Letter Sequence Meeting |
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MONTHYEARML19322D1691978-06-0606 June 1978
Notifies That Lead Engineer Assignments Designated Re B&W Instrumentation in Response to 780517 Request.Forwards Task Definitions, & Lists Target Completion Schedule & Estimated Personpower Requirements
Project stage: Other
ML19248C2221980-10-29029 October 1980
Provides Insights on Overcooling Transients in Plants W/B&W Nsss.Frequency of Overcooling Transients Diminishes Prior to Commercial Operations.Summary of Overcooling Events Encl
Project stage: Other
ML13308B8161980-12-0202 December 1980
Informs of Recently Established Policy Re Communications Between C-E Owners Group & Nrc,Per Group Request.Owners Group Submittals Will Not Be Applicable to Individual Licensees Until Referenced by Licensee for Use on Docket
Project stage: Other
ML20003A9241980-12-30030 December 1980
Final Version of Reactor Vessel Brittle Fracture Analyses During Small Break LOCA Events W/Extended Loss of Feedwater. Info Re power-operated Relief Valve Opening Probability Encl
Project stage: Other
ML20003A9161981-01-30030 January 1981
Follows Up 801230 Response to NUREG-0737.Forwards Reactor Vessel Brittle Fracture Analyses During Small Break LOCA Events W/Extended Loss of Feedwater & Info Re power-operated Relief Valve Opening Probability
Project stage: Other
ML19247E4321981-03-0303 March 1981
Provides fracture-mechanics Parametric Analysis of Overcooling Accident at Facility,In Response to Request
Project stage: Other
ML13302B0031981-03-0606 March 1981
Notification of 810309 Meeting W/Util in Bethesda,Md to Discuss Facility Emergency Plan
Project stage: Request
ML19247E4331981-04-10010 April 1981
Updates Re Safety Implications of Control Sys & Dynamic Characteristics of Nuclear Facilities.Pressurized Thermal Shock Phenomena & Control Sys Implications to Safety Have Not Been Analyzed
Project stage: Other
ML20042C1171981-04-11011 April 1981
Plant Shutdown & Cooldown, Revision 19
Project stage: Other
ML19247E4311981-04-21021 April 1981
Forwards Modified Table 1 to 810421 Memo.Further Consideration of B&W Two Bus Design W/Failure of Single Bus Has Led to Revision of HEP
Project stage: Other
ML19247E4301981-04-21021 April 1981
Forwards Preliminary Assessment of Frequency of Excessive Cooldown Events Challenging Vessel Integrity,In Response to 810417 Request
Project stage: Other
ML19247E4271981-04-28028 April 1981
Forwards Preliminary Assessment of Thermal Shock to PWR Reactor Pressure Vessels,In Response to 810416 Memo
Project stage: Other
ML19350D6861981-04-30030 April 1981
EPRI Research on Properties of Irradiated Matl Pertinent to Overcooling Transients
Project stage: Other
ML20008F8811981-05-0505 May 1981
Informs That Data Presented in BAW-1511 P, Radiation- Induced Reduction & Charpy Upper-Shelf Energy of Reactor Vessel Welds, Is Applicable to Facility.Completion of Work in Other Phases of Program Will Justify Plant Operation
Project stage: Other
ML20004A4921981-05-12012 May 1981
Discusses Results of Preliminary Review of Thermal Shock to PWR Pressure Vessels.Reasonable Assurance Found That Plant Can Continue to Operate During Generic Evaluation
Project stage: Approval
ML19350D6831981-05-12012 May 1981
Forwards Ltr Rept in Response to NRC 810429 Request for Addl Info Re Thermal Shock Issue.Also Forwards Summary of EPRI Programs
Project stage: Request
ML13303A4651981-05-14014 May 1981
Forwards Fes.W/O Encl
Project stage: Request
ML19350D6851981-05-15015 May 1981
Ltr Rept on Reactor Vessel Brittle Fracture Concerns in B&W Operating Plants
Project stage: Other
ML13317A6151981-05-18018 May 1981
Fulfills Commitment Made in Response to NRC 810331 Request Re Vessel Integrity & Responds Further to NRC 810429 Requests & Clarifications Re Reactor Vessel Pressurized Thermal Shock Issue.Discusses Proposed Program
Project stage: Other
ML14133A3531981-05-22022 May 1981
Discusses Commitment to Develop Program Re Potential Reactor Vessel Integrity Concerns Identified in NRC . Program Will Identify Whether Future Addl Plant Specific Analyses &/Or Remedial Actions Will Be Required
Project stage: Other
IR 05000206/19810161981-05-22022 May 1981
IE Insp Rept 50-206/81-16 on 810512-15.No Noncompliance Noted.Major Areas Inspected:Welding Activities Associated W/Mods to Auxiliary Feedwater Sys & Repair of Circumferential Welds on Main Steam Piping
Project stage: Request
ML20004B6971981-05-22022 May 1981
Submits Reactor Vessel Pressurized Thermal Shock Info in Response to .Program to Address Vessel Integrity Concerns Scheduled for Consideration at 810604 Meeting
Project stage: Meeting
ML20004B9341981-05-22022 May 1981
Contends That 810512 B&W Rept Re Reactor Vessel Brittle Fracture Concerns Combined W/Encl Description of Facility Design Features Provide Sufficient Info to Identify That Reactor Vessel Thermal Shock Issue Is Not Safety Concern
Project stage: Other
ML20004B0751981-05-22022 May 1981
Notifies That Info Provided in Re Reactor Vessel Brittle Fracture Concerns in B&W Plants Is Applicable to Facility.Util Will Perform Further Fracture Analyses & Participate in Owners Group Activities Re Thermal Shock
Project stage: Other
ML13317A6591981-06-0202 June 1981
Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment Finding No Outstanding Items That Require Immediate Corrective Action.Deficient Items Replaced.Equipment Qualified for Low Probability Events
Project stage: Request
ML20030A7701981-07-20020 July 1981
Notification of 810728,29 & 30 Meetings W/B&W,Westinghouse & C-E Owners Groups in Bethesda,Md to Discuss Thermal Shock to Reactor Pressure Vessel Issue
Project stage: Meeting
ML20030D6551981-08-21021 August 1981
Requests Addl Info Re Pressurized Thermal Shock to Reactor Pressure Vessels,Per Review of PWR Owners Group 810515 & Licensees 810522 Responses to NRC
Project stage: Approval
IR 05000361/19810171981-08-21021 August 1981
IE Insp Rept 50-361/81-17 on 810715-31.No Noncompliance Noted.Major Areas Inspected:Preoperational Test Program & Procedures,Maint,Plant Tours & Licensee Action on Previously Identified Items
Project stage: Request
ML13330A3941981-08-21021 August 1981
Requests Addl Info Re Pressurized Thermal Shock to Reactor Pressure Vessels,Per Review of PWR Owners Group 810515 & Licensees 810522 Responses to NRC
Project stage: Approval
ML20031F1401981-10-0101 October 1981
Summary of 810918 Meeting W/Westinghouse Owners Group Re Pressurized Thermal Shock to Reactor Pressure Vessels. Attendance List & Handouts Encl
Project stage: Meeting
ML13317A6811981-10-0505 October 1981
Responds to Requesting Addl Action Re Pressurized Thermal Shock to Reactor Pressure vessels.Sixty-day Response Schedule Cannot Be Met.Partial Response Will Be Provided by 811104
Project stage: Other
ML13317A7251981-10-23023 October 1981
Discusses Proposed Response to NRC 810821 Request Re Pressurized Thermal Shock to Reactor Pressure Vessels. Requests Available Portions of Response at Time Provided in ,To Avoid Needless Conservatisms
Project stage: Other
ML20033A3541981-10-30030 October 1981
Forwards NRC Evaluation of ORNL Rept on Pressurized Thermal Shock.Rept Does Not Change Previous NRC Conclusion That Probability of Occurrence of Severe Pressurized Overcooling Transients Too Low to Require Immediate Action
Project stage: Other
ML13323A2601981-10-31031 October 1981
Operating Instructions for SSH-3/FBA-13 Seismic Scram & Trip Sys
Project stage: Request
ML13309A0791981-11-0404 November 1981
Forwards Responses to Safety Evaluation of Environ Qualification of safety-related Electrical Equipment,Addl Info Not Addressed in Safety Evaluation & Revised Pages to
Project stage: Request
ML13317A7201981-11-0404 November 1981
Forwards Partial Response to NRC 810821 Request for Addl Info Re Pressurized Thermal Shock to Reactor Pressure Vessels Per
Project stage: Request
ML13308A0441981-12-31031 December 1981
Forwards CEN-189, Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for C-E NSSS, & Apps A-J,in Response to TMI Action Plan Requirement II.K.2.13
Project stage: Other
ML14092A3011981-12-31031 December 1981
Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for C-E Nsss
Project stage: Other
ML20039F8601981-12-31031 December 1981
Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for San Onofre 2 & 3 Reactor Vessels
Project stage: Other
ML20039F8631981-12-31031 December 1981
Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCA W/Loss of Feedwater for Millstone 2 Reactor Vessel
Project stage: Other
ML13317A8361982-01-25025 January 1982
Forwards Util 150-day Response to 810821 Request for Addl Info Re Pressurizer Thermal shock.Plant-specific Analyses Indicate That Vessel Integrity Will Be Maintained,Therefore Remedial Actions Not Warranted
Project stage: Request
ML13310A3761982-01-26026 January 1982
Forwards Amend 28 to Fsar,Reissuing Facility Emergency Plan & Offsite Emergency Response Plans (Filed in PDR Category K), & Amend 10 to Fire Hazards Analysis (Filed in Category F)
Project stage: Request
ML20041C6781982-02-25025 February 1982
Responds to NRC 820104 Request for Addl Info in Response to NUREG-0737 Item II.K.2.13 Re Thermal Mechanical Rept.Small Break LOCA Will Not Result in Brittle Fracture to Reactor Vessel.Further Operator Training Unwarranted
Project stage: Request
ML20041D7681982-03-0303 March 1982
Submits Correction to Util Re NUREG-0737,Item II.K.2.13, Thermal-Mechanical Rept - Effect of HPI on Vessel Integrity for Small Break LOCA W/No Auxiliary Feedwater
Project stage: Other
ML20042C1181982-03-0808 March 1982
Loss of Reactor Coolant/Rcs Pressure, Revision 17
Project stage: Other
ML13333B8091982-03-0808 March 1982
Summary of 820224 Meeting W/Westinghouse Owners Group, Southern CA Edison,Cp&L & Fl Power & Light in Bethesda,Md Re Pressurized Thermal Shock
Project stage: Meeting
ML20042C1201982-03-0808 March 1982
Loss of Steam Generator Feed, Revision 16
Project stage: Other
ML13310A7011982-03-15015 March 1982
Forwards Request for Addl Info Re Pressurized Thermal Shock.Info Should Be Submitted by 820430
Project stage: RAI
IR 05000361/19820101982-03-15015 March 1982
IE Insp Rept 50-361/82-10 on 820119-0212.No Noncompliance Noted.Major Areas Inspected:Preoperational Test Program,Tmi Mods,Followup on IE Bulletin 80-06,safety Committee Activities & Independent Insp Effort
Project stage: Request
ML20042C1151982-03-17017 March 1982
Responds to NRC & Submits Addl Info Re NUREG-0737 Item II.K.2.13, Thermal Mechanical Rept. Procedures Re Plant Shutdown & Cooldown,Loss of Reactor Coolant/Reactor Coolant Pressure & Loss of Steam Generator Feed Encl
Project stage: Other
1981-04-28
[Table View] |
Notification of 810728,29 & 30 Meetings W/B&W,Westinghouse & C-E Owners Groups in Bethesda,Md to Discuss Thermal Shock to Reactor Pressure Vessel Issue| ML20030A770 |
| Person / Time |
|---|
| Site: |
Beaver Valley, Millstone, Calvert Cliffs, Davis Besse, Browns Ferry, Salem, Oconee, Palisades, Indian Point, Kewaunee, Saint Lucie, Point Beach, Sequoyah, Arkansas Nuclear, Prairie Island, Surry, North Anna, Turkey Point, Crystal River, Haddam Neck, Ginna, Farley, Robinson, San Onofre, Cook, Yankee Rowe, Maine Yankee, Rancho Seco, Zion, Fort Calhoun, McGuire, Trojan, Crane |
|---|
| Issue date: |
07/20/1981 |
|---|
| From: |
Vissing G
Office of Nuclear Reactor Regulation |
|---|
| To: |
Novak T
Office of Nuclear Reactor Regulation |
|---|
| References |
|---|
| TASK-2.K.2.13, TASK-TM TAC-45198, TAC-45202, TAC-46890, TAC-46893, TAC-47549, NUDOCS 8107290005 |
| Download: ML20030A770 (5) |
|
Similar Documents at Beaver Valley, Millstone, Calvert Cliffs, Davis Besse, Browns Ferry, Salem, Oconee, Palisades, Indian Point, Kewaunee, Saint Lucie, Point Beach, Sequoyah, Arkansas Nuclear, Prairie Island, Surry, North Anna, Turkey Point, Crystal River, Haddam Neck, Ginna, Farley, Robinson, San Onofre, Cook, Yankee Rowe, Maine Yankee, Rancho Seco, Zion, Fort Calhoun, McGuire, Trojan, Crane |
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Category:INTERNAL OR EXTERNAL MEMORANDUM
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Calvert Cliffs]] OR [[:Davis Besse]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Palisades]] OR [[:Indian Point]] OR [[:Kewaunee]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Sequoyah]] OR [[:Arkansas Nuclear]] OR [[:Prairie Island]] OR [[:Surry]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Farley]] OR [[:Robinson]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Fort Calhoun]] OR [[:McGuire]] OR [[:Trojan]] OR [[:Crane]] </code>.
Category:MEMORANDUMS-CORRESPONDENCE
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Calvert Cliffs]] OR [[:Davis Besse]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Palisades]] OR [[:Indian Point]] OR [[:Kewaunee]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Sequoyah]] OR [[:Arkansas Nuclear]] OR [[:Prairie Island]] OR [[:Surry]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Farley]] OR [[:Robinson]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Fort Calhoun]] OR [[:McGuire]] OR [[:Trojan]] OR [[:Crane]] </code>. |
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UNITED STATES i
E NUCLEAR REGULATORY COMMISSION
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July 20,.1981 Docket:
(All Operating PWR's).
MEMORANDUM FOR: Thomas Novak, Assistant Director for Operating Reactors, DL FROM:
Guy Vissing, Project Manager Operating Reactors Branch #4, DL
SUBJECT:
FORTHCOMING MEETING WITH THE. BABCOCK & WILCOX, C0f1BUSTION ENGINEER, AND WESTINGHOUSE NSSS OWNERS GROUPS CONCERNING THE THERMAL SH0CK TO RPV ISSUE Time & Date:
According to following schedule B&W Group Westinghouse Group CE Group July 28,1981 July 29,1981 July 30,1981 1 :00-4:15pm 1 :00-4:15pm 1 :00-4:15pm Location:
P-422 P-110 P-ll8 Phillips Building Phillips Building Phillips Building Bethesda, MD Bethesda, MD Bethesda, MD
Purpose:
To discuss the Thermal Shock to Reactor Pressure Vessel Issue according to the attached agenda.
Requested
Participants:
NRC T. Murley, et. al.
B&W Owners Group John Mattimoe, Chairman B&W Representatives Operating Plant Owners Group Representatives Westinghouse Owners Group Robert Jurgensen, Chairman Westinghouse Representatives Operating Plant Owners Group Representatives Combustion Engineers Group Ken Norris, Vice Chairman CE Representatives Operating Plant Owners Group Representatives Gu issing, Project M ager 8107290005 810720 Operating Reactors Branch #4 PDR ADOCK 05000029 Division of Licensing P
PDR Phone (301) 492-8136 cc: See next page
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MEETING NOTICE DISTRIBUTION OkERATING REACTORS, DIVISION OF LICENSING N
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OELD IE-3 OSD-3 SShowe, IE (PWR) or CThayer, IE (BWR)
Licensing Assistant Receptionist, Bethesda ACRS-10 Program Support Branch PTKuo (seismic reviews only)
HGaut, State Programs.
J01shinski Meeting N ce File BKGrimes, Dti SSchwartz, DEP FPagano, EPLB SRamos. EPDB NHughes, DL NRC
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7/20/81 A
AGENDA Meetings with PWR Owners' Group Representatives and Vendor' Representatives
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Pressurized Thermal Shock I.
Introduction - NRR 15 min.
l
- Purpose of Meeting
- Summary of NRC Activities
- NRC Plans 60 min.
II. Owners' Group Representatives
- Summarize Current and Planned Activities
- Specific Questions
- What is each plant's current RT and what is the axpected yearly change over next 10 yeahkI
- What are each licensee's instructions to operators for operation of HPI after automatic initiation?
- What are the estimated costs and benefits for
- removing outer fuel assemblies?
- raising temperature of ECC water?
- in-place annealing?
- other potential fixes?
III.
Detailed Technical Discussions 120 min.
- Bounding Overcooling Transients
- Estimated Probability of Bounding Transients
- Systems Response
- Assumed Operator Response
- Systems Analytical Model (Computer Codes Used)
- Verification of Systems Model
- Mixing Assumptions
- Downcomer Pressure / Temperature vs. Time for Selected Transients (Symmetric / Asymmetric?)
- Heat Transfer Assumptions
- Treatment of Clad Effects on Relatively Small Cracks
- Material Properties Used (Temperature Dependence?)
- Initial Crack Size / Shape Assumptions
- Temperature / Stress /LEFM Algorithms
- Treatn.ent of Upper Shelf
a PRESSURIZED WATER REACTOR LICENSEES Docket No. 50-348 Docket No. 50-334 Farley Unit 1 Beaver Valley Unit 1 Docket.No. 50-313'/
Docket No. 50-302 Arkansas Unit 1 Crystal River 3 Docket No. 50-368v Docket No. 50-335 Arkansas Unit 2 St. Lucie 1 Dockct No. 50-317
' Docket No. 50-250 Calvert Cliffs Unit 1 Turkey Point Unit 3
. Docket No. 50-318 Docket No. 50-251 Calvert Cliffs Unit 2 Turkey Point Unit 4 Docket No. 50-261 Docket No. 50-315 H. B. Robinson Unit 2 D. C. Cook Unit 1 4
Docket No. 50-295 Docket No. 50-316 Zion Unit 1 D. C. Cook Unit 2 Docket No. 50-304 Docket No.60-309 Maine Yankee Zion Unit 2
_ 1 Docket No.<
Docket No. 50-289 Connecticut'50-213-Yank'ee (Haddam Neck)
Three Mile Island Unit 1
-4emiss4=Noos9@
Docket No. 50-320 h
Three Mile Island Unit 2 C
Docket No. 50-247 Docket No. 50-336 Indian Point Unit 2 Millstone Unit 2 Docket No. 50-296 Docket No. 50-282 Indian Point Uait 3 Prairie Island Unit 1 Docket No. 50-255 Docket No. 50-306 Palisades Prairie Island Unit 2 Docket No. 50-269 Dochat No. 50-285 Oconee Unit 1 Ft. Calhoun Docket No. 50-270 Docket No. 50-344 0::onee Unit 2 Trojan Docket No. 50-287 Docket No. 50-272 Oconee Unit Salem Unit 1
. Docket No. 50-244 R. E. Ginna 1 Docket No. 50-312 Rancho Seco Docket No. 50-206 San Onofre Un'it 1 Docket No. 50-346 Davis-Besse 1 LDocket.No. 50-338 North Anna 1-Docket No. 50-280-Surry Unit 1 Docket No. 50-281 Surry Unit 2 Docket No. 50-266 Point Beach Unit 1 Docket No. 50-301-Point Beach Unit 2 Docket No. 50-305 Kewaunee Docket No. 50-29 !
Yankee-Rowe %
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. Docket No. 50-339 j
North Anna 2
! Docket No. 50-311
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! Salem.2
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b[,g i Docket No. 50-327 Sequoyah 1 l
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l r Docket No. 50-369 g
l 1 McGuire 1 5 Docket No. 50-364 Farley 2
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