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| {{#Wiki_filter:CATEGORY j.REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)05060235 DOC.DATE: 98/04/24 NOTARIZED: | | {{#Wiki_filter:CATEGORY j. |
| NO DOCKET¹ert Emmet Ginna Nuclear Plant Unit 1 Rochester G 05000244 ACCESSION NBR:98 FACIL:50-244 Rob AUTH.NICE.AUTHOR AFFILIATION | | REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| ~~MECREDY,R.C.
| | 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 . |
| Rochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION VISSING,G.S. | | ~ AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp. |
| DISTRIBUTION CODE: IEOID COPIES RECEIVED:LTR
| | RECIP.NAME |
| \ENCL Z SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response
| | ~ RECIPIENT AFFILIATION VISSING,G.S. |
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| ==SUBJECT:== | | ==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). | | Provides clarification for several statements made in NRC insp rept 50-244/97-12'td 980209. |
| 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. | | DISTRIBUTION CODE: IEOID COPIES RECEIVED:LTR \ ENCL TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response Z SIZE: |
| 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 | | 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 |
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| ==Subject:== | | ==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,
| | 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, |
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| ==Subject:== | | ==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,. | | ===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,. |
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| ==Subject:== | | ==Subject:== |
| Update to Response to NRC Request for Information Pursuant to 10CFR50.54(f) | | 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, |
| 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, | |
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| ==Subject:== | | ==Subject:== |
| Submittal of Security Plan revision M, dated July 24, 1997
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| ==Dear Mr.Vissing:== | | Submittal of Security Plan revision M, dated July 24, 1997 |
| This letter is to provide clarification for several statements made in NRC Inspection Report 50-244/97-12. | | |
| 1)Statement: | | ==Dear Mr. Vissing:== |
| 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: | | This letter is to provide clarification for several statements made in NRC Inspection Report 50-244/97-12. |
| 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: | | : 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." |
| 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: | | 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 |
| 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. | | 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. |
| This effort is currently scheduled to be completed by June 30, 1998.Statement:
| | '2) Statement: Section E1.3 L' n D i n Ba 14 states "With the completion of the service water |
| 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: | | '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." |
| 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. | | 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. |
| April 24, 1998 Page 3 5)Statement: | | : 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)..." |
| 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: | | 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 |
| 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}} | | '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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Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment
ML17265A6741999-06-15015 June 1999
Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT
ML17265A6751999-06-11011 June 1999
Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification
ML17309A6551999-06-0707 June 1999
Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment
ML17265A6671999-06-0101 June 1999
Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301
ML17265A6641999-05-25025 May 1999
Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested
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
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
