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| {{#Wiki_filter:ZCCEr.ER<TZD DISTR<au TrON DEivrOXSTR~rrON SVSTZM REGULATOR'INFORMATION DISTRIBUTION SL'EM (RIDE)ACCESSXON NBR:9210050344 DOC.DATE: 92/09/15 NOTARIZED: | | {{#Wiki_filter:ZCCEr.ER<TZD DISTR<au TrON DEivrOXSTR~rrON SVSTZM REGULATOR'INFORMATION DISTRIBUTION SL'EM (RIDE) |
| YES FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C. | | ACCESSXON NBR:9210050344 DOC.DATE: 92/09/15 NOTARIZED: YES FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas a Electric Corp. |
| Rochester Gas a Electric Corp.RECXP.NAME RECIPIENT AFFILIATION JOHNSONPA.R. | | RECXP.NAME RECIPIENT AFFILIATION JOHNSONPA.R. Project Directorate I-3 |
| Project Directorate I-3 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forwards application for amend to license DpR-18,revising R app A including TS 3.1.1.4,3.1.1,6 a 4.3.4&adding site specific sections in response to GL 90-06.DXSTRIBUTION CODE: A019D COPIES RECEIVED:LTR I ENCL SIZE: TXTLE: Generic Ltr 90-06 Resolution of GE 70N94 PORVs 9 Block Valve Relz.anil 0 NOTES:License Exp date in accordance with lOCFR2,2el09(9/19/7 | | Forwards application for amend to license DpR-18,revising app A including TS 3.1.1.4,3.1.1,6 a 4.3.4 & adding site R specific sections in response to GL 90-06. |
| ).2.05000244 S RECIPIENT ID CODE/NAME PDl-3 LA JOHNSONPA INTERNAL: KIRKWOODPR.NLS3 | | DXSTRIBUTION CODE: A019D COPIES RECEIVED:LTR I ENCL SIZE: |
| /w REG FIL 01 S7DSIR/RPSIB EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/EMEB PICKETTP D 13H15 RES/DSIR/EIB NUDOCS-ABSTRACT COPIES LTTR ENCL 1 1 1 1'1 1 1 1 1/A 0 p+Q 0 Xt'ft'!)7 NOTE TO ALL RIDS RECIPIENTS:
| | TXTLE: Generic Ltr 90-06 Resolution of GE 70N94 PORVs 9 Block Valve Relz.anil 0 NOTES:License Exp date in accordance with 10CFR2,2el09(9/19/7 2 ).. 05000244 S RECIPIENT COPIES RECIPIENT COPIES / |
| PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK.ROOM Pl-S7{EXT.504-2065)TO ELIMINATE YOUR NAMF FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 12 0 IIIIZZ IIIIIIIIIII Arm IZZggjru ZuSZ(Z un~(ZE/IIIIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION 89 EAST AVENUE, ROCHESTER N.K 14649-0001 ROBERT C MECREDY Vice Prerldent Clnna Nudear Producrion September 15, 1992 1KLEPHONE AREa COOE we 546-2700 IJ.S.Nuclear Regulatory Commission Document Control Desk Attn: Mr.Allen R.Johnson PWR Project Directorate I-3 Washington, D.C.20555 | | ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA 1 1 PD1-3 PD 1 1 A JOHNSONPA 1 1 INTERNAL: KIRKWOODPR.NLS3 1 1 NRR/EMEB ' |
| | 1 1 |
| | /w 1 1 PICKETTP D 13H15 1 0 REG FIL 01 1 1 RES/DSIR/EIB 1 1 S7DSIR/RPSIB 1 1 EXTERNAL: NRC PDR 1 1 NUDOCS-ABSTRACT 1 1 p+ Q 0 Xt'ft'! ) 7 NOTE TO ALL RIDS RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE ROOM Pl-S7 {EXT. 504-2065) DOCUMENT CONTROL DESK. |
| | TO ELIMINATE YOUR NAMF LISTS FOR DOCUMENTS FROM DISTRIBUTION YOU DON'T NEED! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 12 |
| | |
| | IIIIZZ IIIIIIIIIII 0 |
| | Arm IZZggjru ZuSZ(Z un~(ZE/ IIIIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION 89 EAST AVENUE, ROCHESTER N.K 14649-0001 ROBERT C MECREDY 1KLEPHONE Vice Prerldent AREa COOE we 546-2700 Clnna Nudear Producrion September 15, 1992 IJ.S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. Allen R. Johnson PWR Project Directorate I-3 Washington, D.C. 20555 |
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| ==Subject:== | | ==Subject:== |
| Rochester Gas and Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244 Ref.(a): Generic Letter 90-06, Resolution of Generic Issue 70,'Power-Operated. | | Rochester Gas and Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a): Generic Letter 90-06, Resolution of Generic Issue 70, |
| Relief Valve and.Block Valve Reliability'nd Generic Issue 94'Additional Low-Temperature Overpressure Protection for Light-Water Reactors'ear Mr.Johnson: Enclosed is an Application for Amendment to Operating License No.DPR-18 to amend.Appendix A of that license to satisfy Rochester Gas and Electric Corporation's (RGSE's)commitment to revise the Technical Specifications consistent with our April 18, 1991 response to reference (a)=-pursuant to 10CFR50.54(f). | | 'Power-Operated. Relief Valve and. Block Valve |
| On April 30, 1991, we forwarded a letter to your attention confirming our commitment to upgrade PORVs/control circuits to meet environmentally qualified.(EQ)conditions during the 1992 Refueling Outage.Per discussions on January 16, 1992, we informed you that additional time was required, until the 1993 Refueling Outage, to modify the EQ portion of the PORVs.Consistent with our response to Generic Letter 90-06, the proposed Amendment revises Technical Specification Sections 3.1.1.4, 3.1.1.6, 4.3.4 and adds site specific basis sections to address the generic letter.Technical Specification Section 3.1.1.4 will be deleted;however, the provisions of the specification will be relocated under proposed Specification 3.1.1.6.This revision continues to ensure that existing and proposed limiting conditions of operation'are met.The proposed revision also eliminates the need to duplicate identical requirements under two individual specifications. | | 'Additional Low-Temperature Reliability'nd Generic Issue 94 Overpressure Protection for Light-Water Reactors'ear Mr. Johnson: |
| Similarly, Surveillance Requirement 4.3.5.6 will be renumbered and relocated under the provisions of Specification Section 4'.3.4, Relief Valves.This administrative change also ensures consistency with proposed Specification 3.1.1.6.Further, as a result of the insertion of the lengthy basis sections described in the generic letter, several sections within Ginna Technical Specifications were rearranged to accommodate the additional information. | | Enclosed is an Application for Amendment to Operating License No. |
| Rearrangement of the basis sections are I 2 1 92i0050344 PDR,"ADOCK 05000244 i', P | | DPR-18 to amend. Appendix A of that license to satisfy Rochester Gas and Electric Corporation's (RGSE's) commitment to revise the Technical Specifications consistent with our April 18, 1991 response to reference (a)=-pursuant to 10CFR50.54(f). On April 30, 1991, we forwarded a letter to your attention confirming our commitment to upgrade PORVs/control circuits to meet environmentally qualified. (EQ) conditions during the 1992 Refueling Outage. Per discussions on January 16, 1992, we informed you that additional time was required, until the 1993 Refueling Outage, to modify the EQ portion of the PORVs. |
| ~~ | | Consistent with our response to Generic Letter 90-06, the proposed Amendment revises Technical Specification Sections 3.1.1.4, 3.1.1.6, 4.3.4 and adds site specific basis sections to address the generic letter. Technical Specification Section 3.1.1.4 will be deleted; however, the provisions of the specification will be relocated under proposed Specification 3.1.1.6. This revision continues to ensure that existing and proposed limiting conditions of operation'are met. The proposed revision also eliminates the need to duplicate identical requirements under two individual specifications. Similarly, Surveillance Requirement 4.3.5.6 will be renumbered and relocated under the provisions of Specification Section 4'.3.4, Relief Valves. This administrative change also ensures consistency with proposed Specification 3.1.1.6. Further, as a result of the insertion of the lengthy basis sections described in the generic letter, several sections within Ginna Technical Specifications were rearranged to accommodate the additional information. Rearrangement of the basis sections are I 2 1 92i0050344 PDR, "ADOCK 05000244 i', |
| considered to be administrative in nature and promote clarity.Specification section 3.1.1.3 will be revised to address limiting conditions for operation above cold shutdown.This proposed change is conservative and considered to be an administrative change.This proposed Amendment should be considered effective 30 days after receipt of the Commission's approval.Very truly yours, Robert C.Mecre GALN161 Enclosures xc: Mr.Allen R.Johnson (Mail Stop 14D1)Project Directorate I-3 Washington, D.C.20555 Ms.Donna Ross New York State Energy Office U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector}} | | P |
| | |
| | ~ ~ |
| | considered to be administrative in nature and promote clarity. |
| | Specification section 3.1.1.3 will be revised to address limiting conditions for operation above cold shutdown. This proposed change is conservative and considered to be an administrative change. |
| | This proposed Amendment should be considered effective 30 days after receipt of the Commission's approval. |
| | Very truly yours, Robert C. Mecre GALN161 Enclosures xc: Mr. Allen R. Johnson (Mail Stop 14D1) |
| | Project Directorate I-3 Washington, D.C. 20555 Ms. Donna Ross New York State Energy Office U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector}} |
Forwards Application for Amend to License DPR-18,revising TS Sections 3.1.1.4,3.1.1.6,4.3.4 & Adding site-specific Basis Sections to Address GL 90-06 Re Resolution of Generic Issues 70 & 94| ML17262B018 |
| Person / Time |
|---|
| Site: |
Ginna  |
|---|
| Issue date: |
09/15/1992 |
|---|
| From: |
Mecredy R
ROCHESTER GAS & ELECTRIC CORP. |
|---|
| To: |
Andrea Johnson
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
|---|
| Shared Package |
|---|
| ML17262B019 |
List: |
|---|
| References |
|---|
| REF-GTECI-070, REF-GTECI-094, REF-GTECI-NI, TASK-070, TASK-094, TASK-70, TASK-94, TASK-OR GL-90-06, GL-90-6, NUDOCS 9210050344 |
| Download: ML17262B018 (4) |
|
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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
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Text
ZCCEr.ER<TZD DISTR<au TrON DEivrOXSTR~rrON SVSTZM REGULATOR'INFORMATION DISTRIBUTION SL'EM (RIDE)
ACCESSXON NBR:9210050344 DOC.DATE: 92/09/15 NOTARIZED: YES FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas a Electric Corp.
RECXP.NAME RECIPIENT AFFILIATION JOHNSONPA.R. Project Directorate I-3
SUBJECT:
Forwards application for amend to license DpR-18,revising app A including TS 3.1.1.4,3.1.1,6 a 4.3.4 & adding site R specific sections in response to GL 90-06.
DXSTRIBUTION CODE: A019D COPIES RECEIVED:LTR I ENCL SIZE:
TXTLE: Generic Ltr 90-06 Resolution of GE 70N94 PORVs 9 Block Valve Relz.anil 0 NOTES:License Exp date in accordance with 10CFR2,2el09(9/19/7 2 ).. 05000244 S RECIPIENT COPIES RECIPIENT COPIES /
ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA 1 1 PD1-3 PD 1 1 A JOHNSONPA 1 1 INTERNAL: KIRKWOODPR.NLS3 1 1 NRR/EMEB '
1 1
/w 1 1 PICKETTP D 13H15 1 0 REG FIL 01 1 1 RES/DSIR/EIB 1 1 S7DSIR/RPSIB 1 1 EXTERNAL: NRC PDR 1 1 NUDOCS-ABSTRACT 1 1 p+ Q 0 Xt'ft'! ) 7 NOTE TO ALL RIDS RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE ROOM Pl-S7 {EXT. 504-2065) DOCUMENT CONTROL DESK.
TO ELIMINATE YOUR NAMF LISTS FOR DOCUMENTS FROM DISTRIBUTION YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 12
IIIIZZ IIIIIIIIIII 0
Arm IZZggjru ZuSZ(Z un~(ZE/ IIIIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION 89 EAST AVENUE, ROCHESTER N.K 14649-0001 ROBERT C MECREDY 1KLEPHONE Vice Prerldent AREa COOE we 546-2700 Clnna Nudear Producrion September 15, 1992 IJ.S. Nuclear Regulatory Commission Document Control Desk Attn: Mr. Allen R. Johnson PWR Project Directorate I-3 Washington, D.C. 20555
Subject:
Rochester Gas and Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a): Generic Letter 90-06, Resolution of Generic Issue 70,
'Power-Operated. Relief Valve and. Block Valve
'Additional Low-Temperature Reliability'nd Generic Issue 94 Overpressure Protection for Light-Water Reactors'ear Mr. Johnson:
Enclosed is an Application for Amendment to Operating License No.
DPR-18 to amend. Appendix A of that license to satisfy Rochester Gas and Electric Corporation's (RGSE's) commitment to revise the Technical Specifications consistent with our April 18, 1991 response to reference (a)=-pursuant to 10CFR50.54(f). On April 30, 1991, we forwarded a letter to your attention confirming our commitment to upgrade PORVs/control circuits to meet environmentally qualified. (EQ) conditions during the 1992 Refueling Outage. Per discussions on January 16, 1992, we informed you that additional time was required, until the 1993 Refueling Outage, to modify the EQ portion of the PORVs.
Consistent with our response to Generic Letter 90-06, the proposed Amendment revises Technical Specification Sections 3.1.1.4, 3.1.1.6, 4.3.4 and adds site specific basis sections to address the generic letter. Technical Specification Section 3.1.1.4 will be deleted; however, the provisions of the specification will be relocated under proposed Specification 3.1.1.6. This revision continues to ensure that existing and proposed limiting conditions of operation'are met. The proposed revision also eliminates the need to duplicate identical requirements under two individual specifications. Similarly, Surveillance Requirement 4.3.5.6 will be renumbered and relocated under the provisions of Specification Section 4'.3.4, Relief Valves. This administrative change also ensures consistency with proposed Specification 3.1.1.6. Further, as a result of the insertion of the lengthy basis sections described in the generic letter, several sections within Ginna Technical Specifications were rearranged to accommodate the additional information. Rearrangement of the basis sections are I 2 1 92i0050344 PDR, "ADOCK 05000244 i',
P
~ ~
considered to be administrative in nature and promote clarity.
Specification section 3.1.1.3 will be revised to address limiting conditions for operation above cold shutdown. This proposed change is conservative and considered to be an administrative change.
This proposed Amendment should be considered effective 30 days after receipt of the Commission's approval.
Very truly yours, Robert C. Mecre GALN161 Enclosures xc: Mr. Allen R. Johnson (Mail Stop 14D1)
Project Directorate I-3 Washington, D.C. 20555 Ms. Donna Ross New York State Energy Office U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector