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| | issue date = 09/30/1997 | | | issue date = 09/30/1997 |
| | title = Provides Update to Response to NRC RAI Re Adequacy & Availability of Design Bases Info Per 10CFR50.54(f) | | | title = Provides Update to Response to NRC RAI Re Adequacy & Availability of Design Bases Info Per 10CFR50.54(f) |
| | author name = MECREDY R C | | | author name = Mecredy R |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = VISSING G S | | | addressee name = Vissing G |
| | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) | | | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| | docket = 05000244 | | | docket = 05000244 |
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| =Text= | | =Text= |
| {{#Wiki_filter:/RECIPIENT ID CODE/NAME PDl-1 PD COPIES LTTR ENCL 1 1 RECIPIENT ID CODE/NAME VISSING F G.COPIES LTTR ENCL 1 1 CATEGORY 1 REGULATOR INFORMATION DISTRIBUTIOtlSTEM (RIDE)I ACCESSION NBR:9710080012 DOC.DATE: 97/09/30 NOTARIZED: | | {{#Wiki_filter:CATEGORY 1 REGULATOR INFORMATION DISTRIBUTIOtlSTEM (RIDE) |
| NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME i AUTHOR AFFILIATION MECREDY,R.C. | | I ACCESSION NBR:9710080012 DOC.DATE: 97/09/30 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME i AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 6 Electric Corp. |
| Rochester Gas 6 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION VISSINGF G.S. | | RECIP.NAME RECIPIENT AFFILIATION VISSINGF G. S. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Provides update to response to NRC RAI re adec(uacy 6 availability of design bases info per 10CFR50.54(f). | | Provides update to response to NRC RAI re adec(uacy 6 DISTRIBUTION CODE: A0740 TITLE: Responses NOTES:License Exp date to 50.54(f) |
| DISTRIBUTION CODE: A0740 COPIES RECEIVED:LTR j ENCL 1 SIZE: TITLE: Responses to 50.54(f)Req.for Design Basis Info NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
| | COPIES RECEIVED:LTR Req. |
| DOCKET 05000244 05000244 E INTERN': FILE CENTER 01 EXTERNAL: NRC PDR 1 1 1 1 1 1 NRR/DRPM/PGEB PDR-2/THOMAS,K 1 1 3 3 D E N T NOTE TO ALL"RIDS" RECIPIENTS:
| | j availability of design bases info per 10CFR50.54(f). |
| PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9 0 i) | | ENCL for Design Basis Info 1 |
| AND I ROCHESTER GAS AND EIECTR1C CORI/ORATION | | in accordance with 10CFR2,2.109(9/19/72). |
| ~89 FAST AVEhlUE, ROCHESTER, N.Y IrI6494001 AREA CODE 716&f6-2700 ROBERT C.MECREDY Vice President Nvcteor Operotions September 30, 1997 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555 | | SIZE: |
| | 05000244 |
| | / E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-1 PD 1 1 VISSING G. |
| | F 1 1 INTERN ': FILE CENTER 01 1 1 |
| | 1 1 |
| | NRR/DRPM/PGEB PDR-2/THOMAS,K 1 |
| | 3 1 |
| | 3 EXTERNAL: NRC PDR 1 1 D |
| | E N |
| | T NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9 |
| | |
| | 0 i) |
| | AND I |
| | ROCHESTER GAS AND EIECTR1C CORI/ORATION ~ 89 FAST AVEhlUE, ROCHESTER, N. Y IrI6494001 AREA CODE 716 &f6-2700 ROBERT C. MECREDY Vice President Nvcteor Operotions September 30, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555 |
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| ==Subject:== | | ==Subject:== |
| Update to Response to NRC Request for Information Pursuant to 10CFR50.54(f) regarding Adequacy and Availability of Design Bases Information R.E.Ginna Nuclear Power Plant Docket No.50-244 Ref.(a): RG&E letter R.E.Smith to U.S.NRC dated 2/7/97, re: Response to NRC Request for Information Pursuant to 10CFR50.54(f) regarding Adequacy and Availability of Design Bases Information | | Update to Response to NRC Request for Information Pursuant to 10CFR50.54(f) regarding Adequacy and Availability of Design Bases Information R. E. Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a): RG&E letter R.E. Smith to U.S. NRC dated 2/7/97, re: Response to NRC Request for Information Pursuant to 10CFR50.54(f) regarding Adequacy and Availability of Design Bases Information |
| | |
| | ==Dear Mr. Vissing:== |
| | |
| | On February 7, 1997, Rochester Gas & Electric (RG&E) responded to the Nuclear Regulatory Commission's request for information pursuant to 10CFR50.54(f) regarding adequacy and availability of design bases information. |
| | In its response, RG&E made a commitment to collate and validate selected information for specific systems and topics and link this information electronically with the UFSAR. |
| | Further, RG&E stated that its schedule for completion of the above examination and verification of system and topical design bases information had not been established yet, that it intended to develop a firm schedule in the third quarter of 1997, and that it would provide the schedule to the NRC at that time. |
| | RG&E has recognized the need to put in place an information technology (IT) infrastructure to support continued maintenance of the data collected from the UFSAR verification and design basis documentation projects, both of which are in progress. The UFSAR verification project uses the same resources (System Engineers) as does the design basis documentation project, so it is RG&E's intention to concentrate on the UFSAR verification until 10/18/98 iwhile in parallel developing the IT infrastructure) i "f |
| | and then shift focus to the design basis documentation project. This will cause the design basis documentation project's completion date to be extended by one year, until 12/01. |
| | The attached schedule contains the systems and topics RG&E intends to pursue (there may be some substitution). |
| | I 97i00800i2 970'tt30 lllillllilllllllllllliIIIIIillllllllil'. |
| | PDR ADGCK' 05000244 P -PDR L( |
| | ) |
| | : 2. RG&E also stated that it had scheduled, and incorporated into its business plan for 1997, the performance of two internal SSFIs (on the Component Cooling Water and the Service Water systems) and that, based on the results of these SSFIs, it would assess the need to conduct additional SSFIs in conjunction with the other design bases efforts described in the 10CFR50.54(f) response. In June, RG&E performed a Service Water SSFI in preparation for an NRC Architect-Engineer (A/E) inspection. The systems chosen by the NRC A/E Team were Component Cooling Water and Safety Injection. RG&E considers their in-depth review to have satisfied the need to perform any other SSFIs in 1997. |
| | : 3. RG&E has also reviewed its Configuration Management processes and concluded that additional enhancements to existing processes, such as calculation control and Vendor Technical Manual (VTM) control, are warranted. RG&E has recently completed a major upgrade to the VTM program, including strengthening the vendor recontact process. |
| | Improvements in the calculation control processes are being performed at this time. |
| | Very truly yours, Robert C. Mecredy EJF 7480 xc: Mr, Guy S. Vissing (Mail Stop 14B2) |
| | Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 US NRC Ginna Senior Resident Inspector |
| | |
| | , ~ |
| | 2000 2001 |
| | ~ "I6' Task Name Dura .. 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 UFSAR Verif. Sppt/DBD Prep Bb;Orrfti '!4@4%4%4 D8D Support Dbb:,Gr'ou '%:;:!'-':,;.".:.;:N~k~"">":>kmb)"'"'"':"".<'-+"'>"'>x)4@@~>>'>% C. |
| | SE/SME Training 1w Residual Heat Removal Off-Site Power Emergency Diesel Generators Component Cooling Water Standby Aux Feedwater NP4~"~."-.;..':I?j4@kjx>>) |
| | Main Steam Miscellaneous 10 Safety Injection Undervoltage 12 CVCS 13 Reactor Trip System 14 DC Power 16 Service Water 16 Main Steam ARVs 17 EDG HVAC 18 ESFAS 19 480 Volt AC Power 20 Containment 21 CNMT Rectrc Fan Coolers 22 Containment Spray 23 RCS Pressure Boundary 24 High Energy Une Break gr>gi:>'$$ :x(."g'"'@ |
| | Aux Feedwater x,:%>;>:pr 26 Environmental Qualification 27 Elect. Separation/Independen 4w 28 Seismic 29 CNMT Integrity 30 Reactor Pressure Vessel ASME Code Compliance 32 Electrical Codes & Standards 33 10CFR100 Accident Analysis Spechl Phnt Conditions 36 Completion td Page1 |
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| |
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| ==Dear Mr.Vissing:==
| | t) |
| On February 7, 1997, Rochester Gas&Electric (RG&E)responded to the Nuclear Regulatory Commission's request for information pursuant to 10CFR50.54(f) regarding adequacy and availability of design bases information.
| | Oi 4 ~ |
| In its response, RG&E made a commitment to collate and validate selected information for specific systems and topics and link this information electronically with the UFSAR.Further, RG&E stated that its schedule for completion of the above examination and verification of system and topical design bases information had not been established yet, that it intended to develop a firm schedule in the third quarter of 1997, and that it would provide the schedule to the NRC at that time.RG&E has recognized the need to put in place an information technology (IT)infrastructure to support continued maintenance of the data collected from the UFSAR verification and design basis documentation projects, both of which are in progress.The UFSAR verification project uses the same resources (System Engineers) as does the design basis documentation project, so it is RG&E's intention to concentrate on the UFSAR verification until 10/18/98 iwhile in parallel developing the IT infrastructure) i"f and then shift focus to the design basis documentation project.This will cause the design basis documentation project's completion date to be extended by one year, until 12/01.The attached schedule contains the systems and topics RG&E intends to pursue (there may be some substitution).
| | 4 ~ Pi |
| 97i00800i2 970'tt30 PDR ADGCK 05000244)P'"-PDR L(I lllillllilllllllllllliIIIIIillllllllil'. 2.RG&E also stated that it had scheduled, and incorporated into its business plan for 1997, the performance of two internal SSFIs (on the Component Cooling Water and the Service Water systems)and that, based on the results of these SSFIs, it would assess the need to conduct additional SSFIs in conjunction with the other design bases efforts described in the 10CFR50.54(f) response.In June, RG&E performed a Service Water SSFI in preparation for an NRC Architect-Engineer (A/E)inspection.
| | ~ C'}} |
| The systems chosen by the NRC A/E Team were Component Cooling Water and Safety Injection.
| |
| RG&E considers their in-depth review to have satisfied the need to perform any other SSFIs in 1997.3.RG&E has also reviewed its Configuration Management processes and concluded that additional enhancements to existing processes, such as calculation control and Vendor Technical Manual (VTM)control, are warranted.
| |
| RG&E has recently completed a major upgrade to the VTM program, including strengthening the vendor recontact process.Improvements in the calculation control processes are being performed at this time.Very truly yours, Robert C.Mecredy EJF 7480 xc: Mr, Guy S.Vissing (Mail Stop 14B2)Project Directorate I-1 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 US NRC Ginna Senior Resident Inspector
| |
| ,~~"I6'Task Name UFSAR Verif.Sppt/DBD Prep Dura..3 4 1 2 3 4 1 2 3 4 Bb;Orrfti'!4@4%4%4 2000 2001 1 2 3 4 1 2 3 4 D8D Support SE/SME Training Residual Heat Removal 1w"">":>kmb)"'"'"':"".<'-+"'>"'>x)4@@~>>'>%
| |
| C.Dbb:,Gr'ou
| |
| '%:;:!'-':,;.".:.;:N~k~
| |
| 10 12 Off-Site Power Emergency Diesel Generators Component Cooling Water Standby Aux Feedwater Main Steam Miscellaneous Safety Injection Undervoltage CVCS NP4~"~."-.;..':I?j4@kjx>>)
| |
| 13 14 16 Reactor Trip System DC Power Service Water 16 17 18 19 Main Steam ARVs EDG HVAC ESFAS 480 Volt AC Power 20 Containment 21 22 23 24 26 27 28 29 30 32 33 CNMT Rectrc Fan Coolers Containment Spray RCS Pressure Boundary High Energy Une Break Aux Feedwater Environmental Qualification Elect.Separation/Independen Seismic CNMT Integrity Reactor Pressure Vessel ASME Code Compliance Electrical Codes&Standards 10CFR100 4w gr>gi:>'$$
| |
| :x(."g'"'@
| |
| x,:%>;>:pr 36 Accident Analysis Spechl Phnt Conditions Completion td Page1 t)Oi 4~4~Pi~C'}}
| |
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ML17265A7041999-07-16016 July 1999
Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603
ML17265A6911999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached
ML17265A6871999-06-22022 June 1999
Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl
ML17265A6841999-06-21021 June 1999
Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment
ML17265A6741999-06-15015 June 1999
Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT
ML17265A6751999-06-11011 June 1999
Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification
ML17309A6551999-06-0707 June 1999
Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment
ML17265A6671999-06-0101 June 1999
Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301
ML17265A6641999-05-25025 May 1999
Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested
ML17265A6611999-05-24024 May 1999
Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730
ML20206U0921999-05-13013 May 1999
Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21
ML17265A6461999-05-12012 May 1999
Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP
ML17265A6411999-05-12012 May 1999
Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630
ML20206E7221999-04-29029 April 1999
Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21
ML20206H6911999-04-22022 April 1999
Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls
ML17265A6271999-04-19019 April 1999
Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5
ML17309A6501999-04-14014 April 1999
Forwards Revised Ginna Station EOPs & Procedures Index
ML17265A6121999-03-29029 March 1999
Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231
ML17265A6041999-03-24024 March 1999
Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618
ML17265A5641999-03-0101 March 1999
Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl
ML17265A5671999-03-0101 March 1999
Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl
ML17265A5551999-02-25025 February 1999
Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr
ML17265A5561999-02-22022 February 1999
Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d)
ML17265A5451999-02-12012 February 1999
Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii)
ML17309A6491999-02-12012 February 1999
Forwards Ginna Station EOPs
ML17265A5431999-02-0909 February 1999
Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301
ML17265A5361999-02-0202 February 1999
Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl
ML17311A0691999-01-25025 January 1999
Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date
ML17311A0671999-01-14014 January 1999
Forwards Revised Emergency Operating Procedures for Re Ginna NPP
ML17265A5131999-01-12012 January 1999
Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date
ML17265A5111999-01-11011 January 1999
Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl
ML17265A5101999-01-11011 January 1999
Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl
1999-09-30
[Table view] |
Text
CATEGORY 1 REGULATOR INFORMATION DISTRIBUTIOtlSTEM (RIDE)
I ACCESSION NBR:9710080012 DOC.DATE: 97/09/30 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME i AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSINGF G. S.
SUBJECT:
Provides update to response to NRC RAI re adec(uacy 6 DISTRIBUTION CODE: A0740 TITLE: Responses NOTES:License Exp date to 50.54(f)
COPIES RECEIVED:LTR Req.
j availability of design bases info per 10CFR50.54(f).
ENCL for Design Basis Info 1
in accordance with 10CFR2,2.109(9/19/72).
SIZE:
05000244
/ E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-1 PD 1 1 VISSING G.
F 1 1 INTERN ': FILE CENTER 01 1 1
1 1
NRR/DRPM/PGEB PDR-2/THOMAS,K 1
3 1
3 EXTERNAL: NRC PDR 1 1 D
E N
T NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9
0 i)
AND I
ROCHESTER GAS AND EIECTR1C CORI/ORATION ~ 89 FAST AVEhlUE, ROCHESTER, N. Y IrI6494001 AREA CODE 716 &f6-2700 ROBERT C. MECREDY Vice President Nvcteor Operotions September 30, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555
Subject:
Update to Response to NRC Request for Information Pursuant to 10CFR50.54(f) regarding Adequacy and Availability of Design Bases Information R. E. Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a): RG&E letter R.E. Smith to U.S. NRC dated 2/7/97, re: Response to NRC Request for Information Pursuant to 10CFR50.54(f) regarding Adequacy and Availability of Design Bases Information
Dear Mr. Vissing:
On February 7, 1997, Rochester Gas & Electric (RG&E) responded to the Nuclear Regulatory Commission's request for information pursuant to 10CFR50.54(f) regarding adequacy and availability of design bases information.
In its response, RG&E made a commitment to collate and validate selected information for specific systems and topics and link this information electronically with the UFSAR.
Further, RG&E stated that its schedule for completion of the above examination and verification of system and topical design bases information had not been established yet, that it intended to develop a firm schedule in the third quarter of 1997, and that it would provide the schedule to the NRC at that time.
RG&E has recognized the need to put in place an information technology (IT) infrastructure to support continued maintenance of the data collected from the UFSAR verification and design basis documentation projects, both of which are in progress. The UFSAR verification project uses the same resources (System Engineers) as does the design basis documentation project, so it is RG&E's intention to concentrate on the UFSAR verification until 10/18/98 iwhile in parallel developing the IT infrastructure) i "f
and then shift focus to the design basis documentation project. This will cause the design basis documentation project's completion date to be extended by one year, until 12/01.
The attached schedule contains the systems and topics RG&E intends to pursue (there may be some substitution).
I 97i00800i2 970'tt30 lllillllilllllllllllliIIIIIillllllllil'.
PDR ADGCK' 05000244 P -PDR L(
)
- 2. RG&E also stated that it had scheduled, and incorporated into its business plan for 1997, the performance of two internal SSFIs (on the Component Cooling Water and the Service Water systems) and that, based on the results of these SSFIs, it would assess the need to conduct additional SSFIs in conjunction with the other design bases efforts described in the 10CFR50.54(f) response. In June, RG&E performed a Service Water SSFI in preparation for an NRC Architect-Engineer (A/E) inspection. The systems chosen by the NRC A/E Team were Component Cooling Water and Safety Injection. RG&E considers their in-depth review to have satisfied the need to perform any other SSFIs in 1997.
- 3. RG&E has also reviewed its Configuration Management processes and concluded that additional enhancements to existing processes, such as calculation control and Vendor Technical Manual (VTM) control, are warranted. RG&E has recently completed a major upgrade to the VTM program, including strengthening the vendor recontact process.
Improvements in the calculation control processes are being performed at this time.
Very truly yours, Robert C. Mecredy EJF 7480 xc: Mr, Guy S. Vissing (Mail Stop 14B2)
Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 US NRC Ginna Senior Resident Inspector
, ~
2000 2001
~ "I6' Task Name Dura .. 3 4 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 UFSAR Verif. Sppt/DBD Prep Bb;Orrfti '!4@4%4%4 D8D Support Dbb:,Gr'ou '%:;:!'-':,;.".:.;:N~k~"">":>kmb)"'"'"':"".<'-+"'>"'>x)4@@~>>'>% C.
SE/SME Training 1w Residual Heat Removal Off-Site Power Emergency Diesel Generators Component Cooling Water Standby Aux Feedwater NP4~"~."-.;..':I?j4@kjx>>)
Main Steam Miscellaneous 10 Safety Injection Undervoltage 12 CVCS 13 Reactor Trip System 14 DC Power 16 Service Water 16 Main Steam ARVs 17 EDG HVAC 18 ESFAS 19 480 Volt AC Power 20 Containment 21 CNMT Rectrc Fan Coolers 22 Containment Spray 23 RCS Pressure Boundary 24 High Energy Une Break gr>gi:>'$$ :x(."g'"'@
Aux Feedwater x,:%>;>:pr 26 Environmental Qualification 27 Elect. Separation/Independen 4w 28 Seismic 29 CNMT Integrity 30 Reactor Pressure Vessel ASME Code Compliance 32 Electrical Codes & Standards 33 10CFR100 Accident Analysis Spechl Phnt Conditions 36 Completion td Page1
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