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MONTHYEARML24032A2442024-02-0101 February 2024 OEDO-24-00011 - 10 CFR 2.206 Petition Holtec Misuse Decommissioning Fund- Email to Petitioner ML24005A1262024-01-0505 January 2024 Permanently Defueled Emergency Plan Implementation Notification ML23055A1532023-02-24024 February 2023 Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22343A2282022-12-0909 December 2022 Acceptance Review: Palisades Proposed Exemption from 10 CFR 50.54(w)(1) - Onsite Property Damage Insurance ML22343A1902022-12-0909 December 2022 Acceptance Review: Palisades Proposed Exemption from 10 CFR 140.11 (a)(4) Primary and Secondary Liability Insurance ML22284A0502022-10-0707 October 2022 Acceptance Review: License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML22227A0082022-08-12012 August 2022 Acceptance Review: Exemption Request from 10CFR50.47(b), 10 CFR 50.47(c)(2), and 10 CFR Part 50, Appendix E, Section IV ML22227A0092022-08-12012 August 2022 Acceptance Review: License Amendment Request to Revise Emergency Plan and Emergency Action Level Scheme (L-2022-LLA-0099) ML22179A0752022-06-28028 June 2022 E-mail from Entergy Dated June 28, 2022, Notification of Palisades and Big Rock Point License Transfer (EPIDs L-2022-LLM-0002 and L-2020-LLM-0003) ML22159A2672022-06-0202 June 2022 Answers to Your Questions on Palisades ML22159A2652022-05-0303 May 2022 Questions Asked at Palisades Plant Performance Public Meeting April 26, 2022 ML21328A0062021-11-18018 November 2021 NRR E-mail Capture - (External_Sender) State of Michigan Response - Palisades Nuclear Plant and Big Rock Point Plant - Application for Order Consenting to Transfers of Licenses and Conforming License Amendments ML22208A1052021-11-16016 November 2021 NRR E-mail Capture - (External_Sender) State of Michigan Response - Palisades - Preparation for Issuance of Final Environmental Assessment and Finding of No Significant Impact Holtec Exemption Request to Use Dtf ML21309A5152021-11-0505 November 2021 NRR E-mail Capture - Palisades Nuclear Plant - Preparation for Issuance of Final Environmental Assessment and Finding of No Significant Impact Holtec Exemption Request to Use Dtf ML21309A2982021-11-0505 November 2021 NRR E-mail Capture - Palisades Nuclear Plant and Big Rock Point Plant - Application for Order Consenting to Transfers of Licenses and Conforming License Amendments ML21209A9802021-07-28028 July 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Requested Licensing Action, Rescission of Interim Compensatory Measure from Order EA-02-026 ML21189A2462021-07-0606 July 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Requested Licensing Action, Proposed Partial Exemption from Record Retention Requirements ML21189A0432021-07-0606 July 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Requested Licensing Action, Permanently Defueled Technical Specifications ML21054A1822021-02-23023 February 2021 NRR E-mail Capture - Regarding Public Comment on Palisades Request for Relief RR 5-8 ML21028A4092021-01-27027 January 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of Holtec Exemption Request from 10CFR50.82(a)(8)(i)(A) and 10CFR50.75(h)(1)(iv) ML21028A0552021-01-27027 January 2021 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance of License Transfer Application ML21007A3752021-01-0707 January 2021 NRR E-mail Capture - Regarding Public Comment on Palisades Nuclear Plant License Transfer (Sierra Club Nuclear Free Michigan) ML21054A1812021-01-0606 January 2021 NRR E-mail Capture - (External_Sender) Regarding Public Comment on Palisades Request for Relief RR 5-8 ML20275A3432020-10-0101 October 2020 Verbal Authorization for Proposed Alternative (RR 5-8) Reactor Vessel Closure Head Penetration Repairs ML20272A0112020-09-26026 September 2020 Request for Additional Information - Palisades Relief Request RR 5-8 (Proposed Alternative) for Reactor Pressure Vessel Head Penetration Repairs ML20262G9622020-09-17017 September 2020 Acknowledgement to Mr. Muhich e-mail, Dated September 15, 2020 (e-mail) ML20241A1802020-08-27027 August 2020 NRR E-mail Capture - Palisades Nuclear Plant- Upcoming Steam Generator Tube Inservice Inspection ML20162A4522020-04-0808 April 2020 Lake Mich Level Correspondence with Ipotter ML19344C7162019-08-25025 August 2019 Response from NEIMA Local Community Advisory Board Questionnaire 08-25-2019 C Ferry ML19344C8072019-08-16016 August 2019 Scanned Response 09-29-2019 I Potter ML19226A2932019-08-14014 August 2019 NRR E-mail Capture - Request for Additional Information Re License Amendment Request to Adopt TSTF-425, Revision 3 for the Palisades Nuclear Plant ML19226A2922019-08-0505 August 2019 NRR E-mail Capture - Draft Request for Additional Information for Palisades License Amendment Request to Adopt TSTF-425 ML19122A4852019-04-29029 April 2019 NRR E-mail Capture - Request for Additional Information for Palisades License Amendment Request to Revise License Conditions Related to NFPA 805 Modifications ML19095A6572019-04-0505 April 2019 NRR E-mail Capture - Acceptance for Review of Application to Revise the Palisades Nuclear Plant License Renewed Facility Operation License Regarding Full Compliance Implementation Date for the Fire Protection Program ML19059A1782019-02-28028 February 2019 Acceptance Review Results for Relief Request No. EN-19-RR-1 to Use ASME Code Case N-831-1 for Entergy Fleet ML19059A0292019-02-27027 February 2019 NRR E-mail Capture - Acceptance Review Results for License Amendment Request to Adopt TSTF-529, Revision 4, Clarify Use and Application Rules, for Entergy Fleet ML19009A5392019-01-0909 January 2019 NRR E-mail Capture - Request for Additional Information for Palisades License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement 3.3.5.2a ML19009A5382018-12-12012 December 2018 NRR E-mail Capture - Draft Request for Additional Information for Palisades License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement 3.3.5.2a ML18337A1382018-11-30030 November 2018 NRR E-mail Capture - Request for Additional Information Related to Palisades Relief Request Number RR 5-7 ML18337A1352018-11-30030 November 2018 NRR E-mail Capture - Acceptance for Review of Application to Revise the Palisades Nuclear Plant License Renewed Facility Operation License Regarding Changes to the Fire Protection Plan ML18337A1402018-11-29029 November 2018 NRR E-mail Capture - Draft Request for Additional Information Related to Palisades Relief Request 5-7 ML18184A2402018-07-0303 July 2018 NRR E-mail Capture - Acceptance for Review of Application to Revise Technical Specification Surveillance Requirement 3.3.5.2a for the Diesel Generator Undervoltage Start ML18101A1132018-04-11011 April 2018 NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Alternative for Relevant Condition ML18081A2962018-03-22022 March 2018 NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Changes to Site Emergency Plan for Permanently Defueled Condition (CAC MG0198: EPID L-2017-LLA-0305) ML18059A8202018-02-28028 February 2018 NRR E-mail Capture - Palisades Nuclear Plant - Request for Additional Information Regarding Proposed Alternative for Relevant Condition ML17355A0092017-12-20020 December 2017 NRR E-mail Capture - Palisades Nuclear Plant: Acceptance Review for Relief Request No. RR 5-6 - Alternative to the Reexamination Frequency for a Relevant Condition ML17345A0142017-12-0808 December 2017 NRR E-mail Capture - Acceptance Review Results Entergy Request No. EN-17-RR-1 ML17338B1242017-11-30030 November 2017 NRR E-mail Capture - (External_Sender) Palisades Nuclear Plant Flood Hazard Reevaluation Report FHRR Staff Assessment Input ML17335A1042017-11-30030 November 2017 NRR E-mail Capture - Palisades Nuclear Plant - RAI Regarding Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition (CAC MG0021; EPID L-2017-LLA-0266) ML17317A0042017-11-0909 November 2017 NRR E-mail Capture - Palisades Nuclear Plant - Acceptance Review for License Amendment Request to Change the Full Compliance Implementation Date for the Fire Protection Transition License Condition 2024-02-01
[Table view] Category:Graphics incl Charts and Tables
MONTHYEARML23107A0162023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 5, Tables ML23107A0322023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 4, Tables ML23107A0372023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 14, Tables ML23107A0512023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 6, Tables ML23107A0522023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 3, Tables ML23107A0552023-03-31031 March 2023 6 to Updated Final Safety Analysis Report, Chapter 2, Tables ML21354A7552021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 10 of 18 ML21125A3352021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 12, Figures ML21125A3362021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 15, Figures ML21125A3382021-04-14014 April 2021 5 to Updated Final Safety Analysis Report, Chapter 14, Tables ML18354A4272018-12-20020 December 2018 Superseded by Table Received with Mail 15 CNRO-2018-00011, Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018 Submittal of Joint Plant Access Shared Information Table ML17150A2562017-06-0505 June 2017 Entergy Fleet - 2017 Onsite Insurance Submittal Review for Entergy Operations, Inc., and Entergy Nuclear Operations, Inc. (CAC No. TM3058) ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports PNP 2015-042, One-Year Status Notification in Response to Confirmatory Order, EA-14-0132015-06-19019 June 2015 One-Year Status Notification in Response to Confirmatory Order, EA-14-013 ML15016A0912015-01-16016 January 2015 U.S. Nuclear Regulatory Commission, Record of Review Dispositions to Palisades Nuclear Plant (Pnp) Fire PRA (Fpra) Facts and Observations (F&Os ML15016A0732015-01-16016 January 2015 U.S. Nuclear Regulatory Commission, Record of Review Dispositions to Palisades Nuclear Plant (Pnp) Internal Events PRA (Iepra) Facts and Observations (F&Os) ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T ML1214500142012-05-23023 May 2012 NFPA 805 LAR Status Matrix - May 2012 ML1104704522011-02-15015 February 2011 Response to Request for Additional Information (RAI) - Cyber Security Plan ENOC-08-00040, Commitment Update Relating to Application for Order Approving Indirect Transfer of Control of Licenses2008-07-28028 July 2008 Commitment Update Relating to Application for Order Approving Indirect Transfer of Control of Licenses ML0806302532008-02-27027 February 2008 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basic Accidents at Pressurized-Water Reactors ENOC-07-00036, Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses2007-10-31031 October 2007 Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0733310832007-09-21021 September 2007 SG Tube Inspection Discussion During 2007 Palisades Outage ML0530705612005-10-31031 October 2005 Supplementary Information for the Application for Renewal of the Palisades Plant Operating License ML0520002372005-06-0707 June 2005 Precedents for Section 3.2 Exceptions to GALL ML0520002342005-06-0606 June 2005 Precedents for Section 3.1 Exceptions to GALL ML0520002412005-04-16016 April 2005 Precedents for Section 3.3 Exceptions to GALL ML0520004402005-04-0101 April 2005 Precedents for Section 3.5 Exceptions to GALL ML0520004542005-04-0101 April 2005 Precedents for Section 3.6 Exceptions to GALL ML0513800992005-03-31031 March 2005 Precedent Table, Mech Section 3.4 ML0513800922005-03-31031 March 2005 Precedent Table, Civil Section 3.5 ML0513800952005-03-31031 March 2005 Precedent Table, Mech Section 3.2 ML0513800982005-03-31031 March 2005 Precedent Table, Mech Section 3.3 ML0513800942005-03-31031 March 2005 Precedent Table, Mech Section 3.1 ML0513800862005-03-31031 March 2005 Precedent Table, Elec. Section 3.6 ML0520002302005-03-0202 March 2005 Exceptions to GALL Program Elements ML0434501802003-12-11011 December 2003 NMC Program Health Status Fleet Program at a Glance ML18347B2911994-04-13013 April 1994 Notification of Submittal of Request for Renewal of the National Pollutant Discharge Elimination System (NPDES) Permit ML18347B2891991-06-0101 June 1991 Semiannual Radioactive Effluent Release Report ML18344A2461984-05-14014 May 1984 a Steam Generator General Listing of 4C4 ML18346A2461978-08-0808 August 1978 Furnishing Information Re Combustion Engineering Owners' Group Proposed Plan to Resolve the Asymmetric LOCA Loads Issue ML18348A7361978-05-23023 May 1978 Letter Results of Burnup Study ML18346A2441978-04-0505 April 1978 Revision of Steam Generator Tube Dent Data ML18348A7561977-02-14014 February 1977 Primary System Pressure Increase to 2, 100 Psia ML18347A5441976-11-0909 November 1976 Submits Revised Table 6 of Special Report No. 9, Palisades Cycle II Start-Up Report August 27, 1976, Which Makes Provision for Measurement Uncertainty Allowance of 10% of Net Rod Worth ML18347A5581976-09-27027 September 1976 Referring to Meeting of 7/30/1976 Regarding Appendix J Which Requires Air Locks Be Tested After Each Opening, Letter Providing Information for NRC Consideration to CPC Exemption Request ML18347A6711976-04-23023 April 1976 Referring to 4/5/1976 Report, Rod Bow Measurements and Analysis of Effects on DNB, Providing Additional Data from Core I ML18347A6801976-04-0505 April 1976 Information Submitted in Addition to That Provided in Consumers Power Company Submittals of March 26, 1976 and April 5, 1976 2023-03-31
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aies*Ch FW: Steam Generator sTubeip6d"D-cussion Duiring UpcJomin'g`Pa'lisad'es a Outage ........... Page 1 i From: "Dotson, Barbara E." <bdotson @entergy.com>
To: "Mahesh Chawla" <MLC@nrc.gov>
Date: 09/21/2007 12:33:33 PM
Subject:
, FW: Steam Generator Tube Inspection Discussion During Upcoming Palisades Outage Mac, The responses are attached. The call-in numbers are below. I may have been incorrect about the Westinghouse generators. Jim says that they are CE, but it's all Westinghouse now.
Phone Number: 1-866-231-9615 Participant Code: 456295 From: Hager, John Sent: Friday, September 21, 2007 11:56 AM To: Dotson, Barbara E.
Cc: VanWagner, Robert V.; Fouty, Thomas H.; Higgs, Gregg A.; Rexius, Thomas D.; Cullen, Robert 0; Ingram, D urt; MEATHEANY, DANIEL J; O'QUINN, ROBERT C; ADDISON, EDWARD E; 'Cullen, William K.'; 'Spence, William J.'; 'Andy Neff'; 'Michael B Kirk'; Higgs, Gregg A.
Subject:
Steam Generator Tube Inspection Discussion During Upcoming Palisades Outage Barb, The Palisades' responses to the NRR request for Steam Generator Tube Inspection Discussion During Upcoming Palisades Outage are attached.
John
STEAM GENERATOR TUBE INSPECTION DISCUSSION DURING UPCOMING PALISADES OUTAGE
- 1. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.
Refer to attached Primary to Secondary Leak Rate for Operational Cycle 19 Primary to Secondary Leak Rate graph.
- 2. Discuss whether any secondary side pressure tests were performed during the outage and the associated results.
No secondary side pressure tests were performed in the 2007 refueling outage.
- 3. Discuss any exceptions taken to the industry guidelines.
No exceptions were taken to industry guidelines in the 2007 refueling outage.
- 4. For each steam generator, provide a description of the inspections performed including the areas examined and the probes used (e.g., dents/dings, sleeves, expansion-transition, U-bends with a rotating probe), the scope of the inspection (e.g., 100% of dents/dings greater than 5 volts and a 20% sample between 2 and 5 volts), and the expansion criteria.
Refer to attached Table 4A Palisades REFOUT 19 SG Eddy Current Inspection Scope, for a description of inspections performed, expansion criteria and a description of the probe used for the inspections performed.
- 5. For each area examined (e.g., tube supports, dent/dings, sleeves, etc),
provide a summary of the number of indications identified to-date of each degradation mode (e.g., number of circumferential primary water stress corrosion cracking indications at the expansion transition). For the most significant indications in each area, provide an estimate of the severity of the indication (e.g., provide the voltage, depth, and length of the indication). In particular, address whether tube integrity (structural and accident induced leakage integrity) was maintained during the previous operating cycle. In addition, discuss whether any location exhibited a degradation mode that had not previously been observed at this location at this unit (e.g., observed circumferential primary water stress corrosion cracking at the expansion transition for the first time at this unit).
This response is based on eddy current data collected and analyzed as of 13:00, September 20, 2007.
Tubesheet Region +Pt Program:
Five tubes with sludge pile axial outside diameter stress corrosion cracking (ODSCC), 2 in SG E50A, 3 in SG E-50B. Most significant indication is 0.28 +Pt V in 300 kHz, 0.43 inch. Profile not completed.
Three tubes with circumferential ODSCC, all in SGE-50B. Largest +Pt amplitude is 0.22 V, largest arc length 61 degrees (different indications).
One tube with axial primary water stress corrosion cracking (PWSCC) at -10 inches below TTS; 0.58 +Pt V, 0.14 inch length.
Three tubes with possible loose part wear signals, minor +Pt amplitudes and lengths.
Tube Supports:
Six tubes in SGE-50A with axial ODSCC at eggcrates. Largest +Pt amplitude 0.33 V in 300 kHz, longest length 0.33 inch. Profile not completed. This is the first report of "true" eggcrate axial ODSCC.
One tube in SG E-50B with axial ODSCC ding crack signal coincident with an eggcrate; bounded by SG E-50A parameters.
No freespan ding cracks are currently reported; this may be due to limited data through resolution process.
One tube in SGE-50B is reported to contain an axial ODSCC indication at a dent at vertical strap VS4. The dent amplitude is 5.11 V. Length is short, 0.20 inch, flaw amplitude is low.
Only one tube in SG-E-50A has been reported to date with a structure wear scar greater than or equal to 40%TW (41%).
Tube structural and leakage integrity was maintained during Operating Cycle 19 based on observed relatively minor flaw parameters reported for 1 R1 9 (2007 refueling outage). All +Pt signal amplitudes for stress corrosion cracking (SSC) are below the EPRI in-situ pressure testing (ISPT) screening value of 0.50 volt for proof testing; all +Pt signal amplitudes for SCc are below the EPRI ISPT screening values for leakage assessment.
- 6. Describe repair/plugging plans.
Currently there are 11 potential tubes required tube plugging in SG E-50A and 9 potential tubes requiring tube plugging in SG E-50B.
All stress corrosion cracking (SCC) indications are plugged. All circumferential SCC indications near top of tubesheet (TTS) are stabilized and plugged.
All structure wear greater than or equal to 40%TW is plugged.
- 7. Describe in-situ pressure test and tube pull plans and results (as applicable and if available).
Based on the available data to date, no tubes require in-situ pressure testing.
- 8. Provide the schedule for steam generator-related activities during the remainder of the current outage.
Currently bobbin and top of tubesheet +Pt RPC are almost completed in both steam generators. Special interest is in progress and will be completed this weekend in both steam generators (this includes dings/dents, u-bend, cold leg top of tubesheet etc.).
Sludge lancing and batwing inspections are completed on SG E-50A. Foreign object search and retrieval (FOSAR) in progress. SG E-50B sludge lancing/FOSAR has not started but will commence after FOSAR is completed in SG E-50A.
Tube plugging will occur early next week.
- 9. Discuss the following regarding loose parts:
- What inspections are performed to detect loose parts?
The hot leg top of tubesheet (TTS) region is inspected with +Pt up to 3 inches above TTS. A similar inspection is performed for the cold leg TTS region (3 tubes deep along periphery and tube lane. Foreign object search and retrieval (FOSAR) is performed for the periphery, tube lane annulus, and stay cavity areas.
A description of any loose parts detected and their location within the SG FOSAR is in progress in SG E-50A and sludge lancing/FOSAR has not started in SG E-50B.
If the loose parts were removed from the SG FOSAR is in progress in SG E-50A and sludge lancing/FOSAR has not started in SG E-50B.
- Indications of tube damage associated with the loose parts One tube in SG E-50B R137 C92 is reported to contain two volumetric signals at
,approximately 12 inches above TTS. This location is on the hot leg periphery.
Bobbin analysis reported two NQI signals. The axial and circumferential extents are bounded by 0.23 inch and 56 degrees arc. Eddy current analysis suggests the part is no longer present. All surrounding tubes are scheduled for +Pt inspection to a height greater than the indications. FOSAR will examine the area, if possible.
One tube in SGE-50B R3 C58 is reported to contain a volumetric indication at tubesheet hot (TSH). A possible loose part (PLP) signal is reported for location in SG E-50A at R3 C60. Axial and circumferential extents are similar to those for SG E-50A R137 C92 (but not related).
One tube SG E-50A R1 17 C66 is reported to contain a volumetric indication at TSH. Axial and circumferential extents are similar to indications discussed above. Modest +Pt amplitude could produce depth of approximately 30%TW. All surrounding tubes were reevaluated; no PLP signals in adjacent tubes.
The source or nature of the loose parts if known Cannot be determined at this point in time.
- 10. Discuss the results of any secondary side inspections.
Batwing inspection completed on SG E-50A/B -no broken batwings identified FOSAR is in progress in SG E-50A and sludge lancing/FOSAR has not started in SG E-50B.
- 11. Discuss any unexpected or unusual results.
Steam Generator E-50A has identified a new damage mechanism which is axial outside diameter stress corrosion cracking (ODSCC) in eggcrates. Per the Steam Generator Program this has been documented in a condition report CR-PLP-2007-04250.
Upon opening of the hot leg manway, water was observed flowing from the cold leg channel head to the hot leg channel head at the lowest point of the divider plate. This was documented in condition report CR-PLP-2007-03956. Videos were taken of the divider plate from both the hot and cold legs. No abnormalities were observed. The design allows for a 12 mill gap and leakage would be expected per our design. The Combustion Engineering steam generator divider plate design does not have welded connections between the divider plate and channel head/tubesheet. The design includes a divider bar, which is welded to the channel head. The divider bar mates with the divider plate by a tongue-in-groove connection and is held in place via set screws all of which are accounted for.
Prinury to Secondary Leakrate ED
- 1:PCS~as:XE-133 Leak rate:gpm #1 :PCS Gas:XE-1 35 Leakrate:gpm 10 2,3 1&2 10-3--
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I I I I* I I I 10 i i I
i i Jul Oct Jan 2007 Apr Jul 2006 Time
Table 4A Palisades REFOUT 19 SG Eddy Current Inspection Scope Mechanism Location Scope I Detection Probe Confirmation Probe Existing and Potential Degradation Mechanisms Axial and Circumferential Expansion transition and 100% hot leg from 3" above to +Pt N/A ODSCC sludge pile 13.5" below TTS Axial and Circumferential Expanded tube in 100% hot leg from 3" above to +Pt N/A PWSCC tubesheet 13.5" below TTS Axial and Circumferential Small radius U-bends 100% Row 1 - 3 U-bends +Pt N/A PWSCC Axial ODSCC Non-dented structures 100% Full length Bobbin +Pt Freespan 100% Full length Bobbin +Pt Freespan Dings <5V 100% Full length Bobbin- +Pt Freespan Dings >5V 100% >5V dings +Pt N/A Eggcrate Dents >2V 100% +Pt N/A VS, DB Dents >3.5V 100% +Pt N/A Wear Eggcrates, Vertical 100% Bobbin +Pt Straps, Diagonal Bars TTS (foreign objects) 100% hot leg, +Pt N/A 3 tubes deep cold leg periphery Freespan (foreign 100% Bobbin +Pt objects) I Pitting Sludge Pile 100% Full length Bobbin +Pt Non-Relevant Degradation Mechanisms Addressed by Inspection Program Axial PWSCC Dented structures 100% eggcrate dents >2V +Pt N/A 100% VS, DB dents >3.5V Circumferential ODSCC Dented structures 100% eggcrate dents >2V +Pt N/A 100% VS, DB dents >3.5V Axial ODSCC Structure wear sites 25% VS, DB historic wear sites +Pt N/A
Special Interest +Pt Testing:
- All newly reported bobbin signals at vertical straps and diagonal bars
- "Boxing" of PLP and freespan SVI signals
" Any freespan bobbin signal exhibiting change from prior inspections
" Any freespan bobbin NQI or DNI signal
" Any bobbin signal reported at an eggcrate
" Any bobbin wear signal >40%TW