Letter Sequence Response to RAI |
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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
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Text
AmerGen.
AmerGen Energy Company, LLC www.exeloncorp.com An Exelon/British Energy Company 200 Exelon Way Suite 345 Kennett Square, PA 19348 10 CFR 50.90 July 11, 2002 2130-02-20187 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Response To Request For Additional Information Technical Specification Change Request No. 308 General Electric Stability Analysis Methodology (TAC No. MB4960)
Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219 This letter provides additional information in response to NRC request for additional information (RAI) dated June 17, 2002 and as discussed in a conference call on June 27, 2002 regarding Oyster Creek Technical Specification Change Request (TSCR) No. 308, submitted to NRC for review on April 26, 2002. As clarified in the conference call held on June 27, 2002, NRC Questions 1 through 8 of the June 17, 2002 RAI are unrelated to the scope of TSCR No. 308 and a docketed response is not required. The additional information regarding the remaining issue is enclosed.
No new regulatory commitments are established by this submittal. If any additional information is needed, please contact David J. Distel (610) 765-5517.
I declare under penalty of perjury that the foregoing is true and correct.
Very truly yours, Executed On Michael P. Gallagher Director, Licensing & Regulatory Affairs Mid Atlantic Regional Operating Group
Enclosure:
Response to Request for Additional Information c:
H. J. Miller, USNRC Administrator, Region I P. S. Tam, USNRC Senior Project Manager, Oyster Creek R. J. Summers, USNRC Senior Resident Inspector, Oyster Creek File No. 02033
ENCLOSURE Oyster Creek Generating Station Response to Request for Additional Information Technical Specification Change Request No. 308 General Electric Stability Analysis Methodology
Oyster Creek Generating Station 2130-02-20187 Enclosure Pagel of 1 NRC Question If your in-house setpoint calculation methodology was previously approved by the NRC, please cite the approval document. If your methodology was not previously reviewed and approved by the NRC, please confirm that it is based on NRC-approved Industry standards, and meets the 95/95 confidence level requirement.
Response
Oyster Creek setpoint calculations are performed in accordance with AmerGen Engineering Standard ES-002. This methodology is based on ISA-67.04(1982) - Set Points for Nuclear Safety Related Instrumentation Used In Nuclear Power Plants. The methodology outlined in the AmerGen standard meets the 95/95 confidence level requirement.