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Category:Inspection Report
MONTHYEARIR 05000254/20240112024-11-13013 November 2024 Biennial Problem Identification and Resolution Inspection Report 05000254/2024011 and 05000265/2024011 IR 05000254/20240032024-11-12012 November 2024 Integrated Inspection Report 05000254/2024003, 05000265/2024003 and 07200053/2024001 IR 05000237/20254012024-11-0101 November 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000237/2025401 05000249/2025401 IR 05000237/20240032024-10-29029 October 2024 Integrated Inspection Report 05000237/2024003 and 05000249/2024003 IR 05000254/20240102024-10-28028 October 2024 Age Related Degradation Inspection Report 05000254/2024010 and 05000265/2024010 and Notice of Violation IR 05000237/20244022024-09-19019 September 2024 – Security Baseline Inspection Report 05000237/2024402 and 05000249/2024402 - (Public) IR 05000254/20244022024-09-12012 September 2024 Material Control and Accounting Program Inspection Report 05000254/2024402 and 05000265/2024402 (Public) IR 05000254/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Quad Cities Nuclear Power Station (Report 05000254/2024005; 05000265/2024005) IR 05000237/20240022024-08-14014 August 2024 Integrated Inspection Report 05000237/2024002 and 05000249/2024002 IR 05000254/20240022024-08-12012 August 2024 Integrated Inspection Report 05000254/2024002 and 05000265/2024002 IR 05000237/20240102024-08-0909 August 2024 NRC Age-Related Degradation Inspection Report 05000237/2024010 and 05000249/2024010 IR 05000254/20243012024-08-0101 August 2024 NRC Initial License Examination Report 05000254/2024301; 05000265/2024301 IR 05000237/20243012024-06-27027 June 2024 NRC Initial License Examination Report 05000237/2024301; 05000249/2024301 IR 05000254/20240012024-05-14014 May 2024 Integrated Inspection Report Nos. 05000254/2024001 and 05000265/2024001 IR 05000237/20240012024-05-0101 May 2024 Integrated Inspection Report 05000237/2024001 & 05000249/2024001 IR 05000237/20244012024-04-18018 April 2024 – Security Baseline Inspection Report 05000237/2024401 and 05000249/2024401 IR 05000254/20245012024-04-0505 April 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000254/2024501 and 05000265/2024501 IR 05000254/20230062024-02-28028 February 2024 Annual Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2023006 and 05000265/2023006) IR 05000237/20230062024-02-28028 February 2024 Annual Assessment Letter for Dresden Nuclear Station, Units 2 and 3 (Report 05000237/2023006; 05000249/2023006) IR 05000254/20230042024-02-0505 February 2024 Integrated Inspection Report 05000254/2023004 and 05000265/2023004 IR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) IR 05000254/20234032023-12-22022 December 2023 Public- Quad Cities Nuclear Power Station Security Baseline Inspection Report 05000254/2023403 and 05000265/2023403 IR 05000254/20230102023-12-20020 December 2023 Comprehensive Engineering Team Inspection Report 05000254/2023010 and 05000265/2023010 IR 05000237/20230032023-11-13013 November 2023 Integrated Inspection Report 05000237/2023003 and 05000249/2023003 and Exercise of Enforcement Discretion IR 05000254/20230032023-11-0909 November 2023 Integrated Inspection Report 05000254/2023003 and 05000265/2023003 IR 05000254/20230112023-09-20020 September 2023 Safety-Conscious Work Environment Issue of Concern Team Inspection Report 05000254/2023011 and 05000265/2023011 IR 05000237/20230112023-09-0606 September 2023 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 IR 05000237/20234022023-08-29029 August 2023 Security Baseline Inspection Report 05000237/2023402 and 05000249/2023402 IR 05000254/20230052023-08-25025 August 2023 Updated Inspection Plan and Assessment Follow-Up Letter for Quad Cities Nuclear Power Station (Report 05000254/2023005; 05000265/2023005) IR 05000237/20230052023-08-25025 August 2023 Updated Inspection Plan and Assessment Follow-Up Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2023005; 05000249/2023005) IR 05000254/20230022023-08-0808 August 2023 Integrated Inspection Report 05000254/2023002 and 05000265/2023002 IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 IR 05000265/20230402023-06-22022 June 2023 Reissue Quad Cities Nuclear Power Station 95001 Supplemental Inspection Supplemental Report 05000265/2023040 and Follow Up Assessment Letter ML23167B1722023-06-16016 June 2023 95001 Supplemental Inspection Report 05000265/2023040 and Follow-Up Assessment Letter IR 05000237/20233012023-05-30030 May 2023 NRC Initial License Examination Report 05000237/2023301; 05000249/2023301 IR 05000254/20234022023-05-15015 May 2023 Security Baseline and ISFSI Inspection Reports 05000254/2023402, 05000265/2023402, 07200053/2023401 IR 05000254/20230012023-05-0808 May 2023 Integrated Report 05000254/2023001 and 05000265/2023001 IR 05000237/20230012023-05-0404 May 2023 Integrated Inspection Report 05000237/2023001 and 05000249/2023001 IR 05000237/20235012023-04-21021 April 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000237/2023501 and 05000249/2023501 IR 05000237/20230102023-03-0909 March 2023 Biennial Problem Identification and Resolution Inspection Report 05000237/2023010 and 05000249/2023010 ML23065A2832023-03-0707 March 2023 Request for Information for the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000254/2023010 and 05000265/2023010 IR 05000254/20233012023-03-0707 March 2023 NRC Initial License Examination Report 05000254/2023301; 05000265/2023301 IR 05000237/20220062023-03-0101 March 2023 Annual Assessment Letter for Dresden Nuclear Power Station, Units 2 and 3 (Report 05000237/2022006 and 05000249/2022006) IR 05000254/20220062023-03-0101 March 2023 Annual Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2022006 and 05000265/2022006) IR 05000254/20220042023-02-10010 February 2023 Integrated Inspection Report 05000254/2022004 and 05000265/2022004 IR 05000237/20220042023-02-10010 February 2023 Integrated Inspection Report 05000237/2022004, 05000249/2022004 and 07200037/2022002 IR 05000254/20234012023-01-11011 January 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000254/2023401; 05000265/2023401 IR 05000254/20220112023-01-0606 January 2023 Triennial Fire Protection Inspection Report 05000254/2022011 and 05000265/2022011 IR 05000237/20224022023-01-0505 January 2023 Security Baseline Inspection Report 05000237/2022402 and 05000249/2022402 2024-09-19
[Table view] Category:Letter
MONTHYEARIR 05000254/20240112024-11-13013 November 2024 Biennial Problem Identification and Resolution Inspection Report 05000254/2024011 and 05000265/2024011 IR 05000254/20240032024-11-12012 November 2024 Integrated Inspection Report 05000254/2024003, 05000265/2024003 and 07200053/2024001 RS-24-101, License Amendment Request for One-Time Extension of Standby Gas Treatment System Technical Specifications Completion Time to Support Piping Repair2024-11-0404 November 2024 License Amendment Request for One-Time Extension of Standby Gas Treatment System Technical Specifications Completion Time to Support Piping Repair ML24317A1432024-11-0404 November 2024 Constellation Energy Generation, LLC, 2024 Annual Report - Guarantees of Payment of Deferred Premiums ML24303A0712024-11-0404 November 2024 Letter to K. Meshigaud, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24291A0252024-11-0101 November 2024 Letter to R. Blanchard Tribal Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1342024-11-0101 November 2024 Letter to T. Carnes, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0152024-11-0101 November 2024 Letter to C. Harper, Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0692024-11-0101 November 2024 Letter to J.A. Crawford, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0242024-11-0101 November 2024 Letter to D. Kaskaske, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1442024-11-0101 November 2024 Letter to V. Kitcheyna, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0202024-11-0101 November 2024 Letter to C. Chavers, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0492024-11-0101 November 2024 Letter G. Kakkak, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0642024-11-0101 November 2024 Letter to J. Rupnick, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0512024-11-0101 November 2024 Letter to J. Barrett, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0472024-11-0101 November 2024 Letter to G. Cheatham, Chairwoman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1102024-11-0101 November 2024 Letter to R. Gasco, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1352024-11-0101 November 2024 Letter to T. Rhodd, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1172024-11-0101 November 2024 Letter to R. Yob, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0602024-11-0101 November 2024 Letter to J. R. Shotton, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0532024-11-0101 November 2024 Letter to J. Greendeer, President Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0992024-11-0101 November 2024 Lett to R. Carter, Principal Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0272024-11-0101 November 2024 Letter to D. Rios, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0302024-11-0101 November 2024 Letter to D.G. Lankford, Chief Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0172024-11-0101 November 2024 Letter to B. Peters, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0132024-11-0101 November 2024 Letter to B. Barnes, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1422024-11-0101 November 2024 Letter to V. Jefferson, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0432024-11-0101 November 2024 Letter to E. Elizondo, Sr. Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0552024-11-0101 November 2024 Letter to J. Keys, Chairman Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A0892024-11-0101 November 2024 Letter to M. J. Wesaw, Chair Request to Initiate Section 106 Consultation for SLR of DNP Station ML24303A1462024-11-0101 November 2024 Letter to W. Gravelle, Chairperson Request to Initiate Section 106 Consultation for SLR of DNP Station IR 05000237/20254012024-11-0101 November 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000237/2025401 05000249/2025401 RS-24-104, Nuclear Radiological Emergency Plan Document Revision2024-11-0101 November 2024 Nuclear Radiological Emergency Plan Document Revision RS-24-126, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4)2024-10-31031 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4) ML24291A0272024-10-31031 October 2024 NRC Letter to C. Mayer Illinois SHPO Request to Initiate Section 106 Consultation for Subsequent License Renewal of Units 2 and 3 ML24291A0202024-10-31031 October 2024 NRC Letter to J. Loichinger Achp Request for Comments Concerning the Environmental Review of DNPS Units 2 and 3 Subsequent License Renewal Application 05000265/LER-2024-002-01, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure2024-10-30030 October 2024 Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure SVP-24-065, Offsite Dose Calculation Manual (ODCM) Section 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation Report Main Chimney High Range Noble Gas Monitor2024-10-29029 October 2024 Offsite Dose Calculation Manual (ODCM) Section 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation Report Main Chimney High Range Noble Gas Monitor IR 05000237/20240032024-10-29029 October 2024 Integrated Inspection Report 05000237/2024003 and 05000249/2024003 IR 05000254/20240102024-10-28028 October 2024 Age Related Degradation Inspection Report 05000254/2024010 and 05000265/2024010 and Notice of Violation RS-24-102, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-5912024-10-21021 October 2024 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-591 RS-24-103, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-10-21021 October 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests SVP-24-059, Correction to Registration of Use of Casks to Store Spent Fuel2024-10-0404 October 2024 Correction to Registration of Use of Casks to Store Spent Fuel ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24247A1642024-09-30030 September 2024 Alternative Request RP-01 ML24225A2132024-09-26026 September 2024 Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval ML24253A0942024-09-23023 September 2024 License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application (EPID L-2024-Sle-0002) (Docket Numbers: 50-237 and 50-249) SVPLTR 24-0030, ISFSI Annual Effluent Release Report2024-09-20020 September 2024 ISFSI Annual Effluent Release Report 2024-09-30
[Table view] |
Inspection Report - Dresden - 1976010 |
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{{#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> . ,** .. ..
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. *-. .:*-
Sincerelyyours, .*.*, . *" , .... . ,: :*. ,_ .. * * J. 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 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<"';.; . . *.' '* ','-..
.. .';:. 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£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.
Attachments:
Attachments 1 through 4 _.,**, '*, .... *.-; .. ; . ' ' . .. ' \ .. ---.. -< *,. : .. *,,*-:*-... 5.-.. ., ... . ... .. .. .** : ': : . -.* . .,
. : *-* ____ ____,_____:_, __ 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 *
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. .***. .. _.:,*. ...
. *,. ' ..... Attachment 4 '.o'*. 'Part 2. 790 (d). Inforru:ition
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