IR 05000237/1976010: Difference between revisions

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| issue date = 05/27/1976
| issue date = 05/27/1976
| title = Letter Referring to the 04/29/1976 and 05/13/1976 Inspections and IE Inspection Reports 05000237/1976010, 05000249/1976009, 05000254/1976014, and 05000265/1976012 - Dresden Unit 2 and 3 and Quad-Cities Units 1 and 2
| title = Letter Referring to the 04/29/1976 and 05/13/1976 Inspections and IE Inspection Reports 05000237/1976010, 05000249/1976009, 05000254/1976014, and 05000265/1976012 - Dresden Unit 2 and 3 and Quad-Cities Units 1 and 2
| author name = Hind J A
| author name = Hind J
| author affiliation = NRC/RGN-III
| author affiliation = NRC/RGN-III
| addressee name = Lee B
| addressee name = Lee B
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:J / > ---* A UNITED STATES A N.LEAR REGULATORY COMMISSION * *, REGION Ill 799 ROOSEVELT ROAD -----------------------------GL:EN ELl.:VN;-ILt:INOIS '60137 Commonwealth Edison Company AlTNi Mr. Byron Lee, Jr. Vice President P.O. Box 767 Chicago, Illinois 60690 Gentlemen: Docket Docket No. 0-24 Dock.et No. 50-54 . Dock.et No. 50-265 This refers to the inspection conducted* on April 29 and * May 13, 1976, by Mr. c. c. Peck of this office and to the discussion of his findings with Messrs. Larson, Butterfield, _Massiu, Kuhel and other members of your staff at the conclusion of the inspection. Your activities pursuant to Title 10, Code of Federal Regulations, Part 70, "Special Nuclear Material as they pertain to Licenses No. DPR-19, No. DPR-25, No. DPR-29 and No. DPR-30 were the subject of the inspection. * * . ,:* No items of noncompliance with NRC requirements were . identified during the course of this 1.napection. ,, * The inspection consisted of an examination of the plutonium production and uranium fission and transmutation quantities that.Commonwealth Edison.has reported semi-annually on forms MRC-742, Material Status Report for the Dresden 2 and 3 and Quad-{:ities 1 and 2 stations. During a previous * inspection (No. 050-237/75-24 and quantities reported were found to differ significantly from the* amounts that our inspectors considered to be reasonable based on thermal energy generated and fuel exposure for . . some of the. six-months period. The reasons. for such differences were satisfactorily explained to us during this inspection and we have no further questions at this* time. To eliminate the possibility of future discrepancies, it vaa agreed at the conclusion of. the inspection that * future Material Status Reports for_ Commonwealth Edison facilities wou1d show actual in-core plutonium production and uranium fission and transmutation totals on: the.* reverse side of the NRC-742 whenever such totals differ from .** *. quantities recorded on the front * the form. . * *; ... *'. . . . . '* . ''1> . ,** .. ..
{{#Wiki_filter:J / >
y .. . e ' .. * .. ** / *e Commonwealth Edison Company -2 -MAY 2 *7 1976 -------------::" -----------Areas examined during this inspection concern a subject matter which is exempt from disclosure according to Section 2.790 .of the NRC's "Rules of Practice." Part 2, Title lC, Code of Federal Regulations. Consequently, our report of this inspection will not* be placed in the Public Document Room. We will be glad to d1.scuss any questions you have. concerning .t.his ,inspection. *-. .:*-
---* A UNITED STATES A N.LEAR REGULATORY COMMISSION *
  *,
*.~
REGION Ill 799 ROOSEVELT ROAD
--- - ----- ---- --------- ------ -GL:EN ELl.:VN;-ILt:INOIS '60137 Commonwealth Edison Company   Docket No.~7 AlTNi Mr. Byron Lee, J Docket No. 0-24 Vice President  Dock.et No. 50- 54 P.O. Box 767  . Dock.et No. 50-265 Chicago, Illinois 60690 Gentlemen:
This refers to the inspection conducted* on April 29 and *
May 13, 1976, by Mr. c. c. Peck of this office and to the discussion of his findings with Messrs. Larson, Butterfield,
_Massiu, Kuhel and other members of your staff at the conclusion of the inspection. Your activities pursuant to Title 10, Code of Federal Regulations, Part 70, "Special Nuclear Material as they pertain to Licenses No. DPR-19, No. DPR-25, No. DPR-29 and No. DPR-30 were the subject of the inspectio . ,:*
    * *
        *;
No items of noncompliance with NRC requirements were .
identified during the course of this 1.napectio ,, * The inspection consisted of an examination of the plutonium production and uranium fission and transmutation quantities that.Commonwealth Edison.has reported semi-annually on forms MRC-742, Material Status Report for the Dresden 2 and 3 and Quad-{:ities 1 and 2 stations. During a previous *
inspection (No. 050-237/75-24 and 050-249/75~21), quantities reported were found to differ significantly from the*
amounts that our inspectors considered to be reasonable based on thermal energy generated and fuel exposure for .
. some of the. six-months period. The reasons. for such differences were satisfactorily explained to us during this inspection and we have no further questions at this*   ... * ' .
time. To eliminate the possibility of future discrepancies, it vaa agreed at the conclusion of. the inspection that *
        . ~- .
future Material Status Reports for_ Commonwealth Edison   .~ .
facilities wou1d show actual in-core plutonium production and uranium fission and transmutation totals on: the.* reverse side of the NRC-742 form~ whenever such totals differ from .* *.
quantities recorded on the front *o~. the form. .   *
        '* .
    . ~. ,** .. .. (o()~ ''1>
      ~.,.-~~--~-~--~-~~--.__,..,..,,.___,....__* -~


Sincerelyyours, .*.*, . *" , .... . ,: :*. ,_ .. * * J. Hind, Chief * .. * :, *. Safeguards Branch * : I*  
y
..                 *e
.e    Commonwealth Edison      - 2 -    MAY 2 *7 1976 Company
        - ---------- - -::" - --- --- - - - -
Areas examined during this inspection concern a subject matter which is exempt from disclosure according to Section 2.790
    .of the NRC's "Rules of Practice." Part 2, Title lC, Code of Federal Regulations. Consequently, our report of this inspection will not* be placed in the Public Document Roo We will be glad to d1.scuss any questions you have. concerning
    .t.his ,inspectio *- . .:*-


===Enclosure:===
Sincerely yours,
........ : .** : IE Inspection n.eports , . ., .. , .. , .. *' , . .* . . .. . .. No. 050-237/76-10, ;<: *' .............. :,* .**c . _,._, .. No. 050-249/76-09, . . . . ''". .. ,' "" '.* .. *'' . ''*'No*. "<>so-2'54l76-l4, .:'.)/.::><>*L:: ;.:,--:: and No. 050-265/76-12 ; . . . . . . . * * (Part 790(d) . Information).*. *: *:_:, > ;' .<: '* .'. > .. *: * . ;. bee w/encl: * * * Central Files * . . '. . Regions I, II; and V *. * ,,.:>. IE Mail and File Unit . bee w/o encl:**** PDR Local PDR * : _:;* . . .. :;'':: .. ' .. * . . . . . . : . ..' .. ' . ' , . * ... ' .. *. ' ::***' . . . \, .... ** .. ' *' . ,. .. , ..... ' ' I .'' * * ; .. : **.* .: . * * c * * * .. ,*, * ... . . . . : ; : *: *'* ... , . *. :'', .. :',' .. .... *: : ..... : ..... *.: *:_,,, *,I*" . . ' ,.: I ; : * :" .: :.*.-' * .. * :. * *: * . .-' ' * * .. *. . .r;-:*:: -:.*. *-:*: ... * . . : .. . . . . . . . . . . *. . . . . . *. ... . . . . . . . : . . . .":" . ,. .. * ; *-.-*"'. **_ .. * **** .. *: . ... ... . .: . . . . . ... . . . :<***-. ' :* .. *.' . --: :-.-...... -** *:I," ,: . . .. -._. . .. , .. ,,. * ...* . ' . .. :: <. .. . ... . ' "*".:. . **': . .-* . :-. .. *.* . " :**: *';***. _:** ... , .. ' * .* : r' * * * * .* ' * * ' * . * . ,* . * ... : . ,*. *. . . .. . *" .. : .. *. ' . . . . -----* *-*--*-----.**-----.. ,*-***-,,_,_: ___ *_:. ________ .. _____ ... ... ... ""'?::1:***:U<"';.; . . *.' '* ','-..  
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.. .';:. UNITED sAs NUCLEi\R REGULi\TORY COMMissr9 . OFFICE OF INSPECTION i\ND ENFORCEMENT REGION III -----------------------------.* ___ .* ---... . ,.l .. IE Inspection IE Inspection IE Inspection IE Inspection Licensee: ------------Report Report Report Report No. No. No. No. 050-237 /76-10 050-249/76-09 050-254/76-14 050-265/76..:.12 Commonwealth Edison Company P. O. Box 767 Chicago, Illinois 60690 Dresden Nuclear Power Station Units 2 and 3 Morris, Illinois License No. DPR-19 License No. DPR-25 Category: C * Quad-Cities Nuclear Power Station .*License No. DPR-29 Units 1 and 2 License No. DPR-30 Cordova, Illinois Category: C .. Type of Licensee: . BWR, 800 MWe _Type of Inspection:. Materials Safeguards, Announced Dates of Inspection: April 29 and May 13, 1976 7>J. tUr4 A. . Principal Inspector: C. C. Peck * * (Date) Accompanying Inspectors: * Norie * * Other Accompanying Personnel: None . . . -. . . Reviewed By: . * Safeguards Branch '*. * .*. * * ** : . Copy .--1L of . copies. __ Pages * * * Attachme*nt: ** *. Findings (Part 2. 790(d). Information).* .*_ .. ',.* ,., * THIS DOCUMENT IS NOT TO BE ***' :. REPRODUCED WITHOUT SPECIFIC APPROVAL .. OF IE: III* ,: . .. .. ... *.,_. '.-*.-*: .. *'* ._:* . ,; * .. *. ' .. ..... *:* . . . ' ,*, .. * . ., _ .... _ .. : . ***[* ....
    . -~ *" ~ , ....
J" Part 2.790(d) lnforrnat1ori e SUMMARY OF FINDINGS Inspection conducted April 29 and May 13, 1976 (Dresden Units 2, 76-10 and 3, 76-09) (Quad-Cities Units 1, 76-14 and 2, 76-12): The inspection consisted of an examination of uranium depletion and plutonium production quantities that have been reported on Forms NRC-742 by the licensee for the Dresden 2 and 3 and Quad-Cities l and 2 stations. Apparent discrepancies between reported quantities and NRC-calculated quantities were resolved. No items of noncompliance were identified. Enforcement Items No items of noncompliance were identified during the inspection. Licensee Action on Previously Identified Enforcement Items Not applicable. Other Significant Items A. Systems and Components. * .N.one. B. Facility Items (Plans and Procedures) None * .. * C. Managerial Items None. D. Noncompliance Identified and Corrected .. by Licensee None. E. Deviations None. F. Status of Previously Reported Unresolved Items Not.applicable. . .*** . *. ; . .. . . *-2 '. ** ... -*. . ' ... . .:_t*, Part Information PO.rt 2. 7:JO (cl) infor!l13. ti on e e Management Interview At the conclusion of the meeting it was agreed that the licensee would report actual in-core uranium burnup and plutonium production -----------data on t-he--l'everse--of *the-NRG-742*-, Materials-Status Report--forms--* whenever these quantities differed from data reported on the face *-.e of the form. The licensee representatives stated that these differences should tend to be less significant since many of the reasons for past differences have been eliminated. Present at the discussion were: L. D. Butterfield, Supervisor, Nuclear Fuel Services .P .*.* c .. Kuhel, Group Leader, Nuclear -Fuel -Services C. O *. Larson, Comptroller's Staff H. L. Massiu, Group Leader, Nuclear Fuel Services Joan White, Comptroller's Staff C. C. Peck, NRC * .. "*'* >>:*:***--... *' *: .. * ,,... '*" * .. *.:. . : . -3 *" , ... Pa.rt 2 7JO ('I) 1 :. L r* . t. t ,*i. '**. .. -:-:-.. *
              . ,: :*.
Part 7 JO (:l} e e REPORT DETAILS Licensee Personnel Supplying Information L. D. Butterfield J. P. Hill P. C. Kuhel C. 0. Larson H. L. Massiu Joan White Scope of Inspection The inspection was a meeting for the purpose of resolvin*g some apparent discrepancies between uranium and uranium-235 fission and transmutation totals and plutonium production totals reported by the licensee, and corresponding totals manually calculated by NRC inspectors. These data are.reported semi-annually on Form NRC/ERDA-742 in .accordance with Section 70. 53 of 10 CFR Part 70 .. A comparison of NRC-calculated and licensee reported data for all reporting periods since December 1972 for Dresden 2 and 3 (seven periods) and since June 1974 for Quad-Cities 1 and 2 (four * periods) disclosed in general that the reported quantities for the two periods in 1975 appeared incorrect. The manual calculations used by the inspectors cannot be expected to be as accurate generally as the licensee's computerized data, since it is not * * '*posBible "'to :corrsrder variables .in a manual method. the manual method normally agrees within 8% with *.accurate computer data. .Since differences were much larger than 8%, the inspection was made to learn the cause of the inconsistencies. 10 CFR Part 70, Section 70.53 On-line process computers are progranuned .*to print out fuel inventories for the Dresden 2 and 3 and Quad-Cities 1 and 2 reactors. For each of the 725 fuel assemblies .in each of the . reactors, the computer will supply the current inventory of each uranium and plutonium isotope. Facility totals are also provided for the isotopes. The process computers were first used to generate data for use in completing the NRC-742 forms in July 1975. Until that time an off-line computer program supplied by GE was used to provide the data for these forms. , . -4.*-... **.:I . *-r* .._. ..... *.*\ .
      ,_ ..
........ .. * The* li.censee explained that the change to*use of the on-line computer was responsible for most of the discrepancies between the depletion and production quantities reported and actual in-core depletion and production. Perturbations have also been caused by ---re-10cat1-ons--0&#xa3;f-uei in -the--Core: and_ -----'* .. . '* **-The licensee stated that an effort was made to report ending inventory figures as accurately as possible on the 742 forms. The differences between ending inventory totals and beginning inventory, excluding changes caused by receipts and shipments, therefore represent uranium depletion or plutonium production. Discrepancies in the beginning and ending inventories caused by computer program changes, rounding, refueling, etc show up as apparent depletion* and proau*c-tion. *rhere "is 'no other space on the '74.2 form to indicate such discrepancies. Although these perturbations have been relatively small and insignificant as percentages of inventory totals (less than 0.1%), they can represent more than 10% of depletion or production for a six-month period. It was stated that the computer programs for Dresden 2 and 3 and Quad-Cities 1 and 2 were currently being modified to improve their inventory accuracy. Presumably this will also mean that reported uranium depletion and plutonium production figures will also be more accurate. In conclusion it was agreed that the licensee would in the future report actual in-core uranium depletion and plutonium production quantities on the reverse side of the NRC-742 form whenever these data differed from quantities reported on the front .of the form. Attachments 1-4 show comparat.ive licensee-NRC depletion production calculations for the four reactors. For those instances in which the 742-reported data were questioned, the licensee's calculations of actual *in-core depletion are shoW11.
                  ,:
          * * J. A~. Hind, Chief
        *. * :, *. Safeguards Branch *
                : I*
Enclosure:      ........ : .** : *~
IE Inspection n.eports    ,.., .. , .. , .. *' , . .* .. .. . ..
No. 050-237/76-10,   ;<:  *' . . . . . . . . . . . . . . :,* .**c . _,._,..
No. 050-249/76-09,     . . . . ''". .. ,' "" '.* .. *''
    . ''*'No*. "<>so-2'54l76-l4,    .:'.)/.::><>*L::   {<'.~~:'.>: :~  ;.:,--::
and No. 050-265/76-12    ; . .  .. . . .   **
    (Part 2~ 790(d) . Information).*. *: *:_:,    >;' .<: '* .'. ?~-
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===Attachments:===
..
Attachments 1 through 4 _.,**, '*, .... *.-; .. ; . ' ' . .. ' \ .. ---.. -< *,. : .. *,,*-:*-... 5.-.. ., ... . ... .. .. .** : ': : . -.* . .,
UNITED sAs NUCLEi\R REGULi\TORY COMMissr9
. : *-* ____ ____,_____:_, __ e .l'e.rt ( dJ Information e . . e ... Quad-Cities 1 ------------------------*----------------------------Reported Actual NRC NRC-742 Depl/Prod Calculated % Difference Period 1-6/74 u . 233,222 232,209 -o.o U-235 122,000 121,917 -o.o Pu 59,691 56,,859 -4.7 7-12/74 u 424,500 405, 718 -:-4.4 U-235 190,746 201,126 +5.4 Pu 86,120 86,631 +0.6 1-6/75 u 293,090 368,875 375,135 +l. 7 U-235 186,037 175,419 188,614 +7. 5 Pu 53,240 80,624 82,383 +2.2 7-12/75 e u 424,500 430,500 427,645 . -0. 7 .U-235 190,746. 193,006 207,920 +7.7 Pu . 86, 120 83, 130 . 85,833 +3.2 Overall u 1,457,097 1,440,707 -0.7 U-235 681,171 719,577 +5.6 Pu 309,565. 311, 706 +0.7 I -,*_. . *"" Attachment 1 :J .. *. . _ ...... .-. ....-Part 2. 790 (d) Information *
  .';:.  . OFFICE OF INSPECTION i\ND ENFORCEMENT
Part 2, 790 fdJ Inlorrn8.Hon e e e *-Qund-Cities 2 ----Repor-ted ---*--Actual-------*---*NRc--* ------------------*---------------------NRC-742 Depl/Prod Calculated % Difference .Period 1-.6/74 u 447,630 467' 158 +4.4 U-235 234,600 249,853 +6.5 Pu 115,726 119,595 +.3. 3 7-12/74 u 400,710 404,213 +0.9 U-235 194 ,612 . 209,373 +7.6 Pu 91,839 95,743 +4.2 1-6/75 u 80, 113 159,312 161, 798. +I. 6 U-235 73,615 83,350 86,999 +4.4 Pu 14,248 41,590 41,946 +0.8 7-12/75 u 455,529 347,750 345,886 -0.5 e U-235 192,942 175,524. 178,959 +1.9 Pu . 93,973 84,305 81,.693 . -3.1 Overall u 1,355,402 . 1 379 055 .. -:**-. ' . ',*. . . +l. 7 .U-235 688,086. 725, 184* +5.4 Pu 333,460 338, 977 +1.6 * .. *Attachment 2 *-.. * .. . . . .. * , ... * *Part 2, 790 (d) Inform'.l.tion :.-..  
 
*. e Part 2.790(d) Information Dresden 2 _______________________ Rep_or.ted __ '---___ ActuaL ___________ NRC -------------------------------------Period 7/72-6/73 u U-235 Pu 7-12/73 u U-235 Pu 1-6/74 u U-235. Pu 7-12/74 u e U-235 .. Pu .1-6/75 u U-235 Pu 7-12/75 u U-235 Pu Overall u U-235 . Pu . -II''::-*. NRC-742 Depl/Prod Calculated % Difference 950,050 572,244 347,956 436,868 234,340 . 114,008 446,090 220,836 80,752 214,595 98,347 . ,,45,7_19 . 78,226 52,086 17 '908 -475,717 241,571 80,375 41,815' 21,030 . 2,603,695 . 1,409, 153 724,916 964,327 605,926 332,183 468,967 255,193 114, 294 418,051 214,395 85, 372 ... 218, 460 112, 913 . 46;*828 83,368 46,696 22,418 479,252. : 253,860 110,596 '2,632,425 *. 1,488, 983 .. .. 711,691 -. *.*'. . ;*** *:*.' . Attachment 3 .. *.: .: , . .. _. .... ,, . :, .. _ Part 2. 790 (d) Information _ ,, ___ ;, +l. 5 +5.9 -4.5 +7. 3 +8.9 +o.o * -6.3 -2.9 +5.7 +1.8 '+14.8 +2.*4 +3.7 +IL 7. +6.6 +0.7 +5.1 -4. 2 .. +1.1. +5.7 ' -:-1.8. .***. .. _.:,*. ...  
==REGION III==
. *,. ' ..... Attachment 4 '.o'*. 'Part 2. 790 (d). Inforru:ition
--- ------~----
IE
    ..
  -- -- --- --- - - - -
Inspection
    -- - - - --
Report
    --- - - - - -
N ~---
050-237 /76-10
        - - -- - - - - -
IE Inspection Report N /76-09 IE Inspection Report N /76-14 IE Inspection Report N /76..:.12 Licensee:  Commonwealth Edison Company P. O. Box 767 Chicago, Illinois  60690 Dresden Nuclear Power Station    License No. DPR-19 Units 2 and 3    License No. DPR-25 Morris, Illinois    Category: C
    * Quad-Cities Nuclear Power Station .*License No. DPR-29 Units 1 and 2    License No. DPR-30 Cordova, Illinois    Category: C
      ..
Type of Licensee: . BWR, 800 MWe
___
-
.*  .*
_Type of Inspection:. Materials Safeguards, Announced Dates of Inspection:  April 29 and May 13, 1976 7>J. tUr4 *s-fz~ /1,: .
  . Principal Inspector:  ~l)t C. C. Peck * *
          (Date)  ..
Accompanying Inspectors: * Norie *
  * Other Accompanying Personnel:  None
    .  . . .. - .
Reviewed By:
    *
    ~.1 (f(,~ .
Safeguards Branch
--. . .     '*.
            .. *'* ._:*
            .
Attachme*nt: **    * S-F3-76~285 .*. * * ** : .   ..
            ,;
  *. Findings (Part 2. 790(d). Information).*  Copy .--1L of J~ . copie *~ _ Pages *  * * *., ...
        * THIS DOCUMENT IS NOT TO BE
    .*_ .. ',.* ,.,
      ***' :. REPRODUCED WITHOUT SPECIFIC  *.. *. ' ..
APPROVAL.. OF IE: III*
          '.-*.-*:
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Part 2.790(d) lnforrnat1ori e
SUMMARY OF FINDINGS Inspection conducted April 29 and May 13, 1976 (Dresden Units 2, 76-10 and 3, 76-09) (Quad-Cities Units 1, 76-14 and 2, 76-12): The inspection consisted of an examination of uranium depletion and plutonium production quantities that have been reported on Forms NRC-742 by the licensee for the Dresden 2 and 3 and Quad-Cities l and 2 stations. Apparent discrepancies between reported quantities and NRC-calculated quantities were resolved. No items of noncompliance were identifie Enforcement Items No items of noncompliance were identified during the inspectio Licensee Action on Previously Identified Enforcement Items Not applicabl Other Significant Items Systems and Components. *
.N.on Facility Items (Plans and Procedures)
None *
..* Managerial Items Non Noncompliance Identified and Corrected . by Licensee Non Deviations Non Status of Previously Reported Unresolved Items Not.applicabl . .*** .
  .  ** ... -*. ...
J"
  *. ; ~ . . :~-. . '. . '~ .
    *- 2
    .:_t*,
Part 2.?~0(d) Information
 
PO.rt 2. 7:JO (cl) infor!l13. ti on e    e
~  Management Interview At the conclusion of the meeting it was agreed that the licensee would report actual in-core uranium burnup and plutonium production
--- -- --- ---data on t-he--l'everse--of *the-NRG-742*-, Materials-Status Report--forms--*
whenever these quantities differed from data reported on the face of the form. The licensee representatives stated that these differences should tend to be less significant since many of the reasons for past differences have been eliminate Present at the discussion were:
L. D. Butterfield, Supervisor, Nuclear Fuel Services
  .P .* .*c ..Kuhel, Group Leader, Nuclear -Fuel -Services C. O*. Larson, Comptroller's Staff H. L. Massiu, Group Leader, Nuclear Fuel Services Joan White, Comptroller's Staff C. C. Peck, NRC
*-.e
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  *"
    ,...Pa.rt 2 ~ 7JO ('I) 1 :. L r*..r:*~ t. t ,* '**.
 
Part 2~ 7 JO (:l} Ini'c;~rr.o.tion e REPORT DETAILS e
Licensee Personnel Supplying Information L. D. Butterfield J. P. Hill P. C. Kuhel C. 0. Larson H. L. Massiu Joan White Scope of Inspection The inspection was a meeting for the purpose of resolvin*g some apparent discrepancies between uranium and uranium-235 fission and transmutation totals and plutonium production totals reported by the licensee, and corresponding totals manually calculated by NRC inspectors. These data are.reported semi-annually on Form NRC/ERDA-742 in .accordance with Section 70. 53 of 10 CFR Part 7 A comparison of NRC-calculated and licensee reported data for all reporting periods since December 1972 for Dresden 2 and 3 (seven periods) and since June 1974 for Quad-Cities 1 and 2 (four
* periods) disclosed in general that the reported quantities for the . *- r* .._. ~- .....
two periods in 1975 appeared incorrect. The manual calculations used by the inspectors cannot be expected to be as accurate generally as the licensee's computerized data, since it is not *
* '*posBible "'to :corrsrder ~-11--significant variables .in a manual metho However~ the manual method normally agrees within 8% with
*.accurate computer data. .Since differences were much larger than 8%, the inspection was made to learn the cause of the inconsistencie CFR Part 70, Section 70.53 On-line process computers are progranuned .*to print out fuel inventories for the Dresden 2 and 3 and Quad-Cities 1 and 2 reactors. For each of the 725 fuel assemblies .in each of the
. reactors, the computer will supply the current inventory of each uranium and plutonium isotope. Facility totals are also provided for the isotope **.:I The process computers were first used to generate data for use in completing the NRC-742 forms in July 1975. Until that time an off-line computer program supplied by GE was used to provide the data for these forms. ,
    . - 4.*-...
      *.*\ .
 
        ........ ~*.~=-1...-*;_.
 
* ----~---
The* li.censee explained that the change to*use of the on-line computer was responsible for most of the discrepancies between the depletion and production quantities reported and actual in-core depletion and production. Perturbations have also been caused by refu~lings,
  ---re-10cat1-ons--0&#xa3;f-uei in -the--Core: and_ ~O~P~t-er --r~uOdi~g- ~-~th_o_d*~-.- --
The licensee stated that an effort was made to report ending inventory figures as accurately as possible on the 742 forms. The differences between ending inventory totals and beginning inventory, excluding changes caused by receipts and shipments, therefore represent uranium depletion or plutonium production. Discrepancies in the beginning and ending inventories caused by computer program changes, rounding, refueling, etc show up as apparent depletion*
and proau*c-tion. *rhere "is 'no other space on the '74.2 form to indicate such discrepancies. Although these perturbations have been relatively small and insignificant as percentages of inventory totals (less than 0.1%), they can represent more than 10% of depletion or production for a six-month perio It was stated that the computer programs for Dresden 2 and 3 and Quad-Cities 1 and 2 were currently being modified to improve their inventory accuracy. Presumably this will also mean that reported uranium depletion and plutonium production figures will also be more accurat In conclusion  it was agreed that the licensee would in the future report actual  in-core uranium depletion and plutonium production quantities on  the reverse side of the NRC-742 form whenever these data differed  from quantities reported on the front .of the for Attachments 1-4 show comparat.ive licensee-NRC depletion production calculations for the four reactors. For those instances in which the 742-reported data were questioned, the licensee's calculations of actual *in-core depletion are shoW1 Attachments:
Attachments 1 through 4
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      -- -- -- -  --- --
    --- *-- -
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    -  - -- -- -
- - - ------ - ----- - ----- - - --  -
      - ~--
Reported  Actual  NRC NRC-742  Depl/Prod  Calculated % Difference Period 1-6/74 u  . 233,222    232,209  - U-235  122,000    121,917  - Pu  59,691    56,,859  - /74 u  424,500    405, 718  -:- U-235  190,746    201,126  + Pu  86,120    86,631  + /75 u  293,090  368,875  375,135  +l. 7 U-235  186,037  175,419  188,614  +7. 5 Pu  53,240  80,624  82,383  + /75 e  u
  .U-235 Pu 424,500 190,74 . 86, 120 430,500 193,006 83, 130 .
427,645 207,920 85,833
        . -0. 7
          + + Overall u    1,457,097  1,440,707  - U-235    681,171  719,577  + Pu    309,56 , 706  + I
- ,* . *""
Attachment 1
:J ..*.  . _ ...... .- . ....-
Part 2. 790 (d) Information *
 
Part 2, 790 fdJ Inlorrn8.Hon e    e e  *-  Qund-Cities 2
    - -*- -- *NRc--* - ----- - - - - --- ----
-*------- --------- - - - - - ----Repor-ted -- - *--Actual-----
NRC-742 Depl/Prod Calculated  % Difference
  .Period 1-.6/74 u 447,630  467' 158  + U-235 234,600  249,853  + Pu 115,726  119,595  +.3. 3 7-12/74 u 400,710  404,213  + U-235 194 ,612  . 209,373  + Pu 91,839  95,743  + /75 u 80, 113 159,312  161, 79 +I. 6 U-235 73,615 83,350  86,999  + Pu 14,248 41,590  41,946  + /75 u 455,529 347,750  345,886  - e  U-235 Pu 192,942
  .93,973 175,52 ,305 178,959 81,.693 .
        + .1 Overall u  1,355,402 . 1 379 055 .-:**-.  +l. 7
      ' . ',*. . .
  .U-235  688,08 , 184*  + Pu  333,460  338, 977  + ..
      *
      *Attachment 2
    *-.. * ..  . ;~ .
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      :.- . .
  * *Part 2, 790 (d) Inform'.l.tion
 
Part 2.790(d) Information
  *.
e
  *.~
Dresden 2
_______________________ Rep_or.ted __ '--- ___ ActuaL ___________ NRC -- ----------- ----- ------- - ---- -------
NRC-742 Depl/Prod  Calculated  % Difference Period 7/72-6/73 u 950,050  964,327  +l. 5 U-235 572,244  605,926  + Pu 347,956  332,183  - /73 u 436,868  468,967  +7. 3 U-235 234,340  255,193  + Pu . 114,008  114, 294  +o.o *
1-6/74 u 446,090  418,051  - U-23 ,836  214,395  - Pu 80,752  85, 372  + /74 u 214,595  ... 218, 460  + e  U-235
  .. Pu 98,347
  . ,,45,7_19 112, 913
      . 46;*828
        '+1 +2.*4
.1-6/75 u . 78,226 80,375  83,368  + U-235 52,086 41,815'  46,696  +IL Pu 17 '908 - 21,030 . 22,418  + /75 u 475,717  479,25 + U-235 241,571  : 253,860  + Pu 115~45 ,596  -4. 2 ..
Overall u  2,603,695  '2,632,425 *.  + ...
U-235  . 1,409, 153  1,488, 983 .  .. + .
. Pu  724,916  711,691 -  *.*'.
        ' -:- . ;***
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Attachment 3 II''::-*.    .. *.: .: -~. , . .. _. .... ,, .
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Part 2. 790 (d) Information
        .. _.:,*.
 
  . *,. ~ ' ..... Attachment 4
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'Part 2. 790 (d). Inforru:ition
}}
}}

Latest revision as of 19:12, 29 October 2019

Letter Referring to the 04/29/1976 and 05/13/1976 Inspections and IE Inspection Reports 05000237/1976010, 05000249/1976009, 05000254/1976014, and 05000265/1976012 - Dresden Unit 2 and 3 and Quad-Cities Units 1 and 2
ML17252B144
Person / Time
Site: Dresden, Quad Cities  Constellation icon.png
Issue date: 05/27/1976
From: Hind J
NRC/RGN-III
To: Brian Lee
Commonwealth Edison Co
References
IR 1976009, IR 1976010, IR 1976012, IR 1976014
Download: ML17252B144 (11)


Text

{{#Wiki_filter:J / >

---*  A UNITED STATES  A N.LEAR REGULATORY COMMISSION  *
 *,
*.~

REGION Ill 799 ROOSEVELT ROAD

--- - ----- ---- --------- ------ -GL:EN ELl.:VN;-ILt:INOIS '60137 Commonwealth Edison Company   Docket No.~7 AlTNi Mr. Byron Lee, J Docket No. 0-24 Vice President   Dock.et No. 50- 54 P.O. Box 767   . Dock.et No. 50-265 Chicago, Illinois 60690 Gentlemen:

This refers to the inspection conducted* on April 29 and * May 13, 1976, by Mr. c. c. Peck of this office and to the discussion of his findings with Messrs. Larson, Butterfield, _Massiu, Kuhel and other members of your staff at the conclusion of the inspection. Your activities pursuant to Title 10, Code of Federal Regulations, Part 70, "Special Nuclear Material as they pertain to Licenses No. DPR-19, No. DPR-25, No. DPR-29 and No. DPR-30 were the subject of the inspectio . ,:*

    *  *
        *;

No items of noncompliance with NRC requirements were . identified during the course of this 1.napectio ,, * The inspection consisted of an examination of the plutonium production and uranium fission and transmutation quantities that.Commonwealth Edison.has reported semi-annually on forms MRC-742, Material Status Report for the Dresden 2 and 3 and Quad-{:ities 1 and 2 stations. During a previous * inspection (No. 050-237/75-24 and 050-249/75~21), quantities reported were found to differ significantly from the* amounts that our inspectors considered to be reasonable based on thermal energy generated and fuel exposure for .

. some of the. six-months period. The reasons. for such differences were satisfactorily explained to us during this inspection and we have no further questions at this*    ... * ' .

time. To eliminate the possibility of future discrepancies, it vaa agreed at the conclusion of. the inspection that *

       . ~- .

future Material Status Reports for_ Commonwealth Edison .~ . facilities wou1d show actual in-core plutonium production and uranium fission and transmutation totals on: the.* reverse side of the NRC-742 form~ whenever such totals differ from .* *. quantities recorded on the front *o~. the form. . *

       '* .
    . ~. ,** .. ..  (o()~ 1>
     ~.,.-~~--~-~--~-~~--.__,..,..,,.___,....__* -~

y .. *e .e Commonwealth Edison - 2 - MAY 2 *7 1976 Company

       - ---------- - -::" - --- --- - - - -

Areas examined during this inspection concern a subject matter which is exempt from disclosure according to Section 2.790

   .of the NRC's "Rules of Practice." Part 2, Title lC, Code of Federal Regulations. Consequently, our report of this inspection will not* be placed in the Public Document Roo We will be glad to d1.scuss any questions you have. concerning
   .t.his ,inspectio *- . .:*-

Sincerely yours,

     .*.*,
   . -~ *" ~ , ....
              . ,: :*.
      ,_ ..
                 ,:
         * * J. A~. Hind, Chief
        *. * :, *. Safeguards Branch *
               : I*

Enclosure: ........ : .** : *~ IE Inspection n.eports ,.., .. , .. , .. *' , . .* .. .. . .. No. 050-237/76-10,  ;<: *' . . . . . . . . . . . . . . :,* .**c . _,._,.. No. 050-249/76-09, . . . . ". .. ,' "" '.* .. *

   . *'No*. "<>so-2'54l76-l4,    .:'.)/.::><>*L::   {<'.~~:'.>: :~  ;.:,--::

and No. 050-265/76-12  ; . . .. . . . **

    (Part 2~ 790(d) . Information).*. *: *:_:,     >;' .<: '* .'. ?~-
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Central Files * . *. :, .. :',' *~;.. :~. .....: ..... .... *: :*,I*" .

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UNITED sAs NUCLEi\R REGULi\TORY COMMissr9

  .';:.  . OFFICE OF INSPECTION i\ND ENFORCEMENT

REGION III

--- ------~----

IE

   ..
  -- -- --- --- - - - -

Inspection

   -- - - - --

Report

    --- - - - - -

N ~--- 050-237 /76-10

       - - -- - - - - -

IE Inspection Report N /76-09 IE Inspection Report N /76-14 IE Inspection Report N /76..:.12 Licensee: Commonwealth Edison Company P. O. Box 767 Chicago, Illinois 60690 Dresden Nuclear Power Station License No. DPR-19 Units 2 and 3 License No. DPR-25 Morris, Illinois Category: C

   * Quad-Cities Nuclear Power Station .*License No. DPR-29 Units 1 and 2     License No. DPR-30 Cordova, Illinois    Category: C
      ..

Type of Licensee: . BWR, 800 MWe ___

-

.* .* _Type of Inspection:. Materials Safeguards, Announced Dates of Inspection: April 29 and May 13, 1976 7>J. tUr4 *s-fz~ /1~ ,: .

 . Principal Inspector:  ~l)t C. C. Peck * *
         (Date)  ..

Accompanying Inspectors: * Norie *

 * Other Accompanying Personnel:   None
    .  . . .. - .

Reviewed By:

   *
   ~.1 (f(,~ .

Safeguards Branch

--. . .     '*.
           .. *'* ._:*
            .

Attachme*nt: ** * S-F3-76~285 .*. * * ** : . ..

            ,;
 *. Findings (Part 2. 790(d). Information).*   Copy .--1L of J~ . copie *~ _ Pages *  * * *., ...
       * THIS DOCUMENT IS NOT TO BE
    .*_ .. ',.* ,.,
      ***' :. REPRODUCED WITHOUT SPECIFIC   *.. *. ' ..

APPROVAL.. OF IE: III*

          '.-*.-*:
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Part 2.790(d) lnforrnat1ori e SUMMARY OF FINDINGS Inspection conducted April 29 and May 13, 1976 (Dresden Units 2, 76-10 and 3, 76-09) (Quad-Cities Units 1, 76-14 and 2, 76-12): The inspection consisted of an examination of uranium depletion and plutonium production quantities that have been reported on Forms NRC-742 by the licensee for the Dresden 2 and 3 and Quad-Cities l and 2 stations. Apparent discrepancies between reported quantities and NRC-calculated quantities were resolved. No items of noncompliance were identifie Enforcement Items No items of noncompliance were identified during the inspectio Licensee Action on Previously Identified Enforcement Items Not applicabl Other Significant Items Systems and Components. *

.N.on Facility Items (Plans and Procedures)

None *

..* Managerial Items Non Noncompliance Identified and Corrected . by Licensee Non Deviations Non Status of Previously Reported Unresolved Items Not.applicabl . .*** .
  .   ** ... -*. ...

J"

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Part 2.?~0(d) Information

PO.rt 2. 7:JO (cl) infor!l13. ti on e e

~  Management Interview At the conclusion of the meeting it was agreed that the licensee would report actual in-core uranium burnup and plutonium production

--- -- --- ---data on t-he--l'everse--of *the-NRG-742*-, Materials-Status Report--forms--* whenever these quantities differed from data reported on the face of the form. The licensee representatives stated that these differences should tend to be less significant since many of the reasons for past differences have been eliminate Present at the discussion were: L. D. Butterfield, Supervisor, Nuclear Fuel Services

 .P .* .*c ..Kuhel, Group Leader, Nuclear -Fuel -Services C. O*. Larson, Comptroller's Staff H. L. Massiu, Group Leader, Nuclear Fuel Services Joan White, Comptroller's Staff C. C. Peck, NRC
  • -.e
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    ,...Pa.rt 2 ~ 7JO ('I) 1 :. L r*..r:*~ t. t ,* '**.

Part 2~ 7 JO (:l} Ini'c;~rr.o.tion e REPORT DETAILS e Licensee Personnel Supplying Information L. D. Butterfield J. P. Hill P. C. Kuhel C. 0. Larson H. L. Massiu Joan White Scope of Inspection The inspection was a meeting for the purpose of resolvin*g some apparent discrepancies between uranium and uranium-235 fission and transmutation totals and plutonium production totals reported by the licensee, and corresponding totals manually calculated by NRC inspectors. These data are.reported semi-annually on Form NRC/ERDA-742 in .accordance with Section 70. 53 of 10 CFR Part 7 A comparison of NRC-calculated and licensee reported data for all reporting periods since December 1972 for Dresden 2 and 3 (seven periods) and since June 1974 for Quad-Cities 1 and 2 (four

* periods) disclosed in general that the reported quantities for the . *- r* .._. ~- .....

two periods in 1975 appeared incorrect. The manual calculations used by the inspectors cannot be expected to be as accurate generally as the licensee's computerized data, since it is not *

  • '*posBible "'to :corrsrder ~-11--significant variables .in a manual metho However~ the manual method normally agrees within 8% with
  • .accurate computer data. .Since differences were much larger than 8%, the inspection was made to learn the cause of the inconsistencie CFR Part 70, Section 70.53 On-line process computers are progranuned .*to print out fuel inventories for the Dresden 2 and 3 and Quad-Cities 1 and 2 reactors. For each of the 725 fuel assemblies .in each of the
. reactors, the computer will supply the current inventory of each uranium and plutonium isotope. Facility totals are also provided for the isotope **.:I The process computers were first used to generate data for use in completing the NRC-742 forms in July 1975. Until that time an off-line computer program supplied by GE was used to provide the data for these forms. ,
   . - 4.*-...
      *.*\ .
       ........ ~*.~=-1...-*;_.
  • ----~---

The* li.censee explained that the change to*use of the on-line computer was responsible for most of the discrepancies between the depletion and production quantities reported and actual in-core depletion and production. Perturbations have also been caused by refu~lings,

 ---re-10cat1-ons--0£f-uei in -the--Core: and_ ~O~P~t-er --r~uOdi~g- ~-~th_o_d*~-.- --

The licensee stated that an effort was made to report ending inventory figures as accurately as possible on the 742 forms. The differences between ending inventory totals and beginning inventory, excluding changes caused by receipts and shipments, therefore represent uranium depletion or plutonium production. Discrepancies in the beginning and ending inventories caused by computer program changes, rounding, refueling, etc show up as apparent depletion* and proau*c-tion. *rhere "is 'no other space on the '74.2 form to indicate such discrepancies. Although these perturbations have been relatively small and insignificant as percentages of inventory totals (less than 0.1%), they can represent more than 10% of depletion or production for a six-month perio It was stated that the computer programs for Dresden 2 and 3 and Quad-Cities 1 and 2 were currently being modified to improve their inventory accuracy. Presumably this will also mean that reported uranium depletion and plutonium production figures will also be more accurat In conclusion it was agreed that the licensee would in the future report actual in-core uranium depletion and plutonium production quantities on the reverse side of the NRC-742 form whenever these data differed from quantities reported on the front .of the for Attachments 1-4 show comparat.ive licensee-NRC depletion production calculations for the four reactors. For those instances in which the 742-reported data were questioned, the licensee's calculations of actual *in-core depletion are shoW1 Attachments: Attachments 1 through 4 _.,**,

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Quad-Cities 1

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Reported Actual NRC NRC-742 Depl/Prod Calculated % Difference Period 1-6/74 u . 233,222 232,209 - U-235 122,000 121,917 - Pu 59,691 56,,859 - /74 u 424,500 405, 718 -:- U-235 190,746 201,126 + Pu 86,120 86,631 + /75 u 293,090 368,875 375,135 +l. 7 U-235 186,037 175,419 188,614 +7. 5 Pu 53,240 80,624 82,383 + /75 e u

 .U-235 Pu 424,500 190,74 . 86, 120 430,500 193,006 83, 130 .

427,645 207,920 85,833

        . -0. 7
         + + Overall u    1,457,097  1,440,707  - U-235    681,171  719,577  + Pu    309,56 , 706  + I
- ,* . *""

Attachment 1

J ..*. . _ ...... .- . ....-

Part 2. 790 (d) Information *

Part 2, 790 fdJ Inlorrn8.Hon e e e *- Qund-Cities 2

    - -*- -- *NRc--* - ----- - - - - --- ----

-*------- --------- - - - - - ----Repor-ted -- - *--Actual----- NRC-742 Depl/Prod Calculated  % Difference

 .Period 1-.6/74 u 447,630   467' 158  + U-235 234,600   249,853  + Pu 115,726   119,595  +.3. 3 7-12/74 u 400,710   404,213  + U-235 194 ,612   . 209,373  + Pu 91,839   95,743  + /75 u 80, 113 159,312  161, 79 +I. 6 U-235 73,615 83,350  86,999  + Pu 14,248 41,590  41,946  + /75 u 455,529 347,750  345,886  - e  U-235 Pu 192,942
  .93,973 175,52 ,305 178,959 81,.693 .
       + .1 Overall u  1,355,402 . 1 379 055 .-:**-.  +l. 7
     ' . ',*. . .
 .U-235  688,08 , 184*  + Pu   333,460  338, 977  + ..
      *
     *Attachment 2
    *-.. * ..  . ;~ .
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  * *Part 2, 790 (d) Inform'.l.tion

Part 2.790(d) Information

 *.

e

 *.~

Dresden 2 _______________________ Rep_or.ted __ '--- ___ ActuaL ___________ NRC -- ----------- ----- ------- - ---- ------- NRC-742 Depl/Prod Calculated  % Difference Period 7/72-6/73 u 950,050 964,327 +l. 5 U-235 572,244 605,926 + Pu 347,956 332,183 - /73 u 436,868 468,967 +7. 3 U-235 234,340 255,193 + Pu . 114,008 114, 294 +o.o * 1-6/74 u 446,090 418,051 - U-23 ,836 214,395 - Pu 80,752 85, 372 + /74 u 214,595 ... 218, 460 + e U-235

 .. Pu 98,347
 . ,,45,7_19 112, 913
     . 46;*828
       '+1 +2.*4
.1-6/75 u . 78,226 80,375  83,368   + U-235 52,086 41,815'  46,696   +IL Pu 17 '908 - 21,030 . 22,418   + /75 u 475,717   479,25 + U-235 241,571   : 253,860   + Pu 115~45 ,596   -4. 2 ..

Overall u 2,603,695 '2,632,425 *. + ... U-235 . 1,409, 153 1,488, 983 . .. + .

. Pu  724,916  711,691 -  *.*'.
       ' -:- . ;***
. -
      *:*.' . .***.

Attachment 3 II::-*. .. *.: .: -~. , . .. _. .... ,, .

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_,,___ ; , Part 2. 790 (d) Information

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 . *,. ~ ' ..... Attachment 4

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'Part 2. 790 (d). Inforru:ition

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