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Category:Meeting Summary
MONTHYEARML23199A0262023-07-18018 July 2023 Summary of Public Outreach to Discuss the NRC 2022 End of Cycle Plant Performance Assessment of Point Beach Nuclear Plant, Units 1 and 2 ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 ML22144A0022022-09-14014 September 2022 Summary of February 16, and May 18, 2022, Meetings with Nextera Energy/Florida Power & Light Company Regarding Planned Submittal of License Amendment Request for a Common Fleet Emergency Plan ML22181B1182022-06-30030 June 2022 Summary of the June 23, 2022, Public Outreach to Discuss the NRC 2021 End-of-Cycle Plant Performance Assessment of Point Beach Nuclear Plant, Units 1 and 2 ML22019A2792022-01-20020 January 2022 Summary of Public Webinar with NextEra Energy Point Beach, LLC Regarding Future License Amendment and Exemption Request for Generic Letter 2004-02 Closure for Point Beach Nuclear Plant ML22004A0772022-01-0606 January 2022 Summaries of December 8, 2021 Draft Supplemental Environmental Impact Statement for Subsequent License Renewal Application Public Meetings ML21295A2532021-10-26026 October 2021 Summary of Public Webinar with NextEra Energy Point Beach,Llc Regarding Proposed Future LAR to Adopt TSTF-505, Rev.2, Provide Risk Informed Extended Completion Times-RITSTF Initiative 4B, at Point Beach Plant, Units 1&2 (L-2021-LRM-0086) ML21288A1222021-10-20020 October 2021 SLRA Summary of August 5, 2021, Public Meeting on Proposed Aging Management Activities of Irradiated Concrete and Steel Reactor Vessel Supports ML21214A1652021-08-27027 August 2021 SLRA June 30, 2021, Public Meeting - Proposed Aging Management of Reactor Vessel Internals ML21214A1512021-08-27027 August 2021 SLRA June 3, 2021, Public Meeting - Proposed Aging Management Activities of Irradiated Concrete and Steel Reactor Vessel Supports ML21161A2992021-06-17017 June 2021 Summary of May 18, 2021 Public Webinar with Nextera Energy Point Beach, LLC Regarding Path Forward for Generic Letter 2004-02 Closure ML21166A2192021-06-15015 June 2021 Summary of June 10, 2021, Public Webinar to Discuss the NRC 2020 End-Of-Cycle Plant Performance Assessment of the Point Beach Nuclear Plant ML21148A1162021-06-0101 June 2021 SLRA Public Meeting Discussion Questions 6-3-21 ML21075A3422021-03-17017 March 2021 Meeting Summary: Public Scoping Meeting for the Environmental Review of the Subsequent License Renewal Application for Point Beach Nuclear Plant, Unit Nos. 1 and 2 (EPID No.: L-2020-SLE-0002) - Memo ML21075A3432021-02-17017 February 2021 Meeting Summary: Public Scoping Meeting for the Environmental Review of the Subsequent License Renewal Application for Point Beach Nuclear Plant, Unit Nos. 1 and 2 (EPID No.: L-2020-SLE-0002) - Summary ML20253A1382020-09-11011 September 2020 8/13/2020 Summary of Public Meeting with NextEra Energy Point Beach, LLC Regarding Proposed License Amendment Request for Point Beach Nuclear Plant, Unit 1, Containment Building Truss License Condition Change Due to COVID-19 ML20233A7902020-08-20020 August 2020 Summary of the July 30, 2020, Public Webinar to Discuss the NRC 2019 End-Of-Cycle Plant Performance Assessment of the Duane Arnold Energy Center and the Point Beach Nuclear Plant ML19344A0162019-12-12012 December 2019 Summary of Pre-Application Public Teleconference with Nextera Energy Point Beach, LLC, for Point Beach Nuclear Plant, Units 1 and 2 ML19246A6242019-09-10010 September 2019 Summary of August 14, 2019, Pre-Application Public Teleconference with NextEra Energy Point Beach, LLC, for Point Beach Nuclear Plant, Unit 2 ML19179A0662019-07-17017 July 2019 Summary of Closed Meeting with Nextera Energy, LLC, to Discuss Security-Related Information for Point Beach Nuclear Plant, Unit 1 and 2, and Duane Arnold Energy Center ML19095B7772019-04-0505 April 2019 Summary of Public Outreach/Open House to Discuss the NRC 2018 End-of-Cycle Plant Performance Assessment of Point Beach Nuclear Plant, Units 1 and 2 ML18220B0192018-08-13013 August 2018 7/12/2018 Summary of Meeting with NextEra Energy Point Beach, Llc. to Discuss Supplemental Response to the RAI for Containment Dome Truss License Amendment Request for Point Beach Nuclear Plant, Unit 1 and 2 (CAC Nos. MF9532 & MF9533; ... ML18179A4032018-06-29029 June 2018 Public Meeting Discussion Points ML18136A9052018-05-31031 May 2018 Summary of April 25, 2017, Meeting with Florida Power & Light Company/Nextera Energy Regarding Planned Submittal of Exemption Requests to Support Closure of NRC Generic Safety Issue 191/NRC Generic Letter 2004-02 ML18141A8452018-05-29029 May 2018 Summary of May 1, 2018 Meeting with NextEra Energy Point Beach, LLC, to Discuss License Amendment Request for High Winds Probabilistic Risk Assessment for Point Beach Nuclear Plant, Unit Nos. 1 and 2 ML18121A3142018-05-0101 May 2018 Summary of the April 10, 2018 Public Outreach/Open House for the NRC to Discuss the 2017 End-of-Cycle Plant Performance Assessment of Point Beach Plant, Units 1 and 2 ML17346A9122017-12-22022 December 2017 Summary of November 14, 2017 Public Teleconference with NextEra Energy Point Beach, LLC, to Discuss Containment Dome Truss License Amendment Request for Point Beach Nuclear Plant, Unit Nos. 1 and 2 (CAC Nos. MF9532 and MF9533; EPID L-2017-L ML17310B2062017-11-20020 November 2017 Summary of September 20, 2017, Meeting with Florida Power & Light Company and NextEra Energy Regarding Closure of NRC Generic Safety Issue 191/NRC Generic Letter 2004-02 ML17216A1732017-09-0707 September 2017 Notice of Meeting with Florida Power & Light Company and NextEra Energy to Discuss Closing Out Generic Safety Issue-191 and Generic Letter 2004-02 ML17202U7272017-07-19019 July 2017 Summary of July 11, 2017, Open House to Discuss the 2016 End-Of-Cycle Plant Performance Assessment of Point Beach Nuclear Plant, Units 1 and 2 ML16305A3882016-11-0808 November 2016 Summary of October 18, 2016 Meeting with Nextera Energy Point Beach, Llc, to Discuss Containment Dome Truss License Amendment Request for Point Beach Nuclear Plant, Unit Nos. 1 and 2 (TAC Nos. MF8403 and MF8404) ML16160A1742016-06-0707 June 2016 Summary of Public Meeting with Nextera Energy Point Beach, LLC to Discuss the 2015 End-of-Cycle Plant Performance Assessment of Point Beach Nuclear Plant Units 1 and 2 ML15341A0182015-12-16016 December 2015 Summary of Closed Pre-Application Teleconference with Nextera Energy Point Beach Regarding Steam Generators H* License Amendment Request ML15217A3312015-08-26026 August 2015 July 28, 2015, Summary of Ublic Meeting with NextEra Energy Point Beach, LLC, to Discuss a Proposed Licensing Basis Change for the Turbine-Driven Auxiliary Feedwater Pumps at the Point Beach Nuclear Plant, Units 1 and 2 ML15215A0502015-08-0505 August 2015 Summary of Public Meeting with NextEra Energy Point Beach, LLC, to Discuss Proposed Changes to Containment Dome Truss Design Bases Code for Point Beach Nuclear Plant, Units 1 and 2 ML15121A0572015-05-15015 May 2015 June 9 - 12, 2014 Summary of Audit at Point Beach Nuclear Plant, Unit Nos. 1 and 2, Associated with License Amendment Request to Transition to National Fire Protection Association Standard 805 ML15113B3862015-04-23023 April 2015 April 20, 2015 Summary of Public Outreach/Open House to Discuss the NRC 2014 End-Of-Cycle Plant Performance Assessment of Point Beach Nuclear Plant ML15106A7122015-04-23023 April 2015 Summary of April 6, 2015, Meeting with NextEra Energy Point Beach, LLC, to Discuss License Amendment Request to Transition to NFPA 805 ML14114A1002014-04-23023 April 2014 Summary of Public Meeting to Discuss 2013 Annual Assessment Results for Point Beach Nuclear Plant ML13192A1432013-07-10010 July 2013 6/26/2013 - Summary of Open House to Discuss the 2012 Point Beach Nuclear Plant End-Of-Cycle Performance Assessment ML1212805092012-06-18018 June 2012 May 1, 2012 - Summary of Teleconference with Performance Contracting, Inc., Regarding Large Flume Testing for Point Beach Nuclear Plant ML11173A2332011-06-22022 June 2011 Summary of Public Meeting with NextEra Energy Point Beach, LLC to Discuss the Point Beach Nuclear Plant End-of-Cycle Performance Assessment for 2010 ML1108208272011-04-21021 April 2011 Summary of Pre-application Meeting with NextEra Energy, Inc., and Florida Power & Light Company, on Turkey Point, Units 3 and 4, St. Lucie, Units 1 & 2, Point Beach, Units 1 & 2, Duane Arnold Transition to NFPA-805 ML1014000432010-05-20020 May 2010 Summary of Public Meeting with FPL Energy Point Beach, LLC to Discuss Progress on the Nuclear Excellence Model and Updates on Operational Excellence, Generation Reliability, and Organizational Effectiveness at Point Beach ML1012502352010-05-0505 May 2010 Summary of the April 22, 2010, Public Meeting to Discuss the 2009 Point Beach End-of-Cycle Performance Assessment ML0924305212009-08-31031 August 2009 July 29, 2009,Summary of Public Meeting to Discuss the Progress on Actions Taken in Response to Substantive Cross Cutting Issues and the Results of an Independent Assessment of Corrective Actions for Recent Nuclear Safety Culture Surveys ML0914001932009-05-20020 May 2009 Summary of Public Meeting to Discuss the Progress on Actions Taken in Response to a Nuclear Safety Culture Survey in 2008 - Point Beach Nuclear Plant ML0832308202008-11-20020 November 2008 Teleconference Summary Regarding the 2008 Steam Generator Tube Inspection Results ML0829100932008-11-0606 November 2008 Summary of the October 14, 2008, Pre-Application Meeting with FPL Energy Point Beach, LLC, on the Proposed Alternative Source Term Amendment Request ML0828101262008-10-0707 October 2008 Summary of Meeting Between NRC Region III Management and FPL Energy Point Beach, LLC Representatives to Discuss the Cross-Cutting Issues and Recent Culture Survey 2023-07-18
[Table view] Category:Note
MONTHYEARML13193A0322013-07-11011 July 2013 Additional Equipment Height Information with Vulnerability to Flood Waters ML0832308202008-11-20020 November 2008 Teleconference Summary Regarding the 2008 Steam Generator Tube Inspection Results ML0816908552008-07-0202 July 2008 Telconference Summary Regarding Point Beach Nuclear Plant Proposed Power Uprate and Alternate Source Term Amendment ML0515202522005-05-24024 May 2005 2SI 825B Not Full Open ML0514604102005-05-24024 May 2005 Exit Notes - Holmberg, Riii, Bilik, Riii ML0514604122005-05-24024 May 2005 Exit Notes Holmberg, Riii ML0514604162005-05-24024 May 2005 Exit Notes Pederson, Riii, Holmberg, Riii, Bilik, Riii ML0514700762005-05-24024 May 2005 Note from Individual with 05/27/2004 E-Mail from J. Petrosino, NRR, to H. Heller, Riii ML0515201462005-05-24024 May 2005 Sludge Lance and Phone Line Through Containment Hatch While Fuel Movement in Progress ML0515201512005-05-24024 May 2005 Gas Turbine Reliability Not Meeting FSAR Requirements ML0515202122005-05-24024 May 2005 Questions and Notes ML0515202552005-05-24024 May 2005 Rio Entry 191 Note ML0515202562005-05-24024 May 2005 Outage Stand Down Observations ML0515202602005-05-24024 May 2005 Handwritten Notes ML0508800462005-03-22022 March 2005 Notes for Entrance Meeting ML0508400652005-03-21021 March 2005 Briefing Notes for RCS Vent Path Issue ML0505601182005-02-24024 February 2005 Letter from M. Lintz to File Transmitting e-mail to Point Beach Nuclear Plant ML0502701212005-01-25025 January 2005 Summary of Telephone Conference Held on January 05, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units ML0502606992005-01-19019 January 2005 Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units ML0502602372005-01-19019 January 2005 Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, Llc, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units ML0502602472005-01-19019 January 2005 Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units ML0502603192005-01-19019 January 2005 Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units ML0502603592005-01-19019 January 2005 Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units ML0502606362005-01-19019 January 2005 Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units ML0502700372005-01-19019 January 2005 Summary of Telephone Conference Held on January 14, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Draft Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, ML0502700462005-01-19019 January 2005 Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Draft Requests for Additional Information Pertaining to the Point Beach Nuclear ML0502604732005-01-19019 January 2005 Summary of Telephone Conference Held on January 10, 2005, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC, Concerning Requests for Additional Information Pertaining to the Point Beach Nuclear Plant, Units ML0500601672004-12-16016 December 2004 Summary of Telephone Conference Held on December 15, 2004, Between the U.S. Nuclear Regulatory Commission and Nuclear Management Company, LLC Concerning Draft Requests for Additional Information Pertaining to the Point Beach, Units 1 & 2... ML0430206312004-10-28028 October 2004 Summary of Conference Call with Nuclear Management Company, LLC (NMC) to Discuss Responses to the Severe Accident Mitigation Alternatives (SAMA) Requests for Additional Information (Rais) ML0414602652004-08-0909 August 2004 Summary of Scoping & Screening Group Methodology Audit Preparation Visit Between the NRC & NMC -Concerns Receipt of Requested Staff Documentation for Audit Preparation for the Point Beach Nuclear Plant, Units 1 & 2, LRA ML0515204662004-08-0404 August 2004 Outage Inspection Notes ML0414203162004-05-21021 May 2004 Handwritten Comment Handed to Point Beach Resident Inspector from Cassandra Dixon ML0412801022004-05-0606 May 2004 Note 05/06/2004 to All Region III Facility Training Managers Re Reprint of NRC Form 396 ML0508700512004-04-19019 April 2004 Note to U1R28 Shift Outage Managers from Sr. Management Representative, Work Prior to and During Outage Briefing ML0508700502004-04-19019 April 2004 Shift Outage Manager - Days ML0402300912004-02-10010 February 2004 Memo to File Re Facsimile Transmission for Issue Discussed in Telephone Conference ML0308005832002-11-22022 November 2002 1 Page of Handwritten Notes ML0626801962002-07-0303 July 2002 Note to J. Heller from M. Kunowski (Rill) Re Kewaunee and Point Beach Plants ML0627904142002-06-27027 June 2002 Typed Notes of Phone Call Conversation with Lynn Bartleme, Dznps at Point Beach ML0627903882002-02-23023 February 2002 Individual Interview Regarding Fitness-for-Duty Concern at Kewaunee During a Refuel Outage in 2001 ML0626405682001-11-12012 November 2001 Note to Allegation File from J. Heller, Telephone Contact with Al Capristo, Nuclear Management Company. ML0626801922001-11-0808 November 2001 Note to: USNRC Region III from Anonymous with Handwritten Notes 2013-07-11
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 November 20, 2008 NOTE TO:
FROM:
File Jack Cushing, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor LiCenSingr.-
- y. (/7
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Office of Nuclear Reactor Regulation
SUBJECT:
POINT BEACH NUCLEAR PLANT UNIT 1 - TELECONFERENCE
SUMMARY
REGARDING THE 2008 STEAM GENERATOR TUBE INSPECTION RESULTS (TAC NO. MD9468)
On October 20,2008, the U.S. Nuclear Regulatory Commission staff participated in a conference call with Point Beach Unit 1 representatives regarding their ongoing steam generator (SG) tube inspection activities.
Point Beach Nuclear Plant Unit 1 has two Westinghouse 44F SGs each containing 3214 thermally-treated Alloy 600 tubes. Point Beach Unit 1 SGs were replaced during refueling outage 11 in 1984. The tubes have an outside diameter of 0.875 inches, a wall thickness of 0.050 inches, and are supported by six stainless steel tube support plates and a baffle plate.
The tube support plate holes are quatrefoil-shaped. The U bend region of the tubes in rows 1 through 8 was stress relieved after bending.
The licensee is at the midpoint of the first 60 effective full power month period.
The licensee has identified 98 tubes with potentially high residual stresses based on a review of the bobbin coil eddy current data for an offset. The licensee used the bobbin probe as the primary probe for inspecting these tubes (i.e., there are no routine rotating probe samples of expansion transitions or dent/dings in these tubes).
Material provided by the licensee is enclosed. S,ibsequent to the call, the licensee notified the staff that the total amount of material removed via chemical cleaning and sludge lancing was approximately 7500 and 225 pounds, respectively.
The staff did not identify any issues that required follow-up action at this time; however, the staff asked to be notified in the event that any unusual conditions were detected during the remainder of the outage.
Docket No. 50-266
Enclosure:
Conference Summary
SUMMARY
OF CONFERENCE CALL WITH POINT BEACH UNIT 1 REGARDING THE 2008 STEAM GENERATOR TUBE INSPECTION RESULTS DOCKET NO. 50-266 The staff identified the acronyms used below: U1R31 (Unit 1 Refueling Outage 31), gpm (gallons per minute), gpd (gallons per day), SG (steam generator), C/L (cold leg), H/L (hot leg), TIS (top of tubesheet), AVB (anti vibration bar), BLG (bulge), OXP (overexpansion), R (row), C (column), PWSCC (Primary Water Stress Corrosion Cracking), PLP (Possible Loose Part), ECT (Eddy Current Testing), FOSAR (Foreign Object Search and Retrieval),
UT (Ultrasonic Testing), and MRPC (Motorized Rotating Pancake Coil). The information below was provided by the licensee.
- 1. Discuss any trends in the amount of primary-to-secondary leakage observed during the recently completed cycle.
Unit 1 primary-to-secondary leak-rate remains in the range of approximately 0.00021 gpm or 0.2 to 0.4 gpd and has not changed over several operating cycles including the most recent. The leak cannot be attributed to a specific SG.
- 2. Discuss whether any secondary side pressure tests were performed during the outage and the associated results.
No secondary side pressure tests were conducted.
- 3. Discuss any exceptions taken to industry guidelines.
The site has no exceptions to industry guidelines related to SG inspections.
- 4. For each SG, 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 percent of dents/dings greater than 5 volts and a 20 percent sample between 2 and 5 volts), and the expansion criteria.
Inspections completed to date include +Point rotating probe testing in the tubesheet region. The remainder of the program is discussed in the reply to question 11 and will be completed following chemical cleaning of both SGs.
SG A (Completed)
- -50% H/L tubesheet full depth (Tube end to +3" TIS) with +Point o This includes acquiring 50% of BLG/OXPs in the SG
- 100% C/L periphery (-3 tubes deep) (+/- 3") with +Point
- 50% Low row (R1/R2) U-bends with+Point
- Full Depth tubesheet +Point of Unexpanded tube at R38/C96 SG B (Completed)
- 20% H/L tubesheet full depth with +Point
- 50% H/L tubesheet from tube end to +5" above tube end with +Point Enclosure
-2 o Note that these same tubes were inspected from the top of tubesheet down to 17" at U1R30. Thus, U1R30 and U1R31 inspections complete 50% of the tubesheet full depth by the mid-point of this period.
o Tube population ensures 50% BlG/OXP population is inspected within the tubesheet
- 100% C/l periphery (-3 tubes deep) (+/- 3") with +Point
- 20% low row (R1/R2) U-bends with +Point. No expansion criteria have been met
- 5. For each area examined (e.g., tube supports, dent/dings, sleeves, etc), provide a summary of the number of indications identified to-date for 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 PWSCC at the expansion transition for the first time at this unit).
To date there has been no observed stress corrosion cracking.
Through inspections conducted thus far, tube integrity was not challenged during the previous operating cycle No new degradation mechanism has been observed Only indications known to be present are:
- wear associated with a PlP signal in SG B reported this inspection
- historical wear at anti-vibration bars in the u-bends and at tube supports
- historical wear associated with sludge lance equipment in peripheral tubes
- 6. Describe repair/plugging plans In SG A, tube at R38/C96 was not expanded the full depth of the tubesheet on the H/L.
This tube is being considered for preventative plugging to position the plant for adoption of a permanent alternate repair criterion for the tubesheet region.
- 7. Describe in-situ pressure test and tube pull plans and results (as applicable and if available).
No plans for in-situ pressure tests unless ECT results dictate. No plans for tube pull
- 8. Discuss the following regarding loose parts:
- a. What inspections are performed to detect loose parts Enclosure
-3 All periphery tubes will be inspected using +Point (+1- 3" referenced from the top of tubesheet) on H/l and C/L. This is complimented with a visual FOSAR at the tubesheet to include the annulus, blowdown lane and in-bundle looks.
- b. A description of any loose parts detected and their location within the SG (including the source or nature of the loose part if known)
There currently is only one indication of a loose part in SG B C/l Row 1, column 5, 6, 7. Source and nature are unknown at this point. Post chemical cleaning visuals and retrieval attempt are planned.
- c. If the loose parts were removed from the SG In preparation for chemical cleaning a personnel dosimeter was dropped in SG A, but was located and removed. Additional inspections and removal of parts, including the item in SG B C/l discussed above, will occur following chemical cleaning as applicable.
- d. Indication of tube damage associated with the loose parts For the loose part in SG B C/l at row 1, a preliminary wear indication is present for the tube at Row 1 Column 5 - This will be sized following chemical cleaning.
- 9. Discuss the scope and results of any secondary side inspection and maintenance activities (e.g, in-bundle visual inspections, feedring inspections, sludge lancing, assessing deposit loading, etc).
A full bundle chemical cleaning is being conducted. Following the cleaning, sludge lancing will be performed at the Flow Diverter Baftle (FDB) and tubesheet.
Planned visual inspections in both SGs include:
- Tubesheet cleanliness visuals
- Tubesheet FOSAR activities including resolution of PlP signals from ECT
- FDB and first support plate visuals
- Top (6 th ) support plate visuals to verify and document removal of quatrefoil blockage in selected areas.
- Planned inspections of upper internals including:
- 1. Feedring visuals and UT measurements
- 2. Primary moisture separators visuals and UT measurements
- 3. General area visuals of components and supports.
- 10. Discuss any unexpected or unusual results No unusual or unexpected results
- 11. Provide the schedule for SG-related activities during the remainder of the current outage.
Enclosure
-4 Chemical cleaning is expected to begin on October 20 th ,
Sludge lancing is expected to commence on October 27 th ECT is planned to resume on October 25 th
- This will include a 100% bobbin program of A & B
- 100% Top of Tubesheet H/L +Point
- MRPC +Point of selected AVB wears to determine shape
- Dings/dents in hot and cold legs based on the following criteria:
o Bobbin inspect 5 volts and less in freespan straight sections o +Point >5 volts in freespan straight sections o +Point all dings/dents at tube supports and in u-bends
- Any special interest as a result of bobbin inspections Visuals will commence following sludge lancing on October 28th and will continue through October 31.
Enclosure
November 20, 2008 NOTE TO: File FROM: Jack Cushing, Senior Project Manager IRA!
Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
POINT BEACH NUCLEAR PLANT UNIT 1 - TELECONFERENCE
SUMMARY
REGARDING THE 2008 STEAM GENERATOR TUBE INSPECTION RESULTS (TAC NO. MD9468)
On October 20,2008, the U.S. Nuclear Regulatory Commission staff participated in a conference call with Point Beach Unit 1 representatives regarding their ongoing steam generator (SG) tube inspection activities.
Point Beach Nuclear Plant Unit 1 has two Westinghouse 44F SGs each containing 3214 thermally-treated Alloy 600 tubes. Point Beach Unit 1 SGs were replaced during refueling outage 11 in 1984. The tubes have an outside diameter of 0.875 inches, a wall thickness of 0.050 inches, and are supported by six stainless steel tube support plates and a baffle plate.
The tube support plate holes are quatrefoil-shaped. The U bend region of the tubes in rows 1 through 8 was stress relieved after bending.
The licensee is at the midpoint of the first 60 effective full power month period.
The licensee has identified 98 tubes with potentially high residual stresses based on a review of the bobbin coil eddy current data for an offset. The licensee used the bobbin probe as the primary probe for inspecting these tubes (i.e., there are no routine rotating probe samples of expansion transitions or dent/dings in these tubes).
Material provided by the licensee is enclosed. Subsequent to the call, the licensee notified the staff that the total amount of material removed via chemical cleaning and sludge lancing was approximately 7500 and 225 pounds, respectively.
The staff did not identify any issues that required follow-up action at this time; however, the staff asked to be notified in the event that any unusual conditions were detected during the remainder of the outage.
Docket No. 50-266
Enclosure:
Conference Summary DISTRIBUTION:
PUBLIC JCushing,NRR RKrsek Rill LJames, NRR RidsNrrLATHarris AHiser, NRR KKarwoski, NRR AObodoako NRR ADAMS A ccession . N 0.: ML083230820 *b>y memo ML083170563 OFFICE LPL3-1/PM LPL3-1/LA *CSGB/BC LPL3-1/BC NAME Jcushino THarris.J~H~ AHiser LJames 7f:!, '1 DATE 11/18/08 111<<'D 108 11/12/08 11/20 108 OFFICIAL RECORD COPY