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| {{#Wiki_filter:AC CFLEMTED DISTRIBUTION | | {{#Wiki_filter:AC CFLEMTED DISTRIBUTION DEMONSTRATION SYPH'EM r,P REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ESSION NBR:8808300195 DOC.DATE: 88/08/15 NOTARIZED: |
| DEMONSTRATION | | NO ACIL:50-254 Quad-Cities Station, Unit 1, Commonwealth Edison Co.50-265 Quad-Cities Station, Unit 2, Commonwealth Edison Co.AUTH.NAME AUTHOR AFFILIATION BLISS,H.E. |
| SYPH'EM r,P REGULATORY | | Commonwealth Edison Co.RECIP.NAME RECIPIENT AFFXLIATION Region 3, Ofc of the Director DOCKET I'5000254 05000265 |
| INFORMATION | | |
| DISTRIBUTION | | ==SUBJECT:== |
| SYSTEM (RIDS)ESSION NBR:8808300195 | | Responds to NRC 880621 ltr re violations noted in Xnsp Repts 50-254/88-10 |
| DOC.DATE: 88/08/15 NOTARIZED: | |
| NO ACIL:50-254 | |
| Quad-Cities | |
| Station, Unit 1, Commonwealth | |
| Edison Co.50-265 Quad-Cities | |
| Station, Unit 2, Commonwealth | |
| Edison Co.AUTH.NAME AUTHOR AFFILIATION | |
| BLISS,H.E. | |
| Commonwealth | |
| Edison Co.RECIP.NAME | |
| RECIPIENT AFFXLIATION | |
| Region 3, Ofc of the Director DOCKET I'5000254 05000265 SUBJECT: Responds to NRC 880621 ltr re violations | |
| noted in Xnsp Repts 50-254/88-10 | |
| &50-265/88-11. | | &50-265/88-11. |
| DISTRIBUTION | | DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR 3 ENCL SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES I D RECIPIENT ID CODE/NAME PD3-2 PD INTERNAL: ACRS DEDRO NRR/DLPQ/PEB 11 NRR/DOEA DIR 11 NRR/DREP/RPB 10 NRR/PMAS/ILRB12 0 ERMAN, J R G FIL 02 3~ILE 01 EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME ROSS,T AEOD NRR MORISSEAU,D NRR/DLPQ/QAB 10 NRR/DREP/EPB 10 NRR/DRIS DIR 9A NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR DEPY-NRC PDR COPIES LTTR ENCL 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 A S A.D D.TOTAL NUMBER OF COPXES~REQUIRED: LTTR 25 ENCL 25 |
| CODE: IE01D COPIES RECEIVED:LTR | | |
| 3 ENCL SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice | | e Commonwealth Edison One First National Plaza, Chicago, illinois ress ep y to: ost ice ox Chicago, illinois 60690-0767 August 15, 1988 Mr.A.Bert Davis Regional Administrator U.ST Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 |
| of Violation Response NOTES I D RECIPIENT ID CODE/NAME PD3-2 PD INTERNAL: ACRS DEDRO NRR/DLPQ/PEB | | |
| 11 NRR/DOEA DIR 11 NRR/DREP/RPB | | ==Subject:== |
| 10 NRR/PMAS/ILRB12 | | Quad Cities Station Units 1 and 2"Response to IE Inspection Report Nos.50-254/88010 and 50-265/88011"-2 Reference (a): Letter from J.J.Harrison to Cordell Reed dated June 21, 1988. |
| 0 ERMAN, J R G FIL 02 3~ILE 01 EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME ROSS,T AEOD NRR MORISSEAU,D | | |
| NRR/DLPQ/QAB | | ==Dear Mr.Davis:== |
| 10 NRR/DREP/EPB | | This letter is in response to the inspection conducted by the Nuclear Regulatory Commission (NRC)Nondestructive Examination (NDE)Mobile Team of NRC's Region I Office on April 18 through April 29, 1988 of activities at Quad Cities Station Units 1 and 2.The referenced letter indicated that no violations of NRC requirements were identified in the course of the inspection. |
| 10 NRR/DRIS DIR 9A NUDOCS-ABSTRACT | | However, the letter did require Commonwealth Edison Company to provide a written response to Unresolved Item No.50-265/88011-04 (use of SNT-TC-lA 25'b rule).The Inspection Report did not establish a date by which a response was required.In a July 15, 1988 telephone conversation between Ms.I.M.Johnson of my staff and Mr.D.Danielson of your staff, it was mutually agreed that a response would be supplied by August 15, 1988.The Commonwealth Edison Company response to that Unresolved Item is provided in Attachment A.office.If you have any questions regarding this matter, please contact this H.E.liss Nuclear Licensing Manager lm Attachment A cc: NRC Resident Inspector-Quad Cities 5015K 8808300195 880815 PDR ADOCK 05000254 0 PDC |
| OGC/HDS1 RES/DSIR DEPY-NRC PDR COPIES LTTR ENCL 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 A S A.D D.TOTAL NUMBER OF COPXES~REQUIRED: LTTR 25 ENCL 25 | | |
|
| | V D A routine safety inspection of station activities at Quad Cities Station Unit l and 2 was conducted by the NRC NDE Mobile Team of the NRC's Region I office on April l8 through April 29, 1988.A part of the NRC inspection activities consisted of a selective examination of procedures and representative records.The NRC inspector, during his review of the Commonwealth Edison Company's Special Process Procedure Manual (SPPM), made an observation that the requirements in Commonwealth Edison Company's SPPM are not consistent with or do not meet the intent of the SNT-TC-lA. |
| e Commonwealth | | As a result, Mr.J.J.Harrison, NRC Region III, requested a written response to the item (No.50-265/88011/04) in a letter dated June 21, 1988 to Mr.C.Reed, Commonwealth Edison Company.The NRC Inspector's observation pertains to the so called"25%rule" in recommended Practice No.SNT-TC-lA, June 1980 edition, published by American Society for Non-Destructive Testing (ASNT)and the requirements in the procedure 1-1-0, Rev.24 of Commonwealth Edison's SPPM.The NRC inspector stated that the Commonwealth Edison Company procedure in the SPPM has improperly used the SNT-TC-1A 25%rule and that a possibility exists that Commonwealth Edison Company NDE personnel could fulfill certification requirements without satisfying the ASME requirements for minimum experience. |
| Edison One First National Plaza, Chicago, illinois ress ep y to: ost ice ox Chicago, illinois 60690-0767 August 15, 1988 Mr.A.Bert Davis Regional Administrator | | The conclusion was based on the review of the certification of one Commonwealth Edison Company individual who spent most of his worktime on Quality Control (QC)related activities not involving actual application of NDE.The NRC Inspector believed this individual may have been certified using the 25%rule.The individual referenced here is actually certified as a"Radiographic Interpreter", a special category of NDE personnel identified in Commonwealth Edison Company's SPPM.Commonwealth Edison believes that application of the 25%rule and qualification requirements of"RT Interpreters" are two separate issues and will be treated as such in our response which follows: Table 6.2.1A of SNT-TC-lA contains a statement,"credit for ezperience spend at least~~r~<of his worktime on~discipline for which experi-ence is being claimed." This provision has been incorporated into procedure 1-1-0, paragraph 6.1.1 of Commonwealth Edison Company's SPPM in which it is required that"an individual may gain field experience in~w or maxed NDE on~NDE method for which field experience is being claimed".This clearly shows that Commonwealth Edison Company's requirements in the SPPM are consistent with those in the SNT-TC-lA. |
| U.ST Nuclear Regulatory | | l A review was performed, at the NRC's request, of the qualification and certification of all present and past Commonwealth Edison Company personnel where the SNT-TC-1A 25%rule was used.The results of the review of the certification records showed that, of the seventeen NDE inspectors within the Commonwealth Edison system, six work in System Materials Analysis Department (SMAD)which is a group dedicated full time to performing NDE.The remaining eleven are assigned to various generating stations.Of those eleven, eight are qualified and experienced individuals who were hired into Edison from outside NDE Companies. |
| Commission | | It is our understanding that the question of adequancy of training and experience pertains to neither the SMAD NDE group nor with respect to experienced inspectors recruited from outside testing companies. |
| Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Subject: Quad Cities Station Units 1 and 2"Response to IE Inspection | | The question was raised in regard to those Commonwealth Edison Company qualified individuals who are not full time NDE personnel. |
| Report Nos.50-254/88010 | | Our records show only three inspectors who fall into this category.Two are certified to perform only penetrant testing (PT)and one is certified to perform PT and MT (magnetic particle testing).If the provision in the SPPM and SNT-TC-1A for simultaneous qualification using the 25%rule was to be used, it would have been in the case of this one individual who is certified in both PT and MT.The review of his certification showed that the 25'b rule'He had logged one month work experience as defined in the SPPM for each discipline gypsy.before he was certified as a Level 1 inspector. |
| and 50-265/88011"-2 Reference (a): Letter from J.J.Harrison to Cordell Reed dated June 21, 1988.Dear Mr.Davis: This letter is in response to the inspection | | He also worked an additional two months as a Level 1 PT inspector before becoming a Level II PT inspector, and an additional 3 months as a Level 1 MT inspector before being certified as a Level II MT inspector. |
| conducted by the Nuclear Regulatory | | Even though Commonwealth Edison Company's SPPM provides for use of the 25 percent rule as stated above, a review of personnel Edison Company qualified inspectors. |
| Commission (NRC)Nondestructive | | A special subcategory of NDE personnel certified as"Radiographic Interpreter" is identified in the SPPM.This special"RT Interpreter" category was created to develop individuals who would have sufficient knowledge of RT method to review radiographic work done by outside testing contractors. |
| Examination (NDE)Mobile Team of NRC's Region I Office on April 18 through April 29, 1988 of activities | | As specified in Commonwealth Edison Company's"written practice" (SPPM), an"RT Interpreter's" duties are limited to reviewing the radiographic work performed by the others to ensure that radiographs are of good quality and that proper codes and standards have been followed and that defects have been properly identified and evaluated. |
| at Quad Cities Station Units 1 and 2.The referenced | | These RT Interpreters are neither trained to perform actual radiography nor are they allowed to specify techniqes or test parameters. |
| letter indicated that no violations | | We believe that with these limitations, the subcategory of RT Interpreter, is acceptable and meets the intent of the code because:It is permissible according to the SNT-TC-1A recommended practice to create subcategories of NDE personnel depending upon the employer's special needs provided the duties, responsibilities, qualifiction requirements, and any limitations on their certification are described in the employers w |
| of NRC requirements | | |
| were identified | | b.Paragraph IWA-2300.a.3 of ASME Section XI, Winter 80 Addenda, states that,"........training for NDE personnel who perform'f a non-destructive examination method that contains more than one operation, or who perform non-destructive examination of limited scope, may be less than that recommended in Table 6'.1A of SNT-TC-lA We believe that reading and reviewing radiographs is only one aspect of multiple tasks involved in radiographic testing.Our RT Interpreters receive extensive classroom training and they spend a minimum of three months reviewing r'ediographs under the supervision of an experienced and certified RT person.Finally, they take a practical film interpretation test to demonstrate their ability to Commonwealth Edison Company's Chief Level III before being certified as Level II RT Interpreter. |
| in the course of the inspection. | | These Interpreters played a valuable role in overviewing quality of a voluminous amount of RT work performed by the contractors during Commonwealth nuclear plant construction program.Commonwealth Edison's program for qualification and certification of the personnel involved in NDE related activities was designed to provide various degrees of NDE expertise to fulfill our needs.In addition to SMAD's NDE group, all nuclear plants need some personnel in their QC, QA, ISI and Tech Staff groups to be familiar with some, if not all, aspects of NDE disciplines in order to control the overall quality of the NDE work done at their respective plants.Our program as defined in the SPPM provides rules for the training and certification of those"limited" NDE personnel as well as defining the rules for qualification of actual"Examiners or Testers" which are, we believe, in strict accordance with the ASME Code.The extensive review of personnel records showed that 25%rule was not applied in certification of any of the NDE examiners. |
| However, the letter did require Commonwealth | | The"RT Interpreters" subcategory of NDE personnel is permissive by the ASME Code and meets the intent of SNT-TC-lA recommended practice.5015K}} |
| Edison Company to provide a written response to Unresolved | |
| Item No.50-265/88011-04 (use of SNT-TC-lA 25'b rule).The Inspection | |
| Report did not establish a date by which a response was required.In a July 15, 1988 telephone conversation | |
| between Ms.I.M.Johnson of my staff and Mr.D.Danielson of your staff, it was mutually agreed that a response would be supplied by August 15, 1988.The Commonwealth | |
| Edison Company response to that Unresolved | |
| Item is provided in Attachment | |
| A.office.If you have any questions regarding this matter, please contact this H.E.liss Nuclear Licensing Manager lm Attachment | |
| A cc: NRC Resident Inspector-Quad Cities 5015K 8808300195 | |
| 880815 PDR ADOCK 05000254 0 PDC | |
|
| |
| V D A routine safety inspection | |
| of station activities | |
| at Quad Cities Station Unit l and 2 was conducted by the NRC NDE Mobile Team of the NRC's Region I office on April l8 through April 29, 1988.A part of the NRC inspection | |
| activities | |
| consisted of a selective examination | |
| of procedures | |
| and representative | |
| records.The NRC inspector, during his review of the Commonwealth | |
| Edison Company's Special Process Procedure Manual (SPPM), made an observation | |
| that the requirements | |
| in Commonwealth | |
| Edison Company's SPPM are not consistent | |
| with or do not meet the intent of the SNT-TC-lA. | |
| As a result, Mr.J.J.Harrison, NRC Region III, requested a written response to the item (No.50-265/88011/04) | |
| in a letter dated June 21, 1988 to Mr.C.Reed, Commonwealth | |
| Edison Company.The NRC Inspector's | |
| observation | |
| pertains to the so called"25%rule" in recommended | |
| Practice No.SNT-TC-lA, June 1980 edition, published by American Society for Non-Destructive | |
| Testing (ASNT)and the requirements | |
| in the procedure 1-1-0, Rev.24 of Commonwealth | |
| Edison's SPPM.The NRC inspector stated that the Commonwealth | |
| Edison Company procedure in the SPPM has improperly | |
| used the SNT-TC-1A 25%rule and that a possibility | |
| exists that Commonwealth | |
| Edison Company NDE personnel could fulfill certification | |
| requirements | |
| without satisfying | |
| the ASME requirements | |
| for minimum experience. | |
| The conclusion | |
| was based on the review of the certification | |
| of one Commonwealth | |
| Edison Company individual | |
| who spent most of his worktime on Quality Control (QC)related activities | |
| not involving actual application | |
| of NDE.The NRC Inspector believed this individual | |
| may have been certified using the 25%rule.The individual | |
| referenced | |
| here is actually certified as a"Radiographic | |
| Interpreter", a special category of NDE personnel identified | |
| in Commonwealth | |
| Edison Company's SPPM.Commonwealth | |
| Edison believes that application | |
| of the 25%rule and qualification | |
| requirements | |
| of"RT Interpreters" are two separate issues and will be treated as such in our response which follows: Table 6.2.1A of SNT-TC-lA contains a statement,"credit for ezperience | |
| spend at least~~r~<of his worktime on~discipline | |
| for which experi-ence is being claimed." This provision has been incorporated | |
| into procedure 1-1-0, paragraph 6.1.1 of Commonwealth | |
| Edison Company's SPPM in which it is required that"an individual | |
| may gain field experience | |
| in~w or maxed NDE on~NDE method for which field experience | |
| is being claimed".This clearly shows that Commonwealth | |
| Edison Company's requirements | |
| in the SPPM are consistent | |
| with those in the SNT-TC-lA. | |
| l | |
| A review was performed, at the NRC's request, of the qualification | |
| and certification | |
| of all present and past Commonwealth | |
| Edison Company personnel where the SNT-TC-1A 25%rule was used.The results of the review of the certification | |
| records showed that, of the seventeen NDE inspectors | |
| within the Commonwealth | |
| Edison system, six work in System Materials Analysis Department (SMAD)which is a group dedicated full time to performing | |
| NDE.The remaining eleven are assigned to various generating | |
| stations.Of those eleven, eight are qualified and experienced | |
| individuals | |
| who were hired into Edison from outside NDE Companies. | |
| It is our understanding | |
| that the question of adequancy of training and experience | |
| pertains to neither the SMAD NDE group nor with respect to experienced | |
| inspectors | |
| recruited from outside testing companies. | |
| The question was raised in regard to those Commonwealth | |
| Edison Company qualified individuals | |
| who are not full time NDE personnel. | |
| Our records show only three inspectors | |
| who fall into this category.Two are certified to perform only penetrant testing (PT)and one is certified to perform PT and MT (magnetic particle testing).If the provision in the SPPM and SNT-TC-1A for simultaneous | |
| qualification | |
| using the 25%rule was to be used, it would have been in the case of this one individual | |
| who is certified in both PT and MT.The review of his certification | |
| showed that the 25'b rule'He had logged one month work experience | |
| as defined in the SPPM for each discipline | |
| gypsy.before he was certified as a Level 1 inspector. | |
| He also worked an additional | |
| two months as a Level 1 PT inspector before becoming a Level II PT inspector, and an additional | |
| 3 months as a Level 1 MT inspector before being certified as a Level II MT inspector. | |
| Even though Commonwealth | |
| Edison Company's SPPM provides for use of the 25 percent rule as stated above, a review of personnel Edison Company qualified inspectors. | |
| A special subcategory | |
| of NDE personnel certified as"Radiographic | |
| Interpreter" is identified | |
| in the SPPM.This special"RT Interpreter" category was created to develop individuals | |
| who would have sufficient | |
| knowledge of RT method to review radiographic | |
| work done by outside testing contractors. | |
| As specified in Commonwealth | |
| Edison Company's"written practice" (SPPM), an"RT Interpreter's" duties are limited to reviewing the radiographic | |
| work performed by the others to ensure that radiographs | |
| are of good quality and that proper codes and standards have been followed and that defects have been properly identified | |
| and evaluated. | |
| These RT Interpreters | |
| are neither trained to perform actual radiography | |
| nor are they allowed to specify techniqes or test parameters. | |
| We believe that with these limitations, the subcategory | |
| of RT Interpreter, is acceptable | |
| and meets the intent of the code because:It is permissible | |
| according to the SNT-TC-1A recommended | |
| practice to create subcategories | |
| of NDE personnel depending upon the employer's | |
| special needs provided the duties, responsibilities, qualifiction | |
| requirements, and any limitations | |
| on their certification | |
| are described in the employers w | |
|
| |
| b.Paragraph IWA-2300.a.3 | |
| of ASME Section XI, Winter 80 Addenda, states that,"........training | |
| for NDE personnel who perform'f a non-destructive | |
| examination | |
| method that contains more than one operation, or who perform non-destructive | |
| examination | |
| of limited scope, may be less than that recommended | |
| in Table 6'.1A of SNT-TC-lA We believe that reading and reviewing radiographs | |
| is only one aspect of multiple tasks involved in radiographic | |
| testing.Our RT Interpreters | |
| receive extensive classroom training and they spend a minimum of three months reviewing r'ediographs | |
| under the supervision | |
| of an experienced | |
| and certified RT person.Finally, they take a practical film interpretation | |
| test to demonstrate | |
| their ability to Commonwealth | |
| Edison Company's Chief Level III before being certified as Level II RT Interpreter. | |
| These Interpreters | |
| played a valuable role in overviewing | |
| quality of a voluminous | |
| amount of RT work performed by the contractors | |
| during Commonwealth | |
| nuclear plant construction | |
| program.Commonwealth | |
| Edison's program for qualification | |
| and certification | |
| of the personnel involved in NDE related activities | |
| was designed to provide various degrees of NDE expertise to fulfill our needs.In addition to SMAD's NDE group, all nuclear plants need some personnel in their QC, QA, ISI and Tech Staff groups to be familiar with some, if not all, aspects of NDE disciplines | |
| in order to control the overall quality of the NDE work done at their respective | |
| plants.Our program as defined in the SPPM provides rules for the training and certification | |
| of those"limited" NDE personnel as well as defining the rules for qualification | |
| of actual"Examiners | |
| or Testers" which are, we believe, in strict accordance | |
| with the ASME Code.The extensive review of personnel records showed that 25%rule was not applied in certification | |
| of any of the NDE examiners. | |
| The"RT Interpreters" subcategory | |
| of NDE personnel is permissive | |
| by the ASME Code and meets the intent of SNT-TC-lA recommended | |
| practice.5015K | |
| }} | |
|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARSVP-99-181, Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 9906301999-10-20020 October 1999 Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 990630 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217K7011999-10-13013 October 1999 Provides Response to Questions Related to Request for License Amend,Per 10CFR50.90, Credit for Containment Overpressure. Supporting Calculations Encl 05000254/LER-1999-004, Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action1999-10-12012 October 1999 Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action ML20217F6321999-10-0707 October 1999 Forwards Insp Repts 50-254/99-01 & 50-265/99-01 on 990721- 0908.No Violations 05000254/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee1999-10-0707 October 1999 Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee ML20212K9421999-10-0505 October 1999 Informs That NRC Accepts 990513 Inservice Inspection Relief Request CR-31 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr SVP-99-189, Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage1999-09-22022 September 1999 Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage ML20212J0451999-09-21021 September 1999 Forwards Safety Evaluation of Licensee USI A-46 Program at Quad Cities Nuclear Power Station,Units 1 & 2,established in Response to GL 87-02 Through 10CFR50.54(f) Ltr ML20212D8231999-09-20020 September 1999 Informs That Effectieve 991101,NRC Region III Will Be Conducting Safety System Design & Performance Capability Pilot Insp at Quad Cities Nuclear Power Station.Insp Will Be Performed IAW NRC Pilot Insp Procedure 71111-21 ML20212C6961999-09-15015 September 1999 Forwards Insp Repts 50-254/99-17 & 50-265/99-17 on 990823- 0827.No Violations Noted SVP-99-190, Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys1999-09-13013 September 1999 Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys ML20211Q7961999-09-0909 September 1999 Forwards Correction to Administrative Error on Page 8 of NRC Insp Repts 50-254/99-16 & 50-265/99-16,transmitted by Ltr, ML20217H5661999-09-0909 September 1999 Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl ML20211Q6511999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Quad Cities Operator License Applicants During Wk of 000327.Validation of Exam Will Occur at Station During Wk of 000306 ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20211F8251999-08-25025 August 1999 Forwards Insp Repts 50-254/99-15 & 50-265/99-15 on 990816-20.No Violations Noted.Insp Evaluated Effectiveness of Maint Rule Program & Review Periodic Evaluation Specifically Required for 10CFR50.65 ML20211B8691999-08-20020 August 1999 Forwards Insp Repts 50-254/99-10,50-265/99-10,50-454/99-09, 50-455/99-09,50-456/99-10 & 50-457/99-10 on 990628-0721. Action Plans Developed to Address Configuration Control Weaknesses Not Totally Effective as Listed ML20211D1491999-08-19019 August 1999 Forwards Insp Repts 50-254/99-16 & 50-265/99-16 on 990719-22.Staff Identified Major Discrepancy Re Accuracy of Data Submitted to NRC for Protected Area Security Equipment Performance ML20211C7601999-08-19019 August 1999 Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program ML20210R7451999-08-13013 August 1999 Forwards Insp Repts 50-254/99-11 & 50-265/99-11 on 990601-0720.NRC Identified Several Issues Which Were Categorized as Being of Low Risk Significance.Two Issues Involved NCVs of Regulatory Requirements SVP-99-147, Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl1999-08-13013 August 1999 Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl SVP-99-170, Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety1999-08-13013 August 1999 Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML20210T9941999-08-13013 August 1999 Forwards Insp Repts 50-254/99-12 & 50-265/99-12 on 990628-0716.Violations Noted SVP-99-154, Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated1999-08-13013 August 1999 Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated ML20210R9541999-08-10010 August 1999 Informs That During 990804 Telcon Between J Bartlet & M Bielby,Arrangements Were Made for NRC to Insp License Operator Requalification Program at Plant.Insp Planned for Wks of 991018 & 25 ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M5461999-08-0606 August 1999 Discusses 990804 Telcon Between J Bartlet & M Bielby,Where Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant.Insp Planned for Wks of 991018 & 25 ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210L8371999-08-0202 August 1999 Forwards SE Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety Related Motor-Operated Valves ML20210M4691999-07-30030 July 1999 Forwards Insp Repts 50-254/99-14 & 50-265/99-14 on 990713-15.One NCV Was Identified & Discussed in Encl Insp ML20210H4661999-07-29029 July 1999 Forwards Insp Repts 50-254/99-13 & 50-265/99-13 on 990628-0702.No Violations Noted.Insp Consisted of Selective Examination of Procedures & Representative Records, Observations of Activities & Interviews with Personnel 05000254/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed1999-07-29029 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed SVP-99-151, Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 21999-07-23023 July 1999 Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 2 SVP-99-150, Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept1999-07-23023 July 1999 Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept SVP-99-146, Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 9906251999-07-21021 July 1999 Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 990625 ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes SVP-99-139, Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage1999-06-30030 June 1999 Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage ML20209B2081999-06-29029 June 1999 Discusses Closure of Response to RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rvid,Version 2 Issued as Result of Review of Responses.Info Should Be Reviewed & Comments Submitted by 990901 05000265/LER-1999-002, Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action1999-06-25025 June 1999 Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action SVP-99-122, Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 9906011999-06-25025 June 1999 Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 990601 SVP-99-066, Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested1999-06-25025 June 1999 Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested SVP-99-103, Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period1999-06-25025 June 1999 Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period ML20196F7921999-06-24024 June 1999 Forwards Meeting Summary,Nrc Meeting Handout & Licensee Handout from 990608 Meeting ML20196E7131999-06-23023 June 1999 Forwards Insp Repts 50-254/99-09 & 50-265/99-09 on 990421-0531.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20196E4821999-06-21021 June 1999 Discusses 990617 Meeting by Region III Senior Reactor Analysts (SRA) in Cordova,Il to Meet with PRA Staff to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARSVP-99-181, Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 9906301999-10-20020 October 1999 Forwards Biennial Update to Quad Cities Ufsar,Iaw 10CFR50.71(e).Update Includes Changes to Facility & Procedures & Are Current Through 990630 ML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20217K7011999-10-13013 October 1999 Provides Response to Questions Related to Request for License Amend,Per 10CFR50.90, Credit for Containment Overpressure. Supporting Calculations Encl 05000254/LER-1999-004, Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action1999-10-12012 October 1999 Forwards LER 99-004-00,IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Is Committed to Listed Action 05000254/LER-1999-003, Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee1999-10-0707 October 1999 Forwards LER 99-003-00 IAW 10CFR73(a)(2)(v)(A).Commitment Made by Util,Listed.Any Other Actions Described in LER Represent Intended or Planned Actions by Licensee ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr SVP-99-189, Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage1999-09-22022 September 1999 Confirms Completion of Actions Identified During Review of NRC Safety Evaluation of Boiling Water Reactor Owners Group Rept, Utility Resolution Guidance of ECCS Suction Strainer Blockage SVP-99-190, Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys1999-09-13013 September 1999 Clarifies Statement Contained in NRC Insp Repts 50-254/99-12 & 50-265/99-12,dtd 990813,paragraph 4OA1.3B, Observation & Findings, Re Sys Mod to DG Air Start Sys ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) SVP-99-154, Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated1999-08-13013 August 1999 Notifies NRC That M Price,License SOP-31389,is No Longer Required to Maintain Operator License.Price Was Removed from Licensed Duty on 990729 & Comm Ed Requests License Be Terminated SVP-99-170, Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety1999-08-13013 August 1999 Forwards Relief Requests CR-25,CR-26,CR-27,CR-28,PR-11, PR-12 & PR-13,on Basis That Compliance with Specified Requirements Would Result in Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality & Safety SVP-99-147, Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl1999-08-13013 August 1999 Notifies of Change to Bases of TS to Licenses DPR-29 & DPR- DPR-30.Change to TS Section 3/4.9 Provides Clarity & Consistency with Sys Design Description in Ufsar,Sections 8.3.2.1 & 8.3.2.2.TS Bases Page,Encl ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed 05000254/LER-1999-002, Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed1999-07-29029 July 1999 Forwards LER 99-002-01,IAW 10CFR50.73(a)(2)(iv).Rev Includes Cause Codes & Energy Industry Identification Sys Identifiers Which Were Erroneously Omitted in Original Ler.Commitments Listed SVP-99-150, Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept1999-07-23023 July 1999 Forwards Responses to 990520 RAI Re Annual 10CFR50.46 Rept SVP-99-151, Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 21999-07-23023 July 1999 Responds to NRC 990701 Telcon RAI Re Licensee Amend Request Re Use of Containment Overpressure to Support NPSH Available for ECCS at Quad Cities Nuclear Power Station,Units 1 & 2 SVP-99-146, Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 9906251999-07-21021 July 1999 Informs of Termination of License SOP-31132-1,for G Green, as Required by 10CFR50.74(b).Individual Was Removed from License Duty on 990625 ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes SVP-99-139, Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage1999-06-30030 June 1999 Forwards Revised Action 2 & Associated TS Bases Changes, Describing Specific Alternate Method for Determining Drywell Floor Drain Sump Leakage SVP-99-103, Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period1999-06-25025 June 1999 Informs NRC of Results of Subject Evaluation as Committed to in .Evaluation Consisted of Analytically Demonstrating That Cfu Factor for Rv Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period SVP-99-122, Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 9906011999-06-25025 June 1999 Forwards Regulatory Commitment Change Summary Rept, Containing Summary Info from 980601 Through 990601 05000265/LER-1999-002, Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action1999-06-25025 June 1999 Forwards LER 99-002-00 for Quad Cities Nuclear Power Station IAW Requirements of 10CFR50.73(a)(2)(i)(B).Util Commits to One Listed Action SVP-99-066, Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested1999-06-25025 June 1999 Informs That J Reed,License SOP-31034-1,was Removed from License Duty in 990618.Termination of License Is Requested SVP-99-125, Forwards Technical Info Re ECCS Suction Strainers at Quad Cities Nuclear Power Station Units 1 & 2,to Support Review of 990129 Lar.Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept, Encl1999-06-15015 June 1999 Forwards Technical Info Re ECCS Suction Strainers at Quad Cities Nuclear Power Station Units 1 & 2,to Support Review of 990129 Lar.Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept, Encl ML20195E3491999-06-0707 June 1999 Withdraws Util Requesting License Change for Plant Security Plan Rev.Licensee Will re-evaluate Situation & May Request Approval of Change in Future ML20207G1451999-06-0707 June 1999 Forwards Rev 45 to Comed Quad Cities Nuclear Power Station Security Plan.Rev Includes Changes Listed.Security Plan Is Withheld from Public Disclosure Per 10CFR73.21 ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs SVP-99-105, Informs NRC of Rev to Schedule for Completing Setpoint/ Uncertainty Calculations & Procedure Changes,Originally Planned for Completion on 9905291999-05-20020 May 1999 Informs NRC of Rev to Schedule for Completing Setpoint/ Uncertainty Calculations & Procedure Changes,Originally Planned for Completion on 990529 ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB SVP-99-111, Informs NRC of Current Status of Actions on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-05-17017 May 1999 Informs NRC of Current Status of Actions on Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions SVP-99-098, Fulfills Thirty Day & Annual Reporting Requirements of 10CFR50.46 for Plant.Eccs Evaluation Change Rept Transmitted in Entirety,Fulfilling Thirty Day & Annual Reporting Requirements Specified in 10CFR50.46(a)(3)(i)1999-05-17017 May 1999 Fulfills Thirty Day & Annual Reporting Requirements of 10CFR50.46 for Plant.Eccs Evaluation Change Rept Transmitted in Entirety,Fulfilling Thirty Day & Annual Reporting Requirements Specified in 10CFR50.46(a)(3)(i) SVP-99-099, Requests Relief from Requirements of 10CFR50.55a(g) Re Submittal of Relief Requests for Those Welds for Which Examinations of Greater than 90% of Weld Vol Was Not Acheived During 2nd ISI Program Interval1999-05-13013 May 1999 Requests Relief from Requirements of 10CFR50.55a(g) Re Submittal of Relief Requests for Those Welds for Which Examinations of Greater than 90% of Weld Vol Was Not Acheived During 2nd ISI Program Interval SVP-99-096, Provides Suppl Response to Violations Noted in Insp Repts 50-254/98-20 & 50-265/98-23.Corrective Actions:Listed Multidiscipline Team Will Perform self-assessment IAW Station Program for self-assessments in May 19991999-05-12012 May 1999 Provides Suppl Response to Violations Noted in Insp Repts 50-254/98-20 & 50-265/98-23.Corrective Actions:Listed Multidiscipline Team Will Perform self-assessment IAW Station Program for self-assessments in May 1999 05000254/LER-1999-001, Forwards LER 99-001-00 for Quad Cities Nuclear Power Station.Licensee Shall Rept Any Operation or Condition Prohibited by Plant Tech Specs.Util Committing to Listed Actions1999-05-12012 May 1999 Forwards LER 99-001-00 for Quad Cities Nuclear Power Station.Licensee Shall Rept Any Operation or Condition Prohibited by Plant Tech Specs.Util Committing to Listed Actions ML20206F5381999-04-30030 April 1999 Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape SVP-99-108, Forwards Quad Cities 1998 Radiological Environ Operating Rept, IAW Plant TS 6.9.A.3.Rept Contains Results of Radiological Environ & Meteorological Monitoring Programs. Radioactive Effluent Release Rept Was Submitted 9903301999-04-30030 April 1999 Forwards Quad Cities 1998 Radiological Environ Operating Rept, IAW Plant TS 6.9.A.3.Rept Contains Results of Radiological Environ & Meteorological Monitoring Programs. Radioactive Effluent Release Rept Was Submitted 990330 SVP-99-036, Forwards Reg Guide 1.16 Rept Number of Personnel-Rem by Work & Job Function for 1998. Associated Collective Deep Dose Equivalent Reported According to Work & Job Functions1999-04-29029 April 1999 Forwards Reg Guide 1.16 Rept Number of Personnel-Rem by Work & Job Function for 1998. Associated Collective Deep Dose Equivalent Reported According to Work & Job Functions SVP-99-088, Informs That Util Is Withdrawing IST Relief Rquests RV-02B & RV-03B1999-04-29029 April 1999 Informs That Util Is Withdrawing IST Relief Rquests RV-02B & RV-03B ML20205T1141999-04-22022 April 1999 Provides Comments from Technical Review of Draft Info Notice Re Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station,Unit 2,ANO,Unit 2 & JAFNPP ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 SVP-99-065, Requests That License SOP-31516,for Jf Graham,Be Terminated, Per 10CFR50.74(b).Individual Was Removed from License Duty on 990319 & No Longer Requires Operator License1999-04-14014 April 1999 Requests That License SOP-31516,for Jf Graham,Be Terminated, Per 10CFR50.74(b).Individual Was Removed from License Duty on 990319 & No Longer Requires Operator License SVP-99-058, Submits Plant Specific ECCS Evaluation Changes,Per Annual Reporting Requirements of 10CFR50.46.Attachments Include Current Assessment Data Re PCT Info Limiting LOCA Evaluations1999-04-14014 April 1999 Submits Plant Specific ECCS Evaluation Changes,Per Annual Reporting Requirements of 10CFR50.46.Attachments Include Current Assessment Data Re PCT Info Limiting LOCA Evaluations SVP-99-063, Responds to NRC Re Violations Noted in Insp Repts 50-254/98-21 & 50-265/98-21.Corrective Actions:Revised Site ISI Procedure Qcap 0410-06, ISI Plan Implementation for Third Ten Year Insp Interval1999-04-0909 April 1999 Responds to NRC Re Violations Noted in Insp Repts 50-254/98-21 & 50-265/98-21.Corrective Actions:Revised Site ISI Procedure Qcap 0410-06, ISI Plan Implementation for Third Ten Year Insp Interval JAFP-99-0129, Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick1999-04-0909 April 1999 Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick SVP-99-057, Notifies of Change to Bases for TSs Section 3/4.5, ECCS, Re1999-04-0505 April 1999 Notifies of Change to Bases for TSs Section 3/4.5, ECCS, Re ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) SVP-99-062, Informs NRC of Rev to Schedule for Analytically Demonstrating That Cumulative Usage Factor for Reactor Vessel Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period1999-03-31031 March 1999 Informs NRC of Rev to Schedule for Analytically Demonstrating That Cumulative Usage Factor for Reactor Vessel Head Closure Studs Will Remain Below 1.0 for Remainder of Current License Period 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML20065D0511990-09-17017 September 1990 Forwards Objectives & Scope of 901205 Emergency Plan Exercise ML20064A7091990-09-14014 September 1990 Forwards Endorsement 133 to Nelia Policy NF-187 & Endorsement 116 to Maelu Policy MF-54 ML20059F4891990-09-0404 September 1990 Forwards Listing of Changes,Tests & Experiments Completed During Month of Aug 1990 for Plant ML20059B9721990-08-28028 August 1990 Forwards Reactor Head & Upper Shell Insp Plan,Per 900419 Meeting.Insp Plan Does Not Encompass Uppermost shell-to- Shell Weld Due to Technological Limitations ML20059F0311990-08-27027 August 1990 Provides Schedule for Completion of Installation of Mods to Plants Reactor Water Level Instrumentation,Per Generic Ltr 84-23.Penetrations Will Be Installed During Outage 13 for Dresden & During Outage 12 for Quad-Cities ML20059E9531990-08-27027 August 1990 Forwards Summary of Fabrication History for Upper Reactor Vessel,Per 900419 Technical Meeting.Summary Indicates That Fabrication Mismatches,Considered to Be Significant for Development of Insp Plan,Identified at head-to-flange Weld ML20059C7201990-08-23023 August 1990 Forwards Effluent & Waste Disposal Semiannual Rept,Jan-June 1990 Gaseous Effluents-Summation of All Releases & Rev 8 to Quad-Cities Station Process Control Program for Processing of Radioactive Wet Waste ML20058P3481990-08-0909 August 1990 Forwards Summary of Fuel Performance,End of Cycle 10,May 1990. No Leakage or Fuel Failure Noted ML20058M8221990-08-0707 August 1990 Forwards Response to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions ML20058M8041990-08-0606 August 1990 Advises That W/Completion of Operator Training Program,Plant SPDS Meets Requirements Delineated in NUREG-0737,Suppl 1 ML20058M8591990-08-0606 August 1990 Forwards Rept of Metallurgical Exam That Revealed No Evidence of Defects,Porosity or Slag in Weld Overlay. Rept Responds to IGSCC Insp Performed on Facility IGSCC Susceptible Piping ML20058M4101990-08-0101 August 1990 Forwards Listing of Changes,Tests & Experiments Completed During Month of Jul 1990 for Plant ML20058M8291990-07-31031 July 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issue Resolved W/Imposition of Requirements of Corrective Actions. Status of Implementation of Generic Safety Issues Encl ML20055J1631990-07-26026 July 1990 Forwards Reactor Containment Bldg Integrated Leak Rate Test Quad-Cities Nuclear Power Station Unit 2,900427-28, & Related Apps Describing Type a Test,Per 10CFR50,App J, Section V.B.1.Next Test Scheduled for Fall 1991 ML20055H7631990-07-25025 July 1990 Forwards Financial Info Re Decommissioning of Plants ML20055G6331990-07-18018 July 1990 Responds to Generic Ltr 89-06 Re SPDS to Meet Requirements of Suppl 1 to NUREG-0737.SPDS Lesson Plan Incorporated Into Initial License Class Training Program ML17202L2861990-07-0202 July 1990 Forwards Dresden II Upper Vessel Contract Variation Review, La Salle II Upper Vessel Fabrication Summary & Quad-Cities II Upper Vessel Fabrication Summary. ML20055D4741990-06-29029 June 1990 Forwards Annual FSAR Update for Quad-Cities Station ML20055D4341990-06-29029 June 1990 Forwards Comm Ed Rept on Evaluation of Cracking in Quad- Cities Unit 2 Reactor Head, Per Commitment Made at 900419 Meeting W/Nrr.Rept Concludes That Cracks Caused by Interdendritic Stress Corrosion Cracking Mechanism ML20055C8551990-06-15015 June 1990 Forwards Special Neutron Attenuation Test for High Density Spent Fuel Racks (Wet), Final Rept.Rept Provides Results of Neutron Radioassay Measurement Program Conducted During Fall,1989 Refueling Outage ML20043D7661990-06-0404 June 1990 Responds to J Lieberman 900501 Ltr Re Rl Dickherber. Confidence in Dickherber Performance in Future for Nonlicensed Duties Can Be Based Upon Demonstrated Record of Good Past Performance ML20043D7691990-06-0404 June 1990 Responds to 900501 Ltr Re Work Hours for Dickherber.During Outage,Dickherber Worked Extended Hours Traditionally Associated W/Refueling Activities ML20043G4251990-06-0202 June 1990 Forwards Listing of Changes,Tests & Experiments Completed During May 1990 ML20043D3201990-06-0101 June 1990 Forwards Rev 24 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043B6681990-05-22022 May 1990 Forwards Proposed Changes to SER Re Hot Shutdown Repairs in Event of Fire,Per 10CFR50,App R Section Iii.G Covering Spurious Operations & High Impedance Faults & Electrical Isolation Deficiency ML20043A4681990-05-10010 May 1990 Forwards Proposed Changes to 880721 SER Re App R Section Iii.G Exemption for Fire Zones 1.1.1.1S & 1.1.1.2,southern & Northern Torus Level in Unit 1 Reactor Bldg Column & Unit 1 Reactor Bldg Elevations 623 Ft & 647 Ft ML20042H0011990-05-0303 May 1990 Forwards Listing of Changes,Tests, & Experiments Completed During Apr 1990 ML20042G3501990-05-0202 May 1990 Responds to NRC 900404 Ltr Re Violations Noted in Insp Repts 50-254/90-02 & 50-265/90-02.Corrective Actions:Continuous Fire Watch Initiated & Training Conducted on Procedure Rev ML20042F1181990-05-0101 May 1990 Advises of Listed Value for Secondary Containment,Per NRC Request for Addl Info Re LER 50-254/87-025.Value Based on Info Contained in Plant FSAR ML20042F0691990-05-0101 May 1990 Responds to Generic Ltr 83-28,Item 4.5.3 Re Reactor Protection Sys on-line Functional Test Intervals.Endorses Two BWR Owners Group Topical Repts NEDC-30844 & NEDC-30851P Generic Evaluations ML20042F1221990-05-0101 May 1990 Forwards Preliminary Rept of IGSCC Insp Results.Flaw Indication Detected in Weld Overlay Matl of Weld 02J-S3 & Removed by Boat Sample & Std Weld Overlay Thickness Restored.Final Rept Will Be Forwarded within 30 Days ML20042E4491990-04-11011 April 1990 Forwards Request for Rev to Previous NRC Exemption Approval on 860625 Re Combustible Load Values ML20042F0351990-03-23023 March 1990 Forwards Part 3 of 1989 Operating Rept.W/O Rept ML19330D5161990-03-14014 March 1990 Advises That Revs to Inservice Testing Program & Implementation Procedures Will Be Completed by 900629,per Generic Ltr 89-04 ML20012C0721990-03-0808 March 1990 Comments on SALP Board Repts 50-254/89-01 & 50-265/89-01 for Oct 1988 to Nov 1989.Util Appreciates NRC Recognition of Overall Improvements in Areas of Operation & Emergency Preparedness & Good Performance in Area of Security ML20012B5921990-03-0202 March 1990 Forwards Listing of Changes,Tests & Experiments Computed During Month of Feb 1990 for Plant ML20006F3361990-02-0808 February 1990 Responds to NRC Ltr 900110 Ltr Re Violations Noted in Insp Repts 50-254/89-25 & 50-265/89-25.Corrective Actions:Safety Evaluations Submitted Via 900116 Ltr & Table of Content Will Be Completed for 1989 FSAR Update to Be Submitted by 900630 ML20012A9551990-02-0808 February 1990 Responds to Violations Noted in Insp Repts 50-254/89-26 & 50-265/89-26.Corrective Action:Procedure Qis 47-1 Revised to Include Requirement That Equalizing Valve Be Open During Isolation of Transmitter ML20011E7131990-02-0606 February 1990 Forwards Reactor Containment Bldg Integrated Leak Rate Test,Quad Cities Nuclear Power Station,Unit 1,891114-15. Next Type a Test Scheduled for Fall 1990 ML20006E1721990-02-0202 February 1990 Forwards Listing of Changes,Tests & Experiments Completed During Jan 1990,including Items Completed in 1989. Interlocks Installed on Refuel Bridge Fuel Handling Machine to Prevent Raising Hoist While Hoist Loaded ML20006C5071990-01-30030 January 1990 Identifies Schedular Change for Completion of Corrective Actions Associated W/Human Engineering Deficiencies 159,187 & 489 Re Escutcheon Plates for Control Switches Which Need Replacement.Plates Will Be Replaced During Outages ML20006C7401990-01-22022 January 1990 Advises of Receipt of Accreditation Renewal by INPO in Sept 1989 for Operator Requalification Training Program,Per Generic Ltr 87-07 Requirements & Informs That Programs Developed Using Systematic Approach to Training ML19354E8591990-01-16016 January 1990 Responds to NRC 891128 Ltr Re Violations Noted in Insp Repts 50-254/89-17 & 50-265/89-17.Corrective Actions:Procedure NSWP-E-01, Electrical Cable Installation Insp, Will Be Revised to Enhance Human Factor Aspect ML19354D8131990-01-11011 January 1990 Forwards Corrected App C to Monthly Operating Rept for Dec 1989 for Quad Cities Units 1 & 2 ML20005F6441990-01-0303 January 1990 Forwards Listing of Changes,Tests & Experiments Completed During Dec 1989.Summary of Safety Evaluations Being Reported in Compliance w/10CFR50.59 & 10CFR50.71(e) Also Encl ML20005E1691989-12-22022 December 1989 Forwards Rev 22 to Security Plan,Reflecting Administrative Changes in Mgt Structure at Facility.Rev Withheld (Ref 10CFR73.21) ML20043A5741989-12-21021 December 1989 Responds to NRC 891124 Ltr Re Violations Noted in Insp Repts 50-254/89-23 & 50-265/89-23.Corrective Actions:Compressed Gas Cylinder Bottles Secured W/Chain & Fire Marshall Will Increase Tours of Plant Re Transient Combustible Matl ML20005E1211989-12-18018 December 1989 Forwards Final Rept of Fall 1989 IGSCC Insp Plan,Discussing Items Such as Overlay Repair on Weld 02G-S4,mechanical Stress Improvement & Piping Mods ML19332G3401989-12-0808 December 1989 Forwards Response to Generic Ltr 89-21, Implementation Status of USI Requirements. Actions to Resolve USI A-9 Re ATWS Will Be Completed in June 1990 & USI A-42 Re Pipe Cracks in BWRs Will Be Completed in Dec 1990 ML19332F9091989-12-0101 December 1989 Forwards Listing of Changes,Tests & Experiments Completed During Nov 1989 1990-09-04
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AC CFLEMTED DISTRIBUTION DEMONSTRATION SYPH'EM r,P REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ESSION NBR:8808300195 DOC.DATE: 88/08/15 NOTARIZED:
NO ACIL:50-254 Quad-Cities Station, Unit 1, Commonwealth Edison Co.50-265 Quad-Cities Station, Unit 2, Commonwealth Edison Co.AUTH.NAME AUTHOR AFFILIATION BLISS,H.E.
Commonwealth Edison Co.RECIP.NAME RECIPIENT AFFXLIATION Region 3, Ofc of the Director DOCKET I'5000254 05000265
SUBJECT:
Responds to NRC 880621 ltr re violations noted in Xnsp Repts 50-254/88-10
&50-265/88-11.
DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR 3 ENCL SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES I D RECIPIENT ID CODE/NAME PD3-2 PD INTERNAL: ACRS DEDRO NRR/DLPQ/PEB 11 NRR/DOEA DIR 11 NRR/DREP/RPB 10 NRR/PMAS/ILRB12 0 ERMAN, J R G FIL 02 3~ILE 01 EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME ROSS,T AEOD NRR MORISSEAU,D NRR/DLPQ/QAB 10 NRR/DREP/EPB 10 NRR/DRIS DIR 9A NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR DEPY-NRC PDR COPIES LTTR ENCL 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 A S A.D D.TOTAL NUMBER OF COPXES~REQUIRED: LTTR 25 ENCL 25
e Commonwealth Edison One First National Plaza, Chicago, illinois ress ep y to: ost ice ox Chicago, illinois 60690-0767 August 15, 1988 Mr.A.Bert Davis Regional Administrator U.ST Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Quad Cities Station Units 1 and 2"Response to IE Inspection Report Nos.50-254/88010 and 50-265/88011"-2 Reference (a): Letter from J.J.Harrison to Cordell Reed dated June 21, 1988.
Dear Mr.Davis:
This letter is in response to the inspection conducted by the Nuclear Regulatory Commission (NRC)Nondestructive Examination (NDE)Mobile Team of NRC's Region I Office on April 18 through April 29, 1988 of activities at Quad Cities Station Units 1 and 2.The referenced letter indicated that no violations of NRC requirements were identified in the course of the inspection.
However, the letter did require Commonwealth Edison Company to provide a written response to Unresolved Item No.50-265/88011-04 (use of SNT-TC-lA 25'b rule).The Inspection Report did not establish a date by which a response was required.In a July 15, 1988 telephone conversation between Ms.I.M.Johnson of my staff and Mr.D.Danielson of your staff, it was mutually agreed that a response would be supplied by August 15, 1988.The Commonwealth Edison Company response to that Unresolved Item is provided in Attachment A.office.If you have any questions regarding this matter, please contact this H.E.liss Nuclear Licensing Manager lm Attachment A cc: NRC Resident Inspector-Quad Cities 5015K 8808300195 880815 PDR ADOCK 05000254 0 PDC
V D A routine safety inspection of station activities at Quad Cities Station Unit l and 2 was conducted by the NRC NDE Mobile Team of the NRC's Region I office on April l8 through April 29, 1988.A part of the NRC inspection activities consisted of a selective examination of procedures and representative records.The NRC inspector, during his review of the Commonwealth Edison Company's Special Process Procedure Manual (SPPM), made an observation that the requirements in Commonwealth Edison Company's SPPM are not consistent with or do not meet the intent of the SNT-TC-lA.
As a result, Mr.J.J.Harrison, NRC Region III, requested a written response to the item (No.50-265/88011/04) in a letter dated June 21, 1988 to Mr.C.Reed, Commonwealth Edison Company.The NRC Inspector's observation pertains to the so called"25%rule" in recommended Practice No.SNT-TC-lA, June 1980 edition, published by American Society for Non-Destructive Testing (ASNT)and the requirements in the procedure 1-1-0, Rev.24 of Commonwealth Edison's SPPM.The NRC inspector stated that the Commonwealth Edison Company procedure in the SPPM has improperly used the SNT-TC-1A 25%rule and that a possibility exists that Commonwealth Edison Company NDE personnel could fulfill certification requirements without satisfying the ASME requirements for minimum experience.
The conclusion was based on the review of the certification of one Commonwealth Edison Company individual who spent most of his worktime on Quality Control (QC)related activities not involving actual application of NDE.The NRC Inspector believed this individual may have been certified using the 25%rule.The individual referenced here is actually certified as a"Radiographic Interpreter", a special category of NDE personnel identified in Commonwealth Edison Company's SPPM.Commonwealth Edison believes that application of the 25%rule and qualification requirements of"RT Interpreters" are two separate issues and will be treated as such in our response which follows: Table 6.2.1A of SNT-TC-lA contains a statement,"credit for ezperience spend at least~~r~<of his worktime on~discipline for which experi-ence is being claimed." This provision has been incorporated into procedure 1-1-0, paragraph 6.1.1 of Commonwealth Edison Company's SPPM in which it is required that"an individual may gain field experience in~w or maxed NDE on~NDE method for which field experience is being claimed".This clearly shows that Commonwealth Edison Company's requirements in the SPPM are consistent with those in the SNT-TC-lA.
l A review was performed, at the NRC's request, of the qualification and certification of all present and past Commonwealth Edison Company personnel where the SNT-TC-1A 25%rule was used.The results of the review of the certification records showed that, of the seventeen NDE inspectors within the Commonwealth Edison system, six work in System Materials Analysis Department (SMAD)which is a group dedicated full time to performing NDE.The remaining eleven are assigned to various generating stations.Of those eleven, eight are qualified and experienced individuals who were hired into Edison from outside NDE Companies.
It is our understanding that the question of adequancy of training and experience pertains to neither the SMAD NDE group nor with respect to experienced inspectors recruited from outside testing companies.
The question was raised in regard to those Commonwealth Edison Company qualified individuals who are not full time NDE personnel.
Our records show only three inspectors who fall into this category.Two are certified to perform only penetrant testing (PT)and one is certified to perform PT and MT (magnetic particle testing).If the provision in the SPPM and SNT-TC-1A for simultaneous qualification using the 25%rule was to be used, it would have been in the case of this one individual who is certified in both PT and MT.The review of his certification showed that the 25'b rule'He had logged one month work experience as defined in the SPPM for each discipline gypsy.before he was certified as a Level 1 inspector.
He also worked an additional two months as a Level 1 PT inspector before becoming a Level II PT inspector, and an additional 3 months as a Level 1 MT inspector before being certified as a Level II MT inspector.
Even though Commonwealth Edison Company's SPPM provides for use of the 25 percent rule as stated above, a review of personnel Edison Company qualified inspectors.
A special subcategory of NDE personnel certified as"Radiographic Interpreter" is identified in the SPPM.This special"RT Interpreter" category was created to develop individuals who would have sufficient knowledge of RT method to review radiographic work done by outside testing contractors.
As specified in Commonwealth Edison Company's"written practice" (SPPM), an"RT Interpreter's" duties are limited to reviewing the radiographic work performed by the others to ensure that radiographs are of good quality and that proper codes and standards have been followed and that defects have been properly identified and evaluated.
These RT Interpreters are neither trained to perform actual radiography nor are they allowed to specify techniqes or test parameters.
We believe that with these limitations, the subcategory of RT Interpreter, is acceptable and meets the intent of the code because:It is permissible according to the SNT-TC-1A recommended practice to create subcategories of NDE personnel depending upon the employer's special needs provided the duties, responsibilities, qualifiction requirements, and any limitations on their certification are described in the employers w
b.Paragraph IWA-2300.a.3 of ASME Section XI, Winter 80 Addenda, states that,"........training for NDE personnel who perform'f a non-destructive examination method that contains more than one operation, or who perform non-destructive examination of limited scope, may be less than that recommended in Table 6'.1A of SNT-TC-lA We believe that reading and reviewing radiographs is only one aspect of multiple tasks involved in radiographic testing.Our RT Interpreters receive extensive classroom training and they spend a minimum of three months reviewing r'ediographs under the supervision of an experienced and certified RT person.Finally, they take a practical film interpretation test to demonstrate their ability to Commonwealth Edison Company's Chief Level III before being certified as Level II RT Interpreter.
These Interpreters played a valuable role in overviewing quality of a voluminous amount of RT work performed by the contractors during Commonwealth nuclear plant construction program.Commonwealth Edison's program for qualification and certification of the personnel involved in NDE related activities was designed to provide various degrees of NDE expertise to fulfill our needs.In addition to SMAD's NDE group, all nuclear plants need some personnel in their QC, QA, ISI and Tech Staff groups to be familiar with some, if not all, aspects of NDE disciplines in order to control the overall quality of the NDE work done at their respective plants.Our program as defined in the SPPM provides rules for the training and certification of those"limited" NDE personnel as well as defining the rules for qualification of actual"Examiners or Testers" which are, we believe, in strict accordance with the ASME Code.The extensive review of personnel records showed that 25%rule was not applied in certification of any of the NDE examiners.
The"RT Interpreters" subcategory of NDE personnel is permissive by the ASME Code and meets the intent of SNT-TC-lA recommended practice.5015K