ihan in peine years Onwar Sys-i. Intwr costs had gone netverse impact on the operathg tems bitsinMses' cammgs in 19 TR were 23% higher thart Geographic segment information l I"a'q* '* *'*ch = ' 5% 'a "Ta r""'P" ai*
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r 10 o%in f 978 and 9 7%in f 977. However,operntmq generator sen,1 powet flehemy porNets wswa principal i margin doit** In 1979 warn S 172 0 minion higher than in contributnes t he rusriam bminess ogiersted at n Ims in 1979, which wern $259 9 mitilon higher than h I977 t978 m it hadin stie povmus two yeavs Other trirnme from a variety et epoenting nore nnn-Ter hnical Systems arwt Matenals had strong 1979 sq.v mses opaeating noirces was $519 4 minion or 24% vnorein carninry inc,pases on sutwtantinity higher revenues EM-Ua I _./*'**'"" gggg ? 1979 thanin 1978 Major tources of ether income are gineered risatorinig again toad shneply higher earningt nrad othewmin note 4 to tte finserwiat statements Fmm 197710 smieg Altreatt engme also had a gnod intresce in eme- .... - ----- I--- -- - - - s d'll .14o 3 Stp yI2 3 $ t6 0R0 $ $14 1979.othat income increamed $28 7 milliori.nr 7% Prince-ings from sha,psy h ghe, gates Tee hntent Systems smt 1 f' _. 3.'37" _. d'.## $466 9 t,iriked S,tatet $,M2 6 $ tens 92 Stn t3 3 $14.87 4 gg g 3=8 47. .r, m _t.
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.. tr,t. t om 27e s 49 -o ,,e,0, rna,,e,nh,*,em,r.e.,rw,,mr,n,ep,,gi,,..,d,,, re._,.,n,,,,,,,,,,,,,,,,,,,,,,,,e,,e. 3 12% Other meeas et the wneto 3 ni18 3.270 4 2.9t6 7 12" 4 145 t ta 1 @q oN h M br.ome h MWM N Mumm 6hWm FIhninennn cHreermnrany panieg arwi n nnnconsolidated twanium enining agliante Hattual Fletruerrei 1979 earviings were aheari nt "" '#W ""' E'*P""""*"' E,,._O $_5.1._ _ttl,' 5.b, b ~ 5U-e in 1979 than 1978 dip to hlghev interest rams T he 197R in Canadian nperatinnt. principaMy ns a rctult nt hiat*r Ordosest esp *nse was tip t 2% frone 1977, pincipally b*- world mneket pires tne ropper, gold, seawee and rnneybde omngraphee opgmeewirdnem=+ inn M tia=*,1nn ghe beseirmnf Wm 1978 *wt $ L2t6 e esinhm m t977f were to cie=tomersin Etware. Caetse of increamed offshrwe bnrettermas antt higher drp-rusm.was the en$ #Fint in the emeriings galel Natueal operenne sinnigeeng g,wws, nr eneveres Inr%rteetin tJnded stake Aircre ord#m Mbek#e E est and $7412 miMinnin to79($4981 e meeIncinternt untos flesnapres seventweg were 7% hioher in t478 thartin enenrmin'19'8 ewt $574 2 m nem in NT7) were ermrginmers M ,*wemse, were espewI==tes in unatMtate.1otetronare al $2.T721 Promsinn ear income tares was 159 5 milHem higher in 1977, but enenings weie rbwn 8% Austraitan coHng cond muurin en t979. $2.570T enemrm et 19 7e nr=1 $2. tnt 2 mellism in tho f we F egtinr*seting Aevntenha tp S eovenim, phninr%demy. 1977 of msrh em ne. $t %Rt 3iwihrmin 1079 ($t om t 9 emmemin any onet airembo treine hewn imafN a>vt hweton grwereg. t979 than f 978 although me pHerWve tan rsie m low *r shipmerds wave ahrwd the game og for 1977. twd eamings e 09 9%in 1979 rompa ed with 4. 5% for 1978 and 40 9% we,e gnwer.priticipatty herstyme of a niinces3tedse of neartyseven weelig newtt#gher Amt ahantanes tower 8 for 1977)berneem pt timinwer tj S terteenitav este eene +wn carninos news trmes from n'iarilianieon me nper-ps g,m,,mg, Aewets Brwtisetry e*gment resutte: Finarw-tald:sta by industry 989 niinnt sko cemteibested In ths earnings rierrense frma
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_I9J9 _. _ tern _. _1977 _, J9 7 _1978 _ t97! ment for 1977 through 1979 nee presented on pages 42
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thned states St., to p g eso s $ ess 3 St2 693 8 $1 t4 80 4 $1 490 5 through 44 Denniiert romments on 1979 ratufts compared Foreign Multi hwfuttey s earninqq lor 1979 were dnen i rnr r 4,tinrio.ang a, tron. t r3 9 1To i ist e a421 naa s art 2 wiin i978 nrn inriurled rm pages s itwo. gh Fi. neference ,nmewh. on modestty hirfm.,evern,e, a owe. c.enings one, neen, as em on id t,9 s eo? n n15 3.2n7 2 2 n:ia a 7.414 a shnued te made tes ihmn comments, ns wen n, w the ,,,,, rh in pa.: to 97s s,=wwereirrorig gain from sinie of f timinnairmoIIrencompany summary ne reventseg and not caredng9 for the Inst Swa GE s anterest in the Geeman lamp manutachwer. Ostam trangettIrmg {p M n,,,(p Q,_N D ,,, [ h % h,,, N h y,gg,, yhjeh qMo lg pgmentert on pagm 6 throtsgh 21. A GmblI t.atin Ams eirano,ppeatismsexpcelenrodgensently 3 Ye=t ti 4na e $ i_.229_7 Syes.2 $1s.s44 5 Si5mo $ts aas e ,s nA or,ignitironi,t,m comps,ing i9 7, ws,h,973 ,,n,e,,,,,, g,n.,h,,, h,4,n.,,,,,nings canadian m anrt 1978 with 1977.1s incharted hato, c,ne,31 E tee tric had strong sales nort earnisys improve-ammenn meee t t gne 4 ewmno $1so 3 milkin and $' 1:55 6 mil Comumer PrndtK-ts nnr1 Servireirevemaet in f 979 mord9 Foreign Multi Inrtesetty s enenings for 1978.Inrhwl-neveriung. cet earnhage a*ws =,= Sets assoristed wi#is'**k t op-Ikm. emem* eiy as ts=ambm 't. 99 7a. and $ t7a* 7 mi*r=. ,e,* ahead rie 197s in an marn tiusin. s,es. nethnogh n, ing itie nnn,e,.,,,r nq nain..,ee, tip 7% on nusigh.or F e .no,s. nre.hnen s, t.d, n ine shr,ve af neramter 3t. ts79. w eina ncomhna mahai,ms..,*inray **ere.t in erviny and Stat s mmis-i amt s t'sa n-mna marm+ve'v. a' Daa'ad== ,,,,,, w,e,,,targen,,,,,me in ,,d the er t es t9 79 ,e,,nues GF keeraetherrs#y were $2. tot t memrm $t39 onulhnn end
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Supplementalinformation ren-year summary ini twerseasee esactereas _..._'n 9979 vo we. _ w a.am-= rar +=..- --*=== +me 1979 1978 1977 1976 1975 1974 1973 1972 1978 1979 t_ra e e +.as_ _ _. _sse 5se F hit ysare.=e dwnmary nf oparatwmg Salagolprewtucts entf earvicesteorenmars $72.460 8 519 E53 8 SI).5'R 6 195 697 3 314.105.1 $t3_918 2 $11.944 6 $t0.473 7 $9.5%E 7 SR R33 8 Karond esar** 70 65 tewd9mreae 70 A5 Cc9t of onn ts ared 15.990 7 13 915 1 121st7 7 t t 04R 3 10 ?O9 8 10.0't2 2 9.445 4 7.38 2 68089 R te3 5 taureignen= To si a Se91ng. genormi amt actr*niet'at va **pansa 37159 3.204 4 3.oto R 2.614 9 2 23R 2 2.2to 3 2.057 6 1.877 2 1.Ess 3 t.71R 4 g gg Dapreciation. dachtlest anct amewti7 anna 6241 576 4 522 1 4a62 470 5 415.0 379 9 343 7 2*95 3481 Opara'wg costs MN _3@jI MIO5 3 N9? NMi ~If.!jl! 35[jy 3 Nj j.75j f 3Mh N MT7__5_,__ _M S __ Operstkig margies 2.129 9 9.957 9 f.f;99 0 9.5/79 1.18i6 6 _ 1.170 7 0.069 7 RIE 6 772 0 SR3 8 r #,,ta, $ sos $.53 se, a $4y. Othar inenma $19 4 419 0 39n 3 274 3 174 2 2067 202 9 207 3 176 6 877 7 sare we vy.nrtar St% es w 54 % 4% kaarast arvf other finatwhf 6*qas _p59 6). J224 4) _j t99 5) (174 7) _ y e* ** J96 5) J 428) J20 8) Jto? t) J05 51 T*= 'e spiares.e s'ss en 57% en Earnings ba' rem incama taas arwt m*nrway intere<t 2.3a0 7 2.152 5 t,84 R 1.627 5 1.17* 9.180 9 1.129 8 963 9 R46 5 6r16 0 Fmam gem'ar 52% 45 'L1% 4% Prevtsinn try inenma tares (953 4) (893 9) 1773 f) TA El (459 81 (9%7 4) (456 5) (395 %) (312 *: 17372) '***"*"d"'"**'N"**"'*""'*""*"** i ~j5 81 !"J25 7) I 765 5 5 5{694 J5 0) {4 21 jt8 21 t t 9) (28 3) 5 i.J27 5) i 630 6 28 5) 128 95 $'I){d5 5 fI.239 i ~ " ' " * ' " ' " " Minrwety arwar==t 363 6 E85 5 S Sri 5 i'509 5, nnR} cr***m of==enarsamare. we ennamay ciwdnreas =dhu==ce=45 taat aarnings 6 20 $ 5 39 $ 4 79 $ 4 12 5 3 07 S 3 16 5 2 97 $ 2 57 $ 2 30 $ I E6
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== -r -y= Farnings par rommem-hva th) --u = t.Mvertarwis dartared par cerm'wm shwa (cf S 2 75 $ 2 50 $ 2 in 5 1 70 $ 1 60 t 60 S 1 50 $ t 40 $ t 3R S 1 10 p.ers 4 p. to a n pnet suhennart in e** Sanadhas and E *- Eemin.rs a9 e Parrardaca of saias s3% 83% 62% !9% 49% 51% 55% 55% 53% 41% e%we Cma===== Caeta=, Swr manens =do manna cen%9 e Earneef on ovacaga sha** awne.s arr y ?o2% 19 6 % 194% 1R 94 15 7% 17 R% IR 4% 175% 17 2% 13 4% a'ad ana=*='aauwa. is irv*whd *i ewa -prwt. ha=avar. a wt a catwas adt tie awaaaNa emhnut th.rqa bem hweetne stelettene Canseef Etactric Ceanpeny,Feletalet Cennertleist tML439 fMrtarwfg-Canaral th fric S E23 R S SE9 R S 478 9 S 332% $ 293 1 S 291 2 S 272 9 $ 254 8 $ 249 7 $ 215 4 e ,,,,,g,,,,, % % % %, 1hvwierwis_UtahInterna'irmaiIrw trt) ~ S 29 3 $ 33 1 S 23 9 $ 14 0 $ t2 8 11.4 5 R9 ,,,,,,,ip n.pwi sne GE W W e new 4 p.* Dei,- %vas rutstanrfing svararya fin thrweanrts) f a) 227.173 227.0#5 227.1%4 2?5.701 224 262 222 921 222 631 222.503 221.591 2t8 93R paavaa nainarne.w inerw asaturny arece t974 are4gshes GF %,a o.nar ecemmtv ava aga 540.000 552.Ono 553 rm sM.nno %R2.000 SEs.Uno 543.On0 542.000 $29.000 535 000 a s+.,.a t pa. p ar.+ww a.s an,t ewo,m.e,,...nawa
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55 %-45 5"b 43% 57% 47% 59 % 46 52 % 32 % 65 30 75% 55 73 58 % 66W46% 47% 3n% ti,.emnain en.e.or= w.iww.s anes er Heyeno.* *isewa newia w "tw a parretngs ratio vanga tt) 97 18 8 t? In 14-18 17-10 19 9 24-17 25-20 26 38 26 17 d==ared Current 39se4 5 9.3845 S 8.755 0 S 7. PES 2_ - - _ _ - - _ _$ 5.7%0 4 _ $ 5.334 4 1 4.5974 S40568 S33000_.$3.3911 Treaster R ad* S 6 M% 0 9 ureeed liaN# ties 6.871 8 6.t 15 2 5.417 0 4 E04 9 4.163 0 4.032 4 3.5R8 2 2.920 8 2.893 8 2.689 4 C*"*'as Flarbic Company e ww6ing capital i f.St2 7 $ 2.579 8 5'}.545 5'fl>50 i S 1.557 5 I~tj0I I 10V9 2 S 1.t36 0 { 565 f i 505 F
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er.0 3 S ffb S 946 8 9938 1.21'9 3 1.322 3 12395 1.402 9 1.166 2 1.191 2 1.016 2 E913 t eng term brwm.ings %nnriry antarcut in erp#y of er=wrdietverf armtata= 151 7 t%0 6 131 4 1 t9 0 194 6 86 4 62 4 53 4 50 9 45 0 th= FwgH4=Iwwiel pye vd Roenn Sh"'"*'"'***'***Ub*"" ';hva cenars' espity 7.362 3 6.586 7 5.94? 9 52529 4t 70 4.172 2 3.774 3 3.420 2 3.105 4 2.819 t 7ntalrapitallreveefad 5 9.3355 5.65i 5 i, ~k_tjo f 5~f.5_65_3 5_ 5.625 3 $~5.31} i 5'I.5}55 I' 5.t ti t ii.?53 } 54}}5 5 N R"'n'ee'e'sar-humanse2162 c-m--e Onw.. t 15 8% 125% 334% 13 7% 12 7% 12.3 % 10 2% raenarinn ovataga toine tapet.t invetted 17 h% 16 3 % IS R% '; hare rveners' arpity pee cam nnri shmea vaar enet tb) $ 32 3t $ 29 88 1 26 0% S 21 19 $ 20 49 3 1R 65 S 16 94 S 15 35 $ 13 96 $ 17 72 sseparty. piant erwt crymment a' iitenn= ' S i.262 3 S MES 3335 'S7N 4 5 ~599 2 $ 812iT36 S Sf10 R S T50 8 5 6R 3 ~ ~ + T enple,vaa*- evarpaa wrwithwyte 405.000 401.000 3Pinnn 3ac tm '#RO.OnD 409,0n0 392.000 3 73.Ontt 366.Ontt 3en nno k.hw+,As..,,w alFS*N.,o =.wsme A.wi.de v = d ~' ' ~ ~ ~ - ' - - ~ ~ ~ ' ~ ~ " ~ ~ " - - ' - ' ~ - ' ~~ s eat t** =ce,erse,nread as y.E EnM.=a.$.N.na.N,n,.c. t d t s..-.=,,-
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4 GEN ER AL @ ELECTRIC INVESTOR Annual Report Issue General Electnc Comcany Fairfield, Connecticut 06431 I GE Research and Development at new high: Seeking General Electric's commitment to research and de-new earnings growth by accelerating innovation and in-velopment was also signaled by continued strengthening creasing productivity. GE increased 1979 expenditures on of the more than 100 other laboratories associated with research and development to a record $1,440 million, up product operations. A large scale integrated circuit facility ) 13%,with the Company-funded portion amounting to 5640 began operation at Utica, N.Y., adding to the Company's million,23% above 1978. The remaining $800 million capacility for developing the advanced electronic micro-was performed under contract, primanly for U.S. govern-circuits needed for the 1980s. ment agencies. To accelerate technology transfer within the l During 1979, the Company announced plans for a Company, GE established a Corporate Technology Coun-550 million expansion olits corporate Research and De-cil bringing together the Company's technicalleaders, in-j velopment Center, with over half of this amount going into cluding a Sector Technologist from each Sector. building one of U.S. industry's most modern electronics Significant.A&D areas pictured below include work and computer science laboratories. The Center is also on solid state television cameras for use in automated 1 constructing a $7-million programmable process f acility inspection systems (left) and on a new family of superior for making custom integrated circuits in Syracuse, N.Y. engineering plastics-Arnoxt epoxy resins. LO .s Y y ~' R f;[.;"f J 3 f
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i ATTACHMENT F OPERATOR TRAINING AND CERTIFICATION PROGRAM MORRIS OPERATION INTRODUCTION In accordance with requirements of Part 72.92, Title 10, Code of Federal Regulations (10CFR72.92), this attachment contains a description of the program for the training and certification of Operations Technicians and Operations Supervisors at General Electric's Morris Operation, an independent spent fuel storage installation (ISFSI) near Morris, Illinois. The progran description includes identification of the training methods employed, the topics covered, the personnel includec', the means of implementation and the means of documentation. APPLICABILITY This program provides for the training and certification of all operation personnel who may be required to perform safety-related activities, including: o Operations Technicians o Operations Supervisors o Operations Supervisor relief personnel These personnel are referred to by use of the term, " operator" in the following text. PHYSICAL REQUIREMENTS As a prerequisite to acceptance in the training program and for recertification a candidate must successfully pass a medical examination designed to assure that the candidate is in generally good health and is otherwise physically qualified to safely perform assigned work. Minor correctable health deficiencies - - zuch as eyesight or hearing - - will not ge_r se prevent certification.
F-2 TRAIllItiG PROGRAM The training program uses classroom instruction with frequent quizzes to fortify 14arning and identify areas of weakness. Classroom activity is augmented by on-the-job training and proficiency testing to assess the operator's knowledge and practical skills. Subject Matter and Classroom Instruction Training subject matter includes: a. Radiation and industrial safety b. Equipment design, operating characteristics, instrumentation and control c. Management systems and procedures The objective of radiation and industrial safety training is to provide the trainee with the knowledge required to carry out job assignments safely, and to recognize potential safety hazards. Radiation safety training includes the theory of radioactive emissions and the control of radiation exposure, including the use of radiation detection and monitoring equipment, step-off procedures, pro-tective clothing, and respiratory protection needs and equipment. Training in radiation safety emphasizes principles and practices that contribute to re-ducing exposures to as low as reasonably achievable (ALARA). Industrial safety training includes safety practices and Emergency Brigade activities and pro-cedures. The application of safety principles to on-the-job conditions and situations is emphasized. Training in equipment design, operating characteristics, instrumentation and control includes equipment and systems encountered in cask and fuel handling, fuel storage, and auxiliary systems such as basin water cleanup and cooling. Special emphasis is placed on handling and processing low-activity wastes to tssure safety of operations and to minimize waste accumulation. The functions and use of controls and instrumentation associated with the various systems and equipment are carefully integrated in training, with emphasis on normal and abnormal indications. Particular attention is given to activities important to safety; such activities may be conducted only by certified personnel, or by non-certified personnel only when under the observation of duly certified personnel.
1 F-3 l e Training in management systems and procedures is designed to provide an understanding of the administrative controls, approval requirements, comuni- [ cation lbies, instructions and practices to be used by operators in carrying out their assigned duties. Topics in this area of training include use of I Standard Operating Procedures; implenentation of Ccmpliance Tests (Technical l Specifications); operator duties related to security, safeguards, and quality assurance; and discussion'of documents such as the Safety Manual, emergency plans, j and others described in the CSAR Chapter 9 and the Technical Specifications. l Classroom instruction relies heavily on audio-visual instructional equipment, j including video tapes of actual operations. Radiation survey and monitoring [ instruments and other equipment are used in the classrcom as instructional aids. l On-The-Job Training i ) i On-the-job training (0JT) will normally i.nclude review of operating conditions j and procedures for a given activity, and observation of the activity as con-l ducted by certified personnel. As the operator progresses, hands-on experience l will be gained under the direct visual supervision of certified personnel. Where hands-on operation is not possible, " walk-through" discussions of systems l and equipment studied in the classroom are conducted. On-the-job tra'ining l includes all aspects of normal operation, as well as simulated off-normal situa-l tions. { Proficiency Testing i i Proficiency testing is used to verify that the operator is capable of safe and proper performance in operating plant equipment and systems. Proficiency j testing includes the following elements: l i a. Written examination b. Oral (walk-through) examination c. Provisions for retesting after additional training d. Job performance statement 1 Comprehensive written examinations are taken by operators, followed by walk-through examinations where applicable. The written examination covers the
F-4 . training subjects to a degree of detail sufficient to provide reasonable assurance of competent operation. Where applicable, walk-through examination includes not only detailed questions, but actual demonstration of operation of equipment and systems when practical. Both normal and off-normal operation knowledge is tested. Passing grades must be attained on all written examinations for certification eligibility. When written testing or the walk-through examination indicates the need for further training, retraining in the indicated subject matter is conducted on an intensive basis. Retesting is then perfonned and must be passed prior t,o certification. The job performance statement tabv7s' job activities performed by an operator, and indicates specific activity or 'll areas where retraining is indicated. Facility Changes In the course of operation of an Independent Spent Fuel Storage Installation, equipment and operational changes may occur. In order to maintain knowledgeable operators, such changes will be introduced into training materials. The train-i. ing materials will be reviewed and revised when required to reflect such changes as part of the biennial training and recertification process. Also, when such changes in equipment operation or other operational aspects are implemented, the Standard Operating Procedures (50P's) are updated and certified personnel are alerted to such S0P changes. CERTIFICATION Af ter successful completion of training and proficiency testing, Operator Certi-fication is granted. Normally, a new employee will undergo the Operator Training and Certification Program and be certified within a year. After initial certi-j fication, personnel must be retrained, retested and recertified every two years. Completion of the Operate ' raining and Certification Program means that a certified operator is tully authorized to carry out assigned responsibilities. Management personnel who supervise the certified operators also must be certified.
9 F-5 PROGRAM RESPONSIBILITIES The Manager, Plant Operations is delegated by the Manager, Morris Operation, authority for administration, implementation, and maintenance of the Operator I Training and Certification Program. The Manager, Morris Operation may designate other individuals to assume a role in the implementation of the Program, particularly in the area of testing and determination of an individual's pre-paredness for certification. The classroom and on-the-job training *is adminstered by supervisors, engineers or training staff memoers who are referred to as " training officers". Such training officers are certified personnel who have sufficient experience, education, and training to carry out these duties. Preparation for the Training Officers may include their training by other instructors or by non-certified ~ plant personnel in their areas of expertise. The Manager, Morris Operation will designate the certifying officer (s). The qualifications of the certifying officer include a thorough knowledge of the facility, especially the equipment operation facets. A technical degree or equivalent technical experience is a requirement. Five years of industrial experience with three years in the nuclear field is considered minimal for a certifying officer. PROGRAM DOCUMENTATION Records are to be maintained for certified (or recertified) operators for a minimum of five years. Such records include documentation on training subjects, information on physical requirements, job performance statements, copies of l written examinations, information pertaining to walk-through exams, retesting l particulars, e:id a listing of certified (or recertified) operators. l l l \\ J i f i
AT'"ACEMENT G PRCPOSD RE7ISION C3, NEOC-21326C CCNSCLOA E D SAFETT AflAL?S:3 REPCRT FOR MORRIS CPERAT:CN The material in this attach =ent censists cf preposed revisiens and additions te BTEDO-21326 =ade in ecmpliance with requirements cf 10 CFR 72. Revised and new material is indicated by double-bar vertical lines in the right argins. Scme incidental editerial chan6es and new =aterial is included when chey accurred en the same page as Part 72 revisiens, er were c herwise relatec. These :nanges are indicated by a single bar and the letters E '
- %. rial) Or N (New Material).
See the attached letter for other cc==ents applicable te this material. 5 4 NEDO-213 6C3 January 1981 In December 1975, General Electric received a license amendment to increase the fuel storage capacity of the facility fr:m about *C0 TeU3 :: 75c :ec by the insta'.la:1:n of fuel storage system of a new design and through appropriate changes in fuel handling and suppcrt systems. This project, designated by OE as Mar-is Operati:n-Project I, ccnverted the fer=er high level waste s Orage basin to a fuel storage basin. 2e capacity expansien project was co=pleted in 1975 1.1.1 Corcorate Entities, Business, and Exterience The facilities described in this repcrt are cwned and operated by General Elec-tric Company, a ccepcraticn under the laws of the State of New ?crk, with its principal place of business at Schenectady, New ?crk. Se facility is operated through General Electric's Nuclear Fuel and Services Division (NF5SD), with head-quarters at San Jcse, Calif:enia and operati:na at Morris, :llinois. General Electric is a breadly diversified corporation involved in research, design, =anuf ac turin g, and =arketing products and services in seversi fields including industrial products, technical syste=s and =aterials, censu=er products, and power syste=s. Se latter activity includes nuclear syste=s, equip =en,.^2el and ' services. General Electric's experience in nuclear activities includes researen and develop-sent of prototype reacters fer nuclear submarines, opera:icn of the g0vernment's '4anford facilities for nere than 17 years and the development, design, manufacture, and erectica of 41 boiling water reac:ces currently operating at electric pcwer statiens in. the United States and throughout the world. Se staff of the Company'1 Nuclear Energy Group includes literally thousands of scientists, engineers, and technicians, representing ene of the largest ;cols of nuclear knowledge and experi-ence in the world. 1.1.2 Plant Location l Morris Operatica factities are located on the certhern end of a rectangular i tract of about 315 acres owned by General Electric Company, in Gecselake Township, l Grt: dy County, Illinois, near the confluence of the Kankakee and Oes Plaines I rivers (Figure 1-1)." 1-2
=. NEDO-21326C3 January 1981 The tract (Figure 1-2) is about 15 air siles southuest of Joliet and about 50 miles southwest of the Chicago, Illinois - Gary, 2 diana area. Mer-is, :llincis, ^ the county seat of Grundy Ccunty, is about 7 =1les to the west of the tract. The Illinois Waterway and Kankakee River are separated frem the tract to the north and east by lands owned by Oc==onwealta Edison Co., the site of the Dresden Nuclear Power tation (DNPS) and related facilities, and a privately owned plot of about 50 acres.
- he develeping Geoselake ?rsirie State Park is to the west and a refractory mining operation borders the tract to the south.
- he terms used in the text of this document to describo the Genersl Electric property are as follows*
Tract / Controlled Area " - all land holdings of General Electr10 as defined in Section 3 Site the developed area of the General Electric tract, including the protected area, sanitary lagoons, and evaperstien pend. 4 1 i l l l 1 1 =e# 1-2a 4-., ,-e ww .n em--y,, ,y.y.,_.,--w.-n-.r,--,-+ y,, - - - -., www--.y-
3EDO-22326C7 January 1981 1.1 3 Existing Facilities _ ~ 2e existing facilities occupy about 52 acres at the north edge of the tract (Figure 1-3). The principal plant structures, including the ventilatien stack, are within a 15-acre fenced protected area, while the sanitary waste treat =ent facilities and the industrial waste evaporation ;cnd are located i==ediately south of the protected area. The sanitary waste facilities are fenced, also, { but not as part of the protected area. The evaporation pond is not fenced. 1.1.4 Fuel Tree and Execsure "he design basis Pael to be stored is CO2 fuel having had an initial enrich =ent of 5f, U-235 or less, with stainless steel, ::ircenium or Zircaloy cladding, and in a " bundle of reds" 'geo=etry. The design basis fuel may have teen ir: adiated at specific pcwer levels of up to 40 kW/kgU, with exposure to 32,000 M'id/TeU (reactor discharge batch average), and =ust be ecoled for at least 1 year after reactor shutdown and price to receipt at Merris Cperation. 1.1.4.1 Fuel in Sterage
- r:adiated ^ael frem ?4R's and ?dR's has been received and stored at the Merris Cperatien facilities since 1972.3 ~hese activities have re. affirmed experience elsewhere that fael can be handled and stored safely with no impact en the envi-renment.
Bere has been no significant fa 51 leakage (as determined by =easure=ent of basin water activity), indicating that :he.^ael is a stable, inert caterial while in the storsge basin environment. Effective centrol of water quality, M radicactive material concentestion in the water, cask contamination, and airborne radicactive =aterial has beca demonstrated. 1.2 GENERE PLANT OESCRI?""CN The folicwing descriptices are of these aspects of the Morais Cperation facili-tit
- c.st are related to irradiated fuel storage or shipment.
Facilities origi-nal'.y ntended for reprocessing are sectioned cnly as related to Pael storage operations. 1-5 X
NEDO-21326 C3 January 1981 1.2.1.5 Environs Summary s The dis:ances fres the plant stack Oc the tract (controlled area) Ocundaries are 2265 ft to the east, 6512 f t to the scuch and 3100 f t :o the west. The tract boundary to the certh is about 950 ft fr = the stack; hewever, the ONPS site provides an effective exclusion distanceI of about 5950 ft. Studies of populatien and land usage in surrounding areas were =ade and reported in the course of DNPS development, as well as during the MF3P program and Morris Operation Project I. Facters of specific interest are su==arined below; a. Industrial: On the DNPS site there are three nuclear power reactors situated about 0.7 nile northeast of the Morris Opers:10n stack loca-ti n. A large f0ssil-fired pcwer plant is located about 'a siles wes:- southwest Of the stack. A che=4:21 plant is located about 1.5 miles frem the stack to the northwest. Adjacent Oc the scuch boundary of the Morris Operation tract there are clay sining and clay products anu-facturing activities about 1.4 miles frem the stack, b. Residential: The residences nearest to the tract are on about 50 acres directly east of the facilities, between General Electric property and the Kankakee River. The tract owner, wno naintains his permanent resi-dence there (about 0.5 mile frem the stack), has leased individual river front sites on wnich approximately 30 cottages have been built, largely for recreational purposes. There are other residences acress the Kankakee River, the nearest about 0.7 sile frem the stack.
- he total population within a 5-aile esdir ts estimated to be about 5000 including sum =er risitors, increasing to about 3830 by the year 2000.
A population of about 32,000 resides within a 10-m11e radius of the plant, and should increase to about 68,000 by the year 2000. 1 ? pulation in the 5-to 20-mile radius :ene, vnich includes the cities of Aurers and Joliet, is about 252,900. This population should increase to about 032,500 by the year 2000. i ~d 1-9
NEDO-21326C3 January 1981 In general, population projections for the State of Illinois have been '^ icwersi in' recent years. Current projecticns indicate a relatively slew,rewth rate as cenpared :o the ever-all U.S.. ate. c. Recreational: "n additien to fishing, hunting, and beating activi:1es near the ccnfluence cf the Iankakee and Des ?laines Rivers 1 :o 2 niles east of the plant, the Goose !.ake Prait. ie State Park has been established adjacent to the Morris Operatienal tract. This natural prairie preserve of about 1800 acres is west of the tract, with the nearest point being about 0.6 nile fren the stack. 1.2.1.6 Tract Cwnership
- he tract is wholly edned by General Electric Conpany.
Since ;urchase of the original tract, which then total'.ed 1380 acres, apprev -$tely 70 acres 1002:ed d at One southwest cerner and approxinately 50 acres in a 400-ft-wide strip alerg the scuth edge cf the tract have been sold to A. P. Green Refractory Oc=pany, Illinois Products Oivisien, to be used in ccnnecticn with -heir clay mining and clay products manuf acturing activities. A parcel to ths certh and east was sold to Cc=nenwealth Idisen *.,cncany for censtructica of canals to a cooling lake fer the CN?S reae:ces. 1.2,2 Facility Descripticas
- he largest building en the site (the =ain building) was originally censtrue:ed to hcuse the fuel reprocessing chenical facilities, as well as waste nanage-ment, fuel handling, and *uel stcrage facilities (Tigure 1-1).
1.2.2.1 Main 3"4 W7 'he =ain building is a nassive structure of reinterced concrete, about 204 ft by 78 f t in plan, and about 38 f t high above ground. Se western end of the build-ing hcuses most of the fuel storage facilities. 21s portica of the building is of steel frase and insulated metal siding ccnstructien, and is attached to che cenerete =ain building. i 1-10
NEDO-21326C3 January 1981 1.3.7 Emergency Proe_siens
- he structures and syste=s at Merris were designed to more rigorous standards than would be required for spent fuel storage. Emergency plans are in ef fect, and assistance agreements exist with appropriate local agencies. Structures provide access for law enforcement, medical, fire, or other emergency services.
O e O F n ) e i f I 1. I i i 1 44 l l
NEDO-21326C3 January 1981 1.4 REFERENCF.S 1. License and docket int:rmacien and a list of applicable documents are :en-tained in Appendix A.1 and A.2. 2. The Morris Operatica does cet enccmpass 3'dRTO activities, althougn both are General Electric operations. 3. Storage capacity expressed in ter=s of metric tons of uranium (Tet) as contained in L'4R fuel rods. A metric ton equals 1,000,000 gra=s, er One megagra= (Mg). Abbreviation for metric tenne (Te) used as reccc:= ended by A=erican Institute of Physics, A=erican Chemical Society, and others.
- hroughout this report, TeU = MIU.
4
- he 3'4RTC is also on this tract.
Hereaf ter 3'4RTO is ref erred to only vnen germane to the purpose of this report. 3a. " Controlled area" as defined in 10 CFR 72.3 (h). 5. K. J. Eger, Operating Experience - Irradiated Fuel Storage - Morris Operation, Morris, Illinois, General Electric 00mpany, May 1973 (BC O-209698). 6. See Chapter 8. 7. See 10 0FR 100 3 (a) definition. 1 3. Previcualy, the floor could be drained to the site runoff drain systen or the cladd tag vault.
- he runoff drain has been disconnected and capped.
1 9. Also, see Figures 1-12 and 1-13. 3 var 10us documents, the cask un10 acing i basin has :een called fuel unloading pit, cask unicading pit, etc. W 1 45/1 36
1 NEDC-21326C3 January 1981 3.2.2.4 Boundaries for Establishing Effluent Release Limits The centrolled area boundary (the tract beundary shown in Figure 1-2) is the boundary for establishing dose equivalents as defined in 10 CFR 72.57 and 72.68. No credible acts of nature, san-induced events or accidents have been identified that would result in.a biologically significant reler.se of radioactive aterial or a direct radiatien dose in excess of the 11=its of 10 CFR 72.68 outside of the controlled area boundary. Therefore, the Energency Planning Zone (IPZ) for Morris Operation coincides with the controlled area boundary. 3.2.3 Population. Distribution and Trends The data base for the foll wing sections is fcunded on informatica develop,ed by agencies of the States of Illinois and :ndiana, as well as inf treation deve10 ped by General Electric and Cc==onwealth Edison. ta,1b,1c 3.2.3.1 Population Between 0 and 5 Miles (Figures 3 3 througn 3-5A) ~ The population in the i=nediate vicinity of the Merris Operation is very low. Within a radius of 5 miles the population is about 5,000, including 1,500 in the village of Channahen, about 4 miles to the northeast. Included in this accounting are several residences at the Dresden Lock and Dam. The 1970 pop-ulation figures'within a 5-cile radius are based on a 1973 actual house count assuming three persens per house and are not intended to represent 1970 U.S. census data. The 1980 projections for the O-to 5-mile radius are based on an assuned 5% annual growth in all areas except those in which the tract is located.I ~ The population within 5 niles of the sito is projected to increase to 3830 by the year 2000. Within 10 niles, the existing population is about 32,500 and is projected to reacn 68,000 by the year 2000.2a 3.2.3.2 Population Within 50 Miles (Figures 3 4 through 3-7A) The total populatien vithin the 50-cile radius was f0und to be about 6,251,500 in 1970 and is projected to reach 7,500,500 by 20c0 vith about 915 of the total beyond the 30-mile radius.3 j 3-7
1 l NED0-21326C3 January 1981 The 1978 population projections prepared by the State of Illinois and the State- ^ of Indiana f:r count *.es within a 50-cile adius surrounding tha "$"d*y anti:1-pata relatively niner pcpulation growth between 1978 and the year 2005.33 9 Studies by Cc==enwealth Edisen's Edustrial C6velopment Department indicate that since 1946, 32% of the new incustries 1ccati: 4 within the Coc=enwealth system are located within 25 miles of downtewn Chicago, n 1965, 80% of the new industries also located according to this pattern. Curn nt indicatiens l are that this industrial grewth pattern is 310 wing but continuing within the l 25-m11e belt. Sus, the gr:wth adjacent to the GE-CNPS sites (which are cut-side of the 25-mile belt) should continue but at relat 17ely icw rates. Se Joliet and Aurces areas are the closest areas that are likely to see signifi-l, cant population.ncreases. i r 3233 h sient Pepulatica ? There are small seascnal variati:ns in populati:n in the farm lands of the area because of harvest =anpower requirements. Unlike scme farm areas, harvest activities are highly mechani::ed and relatively few additicnal workers are needed. 1 i A1:0s all manufacturing and other industrial activity is nonseasonal and i* draws upon a populat10n base that resides in the same general area. For r example, with the largest part of Chicago's industrial and residential areas j within the 50-mile esdius, the daily movements of people within Chicago and envircus result in a relatively insignificant statistical change from the i viewpoint of ccasiderstiens applicable to the Morris Operatica site. [ As discussed elsewhere in this chapter, recreati:nal uses of lands and water f L in the area result in s=all see.senal chsnges in population in cottages, etc. I These changes have been esti. sated by observati:n and incorpersted in Figures 3 a and 3-5. s 3.2.:4 Users of Nearby Land and Waters i t i The i= mediate neighbors of Morris Cperation.(Figun 3-3) are the DNPS site i 1 en the north, the A. P. Green Refractory Company, Illinois Products civision, l i I 3-12 l
s NEDO-21326C3 January 198L on the south and the Goose Lake Prairie State Park to the west. To the east is the Dresden cooling lake and a private'y, Owned property of about 50 acres, ~~' divided into accut 30 cottage sites. Con =enweal h Edison's Collins Stati:n (a fossil-f;rud plar.0) is to the west-southwest of the Merris si;;e. ?.e present land use patterns in the area sees 'ikely to centinue for some t'.me to ecce. The Northeastern Illinois Planning Commission does not expect a change in the pattern in the southwestern ccenar of adjacent '4111 County, eithers (~he county line is approximately 1-1/2 siles east of the GE tract.) 3 2.4.1 Industrial i
- n additica to the A. P. Green Refracecry Cc=pany operatiens south Of the ract and the Cc cnweal:h Edison holdings to che cast, ncetn, and ncrthsest,
another industrial area,is located along Hignwa'/ :-55. ~his his:s.y .~r.3 north and south, about 4-1/2 siles directly east of the Oract (Figure 1-1). Two silcs east of I-55 is the inactive v*ollet Ar:y A==unition Plant. A large Mobil Oil petroleum refinery' is located wnere I-55 crosses the Des l Plaines River. Industrial sites are alsc 10cate'd en the north bank of the i !111nois River. l i i 3 2.4.2 Residential Use and Population Centers Residential occupancy in the immediate vicinity of Merris Cpera:ica is icw. There is a cluster of about 30 cottages on the west shon of the Kankakee River, i about 0 5 sile from the Morais Operation stack. These are located between I t Dresden Read and the Kankakee River on a tract of about 50 acns adjacent to the 7/ and DNPS sites. Any residential dev+1cpment in the i==ediate vicinity or Mccris Operatien would be limited to this tract which is new nearing I r satura:icn. t Then is also a similar grcup of cottages en the east bank of the Kankakee r River at a distance greater than 1211e from the, Morris Operatica stack. l Scme of the homes in this area are permanent residences, althou6h neat have i been developed fer part-time recreational purpcses. Surveys by Con =cnwealth [ L I Ediaen indicate that within 2-1/2 miles of the DNPS site than are a total 1 l of 129 persanent hemes and 191 par:-time recreational cottages along the l t i L 3-13 i
51CXb21326C3 January 1981 Kankakee River. Other residences in the area include seversi at the Dresden ^ Das about' 1.2 niles to the north. There are no =ajer residential centers developing south of the Kankakee and Illinois ?.tvers in the vicinity of the General Electric tract. ~ Cities and *.cvns having ;cpulaticcs greater than 1,0C0 10cated within 30 siles of the Morris Operatica are listed in Table 3-1. ?cpulation centers of less than 1,000 within about 5 miles of the tract are as fo11cws:
- ' Village - Mincoka, 5 2 miles N 768 people as of 1970.
Population is compact. Subdivisien - Dresden Acres, 3 5 niles NW Appr9ximacely 200 ;eople as of 1975. Populatien is ce= pact. e-Shady Caks Trailer Park - 5.1 miles NNE Approx 1 tately 400 people (150 trailers) as of 1975 Population is compact. Goose Lake Suedivisien - 3 to 5 miles SW and SSW Approxi=ately 1100 people as of 1975. Population is difnise. Teather Woods Subdivision - 1 mile E and ESE Approximately 550 people as of 1975. ?cpulation is acepact. Other areas and sites involving intermittent and tempcrary congregations of persons within 5 miles of the Morris Operation are as f 311cws (data as of 1974-1975): 4 a. Schools - Enrollnent i Mincoka High School 587 MincoKa Junior Hia;h School IlI Mhooka Grsde School Channahen School 772 I111nc!.1 !cuth Centers ~ 30 3-14
NEDO-21326C3 January 1981 No access is allcwed by Ccemonwealth Edisen to the Dresden ecoling lakes f:r ^ recreational uses. The Illineis 'daterway, ene of the majer inland waterways, is adjacent to the DNPS site. An agreement between GE and Occmonwealth Edison provides for access to the Illinois *4aterway througn the DNPS site so that facilities for beat docking and access reads to the waterway could be developed at some future time if required. There are two small " finger lakes" about 2-1/2 miles south of the GE tract where homes have been built, while other lakes on which houses are being built are located r.bcut,3-1/2 miles southwest. Some of these houses are solely for recreatienal purposes. 3.3 NEAR3Y CTDUSTR*.AL, TRANS?CR'"17:CN AND MI' ~~ ART FAC'L'T'ZS Ncne of.he industrial, military, er transpcetation activities in the area present a credible hazard to the fuel storage facility ner to the transport of irradiated nuclear fuel. Tuel in ster 2ge is located well below ground level in a steel-linec, reinfereed concrete water basin, and held in stainless steel baskets latched in a supporting grid., Explosions or fires at " nearby" industrial facilities would be much too far away to have any influence en fuel in storage. Even the explosion of a passing tank truck would not affect the safety of s cred fuel. Likewise, the structural characteristics of fuel. casks and tne nature of nearby activities result in minimum hazard to transportation of spent fuel.2a 3 3.1 Nyirby Nuclear Facilities The locati n and identification of nuclear facilities within 50 miles of the Morris Operac1on site are shown in Table 3-2.
- he closest facilities are the DNPS Unita 1, ? and 3, located about 0.7 nile north of the Mer-is Cperation stack.
"he ecmbined radiological 1.mpacts frem Merris Operation and the DNPS ~ are within the requirements of 10 CFR 72.57 as indicated by cal 0ulations and environmental monitoring results. The calculated cose :cemitments frem Merris Operation are a small fraction of the dose ecmmitments frem DNPS, even consider-s ing the design basis accidents evaluated in Chapter 3. s 3-18
NEDO-21326C3 January 1981 332 Industrial and Military ~he GE tract is near seversi industrial sites in an industrial area along,he Illinois River (Figures 1-1 tnd 1-2). Most of the development is ncrth of the Illinois River at a distance of over 1 nile from the Merris Cperation. '"he rapid development of the last few years is slowing as nest of the suitable j industrial sites are already occupied and the Goose Lake Prairie State Park now occupies most of the remaining land south of the river. Table 3-2 Wr"HU 50 MILF.S OF MORRIS OPEdATICN NUCLElR REAC"'ORSA Capacity Airlins Miles to T7pe (MWe) Cn Line Latitude Longitude Mcrrin Operation Na=e T4R 200 1960 41 022' 380 14' 1 Oresden 1 0 41 22' 380 14' 1 Cresden 2 SWR 309 1970 SWR 309 1971 41 0 2' 38c ar 1
- reseen 3 2
z 3WR 1,078-1978 41021' 380 6' 20 LaSalle 1 b 3 41 21' 38036' 20 LaSalle Eb 0 SWR 1,078 1980 0 6' 380 13' 10 3rsidwood 1b BWR 1,100 1981 41 1 3WR 1,100 1982 410 16' 38C 13' 10 3raidwcod 2'c In addition to DNPS i= mediately to the north and the A. ?. Green Refractory l Company's clay products plant i= mediately to the south, other industry in a 6-mile radius of the Morris Cperation is l'.sted in Table 3-3 t 333 Transeortation k l One of the principal factors in t."e original selection of the Morris site was i the ready availability of excellent rail and highway access to all parts of the United States and vatar transportatien : hat Oculd be developed if required i in the future. 1 aAll plants owied by Commenwealth Idison. s
- Under construction.
i 3-19 l i
i N 2 0-21326c3! Jamnary 1981 Highway access to the tract is via a paved Ocun:7 read, kncwn as Oresden Read, I extending scu h frc= the ON?S site parallel to the Merris tract and intersect-ing Pine Bluff Road (Figure 1-2). ?ine Bluff Road (named Lorenzo Read in Will County) runs in an east-west direction approxi=ately 1 nile souta of the OE tract beundary and provides access to Interstate 55 approxi=ately 4 miles eas ) of the site, and Illinois 47 to the west. Interstate 55/U.S. 66 is a limited-l access highway between Chicago and St. Louis. Another 144 ted-access highway, Interstate 80, which traverses the State from east to west, is approx 1:ately F 5 miles aceth of the GE lands and is accessible either from Interstate 55 or j fr:m a State highway, Illinois 47, at a point approxi=ately 2 =1les north. s Table 3-3 INDUSTRIE, *RANS?CRTACCN, AND F"3T13! ACC7 CESa (6-cile radius) i r i installatica Function ?rord'ity l Reicheid Che=1 cal Plant C:emical plant 1.5 si NW haa: Al=ninum =111 products 3 si NW l Northern Illinois Gas Co. Natural gas =fg 3 si NW Rexene Polymers Co. Chemical plant 4 mi INE Mobil 011 Co. Oil refinery 4 mi ENE Collins ?cwer Station Electricity generation 4 si WSW ( fossil-fired) ARMAK Co. Mfg of fatty acid 4 si WNW derivatives l Northern Petro Chemical Mfg of polyethylene and 4 si NW Co. ethylene glycol Joliet Arsenal Munitiens plant (inactive) 5 si INE Oe=ert and Ocugherty Filling acresci cans 5 s1 3 ? l M aSee Table 3-2 for nearby nuclear pcwer stations. 1 3-20 i
NEDO-21326C3 .fanuary 1981 The seismic risk =ap (yigure 3-12) of the centermineus United States was prepared by a group of researen geophysicists headed by Dr. S. F. Algermissen ^ of the United States Ccast and Geodetic Survey and issued in January 1969. The site area lies well within :ene 1 where since earthquake damage can be expected. According to this ap, :ene 1 correspends to intensities V and 7! en the modified Mercalli scale. Modified Mercalli intensity 7I seems to be the Featest intensity experienced historically in the site area. This intensity was the result of the 1912 earthquake which was centered approximately 15 miles feca the site, and may also have been the result of the 1811-1812 New Madrid, Missourt, earthquakes. Intensity VI, with its correspending acceleration (according to New= ann's curve) of U.C1g =ay be reasonably expected to occur again within the life-tire of the facility. 3.7.5 Earthcuake Desi,,;n Basis The desig earthquake basis for the basin was.a hori: ental pound :otion Of 0.1g. The basin structure and fuel stcrage system are designed to withstand the desip basis earthquake withcut damage to structures er ccmponents essen-tial to the integrity of secred fuel or fuel being =oved in the normal process of stering or shipping fuel. The design earthquake is defined as a seismic event that has a reasonable probability of cccurrence during the life of the facility, based on studies of seismi: histcry and geol 0gy. A maxi =um earth-quake with ground accelerations of 0.2g is also considered in the seismic analyses. The design bases are discussed in Chapter 4 3.8 TRANSPORTATICH OF Ilt1DI.1TED TUEL Irradiated fuel is received by truck or rail at Merris Cperation in casks ter-tified to cmply '#.th applicable U.S. Nuclear Regulatcry Cc= mission regulati:ns.w< ' T7pical shipping casks are discussed in Section 1 3 As c? the end of 1980, 510 shipments of fuel had been ecmpleted, =oving about 316 tonnes - heavy metal in 1220 fuel bundles. Shipments to Mccris Operation have been ocmpleted without highway or rail accidents. Rail shipments were al; fra CNPS. 3-54
NElo-21326C3 Janucry 1981 The environmental impact of these transportation operations has been negligible, ~' thus supporting the conclusions of varicus studies and analyses.18'09 Projected transportation activity required to s cre a full ec=plement of fuel ~ - about 700 TeU, total, er about 1300 additional bundles assu=ing a 50: 40 ratic between ?'#R and Bh'd fuel - is shown be10w. This estimate is based On the assu=p-tion that all shipments are by truck; ship =ents by rail would result in even lower environmental impacts. / a. 1000 shipments (varies with PWR/3hd six) b. 1500-mile trip (one way) c. Elapsed time per trip - about 45 hours d. Turnaround per cask - 18 to 20 hours e. Maxi =t= chi;=ents per year - 300 to 400 The nonradiol gical and radiological impacts of transportation are analyzed in the literature. 0 Environ = ental impact assess =ents of the Mor:is Operation facility by the Nuclear Regulatory Cc==ission staff have also f:und no signift: ant environ = ental impact frem spent fuel transport.41 ' 22 3.9
SUMMARY
OF CONDITIONS AFFECTING FAC~J.27! 0? ERAT 2iG REGUIREMENTS P Irradiated fuel stcrage operations have been underway at.the Merris Operation since January 1972 when the first shi;=ent of irradiated fuel was received i under Materials License No. SNM-1265, Docket 70-1308, issued December 1971, i Threughout this period of Operating experience and during the ca-going environmental studies and senitoring programs, no Oendition has been found to detract frem the desirability of this site as a fuel storage location. i s 0 i 3-56
NEDo-21326C3 January 1981 I 391 significant'yaetors The following facters were significant in selecting the design bases for the existing Morris Cperation facility. l-3 9 1.1 Meteorology The climate at the site offers no severe extremes except tornadoes. Analysis of tornado activity, including offic1al and unofficial records, indicates a frequency close to the average for all states east of the Rocky Mountains. The topography of the site introduces little perturbation in diffusion calcu-lations; only the 630-ft elevation of the Dresden Heights, about 1-1/2 miles north of the Merris Operation stack is of concern in selecting stack design bases. Local fog conditions are involved in dispersion censiderations. Diffusion climatology and characteristics have been firmly established and confirmed by the meteorological measurement program. 3 9 1.2 sydrology Surface hydrolc6y of the site offers no characteristics significant to the selection of design bases (except for the usual consideration of natural drainage pathways, ste.). Subsurface hydrology shows excellent separation l i between the upper strata and the deeper aquifers that provide the water supply - al=est exclusively - fer municipal and industrial use. The intrusion of groundwater is of concern during construction, based on experience during MFRP work. These flows ir.dicate a complex near-surface j groundwater system that becomes significant because of localized fracturing j induced during construction. 3913 Geology and seismology l The site is located in a stable area which has experienced historically low seismic activity. The existing construction is founded on bedrock of Crdovician (Paleozoic) age. Design of the facility and its fuel storage equipment fer l horizontal ground motion of 0.10g is considered conservative. j l 3-57 l i k
1 621326C3 Sanuary 1981 3 10 RE m lENCES 1. See Appendix A.1 f:r decu=ent list. 1a. State of Illinois, Sureau of the Budget, Illinois Population Projections (Revised 1977), Springfield, Septa =ber 1977 1b. State of Indiana, State Scard of Health, Indiana County Population Projec-tiens, Indianapolis, 1978. 1c. Northeastern Illinois Planning Co=missien, Regional Data Repert, Chicago, June 1978. 2. me 5*. grewth in the 0-5 =11e area was developed f-em the assu=p-ion that farmland will.:ot experience growth (urbanination) except in a few sel:!cted areas. This growth was estimated and the overall area growth integrated. Mest people working in local industries live in the Western Joliet and Merris areas; there has been little growth in smaller cecmunities. 2a. Beycnd the 5-m11e area, population data totals on charts have been rounded off to the nearest 100, 3 ne USNRC staff reported an adjusted esti=ated 1980 population for the area within the 50-mile radius of about 9,169,337 (Environ = ental 1 pact Appraisal, Docket 70-1308, NR-FM-C02). 3a. During research for these data, differences were noted between (for exa=ple) the Northeastern Illinois Planning Commisdien data and Federal census ficares. In general, hcwever, the data appear mutually supportive, particularly at the county levels. 4 Within 5 niles of the site the total school populatten is 300, but at slightly nere than 5 miles it increases to about 2,140; the larger cu=ber is shown. 4a. See Reference 39: WASH-1238, Section II, E. 3-58
NEDO-21326C3 January 1981 5. Correctienal institutien (Juvenile) at channahen, 3 siles,WNW. 6. Climatography of the United States, No. 50-11, rev12ed and reprinted June 1969 7 H. E. Landsberg, "Clisates of North A erica, 'dorld Survey of C11sstology, Vol.11, edited by 3rysen, et al., Elsevier Scientific Publication Co. (1974). S. S. S. 71 sher, Cli=atic Atlas of the United States, Harvard University Press, Cambridge (1966). 9 U.S. Department of Cc:::=erce, Cli=atograpby of the United States No. 36-9, { " Decennial Census of United States C7 4-=:e," fer I111coi5, Washington, D.C. (1963). l t
- 10. " Final Environmental Statement related to operatien of the Midwest Fuel Recovery Plant by the General Electric Co., 'oc. 50-268, US AEC (December 1972).
i
- 11. Fluce Cooling Products Cc=pany, " Evaluated '4eather Data fer Cooling Equipment Design," Addendum No.
1, Winter and Su==er Data, Santa ?.csa, CA (1964). i
- 12. D. W. Phillips, et al., "~he Climate of the Great Lakes Basin, Climatological Studies Numcer 20, Environment Canada, Terento ( 1972).
i f
- 13. J. L. 7egel, et al., " Fog Effects ?.esulting from ?cuer Plant Ccoling Lakes,"
i Journal of Applied Metacrology, 7o1.14 ( August 1975). i
- 14. Final Envi.~:nmental Statement related to the operation of Dresden Nuclear
?cwer Statica Units 2 and 3 by the Ccamenwealth Edison Co., Decket No. 50-237 and 50-249, AEC (November 1973).
- 15. Applicants M reemental Statement, Dresden Nuclear ?cwer Station Unit 3, Commenwealth Edison Co., cceket No. 50-249 (July 1970).
r k P E I 3-59 i
NEDO-21326C3 January 1981
- 16. Thom suggests an annual extreme-mile (fastest mile) wind speed of 82 mph for 30 ft above ground and for a 100-r7-mean recurrence interval.
- Thom, H.C.S., "Ne0 Distributiens of Extreme 'ainds in the United States," Journal of the Structural Division, Proc. ASCE, 7o1. 94 No. St. 7 (1968) Applicants Environmental Report, Midwest Fuel Recovery Plant Morris, Illinois, June 1971.
s
- 17. !'urry and Trettel, Inc. Censulting Meteorologists, Chicago, IL. Letter, Literski (M&T) te Eger (GE), September 23, 1976.
- 18. An increase of 55 for a reprocessing facility; less for a stcrage i
facility. l t i
- 19. From Braidwood Statien Invironmental Repert, Co=monwealth Edisen Co.,
Chicago, IL. Year of record: July 1971 - June 1972.
- 20. The application of these =ethods to the Dresden reacters and the descriptien of the techniques used there can be found in Appendix A of the Final Safety Analysis Report for Dresden 2 and 3, Docket 50-237.
- 21. The description of the first year's data taken at the site can be found l
in Amendment No.13, Question 3-11, to the Dresden Unit No. 2 Final Safety Analysis Report, Docket 50-237
- 22. E. C. Watson and C. C. Gamertsf elder, "Divironmental Radioac tive Contamina-j tion as a Factor in Nuclear Plant Siting Criteria," February 14, 19 6 3, EW-S A-l 2809 i
I
- 23. Dames & Mocre repcet dated January, 1971 ( Appendix 3).
j t 1
- 24. Dames & Mocre,1550 Northwest Highway, Park Ridge, Illinois 60068.
l i
- 25. Payne,19u0, page 7; and Eardley,1962, page 45 l
- 26. Willman and Templeton,1951, page 123 t
9 3-60 i
NEDO-21326C3 Jcuntry 1981
- 27. Bristol and Buschbach, 1973, Plate 1.
m
- 28. Will:an and Te=pleten,1952; also Bristol and 3uschbach,1971, Figure 3
- 29. Ikblau, 1956 ; Da=es i Moore, 1965.
- 30. Kempton,1975
- 31. See Table 3-13 for studies referenced in this secti:n.
- 32. Payne, 1940; Wili-mn and Templeton,1951.
- 33. Will=an and Te=plecon, 1951.
33 Ca:es & Mccre, reper: dated Oecencer, 1967 ( Appendix 3).
- 35. J. A. Udden prepared a reper: describing Observations of this earthquakc.
He presents an 1sessis=al map fcr this earthquake and, according to his map, the site was in the area which experienced Rossi-Forel intensity 7: (about 7-VI On the sodified Mercalli scale).
- 36. his intensity is based en an isoseiscal cap prepared by C. W. Nutt 1.
and p resented in the Bull. Seis. Soc. ks., 7o 1. 63, No. 1, 1973
- 37. K. Iger, Opersting ?.xperience Report - Irradiated Fuel Storage at Morris Operation - January 1972 to December 1979, General Electric Company, September 1980 (NEDC-209698).
38.10 CFR 51, St-7 Table S 4, "Invircemental Impact of Transportation of Fuel and Waste To and From Cne Light-Water Cooled Nuclear ?cwer Reacter, U.S. Nuclear Regulatory Co= mission, especially Note 4, "Although the environ-sental risk of radiological effects stemming from transportatien accidents is curantly incapable of being nu=erically quantified, the risk remains small regardless of whether it is being applied to a single reacter er a multireactor site." I 3-61
NEDO-21326C3 January 1981
- 39. Environmental Survey of Transportatica of Radicactive Materials to and frem Nuclear Power Plants, U.S. Atcmic hergy Cocsiss10n, Dece=ber 1972 (*4 ASH-
.^ 1238); and U.S. Nuclear Regulatory Co* sion, April 1975 (Supple =ent 1, NUREG-75/038). LLO. Final Enviren= ental Statement en the Transportation of Radioactive Material by Air and Other Modes, U.S. Nuclear Regulatory Cc= mission, December 1977 (NUREG-0170).
- 41. Environmental Impact App W ul by the Division of Fuel, Cycle and Material Safety Related to License A=endment for Materials License Amendment for j
Materials License No. SNM-1265 Morris Operation Facility - Grmdy County, Illinois fer General Electric Ccmpany - Decket No. 70-1308, Nuclear Regula-l tory Occmission, Dececter 1975 (NR-FM-002), especially Section 5. t
- 32. Envirer.= ental Impact Appraisal related to the Renewal of Materials License No. SNM-1255 for the Receipt, Storage and Transfer of Spent Fuel at Morris Cperation - General Electric Company - Decket No. 70-1308, U.S. Nuclear i
Regulatory Commission, June 1980, especially Secticas 7.5 and 3.2. j l n i 1 t I 1 l l 1 l 1 i 1 l 3-c2 ,. I
, NEDo-21326C3 January 1981 4. DESIGN C3ITE4IA AND COMPLIANCE 4.1 INT 30DUC* ION A general descriptien Of the Morris Cperation and a s"-wy of its operational functions are contained in Chapter 1.' 2e Original design criteria for Morris Operation facilities were developed and established as part of the design for a fuel reprocessing plant - the Midwest Fuel Recovery Plant. The criteria herein are those applicable to the use of those facilities for spent fuel storage. 4.1.1 Material To Be Stored ' The Morais Operati:n is licensed ' to secre irradiated lignt water reactor Pael frc: nuclear power statiens. Se design basis Pael is UO2 Pael with an initial enrich-sent of 5% U-235 or less, with stainless steel, circeniun, er ircahy cladding, in a " bundle of reds" geometry. The design basis fuel =ay have been irradiated at specific pcwer levels of up to 40 W/kgU, with exposure to 23,000 mwd /TeU (batch average), ar'd sust have eccled for at least 1 year after reactor shutdcwn before entering storage at Morris Cperation. The accident analyses in this repce: were originally prepared for fuel cooled 90 and 160 days, and these analyses have not been changed. ~ The calculated fissien product activity contents of fuel irradiated at 40 kW/kgU, exposed at 44,000 mwd /TeU, and booled 90 days,and 160 cays are pre-seated in Table 3-1. Tuel to be ' received and stored typically will have exposures of 33,000 mwd /Tec or less, with cooling periods much longer than 1 year. As of the first of Feb-ruary 1977, the average exposure of SWR Pael in storage was about 3,100 mwd /Teu and that of PWR fuel about 23,700 mwd /Tec. Se average exposure was less than 15,000 mwd /TeU, far less than 43,000 mwd /TeU. As of the first of Nb ur.rv 1977, the average cooling time of %'R fuel in storage was about 61 secths and that of ?T4 was about 52 =cnths. Overall, the average cooling time was about 56 months (2.7 yr). Realistic exposures and cooling ti=es based en the fuel in storage have been used l in some scalyses, as appropriate. Table 3-2 Ocntains a list of analyses and Pael expcaures and cooling times en wnich each is based. 1 'See Section 4.7 for references. 4-1 l
-= NII:DC-21326C3 Jenuary,1981 including the forces that might be imposed by ::atural phenomena such as earth-A quakes, tornadoes, and ficcding conditicns. Standards fer assuring that systa=s, structures and equip =ent will perfcr= safecy functions for their intended service life with a icw probability of failure have been based cc upper ' t te=peratures, cerrosica rates and other stress cendi-tiens derived frca comprehensive analyses, including censiderstion of: a. accessibility for in-service surveillance, monitoring and repair (or replacement); b. potential fer short-term exposure to abnormal opersting cc accident ccnditicas; and c. censequences cf ec=penent failure; no single cecpenent failure er zul:1-pie failures caused by a single 1::itiating event shall result in signif- [ icant radiation expcsure to the public. d. accessibility for emergency services, including a=bulance attendants, fire and police services, and other emergency activity. e i i 4.2.1 Wind and Tornado Leadines s i t.2.1.1 Criteria ?lant structures and components essential fer safety shall be designed to with-stand the effects of short-term vind velocities of 300 mph with pressure differen-tials of up to 3 pst withcut damase to fuel in storage to an extent endangering l public health and safety. 3e site is located in USNRC Tornado Intensity Regica I I, as defined in Regulatory Guide 1.76. f 4.2.1.2 Compliance 3e fuel basic structure (enclosure) was analyned with wind loads applied as uni-form static loads on.the vertical or horizontal projected areas of the walls and roof. Culy dead lead was considered as resisting uplift. Horizontal wind leads I t i ( l i tamh ~ r
NCO-21326C3 Jcnuary 1981 are distributed by the walls to the ricer and roof syscams, which transfer leads ^ to the latersi lead-car ~ying elements Of the structures. Plant structures and cc=ponents were designed to withstand sustained wind velec-l ities of 110 :ph without less of func:1cns. At higher velocities, the encl 0sure ccvering =ay fail ce blew away. ] l These analyses included considerstion of. drop in atmospheric pressure of 3 psi in 3 seconds. his ecnditica wenid damage the basin enclosure, probably da= age or even remove such of the rcot and wall sheathing from the basin enclosure, but would cause no off-site radiological effect. 4.2.2 Tornado Missile 3-etection i 4.2.2.1 Criteria Plant structures and ccmpenents essential for safety shall be designed to withstand the effects of windborne =issileu without damage to fuel in stor3se 50 an ext ent endangering public health and safety. i 4.2.2.2 Compliance The fol10 wing su==ary of analyses indicate that the public health and safety would I not be endangered as a result of tornado =issiles i. pacting the fuel storage struc-tures or components. l Cnly those windborne objects which cculd have a significant downward velocity on entry into the water-fi.lled basin have the potential for causing dama6e to basin j l centents. Such objects must have been at a 31.gnificant elevation above grcund level, pricr to entry, to develop the required vertical velocity co=ponent to result in damage. Potential =issiles can be c?.assified in regard to : heir relative eleva-tion, as follows: j 1 1. Objects in the 1.=nediate area which, when the ter. ado strikes, are at elevations above the level of the basin surface (operating equip-j J sent and auxiliaries, ecmpecents of the enclosing structure, etc.). l i a l 47 t -. ~,,. - ~ ~,.
=-. l l l NEDO-21326C3 January 1981 i ( 4.2 7 Basic Water Cooling l .-~, '1. 2. 7.1 Criteria Means shall be ;:rovided to naintain basin water te:::perature less than 20C F C C (93 3 C). 4.2.7.2 Complitsee Basin water is cooled by a system described in Section 5.5 3 E r i 5 r l ? a f e l i I i f i f I r i s l l 4-41a ~ ,,,-----,iw-r-,--%---
NEDO-21326C3 Jcauary 1981 4.3 SAFET! PROTECCCN SYSTEMS 4.3.1 Genersi 'here are no site-related factors that are suf ficiently unusual to require pre-taction systems or special design considerations beyced these normally required for a facility of this type. Operations shall take into account the proximity of CNPS to assure that the cumulative effects of these operations do not constitute an unreasonable risk to public health and safety. 4.3.2 Protectien by Multiple confinement Barriers and Systems The total confinement system censists of one er : ore ind1vidual confinement barri-ers and systems that successively minimize the potential for release of radicactive sterial to the environment. These features also protect the fuel in s:crage ty protecting the fuel fr m damage and providing a f avorable environ =ent. '4 3.2.1 criteria Equipment and systems containing radioactive or potentially contaminated sace-rials shall provide a continuous boundary against escape of such :sterial and te designed to have a icw probability of gross failure or significant uncontrolled leakage during the design lifetime. Secondary confinement bar-iers such as vaults, ventilation system, etc., shall be designed and constructed to contain the results of primary system failure, under { conditions that may have initiated such failure, without loss of required integ-i rity and to continue operation for the maximum anticipated period of stress. Storage vaults and basins shall be designed and constructed f tr a icw probability i of gross failure or uncontrolled leakage, with =eans provided to sonitor leakage l 5 and preclude transport of rad 10 active saterials to underlying aquifers. For lined l structures containing radioactive or potentially contaminated liquids, leak detec-l tien and emi'ty-out eans shall be provided betweet, the liner and the structure so that release of radioactivity to the envirens csn be avoided by pumping leakage [ back into secrage, effecting repairs where leaks can be located and are accessible, [ or installing additional facilities in the event repair is not feasible. Water i M2
NED0- 21326C3 January 1981 systems shall be desianed to prevent accidental removal of water fecm the basins i by any means to less than a safe level. Basin water level shall be indicated and ^ alar:ed (low water alarm) in the centrol recs. '.3 2.2 Ccmpliance 4 All criteria described above have been satisfied; refer to Chapter 5. 4.3.3 su11 ding 7entilatien 4.3.3 1 Criteria Radioactive naterial in the building vencilati:n exnaust shall be reduced to levels that are as low as reasonably achievable before being released to the envirens. Special venting lines and speeds' ea' sures shall be e= ployed when necessary, such as during cask venting Operatiens, to centine airborne radi: active particulate materials. 4.3.3.2 ccepliance
- he principal methods used to =eet these :.riteria include the f0110 wing:
a. Generation: Airborne radioactive sacerial =ay originate frem cask decen-tamination and venting operations; icw activity solid waste ecmpacter operation; preparation of contaminated equipment for disposal; and frem operatic cf the low-ectivity liquid waste treatment systems. Other than these principal sources and the since leakage from fuel in storage, no other significant source exists.8a *hese activities can be suspended on short notice whenever higher than prescribed levels of rad 10 active materials are detected in the ventilati:n air exhaust stream.
- he waste evaporater system is designed te 11=1t radicactive :aterial in its e f.",u en t.
l 1 b. Confinement: "he building ventilati:n system utilizes pressure differ-entials to maintain air flew paths to exhaust all ventilatten air thrcush i the filter system and the discharge stack. Special venting systems j and special enclosures say be empicyed to ecnfine airber.e ; articulates \\ M3
4 NEDC-21326C3 January 1981 fres cask venting, decontaminatica activities, or si.milar sources to the filter - discharge stack system. he ventilation system is designed m for all credible nereal or anticipated off-nor=al tenditions. c. Release: The building ventilati:n system is designed to collect all ventilation air and exhaust it through a final sand filter Of demonstrated enpability for removing particulate atter, and a 3co-foot-high discharge stack. 4.3.4 Protectien by Ecui ment and Inser mentation 4.3.4.1 Criteria Equipment and instrumentaticn shall be provided to =cniter :~adicactivity and other parameters of operation, anc to perform r= lated centrol functions in acccedance with ,he following: a. Equipment and systems shall be set and adjusted to alarm and/or initiate action suen that specified limits are net exceeded as a result of normal or abacer.21 cccurrences. b. Redundancy and independence shall be ;revided to a deg se suffi: lent ,o assure that no single failure of an instru=ent er equipcent item :an re-sult in less of protection functions. 1 c. Equipment shall be designed to perric inspection, testing, and =aintenance. d. ~he centrol recm shall per=1t occupancy and allew :onitoring of importaa.: systems and functions during normal operations and under anticipated off-normal er accident cenditions. 4.3.4.2 Equipment Ccmpliance Equipment is designed to per:10 inspection, =aintenance, and periodic testing of functions to specified parameters. Temporary removal of single items of equipment fran service has no safety significance. 4 44
NEDO-21326C3 January 1981 [ b 4 3 4.3 Instrumentation Ccmp11ance t 1 i
- .strumentatien ir provided to assure proper operatien Or notificatien of the fail-
[ ure of systecs. Estru=entatien is designed ce specified to standards of knewT1 relia bility. To assure instrument reliability, periodic *,esting and calibration i checking are perfer:ed in accordance with Operations Specificatien 10.4.4.1. I Alams indicating a set point has been exceeded are annunciated in the control { recs, and where there =ay be an 1 =ediate effect en personnel such as radiatien j t exposure they are alar =ed locally as well. t I 4.3.4.4 Control Recm l [ ~he centrol recs is described in Section 5.5.5.4 [ t t 4.3 5 Nuclear criticality Safety i 4.3.5.1 Criteria 8 ,a r i Every reasonable precautica shall be taken to preclude a criticality within theMorr Cperation. Beth desip and ad=inistrative centrols shall be utill:ed. 4 3 5.2 Design control Cc=pliance i f The desip cf the spent fuel storage system includes the fel' centrols to pre-3 clude a criticality incident: f ) a. Sitial analyses were nade in sufficient detail :o demonstrate that { the criticality centrol cencepts censidered (e.g., favorsble gec=etry) were feasible under all credible ccnditions. Additional detailed nuclear j criticality safety evaluatiens of the final des:.gn were =ade by qualified j i experts in the field to assure that final dimensions and Other factors i affecting safety margins were adequate to prevent 'a criticality incident. s The additional detailed analyses required to confirm the final design are included in this document in Appendices A.10 and 3 5. i I 4 35 i
NEDO-21325C3 January 1981 b. In the derivation of subcritical 11=its, the k,ff calculated for the ^ sest reactive credible cenditicas was specified as 0 95 at a 95 per-cent confidence level.9 4 3.3.3 Ad-M strative Control compliance The operation of the spent fuel stcrage facility includes the fc110 wing ad=1nis-trstive controls to preclude a criticality incident: a. Safety evaluatien, review and approval of operating precedures related to design control pars =eters. b. 7erificatica cf nuclear Pael para =eters fer "uel seneduled to be stored l at Morris Operation. c. Verification cf fuel identity fer Pael received at Morris Cperation f for storsge. [ r -l I d. Maintenance cf fuel stcrase locatien recceds. e. Specific fuel and cask handling procedures. f i i f. Personnel training. t i Independent review and audit procedures are utilized to determine the adequacy cf nuclear safety centrol provisions and the effectiveness cf i=plementing f activities, f l 1 436 Radiological w tection t 4 3.6.1 criteria i f Radiatien and radicactive centaminatica ecnditiens at the Mor:is Operation shall [ be controlled to provide protection of persennel health and safety at all times. [ t Emphasis shall be placed en -d nd'M ng both individual exposures and Octal expcsure r (man-Rem) to as la as reascnably achievable (ALARA). l i + 6
1 l NEDo-21326C3 Jcnuary 1981 During ::ccmal operatiens, including anticipated occurrences, the annual dose equivalent to any person located beycnd the controlled area boundary shall not exceed 25 Res to the whole becy, 75 2Res to the thyroid and 25 Rem to any ceter ] cesan as a result of either planned discharges or direct ndia,1cn f.-cm the facility. Any persen located at or beycnd the nearest boundary of the controlled area shall net receive a dose 7,..ater than 5 Res to the wnole body or any crgan from a design e basis accident. t 4 3.6.2 Compliance Criteria are satisfied througn the fc11cwing design features and Operatienal practices : a. Confining radicactive, naterials to pr* scribed locatiens. b. Clearly definirg areas in which significa::: radiation er cen-tamination levels exist. c. Applying special provisions and appropriate procedures to assure personnel safety. d. Applying rigerous surveillance, housekeeping, and clean-up practices. .Providing cocprehensive persencel training in radiological safety. e. Desi=eters are prcvided for assuring accurate detection and assessment of persencel expcsure to icn4-dag radiatica, in acccedance with applicaele procedur4s.
- hermoluminescent devices (T D's) are positioned througacut the site Oc assess trends in beckground dose rates so that increases nay be detected and corrective plans initiated.
4 3.6.2.1 Access Control (Restricted Areas) Provisions have been established for centrolling perscnnel access to areas in which radicactive =aterial is present and ars =aintained to keep the potential for 4-47 1 ,.r- ,,m-. ~ e
4 RED 0-21326C3 Jcounry 1981 contacinatien spread and exposure to radiation as icw as reasonably achievable. This is accomplished by maintaining a series of access control barriers with -s l increasingly restrictive cccupancy ccnstraints and access authcrizati:n require-munts. These access centrols were designed as felicws: a. General Electric Tract: Agricultural fencing with appropriate pesting encieses the tract. Routine surveillance by operating and security personnel is utilined to assure that unauthorized occupancy for signif-l icant perteds of time is prevented. b. Protected Area: An 8-f t-high cha:.n link fence topped with barbed wire surrounds the protected area in which the Morris Operatien stor1ge facili-ties are located. Perscnnel lnd venicle access gatas are iccked or nacned by security personnel at all ti=es. '4h11e in the protected area, perscnnel are required to wear personal identification and desi:eters. All vehicles, saterials and equipsect are checked into and out of tne area foll wing pro-J cedures that require potentially contaminated or rsdicactive items to be =cnitored and cleared before entry or exit is authorized. 1 6 c. Coerating Area: Personnel access to the cperating areas in which radioactive material is secred is controlled by Limiting entrance sucn that occupancy authorizatien requirements can ce strictly en-forced. Access to the 7aricus areas is controlled by the structural compartmentalization and by authorization procedures commensurate with the conditiens existing in the particular areas. Accass to all potentially centaminated areas requiring personnel occupancy is limited to specific routes that have been provided and is in accordance with prescribed procedures, clothing and =enitoring requirements, which are varied according to the ; articular conditions. Exit from the operat-ing areas, except under emergency ccnditions, is by the same centro 11ed routes, through necessary clothing change statiens and moniterug facili-ties. Routine radistica surveys of the area are performed, and TLD's are posted. Equipment requiring access (e.g., basin ecolers) can be decen-i taminated to permit =aintenance. Materials and equipment required for operstica and =aintenance vill i be checked into the areas and will be a:nitored before leaving the 4 38
NItDo-21326C3 3 January 1981 areas in accordance with prescribed centrol procedures. Access for transfer of such ite=s is limited to specific points which are pro- ^ vided with =eans for precluding utauthori::ed usage. d. .Centrolle' Access Areas: Areas with the potential of high dose ra:es are locked, with access centrolled from the Control Recs. 4 3.6.2.2 shielding Radiation shielding is provided to restrict personnel expcaure to levels that are as low as reatenably achievable. 4,.3 6.2 3 Radiatica Alars syste s Sampling and detection syste=s are provided tha: have sufficien; sensitivity and scope of ecverage to assure tha: any radiatien or contamination 00ndition of potential safety significance is accurately and pec=ptly assessed. Area radiation monitors =eet the folicwing requirenents: 1. Monitors will detect r-a radia:icn within the range of 0.1 :o 1000 :R/hr. b.
- he high trip alarm is audible locally and also annunciates in the 00ntrol P003.
c. The criticality sceident alarm system meets the following requirements: (1) The system Ms gamma-sensitive zeniters that meet the sensitivity requirements of 10 CFR 70.24(a)(1). (2) Se system produces an audible alarm that is unique and cannot be shut off even if the exposure rate decreases. (3) iso detectors are provided in :he basin. (4) The system is continuously functional. s 4-49
NEDO-21326C3 January 1981 (5) Detectors are loc.ited in the storage basin area but not underwater. .m (6) The upper alar = Orip circuits fer the system are arranged in parallel so that either alarm will energize all criticali:y alar:s. (7) The alarm circuit that energ1:es the cri:icality horns is designed to stay on once it has been initiated and a manual reset in the :en-trol reem sust be employed to silence the horns. ( 4 3.6.2.4 Effluent Monitoring Sampling and =eni:0 ring systems and associated precedures are provided to measure radionuclides in ventilation ef.'"_uen: and in sample wells. Metecro10gical data and off-sita radicactite sacerials =eni Oring are prodded by a joint pres am with CNPS. 4.3.7 Fire and Exca.csion Frctection 4 3.7.1 Criteria Structures, systems and ccmponents directly invol'ted in the a:Orage of fuel shall be protected so that perfor ::ance of their functions are not i= paired when exposed to credible fire and expl:sion conditions. 4.3.7.2 ccmpliance This, criterion is met by using nencemeustible and heat-resistant sa:erials wnen-ever practical throughout the facility, particularly in locacions tital to the i i functioning of confinement barriers and systems such as the basin areas and the pump recm. Fire detection, alarm, and suppressica systems are installed in ware-house areas, and certain areas of the ~$d" building. Fire extinguishers and other equipment are strstegically located throughout the facility. Fire brigade training is furnished to operntional persennel. Fire alar:s are audible in the control recm. l 1 -./ i l l i 40 =_
s NEDo-21326C3 January 1981 4 3.3 Fuel'and Radicactive *4aste Handling and Storage ,m 4.3.8.1 Spent Fuel Receiving and storage criteria The cask and fuel h.cdling syste=s shall provide f:r the safe, reliable and effi-cient handling of casks and fuel. 4 3.8.2 compliance The cask and fuel handling system is capable of receiving irradiated fuel bundles in shielded casks scunted on trucks or railrcad cars. All major equipment such as cranes located above basin areas containing fuel are designed to ensure that 00=p0-nents will not fall inta the basins.
- he cask handling systes has been designed to preclude a cask f.~:s being :oved Over the fuel s:Orage basins.
Means are ;re-vided to preclude lif ting a fuel bundle Or a fuel st0 rage baskec : an elevation Within a basin sucn that the shield provided by the basin water is reduced suffi-Q ciently to cause excessive exposure to personnel. l l Cask drop analyses have decer=ined that ener57 Absception provimiens in the 4 fuel unicading basin are adequate. l Treatment of the stcrage basin water is adequate to =inisine corrosien and i prevent undue exposure of personnel, i e 4.3.3.3 Radicactive Waste Treatment criteria l I Radicactive aste shall be stored en-site in a manner that dees not preclude re-i trieval and transfer off-site. Provisiens shall be made fer inspection and sam-l pling of the waste material. No liquid rad 1: active waste shall be discharged frec the site. Solid :adicactive wasta shall be disposed of in accordance with current regulaticas. Criteria for storage facilities are given in Section 4.3.2.1. 1 w/ ) 1 i 1 4-51 l 1
-KIDO-21326C3 January 1981 4.3.8.4 Ccmpliance Radioactive liquid waste is stcred La the icw activity waste vault, and periodi-cally reduced in volume by evaporation. The vault can be e=ptied for.aecrieval. No radicactive liquid waste is discharged from the site. A solid waste ecmpact0c is provided to reduce the volu=e of solid waste before disposal via a licensed cen-tractor. 4.3.9 Util?ty Systems 4.3 9.1 Criteria + b Utility systems important ;c safety shall =aintain the capability to perf:rm functions important to safety, assuming a single f ailure. 4.3.9.2 Ccmpliance See Section 5.7.1. t 4.4 CLASSI?ICAT*CN OF STRUC~URES, CCMPCEN*S, AND SYSTEMS The primary quality objective of General Electric Ccmpany is to provide a nuclear fuel storage facility in which structures, systems and ecmponents centributing to the prevention (and/or nitigation of consequences) of conditions that could re-g suit in undue risk to public health and safety will perform their required fune-tions in a predictable nanner during their intended service life. The degree of reliacility that sust be provided for various structures, ecmpo-i nents, and systems is determined primarily by the consequences of failure of that uni t. Failure of seme structures, systems, or ecmponents cculd - if uncer-rc;ted - expose people to ionizing radiation. However, in a passive facility such as a fuel secrase basin, repair or replacement of the failed structure, 1 system cc ecmponent can usually be accomplished long before the consequences l could pose undue risk to public or employee health and safety. Failure of still other structures, systems er ecmponents could result.in an unacceptable t loss of operating efficiency, but would pose no significant icng or short- ] ~/ range danger to employees ce the public. 4_32
3 NEDO-21326C3 January 1981 Quality assurance history and a list of structurer systems, and ccmpenents important to safety are contained in Chapter 11.. The quality assurance plan is contained in Appendix 3.3, 4.3.1 Intensity of Natural Phenemena Provisions have been -de to monitor natural phencuena in the region related to Morris Cperation. Meteorological data is providea througn a joint program with DNPS -(Section 3 4 3). Likewise, provisions for seismic measurements are in place at the adjacent DNPS. 4.5 DECOMMISSIONriC 4.5.1 Criteria The Morris Operation facility shall permit effective decentamination and decem-missioning to an extent permitting return of the site to unrestrictad use, 4.5.2 Ccmoliance The Morris facility design provides a stainless-steel-lined basin that facili-tates cleaning, volume-reducing waste management facilities, and a ventilation sand-filter that vill facilitate decontamination and decommissioning operations. Other features - Originally designed fer a reprocessing facility - facilitate removal of components and contamination Ocntrol (e.g., the canyon area and LAW evaporator). See Appenc1x A.7. 4.6 CODES, GUCES, AND STLYDLES Codes, guides, and standards applicable to the Morris Operation facility, as noted is this report, are listed in Table 3 4 s 4-53
EDo-21326C3 Januarf 1981 ) \\ Table 4-4 1 CODES, GUDES, mfd STrTDAF.DS Section Item '4here Referenced Unifers Building Code 531 ASTM C150 (Cement) 5 5.1.2 ASTM A15 (Rebar) 5.5.1.2 ASTM 262 '(Stainless Steel f.J.ner) 5 5.1 3 Regula* tory Guide 1,76 4.2.1.1 Regulator 7 Guide 1.60 4.2.4.2 Regulatory Guide 1.51 4.2.4.2 AISC Steel Construction Macual
- 3. 2. 3. 2.. a a 7th Edition, Appendix A ACI 318 4.2.5.2.1 MISI-N18.2A 1975 4 2 5.2 API-650, Appendix D 5.6.1.2 ASTM A514 (Stainless Steel)
Appendix A.3 ASTM A265 (Stainless Steel) Appendix A.13 ASTM A240 (Stainless Steel) Appendix A.13 A'4S-ASTM (welding rod) kopendix A.13 i t R a0ther references, also. 4 54
i 'NEDO-21326C3 j January 1981
4.7 REFERENCES
i 1. E. J. Eger, Operating Erperience - Irradiated Tuel Storage - Morris Cperation, Morris, Illinois, Ceneral Ilectric Cenpany, May 1973 OlEOC-209693). l 1 2. Cther postulated nissiles (pipe, wcod planks, steel rod, etc.) have less dan-J 1 age potent.ial than these nissiles censidered. 3 D. R. Miller and '4. A. Williams, Tornado Protection for the Spect Fuel Storage l. Pool, General Electric Ccepany, Novenbec 1968 (APED-5696). l 4.
- 7. C. Bates and A. E. Swansen, Ternado Design Ccnsiderations for Nuclear ?cwer Plants, 31ack & 7eatch, hgineers.
l 3. ?. L. Ocan, Tcrnades and Tornado Effect Consideratiens for Nuclear ?cwer Plant i Structures hcluding the Spent Fuel, United hgineers and Ccnstructors. i i 6. C. 7. Mccre, Design of Barricades for Hazardous Pressure Systess, Nuclear Engineering and Design, 1967 i 7. Design of Structures to Resist the Effects of Ato=1c Weapons, U. S. Arny Ccrps of hgineers. l ? 3. Ammann and '4nitney, Industrial Engineeri.2g Study to Establish Safet7 Cesign i Criteria for Use in Engineering of Explosive Facilities and Cperatiens, April r i 1953 l 3a. See Reference 1: NEDC-2C9693, Sectica '. I 4 9. See ANSI N18.2A-1975, Nuclear Safety Criteria for the Oesign of Staticnary Pressurined Water Reactor Plants. I 9 t l ~ j i ( i h 4-55/3-56
NEDo-21326C1 January 1981 5. FACILI'! DESIGN AND DESC'1IPTICN 5.1 *MT3CDUCT*CN
- his chapter centains descriptive information en the buildings and other features of the plant involved in the receipt, storage or snOment of irradiated fuel.
Facilities associated with fuel reprocessing are discussed caly as they relate to ir-adiated fuel stcrage activities. This information has been censo11 dated fres documents previcusly succitted and part of the public record.
- he :ajority of descriptive saterial is based en the MFRP FSAR (NESC-10178) with amendments and supplecents, and ~he Safety Evaluation Report For Merris Cperation Fuel Storage ?2pansion (NI00-20825).
5.2 SUMMARI DESCRI?"*::N Reproductions of maps and other illustrations in Chapters 1 and 3 (especiall7 Figures 1-1, 1-2, 3-1, and 3-2) provide geog:sphical information about the \\ Merris Operation tract and show the boundaries of the General Electric prop-erty and the general araangement of buildings and other site features. (See Chapter 1 for use of the terns " tract" and " site. ") A =cre detailec laycut and centour map cf the site and envirens is shewn in Figure 5-1. All radicactive saterial handling related to the fuel storage activity at Merris Operation is in facilities located within the ;rceected area. There are no radicactive liquid effluents released to the envirens, and no burial of radioactive er centaminated =aterial en the tract. The Only radicactive or contaminated waste atarials leaving the site are effluents vented through the ventilatica stack er solid icw-level radicactive wastes that are shipped off-site. Off-site shipments are rade in acecrdance wi'.h applicable United States Nuclear Re6ulatory Cecmission (USNRC), United States Depart =ent of Transportation (USDOT), and other State and Federal re6ulatices. 5.2.1 Controlled, Restricted, and ?-otected Areas The entire tract cwned by General Electric (Figure 1-3) is enclosed by agri-cultural fencing with appropriate posting and forms the centrolled area 5-1
NEDO-21326C3 January 1981 (exclusion area) as described in Chapter 3 In addition, the DNPS site to the north is similarly fenced and, posted and those areas to the east of the ^ Morris Cperation. site cccupied by the Cresden ecoling lake and its inle and cutlet canals are also centrolled as exclusien areas by Ccnsenwealth Edison. Be ecmbination of these areas,- supplemented by county read right-of-ways, provides adequate distances in all directiens from the Merris Operation stack iccation in which eccupancy can be centrolled as required to assure protectien of public health and safety. 5.2.1.1 Restricted and Protected Areas Be restricted areas, as defined in Section 20 3,10 CyR Part 20, are within a 15-acre protected area en the northern side of the trset (Figure 5-1), en-closed by a cbmin 1. ink f acce topped with nultiple strands of barced wire for a total fence height of 3 ft. The fence is provided with fence lighting and alum systems for surveillance during hours of darkness and f0rms a prbtected area, as defined in Sectien 73 2(g), 10 CFR Part 73 As shewn in Figure 5-1, facilities located within the protected area include the nain building, the adjacent ventilation sand filter and equipment building, three underground vaults, the ventilation exhaust stack, the cask service facility, the utill:1es and service building, the shop warehouse building, the adninistratien building, the general warehouse, and the water syst.,em well and elevated water.ank. Liquid (nonradicactive) waste dischkrge lines are routed frem the protected area to the sanitary waste treatment lageens and the industrial waste evaperstien i pend located south of the protected area. "'he sanitary waste fa ilities are c fenced, but are not a part of the protected area. Be evaperstion pend is not fenced. 5.2.1.2 Gates Entrance to the protected area is frem ths east-west county read (Collins Read), which bounds the tract on the north side. Entrances for personnel, read and i rail trsffic are at the acrthwest cerneo of the protected area. Entry is controlled from a guard statica in the foyer of the administratica building which 1:nludes the personnel entrance and is adjacent to the mad and esil gates. Two unmanned gates are located en the south and northeast sides of the protected area. The south gate is for construction equipment access ar4 5-3 p6----g-.ef+ g 4 --r-tr-agy in e --t-m--'* g-m-w +w-+--et-- ---n y%-e+we um- +waesew i,msaw -# e-a ge c a-er,t+rF tem-i-ee-tWe'-r w ee
- Ws
>W-
NEDo 21326C3 January 1981 ne fuel stcrage basins and the essk unicading basin are constructed of rein- ^ forced concrete poured on bedrock with a welded stainless steel liner. Se fuel s:crage basins are filled with demineralized water to a nc=inal depch of'28.5 ft. ~he water level =ay be icwered no more than 2 f t for =aintenance or other purposes but at leas 9 ft of wa:er is ner= ally maintained above the top of stored fuel. I' the water level falls =cre than 2 ft, pump suction inlets will be exposed, nere is no =eans cf accidentally draining the basin, nor can any of the basin water systems inadvertently drain the basin (i.e., the water s'ystems are designed with nonreversible pumps, no drainage system, etc.). Basin water level is indicated in the control recm.
- he system includes an audible icw-water alarm, i
~he cask handling, cask unicading, and fuel secrage areas are constructed of cen-crete, steel, and other aterials that are either nonflam=aole or fire-retardant. No significant amount of fla=mable =acerials is used in these areas, and 00her potential fire dangers (bottled gases, etc.) are seldes introduced, and then only under stringent administrative controls. No fire detection or autcmatic fire suppression systems are required in. these areas, er in the basin pump reem and its extension. Fire extinguishers are strategically located, and operation personnel are assigned and trained as a fire brigade. Further ;rc-tec 1cn is provided by surteillance patrols. Reinforced concrete in the basin walls and flecre has been estimated to have a useful life of nere than 100 years, and the stainless steel liner can be expected to have a useful life of scre than 100 years because of the nonagressive service environment. 5.5.1.1 Foundation and F.zcavation The easins are founded on shale bedrock (Figure 5-11). Samples Of the shale have been tested at ultimate ecmpressive strengths ranging from 5000,o 11,000 psi. Appendf.x 3 contains a site survey and foundation report prepared for MFR? constructicu.13 *he excavation was overexcavated and backfilled to Obe south of% sin 2 to facilitate expansica of basin storage capacity at some later date. All lecse and disturbed rock was rmeved price to cencrete con-struction. Backfill consisted of controlled and ccmpacted granular soils. Concrete mud sats were ; cured to fill any area excavated : ore than 4 inches 5-30
~ 9 NEDC-21326C3 .:anuary 1981 deeper than required (except for the south wall of Basin 2). ~he basin vall structure is designed to resist pressures frc backfill and scil water where overexcavattens were cade (south of fuel basin and waste vau'.:s, Figure 5-12). 5.3.1.2 Concrete Structure The ficers of the storage basins were pcured en bedrock and are at least i 3 f t 10 in. thick, but are thicker in so=e areas because of the +0, 4 in. tolerance in excavatien requirements. Se basin flects are desigr.ed fer live 2 leads in excess of 1000 lb/ft. Basin walls extend 3 5 ft above grade. I Materials used f:r ccccrete ecnstruction of the basins are typical f:r Other l concrete construction en the Merris Cperation site. Materials used for rein-forced cencrete structures were j E cement conferming to AS"i C150 type 2; er washed sand; washed and graded aggregate; and e-reinforcing steel per ASTM 115, intermediate grade, j e Cencrete pours had slu=p tests and labora:'ory sa=ples taken, usually at I the discharge from the truck, but at times at, the point of placenent - partie-i ularly en canycn centainment walls. Concrete samples were taken for every i pour of 100 yards er less, vnenever a peur compositicn changed for any reascn, f and cce per 100 yards for pours greatar than 100 yards. A full-time concrete i inspection program was in effect during construction. j c f' Reinfcrcing steel used in the basins is intermediate strength with_ninimum i yield strength of 40,000 psi. Structural welds Oba: carry ' cads frc= cne l element or reinfeccing bar to ancther were not used. ~4here required, 1 cads Y were transferred from bar to bar by conventienal reinforcenent bar laps secured i i in assemblies by steel tie wires.
- n special cases, U-bolts fers used.
3e enly welding permitted was tack-welding the reinforcing steel to brace asse=blies away fr:m the forms or to secure i= bedded items in positica during the concrete I i [ 5-33 i
NEDO-21326C3 January 1981 pour. In mest cases, assembly bracing er i= bed securing was done by the use of additienal reinfeccing steel or structurs1' steel tack welded to the reinftreing ^ steel assembly. I: beds were either welded or cla::: ped to this additional steel. Tack welds were =ade no larger than necessary to produce sound, crack-free welds. 5.5.1.3 'asin Liner ~he unicading and storage basin complex is ce=pletely lined with 304L stainless steel sheets placed flush against the concrete walls and ficers and welded to a gridwork of stainless steel back-up = embers eccedded in the concrete (Figure 5-13). For the unicading pit ficer area, the. liner is 1/4-in. thick and is placed over a 1-3/ -in. thick steel plate provided for distributing i= pact leads over the underlying cencrece structure. Additicnal energy a:scrbing means as may be required by cask drop accident considerstiens for receipt of larger-sined casks Will be installed. The unicading pit shelf liner, also 1/Lin. thick, is placed directly cn the cencrete structure sith an energy abscrbing assembly placed en top of the liner (seen in Figure 1-13). For the recainder cf the storage basin caplex, the ricer liner is 3/16 in. thick.
- he walls of the unicading pit, including the shelf area, and of the transfer tunnel are lined with 11 gauge sheet.
For the fuel secr3ge basin walls, the liner is 11 gauge sheet from ficer level to approximately 16 ft up the wall and is 16 gauge sheet f.~:s there to the top of the basic. The large liner sheets (generally en the order of 6 x 16 f t) were welded con-tinuously along each edge to the gridwerk of back-up bars and also were slot welded to embedded plates at intermediate locatiens so that the liner is held against the cencrete wall to reduce the potential for puncture damage. To faciliate fit-up and to assure high integrity, liner sheets were welded to embedded stainless steel angles at wall-to-wall and ficer-to-wall joints. Also, the liner terminates en a stainless steel f.ngle at the top of the basin. Specifications fcr liner installation include approved joint designs, welding procedures and welder qualification requirements. All velds were visual 1*/ inspected and vacuum box tested to assure leaktightness.14 Final verificatien of liner integrity was provided during basic filling. 5-34
1 NEDO-21326C3 January 1981 Thrcush May 1975, the natural heat-dissipating capacity of the atmosphere and pool structure adequately naintained the basin water temperatures at less than aucC (111.20F).2 Decay heat generated by P.:el in the basin is re=oved prd-$-ily by evaperstics, with the re=ainder conducted througn the basin walls. i 5 5.3 2 Safety Evaluatien Failure of the basin cooling systec. is not critical to the safety of the fael stcesse system. The cooling system has three independent units. Each of the two larger units has adequate capacity to diss.ipate the total expected heat load (6.5 x 106 Stu/hr). In the event of failure of the operational unit, tne basis water could be centinucusly ccoled by the other units while the system 1.3 being repaired. ~n the event that both of the larger heat exchanger units should fail, Or it was decided not *o activate a carbcn-steel unit, there is enough tine to supply nake-up water Oc the basin wcile the cooling system is repaired er replaced. If heat exchanger units were inoperative and the storage -basins were fall of fuel, the ta=perature of the basin water would slowly rise (< 2 F/hr' and C .s appecach boiling in no less than 3 days and pessibly lenger, as decernined by naturs1 conduction and evapersti:n rates within the building. ( As of. January 1979, water te=perature had always been less than *20 F.) Meanwhile, work to 0 repair or replace the cooling system would be initiated. ~n addition, ; reparations to add :nake-up water to the basin wculd be made if that should be dee=ed necessary. If the superstructure covering were removed or blown away, water tenperature would stabiline at about 183CF (8400) because of increased evaporatien este frem the open pool. Potential leaks in the cooling system that could cccur as a result of an accident have been analyned and the assults given in Chapter 3. Ib was concluded that the consequence of a leak in the system is insignificant,19 Se ecclers are periodical 171._ scoted for leaks (Table 10-2). Accumulnion of radicactive cent 2'nimts La the cooling system ccmpenents is =cnitored, and the system ~ s decontaminated when required (Sec. ion 7 3 2.3). 5-44 ~.
NEDO-21326C3 January 1981 5.5.5.4 Control Rocm -~ The central control recs is located in the south gallery area intermediate level (65-ft floce elevation). The reem is about 75 x 21 f t in plan, with direct stairway access to the building lobby and secondary access to the unused ccm-puter recs. Principal items of control reem equipment include the main precess control panel across one side of the rocm, a control console, and various moni-toring equipment. Fuel storage functions monitored in the control reem are listed in Table 5-2, 11though some functions are normally centrolled only frem the control recm (e.g., basin eccler pump and fan controls and well-water pu=p control), the concritical nature of all control syste=s permia establishing local control in case the centrol reem becemes disabled. The control rec; is continuously manned, and its location in the main building permits its centinued occupancy during all operations, including emergency conditiens. 5.5.5.5 Laboratory Irea The intermediate level of the certh saliery area houses the laboratory facili-ties required for fuel stcrage opersti,on. Personnel access is frec the cor- ~ ridor which spans the east end of the main building at 70-ft reference eleva-tien. Equipment is ar unged in individual areas as described below: a. Specialised counting equipment is hcused in a 130 f t 2 reem iccated against the canyen wall. The counting reem is provided with heavy concrete shielding walls and a labyrinen shielded entry deer Opening to the accessway described above. b. The 630 ft2 laboratory houses a series of Pume hcods which prtvide for the venttiation and contamination centrol required for laborstory operations. The exit doce leading to the cutside stairway is located in the laboratory. 5.5.5.6 Precess Steam Generster Reem s The process steam generator, condensate eccler, surge tank, water treatment cenden-sate pumps and other equipment are housed in a separate recm. There is a service platfors at the 60-ft elevatico in the room for access to upper equipment levels. 5-50
NEDO-21326C3 January 1981 which is connected to a sf ngle leak collection sump. ~~ne susp consists of a 6-inch-dia=eter vertical stainless steel pipe e= bedded in the vault.all which extends frem the top cf the vault to approximately 1 feet belcw the vaul; flecr level.
- t contains a liquid level detec cr line and necessary piping fer a 5-sp= (nc=inal) jet-out systes.
Auxiliaries fer the level detection and jet-out systecs, including a =enitoring sample statien, are 1ccated in the hydraulic equipment rocm of the =ain building. Water frem the jet-cut system is routed back to the cladding vault. 57 SUPPORT:2iG FACII."'T:.S Supporting facilities are described in the felicwing sections. As in previcus f sections, these f=ctices related exclusi/ely to *uel reprocessing are ccitted er discussed only briefly. i 5 5.7.1 Utility and Service Building l Cn the north side of the =ain building is located the single-s:Ory high-bay l utility and serv' ce building (Figure 1 4). It is 71 x 50 ft in plan and is i cf conventional steel frame, insulatsd siding and roof censtr=tien en a p ade i level concrete fcundation. The building is divided into a uti'.ity see,ien which ' houses the plant utility steam system (gas-fired boiler), the de:ineral-l 1::C water systes; che primary electrical switchgear; and a personnel section i cr.,ataining change room, lunch recs and office areas. The arrange =ent takes into account the nor ::a1 industrial safety requirements fer gas-fired steam [ generatien facilities and fer major electrical equipment. Consideratien also is given to isolatien of normal industrial f=ctions and equipment frem all pctential scurces of radicactive centamination. Utility services are not cri-r tical to the safer.y of fuel storage operatiens. Interruptien of these services' i for short pericds of time, up to several menths, would have no off-site impacts l r as long as basin water level is maintained. Principal featu.ms are described 1.n the following paragraphs. r i i k i e 5-62 i
i NEDC-21326C3 January 1981 l l 5.7.1.1 Utility Section r . n me 1700 ft2 utility section of the building is divided in:o two rec =s, the larger of wnich houses the water demineralinatien and utili:y boiler systecs. ( 'he deminers11:er system begi.s with a.arcon fil:er to rencve crganic nacerial f from water entering the decineraliners. Se desineraliner cennists of.:Wo i parallel banks of series cation-anien units with degasification provimiens j I between beds. It is capable of treating 25 gpm centinuously or 50 rpm instan-f tanecusly frem the plant utility water supply. ?u=ps-required for operation, distributien and regeneratien are located nearby and a 1CCO-gal demineralined i Water surge tank is mounted en an overhead platfccm in the recm. i ~he primary uni Of the utility steam syste= is a 25,000-lb/hr package boiler l fired by natural gas wnich is designed to operate at 270 psig, but is ner: ally l li:1:ed to 125 psig. Auxiliaries include a pla: fern-counted 1200-321 cendensate l return tank and a 300-gal deaerator, as well as condensate return and boiler 2 feed pumps, ;hosphate and hydracine nakeup and injection facilities, etc. All normal safety provimiens required to assure safe operatien and persennel protection and to neet all requirements of the State of Illinois boiler code are included. A separate 300 ft2 room in the utility section houses the pri=ary l olectries' " **-4 "ution switchgear for the plant. nec=ing power frec the l Cc=menweal:h' Edisen distribution system is reduced to tSOV prior to entry into j i the utility building. f 5.7.1.2 Service Section l
- he 1800 f t2 service secticn of the building centains:
l s. Change room facilities with showers, lavatory and storage lockers j i to acccc=:cdate appecximately 100 Operating people. 1 i i b. i unch rocm facilities (steve, sink, refrigerator, etc.) for about 25 people.- c. About 450 ft2 of office space. s 5-o3
b KEDO-21326 C3 January 1981 7 3.2.1 History or Radicactive Material Concentration n The history of radicactivity in the basin water is sh wn grapnically in Figure 7-1.2 The general trend is a gradual increase in cencentration with increasing fuel leading and ti=e, culminating in plateaus and abrupt decreases. The plateaus
- ay be caused by a reduction in the scurce, or establishment of a steady-state cendition between radicactive sacerial addition and re=cval.
- he decreases are due to accelersted removal of radiecesium and radi: cobalt by the use Of filtration r~
and special 1:n exchange saterial in the basin water filter, t ,7 3 2.2 Contaminnnts
- he principal dissolved radicactive 20ntas1: ant in the basin water has been fission product cesius with cencentrati0ns ranging up to 10~o Ci/ml.
A means Of ~ Oesiu: removal has been f und Obat sakes reducti:n and Ocntrol Of this Ocntaminant l relatively simple. For exa=ple, ever a 10-week period in 1974, the radi: cesium concentration was reduced to one-third of that at the beginning of the period. The basin water inventory was correspendingly reduced frem about 29 to 11 Ct.
- n 1975, during a 4-week period, the radiocesium concentrati0n was reduced by a factor of six and the basin water inventory reduced frem 13 to 2 3 Ci.
At the end of the latter period, the radiccesium Ocncentration was 0.0009 mierecurie per milliliter.2 The MPCy f:r Cs-134 is 3 x 10 " C1/mi. The ability to dramatically reduce the amount of activity in the basin was the result of extensite studies and tests in which an incrgani molecular sieve mediam, Zeolon,3 was used to selectively remove cesium. These tests demonstrated that Zeolan ) i 100 could successfully be added to the ?cwdex system and remove about two-thi.-ds of i 1 the radiocesius per ? wdex charge. 3y routinely using Zeolen and adjusting ?cwdex ] i replacement frequency, cencentrations are effectively centrolled. j
- n addition to radi: cesium, the radi:nuclide contributing most significantly to i
- asin water centamination is cobalt-c0.
Concentrations of this nuclide in the basin water (typically,1 x 10 4 C1/nl) are attributed to corresien products On the surfaces of the fuel bundle which are released to the water, principally during fuel handlin6 Ncreal filtration and 10n exchange reduces the cobalt concentrations without special effort. 7-6
NEDO-21326c3 Jcnunry 1981 As. the fuel in the basin is increased frem about 300 to 750 Teu, the -radicactive contaminants, principally radiocesium,. will tend to increase. However, with the m demonstrated effectiveness of 'eclcn in.he filter,1, is not expected that any increase will tax the existing system. 7.3 2.3 Basin cooler Deconta=1 nation After a peried of operation, depending en the amount of new fuel received, contami-nants Meum'ulate en the inner surfaces of the eccler piping, tubes, and headers. In 1978, a chemical decentamination systen was introduced which is available to reduce exposure rates under the ecclers te acceptable levels. 7.3 3 Airborne Radicactive Ma:erial seurces There are five potential sources that could release radicactive caterial Oc ventilation air, where it would be passed througn the sand filter and sete frac-tien exhausted Oc outside air via the stack: a. effluent frcm the LA*4 evaporator; b. Vented gasses fr0m shipping casks; c. effgas frem defective fuel reds in the basin; d. decontamination activities; and e. urenium used in MFRP testing. Althcugh there could be radicative material in the demisted effluent frem the evaporator, the occurrence would be rars and the amount would be very small. 7ented gasses frem casks are exhausted to the LA'4 vault, and frem there Oc the air tunnel and sand filter. i During over 6 years of fuel secrage experience, there has been no evidence of l gasses leaking fran stored fuel. ~ cidental airborne conta=ination frem decon-n tamination activities (and fuel storage areas) could occur, although the use of special enclosures ("greenheuses") and other techniques limit such releases t
l !E O-21326c3 January 1981 For comparison, the guideline value for compliance to Appendix I of 10 CFR Part ^ 50 is 15 = Rem /yr to any cessn- (Regulatory ' Guide 1.109). 7 7.2.3 Man-Rem Calculattens f Man-Rem calculations were Originally done only for the esti=ated annual thyroid exposure because it was the maxi =t:m dese. Averages Of thyroid exposures were i calculated for con' centric circles with radii of multiples of 10 miles. These average values were multiplied by the population within each area which gives an average annual san-thyroid-Rec. "he sus of these values for each area out to a radius of 50 miles *gives e total of less than four man-thyroid-Rem /yr for { the period frem 1970 to the year 2000. ( An evaluatien based on 1-year-cid fuel would show an even 1:wer i= pace.) Ter Ocmparison, the population expcsure fre= normal background radiation (taken at 100 sR/yr) in the sa=e area is atout 665,000 nan-Rem for 1970, to 750,000 =an-Rem for the year 2000. Therefore, the radiological impac: frem the Merris Operation is insignificant. 7.7.3 Licuid Releases There are no planned releases of liquid wastes from the site. Furtherscre, there is no mechanism under normal operating conditiens for injection of conta=inated i 1 watt.r into the waste water treatment system.
7.3 REFERENCES
1. RESSAR 41 Reference Safety ina17 sis Report, Vol. 6, '4estinghouse, December 1973 i and Amendments. 2. K. J. Eger, Cperating ?.xperience - Ir adiated Fuel Storage - Merris Cperation, Morris, I1'
- nois, General I,lectric Ccmpany, May 1978 (}CO-209693).
22 State of Illinois, Department of ?ublic Health, Monitoring and Regulation of Nuclear Facilities in Illinois, 3pringfield, Illincts (1977). ~'he report shows slightl7 higner levels Of rad 1: activity in the centrol counties. 7-3R -_,_._. _. _.-_ __ _ _ _._..__ _ _-._ _ -.~ _ _._
t P NEDO-21326C3 l January 1981 3 A proprietary product of the Norten Co. n 2 "he average of 111 Ci gross beta is based on data fres 1973 througr. id-1976. This "sversge" has decreased as 1977-1973 data has been incorporated; see NEDO-20969B, May 1973. Be 111 Ci gress beta value is used in the off-sita i analysis. I i 5. Based on Morris Operstien experience over =cre than 6 years. l 6. T. Rockwell, Reacter Shielding Design Manual, 7anNestrand, 1956. l i i 9 7 R. O. Gu=precht, Mathematical 3 asis of Cc=puter Code RI2D, "une 1968 l (;UN 4136). 3. Regulatory Guide 1.109, Calculatien of Annual Doses to Man frem Reutine Releases of Reacter Effluents for the Purpcse of Evaluating Compliance with 10 C7R Part 50, Appendix I, March 1976. P f ) l a f i f i f r t 7-35/7-36 l
NEDO-21326C3 January 1981 8. ACCIDENT SAFFT! ANALYSIS P 3.1 DITRoc0CTICN i This chapter centains an analysis of pcstulated accidents in certs of the cause A of such events, the consequences, and the ability of the Merris Cperation Organiza- ' tien to cope with each situatier..' i The function of the Morris Operation is to receive, stere' and ship irradiated nuclear fuel. A primary require =ent of these operations is to protect the public and employees frem excessive exposure to ionizing radiation, as determined by the requirements of 10 CFR 72.68. Specifically, any individual at er beycnd the cen-trolled area boundary shall not receive a dose greater than 5 Re= to the wncle bcd'/ cr any Organ frem any design basis accident (i.e., these accidents described in this chapter). 3.1.1 Release ?athways F.xpcaure of the public and empicyees sign resui fece pcstula:ed accidents, by direct radiation fr:s the fuel, by airborne release of radi:acti'/e caterial, er by release of radicactive ma:erial to groundwater. These postula:ed events are discussed in :his chapter. None of these potencial releases have off-site inpacts above the requirements of 10 CFR 72.53. 3.1.1.1 Direct Radiation F.xposure of the public and empicyees could be pestulated to result fmm direct radiatien from the fuel in storage er by release of radicactive naterial to the envirens. D:. rect radiation frcm the fuel would occur only if the water level in the storage basin became too low to provide adequate shie'iding. This would pose a hazard to persens caly if they were in relatively close pro:r* ty :o the basin. i.,oss of water could result fmm postulated drai age er evapora:1cn of the basin water, but only when a basin =ake-up water supply quantity cr rate is not sufficient to keep up with tk water icss. Sudden draining of water from the basin is not credible.
- See Sectica 3.11 for references.
3-1
NEDO-21326C3 January 1981 8.1.1.2 Airborne Release <-~ Airborne release of radioactive caterial could be ;;stulated to result froc Nel becoming =echanically damaged sufficiently to release fission gases frem within the plenum of fuel reds. Of the gases released, only Kr-85, :-129, and I-131 would be of cencern. No mechanism exists in the fuel storage environment to cause an airborne release of particulate radicactive saterial' in quantitier, sufficient to cause exposures approaching the limits speci' led in 10 CFR 72.58. Curing canx operatiens in air (e.g., decontaminatica and venting) ; articulate releases sight cecur but in very s=all quantitles, even under the = cst severe ccnditiens that can be pcstulated. "'hese quantities wculd be uch tco small fer an off-site impac t. A criticality can be pestulated to occur by dropping a basket in such a way that all the fuel falls out of the basket and ecces to rest in a critical array, or by fuel cast:sts being deformed into a critical array by a tornado-senerated missile. 'n reality, however, the above events are only marginally pcssible and the results of eitner would be substantially less than the criteria of Part 72.58. Since d.e Nel asse:blien are designed to Operate in a light water :oderated critical array, such a Ori?icality would not cause vapori:stien of fuel. 3.1.1 3 Waterborne Release Release of water containing ridicactive raterials can be postulated to occur frem the LAW vault intrusien water su=p if an inner centainer leak is assumed (Section 5.6.1.2). Water frem this sump is normally disposed of in the on-site evaporation pond, so that an off-site release weuld not be likely. Water frem the storage basins can be pcstulated to be released due to a leak in the basin structure, permitting water to escape to the sur:cunding reck. A s=all a= cunt of water could be released to the ground in the event of a basin water cooler leak. (Such a leak signt also cause a s=all air reletse of centaminated vater vaper.) 8-2
l NEDO-21326C3 l January 1981 l 3.1.2 lecident Description / Discussion The following sections contain discussi:ns of varicus pestulated accidents and estimates of the quantity of rad 10 active =aterial release and projected cense-quences. A st==ary of events and the sequence of events involved in 'pos:ulated direct radiation and rad 1: active aterial releases tha could result in radiation exposure to the public is shown in Figure 8-1. No ecmbination of normal and credible accideat events has been developed that would result in an eff-site release er j direct radiation that would ex:eed the regulatory limits for an accident. 1 l 1 Sased en several analyses of the accident at Three Mile Island No. 2 (TMI-2), i a si=11ar accident at CNPS would have no un=anageable effects en activities at Morris Operat10n. A mucual aid agreement exists between Morris Cperation and DNPS; this agreement and other acergency plan imple=entation 10 Cy3 50, Appendix E), assures that operators at Merris would receive early notification of any significant scer-gency at DNPS. t' A release of noble gases and halogens frec ONPS, similar to or greater than at TMI-2. 1 would not affect fuel storage safety at Merris. The locatien and construe:1:n of the i Morris Operation control rocm, the availability of respiratory protective : asks and { systems, the availability of protective clothing, and c her radic1cgical e=ergency ( preparations at Merris would sinimi:e the i= pact on Morris Cperation of any release frem CNPS.Al Even if it should becc=e necessary to temporarily evacuate Merris Operation, the slew loss of basin water by evaporation and the ease of replace =ent negates pessible detrisental effects, and protects the public health and safety. A simultaneous accident at Morris Operation, such as a fuel drop accident (Section 3.7), would contribute an extrecely 10w additional dese to that frem a reactor 1 accident release, less than 0.019 = Rem whole body and less than 0.C96 mRec thyroid. 1 3.1.3 Exposure ?sths Of the possible exposure paths, only whole body. exposure frem external radiation and exposure through inhalation are censidered credible at any off-site location. No releases have been postulated that would result in the release of raterial (such as I-131) to farmlands, cattle feed lots, cc other sensitive areas that could result in an ingestion dese that would be scre :han a small fraction of the regulatory limits l l 8-3 u
~ s 1 NC O-21326CS 1 January 1961 -8.2 LOSS OF TUEL BASri COOLDIG l e 1 h
- he basin ecoling system is no critical to safety.
Tnen the ecoling system is not in service, the water =ake-up system can be. ed to replace water los l by evaporation. Even if the water sake-up system is cut of service, there is l r adequate time to repair er replace both ecoling and =ake-up syste=s er to provide { make-up water fecm alternate on-site er off-site scurces. (The water =ake-up l i i system includes the water well. anc' all equipment related to the normal make-up j / water supply to the basin.) j i l A censervative approximatica of the time available to provide ake-up water if. both the eccling system and the water =ake-up system were Out Of servi 0e has been calculated to be at least 9 days. ~he calculattens were based On t a constant heat lead of 5.4 x 105 Stu/hr, which is the approximate heat 1:ad l l if both basins were full of fuel like that new in storage and, hat projec ed I to be received. Cther assu=ptions were as f 0llows: l P a. uniform water te=perature throughout the basins; l i i b. ambient air at 70CF and 70". relative humidity in contact with the basin I water surface ; and 6 i c. basin encicsure removed, with :ero air velocity across the basin water surface (wcrst case), i, Under these assumptiens, the temperature of the basin water would slowly rise ii 0 (<2 F/hr) for about 3 days and even sicwer thereaf ter (a nenlinear function C of ttne). ~te saximum tempersture would be about 185 F, and sore than 39,000 ft3 of water would have to evaperste before the tops of the fuel bundles would be exposed.
- his would require scre than 3 days.
I The probability of excessively high :adiation dcse rstes resulting f:cm less of li fuel basin ecoling.is clearly quite small in view of the a=ple ti::'e for repairs i to be made and for water to be added frem any cf several sources. l s-za
NEDO-21326C3 January 1981 8.3 DRiriAGZ CF FUEL BASriS v 7ere are no piping penetrations which, if open, could drain the :tel s:cr-age basins and there are no pctential paths f:r siphening water frem the basin. Therefore, to inadvertently drain water frc= the basin the ba. sin liner =ust be penetrated. Because the basin structure is behw g 2de and because Of the hw. per=eability of the surrounding rcck (except for the overburden) and high level ~ of upper strata groundwater, leakage (even if it were undetected) wculd not uncover f the fuel (Appendix A.13). S.3 1 Basin Liner Rupture Ex erience An accident occur ed in w*une 1972 that resu).:ed in the rupture of the basin liner and demenstrated the ability of the Morais Cperation to withstaa.d and reco ver f.~.c s uch an ' -a d
- No excessive ex;caure to ioni::ing radiatice was experienced ty site persennel er the general ;uolic as a result of the incident and no groundwater conta=inatien abcve background levels was detected.
The impact :n the enviren=ent was so slight as to be un=easurable. Difficulties encounter *d during handling of an e. pty IF-100 shipping cask esulted in puncturing the liner of the :ssk unicading pit. Basin water entered the space between the liner and the structural concrete wall with sese seepage inte ;crtiens of the canycn in the main building. No stedial action was necessary to assure the safety Of site persennel. 2.e O -dng and d sequence of eva 4 were as follows. June 12, 1972 t 1120 hr Model IF-100 ir adiated fuel shipping cen-tainer Serial No. 2~0033 was tipped while attempting to disengage a jan=ed lif ting l yoke and came.o rest agains the south wall of the unl:ading pit. s 8-5
I NEDC-21326 C3 January 1981 1130 hr Alarms in the basin leak detection sump indi- ) '~ cated an inft:w Of water and it was deter-ined that the retal lining Of the cask unload-ing pit wall had been punctured. Approximately 1200 hr Progra s were started to sa:ple wells adjacent to the main building and plans i=plemented to remove the cask from the pt and provide a tem- / pcracy repair. 1230 hr Regien I:: Cc=pliance Office of the US AEC, i State and GE authorities were notified of the incident. 4 2,, i;i- ~.e. .v.... t 0700 hr
- he cask was re=cved frem the unloading basin.
1430 hr A te=porar7 ;atch was posi:10ced over the point of puncture and the outflew of water i frem the basin to the liner was reduced to a flow that was handled by the jet-out syste= (approxt=ately 15 gph ec= pared to a nor=al rate of 4 sph). i June 16,1972 - 0900 hr Fabrication of an accecs cha=cer for permanent repair of the liner was started. 1200 hr An additional well was drilled ncrtheast of f the building in the directicn of the nearest t cotta 688* ) i N i a i J l 8 4 3-0 i
i NED0-21326C3 January 1981 June 19, 1972 - i 1500 hr 2e te=perary patch apparently failed and the leakage rate to the leak detection sys-tem increased rapidly, exceeding the jet-out capacity of -he system. ( 1900 hr The te=perary patch was successfully replaced. / The leakage rate was determihed to be a'ppecxi-mately 15 c h. June 2*,'1972 - 1200 hr Decentamina:icn, inspection, repair and =cdi-fication of :ne tipped cask was Oc=pleted. June 24, 1972 - 2230 hr
- he temporary patch was re=0ved and the access chamber 10wered into the unicading basin.
~he liner was successfully repaired by welding a stain-less steel plate over the damaged area. ~he regicns of the :ain building where basin water 1 grated were :ne extrac-tien cell, mechanical cell, and equipment transfer area. Moisture was also f:und en the wall of the hydraulic equipment recs but no other 13aks were located. ~he air tunnel was inspected and found to be dry. Se amount of water that seeped into the precess cells was not recorded. '4ater was periodically pumped from the cells. Pathways for the leakage were cbserved to be around pipes that penetrate cell walls and through Occstruct10n joints. *4atar also leaked around the seams of the cell wall cladding into the mechanical cell. / 8-7
= -. ~.- i NEDo-21326C3 January 1981 8 3 1_.1 Leakage Disposition e Water less was carefully :enitcred f.~:n "a "-a the breach coeurred a approx-imately 1120 on June 12 until the temporary pa:ch was in place at abou: 1230 en June 13 Overall icas of water during this peried was abou 27CO gal. Of this a= cunt, apprc:ct=ately 4C0 gal were accounted fer through evaporation and 500 gal through a ncrual basin filter medium change. Another approxi ately 900 gal were jetted to the LAW vault from the leak detecticn system. Se remaining 9C0 gal were unaccounted for. With the basin water activity at about 6 x 10 4 uC1/m1, the unac-counted fer water centained about 2 =C1 total activity. The average of sa=ples taken from the basin during this period shewed Cs-134 to be 2'x 10 2 uCi/sl, Cs-137 3 4 x 10-4 uC1/=1 and Co-c0 2 x 10-3 uCi/sl. "h.: ring the 4-heur period on June 19 when the first te=perary ;atch failed and was replaced, approximately 200 gal of basin water centaining less than 1.0 :Ci was unaccounted for.
- uring the '-hcur peried when the seccnd tecperary patch was recove and the cermanent repair was accomplished, approximately 1000 gal of water with con-tamination of approxi=ately 3 :Ci was unaccounced for.
Se total unaccounted-fer leakage during the repai. period was approximately 2500 gal. Se disposition of this water, containing an est:. sated 5 :Ci (primarily Cs-134 and C3-137), is cet k cwn with certainty. It is assused that mes t, if not all of this water re=ained within the confines of the structure and is centained in minute fissures er flaws in the cenerste of storage basins and process cells. "f this water did leak cut of the structure, its probable disposition can be explaine as follows: 9 During construction of the facility, explcsives were used te excavate the rock l formatics for the deep structures. "'his blasting fractured rock formations 1:=e-diately adjacent to the deep structures. Water accu =ulates to sc=e degree in I the fractured rock. Perched water also collects from precipita:icn at varicus l levels in these fermations. The fracticn of precipitation that enters the perche water :enes is not kncwn. However, a small frsctica is sufficient to cause a large amount of dilutten of any leakage from the basins. For exa=ple, approx-imately 6.3 s1111cn gallens of precipitatien falls en the protected area n an s 3-8 -- -.-.-.1
NEDo-21326c3 January 1981 average year (<33 in. annual average rainfall ever an approximate 550-f t x 550-e ft area). 7.f
- 0". of this rain entered the perched water reservoirs and if the 2500 gallens of unaccounted-for water is assumed to have leaked frem the struc-ture and uniformly mixed with the perched water, the dih:10n facter would be approximately 250.
- ests hdicate that there is no significant cennecticn be-tween the perched water formation and the aquifers supplying water for dc=estic or agricultural purposes.
Rese aqttifers are located far belew the perched water
- enes and if contaminated water did leak from the structure, it is unlikely tha:
it wculd ever sig: ate to the 10wer aquifers. It is = cst probable that the basin water would be captured in the perched water ::enes, becoming =cre diluted and gradually dispersing. Bere are no known water wells in the area that tap perche water :enes (other chan Merris Cperation and CNPS sac:ple wells). 3.3 1.2 Monitoring ?regra.m Results bmediately af ter the beident, three wells were monitored for radi0 activity. An addittenal well was drilled 100 ft northeast of the flucrine building to determine if any :adicactive :aterial was migrating Scward the inhabited 00t-tage area. Se wells were not pu= ped before taking a sample. Consequently, sa=ples were taxen from stagnant peels. Se wells were sa pled cnce a day frc: June 12 to June 21, 1972.. Afterwards, through August 14, the wells were sampled twice a week and, currently, sa=pling is dene Once every 2 weeks. 3 additien, the main water well for the plant has been sa= pled several ti. es since the incident. Se analyses of all samples taken 1::dicate no activity above background levels (<0.5 cpm /ml). 3.3 1 3 conclusiens Recovery frem the incident was rapid and successful. Se liner was repaired by welding a stainless steel plate over the damage area. Cor: ective actions - to avoid similar problems were pro =ptly initiated and included: i d I i ) l l 3-9 t
NEDO-21326C3 Jcnuary 1981 8.11 L M IC~a A1 Accceding to recent studies in the U.S. and acread, significan: evidence has accu =ulated to indicate tha: the consequences of a hypothetical fuel =elting accident =ay be less than currently predi::ed by a:.sas
- ne or two crders of =agnitude; see staff reports, Appendices E, ?, and G, Report of the Presi-dent's Cc=missien on the Accident at Three Mile Island.
,1. C. V. Mcore, Design of Barricades for Hazardous Pressure Syste=s, Nucisar Engineering and Oesign (1967). 2. Sandia Laboratories, Full-Scale Tornado-Missile Impact Tests, 'uly 1977 Electri Pcwer Research Institute Reper: No. EPRI NP 420. 3. See Subsection 5.6.3, Design and Analysis Reper of the IT-300 Shipping Cask, GE Occu=en NEDC-1C08h-1, Decke: 70-1220. 3 N. R. Horten, 'd. A. '41111a=s, and J.
- 4. Holt:elaw, Analytical Methods f:r Evaluating the Radiological Aspects of the General Electric 3 oiling " dater Reactor, March 1969 (APED-5756).
5. RESSAR 21, April 1974 6. Attenuation in ' dater of Radiation from the 3ulk Shielding Reac:ce: Measure-ments of the Ga==a-Ray Jose Rate, Fast-Neutron Ocse Rate and Ther=al Neutron Flux, July 8,1958 (ORNL-2518). 8 40
E NEDo-21326C3 January 1981 t 9236 Senio'r Engineer - Licensing and Radiolegical Safety i j n The Senior Engineer - Licensing and ?.adiological Safety reports to the Manager - Morris Cperaticn and is respcesible fer coordinating site regulatory sat:ers with local, State, and Federal regulatory agencies, and directing the site ( ) enviren= ental pregram activities. O.e incumbent reviews facility and operating i 1 procedure changes to determine the need for a nuclear safety review and reviews 'I fuel data to assure ecnfermance with criteria fer fuel storage. 9237 Plant Safety ccmmittee t i In additien to the organination shown in Figure 9-2, a plant safety cc-" ttee is established within the Morris Operation. Plant Safety Oc=mittee =e@ers f include : Manager - Plant Cperatiens; Manager - Plant Engineering and Maintenance; f r Manager - Quality Assura:re and Safeguards; Plan: Safety Supervisce; and Senior Ingineer - Licensing and Radiological Safety, who serves as the ec==ittee secretary. l t ~he Manager - Morris Operstien ner:sily will be a se=ber of the cc=mittee. ".0w-t i ever, at his discrecien, when ite=s of particular significance are being censidered j (e.g., in the evaluatica of a major operaticnal safety matters and develop =ent t of recommended changes in facilities er procedures affecting safety =argins), l he serves as chair:an of the ec==ittee. l 1 The Plant Saf ety Cc==1ttee exercises jurisdiction over those =atters having radiological or nuclear safety implications, with.~! view and appreval authority. f i 9 2 3.3 Trained and certified Personnel l I + l General Electric has, and will =aintain at its Morris Cperation, an adequate f complement of trained and certified personnel to operste the facility. t 1 93 TRLTNG PROGRAMS i C k To provide and =aintain a flexible, well-qualified werk force for safe and l I efficient operation, a comprehensive training program has been i=ple=ented. I Training includes: j t l 6 h i l 9-7 I 1
1 l l NEDO-21326C3 l l January 1981 O i a. Orientation and Indoctrination j 1 j l b. Radiation and :ndustrial Safety c. Security / Safeguards i i I I d. Emergency Brigade Training. l l l e. Quality Assurance f. Basic Plant Facilities and Organination g. Fuel Receiv.ng and Storage Operations h. Utilities and Opersting Syste=s These training pregrs=s are adapted frem the pregr2=s criginally prepared for fuel reprocessing operstier.s and are believed to be =cre cc=precensive than wculd ncrmally be required for Pael storage functices, only. 1 ?.e amount of training and retraining eacn indi7idual receives is directly related to his function. All personnel are ;revided genersi crientation 0 urses which include description of the Merris Operaticn and its functions, plant ) i safety considerations, security requirements, and emergency plans and general procedures. 9.3.1 Cearster Qualification. Trsining, and Certification All personnel assigned duties involving operation of systems and equipment directly related to sevement of casks, Icading er unleading of casks, movecent of fuel, operstien of basin water ecoling er cleanup systems, esdicactive waste nanagement operati:ns, and other activities in the task receiving and P.:e1 storsge areas, including operstions supervisory persennel, shall be trained, tested, and certified by General Electric as qualified to perform specified duties under a program approved by the UStGC. ./ 9-3
NGO-21326C3 January 1981 9.4 NORMAL OPERATIONS 9.4.1 Plant ?recedures Plant precedures are discussed by tatescry in the fcilewing paragraphs. 3 ste=s / and equip =ent requiring personnel certified for specific Mncti ns :37 be oper-ated by concertified personnel only if under the direct visual supervision of an individual trained and certified for the specific operation. 9.4.1.1-Morris operstien Instructicas (MOI's) A system of specific written instructions provides guidance and directi:n for performance of Morris Cperation activities. Se instructions provide for proper safety, quality, and functicnal censiderstions in the planning and i=ple=entation of plant activities, including ad=inistration, licensing, plant engineering and aintenance, =aterials, cperaciens, quality assurance, safeguares, safety, field serviees and transportation. 9 4.1.2 Standard Operating Procedures (SCP's) Operat10n of Merais Operstion facilities are in accordance with a system of Standard Opersting ?rocedures designed to provide detailed guidance and con-trol fer all anticipated ccnditiens. Individual precedures are ;repared by the Plant Operations Unit and approved by the Plant Safety Occ=1ttee before being implemented. The Plant Operations Unit is authorined to =cdify standard procedures en an interim basis as requimd to cover specific ccaditions arising during operstiens. Standard Operating Procedures are modified only after due censiderati:n of the safety implicatiens of the change. Opersting activities are monitored en a shift-by-shift basis by the supervisory staff for ccepliance with Standard Opersting Procedures. 9.4.1 3 Safety Manual To provide the necessary control of work involving icnizing rsdiatien and radicactive =aterials, a system of ~adiation protectica standards has been developed and documented in the Safety Manual. De Manager - Quality Assur-ance and Safeguards is resocasible for the overall administration of the 9-9
NEDo-213:16C3 l January 1981 requirements set forth is the Safety Manus 1. Ceviation frem the established requirements may be required from ti=e to time.
- hese may be On a planned basis, under special :perating 00nditi:ns, Or :here may be deviations required by emergencies.
Planced deviatiens must have prior approval of the Manager - Ouality Assurance and Saf eguards er his delegated representative. -=ergency deviatiens rust be reported prc=ptly to the Cperation Supervisor en duty who, in turn, notifies the Manager - Quality Assurance and Safeguards. 9 4.1.4 Special '4cek Procedures Special work precedures for cases bvolving ncestandard operatiens include l =cdificatiens to standard cperating precedu es and supple = ental Operating instructions, prepared f:r 6:eris use en a centrolled basis and based en specific evaluatien of safety impli:ations. ~here are definite :i=e '
- ts on such apecial authorizaticas during vnica Off-standard condi; ions are to
~ be corrected or established require =ents revised. Special verk precedures are approved by Ouality Assurance and Safeguards, Plan: Operations, and the I unit performing the wrk. B I 9 4.1 5 Regulated '4crk Procedures l i An essential ele = enc of the systems for control of plant safety is the require-f that formal autherbation ' e provided for all cperating, maintenance er ment c repair activities which involve potentially hazardcus cenditiens, i.e., work i in radiatien er centaminated areas. ':he Regulated '4crk Precedure system is i desigrad to assure that such work is accomplished in a safe and efficient =anner i [i in accordance with the standards ar4 requirements set ferth in the Safety Manua*.. i I 1 Regulated '4crk Procedures document prescribed requirements and limits for special j work to be observed prior to beginning each task. Responsibill y for the procedurai system is assigned to the Manager - Quality Assurance and Safeguards, boluding provisions f r shift-by-shift scnitoring of activities for ccepliance with Ocntrol l t requirements, and =aintenance of necessary records of such activities. Regulated } '4crk Procedures are approved by the Plant Safety Ccc=:ittee. i ) 4 s I t k I 9-10 l
!EDO-21326C3 January 1981 9.4.1.6 Equipment Maintenance Fregrams A '4crk Request Systen is e= ployed at the Merris Cperatien for initiating requests for =aintenance, preventive saintenance repairs, =cdificaciens, al: era-tiens and new ins:allati0ns. *derk Requests are reviewed by Plan: Engineering and Maintenance, Plant Operations, and Quality Assurance and Saf eguards for conformance to plant procedures and instructions. Equipment =aintenance is performed in accordance with =anufacturer's recommended practices and operating exp erience.. Overall responsibility for equipment maintenance is assigned to the Manager - Plant Engineering and Maintenance. Assistance is provided by other plant operating cespone~nts, as required, to assure that safety and oper-ability criteria are ccrrectly interpreted and perfor:ance capability =aintained. 9.4.2 Records and Recerts Cc plete files of activities relating to plant safety are accu =ulated to { demonstrate the adequacy of design and construction safety censidera:icns and to assure censistent application of safety principles and objectives to plant operation and maintenance. 9.3.2.1 Record Retention Cccumented records of plant safety assurance activities are maintai.wd :o descastrate that control requirements have been :et, including the precedural l system decu=entation and cc=pliance records noted in the preceding ;aragraphs; environmental scnitoring program reports; personnel ex;caure data and regu-latcry activity files. 9.4 3 Facility Modifications Major sedificaticcs of Mer-is Operation facilities (these related to nuclear safety) an subjected to a ecmprehensive evaluatica and analysis in accordance with SFSO precedures, which provide a formal program for design review and quality assurance. Mince modificaticas and tests and experiments are performed under provisicca of Section 9.4.4 9-11
1 NEDO-21326C3 l January 1981 9.4.3 1-Safety Evaluation.and Project Pi= M ns 1. When a major =cdificatica er project is proposed, a study of the cencept develops i technical criteria and preT
- i r.ary specifications, as well as other data :ucessary l
for a prei!mdnary satety evaluati'en (1, Figure 9-3). mis evalua,1cn is perferned by a function within SFSO (Licensing and Transportation) that is separated fres organizaticnal components directly involved in the proposed project. activity. F.ngineering data *nd recommendations frem other SFSO components are censidered in this evaluation, including recc=mendatiens from the Plant Safety Cc=mittee. ( The evaluatien determines the' need fcr licensing action, as well as special studies cr other evaluatien of the proposed activity. i s Se technical crit. aria, safety evaluation, and other data (such as ince=ing fuel scheduling, =anpower availability, etc.) form the basis of a project plan I developed by Fuel Storage Projects and ccordinated with the Morris Operation. ~n seme cases, the project will be executed at Morris Cperation without further
- articipatica by Fuel Sterage Projects.
Se plan is presented to manage =ent of SFSO and NE?D for approval. '4 hen all administrative and technical requirements have been satisfied, a project authorization is issued by Manager - SFSO. i ~ t i 5 i i t I I 9-11a
NEDO-21326C3 January 1981 9.4 3 2 Project Design Activity e Nuclear safety related and najer des;.gn projects are conducted by Fuel Stor2ge ?rojects, with suppert furnished by Morris Cpei*ation for those requirenents that can best be satisfied at that location. Design activity (2, Tigure 9-3) results in established functional classifications, specificati0ns, drawings, j and other documentation, all subject to an intensive review. Each docu=ent is reviewed by all appropriate organizations within SFSO, including Morris Operatica, with requirements that each organination approve the dccument prior to issue. The varicus f.eatures of the design are also subject to engineering reviews, including design verificatica reviews. Throughcut the design activities, Quality Assurance Progr?ms personnel nenitor and check ccepliance with the quality Assurance Plan, especially the i.nspection and senitoring of vendor and centractor ac 171:1es. 9.4 3 3 Licensing Activity Depending upcn the centent and nature of the project, Licensing and Trans-portatica say provide an envirennental -eport, final safety analysis report, and special safety studies (3, Figure 9-3). Special safety studies =ay be 3 requested by Fuel Storage Projects, by quality Assurance Programs or by other nanage=ent including Manager - Morris Operation. Management and personnel at Morris Operation provide cor *tbutiens to licensing activities, especially in health physics and envirc' .a1 fields. Licensing activities continue as necessary to obtairt regulator 7 approval of changes er :cdificaticas where required. 9.4 3 4 Project Completion 5 the case of a =ajor project, a Fuel Projects Engineer will be assigned the project responsibility for conserv stica, installation, testing, startup, and related activities (4, Figure 9-i). ~he Ma::ager - Morris Operation retains full responsibility for.the safety of all other activities uvolving receipt, j transfer, ce storage of nuclear.'\\:el or other rad 10 active =aterials, including operation of the facility during sodification. 9-13
NEDC-21326c3 January 1981 The Merris Cperation will furnish supporting services, liaison with local 1 govem=ent agencies, etc., as may be required. ~he project and site manage-ent tea =s coordinate activities during projec execu:icn to achieve Outual goals in accomplishing both project and operational activities. Plant Prece-dures for the new facility ce functicn are developed and imple=ented as described in Section 9.4 Upon ecmpletion of startup and turnover operations, all project decu=enta.tien is ce=pleted and filed (both Merris and San Jose sites), and responsibilit',' for the new facility or.^anction assumed by Mor:is Cperation. 9.4 3.5 Audits and Reviews ?clicies and resulting requirements established f0r Mor-is Cpers:1cn require periedic audit, and review of the varicus aspects Of fuel s:crage rativity. General Ocpics fer audi: include:
- Nuclear criticality safety e ?.adiation protection e Physical security E=ergency plans
+
- Envircnmental protection t
+ Ouality ' sternal audits are conducted by Morris Operstion =anagement in safS6uards, i criticality, a:d -adiatica safety. Formal audits and reviews are cenducted i by teams fecm other Nuclear Energy Group and SFSO compecents in accordance l with established Group and SFSO ?c1(cies and Procedures. i l i 1 9-14
NEDC-21326C3 Jantsory 19G1 9 4.4 Changes, Tests, and Experiments f' Changes in the facilities described in this report er precedures described in this repcet, and tests er experiments not described in this report related to receipt, storage, and transfer of spent fuel, may be performed without prior approval of the Nuclear Regulatory C0cmissien provided that such changes, tests, and experiments do not involve significant unreviewed nuclear safety or environ- = ental issues, ccr require a change in Technical Specifications or other license cenditiens. ~hese activities are cet. ducted under provisiens of 10 CFR 72 35. bplementation of such changes, tests, and experinents is accomplished as directed by applicable procedures. 2 general, the procedures require an appropriate analysis and evaluatien, with cencurrence in proposed activity by appropriate Morris Operation and SFSO staff functions, and license a=end:ent activity when appropriate. 95 EMERGENCI Pl.M S 9.5.1 Purpcse and Scope l bergency plans are established and personnel are trained in e=ergency procedures so that effective actions can be taken under the stress of e=ergency ccnditions. The interrelated emergency plans for Merris Operation are diagraced in Figare 93 2:e plans and procedures related to radiological emergencies are enclosed within the dashed line. (~he Physical Security Plan and related provisions are not discussed in this document.) 1 e s 9-15
=_ NEDO-21326C3 Janucry 1981 Emergency plaening at Morais Operatica is related to the everall emergency r~ planning of General Electric's Nuclear Inergy Group, and.mdiological assis-tance plans of the State of. Illinois and the Depart =ent of Inergy. An a.iange-nenc has been esablished between Morris Operatica and Cen=enweal,h Idison (Cresden Nuclear ?cwer Station) for nutual assistance in acergency situaticns. Likewise, e=ergency assistance arrange =ents have been nade with law enfcrce-nent, medical, acd other 1ccal agencies and services. l* s s 'See Section 9 7 for references. J 9-17
9 i NEDo-21326C3 January 1901 10. OPERAnCN SPECI.N.CACCNS t' ' In accordance with requirements of 10 CFR 72, l propcsed technical specifications for Morris Operstion have been submitted to the USNRC. I t Therefore, Chapter 10 has been deleted. j i t e l l ? i l i l I e t I 4 I l 1 l l ? I I I I l l s I 1 i i l 10-1/10-2 1 ..-.-.-,._-i
i NEDO-21326c3 1 January 1981 11. QUE'"! iSSURANCE l l r' 11.1 DIT3CDUC ICN he activities at Morris Operatien are ccnducted in accordance with a quality j assurance plan reviewed and accepted by the USNRC and implemented by instructiens and precedures at the Morais facility. Se quality assurance plan is docu=ented as Spent Fuel Services Cperatien Quality Assurance Plan (NEco-20775). A microfiche copy of this plan is included in this repert. { 11.2 QUm*"I ASSURANC2 HISTCRT I '"he initial design and ccustruction of the Merris facility as a ^ael reprocessing r plant came under a quality assurance progran developed by General Electric.
- uring the construction pericd, the USAEC - then the regula: cry agency --
increased i:s emphasis on the specific sethods of achieving quality assurance, preposing amend =ent of 10 CFR 50 c include Appendix 3, "Cuality Assu m ce l Criteria for Nuclear ?cwer ?lants." i 3efers Appendix 3 was published, General Electric had incorporated quality assurance i provisions inte the over-all safety assurance pregrss for the reprecessing plant. Except fer specific requirements related Oc documented record accumulation, the j key elements calld for in the then-proposed a=endment (as applicable to fuel [ i reprecessing facilities) had been included in the General Electric pregram, which was dccumented in Supplement 3 to the "tesign and Analysis Reper: - Midwes: Fuel I Recovery Plant." Construction of the facility was ccmpleted under this pregram. ? f Af ter the decision not to operate the facility as a reprecessing plant, but j I to centinue fuel storage operations, General Electric proposed the installation i t of a new fuel storsge system. 21s system was licensed by USNRC in December 1975. Se design, fabricatica, and installation of this system were perfer:ed j under the current quality assurance plan, which is in acccrdance with applicacle l requirements of Appendix 3, 10 CF3 50. t i I l i f i l t i l f l 11-1 I
MED0-21326C3 January 1981 W 11 3 STRUCTURES, SISTEMS, mfd COMPONENTS IMPORTANT TO SAFE ~f ,~ The structures, syste=s, and cc=ponents i=portant to safety are listed belew, with a basis fer designation. a. Fuel storage basin - cencrete walls, fleers, and e:q:ansien gate. Se basin's cencrete structure is a principal elecent in protection of stored fuel, and in the isolatien of basin water frem the enviren=ent. b. Fuel storage basin - stainless steel liner. Se liner for=s a second element in fuel protection and basin water isolatien, facilitating decenta=ination. c. Fuel storage system, including baskets and supporting grids. ~he storage system is a principal ele =ent in protection of secred Pael. d. Unicading pit decrway guard. Bis device is designed to prevea.: a leaded fael basket f.~;ct being tipped so that fuel bundles cculd fall inte the cask unicading basin. The unicading pit decrway guard is an ele =ent in protection of fuel during =cvement of leaded basket. s. Filter cell structure. The concrete cell, part of the basin pu=proce area, provides radiatien shielding to reduce occupational expcaure. t l l 11-2
NEDC-21326C3 Jenuary 1981 A.7.5.2 Shipping and Disposal Cests Shipping and burial ecst esti=ates include the 1973 costs of shipping centainers (ncnreusable), transpectatien fees, and burial charges at a icw-level waste dis-i pesal site. De cost estimate includes weights and volu=es of =aterials based on past experience of the Morris Cperation. ~he transpectation costs assu=e [ e that the waste will be trsnaported to the Hanferd Reservation near Richland, l Washingten. l 1 i Disposal of " clean" =aterials is not included in the costs shown in Table A.7-3 l since acccontaminated ite=s are not addressed in this plan. (See Secticn A.7 2.2.) I i A contingency of 25% cf the decc=missioning ecs: (Table A.7-3, Tasks 1 threugn 4) l t was included in the total ecst shcwn. i l A.7.5 3 Firaccial Assurance l i i I The decommissiening cests fer Genersi Electric's irradiated nuclear fuel storage j facilities near Mer-is, Illinois, estiaated to be 36,033,000, are s=all compared to the total assets of the General Electric Company. herefore, it is unlike17 'l that General Electric would be unable te meet the financial ec=mitments generally f associated with the deccc=iss10ning activities as Outlined and estimated. t i i L 1 Cn April 15, 1980, Dr. Bertram Wolfe, Vice President and General Manager, Nuclear Fuels and Services Divisien, General Electric Company, submitted a letter to the i i Nuclear Regulatory Commissica ecccerning financial arrsngements for deccmmissioning ) the Merris Operation. This letter is reproduced in Figure A.7 *. t Dy action of the Board of Directers in seecing on April 27, 1979 (Minute 196t0, April 27,1979), a 71ce President of General Electric Cc=pany ay execute such an obligation en behalf of the Company. A copy of this action of the 3 card was attached to Or. Wolfe's letter of April 15. I i L i l A. 7-1i4 l s
s _ NEDO-21326C3 ) Janua./ 8981 i G ENER AL h ELECTRIC CCNCRAL C's.IO~RIC COMPANY l i7s cuat=cm AvcNu c sam.ose. Aurcam.A asias l 1 I 3 m. s tm?s AM wC Lrt vist se gai.sur amo es sa46 ina=4ese l ..~......c......... i April 15,1980 i i 1 J Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory C0mmission Washingt:n, D. C. 2C555 Attention: R. E. Cunningham, Director Fuel Cycle i Material Safety
SUBJECT:
FUNDS FOR DECCMMISSIONING MCRRIS OPERATICM Cocket No. 70-1308 i Gentl emen: I t General Electric's general revenues anc retained earnings, as snuwn by the 1979 annual report, are sufficiently large tnat, at the time of decommissioning, General Electric will have available the resources deemed necessary to satisfy its obligation to decommission its Morris i Oceration near Merris, Illinois used for the interim st: rage of s:ent fuel. 7he dec:mmissioning of the Morris Operation will ce carried cut by General Electric in ac::rdance witn tnen applicable feceral laws anc regulations, i Attached is a copy of General Electric's Boar: Resolution 59640 i dated April 27, 1979 concerning the execution of contracts and otner instruments which authorizes a Vice President of General Electric i Company to sign this letter. i i Sincerely, ) i i .s ' )p. lu m W W<L l I t I Attacnments i I Figure A.7-1. Letter fran Or Bertram Wolfe, 71ce President and Genersi Manager, Nuclear Fuel & Services Division, l Regarding Financial Arrangemenes for Decommissioning j i i Merris Operation i A.7-15/A.7-16 i,
cp. i to CC 1pC Q [ ATTACHMENT H Ic ,,gNOM G.) % $ a *" f W'I A
- 3 D PROF 0 SED TECHNICAL SPECIFICATIONS h*
f W ( 0., N: ~
1.0 INTRODUCTION
w/ s % M-The tecnnical specifications and other license conditions in tnis document govern 'the receipt, possession, storage, and transfer of irradiated fuel from light water reactors by Morris Operation. Operation of the Morris fuel storage facility cannot result in a sudden, large release of radioactive materials or high radiation levels even under those i credible meteorological and seismic conditions that have been considered in I the design basis of the facility. The consequences of accidents have been analyzed and found to have insignificant environmental effects.' In summary, there are no credible events that could cause a release of radioactivity that would pose a danger to the public.* [ 1.1 DEFINITIONS l T.5e following definitions apply for the purpose of these technical specifications: a. Administrative Controls: Provisions relating to Iorgani:ation and j management, procedures, record keeping, review and audit, and report-ing necessary to conduct activities in a manner consistent with technical scecifications and applicable government regulations, j b. Desian Features: Features of the facility' associated with the l basic design such as. materials of construction, geometric arrange-l ments, dimensionc, etc., which, if altered or modified, could have a j detrimental effect on safety, j c. Functional and Ooeratino Limite: Fuel handling and storage condition.s l required for normal oceration of the facility. l d. Fuel Bundle: The unit of nuclear fuel in the form that is charged or i discharged from the core of a light water reactor (. LWR), Normally, j will consist of a rectangular arrangement of fuel rods held togetner by end fittings, spacers, and tie rods. The SWR fuel bundle does not include the fuel channel (which is. reusable and not shipoed with fuel { badles). e. Limitina Conditions: The lowest functional capabilities or per-formance levels of equipment and systems for safe operation of the I facility.
- 3ee 3ec:icn 7.2 of :his docwen: for references ar.d notes
H-2 f. Surveillance Reouirements: Requirements for monitoring, sampling, testing, calibrating, or ins:ecting fuel in storage, equiccent and systems to demonstrate that functional capabilities or performance levels are maintained as required for normal operation of che facility. g. Tonne (Te): One metric ton, equivalent to 1000 kg or 2204.6 lb. Fuel quantity is expressed in terms of the heavy metal content of the fuel measured in metric tons and written TeU: formerly MTV. 1.2~ GENERAL LICENSE CONDITIONS 1.2.1 Authorized place of Use The irradiated nuclear fuel, as described in Section 2.0, is to be received, possessed, and stored at the Morris Operation located in Grundy County, Illinois, near Morris, Illinois. This site is described in Chapters 1 and 3 of the " Consolidated Safety Analysis Report for Morris Goeration", NE00-21326C-series revisions. 1.2.2 Quality A:surance Activities. at Morris Operation shall be conducted in accordance with require-ments of Appendix B,10CFR Part 50, as described in Spent Fuel Services Oceration Quality Assurance Plan, NE00-20776, as revised. (,Oe Acpendix 3.3 of the CSAR). 1.2.3 Fuel Transfer Canal Closure The upoer end of the transfer canal (CSAR Figure 1-5) has been sealed by welding a stainless steel plate,1/4 inch thick, to imbedded steel angles framing the opening. There are no protrusions from the plate that could be used to facilitate l removal. The fuel basket transfer arm has been rendered inocerative by welding a block in place to prevent arm move:1ent, and by disabling the arm hydraulic system. These conditions shall not be changed without prior soproval by the Commission Staff.
- Eeveafter referred :o ca 9.e C32 l
i .O
9 D H-3 1.2.4 Fluorine Facility The fluorine facility, part of the fuel reprocessing facilities, has been dis-mantled and shall remain inoperative. 1.2.5 Radioloaical Emergency Plan A radiological emergency plan for the facility shall be established and main-tained in accordance.with 10CFR72.33(f). 1.2.6 Physical Security plan A chysical security plan for the facility, including a contingency clan and a plan for qualification and training of security personnel, shall be estaalished and maintained in accordance with 10CFR73. 2.0 FUNCTIONAL AND OPERATING LIMITS Functional and operating limits applicable to Morris Operation are founded on the basic assumotions of the safety analysis and the design of the facility. 2.1 AUTHORIZED MATERIALS 2.1.1 Saecification a. Light water reactor nuclear fuel to be received and stored at Morris Operation shall meet the following requirements: '1) Fuel shall contain uranium as uranium dioxide (UO ) 2 enriched not greater than 5 percent U-235. (2) Fuel shall be clad with stainless steel, zirconium or :ir-conium alloys. (3) Maximum average exposure of reactor discharge batch (fuel) shall be 44,000 mwd /Teu. l (a) Fuel shall have cooled a minimum of one year after reactor shutdown and prior to receipt at Morris Operation. (5) Red lattice k, limits without allowance for burnup sna11 not exceed: o 1.37 for 15x15 PWR (<8.55 inches square) o 1.38 for 10x10 BWR (<5.65 inches square) l .y .,.r,y ,_r.. .-y...- ..r,.ew.
H-4 i o 1.40 for 7x7 or 3x8 SWR o' l.41 for 14xid pWR (<7.80 inches square) b.- Fuel parameters.shall be within the ranges defined in Figures 2-1 and 2-2, or as otherwise specified ir this l specification. ] (1) Morris Operation is authorized to store stainless steel l clad Lacrosse 10x10 BWR fuel pellet diameter of 0.35 inch, a pitch of 0.56,5.and enriched to a maximum of 3.93% U-235. t c. The combined quantity of unirradiated natural uranium and un-irradiated depleted uranium at the Morris Operation facility shall j not exceed 42 Te.2 { d. Instrument, calibration, and laboratory sources may be :ossessed l within the limiting amounts given in Table 2-1. t 9 l { l. S t i
I k H-5 e. Tools and equipment incidental to the conduct of General Electric's nuclear and nuclear-related business which have become contaminated with radioactive materials may be possessed. Items bearing smearable contamination shall be packaged for stor-age. The total contamination of all tools and equipment shall I not exceed 10 Ci as determined by external exposure from the l items as packaged for storage. f. Tools and equipment specifically related to the conduct of fuel j storage operations, such as shipping cask internals, which have i become contaminated with radioactive materials may be possessed. l l Table 2-1 l AUTHORIZED MATERIALS - I?lSTRUME?lT, CALIBRATIO?l, A?ID LABORATORY SOURCES Chemical and/or i Material Physical Form Quantity Radionuclides with Solution or Total aggregrate j atomic numbers ranging calibration disc of 5 curies j from 1 to 83 Cobal t-60 Sealed source 10 curies Cesium-137 Sealed source 10 curies Thorium-230 Any 1 millicurie ?teptunium Any 20 grams j Plutonium Any 50 grams { Uraniutt. 235 Any 250 grams (in uranium of any i enrichment) i Americium-241 Any 200 uCi j Americium-241 Sealed source 40 curies j Plutonium-Seryllium Sealed source 2 curies l Uranium-natural Any 15 kilograms l 2.1.2 Basis The design criteria and subsequent safety analyses of the Morris Operation assumed certain characteristics and limitations for the fuels that are to be i received and stored. Specification 2.1.la assures that these bases remain i valid by defining the allcwable fuel form, cladding, k. and irradiation history. l i i 1
H-6 i Specification 2.1.lb establishes fuel parameters referencing graphical and other criteria. The fuel requirements establish criteria (including k ) for fuel to be stored to protect against an accidentai riticality. For the most reactive conditions credible k for :ny array af stored fuel must be less than 0.95 f eff at 2e 95P. confidence level. l l The design bases for criticality analyses were selected from detailed analytical studies which were based on the physical parameters of specific fuel designs (see Table A.10-1, CSAR Appendix A.10). The largest bundle cross-sectional areas and infinite bundle length were assumed in the calculations. These limits were based on unirradiated, clean fuel and include allowance for the poisoning effect I of the-stainless steel baskets. Fuel centerline locations and other orientations were assumed to be those giving the maximum system reactivity. Figures 2-1 and 2-2 provide k.,, as a function of fuel enrichment and reactor type, as well as correction factors for principal variables affecting k,,: the pellet diameter, the water-to-fuel ratio, and the cladding material. Other fuel con-figurations that have been analyzed and reviewed separately may be excepted from the limitation of Figures 2-1 and 2-2, as referrtnced in Specification 2.1.1b. Specification 2.1.lc defines the allowable quantity of unirradiated natural and depleted uranium to be received and stored. Specification 2.2.1d authorizes possession of various isotopes to be used for instrument and calibration sources. Specification 2 l.le provides for storage of tools and equipment incidental to the conduct of General Electric nuclear businesses wnile awaiting decontami-I nation, reuse, or ultimate disposal. Activity will be back-calculated from l measurements of the highest exposure rate at 3 ft from a package, assuming that the radiation originates from a uniform volumetric source having approximately the same dimensions as the package. Unless otherwise determined, gamma emissions of 1 MeV/ disintegration will be assumed. i l l
H-7 Specification 2.1.lf provides for storage of tools and equioment specifically a related to the conduct of General Electric fuel storage operations, such as cask { internals and yokes, while awaiting decontamination, reuse, or ultimate disposal. These tools and equipment may be contaminated with Co-60, Cs-137, or other isotopes as encountered in fuel handling and storage activities. f i 3 2.2 FUEL STORAGE PROVISIONS { 2.2.1 Specification l I Irradiated fuel bundles shall be stored in authorized fuel storage baskets, mounted in a support grid, under water in a fuel storage basin. f 2.2.2 Basis i The design criteria and subsequent safety analysis for Morris Operation assume irradiated fuel is stored under water in f 2el storage baskets, mounted in a supcort l grid in a fuel storage basin. Specification 2.2.1 assures that these assumotions t remain valid. The fuel storage baskets and support grid are those described in CSAR Chapter 5, 3.0 LIMITING CONDITIONS The limiting conditions described in this section apply to normal operation of l the Morris Operation facility. If a limiting condition is exceeded, plant pro-cedures require action to return operations to within specification requirements. l None of the limiting conditions are crucial to public health and safety, or the health and safety of site personnel. 3.1 ' LIMITING CONDITION - WATER SHIELD I i 3.1.1 Soecification l The depth of water between the uppermost part of a fuel bundle and the surface of the basin water shall be a minimum of 9 ft. 3.1.2 Basis This specification establishes a minimum thickness of water shielding to limit radiation from the fuel stored in the basin area., This specification applies to all fuel in storage or being transferred from cask to storage location. ( Also, see Section 5.2). j I
~. ~ ~ A H-8 Tests have shown that the dose rate at the water surface does not increase above background until the water thickness is decreased to about 7 ft. A conservative water shield thickness of 9 ft (2.74m) has been chosen to provide an increased margin of safety. 3.2 LIMITING CONDITION - CRITICALITY j 3.2.1 Soecification A structure (unloading pit doorway guard: CSAR Figure 5-3)# shall be used at the doorway between the unloading basin and Storage Basin No. 1 to crevent a basket from tipping in a manner such that its contents may be emptied into the unloading basin. [ 3.2.2 Basis The analysis of a fuel basket droo accident (CSAR Chapter 8) indicates that a basket dropped or tipped over in Basin No.1, near the doorway to the cask un-loading basin, could empty its contents into the unloading basin. It is assumed I that the fuel could conceivably fall into an uncontrolled, pote'ntially critical configuration in the bottom of the unloading basin. The unloading pit doorway t guard assures that a basket cannot emoty its fuel into the unloading basin. 6 4.0 SURVEILLANCE REQUIREMENTS Requirements for surveillance of various radiation levels, water levels, and f other physical quantities, as well as inspections and other periodic activities f to provide assurance of specification compliance, are contained in this section. l These requirements are summart:ed in Tables 4-1 and 4-2, from details contained in Sections 4.1 through 4.6. I i i i i i e -,-,n-~ ...,r- ,n-> ,-me-
\\ H-9 ) i i Table 4-1 SURVEILLANCE REQUIREMENTS
SUMMARY
a b Section Ouantity or Item Period '/alue 4.1.1 Effluent air W 3: 4x10~0 uCi/mi 5 4.2.1 Water-evaporation pond M 3: 10-5 uCi/mi 5x10-6 uCi/ml and sanitary lagoons 2: 4.3.1 Sealed sources, 3, y, n, x SA 2 3: 0.005 uCi Sealed sources - 2 Q 2: 0.005 uCi 4.4.1 Instruments (see Table 4-2) 9 4.5.1 Basin water coolers M 2200 dom /100 cm-smearable 4.6.1 Process steam bypass b 10~5 aCi/ml 4.7.1 Cask coolant identification b Water 4.3.1 Cask coolant o Not greater than 10CFR71.35(a)(4) [ 4.9.1 Basin water W pH:4.5 to 9.0 [ nan 0 : <200 ppm 3 Cl~: <10 ppm 4.10.1 Basin water W 0.1 <C1/ul 1 aAnalyses frequency: W: Weekly Q: Quarterly NR: Not Required SA: Samiannual M: Monthly A: Annual See text for requirements i b e ( r
H-10 Table 4-2
SUMMARY
REQUIREMENTS SYSTEM AND EQUIPMENT TEST CALIBRATION Op:rability 3 System or Equipment Testa Calibrate Basin Leak Detection System W M 1 AW Vault Leak Detection System Q NR LAW Vault Intrusion System M NR Cladding Vault Leak Detection System Q NR Area Radiation Mer.4 to r.s Q Q Criticality Monitors A Q a0perability test / calibration frequency: W: Weekly Q: Quarterly NR: Not Recuired M: Monthly A: Annual SA: Semiannual l
H-il 4.1 EFFLUENT AIR SAMPLING 4.1.1 Soecification Effluent air shall be continuously sampled for particulates at a location between the main stack and the sand filter. Samples shall be analyzed weekly for gross beta (S)' activity. The maximum value shall be a weekly average of 4x10-8 uCi/ml. 4.1.2 Basis This specification requires sampling of ventilation air leaving the sand filter to provide assurance that effluent concentrations meet regulatory requirements, with resultant off-site concentrations (calculated) within limits established by 10 CFR 20. The effluent air concentration limit established in Specification 4.1.1 assures tnat off-site concentration will be within 10 CFR 20 limits. The sampling and analysis program provides data for estimating the amounts of radio-active material released to the environment during routine or accident conditions. 4.2 EFFLUENT WATER SAttPLING 4.2.1 Specification Water in the sanitary holding basin and the evaporation pond shall be samoled at. leas.t on_ce_each month,and_ana,l'yzed, for gross alpha and beta radiation. The maximum concentrations shall not exceed 10-5 aci/ml beta and 5x10-6 no sam' ling of that pond is ECi/mi al'pha'ridiat' ion'.~' If 'eithe'r pond is dry, ~ p required. 4.2.2 Basis-Periodic sampling and analysis of Morris Operation effluents is prudent, even though it is very unlikely that any radioactive material would be present in i sewer effluent. The limits selected are for isotopes that are present at the l Morris Operation. o -e--- --,,.y v, -- --r e w -ma
H ) 4.3 SEALED SOURCES 4.3.1 Soecification Each licensed sealed source (not irradiated fuel) containing radioactive material in excess of 100 uCi of beta-gamma emitting material or 10 uCi of aloha-emitting material shall be tested for leakage at least once every 6 months, except that each source designed for the purpose of emitting alpha particles shall be tested at intervals not to exceed 3 months. The maximum level of removable (non-fixed) contamination shall be less than 0.005 uCi total for each source, using dry-wipe testing techniques. 4.3.2 Basis Surface contamination is measured to determine that a sealed source has not de-veloped a leak. The limitations on removable contamination are based on 10 CFR 70.39(c) limits for plutonium, but other provisions of this reference are not applicable. 4.4 INSTRUMENTATION 4.4.1 Soecification Systems and equipment shall be tested for operabil'ity and calibrated at least once during the intervals specified in Table 4-2. Calibration shall be performed in accordance with manufacturer's recommendations, and operational tests shall be performed to check alarm functions and demonstrate other operational features of the system or equipment. 4.4.2 Basis Bases for these test and calibration requirements are as follows: a. Basin Leak Detection System: Operation of this system ensures that a leak in the basin liner will be promotly detected, so that correc-tive action can be initiated. Since the operation of the system is related to the level of water in the detection system, the level Let point is checked and instruments receive periodic calibration. l l 1 l
H-13 I b. LAW Vault Leak Detection System: Operation of this system ensures that a leak in the LAW vault inner container will be promotly detected. ( Since a specific level is not involved, calibration is not required. t c. LAW Vault Intrusion System: Operation of this system detects external groundwater leakage through the concrete structure of the vault, and initiates pump-out action to prevent LAW vault flooding. Since a spe-cific level is not involved, calibration is not required. d. Cladding Vault Leak Detection System: Operation of this system provides for detection of water between the vault liner and the concrete structure, i with subsequent pump-out action. Since a specific level is not involved, calibration is not required. e. Area Radiation Monitors: The audible alarm syst,em for these monitors is tested (operated), and the alarm set point calibrated periodically to provide assurance of reliable operation within equipment specifica-tions, to alert personnel to radiation above preset levels, f. Criticality Monitors: The audible alarm systems for these monitors, which warn personnel of a criticality, are tested (operated) and the alarm set point calibrated periodically to provic? assurance of reliable operation within equipment scecifcations. t 4.5 COOLERS 4.5.1 Soecification Basin water coolers that are in servica shall be inspected at least once each month: The equipment shall be visually inspected for signs of leakage with a. the fans off. b. Random smear surveys for removable beta contamination shall be no mor !an i 2 2200 dpm/100 cm, 1 i i I m m r-. ,r. ,y,_,m.cm.., ,._fm ,,g,y.,wp-. ,,eq3.- 7-o ,, w ww. g, yym--e
I H-14 4.5.2 Basis Leakage could occur'in the coils or pioing of the fin-fan coolers, releasing l contaminated basin water to the environs. Routine visual and smear tests are made to detect leakage, f i 4.6 PROCESS STEAM BYPASS 4.6.1 Soecification e Whenever the process steam generator is bypassed and utility steam is suo-stituted for process steam to operate the low activity waste evaporator, con-i densate from the process steam condensate system returning to the utility boiler shall be sampled at least once each S hours of such coeration and analy;:ed for { { gross beta activity. The highest acceptable concentration so measured shall not exceed 10" uCi/ml. 4.6.2 Basis The sampling requirement helps assure that if radioactive material is released l in the condensate, it would be discovered quickly. 6 I 4.7 CASK C00LANTS 4.7.1 Scecification Water shall be the only liquid coolant permitted in all casks received by Morris Operation. Chemical additives to prevent freezing of the water are prohibited. l Gas-cooled casks may be accepted providing that they can be flushed and other-wise handled as a cask using water coolant. l 4.7.2 Basis The Morris Operation is not normally equipped to accomodate licuid coolants j other than water. 4.6 CASK COOLANT SAMPLING 4.S.1 Scecification The concentration of radioactive material in the cask coolant as determined by analysis of the coolant or first cask flush of an air-cooled cask, shall be less than limits specified in 10CFR Part 71.35(a)(A). If these limits are exceeded, the fuel in the cask shall be assumed to have failed, and action shall be taken in accordance with established procedures. I i r
H-15 4.3.2 Basis This specification provides for detection of off-standard conditions within a cask so that the need for special handling or other considerations can be evaluated. 4.9. BASIN WATER CHEMICAL CHARACTERISTICS 4.9.1 Specification Basin water chemistry shall be maintained as follows: Item Acceotable Analysis pH 4.5 to 9.0 <200 ppm NANO 3 Cl- <10 ppm i 4.9.2 Basis Basin water chemical characteristics are selected to maintain a benign environ-ment for stored fuel and equipment in the basin water. 4.10 BASIN WATER RADI0 ACTIVITY SAMPLING 4.10.1 Soecification Additional basin water cleanup measures shall be initiated if the concentration f of radioactive materials in the water exceeds 0.02 uCi/ml beta. Fuel receiving opera tions shall be stopped if the concentration exceeds 0.1 uCi/ml beta. The USNRC shal' be notified, and immediate measures taken to red'uce concentrat ans below 0.1 i d uCi/ml prior to continuation of fuel receiving operations. 4.10.2 Basis Periodic sampling of the basin water is required to assure that radioactivity levels remain as icw as reasonably achievable. The values selected are consis-i i tent with current decontamination practices. 5.0 OESIGN FEATURES The design features in the following section are those incorporated in the Morris { Operation facility for the safe handling and storage of irradiated fuel. h 5.1 FUEL STORAGE BASIN The energy-absorbing pad on the cask set-off shelf shall not be altered without f appropriate safety review and documentation. i I
~ 4 H-16 5.1.1 Basis - The cask drop accident was analy:ed for the IF-300 cask with the energy-absorb-ing pad in place (CSAR Chapter 8). 5.2 FUEL STORAGE SYSTEM The following pieces of equipment employ favorable geccetry, specific materials and methods of construction to assure nuclear criticality safety. Modifications to the design in dimensions, materials of construction, or construction. methods shall not be made without appropriate safety review and documentation. 5.2.1 Fuel Storace Baskets 5.2.1.1 Basis a. The neutron attenuation croperties of stainless steel are considered in the nuclear safety analysis, b. The structural strength, as fabricated, is considered in seismic arid tornado accident analyses and is related to nuclear safety, c. The heat transfer properties are censidered in fuel cooling thermal analyses and.are related to nuclear safety. 5.2.2 Basket Suecort Grids 5.2.2.1 Basis a. The spacing of the grids determines the spacing of fuel that was used in the nuclear safety analysis. b. The, structural strength of the grids and grid-to-wall intertie are integral to the strength of the system during the design seismic and tornado conditions, and therefore related to nuclear safety. 5.2.3 Fuel Gracoles 5.2.3.1 Basis Fuel grapples used with tne fuel handling crane and those used with the basin l crane are designed to preclude lifting a fuel bundle closer than 9 f t to the i' normal water level of the basin. 5.2.4 Fuel Basket Grsooles 5.2.4.1 Basis Basket grapples are designed for use with the basin crane, and are designed to preclude lifting a basket closer than 9 ft to the normal water level of the basin. l
H-17 l ,i 6.0 ACMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY I The Manager - Morris 0)eration shall be responsible for overall facility opera-tion in accordance with tnese specifications and applicable government regu~ l tio'ns, and shall delegate in writing the succession of this responsibility during .l his absence. Operations involving licensed materials shall be performed by, or j under the supervision cf individuals designated by the Manager - Morris Operation, j or his delegate. j j 6.2 ORGANIZATION 6.2.1 The facility staff organi:ation is shown in the CSAR, Figure 9-2. l I 6.2.2 Staff Qualifications l Minimum qualifications for members of the facility staff shall be the following: j a. Manager - Morris Operation l 0 BS degree in engineering, or related physical science, or equivalent in nuclear industrial experience. Demonstrated competence in the technologies and'controi methods f o applicable to nuclear energy business activities, including radio- [ active materials handling and radiation and criticality safety considerations. l I o Ten years of industrial experience with at least fha years in nuclear facility management. b. Manager - Plant Operations I o BS degree in engineering or eauivalent in nuclear incustrial l experience. i o Demonstrated competence in the technologies and c0ntrol methods applicable to nuclear energy business activities, including radio- ? active materials handling and radiation and criticality safety l l t considerations. Eight years of prior manufacturing or engineering excerience, with j o at least five years in the nuclear industry, c. Manager - Plant Engineering and Maintenance I o BS degree in engineering, or equivalent technical experience. t Thorough knowledge of radiation and criticality safety requirements l o and practice, including safety requirements specifically related to l maintenance operations under radioactive centamination c0nditions. f f s
H-18 o Five years of industrial experience, with at least three of these in the nuclear industry. d. Manager - Quality Assurance and Safeguards o BS degree in Engineering, or equivalent tr.anical experience o Thorough knowledge of nuclear materials handling, safeguards, and quality assurance methods and procedures. o Five years of experience in manufacturing and quality assurance fields, with at least three years of these in the nuclear industry. e. Senior Engineer - Licensing & Radiological Safety o BS degree in Engineering, or eouivalent technical experience. o Speciali::ed kncwlecge of health physics, and thorougn knowledge of radiation and criticality safety requirements for nuclear industrial operations, and knowledge of regulatory reauirements and practice, o Eight years of Engineering experience with at least five years in the nuclear field. 6.3 PLANS AND PROCEDURES Plans and procedures snall be established and implemented to assure compliance with Technical Specifications and applicable governmental regulations. 6.3.1 Chan'ces to Plans and Precedures l All changes or revisions of established plans or procedures reouired by this section shall be made in accordance with facility modification control practices as described in the CSAR, Sections 9.4.3 and 9.4.4. I 6.3.2 Plans and Procedures - Minimum Reauirement Plans and procedures required by this section shall include, but need not be l limited to, the folicwing: l a. A safety manual defining responsibilities and specifying actions to protect the health and safety o'f employees and others while en site, f safety training programs as appropriate, and other measures to main-tain exposures as low as reasonably achievable, b. A radiological emergency plan that defines resconsibilities and specifies actions, including channels of ecmmunication required to cope with credible emergencies on site (Radiological Emergency Plan for Morris Operation, NECE-21894, as revised. This plan requires Commission approval.) I _m__________.-__._.__ m
t H-19 c. Facil'ity change or modification control procedures for facility structures, systems and components. d. Procedures for determining certain characteristics of fuel to be stored. and to verify that fuel meets storage criteria. e. Plans requiring analyses of cask drop accidents for types of casks not previously received or unloaded. f. Procedures for the conduct of routine fuel storage operations. g. A preventative maintenance system for structures, systems, and com-ponents important to site radiological and criticality safety, h. Arrangements for providing makeup water to the storage basins under normal and emergency conditions,
- i. Arrangements for an invironmental monitoring program to demonstrate compliance with technical specifications for effluents.
J. Plans and implementing procedures for the training and certifi-cation of employees, as described in the CSAR, Section 9.3. These plans require Commission approval. k. Plans for decommissioning the facility, including decontamination of' structures and equipment and removal of radioactive wastes and contaminated materials. These plans require Commission approval. 1. Physical security and contingency plans, and other plans and pro-cedures as may be required under 10CFR73 to provide for the physicai security of stored fuel. These plans require Commission approval. m. Procedures sufficient to account for spent fuel in storage. 6.4 REVIEW AND AUDIT 6.4.1 Plant Safety Committee Plans, procedures, and the operations carried out under established plans and procedures involving elements of radiological safety shall.be reviewed and approved by a Plant Safety Caumittee. This Committee shall consist of the following members, as a minimum: a. Manager - Morris Operation b. Manager - Plant Operations c. Manager - Plant Engineering and Maintenance d. Manager - Quality Assurance and Safeguards e. Supervisor - Plant Safety f. Senior Engineer - Licensing and Radiological Safety
H-20 The Committee shall normally meet on a monthly basis, but at no less than 45-day intervals. The Manager - Morris Operation shall establish appropriate procedures and practice; for the conduct of Committee responsibilities. 6.4.2 Audit of Ooerations Activities of Morris Operation shall be audited to ascertain the degree of compliance with specifications, standards and procedures. Audits shall be con-ducted by organizations and persons and at such times as may Le designated by l Manager - Spent Fuel Services Operation and General Manager - Nuclear Fuel and. Services Division. Audits and audit response shall be perfonned in accordance with procedures established by General Electric. 6.5 ACTION REQUIRED FOR SPECIFICATION NON-CCMPLIANCE 6.5.1 Functional and Oceratino Limits ~ The following actions shall be taken if a functional or operating limit (Sections 2.1 and 2.2) is found to have been excceded: a. The Plant Safety Cemittee shall be prcmptly notified of the non-compliance. b. When feasible, prompt action shall be taken to assure timely return of operations to soecification compliance. [ c. Notification of NRC Inspection and Enforcement Regional Offices, Region III, shall be made within 24 hours, advising them of events that resulted in a non-compliance condition. d. A review of the incident shall be made by the Plant Safety Cemittee 6 to establish the cause and to define means to prevent re-occurrence. 6.5.2 L.imiting Conditions, f The following actions shall be taken if a limiting condition is found to have been exceeded: I a. Prompt corrective action shall be taken to assure timely return j of operations to specification compliance. b. The Plant Safety Cemittee shall be advised of the non-comoliance within 24 hours. l r l ,.c ,..-.,r,-.m. r.
e H-21 Notification of NRC Inspection and Enforcement Regionci Office, c. Region III, shall be made at the time of the next insoection to advise them of events resulting in limiting conditions being exceeded. d. A review of a noncompliance situation shall be made by the Plant Safety Committee whenever a given limiting condition has been exceeded more than once in a period of 3 months, or more than_twice in any 12-month period. In these situations, the Committee shall establish the cause and define means to eliminate or reduce the frequency of occurrence. 6.5.3 Surveillance Recuirements The following actions shall be taken if surveillence recuirements are not satisfied: The Manager - Morris Operation, or his delegate, shall take such action a. as may be required to assure future compliance with surveillance require-ments,.and, if necessary, to assure return of operations to specification compliance in minimum time, b. The Plant Safety Committee shall be advised of any event, or sequence of events, involving surveillance requirements that involve systems directly related to radiological safety. The committee shall inves-tigate such events, and recommend corrective action, Notification of NRC Inspection and Enforcement Regional Office. c. Region III, shall be made at the time of the next inspection, advising them of events that resulted in a surveillance requirement being violated. l
H-22 6.5.4 Desian Features Design features shall only be cnanged in accordance with Specification 6.3.1, and CSAR Sections 9.4.3 anc 9.4.4. Unauthorized modifications of speci-l fied design features, or unauthorized introduction of unapproved tools, fixtures, or other equipment shall require action as spceified for limiting conditions in Specification 6.5.2.7 6.6 LOGS, RECORDS AN0 aEPORTS 6.6.1 Loos and Records a. A shift log shall be maintained to record non-routine and sig-nificant events that may occur during a shif t,
- b. Minutes of tne Plant Safety Committee shali be documented, in;;,lud-ing copies of reports required in Section 6.5.1, and other actions of the Committee.
- c. Records of facility changes, ano changes in procedures described in the CSAR shall be maintained throughout the lifetime of the facility.0
- d. Records of tests or experiments conducted under provisions of CSAR Section 9.4.4 shall be maintained throughout the lifetime of the j
facility, and shall include written safety evaluations that provide the bases for determining that the test or experiment did not in-l volve unreviewed safety or environmental questions. l t j
- e. Records of spent fuel receipt or transfer, and annual inventory shall be maintained in duplicate, with one set of records at a l
separate location, as specified in 10CFR72.51. t i
- f. Other records shall be established and maintained in becordance with 10CFR72.55.
I l 6.6.2 Reports
- a. An annual report shall be made to the Commission summarizing cnanges, 1
tests and experiments, including safety evaluations, conducted with-out prior approsal by the Commission,
- b. Accidental criticality shall be reported imediately to tne NRC l
regional office by telephone and telgram or teletype.
- c. Any loss of soecial nuclear material shall be repc'ted immediately to the NRC regional office by telephone and telegram or teletype.
l l
i ? H-23 i
- d. Material status reports shall be made to the Commission in f
accordance with instructions on Form NRC-742 as of March 31 and Septemoer 30 of each year, as specified in 10CFR72.53. j
- e. Upon receipt or transfer of spent fuel, a Nuclear Material Transfer r
Report (FormNRC-741)shallbemadeinaccordancewith10CFR72.54. l
- f. Other reports shall be made in accordance with 10CFR72.33 and 72.55.
l l 6.6.3 CSAR Annual Review i . The CSAR shall be reviewed and updated annually in accordance with f 10CFR72.50.
7.0 REFERENCES
AND NOTES l l 1. See analyses in Chapters 7 and 3, CSAR. 2. This limitation does not include uranium in stored fuel, or uranium used in construction of shipping casks such as the GE IF-300. l t 3. Natural UO, UO, UNH and UF5 used during MFRP testing may be stored j 3 2 in precess vessels in the canyon area, or in the site warehouse. 4. The use of the unloading pit doorway guard is described in the CSAR, f Chapters 1 and 5; see Section 5.4.3.3. 5. Dry to the extent that water samples cannot be obtained in the usual manner. I 6. " Coolant" refers to the heat transfer medium used within the cask. l 7. Authorized modifications and approved tools, fixtures, or other equip- ) ment are those processed under the provisions cf CSAR Sections 9.4.3 and f 9.4.4. 8. Significant changes in structures, systems and procedures described in j the CSAR, when of a permanent nature shall be recorded by incorporation l t in the CSAR. i i f ) --}}