Letter Sequence Other |
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Results
Other: ML020880505, ML021280222, ML021360002, ML021370220, ML021690571, ML022190509, ML022350168, ML022630274, ML022700549, ML022830043, ML022950381, RS-03-034, Delegation of Authority of Amergen Energy Company, LLC (Amergen) Nuclear Power Plants
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MONTHYEARML0205706382002-03-28028 March 2002
Issuance of Amendment Revises the Test Frequency for the Containment Spray Nozzles from Once Per 10 Years to Following Activities That Could Result in Nozzle Blockage
Project stage: Approval
ML0208805052002-03-28028 March 2002
Tech. Spec. Page for Amendment No. 146, Revising the Test Frequency for the Containment Spray Nozzles from Once Per 10 Years to Following Activities That Could Result in Nozzle Blockage
Project stage: Other
ML0212802222002-05-0707 May 2002
Licensing Actions
Project stage: Other
ML0214003812002-05-16016 May 2002
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML0213702202002-05-17017 May 2002
Request Conference Call Proposed Amendment
Project stage: Other
ML0213600052002-06-0404 June 2002
Biweekly Notice Memo, Notice of Issuance of Amendment 151. Amendment Revises Technical Specifications to Be Consistent with Changes Made to 10 CFR 50.59, Changes, Tests, & Experiments
Project stage: Approval
ML0213600022002-06-0404 June 2002
License Amendment, Revising the Technical Specifications to Be Consistent with Changes Made to 10 CFR 50.59, Changes, Tests, and Experiments
Project stage: Other
ML0216905712002-06-0404 June 2002
Tech Specs for Amendment No. 151 Revising the Tech Specs to Be Consistent with Changes Made to 10CFR 50.59, Changes, Tests and Experiments
Project stage: Other
ML0216301202002-06-10010 June 2002
Draft RAI on Your 04/26/02 Amendment Request
Project stage: Draft RAI
ML0220405862002-07-11011 July 2002
Response to Request for Additional Information - Technical Specification Change Request No. 308 General Electric Stability Analysis Methodology
Project stage: Response to RAI
ML0219705332002-07-24024 July 2002
Request for Withholding Information from Public Disclosure, Oyster Creek Nuclear Generating Station
Project stage: Withholding Request Acceptance
ML0222607982002-08-0101 August 2002
Response to Request for Additional Information - Technical Specification Change Request No. 291, Safety Limit Minimum Critical Power Ratio
Project stage: Response to RAI
ML0221905092002-08-0505 August 2002
Conference Call Re. 04/26/02 Proposed Amend
Project stage: Other
ML0222609462002-08-20020 August 2002
Second Request for Additional Information Regarding Your April 26, 2002, Application for Amendment
Project stage: RAI
ML0223501682002-08-23023 August 2002
Site Visit to Address Issues Related to Amendment Application of April 26, 2002
Project stage: Other
ML0224203602002-08-30030 August 2002
Withholding from Public, Response to Request for Additional Information - Technical Specification Change Request No. 291, Safety Limit Minimum Critical Power Ratio, MB5505
Project stage: RAI
ML0226600972002-09-12012 September 2002
Response to Request for Additional Information - Technical Specification Change Request No. 308, General Electric Stability Analysis Methodology
Project stage: Response to RAI
ML0225600192002-09-18018 September 2002
Issuance of Amendment Licensed and Non-Licensed Operating Personnel Training Programs
Project stage: Approval
ML0226302742002-09-18018 September 2002
Oyster Creek,Tech Spec Pages/Amend 232
Project stage: Other
ML0226005292002-09-24024 September 2002
License Amendment Revision to TSs Change Request - Clarification of Requirements for Licensed Operator Qualifications & Training
Project stage: Approval
ML0227005082002-09-24024 September 2002
Tech Spec Pages for Amendment No. 154, Revision to TSs Change Request - Clarification of Requirements for Licensed Operator Qualifications & Training
Project stage: Approval
ML0226805692002-09-26026 September 2002
Issuance of License Amendment Cycle 19 Safety Limit Minimum Critical Power Ratio
Project stage: Approval
ML0227005492002-09-26026 September 2002
Tech Spec Pages for Amendment 233 Cycle 19 Safety Limit Minimum Critical Power Ratio
Project stage: Other
ML0228300432002-10-0909 October 2002
Current TAC List
Project stage: Other
ML0229103652002-10-18018 October 2002
Issuance of Amendment Use of Option II Solution for Reactor Instability Problem
Project stage: Approval
ML0229503812002-10-18018 October 2002
Technical Specification Amendment 235 - 2.3 Limiting Safety System Settings Pages 2.3-1, 2.3-2, 2.3-4, 2.3-5, 2.3-6, 3.1-1, 3.1-7, 3.10-2, 3.10-3, and 3.10-4
Project stage: Other
RS-03-034, Delegation of Authority of Amergen Energy Company, LLC (Amergen) Nuclear Power Plants2003-02-0606 February 2003
Delegation of Authority of Amergen Energy Company, LLC (Amergen) Nuclear Power Plants
Project stage: Other
2002-07-24
[Table View] |
Text
From:
Peter Tam To:
INTernet:David.distel@exeloncorp.com; INTernet:John.Hufnagel@exeloncorp.com Date:
8/5/02 2:08PM
Subject:
Conference call re. 4/26/02 propsoed amend. (TAC MB4960)
John, David:
This is regarding the 4/26/02 amendment request on the BWROGs stability Option II solution methodology. Our reviewer Tai Huang would like to discuss these issues with you ina conference call:
- 1. Provide results and conclusions of the analysis for operation of Oyster Creek in the extended operating region (GE Report MDE-63-0386, "Extended Load Line Limit Analysis for Oyster Creek Nuclear Generating Station," March 1986). Also, provide the ELLLA region in Attachments 1 and 2, and identify the region which is currently restricted from full use of the ELLLA region of the power/flow map because of the flow biased rod block setpoints.
- 2. Provide justification for Oyster Creeks transition to the Generic BWROG Long Term Stability Solution Option II and identify the differences between the current method and the new one recommended by GE for Cycle 19 operation. Also, identify any differences between the BWROG LT Stability Solution Option II and NEDC-33065P and hardware modifications due to this proposed change.
- 3. Describe any impact on the BWROG LT Stability Solution Option II due to 10 CFR Part 21 issue on the Generic DIVOM curve for regional mode oscillations since Option II method using quadrant-based APRM scram to detect and suppress both in-phase and out-of-phase oscillations.
- 4. Provide quantitative results from review of the UFSAR transient events such as rod withdrawal event, loss of feedwater heating, MSIV closure, and startup of an inactive loop at an incorrect temperature and show the old UFSAR results are still valid.
This email aims solely to prepare you for a conference call. Please set this up with me ASAP to support your requested target date of 9/30/02. This email does not formally request for additional information, nor does it convey a formal NRC staff position.
Peter S. Tam, Senior Project Manager Project Directorate I-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation e-mail: pst@nrc.gov Tel.: 301-415-1451 CC:
Tai Huang Mail Envelope Properties (3D4EBF1E.27D : 10 : 20510)
Subject:
Conference call re. 4/26/02 propsoed amend. (TAC MB4960)
Creation Date:
8/5/02 2:08PM From:
Peter Tam Created By:
PST@nrc.gov Recipients Action Date & Time David Transferred 08/05/02 02:08PM distel (INTernet:David.distel@exeloncorp.
John Transferred 08/05/02 02:08PM Hufnagel (INTernet:John.Hufnagel@exelonco nrc.gov owf2_po.OWFN_DO Delivered 08/05/02 02:08PM TLH1 CC (Tai Huang)
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com John INTernet:exeloncorp.
com owf2_po.OWFN_DO 08/05/02 02:08PM nrc.gov Files Size Date & Time MESSAGE 3289 08/05/02 02:08PM Options Auto Delete:
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