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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217D0681999-10-0707 October 1999 Forwards First of Planned Series of Progress Repts Re Status of Remediation & Decommissioning Work Underway at W Waltz Mill Site Near Madison,Pa ML20216K0441999-10-0404 October 1999 Forwards Proposed Replacement Pages to TR-2 Ts,In Order to Provide Addl Clarifications & to Accommodate Minor Editorial Changes.Ts Amend Would Clarify Facility Boundaries ML20216J7501999-10-0101 October 1999 Forwards Proposed Replacement Pages to Decommissioning Plan & for Ts.Pages Are Being Submitted to Replace Similar Pages Previously Transmitted in ML20195H4271999-06-14014 June 1999 Forwards Annual Insp of Retired Wtr Per License TR-2 for 1998.Physical Status of Retired Facility Remains Same as It Was at Time of Last Rept ML20205C8671999-03-26026 March 1999 Forwards ,Addressing Concern Raised in Insp Findings at Westinghouse Test Reactor at Waltz Mill,Pa Under Rept Number 50-022/99-201 ML20205C7461999-03-25025 March 1999 Forwards Amend 9 to License TR-2 & Safety Evaluation.Amend Revises License to Reflect Change in Legal Name of Licensee for W Test Reactor to CBS Corp ML20204F6351999-03-18018 March 1999 Expresses Appreciation to NRC for Forwarding Copy of Insp Rept 50-022/99-201 Reflecting Results of 990203 Insp of W Test Reactor at Waltz Mill Site.Review of Insp Rept Raises Listed Concerns.Nrc Help in Matter Would Be Appreciated ML20205L1141999-03-12012 March 1999 Partially Deleted Ltr Establishing Irrevocable Standby Ltr of Credit in NRC Favor,At Request & for Account of W ML20207M5201999-03-0505 March 1999 Forwards Insp Rept 50-022/99-201 on 990201-03.No Violations Noted.Various Aspects of Reactor Operations,Maint,Safety & Emergency Preparedness Program Were Inspected ML20198L0781998-12-21021 December 1998 Forwards Environ Assessment & Finding of No Significant Impact Re 980928 & 1117 Applications for Amend to License TR-2 to Reflect Change in Legal Name of Licensee from CBS Corp Acting Through W Div to Simply CBS Corp RA-98-070, Forwards Addl Info in Support of Application to Amend License TR-2 Re Name Change1998-11-17017 November 1998 Forwards Addl Info in Support of Application to Amend License TR-2 Re Name Change ML20154G6871998-09-30030 September 1998 Forwards Amend 8 to License TR-2 & Se.Amend Approves Decommissioning Plan for Wtr,In Response to 980731 Submittal & Suppls & 0710.Amend Also Authorizes Approved Decommissioning Plan to Be Included as Suppl to Wtr SAR ML20154B0481998-09-28028 September 1998 Establishes Irrevocable Standby Ltr of Credit 1484 in NRC Favor,At Request & for Account of W,Up to Aggregate Amount of $11,098,000 Upon Presentation of Sight Draft & Signed Statement ML20236V8941998-07-31031 July 1998 Forwards Amend 7 to License TR-2 & Safety Evaluation.Amend Revises Facility License in Response to 971222 Application for Amend Suppl 980615 to Reflect Change in Legal Name for Wtr from Westinghouse Electric Corp to CBS Corp RA-98-038, Forwards Errata to Rev 1 to W Test Reactor TR-2 Final Decommissioning Plan, Correcting Minor Editorial Errors Identified1998-07-10010 July 1998 Forwards Errata to Rev 1 to W Test Reactor TR-2 Final Decommissioning Plan, Correcting Minor Editorial Errors Identified ML20236F7461998-06-26026 June 1998 Forwards Copy of EA & Fonsi Re Application for Amend Dated 971222.Proposed Amend Would Revise Possession Only License for Westinghouse Test Reactor at Waltz to Reflect Change in Legal Name from Westinghouse Electric Co to CBS Corp RA-98-033, Informs That Name of Licensee Can Be Revised Instead to CBS Corp Acting Through Westinghouse Electric Company. Analysis of Issue of Nshc,Encl1998-06-15015 June 1998 Informs That Name of Licensee Can Be Revised Instead to CBS Corp Acting Through Westinghouse Electric Company. Analysis of Issue of Nshc,Encl ML20216F2231998-04-13013 April 1998 Final Response to FOIA Request for Documents.Forwards Documents Listed in App B in Entirety IA-98-100, Final Response to FOIA Request for Documents.Forwards Documents Listed in App B in Entirety1998-04-13013 April 1998 Final Response to FOIA Request for Documents.Forwards Documents Listed in App B in Entirety RA-98-021, Submits Addl Info & Clarification in Response to Questions Raised in Re Decommissioning Plan Submitted on 970731.Attachment 1 Provides Answers to Specific Questions in & Attachment 2 Provides Environ Rept1998-03-20020 March 1998 Submits Addl Info & Clarification in Response to Questions Raised in Re Decommissioning Plan Submitted on 970731.Attachment 1 Provides Answers to Specific Questions in & Attachment 2 Provides Environ Rept ML20199A2981998-01-21021 January 1998 Forwards Request for Addl Info Re Review of Westinghouse Test Reactor Decommissioning Plan Submitted by . Response to Encl RAI Should Be Submitted within 60 Days of Ltr Date ML20199G9611998-01-20020 January 1998 Permits Withdrawal of 970818 Application to Transfer & Amend License for Westinghouse Test Reactor Facility. Withdrawal Notice Encl RA-98-008, Forwards 1997 Annual Insp Rept for Retired Westinghouse Test Reactor.Status of Retired Facility Remains Same as Time of Last Rept1998-01-20020 January 1998 Forwards 1997 Annual Insp Rept for Retired Westinghouse Test Reactor.Status of Retired Facility Remains Same as Time of Last Rept RA-97-091, Submits Request for Withdrawal of Application to Transfer & Amend License for Westinghouse Test Reactor Facility1997-12-18018 December 1997 Submits Request for Withdrawal of Application to Transfer & Amend License for Westinghouse Test Reactor Facility ML20217F0181997-09-23023 September 1997 Forwards Notice of Consideration of Approval of Transfer of License & Issuance of Amend to Facility License,Proposed NSHC & Opportunity for Hearing. Notice Relates to 970818 Application Seeking Approval of Transfer of Authority ML20217E4181997-09-23023 September 1997 Forwards EA & Fonsi Re 970818 Application for Approval of Transfer of License for Waltz Mill Test Reactor from W to (1886) to (1997) & Issuance of Conforming Amend,Per 10CFR50.80 & 10CFR50.90 ML20141J8171997-08-0505 August 1997 Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transferred from Regional Ofc to Nrr.All Activities Re Non-Power Reactors Including Licensing,Insp & Operator Licensing Will Be Responsibility of NRR RA-97-053, Forwards Rept Entitled, Westinghouse Test Reactor TR-2, Final Decommissioning Plan. Rept Provides General Plan & Time Schedule for Radiological Remediation of Wtr Facility on Westinghouse Waltz Mill Site1997-07-31031 July 1997 Forwards Rept Entitled, Westinghouse Test Reactor TR-2, Final Decommissioning Plan. Rept Provides General Plan & Time Schedule for Radiological Remediation of Wtr Facility on Westinghouse Waltz Mill Site ML20147H8931997-04-0707 April 1997 Forwards W Repts Conceptual Remediation Plan & Conceptual Decommissioning Plan, Which Provides Time Schedule for Radiological Remediation of Wtr Facility & Objectives, Priorities,Schedule & Remediation Approaches IR 05000022/19970011997-03-0606 March 1997 Forwards Insp Rept 50-022/97-01 on 970203-05.No Noncompliance Noted ML20057F3401993-10-0404 October 1993 Forwards Insp Rept 50-022/93-01 on 930913.No Safety Concerns or Violations Noted RS-93-008, Informs That Westinghouse Planning to Conduct Radiological Characterizationsurvys of License TR-2 Facilities,In Connection W/Annual Radiological Surveys & Safety/Fire Insps of Reactor Containment Bldg & Associated Facilities1993-02-0505 February 1993 Informs That Westinghouse Planning to Conduct Radiological Characterizationsurvys of License TR-2 Facilities,In Connection W/Annual Radiological Surveys & Safety/Fire Insps of Reactor Containment Bldg & Associated Facilities ML20126D3651992-12-21021 December 1992 Forwards Annual Rept of Insp of Retired Westinghouse Test Reactor for 1992 ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20150D8641988-03-18018 March 1988 Informs of Relocation of NRR to Rockville,Md.Official Mailing Address Still Remains Same & Project Managers Have New Locations & Phone Numbers.Ts Michaels Still Lead Project Manager for Facility & a Adams Will Serve as Backup ML20215C4061987-05-29029 May 1987 Informs of Recent Reorganization of Nrr.T Michaels Assigned as Project Manager for Facility ML20210F7271987-02-0505 February 1987 Forwards Addendum to Annual Insp Rept for Retired Westinghouse Testing Reactor for 1986, Per J Dosa 870128 Telcon W/Author.Addendum Provides Clarification & Addl Info ML20207C4801986-12-22022 December 1986 Forwards Annual Insp of Retired Westinghouse Testing Reactor Per License TR-2 for 1986 ML20138P8891985-12-16016 December 1985 Forwards Annual Insp of Retired Westinghouse Test Reactor (License TR-2) for 1985.Status of Retired Facility Remains Same as Last Rept ML20216F7431969-05-19019 May 1969 Forwards Order Authorizing Partial Dismantle of Wtr to Extent Described in 690429 Application & Suppl, . Notice of Issuance of Order Also Encl ML20216F7351967-06-28028 June 1967 Discusses Re Request for Renewal of License TR-2 ML20216F7181963-03-25025 March 1963 Forwards Amend 2 to License TR-2,authorizing W to Possess, But Not to Operate Wtr.Also Encl Are Notice of Amend & Hazards Analysis Rept ML20216F6401962-03-0202 March 1962 Forwards Analysis of Safety Operation of Wta.Authorization Granted to W to Transfer Sf Elements to Pool in Decontamination Bldg for Storage Prior to Shipment Off Site ML20216F5041960-07-28028 July 1960 Forwards Rept Re Release of Contaminated Water to Storm Sewers on Wtr Site.Prevention of Further Releases of This Type Are Listed ML20216F5401960-07-18018 July 1960 Submits Table Giving Suitable Operating Conditions Which Will Be Observed During Escalation Program.Wtr Operating Procedures P-107 Detailing Action to Be Taken by Reactor Operating Staff in Event of Reactivity Changes Encl ML20216F2411960-06-30030 June 1960 Forwards Order issued,600630,respecting Operation of Westinghouse Testing Reactor ML20216F4091960-04-0404 April 1960 Forwards Rept Dealing W/Incident Involving Release of Radioactivity at Wtr Site,Per Requirements of Wtr Emergency Procedures 1999-06-14
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D0681999-10-0707 October 1999 Forwards First of Planned Series of Progress Repts Re Status of Remediation & Decommissioning Work Underway at W Waltz Mill Site Near Madison,Pa ML20216K0441999-10-0404 October 1999 Forwards Proposed Replacement Pages to TR-2 Ts,In Order to Provide Addl Clarifications & to Accommodate Minor Editorial Changes.Ts Amend Would Clarify Facility Boundaries ML20216J7501999-10-0101 October 1999 Forwards Proposed Replacement Pages to Decommissioning Plan & for Ts.Pages Are Being Submitted to Replace Similar Pages Previously Transmitted in ML20195H4271999-06-14014 June 1999 Forwards Annual Insp of Retired Wtr Per License TR-2 for 1998.Physical Status of Retired Facility Remains Same as It Was at Time of Last Rept ML20204F6351999-03-18018 March 1999 Expresses Appreciation to NRC for Forwarding Copy of Insp Rept 50-022/99-201 Reflecting Results of 990203 Insp of W Test Reactor at Waltz Mill Site.Review of Insp Rept Raises Listed Concerns.Nrc Help in Matter Would Be Appreciated ML20205L1141999-03-12012 March 1999 Partially Deleted Ltr Establishing Irrevocable Standby Ltr of Credit in NRC Favor,At Request & for Account of W RA-98-070, Forwards Addl Info in Support of Application to Amend License TR-2 Re Name Change1998-11-17017 November 1998 Forwards Addl Info in Support of Application to Amend License TR-2 Re Name Change ML20154B0481998-09-28028 September 1998 Establishes Irrevocable Standby Ltr of Credit 1484 in NRC Favor,At Request & for Account of W,Up to Aggregate Amount of $11,098,000 Upon Presentation of Sight Draft & Signed Statement RA-98-038, Forwards Errata to Rev 1 to W Test Reactor TR-2 Final Decommissioning Plan, Correcting Minor Editorial Errors Identified1998-07-10010 July 1998 Forwards Errata to Rev 1 to W Test Reactor TR-2 Final Decommissioning Plan, Correcting Minor Editorial Errors Identified RA-98-033, Informs That Name of Licensee Can Be Revised Instead to CBS Corp Acting Through Westinghouse Electric Company. Analysis of Issue of Nshc,Encl1998-06-15015 June 1998 Informs That Name of Licensee Can Be Revised Instead to CBS Corp Acting Through Westinghouse Electric Company. Analysis of Issue of Nshc,Encl RA-98-021, Submits Addl Info & Clarification in Response to Questions Raised in Re Decommissioning Plan Submitted on 970731.Attachment 1 Provides Answers to Specific Questions in & Attachment 2 Provides Environ Rept1998-03-20020 March 1998 Submits Addl Info & Clarification in Response to Questions Raised in Re Decommissioning Plan Submitted on 970731.Attachment 1 Provides Answers to Specific Questions in & Attachment 2 Provides Environ Rept RA-98-008, Forwards 1997 Annual Insp Rept for Retired Westinghouse Test Reactor.Status of Retired Facility Remains Same as Time of Last Rept1998-01-20020 January 1998 Forwards 1997 Annual Insp Rept for Retired Westinghouse Test Reactor.Status of Retired Facility Remains Same as Time of Last Rept RA-97-091, Submits Request for Withdrawal of Application to Transfer & Amend License for Westinghouse Test Reactor Facility1997-12-18018 December 1997 Submits Request for Withdrawal of Application to Transfer & Amend License for Westinghouse Test Reactor Facility RA-97-053, Forwards Rept Entitled, Westinghouse Test Reactor TR-2, Final Decommissioning Plan. Rept Provides General Plan & Time Schedule for Radiological Remediation of Wtr Facility on Westinghouse Waltz Mill Site1997-07-31031 July 1997 Forwards Rept Entitled, Westinghouse Test Reactor TR-2, Final Decommissioning Plan. Rept Provides General Plan & Time Schedule for Radiological Remediation of Wtr Facility on Westinghouse Waltz Mill Site ML20147H8931997-04-0707 April 1997 Forwards W Repts Conceptual Remediation Plan & Conceptual Decommissioning Plan, Which Provides Time Schedule for Radiological Remediation of Wtr Facility & Objectives, Priorities,Schedule & Remediation Approaches RS-93-008, Informs That Westinghouse Planning to Conduct Radiological Characterizationsurvys of License TR-2 Facilities,In Connection W/Annual Radiological Surveys & Safety/Fire Insps of Reactor Containment Bldg & Associated Facilities1993-02-0505 February 1993 Informs That Westinghouse Planning to Conduct Radiological Characterizationsurvys of License TR-2 Facilities,In Connection W/Annual Radiological Surveys & Safety/Fire Insps of Reactor Containment Bldg & Associated Facilities ML20126D3651992-12-21021 December 1992 Forwards Annual Rept of Insp of Retired Westinghouse Test Reactor for 1992 ML20210F7271987-02-0505 February 1987 Forwards Addendum to Annual Insp Rept for Retired Westinghouse Testing Reactor for 1986, Per J Dosa 870128 Telcon W/Author.Addendum Provides Clarification & Addl Info ML20207C4801986-12-22022 December 1986 Forwards Annual Insp of Retired Westinghouse Testing Reactor Per License TR-2 for 1986 ML20138P8891985-12-16016 December 1985 Forwards Annual Insp of Retired Westinghouse Test Reactor (License TR-2) for 1985.Status of Retired Facility Remains Same as Last Rept ML20216F5041960-07-28028 July 1960 Forwards Rept Re Release of Contaminated Water to Storm Sewers on Wtr Site.Prevention of Further Releases of This Type Are Listed ML20216F5401960-07-18018 July 1960 Submits Table Giving Suitable Operating Conditions Which Will Be Observed During Escalation Program.Wtr Operating Procedures P-107 Detailing Action to Be Taken by Reactor Operating Staff in Event of Reactivity Changes Encl ML20216F4091960-04-0404 April 1960 Forwards Rept Dealing W/Incident Involving Release of Radioactivity at Wtr Site,Per Requirements of Wtr Emergency Procedures 1999-06-14
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Westinghouse ELECTRIC CORPORATlON O
TESTING REACTOR l July 18, 1960 P.O. DOX 107 5 PITTSBURGH 30, PA,
! Mr. H. L. Price, Director Division of Licensing and Regulation U. S. Atomic Energy Commission l Washingto; 25, D. C.
Dear Mr. Price:
Subject:
Lice'nse No. TR-2 Docket 60-22 N9d During a meeting with members of your staff on July 12, 1960 certain information was requested to supplement that furnished you with our letter of July 11, 1960.
In paragraph 3, page 3, of our letter we proposed to limit heat flux by limiting the amount of local boiling in the core. A satifac cory alternate method of heat flux control is the establishment of minimum primary coolant flow conditions as a function of power level.
The following table gives suitable operating conditions which will be l obcerved during the escalation program and early 60 MW operation of the WTR, l
Power Level as a Function of
, Minimum Core Flow I
and Inlet Temperature Thermal Inlet Minimum Core (Approximate Total Power Temperature 'F Flow GPM Coolant Flow GPM )
- 60 140 11 200 16 800 60 115 9 260 13 900 50 140 8 200 12 300 50 115 7 530 11 300 l l
40 140 6 530 9 800 i 40 115 5 930 8 900 ;
In between conditions are to be obtained by linear interpolation.
These values were derived on the basis precented in Section K of Report WTR-49 A 10% hot channel factor has been added to cover small '
defects in fuel elements. The resulting values represent an operational safety factor in burnout heat flux greater than 2 3 under all operating conditions.
9004170116 980413 ' ' '
PDR FOIA ' . ~ . .l NeU9 ROLLER 98-100 PDR gggg//g YOU CAN BE 8MME...it it'sWOStillgl10llSO L -
oh Mr. H. L. Price July 18, 1960
, _ Attached are forty (40) copies of WTR Operating. Procedures P-107 which detail action to be taken by the reactor operating staff in the event of sudden reactivity changes or fission product release to the
! primary coolant.
As requested, we have conducted a thorough review of both the construction drawings and the installed equipment of the primary loop, the vapor container, and the ventilation system in an effort to determine if there were any possible paths of leakage in the containment system.
No other possible direct leakage from the containment system other than i the known venting system of the primary coolant head and surge tanks was discovered. We have recently applied to the Isotopes Branch of the Division of Licensing and Regulation for a broad Byproduct Materials License. In the course of preparing information required for this license, we are conducting a thorough examination and analysis of any possible abnormal radioactive discharge from secondary radiation sources, such as laboratories and hot cells. The results of this study will be presented to the Isotopes Branch.
We have found the incident of the fuel element failure, although regrettable, to have been a valuable experience from the standpoint of operating standards and procedures, the handling of emergency conditions, and the development of techniques. The folloiring requirements have been particularly emphasized:
- a. The need for extreme care in specifying, handling, and inspecting fuel. No step in the process can be taken for granted. In addition to the inspection program outlined in our July 11, 1960 letter, we <
have set up local inspection facilities immediately '
adjacent to the main fuel storage rack for rechecking key mechanical dimensions of fuel elements after receipt from the supplier.
- b. The training process for reactor operators and super-visors must be a continuing program. We have emphasized and will continue to emphasize to the reactor operators that a sudden change in negative reactivity can be as symptomatically significant as a positive change in reactivity. We will, as in the past, continually stress safety at our operations staff meetings and make every
! effort to keep our operators constantly on the alert for :
unusual operating symptoms. '
l As a result of the incident, a number of minor changes have been made or are underway in the plant system. Among the modifications are:
Mr. H. L. Price July 18, 1960
- a. Relocation of the fission product monitor to obtain a greater speed of response.
b .. Addition of more drainage points in the primary loop to permit easier removal of radioactive particles at
' pipe bends and other inconvenient locations,
- c. Addition of lead shielding on the bottom head of the reactor vessel and rabbit tubes to reduce the radiation hvel in the sub-pile room.
- d. Addition of a spray-wach-down system to confine con-tamination to the pressure vecsel when head is being removed.
- e. Addition of new waterproof lines for primary loop temperature instrumentation to permit operation should pipe tunnels become flooded.
- f. Addition of a canal filter and vacuuming system to c1,ean up radioactive particles on the floor of ther canal. ,
.A number of new techniques for handling radiation and decon-tamination problems are now available. Methods have been developed for clearing the reactor vessel of radioactive particles, decontaminating the vessel head, removing the shroud tubes when they are contaminated, cleaning the primary piping system, decontaminating the heat exchangers and cleaning the surge tank. Improved methods of waste disposal and water handling have been developed. Canal machinery and underwater handling processes have been improved. Health Physics instrumentation has been strengthened, and the procedures and clothing for working under radioactive conditions have all been proven or modified by experience.
Our immediate permanent personnel level has been increased from 110 to 135 of which 8 have been additions to the Health Physics Department. i l
In summary, our personnel has been subjected to a rigorous I experience in the handling and control of high-level radiation problems. l This experience has resulted in increased strength in all areas of operation which will be a major factor in the future successful operation. l of the'wTR. i j Sincerely yours,
?XNO+zAa E. T. Morris General Manager i
I l