MD 8.3 Evaluation - March 15, 2004 Trip| ML051450519 |
| Person / Time |
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| Site: |
Millstone  |
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| Issue date: |
03/22/2004 |
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| From: |
James Trapp
NRC Region 1 |
|---|
| To: |
Blough A, Doerflein L, Brian Holian, Jenison K, Silas Kennedy, Kevin Mangan, Nerses V, Reis T, Schmidt W, Schneider M
Division of Reactor Safety I |
|---|
| References |
|---|
| FOIA/PA-2005-0208 |
| Download: ML051450519 (1) |
|
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|---|
Category:E-Mail
MONTHYEARML24032A4702024-02-0101 February 2024
Change in Estimated Review Schedule Revision to TS Design Features Section to Remove the Nine Mile Point Unit 3 Nuclear Project, LLC
ML24024A0202024-01-24024 January 2024
Correction to Safety Evaluation Associated Wit Amendment No. 288 - Revision to Applicability Term for RCS Heat-Up and Cooldown Pressure-Temperature Limitations Figures
ML24024A2452024-01-24024 January 2024
1/24/2024 E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in SE for Amendment No. 288 - Revision to Applicability Term for RCS Heatup and Cooldown Pressure-Temperature Limitations Figures
ML23326A0132023-11-22022 November 2023
Acceptance Review Determination LAR to Support Implementation of Framatome Gaia Fuel
ML23318A0952023-11-14014 November 2023
Request for Additional Information (E-mail Dated 11/14/2023) LAR to Revise TSs Related to Framatome Gaia Fuel
ML23317A0732023-11-13013 November 2023
Acceptance Review Determination - License Amendment Request Modification of TS SR 4.3.6.a
ML23297A2312023-10-24024 October 2023
E-mail to File - Summary of September 13, 2023, Meeting with Dominion to Discuss Proposed LAR to Support Cycle Reloads Using Framatome Gaia Fuel
ML23265A2302023-09-22022 September 2023
Acceptance Review Determination - License Amendment Request Revision to TS Design Features Section to Remove the Nine Mile Point Unit 3 Nuclear Project, LLC
ML23258A0552023-08-31031 August 2023
Setup of Online Reference Portal and Audit Plan for the NRC Staff'S Review of LAR to Use Framatome Small Break and Realistic Large Break LOCA Methodologies (08/31/2023 e-mail)
ML23199A2832023-07-18018 July 2023
Request for Additional Information (E-mail Dated 7/18/2023) LAR to Revise the Pressure-Temperature Limits
ML23172A0752023-06-21021 June 2023
Acceptance Review Determination LAR to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel
ML23171B0522023-06-20020 June 2023
NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted)
ML23145A0052023-05-25025 May 2023
Acceptance Review Determination Exemption to Use Framatome Gaia Fuel Assemblies Containing Fuel Rods Fabricated with M5 Fuel Rod Cladding
ML23145A0042023-05-25025 May 2023
Acceptance Review Determination LAR to Use Framatome Small Break and Realistic Large Break LOCA Methodologies
ML23115A3022023-04-24024 April 2023
4/24/2023 E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in Issuance of Amendments Adoption of TSTF-359, Increase Flexibility in Mode Restraints
ML23089A1882023-03-29029 March 2023
Request for Additional Information (E-mail Dated 3/29/2023) Spring 2022 Steam Generator Tube Inspection Report
ML23067A2162023-03-0707 March 2023
NRR E-mail Capture - RAI for North Anna, 1 & 2, Surry 1 & 2, Millstone, 2 & 3, Request for Approval of App. F Fleet Report DOM-NAF-2-P, Qual of the Framatome ORFEO-GAIA and ORFEO-NMGRID CHF Correlations in the Dominion VIPRE-D Computer Code
ML23038A0152023-02-0707 February 2023
Acceptance Review Determination LAR to Revise the Applicability Term for RCS Heatup and Cooldown Pressure-Temperature Limitations Figures
ML23024A1522023-01-24024 January 2023
Acceptance Review Determination LAR to Supplement Burnup Credit of Criticality Safety Analysis
ML23018A0352023-01-17017 January 2023
NRR E-mail Capture - Acceptance Review for Fleet Report Re Appendix F of DOM-NAF-2-P (L-2022-LLT-0003)
ML22320A5752022-11-16016 November 2022
E-mail to File - Summary of October 18, 2022, Meeting with Dominion to Discuss Requested Actions for Implementing Framatome Gaia Fuel
ML22298A2052022-10-25025 October 2022
Acceptance Review Determination for Alternative Request for Extension of Examination Interval for Reactor Pressure Vessel Head Penetration Nozzles
ML22292A3212022-10-19019 October 2022
Acceptance Review Determination for Alternative Request for Containment RSS Pump Periodic Verification Testing Program
ML22297A1802022-10-0707 October 2022
Email Acknowledgement to Dominion Energy Nuclear Decommissioning Trust Fund Disbursement 30 Day Notification for Millstone Power Station Unit 1: Docket No 50-245
ML22278A0932022-10-0505 October 2022
E-mail to File - Summary of September 7, 2022, Meeting with Dominion to Discuss Proposed Supplement to the Spent Fuel Pool Criticality Safety Analysis (EPID L-2022-LRM-0059
ML22272A0332022-09-29029 September 2022
Memo E-mail to File - Summary of August 29, 2022, Meeting with Dominion to Discuss Proposed Alternative Request Post-peening follow-up Volumetric Exam of RPV Head Penetration Nozzle
ML22252A1772022-09-0909 September 2022
Memo E-mail to File - Summary of August 9, 2022, Meeting with Dominion to Discuss Proposed Alternative Reqeust Recirculation Spray Pump Flow Testing (EPID L:2022-LRM-0057)
ML22242A0452022-08-23023 August 2022
NRR E-mail Capture - Dominion GL 04-02 Response Draft RAIs (L-2017-LRC-0000)
ML22174A3552022-06-23023 June 2022
NRR E-mail Capture - Acceptance Review for Dominion Fleet LAR to Implement TSTF-554 (L-2022-LLA-0078)
ML22123A0812022-05-0303 May 2022
Acceptance Review Determination for Proposed LAR for TS Change Applicable to TSTF-359, Increase Flexibility in Mode Restraints
ML22069A7192022-03-10010 March 2022
E-mail from R. Guzman to S. Sinha - Millstone Unit 3 Steam Generator Outage Conference Call
ML22020A4122022-01-11011 January 2022
1/11/2022 State Consultation E-mail, R. Guzman to J. Semancik Millstone Power Station, Unit 3 Planned Issuance of Amendment to Clarify Shutdown Bank TS and Add Alternate Control Rod Position Monitoring Requirements
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E-mail - Acceptance Review Determination Alternative Request IR-4-09 for Use Alternative Brazed Joint Assessment Methodology for Class 3 Moderate Energy Piping
ML21347A9412021-12-13013 December 2021
E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in Safety Evaluation for Amendment No. 280 Measurement Uncertainy Recapture Power Uprate
ML21334A1922021-11-30030 November 2021
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ML21306A3302021-11-0202 November 2021
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ML21297A0072021-10-19019 October 2021
E-mail from R. Guzman to S. Sinha - Acknowledgemnt of Error in SE for Millstone Power Station, Unit 3, Amendment No. 279 Addition of Analytical Methodology to the COLR for LBLOCA
ML21286A7372021-10-13013 October 2021
Additional Element Included in the Implementation Plan for the Surry Fuel Melt Safety Limit (SL) LAR
ML21223A3042021-08-11011 August 2021
Request for Withholding Information from Public Disclosure Proposed LAR to Add an Analytical Methodology to the COLR for a Large Break LOCA
ML21200A2562021-07-19019 July 2021
7/19/2021 E-mail Pressurizer Steam Space Line Classification
ML21195A2442021-07-13013 July 2021
NRR E-mail Capture - Draft RAI Appendix E to Topical Report DOM-NAF-2 Qualification of the Framatome BWU-I CHF Correlation in the Dominion Energy VIPRE-D Computer Code
ML21182A2902021-07-0101 July 2021
7/1/2021 E-mail - Request for Additional Information Alternative Frequency to Supplemental Valve Position Verification Testing Requirements
ML21147A2982021-05-27027 May 2021
Correction to Projected Review Completion Date, ASME Section XI Inservice Inspection Program Relief Requests, Limited Coverage Examinations, Third Period, 3rd 10-year Inservice Inspection Interval (EPID L-2020-LLR-0081 to LLR-0088)
ML21141A0482021-05-18018 May 2021
5/18/2021 E-mail Proposed License Amendment Request Measurement Uncertainty Recapture Power Uprate
ML21112A3082021-04-22022 April 2021
Request for Additional Information (E-mail Dated 4/22/2021) License Amendment Request for Measurement Uncertainty Recapture Power Uprate
ML21105A1152021-04-15015 April 2021
Request for Additional Information (e-mail Dated 4/15/2021) Proposed LAR for Addition of Analytical Methodology to the Core Operating Limits Report for a LBLOCA
ML21103A0532021-04-13013 April 2021
NRR E-mail Capture - Millstone Unit No. 3 - Acceptance Review Determination: Request for Alternative Frequency to Supplemental Valve Position Indication Verification Testing Requirement
ML21084A0042021-03-25025 March 2021
3/25/2021 E-mail, Acceptance Review Determination, Proposed License Amendment Request to Revise Shutdown Bank TS Requirements and Add Alternate Control Rod Position Monitoring Requirements
2024-02-01
[Table view]
Category:MD 8.3 Reactive Inspection Evaluation
MONTHYEARML0514505172005-05-20020 May 2005
Branch 6, Management Directive 8.3 Check Sheet for 3/15/04 Millstone Unit 2 Turbine Trip
ML0514505132005-05-20020 May 2005
Branch 6, Management Directive 8.3 Check Sheet for 3/6/04 Millstone Unit 2 Turbine Trip
ML0514505392005-04-18018 April 2005
Email Action: MD 8.3 Review for Millstone Scram with Complications
ML0514505192004-03-22022 March 2004
MD 8.3 Evaluation - March 15, 2004 Trip
2005-05-20
[Table view] |
Text
- 7.7 -
Si,as -Kennedy_- Millstone Unit 2 - MD 8.3 Evaluation - March 15, 2004 Trip
' _ .. _ .. a.. .. s ... ... _.rn... _ _ Ad, _ .................. , - ,__L_= , ., . ,. I I Paae 1 Silas Kennedy-Millstone Unit 2 MD 8.3 Evaluation March 15, 2004 Trip Paae 1l From: James Trapp To: A.Randolph Blough; Brian Holian; Kenneth Jenison; Kevin Mangan; Lawrence Doerilein; Max Schneider; Silas Kennedy; Terrence Reis; Victor Nerses; Wayne Schmidt Date: Mon, Mar 22, 2004 2:44 PM
Subject:
Millstone Unit 2 - MD 8.3 Evaluation - March 15, 2004 Trip Based on the attached MD 8.3 evaluation, Branch 6 has determined that no special reactive inspection is needed for the March 15, 2004 reactor trip. This conclusion is based on the deterministic criteria not being met; additionally, the CCDP associated with the trip is low (low E-6). This trip along with 3 others in the past 12 months will be reviewed as part of a 95001 Inspection, due to the reactor trip PI exceeding the greenAvhite threshold.
On March 15, 2004, the UBE SGFP tripped during surveillance testing. The cause for the SGFP trip was determined to be a trip blocking switch that was not held completely in the block position for the duration of the test. The trip of the SGFP resulted in a low S/G level reactor trip. All safety systems responded as expected with two exceptions noted below.
Complications following the trip were main steam safety valves opening and torn enclosure building boots on the safeties. The licensee has verified the safety setpoints are in an acceptable range. They are currently evaluating the transient/safety setpoints to verify this Is a desired response following a loss of feedwater. The resident Inspectors will follow this activity. The enclosure boots were evaluated and found they were not needed for operablity.
CC: Neil Perry R ;D,I