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Category:E-Mail
MONTHYEARML21075A1582021-03-15015 March 2021
E-mail from T. Silko to J. Parrott, NMSS, Vermont Yankee on the State of Vermont Comments on the Review of the Draft Final SER and EA for 20.2002 Alternate Disposal Request
ML21006A0242020-12-22022 December 2020
E-mail from J. Parrott to J. Tierney and N. Creed Vermont Yankee Request to NRC for Alternate Disposal of Wastewater
ML20358A0702020-12-22022 December 2020
E-mail Acceptance Review for Request for Indirect License Transfer (License DPR-28, Docket No. 50-271)
ML20175A2122020-06-23023 June 2020
Acceptance Review of Request for Alternate Disposal of Wastes Under 10 CFR 20.2002 (License DPR-28, Docket No. 50-271)
ML19289A1292019-10-11011 October 2019
Email from Daniel Doyle to Mark Leyse Status of PRM-50-93 and PRM-50-95
ML19288A0292019-10-11011 October 2019
NRC Acceptance Review - Northstar Request for Exemption from 10 CFR 20, App G, Section Iii.E (License DPR-28, Docket No. 50-271)
ML19198A2512019-06-20020 June 2019
Alternate Disposal Request - Rail Shipments (License DPR-28, Docket No. 50-271)
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
ML18289A3622018-10-11011 October 2018
Email from Daniel Doyle to Mark Leyse Status of PRM-50-93 and PRM-50-95
ML18127A5582018-04-25025 April 2018
Email to State of Vermont on Vermont Yankee Nuclear Power Station - Forthcoming Issuance of a License Amendment Regarding the Requirement for the VYNPS to Have a Cyber Security Plan
ML18045A0862018-01-25025 January 2018
Email Request for Review of the Draft Safety Evaluation for Implementation of a Revised Emergency Plan at Vermont Yankee to Reflect an ISFSI-only Configuration
ML17353A0092017-12-18018 December 2017
E-Mail from William Irwin, Vermont Department of Health to Y. Chen/Dsfm Response: Draft Environmental Assessment: Exemption Request for Vermont Yankee Independent Spent Fuel Storage Installation
ML17289A4222017-10-16016 October 2017
E-Mail from Y. J. Chen to W. Irwin Draft Environmental Assessment Exemption Request for Vermont Yankee Independent Spent Fuel Storage Installation
ML17257A0022017-09-14014 September 2017
Email to VY Shpo W Ltr Re VYNPS Exemption Load Campaign - Sept 2017
ML17229B4842017-08-16016 August 2017
Request for Supplemental Documentation to Support Review of the Physical Security Plan
ML17219A0472017-08-0303 August 2017
8/03/2017, E-Mail from Y. J. Chen/Nmss to T. B. Silko/Vermont Yankee Regarding Need for Additional Information Entergy'S Exemption Request for Vermont Yankee ISFSI, Dated May 16, 2017 (ML17142A358)
ML17144A0452017-05-23023 May 2017
5/23/2017, E-Mail to I. William/Vermont Dept. of Health from Y. Chen/Nrc Response: Draft Environment Assessment: Exemption Request for Vermont Yankee Independent Spent Fuel Storage Installation (W/Attachment Ltr to Address Comments on EA)
ML17080A4752017-03-16016 March 2017
3/16/2017, E-Mail from I. William/Vermont Department of Health to Yen-Ju Chen/Dsfm/Sflb, Providing Comments on Draft Environmental Assessment for Entergy/Vermont Yankee'S Exemption from Requirement of 10 CFR 72.7 for CoC No. 72-1014, Amendm
ML17055A6262017-02-24024 February 2017
Cover Email from VY Shpo W Concurrence on No Effects Determination
ML17040A3372017-02-0909 February 2017
Email and Letter to Vermont Shpo ISFSI Exemption No Effects Determination
ML17038A4682017-02-0707 February 2017
2/07/2017, E-mail from Yen-Ju Chen/NRC-DSFM to W. Irwin/Vermont Dept. of Health Draft Environment Assessment for Entergy/Vermont Yankee'S Exemption from Requirement of 10 CFR 72.7 for Certificate of Compliance No. 72-1014, Amendment 10
ML17012A2472017-01-11011 January 2017
E-mail - State of Vermont Comments Regarding Vermont Yankee'S 10 CFR 20.2002 Request
ML16349A2492016-12-13013 December 2016
E-Mail to T. B. Silko/Entergy from Yen-Ju Chen/Dsfm Regarding Need for Supplemental Information for Entergy'S Exemption Request for Vermont Yankee ISFSI, Dated November 9, 2016 (ML16319A102)
ML17013A2502016-12-12012 December 2016
Email Requesting Review of Draft EA and SER for Vermont Yankee Request to NRC for Alternate Disposal of Waste
ML16231A0282016-08-11011 August 2016
Response to NRC Questions Related to Request for 20.2002 Disposal of Contaminated Water
ML16231A2192016-07-28028 July 2016
Follow-up Questions Related to Entergy Request for 20.2002 Disposal of Contaminated Water
ML16069A0952016-03-0303 March 2016
Request for 20.2002 Disposal, Request for Additional Information
ML16053A5152016-02-17017 February 2016
Comment (037) of Emma Stamas on ANPR-26, 50, 52, 73, and 140 - Regulatory Improvements for Decommissioning Power Reactors
ML15329A1802015-11-24024 November 2015
E-mail from J. Whited Draft RAIs Re Duke License Amendment Request to Adopt TSTF-523 (CAC Nos. MF6413 Through MF6422)
ML15295A2132015-10-21021 October 2015
NRR E-mail Capture - VY RAI for Off-site Insurance Exemption (10 CFR 140.11) - MF3980
ML15289A6002015-09-24024 September 2015
La 3 - Vermont Yankee Draft Responses or Edits 9 24 15.docx
ML15289A6012015-09-23023 September 2015
La 3 - Nrr_Vermont Yankee Nuclear Power Station Decommissioning Status.Docx
ML15288A3532015-09-21021 September 2015
La 3 - VY Dtf LAR - Status
ML15257A6172015-09-14014 September 2015
La 3 - Testing the New Profile for Vermont Yankee La 3 - Public
ML15195A3592015-07-14014 July 2015
NRR E-mail Capture - Acceptance Review for Vermont Yankee Amendment -Revise Cyber Security Plan Implementation
ML15289A0022015-06-17017 June 2015
La 3 - Question from Ma
ML15289A5982015-06-0909 June 2015
La 3 - FW: Docket No. 50-271 (Vermont Yankee); June 5 2015 Letter from Vermont, Vynpc, and Gmp to NRC Attached
ML15289A0072015-06-0505 June 2015
La 3 - Information Regarding Vermont Yankee Decommissioning Trust Fund Exemption
ML15289A2432015-06-0404 June 2015
La 3 - FW: Docket No. 50-271 (Vermont Yankee); June 4 2015 Vermont Letter to NRC Attached
ML15289A0062015-06-0404 June 2015
La 3 - FW: Information Regarding Vermont Yankee Decommissioning Trust Fund Exemption
ML15288A3592015-06-0101 June 2015
La 3 - Vermont Yankee LA3 - Availability for Oral Argument
ML15288A3602015-06-0101 June 2015
La 3 - Vermont Yankee LA3 - Availability for Oral Argument
ML15288A3622015-06-0101 June 2015
La 3 - Vermont Yankee LA3 - Availability for Oral Argument
ML15288A4822015-05-22022 May 2015
La 3 - Vermont Reply to NRC & Entergy Answers Re VY LA-3
ML15289A0042015-05-19019 May 2015
La 3 - New Proposal Dates for Phone Call with VT
ML15289A0052015-05-11011 May 2015
La 3 - ML Numbers for Disbursement Letters for Vermont Yankee
ML15289A5992015-05-0808 May 2015
La 3 - Call with State of VT
ML15289A0032015-05-0707 May 2015
La 3 - Other than for Comanche Peak,
ML15289A1252015-05-0606 May 2015
La 3 - FRN Review - VY Dtf Exemption
ML15128A0232015-04-27027 April 2015
NRR E-mail Capture - Petitioners Response to Request for Comments on the Proposed Director'S Decision on the 2.206 Petition Regarding Financial Qualifications of Entergy
2021-03-15
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I Rick Ennis - Fwd: DRAFT response RAI SRXB-A-17 Page 1 I Rick Ennis - Fwd: DRAFT response RAI SRXB-A-17 Page 1 I From: Rick Ennis To: George Thomas Date: 8/10/05 11:08AM
Subject:
Fwd: DRAFT response RAI SRXB-A-17 George, See VY's draft revised repsonse to your RAI SRXB-A-17 based on our conference call on 8/3. Please let me know you availability for a followup call today or tomorrow.
thanks, Rick 415-1420 CC: Frank Akstulewicz; Muhammad Razzaque
t c:\temP\GW}00001.TMP Page Paqe 1 I 11 I c:\temp\GWIOOOOI .TMP Mail Envelope Properties (42FA1888.E73 :11: 372)
Subject:
Fwd: DRAFT response RAI SRXB-A-17 Creation Date: 8/10/05 11:08AM From: Rick Ennis Created By: RXE(nrc.gov Recipients Action Date & Time OWGWPO0 1.HQGWDO01 FMA CC (Frank Akstulewicz)
TWGWPOO1 .HQGWDO01 MMRI CC (Muhammad Razzaque) owf2_po.OWFNDO GXT (George Thomas)
Post Office Delivered Route OWGWPO0 1.HQGWDO0 1 Pending TWGWPO0 1.HQGWDO0 1 Pending owf2_po.OWFNDO Pending Files Size Date & Time MESSAGE 764 08/10/05 11:08AM Mail Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard Repl) Requested: No Return Notification: None Concealed
Subject:
No Security: Standard To Be Delivered: Immediate Status Tracking: Delivered & Opened
I Rick Ennis - DRAFT response RAI SRXB-A-17 Page 1 I From: "Daflucas, Ronda" <rdafluc@entergy.com>
To: "Rick Ennis" <RXE@nrc.gov>
Date: 8/10/05 11:03AM
Subject:
DRAFT response RAI SRXB-A-17 Rick - Provided is an attachment to support discussion with the NRR reviewer, George Thomas.
Would you please provide to the reviewer and request his availability for a call with VY?
Thank you, Ronda Daflucas
<<SRXB-17 Revised-050810 LTG.doc>>
DRAFT (8/10/05)
FOR DISCUSSION PURPOSES ONLY NRC RAI SRXB-17 In Supplement 4, Attachment 5, Matrix 8, page 13, note for SE Section 2.8.5.4.1, there is an explanation for uncontrolled control rod withdrawal from a subcritical or low power startup condition. In this explanatory section, this event is considered as an accident and a fuel enthalpy of 170 calories/gram is given as the acceptance criterion. However, in SRP Section 15.4.1, this event is considered as a transient, not as an accident, and hence specified acceptable fuel design limit criteria is applied. Why is this event considered as an accident rather than a transient?
Proposed New Response The transient thermal limits are established such that no fuel damage is to occur during the most severe abnormal operating transient. Fuel damage is defined as perforation of the cladding that permits release of fission products. Fuel damage can occur due to two primary mechanisms: (1) severe overheating of the fuel cladding caused by inadequate cooling, and (2) fracture of the fuel cladding due to stresses which may be induced by the relative expansion of the fuel pellet inside the cladding.
To achieve severe overheating of the cladding due to inadequate cooling, it would be necessary to generate more thermal power (heat) in the fuel than can be adequately.
transferred through the cladding to the coolant. Transients that can cause this type of behavior, typically occur during higher power operation. Operation within the Operating Limit Maximum Critical Power Ratio (OLMCPR) protects against this.
At lower power, rapid fission gas generation and pellet expansion induced cladding stresses are a concern. In order to protect against events of this type, including the Continuous Rod Withdrawal during Startup transient, a criterion was developed that limited peak fuel enthalpy below the cladding stress failure limit.
For the Continuous Rod Withdrawal during Reactor Startup transient, NEDO-23842 (Ref. 1) establishes a peak fuel enthalpy licensing basis criterion of 170 cal/gm that shall not be exceeded. This criterion was adopted from NEDO 10527 (Ref. 2), which states that this value is the fuel cladding failure threshold. This criterion is widely used by operating BWRS, and its use has been accepted by NRC. Infact, NUREG 1433 (Ref. 3)
Section B3.3.1.1 states "to demonstrate the capability of the IRM System to mitigate control rod withdrawal events, generic analyses have been performed (Ref. 4) to evaluate the consequences of control rod withdrawal events during startup that are mitigated only by the IRM." The "(Ref. 4)" from this section of NUREG 1433 is NEDO-23842 (Ref. 1).
VYNPS Updated Final Safety Analysis Report (UFSAR) (Ref. 5) Section 14.5.3.2, "Continuous Rod Withdrawal during Reactor Startup," states that the peak fuel enthalpies resulting from this event are less than 60 cal/gm, which is significantly less that the licensing basis limit of 170 cal/gm. As such, this is VYNPS' current licensing basis for this event, and it is not being changed for EPU. Because this event is considered a non-limiting transient, it is not required to be analyzed for EPU per NEDO-33004-A (Ref. 6), as approved by the NRC in a safety evaluation dated March 31, 2003.
However, VYNPS did perform an evaluation of the Continuous Rod Withdrawal during Reactor Startup transient for EPU.
DRAFT (8/10/05)
FOR DISCUSSION PURPOSES ONLY For EPU by itself, peak fuel enthalpy is not expected to increase. However, indirectly, EPU fuel and core designs may lead to higher rod worth and, therefore, higher peak fuel enthalpy at low power. It was conservatively assumed that a 20% increase in rated power would increase peak fuel enthalpy at low power by 20%, resulting in a peak fuel enthalpy for the Continuous Rod Withdrawal during Reactor Startup of 72 cal/gm, still far below the peak fuel enthalpy limit of 170 cal/gm.
References:
- 1. NEDO-23842, R.C. Stirn & J.F. Klapproth, "Continuous Control Rod Withdrawal Transient in the Startup Range," April, 18, 1978
- 2. NEDO-10527, C.J. Paone, R.C. Stirn, & J.A. Woolley, "Rod Drop Accident Analysis for Large Boiling Water Reactors," March 1972
- 3. NUREG-1433, Revision 3.0, "Standard Technical Specifications General Electric Plants, BWR/4," June 2004
- 4. NEDO-23842, R.C. Stirn & J.F. Klapproth, 'Continuous Control Rod Withdrawal Transient in the Startup Range," April, 18, 1978 (same as Ref. 1)
- 5. Updated Final Safety Analysis Report (UFSAR), Vermont Yankee Nuclear Power Station, Revision 19
- 6. NEDO-33004-A, Revision 4, "Licensing Topical Report, Constant Pressure Power Uprate,"
July 2003
