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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217L8831999-10-21021 October 1999
Safety Evaluation Supporting Proposed Alternatives to Code Requirements Described in RR-V17 & RR-V18
ML20217G2041999-10-13013 October 1999
Safety Evaluation Supporting Amend 179 to License DPR-28
ML20212C2551999-09-17017 September 1999
Safety Evaluation Supporting Amend 175 to License DPR-28
ML20206E8741999-04-29029 April 1999
SER Determined That Flaw Evaluation Meets Rules of ASME Code & Assumed Crack Growth Rate Adequate for Application
ML20205K7581999-04-0707 April 1999
Safety Evaluation Supporting Alternative Proposal for Reexamination of Circumferential Welds with Detected Flaw Indications in Plant RPV
ML20203H9881999-02-18018 February 1999
SER Accepting Alternative to 10CFR50.55a(g)(6)(ii)(A) Augmented Reactor Vessel Exam at Vermont Yankee Nuclear Power Station.Technical Ltr Rept Encl
ML20199K7151999-01-21021 January 1999
Corrected Safety Evaluation Supporting Amend 163 Issued to FOL DPR-28.Pages 2 & 3 Required Correction & Clarification
ML20199K6991999-01-20020 January 1999
Safety Evaluation Concluding That Request to Use YAEC-1339, Yankee Atomic Electric Co Application of FIBWR2 Core Hydraulics Code to BWR Reload Analysis, at Vermont Yankee Acceptable
ML20199L5951999-01-14014 January 1999
Safety Evaluation Accepting Licensee Proposed Alternative to Code Requirement,Described in Rev 2 to Pump Relief Request RR-P10 Pursuant to 10CFR50.55a(a)(3)(i)
ML20195C4161998-11-0909 November 1998
SER Accepting Request That NRC Approve ASME Code Case N-560, Alternative Exam Requirement for Class 1,Category B-J Piping Welds
ML20155B6471998-10-26026 October 1998
Safety Evaluation Accepting Jet Pump Riser Insp Results & Flaw Evaluation,Conducted During 1998 Refueling Outage
ML20154B6951998-10-0101 October 1998
SER Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Vermont Yankee Nuclear Power Station
ML20239A1361998-09-0202 September 1998
SER Re License Request for NRC Review & Concurrence W/Changes to NRC-approved Fire Protection Program
ML20216F1001998-04-15015 April 1998
Safety Evaluation Accepting 980331 Licensee Proposal to Perform Alternative Testing for Containment Pressurization Test for Vynp
ML20217F3421998-03-25025 March 1998
SER Accepting Plans for 1998 & 1999 Refueling Outages Re Reactor Vessel Internals for Plant
ML20212H1521998-03-0606 March 1998
Correction to Page 7 of SE Re Relief Request for Third 10-yr Interval Pump & Valve IST Program for Plant
ML20217N4911998-02-27027 February 1998
SER Pertaining to Cracking of EDG Lube Oil Piping at Vermont Yankee
ML20198P9941998-01-15015 January 1998
SE Authorizing Relief Requests for Third Interval Pump & Valve Inservice Testing Program
ML20141A4151997-06-18018 June 1997
Revised SE Accepting Proposed Onsite Disposal of Slightly Contaminated Silt Removed from Vermont Yankee Cooling Towers
ML20135E5401997-03-0303 March 1997
Safety Assessment Accepting Mod of RHR & CS Sys Containment Isolation Function Configuration
ML20134N8271996-11-20020 November 1996
Safety Evaluation Accepting Licensee Scope & Insp Methods Proposed for Insp of Core Spray Internal Piping During Fall 1996 Refueling Outage at Plant
ML20134F9631996-11-0505 November 1996
Safety Evaluation Re Power/Flow Exclusion Region Calculation Method Using LAPUR5 Computer Code & Implementation of Solomon Stability Monitor for Licensee Facility
ML20128N3531996-10-11011 October 1996
Safety Evaluation Accepting Licensee Flaw Evaluation of Indication Found During Reactor Pressure Vessel Insp at Plant
ML20129G3611996-10-0202 October 1996
Safety Evaluation Accepting Proposed Repair for Plant Core Shroud
ML20057A6991993-09-0303 September 1993
Safety Evaluation of IST Program Relief Requests for Pumps & Valves for Third 10-yr Insp Interval
ML20057A2791993-08-12012 August 1993
Safety Evaluation Accepting Licensee Reasons Given for Delay in Completing short-term Actions Requested in Ieb 93-003, Resolution of Issues Re to Rv Water Level Instrumentation in Bwrs
ML20246D7731989-08-21021 August 1989
Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Item 2.2.1, Required Actions Based on Generic Implications of Salem ATWS Events. Equipment Classification Program for safety-related Components Acceptable
ML20244D0311989-06-0707 June 1989
Safety Evaluation Accepting Util Second 10-yr Interval Inservice Insp Program Plan
ML20205T4181988-10-14014 October 1988
Errata to Safety Evaluation Concluding Util Submittal Re Spent Fuel Pool Expansion
ML20204F7271988-10-14014 October 1988
Safety Evaluation Supporting Proposed Expansion of Spent Fuel Pool at Facility
ML20236N6461987-08-0707 August 1987
Safety Evaluation Re Permanent Elimination of Liquid Penetrant Exam of Feedwater Nozzles at Facility.Due to Lack of Reasonable Assurance That Ultrasonic Exam Can Totally Replace Penetrant Exam,Request Unacceptable
ML20214T9891987-05-28028 May 1987
Safety Evaluation Re Util 870112 Proposed Plans to Inspect Two Overlay Repaired Core Spray safe-ends in Lieu of Replacement During Upcoming 1987 Refueling Outage.Plans Acceptable,Providing That Insp Results Satisfactory
ML20207S7801987-03-12012 March 1987
Safety Evaluation Granting Relief from Tech Spec 4.7.A.3 on one-time Basis to Perform RHR Pump Wear Ring Replacement
ML20214T4921986-11-24024 November 1986
Safety Evaluation Accepting Licensee 830511 & 860117 Responses to Generic Ltr 83-08 Re Mod of Vaccum Breakers on Mark I Containments
ML20215M5871986-10-24024 October 1986
Preliminary Evaluation of Containment Study Transmitted w/860902 Ltr.Licensee Estimates Appear Optimistic Considering Uncertainties Inherent in Failure Rate Data
ML20206F3651986-06-16016 June 1986
Safety Evaluation Re Proposed Repair of Core Spray safe- Ends,During Current Refueling Outage.Plant Can Be Safely Returned to Power Operation After Satisfactory Completion of Core Spray safe-end Repairs
ML20206F0681986-06-13013 June 1986
Safety Evaluation Supporting 850514,0710,860327,0411 & 0513 Requests for Approval to Use Pvrc Damping Values (ASME Code Case N-411) for Piping Sys Reanalysis
ML20202J4211986-03-31031 March 1986
Safety Evaluation Accepting Util Design Mods & Tech Spec Changes Re Degraded Grid Voltage Protection for Class 1E Sys.Lll Technical Evaluation Rept Encl
ML20155B8351986-03-31031 March 1986
Safety Evaluation Supporting Revised Procedure OP-3140, Providing Technically Acceptable Actions During Degraded Grid Voltage Conditions W/O LOCA to Assure Protection of Class 1E Electrical Sys & Equipment
ML20140H9881986-03-25025 March 1986
Safety Evaluation Re Util 851008 Request to Install Carpet Over Vinyl Asbestos Tiled Control Room Floor Covering. Installation of Carpet Will Not Decrease Level of Fire Safety in Control Room & Deviation Acceptable
ML20138E4201985-12-0202 December 1985
Safety Evaluation Supporting Util 831107 & 840320 Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 Re post-maint Testing & Reactor Trip Sys Reliability
ML20136F1241985-11-18018 November 1985
Safety Evaluation Re IE Bulletin 80-11, Masonry Wall Design. Issues Re Arching Action Theory Resolved
ML20137S7331985-09-27027 September 1985
Safety Evaluation Approving Use of Fuel Thermal Performance Code,Frosstey,For Analysis of LOCA Conditions at Low & Moderate Burnups
ML20135C8921985-09-10010 September 1985
Safety Evaluation Supporting 840824 Commitment to Convert Air Containment Atmosphere Dilution Sys to Nitrogen Sys,In Response to Generic Ltr 84-09
ML20135C9121985-09-10010 September 1985
Safety Evaluation Supporting Conclusion That Diversification of Scram Discharge Vol Level Instrumentation Not Necessary & Tech Specs,As Modified in Amend 76,resolve Staff Concerns Re Need for Instrumentation Diversity
ML20134K7351985-08-19019 August 1985
Safety Evaluation Accepting 831107 Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing
ML20136G3611985-08-12012 August 1985
Safety Evaluation Accepting Seismic Design Criteria Utilized for Evaluation of Modified Recirculation Sys
ML20132D8971985-07-22022 July 1985
Safety Evaluation Supporting Use of Pvrc Damping Values (ASME Code Case N-411) for Response Spectrum Seismic Piping Analyses
ML20127D8991985-05-0606 May 1985
Safety Evaluation Re 840925 & 1002 Responses to Generic Ltr 83-28,Item 1.1 Concerning post-trip Review Program & Procedures.Program & Procedures Acceptable
1999-09-17
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Category:TEXT-SAFETY REPORT
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- . ?t i l* S UNITED STATES l' ! NUCLEAR REGULATORY COMMISSION WASmCTON. D C. 2055MT1 N .w....., ,/
SAFETY EVALUATION BY THE OFFICE OF NbCLEAR REACTOR REGULATION VERMONT YANKEE NUCLEAR POWER CORPORATION VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO.50-27I
1.0 INTRODUCTION
By letter dated June 9,1993, Vermont Yankee Nuclear Power Corporation, the licensee for Vermont Yankee duclear Power Station, submitted a 15-day response to Bulletin 93-03, " Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs," issued May 28, 1993. This report explains why the licensee did not complete the requested short-term corrective actions in the allocated time frame.
2.0 EVALUATION The licensee has indicated that they will fully implement the short-term compensatory actions requested by Bulletin 93-03 by the designated date with the exception of requirement 1(b) which states:
Each licensee shall, by July 30, 1993, " Complete augmented operator training on loss of RPV inventory scenarios during Mode 3, including RPV draindown events and cracks or breaks in piping."
The licensee will give the requested training to all licensed individuals scheduled to perform control room duties by July 30, 1993. Due to simulator and licensed operator requalification schedules, Vermont Yankee will not meet the July 30, 1993, deadline for the completion of all training. One operating crew will not complete training until August 6, 1993, The licensee has stated that this crew is not scheduled for shift duty until their training is complete. Also, a group of staff members currently holding licenses, but not on shift duty, will complete their training on August 13, 1993.
The staff finds the above response to be acceptable since all operating crews will complete the requested training prior to resuming control room duties.
3.0
SUMMARY
AND CONCLUSIONS The staff has reviewed the licensee's response to Bulletin 93-03. The staff finds the reasons given for their delay in completing the requested short-term actions acceptable based on the above evaluation.
9309130311 930812 PDR P ADOCK 05000271 I PDR !
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4.0 REFERENCES
- 1. NRC Bulletin 93-03, " Resolution of Issues related to Reactor Vessel Water Level Instrumentation in RWRs," May 28, 1993.
- 2. Vermont Yankee response to NRC Bulletin 93-03, June 9, 1993. '
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Principal Contributor: B. Korona
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Date: August 12, 199?
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