ML19296B113: Difference between revisions

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| number = ML19296B113
| number = ML19296B113
| issue date = 12/20/1979
| issue date = 12/20/1979
| title = Responds to NRC 791123 Ltr Re Violations Noted in IE Insp Repts 50-317/79-18 & 50-318/79-15.Corrective Actions: Evaluation Required by Plant Procedure Completed & Dosimetric Results Assigned to Individual Exposure Records
| title = Responds to NRC Re Violations Noted in IE Insp Repts 50-317/79-18 & 50-318/79-15.Corrective Actions: Evaluation Required by Plant Procedure Completed & Dosimetric Results Assigned to Individual Exposure Records
| author name = Lundvall A
| author name = Lundvall A
| author affiliation = BALTIMORE GAS & ELECTRIC CO.
| author affiliation = BALTIMORE GAS & ELECTRIC CO.
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| contact person =  
| contact person =  
| document report number = NUDOCS 8002200085
| document report number = NUDOCS 8002200085
| title reference date = 11-23-1979
| package number = ML19296B106
| package number = ML19296B106
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
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=Text=
=Text=
{{#Wiki_filter:e l                   .
{{#Wiki_filter:e l
B ALTIMORE G AS AND ELECTRIC COMPANY P.O. B O X 1475 B A LTIM O R E. M A R YL A N D 21203 ARTHUR C. LUN DVALL,dR.
B ALTIMORE G AS AND ELECTRIC COMPANY P.O. B O X 1475 B A LTIM O R E. M A R YL A N D 21203 ARTHUR C. LUN DVALL,dR.
V'C L Pet tiOt sef Sueev December 20, 1979 U.S. Nuclear Regulatory Commission                                     Docket Nos. 50-317 Region I                                                                             50-318 631 Park Avenue                                                         License Nos. OPR-53 King of Prussia, PA             19406                                               DPR-69 Attention: George H. Smith, Chief Fuel Facility and Materials Safety Branch Gentlemen:
V'C L Pet tiOt sef Sueev December 20, 1979 U.S. Nuclear Regulatory Commission Docket Nos.
50-317 Region I 50-318 631 Park Avenue License Nos.
OPR-53 King of Prussia, PA 19406 DPR-69 Attention: George H. Smith, Chief Fuel Facility and Materials Safety Branch Gentlemen:
This refers to your Inspection Report 50-317/79-18; 50-318/79-15, which transnitted an item of apparent noncomoliance with NRC requirements.
This refers to your Inspection Report 50-317/79-18; 50-318/79-15, which transnitted an item of apparent noncomoliance with NRC requirements.
Enclosure (1) to this letter is a written statement in reply to the item noted in your letter of November 23, 1979.                                 ,
Enclosure (1) to this letter is a written statement in reply to the item noted in your letter of November 23, 1979.
Should you have further questions regarding this reply, we will be pleased to discuss them with you.
Should you have further questions regarding this reply, we will be pleased to discuss them with you.
Very truly ours A. E. Lun vali ,
Very truly ours
_tunM Jr.
_tunM A. E. Lun vali, Jr.
Vice President-Supply AEL/ETR/gla Enclosure 80022 00 b
Vice President-Supply AEL/ETR/gla Enclosure 80022 00 b


ENCLOSURE (1)
ENCLOSURE (1)
REPLY TO APPENDIX A 0F flRC (IE: REGION I) LETTER OF NOVEMBER 23, 1979 The evaluation required by plant procedure RCP 3-310, " Personnel Dosimetry Quality Assurance" and noted in your report was completed as of November 3,1979, and dosimetric results have been assigned to the affected individ-uals' exposure record for the monitoring period involved. Additionally, the Radiation Safety and Chemistry Foreman has been reminded to ensure prompt submission of SRD vs. TLD Error Report to the Radiation Safety and Chemistry Engineer for resolution whenever errors greater than 25% are detected and cannot be explained and discrepancies corrected. It is con-sidered that we are now in full compliance with the requirements of Tech-nical Specification 6.11.}}
REPLY TO APPENDIX A 0F flRC (IE:
REGION I) LETTER OF NOVEMBER 23, 1979 The evaluation required by plant procedure RCP 3-310, " Personnel Dosimetry Quality Assurance" and noted in your report was completed as of November 3,1979, and dosimetric results have been assigned to the affected individ-uals' exposure record for the monitoring period involved. Additionally, the Radiation Safety and Chemistry Foreman has been reminded to ensure prompt submission of SRD vs. TLD Error Report to the Radiation Safety and Chemistry Engineer for resolution whenever errors greater than 25% are detected and cannot be explained and discrepancies corrected.
It is con-sidered that we are now in full compliance with the requirements of Tech-nical Specification 6.11.}}

Latest revision as of 07:46, 2 January 2025

Responds to NRC Re Violations Noted in IE Insp Repts 50-317/79-18 & 50-318/79-15.Corrective Actions: Evaluation Required by Plant Procedure Completed & Dosimetric Results Assigned to Individual Exposure Records
ML19296B113
Person / Time
Site: Calvert Cliffs  
Issue date: 12/20/1979
From: Lundvall A
BALTIMORE GAS & ELECTRIC CO.
To: Galen Smith
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19296B106 List:
References
NUDOCS 8002200085
Download: ML19296B113 (2)


Text

e l

B ALTIMORE G AS AND ELECTRIC COMPANY P.O. B O X 1475 B A LTIM O R E. M A R YL A N D 21203 ARTHUR C. LUN DVALL,dR.

V'C L Pet tiOt sef Sueev December 20, 1979 U.S. Nuclear Regulatory Commission Docket Nos.

50-317 Region I 50-318 631 Park Avenue License Nos.

OPR-53 King of Prussia, PA 19406 DPR-69 Attention: George H. Smith, Chief Fuel Facility and Materials Safety Branch Gentlemen:

This refers to your Inspection Report 50-317/79-18; 50-318/79-15, which transnitted an item of apparent noncomoliance with NRC requirements.

Enclosure (1) to this letter is a written statement in reply to the item noted in your letter of November 23, 1979.

Should you have further questions regarding this reply, we will be pleased to discuss them with you.

Very truly ours

_tunM A. E. Lun vali, Jr.

Vice President-Supply AEL/ETR/gla Enclosure 80022 00 b

ENCLOSURE (1)

REPLY TO APPENDIX A 0F flRC (IE:

REGION I) LETTER OF NOVEMBER 23, 1979 The evaluation required by plant procedure RCP 3-310, " Personnel Dosimetry Quality Assurance" and noted in your report was completed as of November 3,1979, and dosimetric results have been assigned to the affected individ-uals' exposure record for the monitoring period involved. Additionally, the Radiation Safety and Chemistry Foreman has been reminded to ensure prompt submission of SRD vs. TLD Error Report to the Radiation Safety and Chemistry Engineer for resolution whenever errors greater than 25% are detected and cannot be explained and discrepancies corrected.

It is con-sidered that we are now in full compliance with the requirements of Tech-nical Specification 6.11.