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


=Text=
=Text=
{{#Wiki_filter:CATEGORY j.REGULATORY
{{#Wiki_filter:CATEGORY j.
INFORMATION
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION
ACCESSION NBR:98 05060235           DOC.DATE: 98/04/24         NOTARIZED: NO             DOCKET   ¹ FACIL:50-244 Rob ert Emmet Ginna Nuclear Plant Unit 1 Rochester                     G   05000244 AUTH. NICE .
SYSTEM (RIDS)05060235 DOC.DATE: 98/04/24 NOTARIZED:
        ~                AUTHOR AFFILIATION MECREDY,R.C.         Rochester Gas & Electric Corp.
NO DOCKET¹ert Emmet Ginna Nuclear Plant Unit 1 Rochester G 05000244 ACCESSION NBR:98 FACIL:50-244
RECIP.NAME
Rob AUTH.NICE.AUTHOR AFFILIATION
          ~              RECIPIENT AFFILIATION VISSING,G.S.
~~MECREDY,R.C.
 
Rochester Gas&Electric Corp.RECIP.NAME
==SUBJECT:==
RECIPIENT AFFILIATION
Provides clarification for several statements               made   in NRC insp rept 50-244/97-12'td 980209.
VISSING,G.S.
DISTRIBUTION CODE: IEOID COPIES RECEIVED:LTR \ ENCL TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response Z    SIZE:
DISTRIBUTION
NOTES:License Exp date        in accordance with 10CFR2,2.109(9/19/72).                  05000244 E
CODE: IEOID COPIES RECEIVED:LTR
RECIPIENT            COPIES             RECIPIENT             COPIES ID CODE/NAME         LTTR ENCL          ZD CODE/NAME          LTTR ENCL PD1-1 PD                                VISSZNG,G.                                       0 INTERNAL: AEOD/SPD/RAB DEDRO NRR/DRCH/HHFB                          NRR/DRPM/PECB NRR/DRPM/PERB                          NUDOCS-ABSTRACT OE DIR                                  OGC/HDS3 RGN1    FILE    01 EXTERNAL: LITCO BRYCE,J H                           NOAC NRC PDR                                 NUDOCS FULLTEXT D
\ENCL Z SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice
0 N
of Violation Response SUBJECT: Provides clarification
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
for several statements
 
made in NRC insp rept 50-244/97-12'td
April   24, 1998 U. S. Nuclear Regulatory Commission Document   Control Desk Attn:       Guy S.           Vissing Project Directorate I-1 Washington,             D.C. 20555
980209.NOTES:License
 
Exp date in accordance
==Subject:==
with 10CFR2,2.109(9/19/72).
Clarification of           Statements Made   in NRC Inspection Report 50-244/97-12, dated February 9, 1998 Ref . (1)    NRC         Integrated Inspection Report 50-244/97-12 and Notice of Violation, dated February 9, 1998 (2)    Letter from R.E. Smith, RGEE, to NRC,  
05000244 E RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: AEOD/SPD/RAB
 
DEDRO NRR/DRCH/HHFB
==Subject:==
NRR/DRPM/PERB
 
OE DIR RGN1 FILE 01 COPIES LTTR ENCL RECIPIENT ZD CODE/NAME VISSZNG,G.
===Response===
NRR/DRPM/PECB
to NRC Request for Information Pursuant to 10CFR50.54(f)
NUDOCS-ABSTRACT
Regarding Adeqacy and Availability of Design Information R.E. Ginna Nuclear Power Plant, dated February 7, 1997 (3)    Letter from R.C. Mecredy, RG&E, to G.S. Vissing, NRC,.
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
==Subject:==
REMOVED FROM DISTRIBUTION
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 (4)    Letter from'.C.                 Mecredy,   RG6E,   to   NRC,  
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
==Subject:==
Commission
 
Document Control Desk Attn: Guy S.Vissing Project Directorate
Submittal of Security Plan revision               M,   dated July 24, 1997
I-1 Washington, D.C.20555 Subject: Ref.(1)(2)(3)(4)Clarification
 
of Statements
==Dear Mr. Vissing:==
Made in NRC Inspection
 
Report 50-244/97-12, dated February 9, 1998 NRC Integrated
This letter is to provide clarification for several statements                   made in NRC Inspection Report 50-244/97-12.
Inspection
: 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."
Report 50-244/97-12
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 05000244 980424'DR ADQCK 8                         PDR
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)
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.
Regarding Adeqacy and Availability
'2)     Statement: Section E1.3 L'               n D i n Ba 14 states     "With the completion of the service water
of Design Information
                                                              'v'age 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."
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
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 closeout of Motor-Operated Valve (GL89-10) and Service well's Water (GL89,-13) issues.           Therefore, RG&E is not currently intending to perform an AFW system SSFI in 1998.
Pursuant to 10CFR50.54(f)
: 3)    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 in the licensee's Commitment and Action Tracking System         to'OS598 (CATS)..."
Regarding Adequacy and Availability
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
of Design Basis Information
                                                                        'r effort is currently scheduled to be completed by June 30, 1998.
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
Statement: Section E8.2                       v   I 04 ~
for several statements
S rv'                   m R               imiz 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."
made in NRC Inspection
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.
Report 50-244/97-12.
 
1)Statement:
April Page 5) 3 24, 1998 Statement:
Section E1.3'D v page 14 states"The UFSAR verfication
selected barrier Section   S3     u 'fe         ua d P   ur s page 23 states "The inspectors verified that changes to the Plan associated with the vehicle 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."
project was scheduled to proceed in parallel with the validation
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.
of all other design basis source documents so that an electronic
Very truly yours, Robert C. Mecredy GJWE498 xc:    Mr. Guy S. Vissing (Mail Stop 14B2)
link of these yource documents to a living UFSAR could be accomplished
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}}
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
}}

Latest revision as of 09:14, 4 February 2020

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)

ACCESSION NBR:98 05060235 DOC.DATE: 98/04/24 NOTARIZED: NO DOCKET ¹ FACIL:50-244 Rob ert Emmet Ginna Nuclear Plant Unit 1 Rochester G 05000244 AUTH. NICE .

~ AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.

RECIP.NAME

~ RECIPIENT AFFILIATION VISSING,G.S.

SUBJECT:

Provides clarification for several statements made in NRC insp rept 50-244/97-12'td 980209.

DISTRIBUTION CODE: IEOID COPIES RECEIVED:LTR \ ENCL TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response Z SIZE:

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 E

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ZD CODE/NAME LTTR ENCL PD1-1 PD VISSZNG,G. 0 INTERNAL: AEOD/SPD/RAB DEDRO NRR/DRCH/HHFB NRR/DRPM/PECB NRR/DRPM/PERB NUDOCS-ABSTRACT OE DIR OGC/HDS3 RGN1 FILE 01 EXTERNAL: LITCO BRYCE,J H NOAC NRC PDR 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:

Clarification of Statements Made in NRC Inspection Report 50-244/97-12, dated February 9, 1998 Ref . (1) NRC Integrated Inspection Report 50-244/97-12 and Notice of Violation, dated February 9, 1998 (2) 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 (3) 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 (4) 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 05000244 980424'DR ADQCK 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 14 states "With the completion of the service water

'v'age 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."

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 closeout of Motor-Operated Valve (GL89-10) and Service well's Water (GL89,-13) issues. Therefore, RG&E is not currently intending to perform an AFW system SSFI in 1998.

3) 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 in the licensee's Commitment and Action Tracking System to'OS598 (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

'r effort is currently scheduled to be completed by June 30, 1998.

Statement: Section E8.2 v I 04 ~

S rv' m R imiz 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 Page 5) 3 24, 1998 Statement:

selected barrier Section S3 u 'fe ua d P ur s page 23 states "The inspectors verified that changes to the Plan associated with the vehicle 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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