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| {{#Wiki_filter:}} | | {{#Wiki_filter:Quad Cities Nuclear Power Station ~. |
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| | O' Commonwealth Edison 22710.06 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 |
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| | RAR-88-27 May 31, 1988 Director of Nuclear Reactor Regulations U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C. 20555 Enclosed please find a listing of those changes, tests, and experiments completed during the month of May, 1988, for Quad-Cities Station Units 1 and 2, DPR-29 and DPR-30. A summary of the safety evaluation is being reported in compliance with 10CFR50.59. |
| | Thirty-nine copies are provided for your use. |
| | Respectfully, COMMONWEALTH EDISON COMPANY Q'IAD-CITIES NUCLEAR POWER STATION k-R.A. Robey Services Superintendent AAR/vk Enclosure cc: 1. Johnson T. Watts /J. Galligan I |
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| | Modification M-4-1-1/2-83-1 Description This modification was implemented to provide _a crosstie pipe (1/2-10124B-16") |
| | connecting the 1B and 2B RHR service water lines, between the RHRS service water |
| | - pumps and flow elements. The crosstie pipe ties into the Unit 1. Loop B RHRS service water line (1-1005B-16") in the Unit 1 RCIC room, goes'thru the wall, and ties into the Unit 2 Loop B RHR service water line (2-1005B-16"). A 16" manual. gate' valve (1/2-1099-1B) isolates crosstie usage. |
| | This modification was initiated per AIR 4-82-27. |
| | Evaluation This modification is required to enable the use of the Unit 2 RHR system in the event of failure of the underground portion of RHR line 2-1005-16". The installation of the system does not change any previous FSAR evaluations. |
| | The installation of the new piping and valve system will not affect the availability of the RHR system. The crosstie line is being installed to allow continued operation of both' units in the event Loop 'B' fails. |
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| | , Modification M-4-1/2-83-27 f-Description. |
| | .The purpose of this modification is to reduce the post-accident radiation-3g |
| | * . doses to the. Standby Gag Treatment System (SBGTS) control panels for both' Units |
| | ~ 1 and'2.to below 5 x 10 rads. This.was accomplished by the installation of Scismic Category I shield walls between the SGTS trains and their respective di control cabinets to isolate the' cabinets from the harsh environment caused by the filters on the trains. These walls have been installed to comply with I.E. Bulletin 79-01B. |
| | Evaluation The installation of these walls are classified as Seismic Category I-so the' operation of existing equipment will not be_ effected in anyway. These walls have increased the margin of safety and aid in assuring proper equipment operation through control of the environment. |
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| | Modification M-4-1/2-86-19 Description This modification modified four supports on line 2-1005-16". During the project close-out of the addition of the loop 'B' RHR Service Water Crosstie (M-4-1/2-83-1), it was determined that drawings for support modifications on the existing RHR Service Water lines were not issued, and consequently the modifications were not installed. An operability assessment was performed, which proved the system was functional even without those modifications. |
| | The lines, however, did not meet FSAR requirements. This modification of four supports brings the existing lines within FSAR requirements. |
| | Licensee Event Report 86-024 documents the RHR Service Water piping exceeds Code Stress Allowables. |
| | Evaluation By modifying and adding supports, the system will be upgraded to meet FSAR design requirements. No changes are being performed to any system, therefore, no new scenario is postulated. The modification and additional supports actually assure that the hargin of Safety, as defined in the Technical Specifications, is upheld. |
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| | Modification M-4-1-84-39 |
| | ' Description The modification is to install three-hour rated fire' dampers in the HVAC duct penetrations:and remove the old sections of duct work and install new sections of duct work.- The reason for the modification is to meet the require-ments'of 10CFR50 Appendix R. |
| | Evaluation This modification provides protection from a fire spreading from one fire zone to another. The margin of safety is maintained. The modification has no mechanical or electrical interfaces or interaction with existing safety related systems or equipment. |
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| | Modification M-4-1-85-37 Description This m'odification was to . install a new RHR pump motor for the IB RHR pump. |
| | - This was initiated due to the inoperability_of a badly damaged IB RHR pump motor and no exact motor replacement could be found. |
| | - A'similar' environmentally qualified motor was obtained from Northern States . |
| | Power Monticello station and was adapted to the station's motor stand and coupling |
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| | Evaluation , |
| | The motor is identical in horsepower, kV rating, and rpm. Thus, it~ met the basic requirements for the IB RHR pump. All flows remained the same and met the Tech Spec requirements. The motor met or exceeded all of the environ-mental qualification requirements. |
| | No safety concerns have been created due to this modification. |
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| | Modification M-4-1-85-43 Description Modification M-4-1-85-43 replaced the entire Unit One 250 volt battery. |
| | and its racks. ..This modification was initiated due to concerns regarding the |
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| | integrity of the existing plant type batteries. Later concerns regarding'the seismic adequacy of the tacks hastened the modification installation. A new |
| | -250 volt battery, a GNB type NCX 1500, was installed along.with new seismically. |
| | qualified battery racks. |
| | Evaluation The new battery is sized to provide sufficient DC power for the worst case accident load profile.' The racks are designed to be seismically qualified. |
| | Thus, plant safety is not decreased by this modification. |
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| | " Modification M-4-1-85-53 Description The existing main steam line' radiation monitors (GE model #194X629), |
| | 1-1705-2A-thru D, were obsolete. They were removed from their locations on |
| | ., the 901-10 panel and. replaced with modern, technically superior monitors (GE model #304A3700G002). The'new monitors are exact functional. replacements and are~ plug compatible units. |
| | Evaluation The new main steam line radiation monitors are providing the same function as-the'old monitors. The trip points have remained the same. The safety aspects have not changed. |
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| | Modification M-4-1-85-58 Description The modification'is to increase the concentrations of steam'in-the off-gas |
| | - system where existing off-gas concentrations are. combustible. This modification to the off-gas system will eliminate off-gas fires. The modification is to eliminate the flammable. region of the off-gas system. |
| | Evaluation This modification will reduce the probability of off-gas fires without effecting equipment important to safety. The modification does not interface with any. safety related equipment and the design does not change the design intent of-the technical ~ specification requirements of the off-gas system. |
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| | Modification M-4-1-86-20 Description This modification will provide three hour fire rated penetration seals in cable penetration openings under 4KV Switchgears 13-1 and 14-1. It will l also provide a one hour rated fire wrap over the bus duct from the 1/2 Diesel Generator to 4KV Switchgear 13-1 for that portion which runs in the Turbine Building. These items are required to meet our Appendix R Safe Shutdown Analysis. |
| | This modification will also provide three hour fire rated penetration seals in the cable penetration openings under the MG-Sets. |
| | Evaluation The installation of the penetrati>n seals and the wrapping of the duct will prevent the propagation of a fire from one fire area to another. |
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| | Modification M-4-1-86-22 |
| | "'1 Description' |
| | -This modification replaced two electro-mechanical timers with one solid state agastat time delay relay per division on the Core Spray system. The time delay relay is used to sequentially load the Core Spray pump to the bus in the event of a core spray initiation and loss of off-site power. |
| | The electro-mechanical timers were less reliable and crratic in time. |
| | They were required ~to return to an "AT HOME PCSITION" to be ready for the next start. 'On occasions, they would not return to the "AT HOME POSITION". |
| | Because the new agastat relay was more reliable'and did not require an |
| | '"Kr HOME POSITION" alarm, the two electro-mechanical timers were replaced with one solid state relay. |
| | Evaluation The new time. delay relay performs the sat.e function as the two electro-mechanical timers except for the "AT HOME POSITION" annunciator. By removing the-redundancy of two electro-mechanical timers and replacing them with one solid state time delay relay, the possibility of creating a malfunction is not increased'because of the reliability of the new time delay ralays. |
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| | 7 Modification M-4-2-82-16 Description The pressure suppression chamber wide. range level monitoring system was installed as a result of AIR 4-82-6 to provide the main control room with level indication outside the normal ~ range of operation. The system is comprised of two independant channels and uses differential pressure between the top and the bottom of the pressure suppression chamber to sense the level. Each channel has a gauge readout on the 902-3 panel and a strip chart recorder-on the 902-2 panel. Pressure indication is provided alongside level readout on all four indicators. |
| | Evaluation The existing pressure suppression chamber level monitoring system will remain intact and will be used during normal operation. In the event that suppression chamber level rises / falls outside the range of the existing level monitoring system, the wide range level monitoring system will provide the necessary information. Since this system only supplies additional information, the margin of safety is increased. |
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| | Modification M-4-2-82-17 |
| | ~ Description-The modification is to install a hydrogen monitoring system. The existing system does not. fully. satisfy NRC requirements listed in the NUREG 0737. The existing in-containment system will be replaced with an out-of-containment 1 hydrogen monitoring system.- |
| | Evaluation The modifications upgrade is to meet new NRC standards. The function and basic operation of the system is not being changed. The margin of safety is not reduced. g l |
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| | : D- Modification M-4-2-83-30 |
| | ' Description The modification-is to install alternate power feeds and control for Diesel Generator auxiliaries, alternate feeds to the, Division II IUIR room cooler, reroute RHR. pump power feeds, and install additional smoke detectors, , |
| | wet pipe sprinkler ~ system-and local control isolation capability for the RCIC steam supply isolation valve. The modification is necessary for the station to comply with 10CFR50 Appendix R. |
| | Evaluation The modifications are to reduce the possible consequences of a fire in various zones, this reduces the probability of an accident or malfunction of equipment. It also increases the reliability of the on-site power system, RHR system and fire protection system. The margin of safety is increased. |
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| | l Modification M-4-2-83-45 |
| | ' Description |
| | 'This modification was initiated to replace the old Unit One 1255 volt battery which was nearing the end of its service life. A new 125 volt battery, aLGNB type NCT 1344, was. installed along with new seismically qualified battery racks. |
| | Evaluation The new 125 volt battery has a greater ampere-hour capacity which enhances r plant safety. The battery rack is designed to be seismically qualified and therefore does not change the margin of plant safety. |
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| | Modification M-4-2-84-39 Descriptiqn The modification is to install three-hour rated fire dampers in the HVAC duct penetrations and remove the old sections of duct work and install new sections of duct work. The reason for the modification is to meet the require-ments of 10CFR50 Appendix'R. |
| | Evaluation This modification provides protection from a fire spreading from one fire zone to another. The margin of safety is maintained. The modification has no mechanical or electrical interfaces or interaction with existing safety related systems or equipment |
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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
[Table view] |
Text
Quad Cities Nuclear Power Station ~.
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O' Commonwealth Edison 22710.06 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241
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RAR-88-27 May 31, 1988 Director of Nuclear Reactor Regulations U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C. 20555 Enclosed please find a listing of those changes, tests, and experiments completed during the month of May, 1988, for Quad-Cities Station Units 1 and 2, DPR-29 and DPR-30. A summary of the safety evaluation is being reported in compliance with 10CFR50.59.
Thirty-nine copies are provided for your use.
Respectfully, COMMONWEALTH EDISON COMPANY Q'IAD-CITIES NUCLEAR POWER STATION k-R.A. Robey Services Superintendent AAR/vk Enclosure cc: 1. Johnson T. Watts /J. Galligan I
I e80620o233 DR 080531 N ADOCK0500g a
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Modification M-4-1-1/2-83-1 Description This modification was implemented to provide _a crosstie pipe (1/2-10124B-16")
connecting the 1B and 2B RHR service water lines, between the RHRS service water
- pumps and flow elements. The crosstie pipe ties into the Unit 1. Loop B RHRS service water line (1-1005B-16") in the Unit 1 RCIC room, goes'thru the wall, and ties into the Unit 2 Loop B RHR service water line (2-1005B-16"). A 16" manual. gate' valve (1/2-1099-1B) isolates crosstie usage.
This modification was initiated per AIR 4-82-27.
Evaluation This modification is required to enable the use of the Unit 2 RHR system in the event of failure of the underground portion of RHR line 2-1005-16". The installation of the system does not change any previous FSAR evaluations.
The installation of the new piping and valve system will not affect the availability of the RHR system. The crosstie line is being installed to allow continued operation of both' units in the event Loop 'B' fails.
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, Modification M-4-1/2-83-27 f-Description.
.The purpose of this modification is to reduce the post-accident radiation-3g
- . doses to the. Standby Gag Treatment System (SBGTS) control panels for both' Units
~ 1 and'2.to below 5 x 10 rads. This.was accomplished by the installation of Scismic Category I shield walls between the SGTS trains and their respective di control cabinets to isolate the' cabinets from the harsh environment caused by the filters on the trains. These walls have been installed to comply with I.E. Bulletin 79-01B.
Evaluation The installation of these walls are classified as Seismic Category I-so the' operation of existing equipment will not be_ effected in anyway. These walls have increased the margin of safety and aid in assuring proper equipment operation through control of the environment.
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Modification M-4-1/2-86-19 Description This modification modified four supports on line 2-1005-16". During the project close-out of the addition of the loop 'B' RHR Service Water Crosstie (M-4-1/2-83-1), it was determined that drawings for support modifications on the existing RHR Service Water lines were not issued, and consequently the modifications were not installed. An operability assessment was performed, which proved the system was functional even without those modifications.
The lines, however, did not meet FSAR requirements. This modification of four supports brings the existing lines within FSAR requirements.
Licensee Event Report 86-024 documents the RHR Service Water piping exceeds Code Stress Allowables.
Evaluation By modifying and adding supports, the system will be upgraded to meet FSAR design requirements. No changes are being performed to any system, therefore, no new scenario is postulated. The modification and additional supports actually assure that the hargin of Safety, as defined in the Technical Specifications, is upheld.
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Modification M-4-1-84-39
' Description The modification is to install three-hour rated fire' dampers in the HVAC duct penetrations:and remove the old sections of duct work and install new sections of duct work.- The reason for the modification is to meet the require-ments'of 10CFR50 Appendix R.
Evaluation This modification provides protection from a fire spreading from one fire zone to another. The margin of safety is maintained. The modification has no mechanical or electrical interfaces or interaction with existing safety related systems or equipment.
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Modification M-4-1-85-37 Description This m'odification was to . install a new RHR pump motor for the IB RHR pump.
- This was initiated due to the inoperability_of a badly damaged IB RHR pump motor and no exact motor replacement could be found.
- A'similar' environmentally qualified motor was obtained from Northern States .
Power Monticello station and was adapted to the station's motor stand and coupling
. pieces.
Evaluation ,
The motor is identical in horsepower, kV rating, and rpm. Thus, it~ met the basic requirements for the IB RHR pump. All flows remained the same and met the Tech Spec requirements. The motor met or exceeded all of the environ-mental qualification requirements.
No safety concerns have been created due to this modification.
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Modification M-4-1-85-43 Description Modification M-4-1-85-43 replaced the entire Unit One 250 volt battery.
and its racks. ..This modification was initiated due to concerns regarding the
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integrity of the existing plant type batteries. Later concerns regarding'the seismic adequacy of the tacks hastened the modification installation. A new
-250 volt battery, a GNB type NCX 1500, was installed along.with new seismically.
qualified battery racks.
Evaluation The new battery is sized to provide sufficient DC power for the worst case accident load profile.' The racks are designed to be seismically qualified.
Thus, plant safety is not decreased by this modification.
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" Modification M-4-1-85-53 Description The existing main steam line' radiation monitors (GE model #194X629),
1-1705-2A-thru D, were obsolete. They were removed from their locations on
., the 901-10 panel and. replaced with modern, technically superior monitors (GE model #304A3700G002). The'new monitors are exact functional. replacements and are~ plug compatible units.
Evaluation The new main steam line radiation monitors are providing the same function as-the'old monitors. The trip points have remained the same. The safety aspects have not changed.
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Modification M-4-1-85-58 Description The modification'is to increase the concentrations of steam'in-the off-gas
- system where existing off-gas concentrations are. combustible. This modification to the off-gas system will eliminate off-gas fires. The modification is to eliminate the flammable. region of the off-gas system.
Evaluation This modification will reduce the probability of off-gas fires without effecting equipment important to safety. The modification does not interface with any. safety related equipment and the design does not change the design intent of-the technical ~ specification requirements of the off-gas system.
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Modification M-4-1-86-20 Description This modification will provide three hour fire rated penetration seals in cable penetration openings under 4KV Switchgears 13-1 and 14-1. It will l also provide a one hour rated fire wrap over the bus duct from the 1/2 Diesel Generator to 4KV Switchgear 13-1 for that portion which runs in the Turbine Building. These items are required to meet our Appendix R Safe Shutdown Analysis.
This modification will also provide three hour fire rated penetration seals in the cable penetration openings under the MG-Sets.
Evaluation The installation of the penetrati>n seals and the wrapping of the duct will prevent the propagation of a fire from one fire area to another.
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Modification M-4-1-86-22
"'1 Description'
-This modification replaced two electro-mechanical timers with one solid state agastat time delay relay per division on the Core Spray system. The time delay relay is used to sequentially load the Core Spray pump to the bus in the event of a core spray initiation and loss of off-site power.
The electro-mechanical timers were less reliable and crratic in time.
They were required ~to return to an "AT HOME PCSITION" to be ready for the next start. 'On occasions, they would not return to the "AT HOME POSITION".
Because the new agastat relay was more reliable'and did not require an
'"Kr HOME POSITION" alarm, the two electro-mechanical timers were replaced with one solid state relay.
Evaluation The new time. delay relay performs the sat.e function as the two electro-mechanical timers except for the "AT HOME POSITION" annunciator. By removing the-redundancy of two electro-mechanical timers and replacing them with one solid state time delay relay, the possibility of creating a malfunction is not increased'because of the reliability of the new time delay ralays.
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7 Modification M-4-2-82-16 Description The pressure suppression chamber wide. range level monitoring system was installed as a result of AIR 4-82-6 to provide the main control room with level indication outside the normal ~ range of operation. The system is comprised of two independant channels and uses differential pressure between the top and the bottom of the pressure suppression chamber to sense the level. Each channel has a gauge readout on the 902-3 panel and a strip chart recorder-on the 902-2 panel. Pressure indication is provided alongside level readout on all four indicators.
Evaluation The existing pressure suppression chamber level monitoring system will remain intact and will be used during normal operation. In the event that suppression chamber level rises / falls outside the range of the existing level monitoring system, the wide range level monitoring system will provide the necessary information. Since this system only supplies additional information, the margin of safety is increased.
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Modification M-4-2-82-17
~ Description-The modification is to install a hydrogen monitoring system. The existing system does not. fully. satisfy NRC requirements listed in the NUREG 0737. The existing in-containment system will be replaced with an out-of-containment 1 hydrogen monitoring system.-
Evaluation The modifications upgrade is to meet new NRC standards. The function and basic operation of the system is not being changed. The margin of safety is not reduced. g l
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- D- Modification M-4-2-83-30
' Description The modification-is to install alternate power feeds and control for Diesel Generator auxiliaries, alternate feeds to the, Division II IUIR room cooler, reroute RHR. pump power feeds, and install additional smoke detectors, ,
wet pipe sprinkler ~ system-and local control isolation capability for the RCIC steam supply isolation valve. The modification is necessary for the station to comply with 10CFR50 Appendix R.
Evaluation The modifications are to reduce the possible consequences of a fire in various zones, this reduces the probability of an accident or malfunction of equipment. It also increases the reliability of the on-site power system, RHR system and fire protection system. The margin of safety is increased.
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l Modification M-4-2-83-45
' Description
'This modification was initiated to replace the old Unit One 1255 volt battery which was nearing the end of its service life. A new 125 volt battery, aLGNB type NCT 1344, was. installed along with new seismically qualified battery racks.
Evaluation The new 125 volt battery has a greater ampere-hour capacity which enhances r plant safety. The battery rack is designed to be seismically qualified and therefore does not change the margin of plant safety.
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Modification M-4-2-84-39 Descriptiqn The modification is to install three-hour rated fire dampers in the HVAC duct penetrations and remove the old sections of duct work and install new sections of duct work. The reason for the modification is to meet the require-ments of 10CFR50 Appendix'R.
Evaluation This modification provides protection from a fire spreading from one fire zone to another. The margin of safety is maintained. The modification has no mechanical or electrical interfaces or interaction with existing safety related systems or equipment
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