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        ,.-                                              December 19, 1997 l
December 19, 1997 l
i Mr. Nicholas J. Liparulo, Manager Nuclea- Safety and Regulatory Analysis Nuc! ear and Advanced Technology Division Westinghouse Electric Corporation -
Mr. Nicholas J. Liparulo, Manager i
Nuclea-Safety and Regulatory Analysis Nuc! ear and Advanced Technology Division Westinghouse Electric Corporation -
P.O. Box 355 Pittsburgh, PA 15230
P.O. Box 355 Pittsburgh, PA 15230


Line 25: Line 26:


==Dear Mr. Liparulo:==
==Dear Mr. Liparulo:==
The Reactor Systems Branch has provided their open items conceming Chapter 20 of the SER -
The Reactor Systems Branch has provided their open items conceming Chapter 20 of the SER -
to the projects staff. These open items can be found in the enclosure to this letter.
to the projects staff. These open items can be found in the enclosure to this letter.
You have requested that portions of the information submitted in the June 1992, application for design certification be exempt from mandatory public disclosure. While the staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.790, that portion of the submitted information is being withheld from public disclosure pending the staffs final determination. The staff concludes that these fo!'ow on questions do not contain those portions of the information for which exemption is sought. However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Westinghouse the opportunity to verify the staffs conclusions. If, after that time, you do not request that all or portions of the information in the enclosures be withheld from public disclosure in accordance with 10 CFR 2.790, this letter will be placed in the Nuclear Regulatory Commission Public Document Room.
You have requested that portions of the information submitted in the June 1992, application for design certification be exempt from mandatory public disclosure. While the staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.790, that portion of the submitted information is being withheld from public disclosure pending the staffs final determination. The staff concludes that these fo!'ow on questions do not contain those portions of the information for which exemption is sought. However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Westinghouse the opportunity to verify the staffs conclusions. If, after that time, you do not request that all or portions of the information in the enclosures be withheld from public disclosure in accordance with 10 CFR 2.790, this letter will be placed in the Nuclear Regulatory Commission Public Document Room.
If you have any questions regarding this matter, you may contact me at (301) 415-1132.
If you have any questions regarding this matter, you may contact me at (301) 415-1132.
Slocerely,         .
Slocerely, Original signed by:
Original signed by:
Joseph M. Sebrosky, Project Manager Standardization Project Directorate i
Joseph M. Sebrosky, Project Manager Standardization Project Directorate i g Division of Reactor Progrom Management Office of Nuclear Re, actor Regulation Docket No. 52-003
Division of Reactor Progrom Management g
Office of Nuclear Re, actor Regulation Docket No. 52-003


==Enclosure:==
==Enclosure:==
As stated p
As stated p
cc wienet: See next page                                                     '
cc wienet: See next page E*e'n"e'"t p0" NRC RLE CEBiiB COPY 9802030089 981219 PDR ADOCK 05200003 E
E*e'n"e'"t p0" 9802030089 981219                                            NRC RLE CEBiiB COPY PDR     ADOCK 05200003 E                     FDR DOCUMENT NAME: A: SPLB 20.RV1 To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure"E" = Copy with attachment / enclosure "N" = No copy OFFICE PM:PDST:DRPM             -  D:SRXB:DSSA tJ D:PDST:DRPMm l
FDR DOCUMENT NAME: A: SPLB 20.RV1 To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure"E" = Copy with attachment / enclosure "N" = No copy OFFICE PM:PDST:DRPM D:SRXB:DSSA tJ D:PDST:DRPMm l
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12/ 4/97 12/' I97 (/ @
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4 Mr. Nicholas J. Liparulo Docut No. 52-003 Westinghouse Electric Corporation               AP600 cc:   Mr. B. A. McIntyre               _
4 Mr. Nicholas J. Liparulo Docut No. 52-003 Westinghouse Electric Corporation AP600 cc:
Ms. Cindy L. Haag Advanced Plant Safety & Licensing         Advanced Plant Safety & Licensinq Westinghouse Electric Corporation         Westinghouse Electric Corporation Energy Systems Business Unit               Energy Systems Business Unit P.O. Box 355                               Box 355 Pittsburgh, PA 15230                       Pittsburgh, PA 15230 Enclosure to be distributed to the following addressees after the result of the proprietary evaluation is received from West'nghouse:
Mr. B. A. McIntyre Ms. Cindy L. Haag Advanced Plant Safety & Licensing Advanced Plant Safety & Licensinq Westinghouse Electric Corporation Westinghouse Electric Corporation Energy Systems Business Unit Energy Systems Business Unit P.O. Box 355 Box 355 Pittsburgh, PA 15230 Pittsburgh, PA 15230 Enclosure to be distributed to the following addressees after the result of the proprietary evaluation is received from West'nghouse:
Mr. Russ Bell                             Ms. Lynn Connor Senior Project Manager, Programs           DOC-Search Associates Nuclear Energy Institute Post Office Box 34 17761 Street, NW.                         Cabin John, MD 20818 Suite 300 Washington, DC 20006 3706 Mr. Robert H. Buchholz GE Nuclear Energy Dr. Craig D. Sawyer, Manager               175 Curtner Avenue, MC-761 Advanced Reactor Programs                 San Jose, CA 95125 GE Nuclear Energy 175 Curtner Avenue, MC-754               Mr. Sterling Franks San Jose, CA 95125 U.S. Department of Energy NE-50 Barton Z. Cowan, Esq.
Mr. Russ Bell Ms. Lynn Connor Senior Project Manager, Programs DOC-Search Associates Nuclear Energy Institute Post Office Box 34 17761 Street, NW.
19901 Germantown Road Eckert Seamans Cherin & Mellott           Germantown, MD 20874 600 Grant Street 42nd Floor Pittsburgh, PA 15219 Mr. Charles Thompson, Nuclear Engineer AP600 Certification Mr. Frank A. Ross                         NE-50 U.S. Department of Energy, NE-42           19901 Germantown Road Office of LWR Safety and Technology-       Germantown, MD 20874 19901 Germantown Road Germantown, MD 20874 Mr. Ed Rodwell, Manager                                                                       .
Cabin John, MD 20818 Suite 300 Washington, DC 20006 3706 Mr. Robert H. Buchholz GE Nuclear Energy Dr. Craig D. Sawyer, Manager 175 Curtner Avenue, MC-761 Advanced Reactor Programs San Jose, CA 95125 GE Nuclear Energy 175 Curtner Avenue, MC-754 Mr. Sterling Franks San Jose, CA 95125 U.S. Department of Energy NE-50 Barton Z. Cowan, Esq.
PWR Design Certification Electric Power Research Institute 3412 Hillview Avenue Palo Alto, CA 94303                                                                           i Mr. Robert Maiers, P.E.
19901 Germantown Road Eckert Seamans Cherin & Mellott Germantown, MD 20874 600 Grant Street 42nd Floor Pittsburgh, PA 15219 Mr. Charles Thompson, Nuclear Engineer AP600 Certification Mr. Frank A. Ross NE-50 U.S. Department of Energy, NE-42 19901 Germantown Road Office of LWR Safety and Technology-Germantown, MD 20874 19901 Germantown Road Germantown, MD 20874 Mr. Ed Rodwell, Manager PWR Design Certification Electric Power Research Institute 3412 Hillview Avenue Palo Alto, CA 94303 i
Mr. Robert Maiers, P.E.
Pennsylvania Department of Environmental Protection Bureau of Radiation Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469
Pennsylvania Department of Environmental Protection Bureau of Radiation Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469


DISTRIBUTION: Letter to Mr. Nicholas J. Lioarulo. Dated:   December 19, 1997
DISTRIBUTION: Letter to Mr. Nicholas J. Lioarulo. Dated:
December 19, 1997
(* Docket File 4* Enclosure to be held for 30 days
(* Docket File 4* Enclosure to be held for 30 days
            *PUBLIC PDST R/F TQuay TKenyon WHuffman                                                                     ,
*PUBLIC PDST R/F TQuay TKenyon WHuffman JSebrosky DScaletti
JSebrosky DScaletti
-JNWilson WDean,0-5 E23 ACRS (11)
          -JNWilson
JMoore,0-15 B18 TCollins,0-8 E23 RCaruso,0-8 E23 -
* WDean,0-5 E23 ACRS (11)
JMoore,0-15 B18 TCollins,0-8 E23 RCaruso,0-8 E23 -                                                             ,
DDiec,0-8 E23 1
DDiec,0-8 E23 1
1 4
1 4


OPEN ITEMS ASSOCIATED WITH CHAPTER 20                                                                       ,
OPEN ITEMS ASSOCIATED WITH CHAPTER 20 650.35F:
650.35F:     lasue A 9: Anticipated Transient Without Scram 10 CFR 50.62 requires the automatic 'nitiation of the auxiliary feedwater system under conditions indicative of an ATWS. The AP600 does not include this design feature, but instead automstically initia'es the PRHR system. The applicant should request an exemption from the 10 CFR 50.62 for automatic initiation of auxiliary fecdwater, and update the discussion in SSAR Section 1.9.4.2.2 accordingly.
lasue A 9: Anticipated Transient Without Scram 10 CFR 50.62 requires the automatic 'nitiation of the auxiliary feedwater system under conditions indicative of an ATWS. The AP600 does not include this design feature, but instead automstically initia'es the PRHR system. The applicant should request an exemption from the 10 CFR 50.62 for automatic initiation of auxiliary fecdwater, and update the discussion in SSAR Section 1.9.4.2.2 accordingly.
650.36F:     Issue 105: Inte:Tacing System t.OCA All Pressure isolation Valves (FIV) in the RNS, CVS, and PSS should be included in AP600 Technical Specification Section 3.4.16, and should be subject to periodic PlV leak festing.                                           ;
650.36F:
Issue 105: Inte:Tacing System t.OCA All Pressure isolation Valves (FIV) in the RNS, CVS, and PSS should be included in AP600 Technical Specification Section 3.4.16, and should be subject to periodic PlV leak festing.
WCAP-14425 does not provide the relieving capacity and set pressure of de makeup system relief valves, as well as an analysir to demonstrate that they have been properly sized. The relieving capacity and set pressure of the CVS makeup system relief valves, as well as their bases, should be documented in the SSAR.
WCAP-14425 does not provide the relieving capacity and set pressure of de makeup system relief valves, as well as an analysir to demonstrate that they have been properly sized. The relieving capacity and set pressure of the CVS makeup system relief valves, as well as their bases, should be documented in the SSAR.
3 Enclosure
3 Enclosure
___ ___                                                                          - _ _ _ _ _ - _ _ - _ _ .}}
_ _ _ _ _ - _ _ - _ _.}}

Latest revision as of 07:49, 10 December 2024

Forwards Open Items Associated W/Chapter 20 of AP600 SER
ML20199F207
Person / Time
Site: 05200003
Issue date: 12/19/1997
From: Joseph Sebrosky
NRC (Affiliation Not Assigned)
To: Liparulo N
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9802030089
Download: ML20199F207 (4)


Text

_

December 19, 1997 l

Mr. Nicholas J. Liparulo, Manager i

Nuclea-Safety and Regulatory Analysis Nuc! ear and Advanced Technology Division Westinghouse Electric Corporation -

P.O. Box 355 Pittsburgh, PA 15230

SUBJECT:

OPEN ITEMS ASSOCIATED WITH CHAPTER 20 CF THE AP600 SAFETY EVALUATION REPORT (SER) -

Dear Mr. Liparulo:

The Reactor Systems Branch has provided their open items conceming Chapter 20 of the SER -

to the projects staff. These open items can be found in the enclosure to this letter.

You have requested that portions of the information submitted in the June 1992, application for design certification be exempt from mandatory public disclosure. While the staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.790, that portion of the submitted information is being withheld from public disclosure pending the staffs final determination. The staff concludes that these fo!'ow on questions do not contain those portions of the information for which exemption is sought. However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Westinghouse the opportunity to verify the staffs conclusions. If, after that time, you do not request that all or portions of the information in the enclosures be withheld from public disclosure in accordance with 10 CFR 2.790, this letter will be placed in the Nuclear Regulatory Commission Public Document Room.

If you have any questions regarding this matter, you may contact me at (301) 415-1132.

Slocerely, Original signed by:

Joseph M. Sebrosky, Project Manager Standardization Project Directorate i

Division of Reactor Progrom Management g

Office of Nuclear Re, actor Regulation Docket No.52-003

Enclosure:

As stated p

cc wienet: See next page E*e'n"e'"t p0" NRC RLE CEBiiB COPY 9802030089 981219 PDR ADOCK 05200003 E

FDR DOCUMENT NAME: A: SPLB 20.RV1 To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure"E" = Copy with attachment / enclosure "N" = No copy OFFICE PM:PDST:DRPM D:SRXB:DSSA tJ D:PDST:DRPMm l

l.AME JSebrosky:sg Ju%

TCollins fri.

TQuayM DATE 12/4/97 t/

12/ 4/97 12/' I97 (/ @

d 1

OFHCIAL RECORD COPY a

hD(.

b hob s

4 Mr. Nicholas J. Liparulo Docut No.52-003 Westinghouse Electric Corporation AP600 cc:

Mr. B. A. McIntyre Ms. Cindy L. Haag Advanced Plant Safety & Licensing Advanced Plant Safety & Licensinq Westinghouse Electric Corporation Westinghouse Electric Corporation Energy Systems Business Unit Energy Systems Business Unit P.O. Box 355 Box 355 Pittsburgh, PA 15230 Pittsburgh, PA 15230 Enclosure to be distributed to the following addressees after the result of the proprietary evaluation is received from West'nghouse:

Mr. Russ Bell Ms. Lynn Connor Senior Project Manager, Programs DOC-Search Associates Nuclear Energy Institute Post Office Box 34 17761 Street, NW.

Cabin John, MD 20818 Suite 300 Washington, DC 20006 3706 Mr. Robert H. Buchholz GE Nuclear Energy Dr. Craig D. Sawyer, Manager 175 Curtner Avenue, MC-761 Advanced Reactor Programs San Jose, CA 95125 GE Nuclear Energy 175 Curtner Avenue, MC-754 Mr. Sterling Franks San Jose, CA 95125 U.S. Department of Energy NE-50 Barton Z. Cowan, Esq.

19901 Germantown Road Eckert Seamans Cherin & Mellott Germantown, MD 20874 600 Grant Street 42nd Floor Pittsburgh, PA 15219 Mr. Charles Thompson, Nuclear Engineer AP600 Certification Mr. Frank A. Ross NE-50 U.S. Department of Energy, NE-42 19901 Germantown Road Office of LWR Safety and Technology-Germantown, MD 20874 19901 Germantown Road Germantown, MD 20874 Mr. Ed Rodwell, Manager PWR Design Certification Electric Power Research Institute 3412 Hillview Avenue Palo Alto, CA 94303 i

Mr. Robert Maiers, P.E.

Pennsylvania Department of Environmental Protection Bureau of Radiation Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469

DISTRIBUTION: Letter to Mr. Nicholas J. Lioarulo. Dated:

December 19, 1997

(* Docket File 4* Enclosure to be held for 30 days

  • PUBLIC PDST R/F TQuay TKenyon WHuffman JSebrosky DScaletti

-JNWilson WDean,0-5 E23 ACRS (11)

JMoore,0-15 B18 TCollins,0-8 E23 RCaruso,0-8 E23 -

DDiec,0-8 E23 1

1 4

OPEN ITEMS ASSOCIATED WITH CHAPTER 20 650.35F:

lasue A 9: Anticipated Transient Without Scram 10 CFR 50.62 requires the automatic 'nitiation of the auxiliary feedwater system under conditions indicative of an ATWS. The AP600 does not include this design feature, but instead automstically initia'es the PRHR system. The applicant should request an exemption from the 10 CFR 50.62 for automatic initiation of auxiliary fecdwater, and update the discussion in SSAR Section 1.9.4.2.2 accordingly.

650.36F:

Issue 105: Inte:Tacing System t.OCA All Pressure isolation Valves (FIV) in the RNS, CVS, and PSS should be included in AP600 Technical Specification Section 3.4.16, and should be subject to periodic PlV leak festing.

WCAP-14425 does not provide the relieving capacity and set pressure of de makeup system relief valves, as well as an analysir to demonstrate that they have been properly sized. The relieving capacity and set pressure of the CVS makeup system relief valves, as well as their bases, should be documented in the SSAR.

3 Enclosure

_ _ _ _ _ - _ _ - _ _.