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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N8911999-10-15015 October 1999 Forwards Rept of Changes,Tests & Experiments at Pilgrim Nuclear Power Station for Period of 970422-990621,IAW 10CFR50.59(b).List of Changes Effecting Fsar,Encl ML20217D3951999-10-13013 October 1999 Forwards Request for Addl Info Re Util 990806 Submittal on USI A-46, Implementation Methodology Used at Pilgrim Nuclear Power Station, Per GL 87-02 ML20217E1581999-10-0808 October 1999 Forwards Insp Rept 50-293/99-05 on 990726-0905.Three Violations Noted & Being Treated as Ncvs.Violations Include Failure to Assure That Design Bases Correctly Translated Into Specifications ML20217C3151999-10-0606 October 1999 Forwards Scenario Package for Pilgrim Nuclear Power Station Nrc/Fema Evaluated Exercise Scheduled for 991207.Without Encl ML20217D5591999-10-0505 October 1999 Documents Pilgrim Nuclear Power Station Five Yr Survey of Main Breakwater.Survey Has Determined That Pilgrim Main Breakwater Is Intact & Remains Adequately Constructed to Perform Designed Safety Function ML20217C8051999-10-0505 October 1999 Forwards Proprietary Results of Audiologic Evaluations for Jp Giar,License SOP-10061-3.Attachment Clearly Shows Requirements for Operator Hearing Ability Are Met. Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20212J8301999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Integrate Performance Info & to Plan Insp Activities at Facility Over Next Six Months ML20216J9961999-09-29029 September 1999 Forwards Resume of Person Identified as Acting RPM in Licensee to NRC Re Notification That Person Named in License Condition 11 of 20-07626-02,is No Longer Employed at Pilgrim Station.Resume Withheld,Per 10CFR2.790 ML20212F7871999-09-24024 September 1999 Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses ML20212H1381999-09-23023 September 1999 Submits Info in Support of Request Filed on 990730 to Grant one-time Exemption from 10CFR50,App E,Authorizing Biennial Full Participation Emergency Preparedness Exercise to Be Conducted in 2002 Instead of 2001 ML20212H1441999-09-23023 September 1999 Withdraws 990121 Request for License Change Re Emergency Core Cooling Sys Net Positive Suction Head,Due to Incorrect Datum Preparation ML20216F3451999-09-16016 September 1999 Forwards Summary Rept Providing Results of ISI Conducted at PNPS on-line & Refueling Outage (RFO 12) ML20212C2861999-09-16016 September 1999 Forwards SER Accepting Licensee 981123 Request for Relief RR-E1,RR-E5,RR-E6 Pursuant to 10CFR50.55a(a)(3)(i) & Request for Relief RR-E2,RR-E3 & RR-E4 Pursuant to 10CFR50.55a(a)(3)(ii) ML20216E7111999-09-0909 September 1999 Forwards License Renewal Application Including Form NRC-398 & Form NRC-396 for Jp Giar,License SOP-10061-3.Without Encls ML20216E5891999-09-0707 September 1999 Forwards Copy of Pilgrim Station Organization Structure. Encl Refelcts Changes in Upper Mgt Level Structure.Changes Were Effective 990901 ML20211M4501999-09-0303 September 1999 Informs That Pilgrim Nuclear Power Station Plans to Conduct Full Participation Emergency Preparedness Exercise with Commonwealth of Ma on 991207,IAW 10CFR50,App E,Section IV.F.2 ML20211M9161999-08-31031 August 1999 Submits Review & Correction of Info in Reactor Vessel Integrity Database (Rvid),Version 2,re Pilgrim Station ML20211J8391999-08-30030 August 1999 Forwards Rev 1 to Provisional Decommissioning Trust Agreement for Plant,Changing Portions of Agreement to Permit Up to Two Distributions & Clarify Formula for Distribution ML20211H5701999-08-27027 August 1999 Forwards Insp Rept 50-293/99-04 on 990610-0725.Two Violations Identified Being Treated as non-cited Violations ML20211C3381999-08-19019 August 1999 Provides semi-annual LTP Update,Including Schedule, Commitment Descriptions,Progress Since Last Update & Summary of Changes.Rev Bars Indicate Changes in Status Since Last Submittal ML20210U5761999-08-18018 August 1999 Responds to Opposing Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts. Informs That for Sale,Nrc Responsible for Only Ensuring That Entergy Technically & Financially Qualified to Operate NPP ML20210U6691999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opposing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U7521999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opossing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5151999-08-17017 August 1999 Forwards Notice of Withdrawal of Application for Approval of Indirect Transfer of FOL for Pilgrim in Response to .Approval No Longer Needed Since Beco Sold Interest in Pilgrim to EOI on 990713 ML20211B3841999-08-16016 August 1999 Forwards Response to NRC Second RAI Re Pressure Locking & Thermal Binding of SR power-operated Gate Valves ML20210U4831999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data Sheets for Period of 990101-0630,per 10CFR26.71(d) ML20210S0891999-08-0909 August 1999 Forwards Amend 11 to Indemnity Agreement B-48 Signed by Boston Edison Co & Entergy Nuclear Generation Co ML20210R6251999-08-0606 August 1999 Provides Supplementary Info on USI A-46 Implementation Methodology at Pilgrim Station,To Enable NRC to Perform Evaluation & Issuance of Plant Specific SER for Plant ML20210M9411999-08-0202 August 1999 Requests That NRC Treat Pending Actions Requested by Beco Prior to 990713,as Requests Made by Entergy.Ltr Requests That Minor Administrative Changes to License Amend 182 & Associated Ser, ,reflect 990713 Transfer ML20210H8761999-07-30030 July 1999 Requests That NRC Grant Exemption from Requirements of 10CFR50,App E,Section IV F,Which Would Authorize Rescheduling of 2001 Biennial Full Participation Emergency Preparedness Exercise for Pilgrim Station to 2002 ML20210H8661999-07-29029 July 1999 Provides Revised Response to GL 96-06 & Addresses NRC Insp Concern for Containment Penetration X-12.Info Submitted to Facilitate NRC Review & Closeout of Subject GL for Plant ML20216E2321999-07-26026 July 1999 Discusses GL 92-01,rev 1,suppl 1, Rv Structural Integrity. NRC Revised Info in Rvid & Releasing as Rvid Version 2 ML20216D4131999-07-22022 July 1999 Informs That J Conlon,License OP-11040-1,terminated Employment with Beco on 990703,per 10CFR50.74.Individual Will Not Participate in Util Licensed Operator Requalification Training Program ML20210E2231999-07-20020 July 1999 Discusses Arrangements Made by Dennis & M Santiago During 990615 Telephone Conversation for NRC to Inspect Licensed Operator Requalification Program at Pilgrim During Wk of 991004 ML20210C4151999-07-19019 July 1999 Informs That Util Intends to Submit Approx Eight Licensing Actions in FY00 & Eight in FY01,in Response to Administrative Ltr 99-02.Actions Are Not Expected to Generate Complex Reviews ML20210F3711999-07-14014 July 1999 Informs NRC That Effective 990713,listed Pilgrim Station Security Plans Have Been Transferred from Boston Edison to Entergy & Are Still in Effect ML20210A9441999-07-14014 July 1999 Responds to Re Changes to Pilgrim Nuclear Power Station Physical Security Plan Identified as Issue 2,rev 14, Addendum 1,respectively.No NRC Approval Is Required IAW 10CFR54(p) ML20209G2251999-07-0909 July 1999 Forwards Insp Rept 50-293/99-03 on 990419-0609.Five Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C. Several Individual Tagging Errors Occurred ML20209C4661999-07-0707 July 1999 Forwards SE Accepting Addendum on Proposed Change in Corporate Ownership Structure Involving Entergy Nuclear Generation Co ML20209C7761999-07-0606 July 1999 Submits Annual Summary Rept of Changes Made to QAP Description as Described in QA Manual,Vol Ii.Rept Covers Period of Jul 1998 Through June 1999.No Changes Made During Period ML20209C3851999-07-0606 July 1999 Forwards Redacted Draft of Decommissioning Trust Agreement Re Transfer of PNPS & NRC Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generating Co ML20196J7251999-07-0101 July 1999 Informs of Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Pilgrim Nuclear Power Station ML20209B9411999-06-30030 June 1999 Discusses Deferral of IGSCC Welds to RFO 13.Deferral of Welds to Refueling Outage 13 Does Not Impact Acceptable Level of Quality & Safety Per 10CFR50.55(a)(3)(i) Since Plant in Compliance W/Exam Percentage Requirements ML20209B9431999-06-30030 June 1999 Provides Formal Notification That Closing Date for Sale & Transfer of Pilgrim Station Scheduled to Occur on 990713. a Wang Will Be Verbally Notified of Time of Sale Closing ML20209B9791999-06-29029 June 1999 Forwards Rev 13A to Pilgrims COLR for Cycle 13,IAW TS 5.6.5 Requirements.Rev 13A Provides cycle-specific Limits for Operating Pilgrim During Remainder of Cycle 13 ML20196H2381999-06-29029 June 1999 Forwards SER Denying Licensee 980820 Request for Alternative Under PRR-13,rev 2 for Use of Code Case N-522 During Pressure Testing of Containment Penetration Piping ML20209A8761999-06-28028 June 1999 Forwards SER Authorizing Licensee 990317 Relief Request to Use ASME Code Case N-573 as Alternative to ASME Code Section XI Article IWA-4000 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209A8701999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant,Reporting Status of Facility Y2K Readiness Encl ML20210U5901999-06-25025 June 1999 Opposes Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts.Expresses Skepticism Re Claim by Companies That Consumers Will Benefit from Proposed Consolidation & four-year Freeze in Base Rates ML20209C3431999-06-22022 June 1999 Forwards Addendum 1,Rev 14 to Pilgrim Station Security Plan,Iaw 10CFR50.54(p)(2).Changes Proposed Have Been Implemented & Constitute Increase in Plant Defense Plan Commitments.Encl Withheld,Per 10CFR73.21 1999-09-09
[Table view] Category:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
MONTHYEARML20245C1421989-04-0303 April 1989 Forwards Endorsements 75,108,108,96 & 110 to Maelu Policies MF-56,MF-26,MF-58,MF-39 & MF-52,respectively & Endorsements 93,129,127,109 & 122 to Nelia Policies NF-186,NF-76,NF-188, NF-151 & NF-173,respectively ML20206H0511988-11-14014 November 1988 Urges Relicensing of Pilgrim & Expedited Operation of Seabrook.Newspaper Clipping Encl ML20206B8471988-06-16016 June 1988 Accepts 880601 Protocol for Jul 1988 Insp.Nrc Insp Plan Requested ML20235A1251987-12-16016 December 1987 Forwards Info Re Resource Technical Svcs,Inc,Including Summary of NRC Contract Work,Nrc Form 26 for Three Existing Contracts,Audit Info,Work History & Lists of Expertise Available for Special Insps & of Current Resource Svcs ML20235V1321987-08-28028 August 1987 Forwards EGG-NTA-7471, Technical Evaluation Rept,Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28.... Based on Licensee Responses,Plants Reviewed Conform W/Exceptions Listed in Section 14 ML20245A4451986-09-25025 September 1986 Forwards Revised Draft EGG-NTA-7188, Conformance to Generic Ltr 83-28 Item 2.1 (Part 1) Equipment Classification Hope Creek,Peach Bottom 2 & 3,Perry 1 & 2 & Pilgrim 1 ML20204J0041986-06-0404 June 1986 Forwards Cover Ltrs,Revs 810 & 860 to Model DOS-502A Digital Alarm Dosimeter Specs & Recommendations for Operation of Dositec Model DOS-502A.Documents Sent to Users in Nuclear Power Plants,Utils & non-nuclear Facilities ML20133H0871985-10-10010 October 1985 Requests Ltr Stating That Listed Facilities Do Not Have Fuel Element Transfer Tubes.Documentation Needed for IE Bulletin 78-08 Closeout Rept ML20039B7401981-11-30030 November 1981 Forwards Review & Evaluation of Licensee 810318 Submittal Requesting Exemption for Vital Motor Generator Set Room from Section III,G,2 of App R to 10CFR50,per Guidelines in SRP, Section 9.5.1 & App A.Exemption Request Should Be Denied ML19329D5321968-02-28028 February 1968 Forwards Rept to Aec,Adequacy of Structural Criteria for Crystal River 3 & 4. Notifies That Addl Thought to Be Given Re Attachment of Liner to Angles & Buckling Strength. Suggests Request for Addl Info 1989-04-03
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N8911999-10-15015 October 1999 Forwards Rept of Changes,Tests & Experiments at Pilgrim Nuclear Power Station for Period of 970422-990621,IAW 10CFR50.59(b).List of Changes Effecting Fsar,Encl ML20217C3151999-10-0606 October 1999 Forwards Scenario Package for Pilgrim Nuclear Power Station Nrc/Fema Evaluated Exercise Scheduled for 991207.Without Encl ML20217C8051999-10-0505 October 1999 Forwards Proprietary Results of Audiologic Evaluations for Jp Giar,License SOP-10061-3.Attachment Clearly Shows Requirements for Operator Hearing Ability Are Met. Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20217D5591999-10-0505 October 1999 Documents Pilgrim Nuclear Power Station Five Yr Survey of Main Breakwater.Survey Has Determined That Pilgrim Main Breakwater Is Intact & Remains Adequately Constructed to Perform Designed Safety Function ML20216J9961999-09-29029 September 1999 Forwards Resume of Person Identified as Acting RPM in Licensee to NRC Re Notification That Person Named in License Condition 11 of 20-07626-02,is No Longer Employed at Pilgrim Station.Resume Withheld,Per 10CFR2.790 ML20212H1441999-09-23023 September 1999 Withdraws 990121 Request for License Change Re Emergency Core Cooling Sys Net Positive Suction Head,Due to Incorrect Datum Preparation ML20212H1381999-09-23023 September 1999 Submits Info in Support of Request Filed on 990730 to Grant one-time Exemption from 10CFR50,App E,Authorizing Biennial Full Participation Emergency Preparedness Exercise to Be Conducted in 2002 Instead of 2001 ML20216F3451999-09-16016 September 1999 Forwards Summary Rept Providing Results of ISI Conducted at PNPS on-line & Refueling Outage (RFO 12) ML20216E7111999-09-0909 September 1999 Forwards License Renewal Application Including Form NRC-398 & Form NRC-396 for Jp Giar,License SOP-10061-3.Without Encls ML20216E5891999-09-0707 September 1999 Forwards Copy of Pilgrim Station Organization Structure. Encl Refelcts Changes in Upper Mgt Level Structure.Changes Were Effective 990901 ML20211M4501999-09-0303 September 1999 Informs That Pilgrim Nuclear Power Station Plans to Conduct Full Participation Emergency Preparedness Exercise with Commonwealth of Ma on 991207,IAW 10CFR50,App E,Section IV.F.2 ML20211M9161999-08-31031 August 1999 Submits Review & Correction of Info in Reactor Vessel Integrity Database (Rvid),Version 2,re Pilgrim Station ML20211J8391999-08-30030 August 1999 Forwards Rev 1 to Provisional Decommissioning Trust Agreement for Plant,Changing Portions of Agreement to Permit Up to Two Distributions & Clarify Formula for Distribution ML20211C3381999-08-19019 August 1999 Provides semi-annual LTP Update,Including Schedule, Commitment Descriptions,Progress Since Last Update & Summary of Changes.Rev Bars Indicate Changes in Status Since Last Submittal ML20211B3841999-08-16016 August 1999 Forwards Response to NRC Second RAI Re Pressure Locking & Thermal Binding of SR power-operated Gate Valves ML20210U4831999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data Sheets for Period of 990101-0630,per 10CFR26.71(d) ML20210S0891999-08-0909 August 1999 Forwards Amend 11 to Indemnity Agreement B-48 Signed by Boston Edison Co & Entergy Nuclear Generation Co ML20210R6251999-08-0606 August 1999 Provides Supplementary Info on USI A-46 Implementation Methodology at Pilgrim Station,To Enable NRC to Perform Evaluation & Issuance of Plant Specific SER for Plant ML20210M9411999-08-0202 August 1999 Requests That NRC Treat Pending Actions Requested by Beco Prior to 990713,as Requests Made by Entergy.Ltr Requests That Minor Administrative Changes to License Amend 182 & Associated Ser, ,reflect 990713 Transfer ML20210H8761999-07-30030 July 1999 Requests That NRC Grant Exemption from Requirements of 10CFR50,App E,Section IV F,Which Would Authorize Rescheduling of 2001 Biennial Full Participation Emergency Preparedness Exercise for Pilgrim Station to 2002 ML20210H8661999-07-29029 July 1999 Provides Revised Response to GL 96-06 & Addresses NRC Insp Concern for Containment Penetration X-12.Info Submitted to Facilitate NRC Review & Closeout of Subject GL for Plant ML20216D4131999-07-22022 July 1999 Informs That J Conlon,License OP-11040-1,terminated Employment with Beco on 990703,per 10CFR50.74.Individual Will Not Participate in Util Licensed Operator Requalification Training Program ML20210C4151999-07-19019 July 1999 Informs That Util Intends to Submit Approx Eight Licensing Actions in FY00 & Eight in FY01,in Response to Administrative Ltr 99-02.Actions Are Not Expected to Generate Complex Reviews ML20210F3711999-07-14014 July 1999 Informs NRC That Effective 990713,listed Pilgrim Station Security Plans Have Been Transferred from Boston Edison to Entergy & Are Still in Effect ML20209C3851999-07-0606 July 1999 Forwards Redacted Draft of Decommissioning Trust Agreement Re Transfer of PNPS & NRC Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generating Co ML20209C7761999-07-0606 July 1999 Submits Annual Summary Rept of Changes Made to QAP Description as Described in QA Manual,Vol Ii.Rept Covers Period of Jul 1998 Through June 1999.No Changes Made During Period ML20209B9411999-06-30030 June 1999 Discusses Deferral of IGSCC Welds to RFO 13.Deferral of Welds to Refueling Outage 13 Does Not Impact Acceptable Level of Quality & Safety Per 10CFR50.55(a)(3)(i) Since Plant in Compliance W/Exam Percentage Requirements ML20209B9431999-06-30030 June 1999 Provides Formal Notification That Closing Date for Sale & Transfer of Pilgrim Station Scheduled to Occur on 990713. a Wang Will Be Verbally Notified of Time of Sale Closing ML20209B9791999-06-29029 June 1999 Forwards Rev 13A to Pilgrims COLR for Cycle 13,IAW TS 5.6.5 Requirements.Rev 13A Provides cycle-specific Limits for Operating Pilgrim During Remainder of Cycle 13 ML20209A8701999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant,Reporting Status of Facility Y2K Readiness Encl ML20210U5901999-06-25025 June 1999 Opposes Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts.Expresses Skepticism Re Claim by Companies That Consumers Will Benefit from Proposed Consolidation & four-year Freeze in Base Rates ML20209C3431999-06-22022 June 1999 Forwards Addendum 1,Rev 14 to Pilgrim Station Security Plan,Iaw 10CFR50.54(p)(2).Changes Proposed Have Been Implemented & Constitute Increase in Plant Defense Plan Commitments.Encl Withheld,Per 10CFR73.21 ML20195G3721999-06-0707 June 1999 Informs That Proposed Indicators Failed QA Assessments for Digital Verification,Validation & Control of Software. Proposed Mod Can Be Completed on-line ML20195B5021999-05-27027 May 1999 Provides Suppl Info to 990203 Request of Beco That NRC Consent to Indirect Transfer of Control of Util Interest in License DPR-35.Request Described Proposed Merger of Bec Energy with Commonwealth Energy Sys ML20207D4681999-05-24024 May 1999 Provides Addl Info to That Included in Beco Ltr 98-123 Dtd 981001,addressing NRC Concerns Described in GL 96-06, Concerning Waterhammer in Reactor Bldg Closed Cooling Water Sys ML20195B9051999-05-20020 May 1999 Forwards Completed Renewal Applications for Listed Operators.Without Encls ML20206J4901999-05-0606 May 1999 Forwards Completed License Renewal Application,Including Forms NRC-398 & 396 for Sc Power,License OP-6328-3 ML20206P0711999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, for K Walz,License SOP-10886-1.Encl Withheld IAW 10CFR2.790(a)(6) ML20206D3621999-04-27027 April 1999 Informs NRC That Final Five Sys self-assessments Required to Fulfill Commitment Made in 980828 Response to Insp Rept 50-293/98-04 Were Completed on 990422.Completion Was Delayed by High Priority Refueling Outage 12 Preparatory Work ML20205R9871999-04-21021 April 1999 Forwards Affidavit of JW Yelverton of Entergy Nuclear Generation Co Supporting Request for Withholding Info from Rept on Audit of Financial Statements for Year Ended 971231. Pages 16 & 18 of Subj Rept Also Encl ML20207B0891999-04-20020 April 1999 Forwards e-mail Message from Constituent,J Riell Re Y2K Compliance of Nuclear Power Plant in Plymouth,Massachusetts. Copy of Article Entitled Nuke Plants May Not Be Y2K Ready Also Encl ML20206A2741999-04-16016 April 1999 Dockets Encl Ltr Which Was Sent to AL Vietti-Cook Re Condition of Approval of Transfer of License & License Condition for DPR-35.Encl Resolves Issues Between Attorney General of Commonwealth of Massachusetts & Applicants ML20205P9131999-04-16016 April 1999 Submits Applicant Consent to Listed Condition of Approval of Transfer of License & License Condition for License DPR-35 & Affirmatively Request That NRC Adopt Listed Language in Order ML20205P9271999-04-16016 April 1999 Withdraws Motion for Leave to Intervene & Petition for Summary Or,In Alternative,For Hearing.Requests That NRC Adopt Condition of Approval of Transfer of License & License Condition Agreed to Beco & Entergy Nuclear Generation Co ML20205Q9231999-04-15015 April 1999 Forwards Proprietary & non-proprietary Addl Info in Support of Request to Transfer of Plant FOL & Matls License to Entergy Nuclear Generation Co.Proprietary Info Withheld,Per 10CFR2.790 ML20205P9631999-04-15015 April 1999 Provides Attachments a & B in Support of Request for Transfer of Plant Operating License & NRC Matl License from Beco to Entergy Nuclear Generation Co as Submitted in Ref 1. Info Provided in Response to Request at 990413 Meeting ML20205H9281999-04-0707 April 1999 Requests Withdrawal of Uwua Locals 369 & 387 Unions Joint Intervention in Listed Matter ML20205F3731999-04-0202 April 1999 Submits Addl Info Provided in Support of Request for Transfer of Pilgrim Nuclear Power Station Operating License & Matls License.State of Ma Order Authorizing Divestiture & Copy of Financial Arrangement Encl ML20204H3771999-03-26026 March 1999 Informs That Local 387,Utility Workers Union of America,AFL- Cio Voted to Approve New Contract with Entergy Nuclear Generation Co & Voted to Accept Boston Edison Divestiture Agreement ML20205D4231999-03-24024 March 1999 Forwards Decommissioning Funding Rept for Pilgrim Nuclear Power Station,In Accordance with 10CFR50.75(f)(1) 1999-09-09
[Table view] |
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O -
DOSITEC, INC.
TEL(617)875-8777 120 ALEXANDER STREET P.O. BOX 4744 FRAMINGHAM, M ASSACHUSETTS 01701 Mr. James E. Wigginton June 4, 1986 Senior Reactor Health Physicist US Nuclear Regulatory Commission Div. of Emergency Prep. & Engrg. Resp.
Office of Inspection & Enforcement Mail Stop EWW-507 Washington, DC 20555
Dear Mr. Wigginton:
Thank you very much for giving me the opportunity to discuss the Dositec Model DOS-502A Digital Alarm Dosimeter in your office two weeks ago.
Enclosed please find the three (3) sets of documents listed below which have been sent to all users of the Model DOS-502A:
Set 1 - These documents have been sent to the users in the nuclear power plants and utility companies:
a) cover letter indicating a detection range .,
up to 5 R/hr b) updated Specification Sheet (810 Rev. 5/86) c) Recommendations for Operation.
Set 2 - These documents have been sent to the users in the nuclear power plants and utility companies:
a) cover letter indicating a detection range I up to 5 R/hr b) updated Specification Sheet (860 Rev. 5/86) c) Recommendations for Operation.
Set 3 - These documents have been sent to some users of
-special-ordered DOS-502A in facilities other than
" nuclear power plants:
a) cover letter indicating a detection range up to 1 R/hr b) updated Specification Sheet (810 Rev. 5/86) c) Recommendations for Operation.
If you have further questions concerning this matter, please let me know.
Very truly yours l
80 9 h00 3 - - - M/ =
SamS.Hau,PM.D.
p President SSH/ba l
Enclosures
o .
DOSITEC, INC.
120 ALEXANDER STREET TEL. (617) 875-8777 P.O. BOX 4744 FRAMINGHAM, MASSACHUSETTS 01701 May, 1986 1
Reference:
Dositec Model DOS-502A Digital Alarm Dosimeter
Dear Customer:
It has come to my attention that some users of the Dositec Model DOS-502A Digital Alarm Dosimeters have used these dosimeters incorrectly.
The DOS-502A is designed to be linear up to 5 R/hr field with a 120% accuracy. They can be custom-made to be linear up to 50 R/hr field with an accuracy of t20% for some specific applications. It is not recommended to use this instrument in the field beyond the calibration range with an accuracy over 120%. .
Please note that the DOS-502A, just like any other dosimetry device, must be source-checked at the highest possiblo field in which the dosimeter will be used.
Enclosed please find an updated Specification Sheet (810 Rev. 5/86) and a " Recommendations for Operation" for DOS-502A. Please insert these two sheets in your Instruction Manual and notify all appropr'iate individuals in your organization to properly use the Dositec Model DOS-502A Digital Alarm Dosimeters.
Very truly yours,
=_
~
Sam S. Hsu, Ph.D.
President SSH/ba Enclosures 4
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6 MODEL DOS-502A DIGITAL ALARM DOSIMETER REV 810 5/86 SPECIFICATIONS Detector Type Solid State Detector - Cadmium Telluride (CdTe)
Radiation Detected X and Gamma Rays Energy Range 100 kev and up Energy Response 1254 100 kev - 1.2 MeV Range 0-9999 mR ,
Display 4 Digit LED Display Accuracy Unless otherwise specified on Data Sheet, linearity '
up to 5 R/hr with 1204 accuracy when calibrated with Cs137 Preset Alarm 4 Screwdriver Adjusted Digital Switches providing setting from 0000 to 9999 mR in increments of 1 mR Alarm Constant Audible Signal when integrated exposure reaches preset radiation level 75 db at 100 cm from the dosimeter Chirping Rate -
One Chirp per mR Battery 9-Volt Alkaline Battery Life Typically 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />.
5 Battery Test If pushbutton lights Battery Test LED Lamp, the battery will function adequately for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Shock Resistance Detector packaged in rubber l Packaging Anodized Aluminum case Weight (Approx.) 8 ounces Size (Approx.) 2.5 in. x 4 in. x 1 in.
i Clip Attached ALL SPECIFICATIONS ARE SUBJECT TO CHANGE WITHOUT NOTICE.
l l
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RECOMMENDATIONS FOR OPERATION 5/86 DOSITEC MODEL DOS-502A DIGITAL ALARM DOSIMETERS .
- 1. The instrument should be source-checked prior td us in a radiation field equal to the highest expected field conditions.
- 2. The instrument should not be used in a radiation field higher than that listed on the data sheet.
- 3. The instrument is not designed for use in any Nitrogen-16 (N-16) field. Please consult the factory if the instrument is to be used in the'N-16 field.
- 4. The Rubber Cover should be put on to avoid mechanical shock.
- 5. Try to minimize the mechanical tapping on the dosimeter.
- 6. If the instrument has been exposed to high heat, water, chemical, or dropped or subjected to high impact, or any other unusual .,
exposure, the instrument should be source-checked before use to make sure it responds properly.
- 7. If the instrument is found to be contaminated, it should be decontaminated and then source-checked prior to use to make sure the instrument responds properly.
I t
~~-
em M
l i
8 .
JOS : C, I NC.
120 ALEXANDER STREET TEL. (617) S75-877:
P.O. BOX 4744 FRAMINGHAM, MASSACHUSETTS 01701 May, 1986
Reference:
Dosite.c Mcdel DOS-502A Digital Alarm Dosimeter
Dear Customer:
It has come to my attention that some users of the Dositec Model DOS-502A Digital Alarm Dosimeters have used these dosimeters incorrectly.
The DOS-502A is designed to be linear up to 5 R/hr field with a 20% accuracy. They can be custom-made to be linear up to 50 R/hr field with an' accuracy of 20% for some specific applications. It is not recommended to use this instrument in the field beyond the calibration range with an accuracy over 120%.
Please note that the DOS-502A, just like any other dosimetry device, 's must be source-checked at the highest possible field in which the dosimeter will be used.
Enclosed please find an updated Specification Sheet (860 Rev. 5/86) and a " Recommendations for Operation" for DOS-502A. Please insert these two sheets in your Instruction Manual and notify all apprcpriate individuals in your organization to properly use the Dositec Model DOS-502A Digital Alarm. Dosimeters.
Very truly yours, I
l 2 Sam S. Hsu, Ph.D.
President l
SSH/ba l Enclosures l
l t
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1 4 SPECIFICATIONS MODEL DOS-502A DIGITAL ALARM DOSIMETER RE7 860 5/86 Detector Type Solid State Detector - Cadmium Telluride (CdTe)
Radiation Detected X and Gamma Rays Energy Range 100 kev and up Energy Response 1254 100 kev - 1.2 MeV Range. 0-9999 mR Display 4 Digit LED Display Accuracy Unless otherwise specified on data Sheet, linearity up to 5 R/hr with 120s accuracy when calibrated with Cal 37 i Preset Alarm 4 Screwdriver Adjusted Digital Switches providing setting from 0000 to 9999 mR in increments of 1 mR Alarm Constant Audible Signal when integrated exposure reaches preset radiation level; 75 db at 100 cm from the dosimeter Chirping. Rate One Chirp per mR Battery 9-Volt Alkaline Battery Life Typically 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> Battery Test If pushbutton lights Battery Test LED Lamp, the battery will function adequately for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> .
Shock Resistance Detector packaged in rubber Packaging Anodized Aluminum case Weight (Approx.) 8 ounces Size (Approx.) 2.5 in. x 4 in. x 1 in.
Clip Attached I
ALL SPECIFICATIONS. ARE SUBJECT TO CHANGE WITHOUT NOTICE.
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RECOMMENDATIONS FOR OPERATION 5/86 DOSITEC MODEL DOS-502A DIGITAL ALARM DOSIMETERS
- 1. The instrument should be source-checked prior to us in a radiation field equal to the highest expected field conditions.
- 2. The instrument should not be used in a radiation field higher than that listed on the data sheet.
- 3. The instrument is not designed for use in any Nitrogen-16 (N-16) field. Please consult the factory if the instrument is to be used in the'N-16 field.
- 4. The Rubber Cover should be put on to avoid mechanical shock.
- 5. Try to minimize the mechanical tapping on the dosimeter.
- 6. If the instrument has been exposed to high heat, water, chemica'1, or dropped or subjected to high impact, or any other unusual exposure, the instrument should be source-checked before use to make sure it responds properly. '.
- 7. If the instrument is found to be contaminated, it should be decontaminated and then source-checked prior to use to make sure the instrument responds properly.
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6 DOSITEC, INC.
120 ALEXANDER STREET TEL (617)875-8777 P.O. BOX 4744 FRAMINGH AM, MASSACHUSETTS 01701 May 1986
Reference:
Dositec Model DOS-502A Digital Alarm Dosimeter
Dear Customer:
It has come to my attention that some users of the Dositec Model DOS-502A Digital Alarm Dosimeters have used these dosimeters incorrectly.
The DOS-502A is designed to be linear up to 1 R/hr field with a 120% accuracy. They can be custom-made to be linear up to 50 R/hr field with an accuracy of 120% for some specific applications. It is not recommended to use this instrument in the field beyond the calibration range with an accuracy over 120%.
Please note that the DOS-502A, just like any other dosimetry device, must be source-checked at the highest possible field in which the dosimeter will be used.
Enclosed please find an updated Specification Sheet (810 Rev. 5/86) and a " Recommendations for Operation" for DOS-502A. Please insert these two sheets in your Instruction Manual and notify all appropriate individuals in your organization to properly use the Dositec Model DOS-502A Digital Alarm Dosimeters.
Very truly yours, Sam S. Hsu, Ph.D.
~~ President SSH/ba Enclosures O
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SPECIFICATIONS MODEL DOS-502A DIGITAL ALARM DOSIMETER REV 810 5/86 Detector Type Solid State Detector - Cadmium Telluride (CdTe)
Radiation Detected X and Gamma Rays Energy Range 100 kev and up Energy Response 1254 100 kev - 1.2 MeV Range 0-9999 mR Display 4 Digit LED Display ,
Accuracy Unless otherwise specified on Da'ta Sheet, linearity up to 5 R/hr with 120% accuracy when calibrated with .
Csl37 Preset Alarm 4 Screwdriver Adjusted Digital Switches providing setting from 0000 to 9999 mR in increments of 1 mR Alarm Constant Audible Signal when integrated exposure reaches preset radiation level 75 db at 100 cm from the dosimeter Chirping Rate One Chirp per mR Battery 9-Volt Alkaline Battery Life Typically 300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />.
Battery Test If pushbutton lights Battery Test LED Lamp, the 5
battery will function adequately for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Shock Resistance Detector packaged in rubber Packaging Anodized Aluminum case Weight (Approx.) 8 ounces Size (Approx.) 2.5 in. x 4 in. x 1 in.
Clip Attached 1
1 ALL SPECIFICATIONS ARE SUBJECT TO CHANGE WITNOUT NOTICE.
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RECOMMENDATIONS FOR OPERATION 5/86 DOSITEC MODEL DOS-502A DIGITAL ALARM DOSIMETERS .
- 1. The instrument should be source-checked prior to us in a radiation field equal to the highest expected field conditions.
- 2. The instrument should not be used in a radiation field higher than that listed on the data sheet.
- 3. The instrument is not designed for use in any Nitrogen-16 (N-16) field. Please consult the factory if the instrument is to be used in the'N-16 field.
- 4. The Rubber Cover should be put on to avoid mechanical shock.
- 5. Try to minimize the mechanical tapping on the dosimeter.
- 6. If the instrument has been exposed to high heat, water, chemical, or dropped or subjected to high impact, or any other unusual exposure, the instrument should be source-checked before use to make sure it responds properly. ,
- 7. If the instrument is found to be contaminated, it should be decontaminated and then source-checked prior to use to.make sure the instrument responds properly.
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