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| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE |
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| {{#Wiki_filter:PRIORITY 1 (ACCELERATED RZDS PROCESSING) | | {{#Wiki_filter:PRIORITY 1 (ACCELERATED RZDS PROCESSING) |
| REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9509080079 DOC.DATE: 95/08/31 NOTARIZED: | | REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| YES DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 P AUTH.NAME , AUTHOR AFFILIATION MECREDY,R.C. | | ACCESSION NBR:9509080079 DOC.DATE: 95/08/31 NOTARIZED: YES DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 P AUTH. NAME AUTHOR AFFILIATION Rochester Gas & Electric Corp. |
| Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFXLXATION JOHNSON,A.R.
| | MECREDY,R.C. |
| | RECIP.NAME RECIPIENT AFFXLXATION JOHNSON,A.R. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Forwards application for amends to license DPR-18,proposing TS to implement WCAP-10271,its assoc suppl 6 other re changes w/respect to RTS 6 ESFAS.0 DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR Q ENCL+SIZE: 3+l2, TITLE: OR Submittal General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). | | Forwards application for amends to license DPR-18,proposing TS to implement WCAP-10271,its assoc suppl 6 other re changes w/respect to RTS 6 ESFAS. 0 DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal General Distribution Q ENCL + SIZE: 3 +l2, NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 I RECXPIENT =COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL XD CODE/NAME LTTR ENCL PD1-1 LA 1 1 PD1-1 PD 1 1 JO A 1 1 INTERNAL FILE C 01 1 1 NRR/DE/EMCB 1 1 DRCH/HICB- 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 0 |
| 05000244 I RECXPIENT ID CODE/NAME PD1-1 LA JO A=COPIES RECIPIENT LTTR ENCL XD CODE/NAME 1 1 PD1-1 PD 1 1 COPIES LTTR ENCL 1 1 INTERNAL FILE C 01 DRCH/HICB-NRR/DSSA/SRXB OGC/HDS3 EXTERNAL: NOAC 1 1 1 1 1.1 1 0 1 1 NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR 1 1 1 1 1 1 1 1 0 C N NOTE TO ALL"RZDS" RECIPIENTS: | | C N |
| PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D8 (415-2083) | | NOTE TO ALL "RZDS" RECIPIENTS: |
| TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 11 r, q 5 L Aen ROCHESTER GAS AND ElECTRIC CORPORATION | | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D8 (415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 11 |
| ~89 EASTAYENUE, ROCHESTER, M Y ld649-0001 AREA CODE7I6 5'-2700 ROBERT C.MECREDY Vice President Hvdeoroperotions August 31, 1995 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-3 Washington, D.C.20555 | | |
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| | Aen ROCHESTER GAS AND ElECTRIC CORPORATION ~ 89 EASTAYENUE, ROCHESTER, M Y ld649-0001 AREA CODE7I6 5'-2700 ROBERT C. MECREDY Vice President Hvdeoroperotions August 31, 1995 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:== |
| Changes to Technical Specification Instrumentation Requirements Conversion to Improved Technical Specifications Rochester Gas 2 Electric Corporation R.E.Ginna Nuclear Power Plant Docket No.50-244 | | Changes to Technical Specification Instrumentation Requirements Conversion to Improved Technical Specifications Rochester Gas 2 Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244 |
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| ==Dear Mr.Johnson,== | | ==Dear Mr. Johnson,== |
| By Reference (a), RGB'roposed to convert the current Ginna Station Technical Specifications to the Improved Standard Technical Specifications (i.e., NUEEG-1431). | | |
| Included within this conversion were numerous changes to the current requirements for the Reactor Trip System (RTS)and Engineered Safety Features Actuation System (ESFAS).Several of these changes were based on Reference (b), which if approved, would allow up to 72 hours to place inoperable RTS and ESFAS channels in the tripped condition and allow the bypass of an inoperable channel for up to 12 hours.Based on conversations with NRC staff RGEcE has agreed to defer these changes until after the conversion process since WCAP-14333 has not yet received staff review and approval.In place of the changes justified by WCAP-14333, RG&E proposes to implement those documented in References (c), (d), and (e)which have received NRC staff review and generic approval.The purpose of this submittal is to provide the necessary justification to implement the changes to the RTS and ESFAS surveillance requirements and required actions as documented in WCAP-10271 and its supplements. | | By Reference (a), RGB'roposed to convert the current Ginna Station Technical Specifications to the Improved Standard Technical Specifications (i.e., NUEEG-1431). Included within this conversion were numerous changes to the current requirements for the Reactor Trip System (RTS) and Engineered Safety Features Actuation System (ESFAS). Several of these changes were based if on Reference (b), which approved, would allow up to 72 hours to place inoperable RTS and ESFAS channels in the tripped condition and allow the bypass of an inoperable channel for up to 12 hours. Based on conversations with NRC staff RGEcE has agreed to defer these changes until after the conversion process since WCAP-14333 has not yet received staff review and approval. In place of the changes justified by WCAP-14333, RG&E proposes to implement those documented in References (c), (d), and (e) which have received NRC staff review and generic approval. |
| In order to support NRC review of this change, this submittal is organized as follows: The implementation of WCAP-10271 and other related changes is documented in this.submittal as a separate license amendment request (LAR)with respect to the current Ginna Station Technical Specifications. | | The purpose of this submittal is to provide the necessary justification to implement the changes to the RTS and ESFAS surveillance requirements and required actions as documented in WCAP-10271 and its supplements. In order to support NRC review of this change, this submittal is organized as follows: |
| Therefore, the required plant specific justification of this implementation and significant hazards consideration are provided in this submittal. | | The implementation of WCAP-10271 and other related changes is documented in this. |
| ~, sst50tst08007tst sst5083i PDR ADOCK 05000244 PDR | | submittal as a separate license amendment request (LAR) with respect to the current Ginna Station Technical Specifications. Therefore, the required plant specific justification of this implementation and significant hazards consideration are provided in this submittal. |
| ~1~~P V V b.The implementation of WCAP-10271 and other related changes and the removal of WCAP-14333 with respect to Reference (a)is being provided for the marked up Ginna Station Technical Specifications only (i.e., Attachment A and B to Reference (a)has been revised to show the resulting differences). | | ~, |
| The necessary changes to the NUREG-1431 markups (Attachment D to Reference (a))and the proposed Improved Technical Specifications for Ginna Station (Attachment C to Reference (a))will be provided at a later date.Based on the above, the review of this submittal should be coordinated with the overall NRC review of the May 26, 1995 submittal since they are interrelated. | | sst50tst08007tst sst5083i PDR ADOCK 05000244 PDR |
| Very y yours, Robert C.Mecredy MDF 5749 Attachments References (a)Letter from R.C.Mecredy, RGAE, to A.R.Johnson, NRC, | | |
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| | P V V |
| | : b. The implementation of WCAP-10271 and other related changes and the removal of WCAP-14333 with respect to Reference (a) is being provided for the marked up Ginna Station Technical Specifications only (i.e., Attachment A and B to Reference (a) has been revised to show the resulting differences). The necessary changes to the NUREG-1431 markups (Attachment D to Reference (a)) and the proposed Improved Technical Specifications for Ginna Station (Attachment C to Reference (a)) willbe provided at a later date. |
| | Based on the above, the review of this submittal should be coordinated with the overall NRC review of the May 26, 1995 submittal since they are interrelated. |
| | Very y yours, Robert C. Mecredy MDF5749 Attachments References (a) Letter from R.C. Mecredy, RGAE, to A.R. Johnson, NRC, |
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| ==Subject:== | | ==Subject:== |
| Application for Amendment to Facility Operating License, Conversion to Improved Technical Specifications, dated May 26, 1995.(b)WCAP-14333, Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times, May 1995.(c)WCAP-10271-P-A, Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instnanentali on System, May 1986.(d)WCAP-10271-P-A, Supplement 1, Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System, May 1986.(e)WCAP-10271-P-A, Supplement 2, Revision 1, Evaluation of Surveillance Isrequencies and Out of Service Ti Ines for th'e Engineered Safety Features Actuation System, June 1990. 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 Mr.Carl Schulten Technical Specifications Branch (Mail Stop 011E22)Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Mr.Jim Andrachek Westinghouse Electric Company Energy Center East 4-1 4350 Northern Pike Monroeville, PA 15146-2886 Mr.Donald Hoffman EXCEL Services Corporation 11921 Rockville Pike Suite 100 Rockville, MD 20852}} | | Application for Amendment to Facility Operating License, Conversion to Improved Technical Specifications, dated May 26, 1995. |
| | (b) WCAP-14333, Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times, May 1995. |
| | (c) WCAP-10271-P-A, Evaluation ofSurveillance Frequencies and Out ofService Times for the Reactor Protection Instnanentali on System, May 1986. |
| | (d) WCAP-10271-P-A, Supplement 1, Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System, May 1986. |
| | (e) WCAP-10271-P-A, Supplement 2, Revision 1, Evaluation ofSurveillance Isrequencies and Out ofService Ti Ines for th'e Engineered Safety Features Actuation System, June 1990. |
| | |
| | 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 Mr. Carl Schulten Technical Specifications Branch (Mail Stop 011E22) |
| | Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Mr. Jim Andrachek Westinghouse Electric Company Energy Center East 4-1 4350 Northern Pike Monroeville, PA 15146-2886 Mr. Donald Hoffman EXCEL Services Corporation 11921 Rockville Pike Suite 100 Rockville, MD 20852}} |
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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
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Text
PRIORITY 1 (ACCELERATED RZDS PROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9509080079 DOC.DATE: 95/08/31 NOTARIZED: YES DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 P AUTH. NAME AUTHOR AFFILIATION Rochester Gas & Electric Corp.
MECREDY,R.C.
RECIP.NAME RECIPIENT AFFXLXATION JOHNSON,A.R.
SUBJECT:
Forwards application for amends to license DPR-18,proposing TS to implement WCAP-10271,its assoc suppl 6 other re changes w/respect to RTS 6 ESFAS. 0 DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal General Distribution Q ENCL + SIZE: 3 +l2, NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 I RECXPIENT =COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL XD CODE/NAME LTTR ENCL PD1-1 LA 1 1 PD1-1 PD 1 1 JO A 1 1 INTERNAL FILE C 01 1 1 NRR/DE/EMCB 1 1 DRCH/HICB- 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 0
C N
NOTE TO ALL "RZDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D8 (415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL 11
r, q
L 5
Aen ROCHESTER GAS AND ElECTRIC CORPORATION ~ 89 EASTAYENUE, ROCHESTER, M Y ld649-0001 AREA CODE7I6 5'-2700 ROBERT C. MECREDY Vice President Hvdeoroperotions August 31, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555
Subject:
Changes to Technical Specification Instrumentation Requirements Conversion to Improved Technical Specifications Rochester Gas 2 Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Johnson,
By Reference (a), RGB'roposed to convert the current Ginna Station Technical Specifications to the Improved Standard Technical Specifications (i.e., NUEEG-1431). Included within this conversion were numerous changes to the current requirements for the Reactor Trip System (RTS) and Engineered Safety Features Actuation System (ESFAS). Several of these changes were based if on Reference (b), which approved, would allow up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to place inoperable RTS and ESFAS channels in the tripped condition and allow the bypass of an inoperable channel for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Based on conversations with NRC staff RGEcE has agreed to defer these changes until after the conversion process since WCAP-14333 has not yet received staff review and approval. In place of the changes justified by WCAP-14333, RG&E proposes to implement those documented in References (c), (d), and (e) which have received NRC staff review and generic approval.
The purpose of this submittal is to provide the necessary justification to implement the changes to the RTS and ESFAS surveillance requirements and required actions as documented in WCAP-10271 and its supplements. In order to support NRC review of this change, this submittal is organized as follows:
The implementation of WCAP-10271 and other related changes is documented in this.
submittal as a separate license amendment request (LAR) with respect to the current Ginna Station Technical Specifications. Therefore, the required plant specific justification of this implementation and significant hazards consideration are provided in this submittal.
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sst50tst08007tst sst5083i PDR ADOCK 05000244 PDR
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- b. The implementation of WCAP-10271 and other related changes and the removal of WCAP-14333 with respect to Reference (a) is being provided for the marked up Ginna Station Technical Specifications only (i.e., Attachment A and B to Reference (a) has been revised to show the resulting differences). The necessary changes to the NUREG-1431 markups (Attachment D to Reference (a)) and the proposed Improved Technical Specifications for Ginna Station (Attachment C to Reference (a)) willbe provided at a later date.
Based on the above, the review of this submittal should be coordinated with the overall NRC review of the May 26, 1995 submittal since they are interrelated.
Very y yours, Robert C. Mecredy MDF5749 Attachments References (a) Letter from R.C. Mecredy, RGAE, to A.R. Johnson, NRC,
Subject:
Application for Amendment to Facility Operating License, Conversion to Improved Technical Specifications, dated May 26, 1995.
(b) WCAP-14333, Probabilistic Risk Analysis of the RPS and ESFAS Test Times and Completion Times, May 1995.
(c) WCAP-10271-P-A, Evaluation ofSurveillance Frequencies and Out ofService Times for the Reactor Protection Instnanentali on System, May 1986.
(d) WCAP-10271-P-A, Supplement 1, Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System, May 1986.
(e) WCAP-10271-P-A, Supplement 2, Revision 1, Evaluation ofSurveillance Isrequencies and Out ofService Ti Ines for th'e Engineered Safety Features Actuation System, June 1990.
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 Mr. Carl Schulten Technical Specifications Branch (Mail Stop 011E22)
Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector Mr. Jim Andrachek Westinghouse Electric Company Energy Center East 4-1 4350 Northern Pike Monroeville, PA 15146-2886 Mr. Donald Hoffman EXCEL Services Corporation 11921 Rockville Pike Suite 100 Rockville, MD 20852
