ML17261B148: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:ACCELERATED DIS RIBUTION DEMONSTRATION SYSTEM r i~g~4 REGULATORY INFORMATXON DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9009100295 DOC.DATE: 90/08/28 NOTARIZED:
{{#Wiki_filter:ACCELERATED DIS RIBUTION DEMONSTRATION SYSTEM r i
NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
          ~   g ~
Rochester Gas&Electric Corp.RECXP.NAME RECIPIENT AFFXLIATION JOHNSON,A.R.
4 REGULATORY INFORMATXON DISTRIBUTION SYSTEM (RIDS)
Project Directorate I-3 DOCKET 05000244 R$05000244 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
ACCESSION NBR:9009100295                   DOC.DATE: 90/08/28       NOTARIZED: NO       DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester                     G 05000244 AUTH. NAME                 AUTHOR AFFILIATION MECREDY,R.C.               Rochester Gas & Electric Corp.
RECXP.NAME                 RECIPIENT AFFXLIATION JOHNSON,A.R.                   Project Directorate I-3                                           R


==SUBJECT:==
==SUBJECT:==
Lists understanding of issues util planning to address re I containment integrity,per 900718 telcon.DISTRIBUTXON CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:
Lists understanding of issues util planning to address re                         I containment integrity,per 900718 telcon.
General Distribution RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: NRR/DET/ECMB 9H NRR/DST 8E2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS2 RES/DSXR/EIB EXTERNAL: NRC PDR COPIES LTTR ENCL RECIPXENT ID CODE/NAME PD1-3 PD NRR/DOEA/OTS B1 1 NRR/DST/SELB 8D NRR/DST/SRXB 8E OC/LFMB.~~IaQEeenmee~
DISTRIBUTXON CODE: A001D               COPIES RECEIVED:LTR         ENCL     SIZE:
0i~NSIC COPIES LTTR ENCL D D a (>gg)q~)~~R D$NOTE TO ALL"RIDS" RECIPIENTS:
TITLE:     OR   Submittal: General Distribution                                                 $
PLEASE HELP US TO REDUCE iVASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL A D D N I I i 4)~ZuZu//'I//I/////////
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).                        05000244 RECIPIENT               COPIES            RECIPXENT          COPIES ID  CODE/NAME            LTTR ENCL        ID CODE/NAME     LTTR ENCL PD1-3 LA                                   PD1-3 PD                                D JOHNSON,A D
/I///I I////I///I
INTERNAL: NRR/DET/ECMB 9H                                 NRR/DOEA/OTS B1 1 NRR/DST            8E2                      NRR/DST/SELB 8D NRR/DST/SICB 7E                            NRR/DST/SRXB 8E NUDOCS-ABSTRACT                            OC/LFMB OGC/HDS2                                      .~~IaQEeenmee~ 0i ~
/////Z//ZSF/ROCHESTER GAS AND ELECTRIC CORPORATION HEW Liil Oalla I'i TOE@STATE 4 89 EAST AVENUE, ROCHESTER N.Y.14649-0001 ROBERT C MECREDY Vice Ptesldent Clnna Nuclear Ptoduction TELEPHONE AREA CODE 71B 546 2700 August 28, 1990 U.S.Nuclear Regulatory Commission Attention:
RES/DSXR/EIB EXTERNAL: NRC PDR                                        NSIC a
Allen R.Johnson Project Directorate I-3 Document Control Desk Washington, D.C.20555  
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R D
                                                                                                  $
A D
D NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR                   17   ENCL
 
N I
I
 
i 4 ) ~
ZuZu//'I     //I/////////                                                                 LiilOalla      HEW I        'i  TOE@
                      /I// /I     I////I///I
                  /////Z       //ZSF/                                                                                         STATE ROCHESTER GAS AND ELECTRIC CORPORATION                           4 89 EAST AVENUE, ROCHESTER   N. Y. 14649-0001 ROBERT C MECREDY                                                                                   TELEPHONE Vice Ptesldent                                                                               AREA CODE 71B 546 2700 Clnna Nuclear Ptoduction August 28, 1990 U.S. Nuclear Regulatory Commission Attention: Allen R. Johnson Project Directorate I-3 Document                       Control Desk Washington, D.C.                             20555


==Subject:==
==Subject:==
Containment Integrity R.E.Ginna Nuclear Power Plant Docket No.50-244  
Containment   Integrity R. E. Ginna Nuclear Power         Plant Docket No. 50-244
 
==Dear Mr. Johnson:==


==Dear Mr.Johnson:==
In letters dated July 11, 1990 and August 15, 1990, RG&E provided to the NRC our proposed course of action for resolution of containment issues. Based on this correspondence, and a July 18, 1990 conference call between the NRC and RG&E, the following is a tabulation of our understanding of the issues that RG&E is planning to address relative to the integrity of the Ginna Station Containment.
In letters dated July 11, 1990 and August 15, 1990, RG&E provided to the NRC our proposed course of action for resolution of containment issues.Based on this correspondence, and a July 18, 1990 conference call between the NRC and RG&E, the following is a tabulation of our understanding of the issues that RG&E is planning to address relative to the integrity of the Ginna Station Containment.
: 1.                 Take expeditious steps to remove the standing water from the containment annular access area, and maintain it dry.
1.Take expeditious steps to remove the standing water from the containment annular access area, and maintain it dry.2.Relative to the structural detail between the cylin-drical wall of the containment and the basemat, verify when and if sliding will occur under design load con-ditions.Also evaluate the effects of no sliding on wall stresses.3.Determine the effects of the bellows on the function of the tendons.Consider the bellows performing or not performing their design intent.4.Determine the capability of the tension rods to perform their functions, and assess the margins associated with this system.9009100295 900S28 PDR ADOCK 05000244 P PDI Te(P+)Pl lf (pg l" 5.Perform an assessment of the following boundary condi-tions on the overall joint design.a.Sliding condition with hinge connection.
: 2.                 Relative to the structural detail between the cylin-drical wall of the containment and the basemat, verify when and if sliding will occur under design load con-ditions. Also evaluate the effects of no sliding on wall stresses.
b.Non-sliding condition with hinge connection.
: 3.                 Determine the effects of the bellows on the function of the tendons. Consider the bellows performing or not performing their   design intent.
c.Partially fixed base for a and b above.6.Investigate all above issues, considering appropriate seismic and LOCA load combinations.
: 4.                 Determine the   capability of the tension rods to perform their functions,   and assess the margins associated with this system.
7.Provide a copy of GAI Report I2347"Containment Building Tendon Investigation", and the results of the chemical analysis of the groundwater at Ginna to the NRC.We understand that the NRC will make a site visit to Ginna Station on September 5 and 6, 1990.Any concerns or action items different from those listed above should be provided to RGGE prior to that time.Very truly yours, LAS/155 Robert C.Mecr y xc: Mr.Allen R.Johnson (Mail Stop 14D1)Project Directorate I-3 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector}}
9009100295 900S28 PDR P
ADOCK 05000244 PDI Te(   P+         l")Pl lf (pg
: 5. Perform an assessment     of the following boundary condi-tions on the overall     joint design.
: a. Sliding condition with hinge connection.
: b. Non-sliding condition with hinge connection.
: c. Partially fixed base for a and b above.
: 6. Investigate all above issues, considering appropriate seismic and   LOCA load combinations.
: 7. Provide a copy   of GAI Report I2347 "Containment Building Tendon   Investigation", and the results of the chemical analysis of the groundwater at Ginna to the NRC.
We understand that the NRC will make a site visit to Ginna Station on September 5 and 6, 1990. Any concerns or action items different from those listed above should be provided to RGGE prior to that time.
Very truly yours, Robert C. Mecr y LAS/155 xc:   Mr. Allen R. Johnson (Mail Stop     14D1)
Project Directorate I-3 Washington, D.C.     20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia,   PA   19406 Ginna Senior Resident Inspector}}

Revision as of 17:48, 29 October 2019

Lists Understanding of Issues Util Planning to Address Re Containment Integrity,Per 900718 Telcon.Any Concerns or Action Items Different from Listed Submittal Should Be Provided to Util Prior to NRC 900905 & 06 Visit to Plant
ML17261B148
Person / Time
Site: Ginna Constellation icon.png
Issue date: 08/28/1990
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Andrea Johnson
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9009100295
Download: ML17261B148 (4)


Text

ACCELERATED DIS RIBUTION DEMONSTRATION SYSTEM r i

~ g ~

4 REGULATORY INFORMATXON DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9009100295 DOC.DATE: 90/08/28 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.

RECXP.NAME RECIPIENT AFFXLIATION JOHNSON,A.R. Project Directorate I-3 R

SUBJECT:

Lists understanding of issues util planning to address re I containment integrity,per 900718 telcon.

DISTRIBUTXON CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution $

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPXENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 LA PD1-3 PD D JOHNSON,A D

INTERNAL: NRR/DET/ECMB 9H NRR/DOEA/OTS B1 1 NRR/DST 8E2 NRR/DST/SELB 8D NRR/DST/SICB 7E NRR/DST/SRXB 8E NUDOCS-ABSTRACT OC/LFMB OGC/HDS2 .~~IaQEeenmee~ 0i ~

RES/DSXR/EIB EXTERNAL: NRC PDR NSIC a

( >gg) q~) ~~

R D

$

A D

D NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL

N I

I

i 4 ) ~

ZuZu//'I //I///////// LiilOalla HEW I 'i TOE@

/I// /I I////I///I

/////Z //ZSF/ STATE ROCHESTER GAS AND ELECTRIC CORPORATION 4 89 EAST AVENUE, ROCHESTER N. Y. 14649-0001 ROBERT C MECREDY TELEPHONE Vice Ptesldent AREA CODE 71B 546 2700 Clnna Nuclear Ptoduction August 28, 1990 U.S. Nuclear Regulatory Commission Attention: Allen R. Johnson Project Directorate I-3 Document Control Desk Washington, D.C. 20555

Subject:

Containment Integrity R. E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

In letters dated July 11, 1990 and August 15, 1990, RG&E provided to the NRC our proposed course of action for resolution of containment issues. Based on this correspondence, and a July 18, 1990 conference call between the NRC and RG&E, the following is a tabulation of our understanding of the issues that RG&E is planning to address relative to the integrity of the Ginna Station Containment.

1. Take expeditious steps to remove the standing water from the containment annular access area, and maintain it dry.
2. Relative to the structural detail between the cylin-drical wall of the containment and the basemat, verify when and if sliding will occur under design load con-ditions. Also evaluate the effects of no sliding on wall stresses.
3. Determine the effects of the bellows on the function of the tendons. Consider the bellows performing or not performing their design intent.
4. Determine the capability of the tension rods to perform their functions, and assess the margins associated with this system.

9009100295 900S28 PDR P

ADOCK 05000244 PDI Te( P+ l")Pl lf (pg

5. Perform an assessment of the following boundary condi-tions on the overall joint design.
a. Sliding condition with hinge connection.
b. Non-sliding condition with hinge connection.
c. Partially fixed base for a and b above.
6. Investigate all above issues, considering appropriate seismic and LOCA load combinations.
7. Provide a copy of GAI Report I2347 "Containment Building Tendon Investigation", and the results of the chemical analysis of the groundwater at Ginna to the NRC.

We understand that the NRC will make a site visit to Ginna Station on September 5 and 6, 1990. Any concerns or action items different from those listed above should be provided to RGGE prior to that time.

Very truly yours, Robert C. Mecr y LAS/155 xc: Mr. Allen R. Johnson (Mail Stop 14D1)

Project Directorate I-3 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector