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{{#Wiki_filter:e-e | {{#Wiki_filter:e-e July 29, 1988 Docket No. 50-601 | ||
July 29, 1988 Docket No. 50-601 | |||
{ | { | ||
Hr. David Ward, Chairman Subcomittee on Advanced Pressurized Water Reactors (Westinghouse and Combustion Engineering) | Hr. David Ward, Chairman Subcomittee on Advanced Pressurized Water Reactors (Westinghouse and Combustion Engineering) | ||
Advisory Committee on Reactor Safeguards United States Nuclear Regulatory Commission Washington, D.C. 20555 | Advisory Committee on Reactor Safeguards United States Nuclear Regulatory Commission Washington, D.C. | ||
20555 | |||
==Dear Mr. Ward:== | ==Dear Mr. Ward:== | ||
==SUBJECT:== | ==SUBJECT:== | ||
BNL REPORTS REGARDING PROBABILISTIC SAFETY STUDY FOR THE RESAR SP/90 As part of our ongoing review of Westinghouse's application for a Preliminary Design Approval (PDA) for the RESAR SP/90 Advanced PWR, we contracted with Brookhaven National Laboratory (BNL) to assist us in our review of Module 16, "Probabilistic Safety Study." As part of this effort, BNL has prepared the attached NUREG/CR 5177, Volurres 1 and 2, entitled "A Review of the WAPWR Probabilistic Safety Study (Internal Events, Core Damage Frequency)" snd "A Review of the WAPWR Probabilistic Safety Study (Internal Events, Containment Response, and Offsite Consequences)," respectively. | BNL REPORTS REGARDING PROBABILISTIC SAFETY STUDY FOR THE RESAR SP/90 As part of our ongoing review of Westinghouse's application for a Preliminary Design Approval (PDA) for the RESAR SP/90 Advanced PWR, we contracted with Brookhaven National Laboratory (BNL) to assist us in our review of Module 16, "Probabilistic Safety Study." As part of this effort, BNL has prepared the attached NUREG/CR 5177, Volurres 1 and 2, entitled "A Review of the WAPWR Probabilistic Safety Study (Internal Events, Core Damage Frequency)" snd "A Review of the WAPWR Probabilistic Safety Study (Internal Events, Containment Response, and Offsite Consequences)," respectively. | ||
We are providing these reports to assist you in understanding the concerns of the staff and our contractor. | We are providing these reports to assist you in understanding the concerns of the staff and our contractor. | ||
Note that some of the material contained in these enclosures are considered to be proprietary and, therefore, is being withheld from public disclosure per 10 CFR 2.740. If you have any questions concerning this matter, please contact Tom Kenyon at (301) 492-1120. | Note that some of the material contained in these enclosures are considered to be proprietary and, therefore, is being withheld from public disclosure per 10 CFR 2.740. | ||
If you have any questions concerning this matter, please contact Tom Kenyon at (301) 492-1120. | |||
Sincerely, Original Signed By: | Sincerely, Original Signed By: | ||
Charles L. Itiller, Acting Director 8800170056 080729 | Charles L. Itiller, Acting Director 8800170056 080729 Standardization and Non-Power PDR ADOCK 05000601 Reactor Project Directorate A | ||
PNU Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation Enriosures: | |||
As stated PFPI DISTRIBUTION: | As stated PFPI DISTRIBUTION: | ||
W/ Enclosure Docket File ' | W/ Enclosure Docket File ' | ||
W/0 Enclosure NRC PDRs | g g | ||
PDSNP Reading | i TXenyon ACRS (10) | ||
DCru[tchfield | W/0 Enclosure NRC PDRs LRubenstein DPersinko MCunningham PDSNP Reading EHylton EJordan HVandermolen i | ||
f DCru[tchfield EShomaker 0GC BGrines b~~ | |||
on | EChelliah 1 | ||
f;Ijk N | |||
PDSgTI OC PI58 PDSNP | |||
^ | |||
on TXe iT: 1s nomAker DPersinkh Citiller 07 | |||
/88 07/ /88 07/pf88 07/;j/88 07 M /88 7 | |||
#eno:\\~ | |||
UNITED STATES NUCLEAR REGULATORY COMMISSION y | |||
WASHINGTON, D. C. 20604 July 29, 1988 Docket No. 50-601 Mr. David Ward, Chairman Subcomittee on Advanced Pressurized Water Reactors (Westinghouse and Combustion Engineering) | |||
Advisory Comittee on Reactor Safeguards United States Nuclear Regulatory Comission Washington, D.C. 20555 | Advisory Comittee on Reactor Safeguards United States Nuclear Regulatory Comission Washington, D.C. | ||
20555 | |||
==Dear Mr. Ward:== | ==Dear Mr. Ward:== | ||
==SUBJECT:== | ==SUBJECT:== | ||
BNL REPORTS REGARDING PROBABILISTIC SAFETY STUDY FOR THE RESAR SP/90 | BNL REPORTS REGARDING PROBABILISTIC SAFETY STUDY FOR THE RESAR SP/90 As part of our ongoing review of Westinghouse's application for a Preliminary Design Approval (PDA) for the RESAR SP/90 Advanced PWR, we contracted with Brookhaven National Laboratory (BNL) to assist us in our review of Module 16 "Probabilistic Safety Study." As part of this effort BNL has prepared the attached NUREG/CR 5177, Volumes 1 and 2, entitled "A Review of the WAPhR Probabilistic Safety Study (Internal Events, Core Damage Frac;uency)" and "A Review of the WAPWR Probabilistic Safety Study (Internal Events, Containment Response, and Offsite Consegaences)." respectively. | ||
As part of our ongoing review of Westinghouse's application for a Preliminary Design Approval (PDA) for the RESAR SP/90 Advanced PWR, we contracted with Brookhaven National Laboratory (BNL) to assist us in our review of Module 16 "Probabilistic Safety Study." As part of this effort BNL has prepared the attached NUREG/CR 5177, Volumes 1 and 2, entitled "A Review of the WAPhR | |||
^ | ^ | ||
We are providing these reports to assist you in understanding the concerns of | We are providing these reports to assist you in understanding the concerns of t | ||
Note that some of the material contained in these enclosures are considered to | the staff and our contractor. | ||
Sincerely, CAA.a l | Note that some of the material contained in these enclosures are considered to i | ||
IV, Y and Special Projects | be prcprietary and, therefore, is being withheld from public disclosure per 10 CFR 2.740. | ||
Office of Nuclear Reactor Regulation | If you have any questions concerning this matter, please contact Tom Kenyon at (301) 492-1120. | ||
Sincerely, CAA.a l r | |||
Charles L. Miller, Acting Director Standardization and Non-Power i | |||
Reactor Project Directorate Division of Reactor Projects III. | |||
IV, Y and Special Projects Office of Nuclear Reactor Regulation i | |||
l | |||
==Enclosures:== | ==Enclosures:== | ||
As stated 1 | |||
i l | |||
I}} | |||
Latest revision as of 22:01, 6 December 2024
| ML20207E142 | |
| Person / Time | |
|---|---|
| Site: | 05000601 |
| Issue date: | 07/29/1988 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | Ward D Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML19292J245 | List: |
| References | |
| RTR-NUREG-CR-5177 NUDOCS 8808170056 | |
| Download: ML20207E142 (2) | |
Text
e-e July 29, 1988 Docket No. 50-601
{
Hr. David Ward, Chairman Subcomittee on Advanced Pressurized Water Reactors (Westinghouse and Combustion Engineering)
Advisory Committee on Reactor Safeguards United States Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Ward:
SUBJECT:
BNL REPORTS REGARDING PROBABILISTIC SAFETY STUDY FOR THE RESAR SP/90 As part of our ongoing review of Westinghouse's application for a Preliminary Design Approval (PDA) for the RESAR SP/90 Advanced PWR, we contracted with Brookhaven National Laboratory (BNL) to assist us in our review of Module 16, "Probabilistic Safety Study." As part of this effort, BNL has prepared the attached NUREG/CR 5177, Volurres 1 and 2, entitled "A Review of the WAPWR Probabilistic Safety Study (Internal Events, Core Damage Frequency)" snd "A Review of the WAPWR Probabilistic Safety Study (Internal Events, Containment Response, and Offsite Consequences)," respectively.
We are providing these reports to assist you in understanding the concerns of the staff and our contractor.
Note that some of the material contained in these enclosures are considered to be proprietary and, therefore, is being withheld from public disclosure per 10 CFR 2.740.
If you have any questions concerning this matter, please contact Tom Kenyon at (301) 492-1120.
Sincerely, Original Signed By:
Charles L. Itiller, Acting Director 8800170056 080729 Standardization and Non-Power PDR ADOCK 05000601 Reactor Project Directorate A
PNU Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation Enriosures:
As stated PFPI DISTRIBUTION:
W/ Enclosure Docket File '
g g
i TXenyon ACRS (10)
W/0 Enclosure NRC PDRs LRubenstein DPersinko MCunningham PDSNP Reading EHylton EJordan HVandermolen i
f DCru[tchfield EShomaker 0GC BGrines b~~
EChelliah 1
f;Ijk N
PDSgTI OC PI58 PDSNP
^
on TXe iT: 1s nomAker DPersinkh Citiller 07
/88 07/ /88 07/pf88 07/;j/88 07 M /88 7
- eno:\\~
UNITED STATES NUCLEAR REGULATORY COMMISSION y
WASHINGTON, D. C. 20604 July 29, 1988 Docket No. 50-601 Mr. David Ward, Chairman Subcomittee on Advanced Pressurized Water Reactors (Westinghouse and Combustion Engineering)
Advisory Comittee on Reactor Safeguards United States Nuclear Regulatory Comission Washington, D.C.
20555
Dear Mr. Ward:
SUBJECT:
BNL REPORTS REGARDING PROBABILISTIC SAFETY STUDY FOR THE RESAR SP/90 As part of our ongoing review of Westinghouse's application for a Preliminary Design Approval (PDA) for the RESAR SP/90 Advanced PWR, we contracted with Brookhaven National Laboratory (BNL) to assist us in our review of Module 16 "Probabilistic Safety Study." As part of this effort BNL has prepared the attached NUREG/CR 5177, Volumes 1 and 2, entitled "A Review of the WAPhR Probabilistic Safety Study (Internal Events, Core Damage Frac;uency)" and "A Review of the WAPWR Probabilistic Safety Study (Internal Events, Containment Response, and Offsite Consegaences)." respectively.
^
We are providing these reports to assist you in understanding the concerns of t
the staff and our contractor.
Note that some of the material contained in these enclosures are considered to i
be prcprietary and, therefore, is being withheld from public disclosure per 10 CFR 2.740.
If you have any questions concerning this matter, please contact Tom Kenyon at (301) 492-1120.
Sincerely, CAA.a l r
Charles L. Miller, Acting Director Standardization and Non-Power i
Reactor Project Directorate Division of Reactor Projects III.
IV, Y and Special Projects Office of Nuclear Reactor Regulation i
l
Enclosures:
As stated 1
i l
I