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| {{#Wiki_filter:CATEGORY j.REGULATC.INFORMATION DISTRIBUPEON | | {{#Wiki_filter:CATEGORY j. |
| ..TEM (RIDS)ACCESSION NBR:9602130347 DOC.DATE: 96/02/09 NOTARIZED: | | REGULATC. INFORMATION DISTRIBUPEON .. TEM (RIDS) |
| NO DOCKET I FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester, 6.Q5090244.AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C. | | ACCESSION NBR:9602130347 DOC.DATE: 96/02/09 NOTARIZED: NO DOCKET I FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester, 6 . Q5090244. |
| Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. | | AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp. |
| | RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forwards LAR revising TS to incorporate methodology for dekermining LTOP limits in Administrative Controls Section 5.6.6.DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR j ENCL J SIZE:+TITLE: OR Submittal: | | Forwards LAR revising TS to incorporate methodology for dekermining LTOP limits in Administrative Controls Section TITLE: OR 5.6.6. |
| General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). | | DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR Submittal: General Distribution j ENCL NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). |
| 05000244 E RECIPIENT ID CODE/NAME PDl-1 LA JOHNSON,A INTERNA: FILE'ENTER.-='01 | | J SIZE: + |
| 'NRR/DRCH/H I CB NRR/DSSA/SRXB OGC/HDS3 COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME PD1-1 PD 1 1 NRR/DE/EMCB 1 1 NRR/DSSA/SPLB 1 1 NUDOCS-ABSTRACT 1 0 COPIES LTTR ENCL 1 1 1 1 1 1 1 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D E N NOTE TO ALL"RIDS" RECIPIENTS: | | 05000244 E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL 0 PDl-1 LA 1 1 PD1-1 PD 1 1 JOHNSON,A 1 1 INTERNA: FILE'ENTER.-='01 1 1 NRR/DE/EMCB 1 1 |
| PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL.11 | | 'NRR/DRCH/H ICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D |
| ~r g~I r r r t"tttL3 ANn ROCHESTER GAS AND ELECTRIC CORPORATION | | E N |
| ~89 FAST AVENUE ROCHESTER N.Y Irt6rt9 000I ARFA CODE716 Sf6-2700 ROBERT C.MECREDY Vice President Nudeor Operotions February 9, 1996 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-3 Washington, D.C.20555 | | NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| | TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL . 11 |
| | |
| | ~r g~ I r |
| | r r t "tttL3 ANn ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 FAST AVENUE ROCHESTER N. Y Irt6rt9 000I ARFA CODE716 Sf6-2700 ROBERT C. MECREDY Vice President Nudeor Operotions February 9, 1996 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555 |
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| ==Subject:== | | ==Subject:== |
| Application for Amendment to Facility Operating License Methodology for Low Temperature Ove'rpressure Protection (LTOP)Limits Rochester Gas A Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244 | | Application for Amendment to Facility Operating License Methodology for Low Temperature Ove'rpressure Protection (LTOP) Limits Rochester Gas A Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244 |
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| ==References:== | | ==References:== |
| (a)NUREG-1431, Standard Technical Specifications, 8'estinghouse Plants, April 1995.(b)Letter from R.C.Mecredy, RGB'.E, to A.A.Johnson, NRC, | | (a) NUREG-1431, Standard Technical Specifications, 8'estinghouse Plants, April 1995. |
| | (b) Letter from R.C. Mecredy, RGB'.E, to A.A. Johnson, NRC, |
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| ==Subject:== | | ==Subject:== |
| Technical Specification Improvement Program, Reactor Coolant Systeni (RCS)Pressure and Temperature Limits Report (PTLR), dated December 8, 1995.(c)Letter from L.T.Marsh, NRC, to R.C.Mecredy, RGELE, | | |
| | Technical Specification Improvement Program, Reactor Coolant Systeni (RCS) Pressure and Temperature Limits Report (PTLR), dated December 8, 1995. |
| | (c) Letter from L.T. Marsh, NRC, to R.C. Mecredy, RGELE, |
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| ==Subject:== | | ==Subject:== |
| R,L.Ginna-Acceptance for Referencing of Pressure Temperature Limits Report (TAC 0 M92320), dated December 26, 1995. | | R,L. Ginna |
| | - Acceptance for Referencing ofPressure Temperature Limits Report (TAC 0 M92320), dated December 26, 1995. |
| | |
| | ==Dear Mr. Johnson,== |
| | |
| | The enclosed License Amendment Request (LAR) proposes to revise the Ginna Station Technical Specifications to incorporate the methodology for determining the LTOP limits into Administrative Controls Section 5.6.6. This change will allow RGkE to perform future LTOP evaluations using NRC approved methodology without requiring a potential technical specification change. The change will also provide consistency with NUREG-1431 (Ref. (a)). |
| | i30089 9602i30347 960209 PDR ADQCK 05000244 P PDR |
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| | T |
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| ==Dear Mr.Johnson,==
| | The actual methodology being proposed by RGB'or determining LTOP limits was previously submitted to the NRC during the conversion to improved standard technical specifications for Ginna Station (Ref. (b), Attachment Il). By Reference (c), the NRC stated that the staff could not complete its review of the methodology for the LTOP and RCS pressure and temperature limits provided in the PTLR since "RG&E had determined that they need to operate in accordance with the existing limits, previously approved by the staff." Therefore, the NRC allowed RGkE to relocate the actual, limits to the PTLR but any changes to these limits would require NRC review and approval. |
| The enclosed License Amendment Request (LAR)proposes to revise the Ginna Station Technical Specifications to incorporate the methodology for determining the LTOP limits into Administrative Controls Section 5.6.6.This change will allow RGkE to perform future LTOP evaluations using NRC approved methodology without requiring a potential technical specification change.The change will also provide consistency with NUREG-1431 (Ref.(a)).i30089 9602i30347 960209 PDR ADQCK 05000244 P PDR 1 1 T~p The actual methodology being proposed by RGB'or determining LTOP limits was previously submitted to the NRC during the conversion to improved standard technical specifications for Ginna Station (Ref.(b), Attachment Il).By Reference (c), the NRC stated that the staff could not complete its review of the methodology for the LTOP and RCS pressure and temperature limits provided in the PTLR since"RG&E had determined that they need to operate in accordance with the existing limits, previously approved by the staff." Therefore, the NRC allowed RGkE to relocate the actual, limits to the PTLR but any changes to these limits would require NRC review and approval.However, the determination that Ginna Station needed to"operate in accordance with existing limits" was with respect to the RCS pressure and temperature limits that are included in the PTLR, not for the LTOP limits.As such, this LAR requests that the LTOP methodology be reviewed and approved by the NRC staff such that it can be referenced within the Administrative Controls section of the technical specifications.
| | However, the determination that Ginna Station needed to "operate in accordance with existing limits" was with respect to the RCS pressure and temperature limits that are included in the PTLR, not for the LTOP limits. As such, this LAR requests that the LTOP methodology be reviewed and approved by the NRC staff such that it can be referenced within the Administrative Controls section of the technical specifications. Any changes to the RCS pressure and temperature limits included in the PTLR will still require NRC review and approval following this change. |
| Any changes to the RCS pressure and temperature limits included in the PTLR will still require NRC review and approval following this change.Very truly yours, C'DFi802 Attachments XC: U.S.Nuclear Regulatory Commission Mr.Allen R.Johnson (Mail Stop 14B2)PWR Project Directorate I-1 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Mr.F.William Valentine, President New York State Energy, Research, and Development Authority 2 Rockefeller Plaza Albany, NY 12223-1253}} | | Very truly yours, C'DFi802 Attachments XC: U.S. Nuclear Regulatory Commission Mr. Allen R. Johnson (Mail Stop 14B2) |
| | PWR Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Mr. F. William Valentine, President New York State Energy, Research, and Development Authority 2 Rockefeller Plaza Albany, NY 12223-1253}} |
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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
CATEGORY j.
REGULATC. INFORMATION DISTRIBUPEON .. TEM (RIDS)
ACCESSION NBR:9602130347 DOC.DATE: 96/02/09 NOTARIZED: NO DOCKET I FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester, 6 . Q5090244.
AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.
SUBJECT:
Forwards LAR revising TS to incorporate methodology for dekermining LTOP limits in Administrative Controls Section TITLE: OR 5.6.6.
DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR Submittal: General Distribution j ENCL NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
J SIZE: +
05000244 E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL 0 PDl-1 LA 1 1 PD1-1 PD 1 1 JOHNSON,A 1 1 INTERNA: FILE'ENTER.-='01 1 1 NRR/DE/EMCB 1 1
'NRR/DRCH/H ICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D
E N
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL . 11
~r g~ I r
r r t "tttL3 ANn ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 FAST AVENUE ROCHESTER N. Y Irt6rt9 000I ARFA CODE716 Sf6-2700 ROBERT C. MECREDY Vice President Nudeor Operotions February 9, 1996 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555
Subject:
Application for Amendment to Facility Operating License Methodology for Low Temperature Ove'rpressure Protection (LTOP) Limits Rochester Gas A Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244
References:
(a) NUREG-1431, Standard Technical Specifications, 8'estinghouse Plants, April 1995.
(b) Letter from R.C. Mecredy, RGB'.E, to A.A. Johnson, NRC,
Subject:
Technical Specification Improvement Program, Reactor Coolant Systeni (RCS) Pressure and Temperature Limits Report (PTLR), dated December 8, 1995.
(c) Letter from L.T. Marsh, NRC, to R.C. Mecredy, RGELE,
Subject:
R,L. Ginna
- Acceptance for Referencing ofPressure Temperature Limits Report (TAC 0 M92320), dated December 26, 1995.
Dear Mr. Johnson,
The enclosed License Amendment Request (LAR) proposes to revise the Ginna Station Technical Specifications to incorporate the methodology for determining the LTOP limits into Administrative Controls Section 5.6.6. This change will allow RGkE to perform future LTOP evaluations using NRC approved methodology without requiring a potential technical specification change. The change will also provide consistency with NUREG-1431 (Ref. (a)).
i30089 9602i30347 960209 PDR ADQCK 05000244 P PDR
1 1
T
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The actual methodology being proposed by RGB'or determining LTOP limits was previously submitted to the NRC during the conversion to improved standard technical specifications for Ginna Station (Ref. (b), Attachment Il). By Reference (c), the NRC stated that the staff could not complete its review of the methodology for the LTOP and RCS pressure and temperature limits provided in the PTLR since "RG&E had determined that they need to operate in accordance with the existing limits, previously approved by the staff." Therefore, the NRC allowed RGkE to relocate the actual, limits to the PTLR but any changes to these limits would require NRC review and approval.
However, the determination that Ginna Station needed to "operate in accordance with existing limits" was with respect to the RCS pressure and temperature limits that are included in the PTLR, not for the LTOP limits. As such, this LAR requests that the LTOP methodology be reviewed and approved by the NRC staff such that it can be referenced within the Administrative Controls section of the technical specifications. Any changes to the RCS pressure and temperature limits included in the PTLR will still require NRC review and approval following this change.
Very truly yours, C'DFi802 Attachments XC: U.S. Nuclear Regulatory Commission Mr. Allen R. Johnson (Mail Stop 14B2)
PWR Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Mr. F. William Valentine, President New York State Energy, Research, and Development Authority 2 Rockefeller Plaza Albany, NY 12223-1253
