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| During a telephone conversation on Tuesday, March 11, 1975, a member of your staff requested additional information with regard to our March 10, 1975 submittal concerning eddy current testing performed during February 1975. | | During a telephone conversation on Tuesday, March 11, 1975, a member of your staff requested additional information with regard to our March 10, 1975 submittal concerning eddy current testing performed during February 1975. |
| * This information was delivered to your staff on March 13; 1975 and is transmitted, attached to this letter, to formally document our responses. The attached items are:
| | This information was delivered to your staff on March 13; 1975 and is transmitted, attached to this letter, to formally document our responses. The attached items are: |
| Table 1 - Palisades "A" Steam Generator Eddy Current Test Results Table 2 - Palisades "B" Steam Generator Eddy Current Test Results Table 3 - Tubes Plugged as Part of the February 1975 Palisades "A" Steam Generator Inspection Table 4- Tubes Plugged as Part of the February 1975 Palisades "B" Steam Generator Inspection Table 5 - Tubes with an indication.~ 50% which, when averaged with addi-tional readings, were below 50% and remain in service following the February 1975 Palisades "A" steam generator inspection. | | Table 1 - Palisades "A" Steam Generator Eddy Current Test Results Table 2 - Palisades "B" Steam Generator Eddy Current Test Results Table 3 - Tubes Plugged as Part of the February 1975 Palisades "A" Steam Generator Inspection Table 4- Tubes Plugged as Part of the February 1975 Palisades "B" Steam Generator Inspection Table 5 - Tubes with an indication.~ 50% which, when averaged with addi-tional readings, were below 50% and remain in service following the February 1975 Palisades "A" steam generator inspection. |
| Table 6 - Tubes with an indication ~ 50% which, when averaged with addi-tional readings, were below 50% and remain in service following the Fepruary 1975 Palisades "B" steam generator inspection. | | Table 6 - Tubes with an indication ~ 50% which, when averaged with addi-tional readings, were below 50% and remain in service following the Fepruary 1975 Palisades "B" steam generator inspection. |
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| * DAB/ce CC: JGKeppler, USNRC Ralph B. Sewell Nuclear Licensing Administrator | | * DAB/ce CC: JGKeppler, USNRC Ralph B. Sewell Nuclear Licensing Administrator |
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| consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 | | consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 |
| * Area Code 517 788-0550' February 3, 1975 Mr. J. G. Keppler Re: Docket 50-25~ | | * Area Code 517 788-0550' February 3, 1975 Mr. J. G. Keppler Re: Docket 50-25~ |
Latest revision as of 14:43, 2 February 2020
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Category:Letter
MONTHYEARML24320A1232024-11-18018 November 2024 Confirmation of Initial License Examination IR 05000255/20240122024-11-12012 November 2024 Restart Inspection Report 05000255/2024012 ML24312A2262024-11-0606 November 2024 Letter from C. Nelson, Michigan SHPO Regarding Palisades Nuclear Plant Architectural Survey ML24310A0142024-11-0505 November 2024 Ape Notification to Mackinac Bands of Chippewa Palisades ML24292A1572024-11-0505 November 2024 Ape Notification to Burt Lake Band Palisades ML24310A0132024-11-0505 November 2024 Ape Notification to Grand River Bands of Ottawa Indians Palisades ML24309A2032024-11-0404 November 2024 Ape Notification to Ottawa Tribe of Oklahoma Palisades ML24309A2072024-11-0404 November 2024 Ape Notification to Quechan Tribe of the Fort Yuma Indian Reservation Palisades ML24309A1832024-11-0404 November 2024 Ape Notification to Bois Forte Band of the Minnesota Chippewa Tribe Palisades ML24309A2122024-11-0404 November 2024 Ape Notification to Sault Ste. 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Decommissioning Security Inspection Report 05000255/2024402 PNP 2024-029, Notice of Payroll Transition at Palisades Nuclear Plant2024-08-15015 August 2024 Notice of Payroll Transition at Palisades Nuclear Plant IR 05000255/20240022024-08-0909 August 2024 NRC Inspection Report No. 05000255/2024002 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 PNP 2024-032, Supplement to License Amendment Request to Revise Selected Permanently Defueled Technical Specifications Administrative Controls to Support Resumption of Power Operations2024-07-31031 July 2024 Supplement to License Amendment Request to Revise Selected Permanently Defueled Technical Specifications Administrative Controls to Support Resumption of Power Operations 2024-09-06
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARPNP 2024-037, Response to Requests for Additional Information Regarding the Proposed Reauthorization of Power Operations Under Renewed Facility Operating License Number DPR-0202024-10-0404 October 2024 Response to Requests for Additional Information Regarding the Proposed Reauthorization of Power Operations Under Renewed Facility Operating License Number DPR-020 PNP 2024-033, Response to Request for Additional Information - License Amendment Request to Revise the Palisades Nuclear Plant Site Emergency Plan to Support Resumption of Power Operations2024-07-24024 July 2024 Response to Request for Additional Information - License Amendment Request to Revise the Palisades Nuclear Plant Site Emergency Plan to Support Resumption of Power Operations PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-012, Response to Request for Additional Information Regarding License Amendment Request to Revise Facility Operating License and Technical Specifications for a Permanently Defueled Condition2022-04-21021 April 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Facility Operating License and Technical Specifications for a Permanently Defueled Condition CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L ML20272A1662020-09-30030 September 2020 Attachment 3 - Framatome Document No. ANP-3876, Revision 1Q1NP, Response to NRC Request for Additional Information of Palisades Relief Request Number RR 5-8, Repair of Reactor Pressure Vessel Head Penetration, Inservice Inspection Program, CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary PNP 2019-034, Response to Request for Additional Information Regarding License Amendment Request Resubmittal to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification...2019-08-23023 August 2019 Response to Request for Additional Information Regarding License Amendment Request Resubmittal to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification... ML19149A3032019-05-28028 May 2019 Enclosure Attachment 1 to Pnp 2019-028: Renewed Facility Operating License Page Markups ML19149A3022019-05-28028 May 2019 Enclosure to Pnp 2019-028: Response to Request for Additional Information - License Amendment Request to Revise Existing Facility Operating License Conditions Regarding NFPA 805 Modifications ML19149A3042019-05-28028 May 2019 Enclosure Attachment 1 (Continued) to Pnp 2019-028: Operating License Page Change Instructions and Retyped Renewed Facility Operating License Pages PNP 2019-003, Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement2019-02-0707 February 2019 Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement PNP 2018-059, Response to Request for Additional Information for Relief Request No. RR-5-7, Proposed Alternative to ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations2018-12-0303 December 2018 Response to Request for Additional Information for Relief Request No. RR-5-7, Proposed Alternative to ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations PNP 2018-023, Response to Second Request for Additional Information - Alternative to the Reexamination Frequency for a Relevant Condition Foreign Material Lodged in the Reactor Pressure Vessel2018-04-30030 April 2018 Response to Second Request for Additional Information - Alternative to the Reexamination Frequency for a Relevant Condition Foreign Material Lodged in the Reactor Pressure Vessel PNP 2018-018, Response to Request for Additional Information - Proposed Changes to the Emergency Plan to Reflect a Permanently Shut Down and Defueled Reactor Vessel2018-04-16016 April 2018 Response to Request for Additional Information - Proposed Changes to the Emergency Plan to Reflect a Permanently Shut Down and Defueled Reactor Vessel PNP 2018-014, Response to Request for Additional Information - Alternative to the Reexamination Frequency for a Relevant Condition Foreign Material Lodged in the Reactor Pressure Vessel2018-03-27027 March 2018 Response to Request for Additional Information - Alternative to the Reexamination Frequency for a Relevant Condition Foreign Material Lodged in the Reactor Pressure Vessel PNP 2017-075, Response to Request for Additional Information - Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition2017-12-19019 December 2017 Response to Request for Additional Information - Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition PNP 2017-020, Response to Request for Additional Information - Relief Request Number RR 4-25 Impracticality - Limited Coverage Examinations During the Fourth 10-year Inservice Inspection Interval2017-04-0505 April 2017 Response to Request for Additional Information - Relief Request Number RR 4-25 Impracticality - Limited Coverage Examinations During the Fourth 10-year Inservice Inspection Interval PNP 2016-055, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools.2016-10-25025 October 2016 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools. PNP 2016-053, Supplement to License Amendment Request: Control Rod Drive Exercise Surveillance2016-09-0808 September 2016 Supplement to License Amendment Request: Control Rod Drive Exercise Surveillance PNP 2016-047, Voluntary Response to NRC Regulatory Issue Summary 2016-09: Preparation and Scheduling of Operator Licensing Examinations2016-07-26026 July 2016 Voluntary Response to NRC Regulatory Issue Summary 2016-09: Preparation and Scheduling of Operator Licensing Examinations PNP 2016-037, Response to Request for Additional Information Regarding the License Amendment Request for Implementation of an Alternate Repair Criterion on the Steam Generator Tubes (CAC No. MF74352016-06-0707 June 2016 Response to Request for Additional Information Regarding the License Amendment Request for Implementation of an Alternate Repair Criterion on the Steam Generator Tubes (CAC No. MF7435 ML16071A4412016-03-0707 March 2016 Entergy Fleet Relief Request No. RR-EN-15-1-Proposed Alternative to Use ASME Code Case N-789-1 - E-mail from G.Davant to R.Guzman - Response to Second RAI (MF6340 - MF6349) PNP 2016-016, Reply to Request for Information EA-16-0112016-03-0303 March 2016 Reply to Request for Information EA-16-011 CNRO-2016-00005, Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM)2016-02-25025 February 2016 Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2016-00002, Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Secti2016-01-29029 January 2016 Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section Xl, CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 12015-12-0404 December 2015 Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1 PNP 2015-069, Response to Request for Additional Information Regarding Relief Request No. RR 5-22015-09-0909 September 2015 Response to Request for Additional Information Regarding Relief Request No. RR 5-2 PNP 2015-063, Supplemental Information for the Response to the First Request for Additional Information Regarding the License Amendment Request to Implement 10 CFR 50.61a2015-08-14014 August 2015 Supplemental Information for the Response to the First Request for Additional Information Regarding the License Amendment Request to Implement 10 CFR 50.61a PNP 2015-059, Response to Request for Supplemental Information for Relief Request Number RR 4-2 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination2015-07-31031 July 2015 Response to Request for Supplemental Information for Relief Request Number RR 4-2 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination ML18344A4421993-11-30030 November 1993 Reply to NRC Request for Information Regarding the Pressurizer Safe End Crack Critical Flaw Size and Margin to Failure Analysis. Response to Items 10 and 11 of the Nrc'S October 8, 1993 Information Request ML18346A2931993-09-22022 September 1993 CPC Letter of 7/6/1993, Responding to Inspection Report 93010 & Subsequent Conference Call of 7/22/1993, Letter Submit Supplemental Information to Inspection Report within 60 Days ML18344A2651993-08-16016 August 1993 Response to Request for Additional Information Recent Fuel Failure Event ML18354A6531990-05-30030 May 1990 Information Required by the November 9, 1989 Technical Evaluation Report - NUREG 0737, Item Ii.D.L, Performance Testing of Relief and Safety Valves, Palisades Plant to Close Items Not Fully Resolved ML18354A6151988-01-15015 January 1988 Updated Response to IE Bulletin 87-03 Dated 11/15/1985, Entitled, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings ML18348A8881979-05-15015 May 1979 Rapid Response to Additional Information Request on Three Mile Island ML18348A3721978-07-0707 July 1978 Provide Additional Information Related to Diesel Generators Control Circulatory, as Requested ML18348A3741978-07-0606 July 1978 Provide Requested Information of Additional Analysis Specific to Determine Consequences of Potential Boron Dilution Incidents ML18348A7441978-05-23023 May 1978 Response to Request for Additional Information Reactor Vessel Material Surveillance ML18346A1121978-01-24024 January 1978 Response to Request for Additional Information Relating to Water Hammer in Feed-Water Lines and Feed-Water Spargers ML18353B1571977-12-22022 December 1977 Response to Request for Specific Information Re Potential Problem of Post-LOCA Ph Control of Containment Sump Water of IE Bulletin 77-04 ML18347A1711977-09-26026 September 1977 Additional Information Relating to Power Increase Request ML18348A3961977-07-29029 July 1977 Response to Request for Specific Information Concerning Reactor Vessel Materials & Associated Surveillance Programs ML18348A4151977-07-12012 July 1977 Response to Request for Additional Information Re IE Bulletin 77-01, Relating to Use of Pneumatic Time Delay Relays in Safety-Related Systems ML18348A6911977-05-16016 May 1977 Response to Request for Additional Information Alarm and Diesel Generator Control Circuitry ML18348A6921977-05-12012 May 1977 Response to Request for Additional Information Proposed Emergency Dose Assessment System ML18348A8521977-05-0404 May 1977 Advising Exxon Concluded Three of Six Documents Do Not Contain Proprietary Information, Which Was Identified by AEC Letter of 3/1/1977, & Forwarding Affidavit as Additional Information Re Proprietary Documents ML18348A7051977-03-23023 March 1977 Response to Request for Additional Information Environmental Qualification of Electrical Equipment and the Effects of Its Submergence ML18348A8681977-03-0808 March 1977 Letter Reactor Vessel Overpressurization 2024-07-24
[Table view] |
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- Power company gan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 March 25, 1975 Mr. Angelo Giambusso Re: Docket 50-255 Director of Reactor Licensing License DPR-20 US Nuclear Regulatory Commission Palisades Plant Washington, DC 20555 Additional Eddy Current Test Information
Dear Mr. Giambusso:
During a telephone conversation on Tuesday, March 11, 1975, a member of your staff requested additional information with regard to our March 10, 1975 submittal concerning eddy current testing performed during February 1975.
This information was delivered to your staff on March 13; 1975 and is transmitted, attached to this letter, to formally document our responses. The attached items are:
Table 1 - Palisades "A" Steam Generator Eddy Current Test Results Table 2 - Palisades "B" Steam Generator Eddy Current Test Results Table 3 - Tubes Plugged as Part of the February 1975 Palisades "A" Steam Generator Inspection Table 4- Tubes Plugged as Part of the February 1975 Palisades "B" Steam Generator Inspection Table 5 - Tubes with an indication.~ 50% which, when averaged with addi-tional readings, were below 50% and remain in service following the February 1975 Palisades "A" steam generator inspection.
Table 6 - Tubes with an indication ~ 50% which, when averaged with addi-tional readings, were below 50% and remain in service following the Fepruary 1975 Palisades "B" steam generator inspection.
Yours very truly,
- DAB/ce CC: JGKeppler, USNRC Ralph B. Sewell Nuclear Licensing Administrator
consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550' February 3, 1975 Mr. J. G. Keppler Re: Docket 50-25~
Regional Director License DPR-20 Directorate of Regulatory Operations Palisades Plant Region III UE-74-3 US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Dear Mr. Keppler:
This letter is written to confirm previous discussions with members of your staff and to close out the possible loss of special nuclear material (SNM) as reported to you by Mr. R. B. DeWitt's TWX of January 7, 1975.
The TWX dated January 7, 1975 transmitted a chronological listing of.events regarding the possible loss of an out-of-core fission chamber containing approximately 1.7 grams of enriched uranium. This chronological listing started with the date of shipment of the fission chamber and included the efforts by Consumers Power Company to locate the fission chamber,as it had not arrive~ at the plant in the expected time frame. The TWX'concluded that the fission chamber was definitely lost. "'
On January 9, 1975, two days after submittal of the TWX, the fission chamber arrived at the Palisades Plant. At that time, Consumers Power Company again attempted to trace its routing in an effort to preclude a similar recurrence. We have drawn the following major conclusions with respect to the shipment:
- 1. Emery Air Freight acknowledged receiving the fis$ion chamber on December 4, 1974 in Cleveland, Ohio.
- 2. The fission chamber was shipped from Cleveland to Chicago O'Hare on about December 11, 1974. It is not clear what the status of the fission chamber was between December 4, 1974 and December 11, 1974.
- 3. The fission chamber remained at O'Hare Airport (apparently in the custody of Emery Air Freight) until December 31, 1974. On December 31, 1974, the fission chamber was received by Associated Truck Lines at their Chicago terminal.
I
\
-4 Mr. Jo G. Kep!r 2 Palisades Plant February 3, 1975
- 4. The fission chamber left the Associated Truck Lines
.terminal in Chicago on January 2, 1975 and was shown to have arrived in the Benton Harbor terminal of Associated Truck Lines on January 3, 1975.
- 5. The shipment remained in the Associated Truck Lines Benton Harbor terminal until delivered to Palisades on January 9, 1975.
The quantity of SNM involved is nearly negligible. (Less than 0.5 gram is defined as negligible.) Even so, fission chambers are important to the operation of the Palisades reactor. The expe-rience gained with this shipment will be taken into account when procuring fission chambers in the future.
This report has been classified as Unusual Event 74-3 in the Palisades Plant reporting system for purposes of formally docu-menting the event.
Yours very truly, Ralph B. Sewell (Signed)
RBS/mel Ralph B. Sewell Nuclear Licensing Administrator CC: Directorate of Regulatory Operations, Washington, DC Directorate of Licensing, Washington, DC