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Other: ML062080142, ML062480361, ML062480362, ML062480381, ML062480383, ML062480388, ML062480391, ML062510295, ML062510296, ML062510299, ML062510302, ML062510306, ML062510307, ML062510324, ML062510346, ML062510350, ML062510355, ML062510359, ML062510361, ML063050380, ML063050385, ML063050388, ML063050392, ML063050396, ML063050501, ML063050504, ML063050506, ML063050512, ML063050514, ML063050518, ML063050603, ML063050610, ML063050613, ML063060239, ML063060249, ML063060259, ML063060267, ML063060296, ML063060299, ML063060302, ML063060309, ML063060322, ML063070187, ML063070190, ML063070217, ML063070219, ML063070220, ML063070222, ML063070225, ML063070232... further results
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Category:E-Mail
MONTHYEARML22335A2802022-11-0404 November 2022 11-4-2022 Email Transmitting Draft Questions Pertaining to Pilgrim ISFSI Exemption Request ML22270A0422022-09-26026 September 2022 Acknowledgement Email for Holtec'S Request for Reporting Exemption with Regards to the Pilgrim ISFSI Annual Radioactive Effluent Release Report (Docket No. 05000293) ML22154A1622022-05-26026 May 2022 Letter and Email from Save Our Bay/Diane Turco Regarding Irradiated Water Release from Pilgrim ML22007A2602021-12-0606 December 2021 E-mail from P. O'Brien, Holtec, to A. Snyder, NRC, on Pilgrim Effluent Discharge ML21287A6192021-10-14014 October 2021 E-mail from S. Phillips, MEMA, to A. Snyder, NRC, Pilgrim Nuclear Power Station, Commonwealth of Massachusetts Consultation Response to Amendment Review for Emergency Preparedness ML21266A2512021-09-23023 September 2021 Consultation with Commonwealth of Massachusetts Regarding Proposed Amendment Application for Emergency Plan and Emergency Action Levels ML21266A2772021-09-23023 September 2021 HDI Clarification of Exemption Requested from 10 CFR 20, Appendix G, Section Iii.E ML21267A0012021-09-23023 September 2021 E-mail from A. Snyder, NRC, to A. Sterdis, Holtec, - Pilgrim Nuclear Power Station - Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E Acceptance Review ML21257A3832021-09-15015 September 2021 E-mail from A. Snyder, NRC, to A. Sterdis, Holtec, - Pilgrim Nuclear Power Station - Follow-on Request Re Request for Additional Information 2 Pilgrim - License Amendment Request Independent Spent Fuel Storage Installation Only Emergency Pl ML21211A5912021-07-22022 July 2021 Consultation Response from Commonwealth of Massachusetts Regarding Proposed Pilgrim ISFSI Only Technical Specifications ML21211A5162021-07-22022 July 2021 Consultation Response from Commonwealth of Massachusetts Regarding Proposed Pilgrim ISFSI Only Physical Security Plan ML21200A2352021-07-13013 July 2021 Consultation Request to Commonwealth of Massachusetts Regarding Proposed Pilgrim ISFSI Only Technical Specifications ML21200A1522021-07-13013 July 2021 Consultation Request to Commonwealth of Massachusetts Regarding Proposed Pilgrim Isfi Only Physical Security Plan ML21176A1842021-06-25025 June 2021 Email from HDI Regarding Pilgrim Nuclear Power Station Training ML21180A0582021-06-17017 June 2021 Email from Region I Regarding Pilgrim Nuclear Power Station Inspection - EA-13-132 ML21097A0402021-04-0606 April 2021 E-Mail Consult with Commonwealth of Mass Re - Amendment Application - Physical Security Plan for the Pilgrim Nuclear Power Station L-20-092, Email Pilgrim Nuclear Power Station-Exemption from Annual Force-On-Force Exercise Requirements of 10 CFR Part 73, Appendix B,2020-12-10010 December 2020 Email Pilgrim Nuclear Power Station-Exemption from Annual Force-On-Force Exercise Requirements of 10 CFR Part 73, Appendix B, L-20-096, Supplemental Information to Support Physical Security Plan Revision and License Amendment Request to Incorporate Alternate Measures - Holtec Email Dated December 10, 20102020-12-10010 December 2020 Supplemental Information to Support Physical Security Plan Revision and License Amendment Request to Incorporate Alternate Measures - Holtec Email Dated December 10, 2010 ML20328A2982020-11-16016 November 2020 Response from Commonwealth of Massachusetts on No Significant Hazard for Pilgrim ISFSI Amendment to Address ISFSI II Dated November 16, 2020 ML20297A2372020-10-22022 October 2020 Request for Additional Information - HDI Fleet Decommissioning Quality Assurance Program ML20266G4032020-09-22022 September 2020 Acceptance Review Email - Request for Approval of HDI Fleet Decommissioning Quality Assurance Program, Revision 0 ML20163A6802020-06-11011 June 2020 Confirmation of the Scope of the Requested Regulatory Relief for Pilgrim Security Qualifications ML20280A1912020-04-17017 April 2020 Request for Additional Information- Clarifying Information for Pilgrim ISFSI Physical Security Amendment Application ML20269A3542020-03-0505 March 2020 CFR 26.717 Reports 2019 Transmittal Email ML19336A0302019-11-27027 November 2019 OEDO-15-00479 - Re 2.206 Petition Regarding Pilgrim Nuclear Power Station'S Current Licensing Basis for Flooding ML19336A0332019-11-26026 November 2019 OEDO-15-00479 - E-mail to Petitioner - 2.206 Petition Regarding Pilgrim Nuclear Power Station'S Current Licensing Basis for Flooding (CAC No. MF6460; EPID L-2015-CRS-0002)- Issuance of Final Director'S Decision ML19331A1952019-11-21021 November 2019 NRR E-mail Capture - (External_Sender) Pilgrim Nuclear Power Station - Commonwealth Consultation Response - Amendment Regarding Site Emergency Plan and Emergency Action Level Scheme ML19331A1732019-11-12012 November 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station -Consult with Commonwealth - Amendment Regarding Cyber Security Plan ML19331A1642019-11-0505 November 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station -Consult with Commonwealth - Amendment Regarding Site Emergency Plan and Emergency Action Level Scheme ML19331A1792019-11-0505 November 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station - EA and Fonsi for Pilgrim Emergency Planning Exemption CY-19-007, LTR-19-0441 Henrietta Cosentino, E-mail SECY-19-0078 Request by Entergy Nuclear Operations Inc. for Exemptions from Certain Emergency Planning Requirements for the Pilgrim Nuclear Power Station2019-11-0404 November 2019 LTR-19-0441 Henrietta Cosentino, E-mail SECY-19-0078 Request by Entergy Nuclear Operations Inc. for Exemptions from Certain Emergency Planning Requirements for the Pilgrim Nuclear Power Station ML19275H1962019-09-24024 September 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station - Consult with Commonwealth - Amendment Regarding Permanently Defueled Technical Specifications (PDTS) ML19239A0372019-08-26026 August 2019 E-mail from Entergy Dated August 26, 2019, Notification of Pilgrim License Transfer ML19239A0262019-08-23023 August 2019 LTR-19-0330 Janet Azarovitz, E-mail a Plea for More Time and Reasonable Discussion Including the Citizens of the Commonwealth in the Sale of the Pilgrim Nuclear Power Station ML19234A2072019-08-20020 August 2019 LTR-19-0328 Lawrence Delafield, President, Six Ponds Improv Assoc., Plymouth, Ma, Ltr Requests NRC to Postpone Consideration of Transferring the Licenses for the Pilgrim Nuclear Power Until the NRC Has Answered Concerns by Pilgrim Watch, Se ML19232A4032019-08-20020 August 2019 LTR-19-0322 Diane Turco, Director, Cape Downwinders, Massachusetts, Letter/E-mail Requests Suspension of the Pilgrim License Transfer from Entergy to Holtec Until the Adjudicatory Hearing Is Held and Raised Contentions Are Resolved ML19308A9942019-08-19019 August 2019 Entergy Nuclear Operations, Inc. Confirmatory Order Rescission Supplemental Information ML19226A3912019-08-14014 August 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station - EA and Fonsi for Pilgrim Decommissioning Trust Fund Exemption (Holtec) ML19226A3962019-08-14014 August 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station -Consult with Commonwealth - Conforming Amendment in Support of Pilgrim License Transfer Application ML19226A1212019-08-13013 August 2019 OEDO-15-00479-2.206 Petition Regarding Pilgrim Nuclear Power Station'S Current Licensing Basis for Flooding - Status (CAC No. MF6460; EPID L-2015-CRS-0002) ML19227A1032019-08-0707 August 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station - Draft Wording for Potential Condition of License Transfer Order ML19207B3662019-07-26026 July 2019 NRR E-mail Capture - Pilgrim - RAI Direct and Indirect Transfer of Lic.; Conforming Lic. Amend.; Req. for Exemption 10 CFR 50.82(A)(8)(I)(A) for Holtec Decom. International, Llc ML19176A3452019-06-25025 June 2019 2.206 Petition Regarding Pilgrim Nuclear Power Station'S Current Licensing Basis for Flooding - Information (OEDO-15-00479) (CAC No. MF6460; EPID L-2015-CRS-0002) ML19154A0652019-06-0303 June 2019 NRR E-mail Capture - Pilgrim - Permanent Cessation of Power Operations ML19154A5242019-06-0303 June 2019 NRR E-mail Capture - RAI - Pilgrim Post-Decommissioning Technical Specifications (PDTS) License Amendment Request (LAR) ML19161A2122019-05-20020 May 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station - Acceptance of License Amendment Request to Remove Cyber Security Plan Requirements ML19123A0332019-05-0101 May 2019 NRR E-mail Capture - Logbook Entry: 05/01/2019 Endangered Species Report Regarding a Confirmed Sighting of North Atlantic Right Whale(S) (Balaena Glacialis) ML19122A4912019-04-29029 April 2019 NRR E-mail Capture - Logbook Entry: 04/29/2019 Regarding the Confirmed Sighting of Ten North Atlantic Right Whales (Balaena Glacialis) ML19108A2372019-04-18018 April 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station - Acceptance of Requested Licensing Action, Proposed Exemptions from 10 CFR 50.54(w)(1) - On-Site Property Damage Insurance ML19108A2362019-04-18018 April 2019 NRR E-mail Capture - Pilgrim Nuclear Power Station - Acceptance of Requested Licensing Action, Proposed Exemptions from 10 CFR 140.11(a)(4) - Primary and Secondary Liability Insurance 2022-09-26
[Table view] Category:Letter
MONTHYEARL-24-002, Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G2024-02-0202 February 2024 Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G ML23342A1182024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23334A1822023-11-30030 November 2023 Biennial Report for the Defueled Safety Analysis Report Update, Technical Specification Bases Changes, 10 CFR 50.59 Evaluation Summary, and Regulatory Commitment Change Summary November 2021 Through October 2023 L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) L-23-011, 10 CFR 72.48 Biennial Change Summary Report2023-10-27027 October 2023 10 CFR 72.48 Biennial Change Summary Report IR 05000293/20234012023-08-31031 August 2023 NRC Inspection Report No. 05000293/2023401 & 2023001 (Cover Letter Only) IR 05000293/20230022023-08-0404 August 2023 NRC Inspection Report No. 05000293/2023002 L-23-008, Correction to Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations Holtec Decommissioning International, LLC (HDI)2023-05-23023 May 2023 Correction to Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations Holtec Decommissioning International, LLC (HDI) ML23136A7792023-05-15015 May 2023 Annual Radiological Environmental Operating Report, January 1 Through December 31, 2022 ML23135A2152023-05-15015 May 2023 Annual Radioactive Effluent Release Report, January 1 Through December 31, 2022 L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance ML23069A2782023-03-13013 March 2023 Request for Scoping Comments Concerning the Environmental Review of Monticello Nuclear Generating Plant, Unit 1 Subsequent License Renewal Application ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities IR 05000293/20220042023-02-15015 February 2023 NRC Inspection Report No. 05000293/2022004 ML22356A0712023-01-31031 January 2023 Issuance of Exemption for Pilgrim Nuclear Power Station ISFSI Regarding Annual Radioactive Effluent Release Report - Cover Letter ML22347A2782022-12-21021 December 2022 Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022 L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 L-22-041, Supplemental Information to Enhance Exemption Request Detail for Pilgrim ISFSI Annual Radioactive Effluent Release Report Due Date Extension2022-12-0909 December 2022 Supplemental Information to Enhance Exemption Request Detail for Pilgrim ISFSI Annual Radioactive Effluent Release Report Due Date Extension IR 05000293/20220032022-11-18018 November 2022 NRC Inspection Report No. 05000293/2022003 L-22-036, Decommissioning Trust Fund Agreement2022-11-0808 November 2022 Decommissioning Trust Fund Agreement ML22276A1762022-10-24024 October 2022 Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22266A1922022-09-23023 September 2022 and Pilgrim Nuclear Power Station - Request to Withdraw Prior Submissions from NRC Consideration ML22272A0352022-09-22022 September 2022 S. Lynch-Benttinen Letter Regarding U.S. Citizen Intent to Sue U.S. Fish and Wildlife and NOAA Fisheries Representing the Endangered Species (Na Right Whale) Which Will Be Adversely Affected by Holtec International Potential Actions ML22269A4202022-09-22022 September 2022 Citizen Lawsuit ML22241A1122022-08-29029 August 2022 Request for Exemption from 10 CFR 72.212(a)(2), (b)(2), (b)(3), (b)(4), (B)(5)(i), (b)(11), and 72.214 for Pilgrim ISFSI Annual Radioactive Effluent Release Report IR 05000293/20220022022-08-12012 August 2022 NRC Inspection Report No. 05000293/2022002 ML22215A1772022-08-0303 August 2022 Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages ML22206A1512022-08-0101 August 2022 NRC Office of Investigations Case Nos. 1-2022-002 & 1-2022-006 ML22221A2592022-08-0101 August 2022 LTR-22-0217-1-NMSS - Town of Duxbury Letter Opposing the Irradiated Water Release from Pilgrim (Docket No. 05000293) ML22193A1662022-07-28028 July 2022 LTR-22-0154-1 - Heather Govern, VP, Clean Air and Water Program, Et Al., Letter Regarding Radioactive Wastewater Disposal from the Pilgrim Nuclear Power Station (Docket No. 05000293) ML22175A1732022-07-28028 July 2022 LTR-22-0153-1 - Response Letter to D. Turco, Cape Downwinders, from A. Roberts, NRC, Regarding Holtec-Pilgrim Plans to Dump One Million Gallons of Radioactive Waste Into Cape Cod Bay ML22154A4882022-06-0101 June 2022 Letter from Conservation Law Foundation Regarding Irradiated Water Release from Pilgrim ML22154A1622022-05-26026 May 2022 Letter and Email from Save Our Bay/Diane Turco Regarding Irradiated Water Release from Pilgrim ML22136A2602022-05-16016 May 2022 Submittal of Annual Radiological Environmental Operating Report for January 1 Through December 31, 2021 ML22136A2572022-05-16016 May 2022 Submittal of Annual Radioactive Effluent Release Report for January 1 Through December 31, 2021 ML22102A0932022-05-12012 May 2022 LTR-22-0067 Response to Matthew P. Levesque, President, Barnstable Town Council Regarding Irradiated Water Release from Pilgrim IR 05000293/20220012022-05-11011 May 2022 NRC Inspection Report No. 05000293/2022001 ML22104A0542022-04-30030 April 2022 LTR-22-0093 Response to Sheila Lynch-Benttinen, Regarding Irradiated Water Release from Pilgrim L-22-026, Occupational Radiation Exposure Data Report - 20212022-04-29029 April 2022 Occupational Radiation Exposure Data Report - 2021 ML22152A2592022-04-25025 April 2022 Zaccagnini Letter Dated 04/25/22 ML22152A2642022-04-19019 April 2022 Flynn Letter Dated 04/19/22 ML22091A1062022-04-0101 April 2022 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) L-22-022, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec.2022-03-25025 March 2022 and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec. ML22130A6762022-03-14014 March 2022 Decola Ltr Dtd 03/14/22 Re Potential Discharge of Radioactive Water from Pilgrim Nuclear Power Station ML22041B0762022-03-0707 March 2022 03-07-22 - Letter to the Honorable William R. Keating, Responds to Letter Regarding Proposed Release of Irradiated Water at Pilgrim Nuclear Power Station Into Cape Cod Bay ML22054A2962022-02-23023 February 2022 Annual ISFSI Radioactive Effluent Release Report for 2021 2024-02-02
[Table view] |
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LKent Howard - FW: LRA Amendment 2 (Updated Drell Shell Information) Pagel1 From: "Ellis, Douglas" <dellisl @entergy.com>
To: "Ram Subbaratnam" <RXS2@nrc.gov>
Date: 6/8/2006 1:29:26 PM
Subject:
FW: LRA Amendment 2 (Updated Drywell Shell Information)
Ram - here is the updated Drywell Shell Information letter.
You will be getting a hard copy in the mail, and the original has been mailed to the Document Control Desk.
Doug Ellis, Pilgrim Licensing.
Original Message -----
From: PNP616_DoNotReply@entergy.com
entergy.com
Sent: Thursday, June 08, 2006 7:38 AM To: Ellis, Douglas; Ellis, Douglas
Subject:
206049 Please open the attached document. It was scanned and sent to you using a Xerox WorkCentre Pro.
Sent by: Guest [PNP616_DoNotReply@entergy.com]
Number of Images: 9 Attachment File Type: PDF WorkCentre Pro Location: ESB 2nd FI Licensing Device Name: PNP616 For more information on Xerox products and solutions, please visit http://www.xerox.com
Lc:\temp\GW}00001 .TMP __fagI Mail Envelope Properties (44885E6C.420: 12 : 58400)
Subject:
FW: LRA Amendment 2 (Updated Drywell Shell Information)
Creation Date 6/8/2006 1:26:48 PM From: "Ellis, Douglas" <dellisl @entergy.com>
Created By: dellis 1@entergy.com Recipients nrc.gov TWGWPO02.HQGWDO01 RXS2 (Ram Subbaratnam)
Post Office Route TWGWPO02.HQGWDO01 nrc.gov Files Size Date & Time MESSAGE 748 6/8/2006 1:26:48 PM 20604001.PDF 587846 Mime.822 1 Options Expiration Date: None Priority: Standard ReplyRequested: No Return Notification: None Concealed
Subject:
No Security: Standard Junk Mail Handling Evaluation Results Message is eligible for Junk Mail handling This message was not classified as Junk Mail Junk Mail settings when this message was delivered Junk Mail handling disabled by User Junk Mail handling disabled by Administrator Junk List is not enabled Junk Mail using personal address books is not enabled Block List is not enabled
Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 Michael A. Balduzzi Site Vice President June 7, 2006 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 License Renewal Application, Amendment 2
REFERENCE:
Entergy letter to U.S. NRC, License Renewal Application, Amendment 1, dated May 11, 2006, Letter No. 2.06.040 LETTER NUMBER: 2.06.049
Dear Sir or Madam:
Based on recent discussions between industry and the NRC staff, Entergy provided additional information concerning the drywell shell in the referenced letter. The attachment of this letter provides more detail regarding specific elevations (i.e. addition of inches) in the "Operating Experience and Actions Taken to Prevent Drywell Corrosion" section of the attached information on the drywell shell. For convenience, change bars are included to assist in identifying these specific elevations. Moreover, this letter replaces the figure of the sand pocket (page 6 of 6 of the attachment contained in the referenced letter) with a nearly identical figure that is more legible.
This letter contains no commitments.
Please contact Bryan Ford, (508) 830-8403, if you have any questions regarding this subject.
I declare under penalty of perjury that the foregoing is true and correct. Executed on June 7, 2006.
Sincerely, Michael A. Balduzzi DWE/dm Attachments: Pilgrim Nuclear Power Station Drywell Shell Information (6 pages)
Entergy Nuclear Operations, Inc. Letter Number: 2.06.049 Pilgrim Nuclear Power Station Page 2 cc: with Attachment Mr. Ram Subbaratnam Mr. Joseph Rogers Project Manager Commonwealth of Massachusetts U.S. Nuclear Regulatory Commission Assistant Attorney General Office 0-11 F1 Division Chief, Utilities Division 11555 Rockville Pike 1 Ashburton Place Rockville, MD 20852 Boston, MA 02108 Mr. James Shea, Project Manager Mr. Robert Walker, Director Plant Licensing Branch I-1 Massachusetts Department of Public Health Division of Operator Reactor Licensing Radiation Control Program Office of Nuclear Reactor Regulation 90 Washington Street, 2 nd Floor U.S. Nuclear Regulatory Commission Dorchester, MA 02121 One White Flint North O-8C2 11555 Rockville Pike Rockville, MD 20852 Mr. Jack Strosnider, Director Ms. Cristine McCombs, Director Office of Nuclear Material and Safeguards Massachusetts Emergency Management Agency U.S. Nuclear Regulatory Commission 400 Worchester Road Washington, DC 20555-00001 Framingham, MA 01702 Mr. Samuel J. Collins Mr. James Dyer, Director Regional Administrator, Region 1 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission 475 Allendale Road Washington, DC 20555-00001 King of Prussia, PA 19406-1415 NRC Resident Inspector Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 206049
Attachment to Letter Number 2.06.049 Pilgrim Nuclear Power Station Drywell Shell Information
Pilgrim Nuclear Power Station Drywell Shell Information Purpose For license renewal, the NRC evaluates the potential for corrosion of the Mark I steel containment drywell shell. This issue previously was the subject of generic NRC communications in the 1980s. Specifically, Generic Letter (GL) 87-05 addressed potential degradation of Mark I drywells due to corrosion. The following provides additional information on the Pilgrim Station drywell shell relative to recent industry experience in this area.
Background
In 1980, the Oyster Creek Station observed water coming from lines that drain water from the annulus region between the drywell wall and the surrounding concrete and the sand cushion region. The water source was initially identified in 1983 as coming from the Drywell-Refueling Cavity. bellows drain line gasket. After performing ultrasonic thickness measurements in 1986, Oyster Creek Station reported that corrosion and material loss had occurred to the Drywell Shell in the area of the sand-cushion. This finding led to the issuance of NRC Information Notice 86-99, "Degradation of Steel Containments," Generic Letter 87-05, "Request for Additional Information - Assessment of Licensee Measures to Mitigate and/or Identify Potential Degradation of Mark I Drywells," and Information Notice 86-99 Supplement 1.
The purpose of GL 87-05 was "...to initiate the collection of information of the licensee's current and proposed action to assure the degradation of the Drywell Shell plates adjacent to the sand-cushion has not occurred and to determine if augmented inspections above and beyond those planned by the licensee's are necessary."
In 1995, subsequent to the GL responses, the staff approved the use of ASME Section XI, Subsection IWE (Requirements for Class MC and Metallic Liners of Class CC Components of Light-Water Cooled Plants) which exempts, in accordance with Subparagraph IWE-1220(b), "embedded or inaccessible portions of containment vessels, parts, and appurtenances that met the requirements of the original Construction Code..." However, Paragraph IWE-1240 establishes criteria for determining the need for augmented examinations.
PNPS Primary Containment Design PNPS employs a low-leakage pressure suppression system which houses the reactor vessel, the reactor coolant recirculation loops, and other branch connections of the reactor primary system. The pressure suppression system consists of a drywell, a pressure suppression chamber containing a large volume of water, a connecting vent system between the drywell and the pressure suppression chamber, isolation valves, vacuum relief system, containment cooling systems, and other service equipment.
The drywell is a light bulb-shaped carbon steel primary containment structure with a spherical lower portion, 64 feet in diameter, and a cylindrical upper portion 34 feet 2 inches in diameter. The overall height is approximately 110 feet. The drywell is enclosed in reinforced concrete for shielding purposes and to provide additional resistance to deformation and buckling in areas where the concrete backs up the steel shell. Shielding above the drywell is provided by removable, segmented, reinforced concrete shield plugs 1 of 6
Pilgrim Nuclear Power Station Drywell Shell Information located on the reactor building refuel floor. The reinforced concrete drywell floor contains the drywell floor drain and equipment drain sumps and supports the reactor pedestal.
The design, fabrication, inspection, and testing of the drywell complies with requirements of the ASME Boiler & Pressure Vessel Code,Section III, Subsection B, Requirements for Class B Vessels, which pertain to containment vessels for nuclear power stations.
Drywell Shell Exterior The sand cushion at the base of the drywell is designed to provide a smooth transition to reduce thermal and mechanical discontinuities. The sand provides lateral support to the drywell in this region. The sand cushion area is drained to protect the exterior surface of the drywell shell at the sand cushion interface from water that might enter the air gap.
The coating specified for the PNPS drywell shell exterior surfaces was an alkyd-base primer (red lead or zinc chromate). No degradation of this coating in the sand cushion area was noted in 1987 when fiberscopes were used to examine the 4 inch annulus air gap drain lines.
To ensure the drywell shell exterior remains dry during refueling evolutions, the drywell to reactor building bellows assembly separates the refueling cavity filled with water from the exterior surface of the drywell shell. Any leakage through the bellows assembly is directed to a drain system (refueling: bellows seal trough drains) which is equipped with an alarm for notification of operators.
The drywell exterior surface is essentially inaccessible for inspection. Surfaces that are accessible for examination include the drywell hemispherical head exterior surfaces and some penetrations in the structure.
Drywell Shell Interior The majority of the upper portion of the drywell shell interior surfaces are accessible for inspection, except the lower portion of the drywell where it-is covered by the concrete drywell floor which provides structural support for the reactor pedestal and other equipment.
The PNPS primary containment system is inerted with nitrogen gas during normal power operations so that oxygen levels are maintained at less than 4%. Inerting with nitrogen provides an atmosphere that is not conducive to corrosion of containment interior surfaces.
Operatingq Experience and Actions Taken to Prevent Drvwell Corrosion There has been no observed leakage causing moisture in the vicinity of the sand cushion at PNPS and no moisture has been detected or is suspected on the inaccessible areas of the drywell shell. Further, as discussed above, any potential leakage through the refueling bellows assembly is directed to a drain system. Therefore, no additional components have been identified that require aging management review as a source of moisture that might affect the drywell shell in the lower region.
As stated in the response to GL 87-05, PNPS performed UT thickness measurements of the drywell shell in January 1987. The UT thickness measurements were taken at twelve 2 of 6
Pilgrim Nuclear Power Station Drywell Shell Information locations directly above the sand cushion region. These measurements detected no loss of wall thickness.
PNPS verified that the annulus air gap drain lines are unobstructed. In 1987, access holes were machined in the drain line elbows on all four drain lines to allow access for remote visual examination using fiberscopes. This inspection determined that the four annulus air gap drains are unobstructed and found no signs of corrosion on visible portions of the drywell surface.
PNPS monitors the annulus air gap drains during every refueling outage.
PNPS performed additional UT thickness measurements adjacent to the sand cushion region at the 9 foot 1 inch elevation in 1999 and 2001. The sand cushion region of the drywell shell is inaccessible unless concrete is removed. For the examinations in 1999 and 2001, concrete at the periphery of the 9 foot 2 inch elevation was chipped away to allow UT I wall thickness measurements of the drywell shell to be taken at the level of the upper sand cushion. These examinations are destructive in nature and are performed in a high radiation area. The areas were then re-grouted prior to resuming operations. The observed wall thickness readings showed the drywell wall thickness in these areas to be essentially as-built. Based on the following four factors, PNPS removed UT thickness measurements in the sand cushion region from the IWE program after the 2001 outage:
- Satisfactory results from monitoring for leakage from the annulus air gap drains.
" Satisfactory drywell wall thickness at the 9 foot 1 inch elevation sand cushion region I (and upper drywell) after 27 years of operation (as of 1999).
" High radiation exists in areas of sand cushion UT exams.
" The potential for damage to the drywell shell from concrete removal tools used to facilitate the examinations.
Ongoinq Actions to Prevent Drywell Corrosion The following ongoing actions are being taken to prevent and identify drywell corrosion:
- PNPS monitors the four annulus air gap drains twice every refuel outage, once after floodup and again prior to flooddown at the end of the outage. Leakage has never been detected from the annulus air gap drains at PNPS.
" Functional checks are performed each refueling outage on the flow switch associated with the bellows seal leakage monitoring system.
- Drywell interior surfaces are examined for degradation every refueling outage as required by Technical Specification 4.7.A.2.d. Additionally, drywell interior surfaces are examined every other outage in accordance with the PNPS IWE Program.
Drywell structures are examined in accordance with ASME Section Xl - 1998 Edition with 2000 Addenda, Subsection IWE, Requirements for Class MC and Metallic Liners of Class CC Components of Light-Water Cooled Plants. Since IWE 3 of 6
Pilgrim Nuclear Power Station Drywell Shell Information requirements were mandated in 1996, no areas have been identified that exceeded code acceptance criteria on the drywell interior surfaces during these inspections.
- PNPS inspects the liner drains for the water reservoirs on the refuel floor (e.g., spent fuel pool, dryer/separator pool, and reactor cavity) for leakage. Leakage into the liner drains could be a precursor for water leaks which could wet the drywell shell exterior surface. These drains are examined for leakage after filling the refueling cavity.
- Paragraph IWE-1242 of the ASME Xl code states that surface areas likely to experience accelerated degradation and aging require augmented examination.
These examinations are included in the PNPS ISI Program along with other containment examinations. The IWE requirements for augmented examination are required by 10 CFR 50.55a.
The code requires owners to identify locations they believe are suspect. or potential problem areas for augmented inspection. After a review of PNPS drywell construction methods, PNPS identified various locations for augmented examination.
The presence of ethafoam rings left in place at certain elevations of the drywell caused a concern that they could trap and hold leakage from the bellows or fuel pool and cause corrosion of the shell outer surface. For this reason, augmented UT examinations in the upper drywell at elevations 72 feet and 83 feet (four locations at each elevation) were performed in vertical strips to ensure the region of'interest was examined. The examinations performed in 1999 and 2001 revealed no degradation of the drywell shell thickness in the upper drywell.
- UT thickness examinations will continue to be performed under the PNPS IWE program at two locations in the upper drywell immediately adjacent to the fuel pool due to the potential for leakage from the fuel pool liner.
- The drywell shell to floor joint'is inspected under the PNPS IWE Program.
Conclusion PNPS has effectively addressed the issue of drywell shell corrosion through actions taken in response to GL 87-05 as well as additional actions subsequent to the response to GL 87-05.
UT examinations to determine the drywell wall thickness at the sand cushion region and upper drywell indicated no detectable loss of material and hence no discernable corrosion rate. Based on this corrosion rate, no discernable loss of drywell shell thickness is projected through the period of extended operation. The above described ongoing actions to prevent drywell shell degradation provide continuing reasonable assurance of satisfactory drywell shell condition through the period of extended operation.
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Pilgrim Nuclear Power Station Drywell Shell Information II Taken from ISIIWEAUG1 5 of 6
PILGRIM NUCLEAR POWER STATION DRYWELL INFORMATION SAND FILL COMPACTED TO 0.8 VOID RATIO--
EL SAND POCKET TAKEN FROM PNPS DWG. C-71 6 of 6