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See also: [[see also::IR 05000244/1997012]]


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{{#Wiki_filter:CATEGORY j.REGULATORY
{{#Wiki_filter:CATEGORY j.REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)05060235 DOC.DATE: 98/04/24 NOTARIZED:
INFORMATION
NO DOCKET¹ert Emmet Ginna Nuclear Plant Unit 1 Rochester G 05000244 ACCESSION NBR:98 FACIL:50-244 Rob AUTH.NICE.AUTHOR AFFILIATION
DISTRIBUTION
SYSTEM (RIDS)05060235 DOC.DATE: 98/04/24 NOTARIZED:
NO DOCKET¹ert Emmet Ginna Nuclear Plant Unit 1 Rochester G 05000244 ACCESSION NBR:98 FACIL:50-244
Rob AUTH.NICE.AUTHOR AFFILIATION
~~MECREDY,R.C.
~~MECREDY,R.C.
Rochester Gas&Electric Corp.RECIP.NAME
Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.
RECIPIENT AFFILIATION
DISTRIBUTION CODE: IEOID COPIES RECEIVED:LTR
VISSING,G.S.
\ENCL Z SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response  
DISTRIBUTION
 
CODE: IEOID COPIES RECEIVED:LTR
==SUBJECT:==
\ENCL Z SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice
Provides clarification for several statements made in NRC insp rept 50-244/97-12'td 980209.NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
of Violation Response SUBJECT: Provides clarification
05000244 E RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: AEOD/SPD/RAB DEDRO NRR/DRCH/HHFB NRR/DRPM/PERB OE DIR RGN1 FILE 01 COPIES LTTR ENCL RECIPIENT ZD CODE/NAME VISSZNG,G.
for several statements
NRR/DRPM/PECB NUDOCS-ABSTRACT OGC/HDS3 COPIES LTTR ENCL 0 EXTERNAL: LITCO BRYCE,J H NRC PDR NOAC NUDOCS FULLTEXT D 0 N 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 17 ENCL April 24, 1998 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555  
made in NRC insp rept 50-244/97-12'td
 
980209.NOTES:License
==Subject:==
Exp date in accordance
Ref.(1)(2)(3)(4)Clarification of Statements Made in NRC Inspection Report 50-244/97-12, dated February 9, 1998 NRC Integrated Inspection Report 50-244/97-12 and Notice of Violation, dated February 9, 1998 Letter from R.E.Smith, RGEE, to NRC,  
with 10CFR2,2.109(9/19/72).
 
05000244 E RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: AEOD/SPD/RAB
==Subject:==
DEDRO NRR/DRCH/HHFB
Response to NRC Request for Information Pursuant to 10CFR50.54(f)
NRR/DRPM/PERB
Regarding Adeqacy and Availability of Design Information R.E.Ginna Nuclear Power Plant, dated February 7, 1997 Letter from R.C.Mecredy, RG&E, to G.S.Vissing, NRC,.
OE DIR RGN1 FILE 01 COPIES LTTR ENCL RECIPIENT ZD CODE/NAME VISSZNG,G.
 
NRR/DRPM/PECB
==Subject:==
NUDOCS-ABSTRACT
Update to Response to NRC Request for Information Pursuant to 10CFR50.54(f)
OGC/HDS3 COPIES LTTR ENCL 0 EXTERNAL: LITCO BRYCE,J H NRC PDR NOAC NUDOCS FULLTEXT D 0 N NOTE TO ALL"RIDS" RECIPIENTS
Regarding Adequacy and Availability of Design Basis Information R.E.Ginna Nuclear Power Plant, dated September 30, 1997 Letter from'.C.Mecredy, RG6E, to NRC,  
PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION
 
REMOVED FROM DISTRIBUTION
==Subject:==
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 17 ENCL  
Submittal of Security Plan revision M, dated July 24, 1997  
April 24, 1998 U.S.Nuclear Regulatory
 
Commission
==Dear Mr.Vissing:==
Document Control Desk Attn: Guy S.Vissing Project Directorate
This letter is to provide clarification for several statements made in NRC Inspection Report 50-244/97-12.
I-1 Washington, D.C.20555 Subject: Ref.(1)(2)(3)(4)Clarification
of Statements
Made in NRC Inspection
Report 50-244/97-12, dated February 9, 1998 NRC Integrated
Inspection
Report 50-244/97-12
and Notice of Violation, dated February 9, 1998 Letter from R.E.Smith, RGEE, to NRC, Subject: Response to NRC Request for Information
Pursuant to 10CFR50.54(f)
Regarding Adeqacy and Availability
of Design Information
R.E.Ginna Nuclear Power Plant, dated February 7, 1997 Letter from R.C.Mecredy, RG&E, to G.S.Vissing, NRC,.Subject: Update to Response to NRC Request for Information
Pursuant to 10CFR50.54(f)
Regarding Adequacy and Availability
of Design Basis Information
R.E.Ginna Nuclear Power Plant, dated September 30, 1997 Letter from'.C.Mecredy, RG6E, to NRC, Subject: Submittal of Security Plan revision M, dated July 24, 1997 Dear Mr.Vissing: This letter is to provide clarification
for several statements
made in NRC Inspection
Report 50-244/97-12.
1)Statement:
1)Statement:
Section E1.3'D v page 14 states"The UFSAR verfication
Section E1.3'D v page 14 states"The UFSAR verfication project was scheduled to proceed in parallel with the validation of all other design basis source documents so that an electronic link of these yource documents to a living UFSAR could be accomplished by October 1998 for use during the DBD project." Clarification:
project was scheduled to proceed in parallel with the validation
The UFSAR verification project and design basis documentation project are not proceeding in parallel.This was explained in our letter dated September 30, 1997 (Reference 3).The UFSAR verfication and design basis documentation projects use some of the same resources; therefore, it was decided to concentrate on the UFSAR verification project until 9805060235 980424'DR ADQCK 05000244 8 PDR April 24, 1998 page 2 October 18, 1998 and then shift additional resources to the design basis documentation project.The links from the UFSAR to the source documents will not be completed until December 2001 as explained in Reference 3.'2)Statement:
of all other design basis source documents so that an electronic
Section E1.3 L'n D i n Ba'v'age 14 states"With the completion of the service water safety system functional inspection (SSFI)and the NRC design team inspection of Ginna, RG&E noted in the updated response letter of September 30, 1997, that they had completed the commitment to perform two SSFIs in 1997.RG&E indicated that they would perform a SSFI of the AFW system in 1998." 3)Clarification:
link of these yource documents to a living UFSAR could be accomplished
RG&E has determined we, should concentrate the majority of our resources on the Design Basis Documentation (DBD)and UFSAR verification projects described above, as well's closeout.of Motor-Operated Valve (GL89-10)and Service Water (GL89,-13) issues.Therefore, RG&E is not currently intending to perform an AFW system SSFI in 1998.Statement:
by October 1998 for use during the DBD project." Clarification:
Section ES F 1 V'n-2 Ev T m HQV-4~1 , page 17 states"The inspector noted that the licensee work in compiling a document of all variables used in the UFSAR Accident Analysis chapter was partially complete and was scheduled for completion by March 1, 1998, according to'OS598 in the licensee's Commitment and Action Tracking System (CATS)..." Clarification:
The UFSAR verification
The scope of the compilation of the major variables used in the UFSAR Accident Analysis chapter has been expanded to include additional items, such as accident and analysis assumptions, valve stroke times and setpoints.
project and design basis documentation
project are not proceeding
in parallel.This was explained in our letter dated September 30, 1997 (Reference
3).The UFSAR verfication
and design basis documentation
projects use some of the same resources;
therefore, it was decided to concentrate
on the UFSAR verification
project until 9805060235
980424'DR ADQCK 05000244 8 PDR  
April 24, 1998 page 2 October 18, 1998 and then shift additional
resources to the design basis documentation
project.The links from the UFSAR to the source documents will not be completed until December 2001 as explained in Reference 3.'2)Statement:
Section E1.3 L'n D i n Ba'v'age 14 states"With the completion
of the service water safety system functional
inspection (SSFI)and the NRC design team inspection
of Ginna, RG&E noted in the updated response letter of September 30, 1997, that they had completed the commitment
to perform two SSFIs in 1997.RG&E indicated that they would perform a SSFI of the AFW system in 1998." 3)Clarification:
RG&E has determined
we, should concentrate
the majority of our resources on the Design Basis Documentation (DBD)and UFSAR verification
projects described above, as well's closeout.of Motor-Operated
Valve (GL89-10)and Service Water (GL89,-13)
issues.Therefore, RG&E is not currently intending to perform an AFW system SSFI in 1998.Statement:
Section ES F 1 V'n-2 Ev T m HQV-4~1 , page 17 states"The inspector noted that the licensee work in compiling a document of all variables used in the UFSAR Accident Analysis chapter was partially complete and was scheduled for completion
by March 1, 1998, according to'OS598 in the licensee's
Commitment
and Action Tracking System (CATS)..." Clarification:
The scope of the compilation
of the major variables used in the UFSAR Accident Analysis chapter has been expanded to include additional
items, such as accident and analysis assumptions, valve stroke times and setpoints.
This effort is currently scheduled to be completed by June 30, 1998.Statement:
This effort is currently scheduled to be completed by June 30, 1998.Statement:
Section E8.2 v I 04~S rv'm R imiz'r W page 18 states"In addition to issues related to heat exchanger performance
Section E8.2 v I 04~S rv'm R imiz'r W page 18 states"In addition to issues related to heat exchanger performance testing and revision of the SWSROP, comments were made regards.ng the need to update the SW system hydraulic flow model since it under predicted flows in some cases.The licensee indicated that this work was being done in-house and was scheduled for completion by the end of January 1998." Clarification:
testing and revision of the SWSROP, comments were made regards.ng
Additional testing has been performed to better predict flows to the CRFC motor coolers.With the inclusion of this data, the SW system Hydraulic model is expected to be refined by June 16, 1998.
the need to update the SW system hydraulic flow model since it under predicted flows in some cases.The licensee indicated that this work was being done in-house and was scheduled for completion
by the end of January 1998." Clarification:
Additional
testing has been performed to better predict flows to the CRFC motor coolers.With the inclusion of this data, the SW system Hydraulic model is expected to be refined by June 16, 1998.  
April 24, 1998 Page 3 5)Statement:
April 24, 1998 Page 3 5)Statement:
Section S3 u'fe ua d P ur s page 23 states"The inspectors
Section S3 u'fe ua d P ur s page 23 states"The inspectors verified that selected changes to the Plan associated with the vehicle barrier system (VBS), as implemented, did not decrease the effectiveness of the Plan.Discussions with the licensee indicated that the plan was currently being reviewed and a plan revision would be submitted in accordance with the provisions of 10CFR 50.54(p)in the near future." Clarification:
verified that selected changes to the Plan associated
RGRE submitted a Security Plan revision M on July 24, 1997 (Refe'rence 4)which provided enhancement to the VBS.Also, RGGE submitted Security Plan revision N on January 15, 1998 although this revision was not related to the VBS.Very truly yours, Robert C.Mecredy GJWE498 xc: Mr.Guy S.Vissing (Mail Stop 14B2)Senior Project Manager Project Directorate I-1 Washington, D.C.20555 Mr.Hubert J.Miller U.S.Nuclear Regulatory Commission Regional Administrator, Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector}}
with the vehicle barrier system (VBS), as implemented, did not decrease the effectiveness
of the Plan.Discussions
with the licensee indicated that the plan was currently being reviewed and a plan revision would be submitted in accordance
with the provisions
of 10CFR 50.54(p)in the near future." Clarification:
RGRE submitted a Security Plan revision M on July 24, 1997 (Refe'rence
4)which provided enhancement
to the VBS.Also, RGGE submitted Security Plan revision N on January 15, 1998 although this revision was not related to the VBS.Very truly yours, Robert C.Mecredy GJWE498 xc: Mr.Guy S.Vissing (Mail Stop 14B2)Senior Project Manager Project Directorate
I-1 Washington, D.C.20555 Mr.Hubert J.Miller U.S.Nuclear Regulatory
Commission
Regional Administrator, Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector
}}

Revision as of 13:15, 17 August 2019

Provides Clarification for Several Statements Made in NRC Insp Rept 50-244/97-12 Dtd 980209
ML17265A248
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/24/1998
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Vissing G
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
50-244-97-12, NUDOCS 9805060235
Download: ML17265A248 (4)
v • d • e


Text

CATEGORY j.REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)05060235 DOC.DATE: 98/04/24 NOTARIZED:

NO DOCKET¹ert Emmet Ginna Nuclear Plant Unit 1 Rochester G 05000244 ACCESSION NBR:98 FACIL:50-244 Rob AUTH.NICE.AUTHOR AFFILIATION

~~MECREDY,R.C.

Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S.

DISTRIBUTION CODE: IEOID COPIES RECEIVED:LTR

\ENCL Z SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response

SUBJECT:

Provides clarification for several statements made in NRC insp rept 50-244/97-12'td 980209.NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244 E RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: AEOD/SPD/RAB DEDRO NRR/DRCH/HHFB NRR/DRPM/PERB OE DIR RGN1 FILE 01 COPIES LTTR ENCL RECIPIENT ZD CODE/NAME VISSZNG,G.

NRR/DRPM/PECB NUDOCS-ABSTRACT OGC/HDS3 COPIES LTTR ENCL 0 EXTERNAL: LITCO BRYCE,J H NRC PDR NOAC NUDOCS FULLTEXT D 0 N 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 17 ENCL April 24, 1998 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555

Subject:

Ref.(1)(2)(3)(4)Clarification of Statements Made in NRC Inspection Report 50-244/97-12, dated February 9, 1998 NRC Integrated Inspection Report 50-244/97-12 and Notice of Violation, dated February 9, 1998 Letter from R.E.Smith, RGEE, to NRC,

Subject:

Response to NRC Request for Information Pursuant to 10CFR50.54(f)

Regarding Adeqacy and Availability of Design Information R.E.Ginna Nuclear Power Plant, dated February 7, 1997 Letter from R.C.Mecredy, RG&E, to G.S.Vissing, NRC,.

Subject:

Update to Response to NRC Request for Information Pursuant to 10CFR50.54(f)

Regarding Adequacy and Availability of Design Basis Information R.E.Ginna Nuclear Power Plant, dated September 30, 1997 Letter from'.C.Mecredy, RG6E, to NRC,

Subject:

Submittal of Security Plan revision M, dated July 24, 1997

Dear Mr.Vissing:

This letter is to provide clarification for several statements made in NRC Inspection Report 50-244/97-12.

1)Statement:

Section E1.3'D v page 14 states"The UFSAR verfication project was scheduled to proceed in parallel with the validation of all other design basis source documents so that an electronic link of these yource documents to a living UFSAR could be accomplished by October 1998 for use during the DBD project." Clarification:

The UFSAR verification project and design basis documentation project are not proceeding in parallel.This was explained in our letter dated September 30, 1997 (Reference 3).The UFSAR verfication and design basis documentation projects use some of the same resources; therefore, it was decided to concentrate on the UFSAR verification project until 9805060235 980424'DR ADQCK 05000244 8 PDR April 24, 1998 page 2 October 18, 1998 and then shift additional resources to the design basis documentation project.The links from the UFSAR to the source documents will not be completed until December 2001 as explained in Reference 3.'2)Statement:

Section E1.3 L'n D i n Ba'v'age 14 states"With the completion of the service water safety system functional inspection (SSFI)and the NRC design team inspection of Ginna, RG&E noted in the updated response letter of September 30, 1997, that they had completed the commitment to perform two SSFIs in 1997.RG&E indicated that they would perform a SSFI of the AFW system in 1998." 3)Clarification:

RG&E has determined we, should concentrate the majority of our resources on the Design Basis Documentation (DBD)and UFSAR verification projects described above, as well's closeout.of Motor-Operated Valve (GL89-10)and Service Water (GL89,-13) issues.Therefore, RG&E is not currently intending to perform an AFW system SSFI in 1998.Statement:

Section ES F 1 V'n-2 Ev T m HQV-4~1 , page 17 states"The inspector noted that the licensee work in compiling a document of all variables used in the UFSAR Accident Analysis chapter was partially complete and was scheduled for completion by March 1, 1998, according to'OS598 in the licensee's Commitment and Action Tracking System (CATS)..." Clarification:

The scope of the compilation of the major variables used in the UFSAR Accident Analysis chapter has been expanded to include additional items, such as accident and analysis assumptions, valve stroke times and setpoints.

This effort is currently scheduled to be completed by June 30, 1998.Statement:

Section E8.2 v I 04~S rv'm R imiz'r W page 18 states"In addition to issues related to heat exchanger performance testing and revision of the SWSROP, comments were made regards.ng the need to update the SW system hydraulic flow model since it under predicted flows in some cases.The licensee indicated that this work was being done in-house and was scheduled for completion by the end of January 1998." Clarification:

Additional testing has been performed to better predict flows to the CRFC motor coolers.With the inclusion of this data, the SW system Hydraulic model is expected to be refined by June 16, 1998.

April 24, 1998 Page 3 5)Statement:

Section S3 u'fe ua d P ur s page 23 states"The inspectors verified that selected changes to the Plan associated with the vehicle barrier system (VBS), as implemented, did not decrease the effectiveness of the Plan.Discussions with the licensee indicated that the plan was currently being reviewed and a plan revision would be submitted in accordance with the provisions of 10CFR 50.54(p)in the near future." Clarification:

RGRE submitted a Security Plan revision M on July 24, 1997 (Refe'rence 4)which provided enhancement to the VBS.Also, RGGE submitted Security Plan revision N on January 15, 1998 although this revision was not related to the VBS.Very truly yours, Robert C.Mecredy GJWE498 xc: Mr.Guy S.Vissing (Mail Stop 14B2)Senior Project Manager Project Directorate I-1 Washington, D.C.20555 Mr.Hubert J.Miller U.S.Nuclear Regulatory Commission Regional Administrator, Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector

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