|
|
Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:}} | | {{#Wiki_filter:I |
| | .'' |
| | * sa ur i |
| | + UNITED STATES |
| | ! g NUCLEAR REGULATORY COMMISSION |
| | + |
| | * WASHINGTON. D. C. 20666 L :j k . o. . . p# November 22, 1988 Docket No. 50-601 l Mr. W. J. Johnson Nuclear Safety Department Westinghouse Electric Corporation Water Reactor Division Box 355 Pittsburg, Pennsylvania 15230 |
| | |
| | ==Dear Mr. Johnson:== |
| | |
| | ==SUBJECT:== |
| | SCOPE OF DESIGN AND SCOPE OF STAFF REVIEW CF RESAR SP/90 Although not formally documented, it is the staff's understanding that Westinghouse intends to apply for design certification for the RESAR SP/90 design currently inhouse for a Preliminary Design Approval (PDA) review. This letter provides guidance regarding the scope of the design and the scope of the staff's review should you decide to pursue such an application. We request that you use it in preparing the application for an FDA and the accompanying Licensing Review Basis. |
| | Scope of Design In the proposed regulation 10 CFR Part 52, the staff has defined the desired scope of designs for standard plants requesting certification. The proposed regulation states that "Ideally, the designs for which certification is sought will be for essentially complete plants." It also states that "the NRC will give priority in allocation of resources to support reviews and approval of applications for essentially corplete plants." |
| | Should you decide to pursue the application for design certification of RESAR SP/90, we request that the application be for a design whose scope is essentially complete and consistent with the proposed 10 CFR Part 52 in order for us to give appropriate priority to your application's review. |
| | Scope of Staff Review The staff will be considering issues that may go beyond the Standard Review Plan involving such subjects as fire protection, electrical systems and others. |
| | Some of these items are briefly discussed in the enclosure to this letter. |
| | The draft and final SER regarding the review of the PDA application for RESAR SP/90 subjectsmay(already reflect staff i.e.,fireprotection). Theseconsideration ofaddressed issues will be these issues for certain in the Licensing Review Basis document after the decision on the PDA application is reached. |
| | $$k $(($ b!bb i d n o I |
| | L |
| | |
| | Mr. 'W. J. Johnson November 22, 1988 a' Because your position concerning design certification of the RESAR SP/90 has not been formally documented, we request you inform us of ycur intentions in this matter along with your schedule for submitting your application, including the submittal of the Final Reference Safety Analysis Report, and the scope of |
| | ; the design within 30 days from receipt of this letter. The schedule may be discussed in terms of receipt of the PDA for the facility design. |
| | i Sincerely, I |
| | j Dennis M. Crutchfield |
| | , Acting Associate Dir tor for Projects |
| | ! Office of Nuclear Reactor Regulation |
| | |
| | ==Enclosure:== |
| | |
| | As stated i cc w/ enc 1: |
| | j- See next page 6 |
| | k i |
| | !l I |
| | i l |
| | |
| | Mr.'W. J. 'ohnson Docket No. 50-601 RESAR-SP/!t ec: |
| | Trevor Pratt Brookhaven National Laboratory Building 130 Upton, New York 11973 Mr. William Schivley Westinghouse Electric Corporation ECE-410 Mail Stop 4-08 Box 355 Pittsburgh, Pennsylvania 15230 |
| | |
| | ENCLOSURE POTENTIAL REVIEW SUBJECTS FOR STANDARD PLANT DESIGNS The staff met to discuss major issues related to the review of advanced light water reactor applications. Included in the discussions were issues in which the scope of the staff's acceptance criteria may go beyond that of the current Standard Review Plan to e mure improved design, construction, and/or operation of these advanced plants. The staff's positions on these matters will be . |
| | l finalized during the development of the Licensing Review Basis (LRB) for the Westinghouse designs. The following are brief discussions of the staff's current views on some of these matters. |
| | i |
| | : 1. 60 YEAR LIFE: |
| | For applications proposing a 60-year deitgn life, the staff would review the designs for a 60-year life notwithstanding the fact that a 40-year license term limitation is presently in the regulations. It is the applicants' responsibility to identify the components and systems which '. |
| | are affected. Applications for design certific3 tion will have to provide information and programs to support design life, and the reviews for such issues as fatigue, corrosion and themal aging. |
| | : 2. FIRE PROTECTION: |
| | Improved fire protection criteria are needed in view of the significant , |
| | contribution of fires to core melt probability. The current Appendix R - |
| | and BTP 9-5.1 requirements (e.g. 20 ft, separation) should be replaced by ; |
| | a requirement for safe shutdown capability in the event of a corplete loss of any fire area. |
| | : 3. TECHNICAL SPECIFICATIONS: |
| | The staff considers that (1) proposed Technical Specifications should be developed as early as practicable, but be submitted no later than the FDA application,(2)proposedlechnicalSpecificationsrepresentativeofthe design should be submitted for review and approval by the staff as part of the FDA submittal, and will be included in the Design Certification process, and (3) applicants should identify design features that are necessary for testing and maintenance during operation without challenging safety systems. |
| | The Technical Specifications should be developed, where practicable, based upon risk and reliability considerations. |
| | : 4. TESTING AND MAINTENANCE: |
| | 1 Certification of a design will be based in part upon a probabilistic risk assessment of that design. In that the validity of a PRA is highly dependent on the reliability of systems, structures and components, the |
| | . staff requires assurance that programs will be implemented which will ensure that the reliability of those systems, structures and components l (assured in analyses) will be maintained throughout plant life. There-fore, a program to assure design reliability must be provided as part of ; |
| | |
| | i the FDA application. This program which will be certified as part of the design should address items such as (1) the Technical Specifications and ISI/IST,(2)theMaintenanceProgram,(3)PlantProcedures,and(4) |
| | Security. |
| | : 5. INDUSTRY USE OF MAAP: |
| | Review of the NAAP code is unnecessar MELCOR and Source Term Code STCP) Package (y since codes the staff can apply its own in its evaluations. , |
| | : 6. STATION BLACKOUT AND ELECTRICAL SYSTEM: |
| | Future ALWRs should adopt improved electrica, systemt to ensure a safe shutdown of the reactor. These systems should provide, in part, for diverse power sources in order to eliminate the concerns related to ! |
| | station blackout. General guidelines will be developed and finalized ' |
| | during development of the LRB. |
| | : 7. LEAK BEFORE BREAK: |
| | Leak before break can be considered where justified. Where applicable, designs must address good practices in order to maintain steam generator tube integrity. Also, designs should address issues of material embrittle-ment associated with current vessel materials and vessel supports. l A new rule and draf t SRP Section 3.6.3 have been issued. The EPRI design requirements has adopted these criteria. , |
| | : 8. SOURCE TERMS: |
| | The staff is concerned that the licensing basis source term "TID 14844' is not consistent with current knowledge. Therefore, with EPRI input, realistic source terms will be established to be uniformly applied to future ALWRS. |
| | : 9. PHYSICAL SECURITY: |
| | Sabotage should be addressed in all future ALWRS applications. As a i minimum, infornation should be provided to demonstrate the existence of adequate physical barriers to protect vital equipment in accordance with 10 CFR 73.55(c) in accordance with and to identify 10 CFR 73.05 d).(access control points to all vital areas [ |
| | 4 |
| | : 10. O_BE/0YNAMIC ANALYSIS HETH005: |
| | The staff agrees that the OBE should not control the design of safety 4 systems as now required by 10 CFR 100 Appendix A. The staff will take |
| | : this issue under consideration as part of the design certification f |
| | ; process. |
| | 1 |
| | |
| | i 11. TYPE C CONTAINMENT LEAKAGE RATE: |
| | Containment leakage is acknowledged by the staff as being a function of containment pressure. |
| | : 12. HYDROGEN GENERATION: |
| | 10 CFR 50.34(f) related to the issue of a 100% r,etal water reaction will be invoked for ALWRs consistent with Commission Policy and proposed 10 CFR Part 52. |
| | 1 I |
| | |
| | re, < #l Mr. W. J. Johnson November 22, 1988 Because your position concerning design certification of the RESAR SP/90 has not been formally documented, we request you inform us of your intentions in this matter along with your schedule for submitting your application, including the submittal of the Final Reference Safety Analysis Report, and the scope of the design within 30 days fron receipt of this letter. The schedule may be discussed in terms of receipt of the PDA for the facility design. |
| | Sincerely, |
| | /s/ |
| | Dennis M. Crutchfield Acting Associate Director for Projects Office of Nuclear Reactor Regulation |
| | |
| | ==Enclosure:== |
| | |
| | As stated i cc w/ enc 1: |
| | See next page DISTRIBUTION: |
| | Docket File NRC PDR PDSNP R/F EHylton TKenyon EJordan BGrimes OGC-Rockville ACRS (10) |
| | LRubenstein GHolahan DCrutchfield l |
| | l i |
| | 4 i |
| | 1 (WSCOPE) *SEE PREVIOUS C0hCURRENCE |
| | *LA:PDSNP EHylton |
| | *HWADSNP *D:PDSNP CMiller |
| | *ADR4 *A:0:DRSP A :, //d- |
| | ! ig6h}un LRubenstein GHolahan chfield 11/15/88 11/15/08 11/16/88 11/16/88 11/16/88 DCx{/CE 11// |
| | i |
| | : r |
| | . i |
| | ; Mr. W. J. Johnson i 1 i |
| | : Because your position concerning design certification of the RESAR SP/90 has i not been formally documented, we request you inforin us of your intentions in ' |
| | this matter along with your schedule for submitting your application, including |
| | 'l the submittal of the Final Reference Safety Analysis Report, and the scope of , |
| | 4 the design within 30 days from receipt of this letter. Tne schedule may be ; |
| | i discussed in terms of receipt of the PDA for the facility design. ! |
| | l i j Sinewely, l |
| | 4 i |
| | Dennis M. Crutchfield j Acting Associate Director for Projects |
| | : Office of Nuclear Reactor Regulation ; |
| | 4 i |
| | |
| | ==Enclosure:== |
| | j As stated ! |
| | cc: See next page |
| | . DISTRIBUTION: I |
| | ; Docket File ! |
| | ! NRC PDR j PDSNP R/F Elfylton TKenyon |
| | ! EJordan BGrimes |
| | ! OGC-Rockville r i |
| | ACRS(10) i |
| | ! LRubenstein l GHolahan i 0Crutchfield 1 |
| | 5P F$ SNP 0:PDb ADR p 0:DR$P (A)ADP { |
| | on TKe'nyon Chiller LRubenstc'n Holahan 0CRutchfield i 11/fy/88 11&f/88 11//c /88 11/<'4 /88 114b /88 11/ /88 { |
| | l.7t'u H L l 1 |
| | I I |
| | i |
| | _ _ _ _ . _ _ _ _ -'}} |
|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217C5661991-07-0101 July 1991 Forwards Rev Updating Fnmcp.Encl Withheld (Ref 10CFR2.790) NRC-91-3569, Forwards Proprietary SER Re Preliminary Design of Std Nuclear Steam Supply Ref Sys RESAR SP/90. Encl Withheld1991-02-12012 February 1991 Forwards Proprietary SER Re Preliminary Design of Std Nuclear Steam Supply Ref Sys RESAR SP/90. Encl Withheld ML20012E9261990-03-20020 March 1990 Forwards SP/90 Position on Severe Accident Policy Issues Presented by NRC During 900209 ACRS Full Committee Meeting NRC-89-3461, Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 2, Regulatory Conformance1989-10-0303 October 1989 Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 2, Regulatory Conformance ML20248H8461989-10-0303 October 1989 Requests That Proprietary Amend 3 to RESAR-SP/90 Pda Module 2, Regulatory Conformance, Be Withheld from Public Disclosure (Ref 10CFR2.790).Affidavit Encl ML20247H2791989-09-12012 September 1989 Grants Request for Withholding of Response to NRC Draft SER Open Issues 1-41 Re Review of RESAR SP/90 Pda Application, Per 10CFR2.790(b)(5) NRC-89-3453, Forwards Proprietary & Nonproprietary Responses to NRC Draft SER Open Issues 82-107 in Review of RESAR-SP/90 Pda. Responses Include Associated Text Changes That Will Be Made in Final Submittal to Draft Ser.Proprietary Rept Withheld1989-08-31031 August 1989 Forwards Proprietary & Nonproprietary Responses to NRC Draft SER Open Issues 82-107 in Review of RESAR-SP/90 Pda. Responses Include Associated Text Changes That Will Be Made in Final Submittal to Draft Ser.Proprietary Rept Withheld ML20247G2581989-08-31031 August 1989 Requests That Response to Draft SER Open Issue 82-107 Re RESAR-SP/90 Pda Be Withheld from Public Disclosure (Ref 10CFR2.790) NRC-89-3448, Forwards Westinghouse SP/90 Position on Selected Severe Accident Issues to Be Discussed During 890714 Meeting W/Nrc in Rockville,Md.Issue Topics Include Fire Protection, Intersys Loca,Midloop Operation & ATWS1989-07-11011 July 1989 Forwards Westinghouse SP/90 Position on Selected Severe Accident Issues to Be Discussed During 890714 Meeting W/Nrc in Rockville,Md.Issue Topics Include Fire Protection, Intersys Loca,Midloop Operation & ATWS ML20246H2151989-07-0606 July 1989 Approves Request to Withhold Amends 1a & 2 to Westinghouse Advanced PWR RESAR SP/90 Preliminary Design Approval Module 7, Structural/Equipment Design, (Ref 10CFR2.790) ML20245J8861989-06-28028 June 1989 Requests That Response to Draft SER Open Issues 1-41 Re RESAR-SP/90 Pda Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20245J8821989-06-28028 June 1989 Forwards Proprietary & Nonproprietary Responses to NRC Draft SER Open Issues 1-41 Re RESAR-SP/90 Pda.Proprietary Response Withheld (Ref 10CFR2.790) NRC-89-3438, Forwards Nonproprietary Draft Responses to Open Issues 42-81 of Draft SER Re RESAR-SP/90 Preliminary Design Application1989-06-0909 June 1989 Forwards Nonproprietary Draft Responses to Open Issues 42-81 of Draft SER Re RESAR-SP/90 Preliminary Design Application NRC-89-3419, Forwards Draft Response to NRC Questions 730.1 - 730.4 Re RESAR-SP/90 Pda,Module 2, Regulatory Conformance1989-03-15015 March 1989 Forwards Draft Response to NRC Questions 730.1 - 730.4 Re RESAR-SP/90 Pda,Module 2, Regulatory Conformance ML20236B3751989-03-0909 March 1989 Forwards to Wj Johnson,Forwarding NRC Draft SER Re RESAR SP/90 on Listed Technical Areas.Ltrs Provided to ACRS Members of Progress in Reviewing Pda Application ML20236B3571989-03-0909 March 1989 Forwards Proprietary Draft SER Re Status of Review of Pda Application for RESAR SP/90.Encl Withheld (Ref 10CFR2.790) NRC-89-3400, Forwards Nonproprietary & Proprietary Amends 1a & 2 to Wapwr RESAR-SP/90 Module 7, Structure Equipment Design1989-02-14014 February 1989 Forwards Nonproprietary & Proprietary Amends 1a & 2 to Wapwr RESAR-SP/90 Module 7, Structure Equipment Design ML20235N4451989-02-14014 February 1989 Application for Withholding Proprietary Amends 1a & 2 to Wapwr RESAR-SP/90 Pda Module 7, Structural/Equipment Design, from Public Disclosure ML20195H1161988-11-22022 November 1988 Provides Guidance Re Scope of Design & NRC Review of RESAR SP/90 Design.Westinghouse Intends to Apply for Design Certification for RESAR SP/90 Design Currently Inhouse for Preliminary Design Approval Review ML20206F8681988-11-0808 November 1988 Requests Withholding Proprietary Rept from Public Disclosure Per 10CFR2.790 NRC-88-3382, Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 5, Reactor Sys. Proprietary Rept Withheld (Ref 10CFR2.790)1988-11-0808 November 1988 Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 5, Reactor Sys. Proprietary Rept Withheld (Ref 10CFR2.790) NRC-88-3365, Discusses Design Approval & Certification Programs for AP-600 & SP-90 Designs for Std Nuclear plants.SP-90 Plant Currently Being Evaluated by NRC & Completion of Safety Review & Receipt of SER Anticipated First Quarter 19891988-11-0101 November 1988 Discusses Design Approval & Certification Programs for AP-600 & SP-90 Designs for Std Nuclear plants.SP-90 Plant Currently Being Evaluated by NRC & Completion of Safety Review & Receipt of SER Anticipated First Quarter 1989 ML20195C7871988-10-26026 October 1988 Requests Withholding of Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 4, RCS from Public Disclosure (Ref 10CFR2.790) NRC-88-3379, Forwards Proprietary & Nonproprietary Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 4, Rcs. Proprietary Amend Withheld (Ref 10CFR2.790)1988-10-26026 October 1988 Forwards Proprietary & Nonproprietary Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 4, Rcs. Proprietary Amend Withheld (Ref 10CFR2.790) NRC-88-3374, Forwards Response to NRC 880414 Questions 260.1-260.33 Re QA Program for RESAR-SP/90 Pda.Responses Reflect Discussions Between NRC & Westinghouse During Telcons & 880616 Meeting1988-10-25025 October 1988 Forwards Response to NRC 880414 Questions 260.1-260.33 Re QA Program for RESAR-SP/90 Pda.Responses Reflect Discussions Between NRC & Westinghouse During Telcons & 880616 Meeting ML20207J9441988-09-19019 September 1988 Requests Withholding of Proprietary Version of Amend 4 to RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys (Ref 10CFR2.790) NRC-88-3371, Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys. Application for Withholding & Affidavit Also Encl. Proprietary Amend 4 Withheld (Ref 10CFR2.790)1988-09-19019 September 1988 Forwards Proprietary & Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys. Application for Withholding & Affidavit Also Encl. Proprietary Amend 4 Withheld (Ref 10CFR2.790) NRC-88-3368, Forwards Proprietary & Nonproprietary Versions of Amend 3 to Wapwr RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Version Withheld (Ref 10CFR2.790)1988-08-25025 August 1988 Forwards Proprietary & Nonproprietary Versions of Amend 3 to Wapwr RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Version Withheld (Ref 10CFR2.790) ML20153F7131988-08-25025 August 1988 Requests Withholding of Amend 3 to Wapwr RESAR-SP/90 Pda Module 3, Radiation Protection (Ref 10CFR2.790) NRC-88-3364, Forwards Proprietary & Nonproprietary Amend 4 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Rept Withheld (10CFR2.790)1988-08-0505 August 1988 Forwards Proprietary & Nonproprietary Amend 4 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Rept Withheld (10CFR2.790) ML20151T8611988-08-0505 August 1988 Requests That Proprietary Amend 4 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 13, Auxiliary Sys Be Withheld from Public Disclosure (10CFR2.790) ML20207E1421988-07-29029 July 1988 Forwards Proprietary BNL Repts Re Probability Safety Study for RESAR SP/90.Repts Withheld (Ref 10CFR2.740) NUREG/CR-5177, Forwards Proprietary Vols 1 & 2 to NUREG/CR-5177 Re Review of Westinghouse Advanced PWR Probabilistic Safety Study,For Review.Repts Withheld (Ref 10CFR2.790)1988-07-29029 July 1988 Forwards Proprietary Vols 1 & 2 to NUREG/CR-5177 Re Review of Westinghouse Advanced PWR Probabilistic Safety Study,For Review.Repts Withheld (Ref 10CFR2.790) NRC-88-3360, Forwards Amend 2 to Proprietary & Nonproprietary RESAR-SP/90 Pda Module 11, Radiation Protection & RESAR-SP/90 Pda Module 12, Waste Mgt. Proprietary Repts Withheld (Ref 10CFR2.790)1988-07-27027 July 1988 Forwards Amend 2 to Proprietary & Nonproprietary RESAR-SP/90 Pda Module 11, Radiation Protection & RESAR-SP/90 Pda Module 12, Waste Mgt. Proprietary Repts Withheld (Ref 10CFR2.790) ML20151N4281988-07-27027 July 1988 Requests That Proprietary Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 11, Radiation Protection & Amend 2 to RESAR-SP/90 Pda Module 12, Waste Mgt, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20150C9011988-06-23023 June 1988 Requests Withholding of Addendum 10 to Wapwr RESAR-SP-90 Pda Re Westinghouse Response to NRC Outstanding SEB Questions from Public Disclosure (Ref 10CFR2.790) NRC-88-3349, Forwards Addendum 10 to Wapwr RESAR-SP/90 Pda Re Westinghouse Response to Outstanding SEB Questions. Affidavit for Withholding Addendum (Ref 10CFR2.790) Encl1988-06-23023 June 1988 Forwards Addendum 10 to Wapwr RESAR-SP/90 Pda Re Westinghouse Response to Outstanding SEB Questions. Affidavit for Withholding Addendum (Ref 10CFR2.790) Encl NRC-88-3345, Forwards Addendum 9 to Wapwr RESAR-SP/90 Pda,To Complete Westinghouse Response to NRC Questions Documented in Tj Kenyon to Wj Johnson1988-06-14014 June 1988 Forwards Addendum 9 to Wapwr RESAR-SP/90 Pda,To Complete Westinghouse Response to NRC Questions Documented in Tj Kenyon to Wj Johnson ML20195H1131988-06-14014 June 1988 Requests That Westinghouse Submittal Re Response to Outstanding NRC Questions Be Treated as Proprietary Info Per 10CFR2.790(a) ML20155C2591988-05-27027 May 1988 Submittal of Westinghouse Response to Staff Questions 470.1 to 470.2 in Review of Wapwr RESAR-SP/90 Pda & Application for Withholding Proprietary Info from Public Disclosure NRC-88-3344, Forwards Proprietary Addendum 8 to Wapwr RESAR-SP/90 Pda & Application for withholding,AW-88-054 (non-proprietary),per 880414 & 880425 Requests1988-05-27027 May 1988 Forwards Proprietary Addendum 8 to Wapwr RESAR-SP/90 Pda & Application for withholding,AW-88-054 (non-proprietary),per 880414 & 880425 Requests ML20154J8091988-05-23023 May 1988 Requests That Proprietary Addendum 7 to RESAR-SP/90,PDA Module 2, Regulatory Conformance, Including Responses to Outstanding Safety Issues,Be Withheld from Public Disclosure (Ref 10CFR2.790) NRC-88-3343, Forwards Proprietary Addendum 7 to RESAR-SP/90 Pda Module 2, Regulatory Conformance, Including Responses to Outstanding Safety Issues.Info Constitutes First Step in Updating Module 2.Proprietary Rept Withheld1988-05-23023 May 1988 Forwards Proprietary Addendum 7 to RESAR-SP/90 Pda Module 2, Regulatory Conformance, Including Responses to Outstanding Safety Issues.Info Constitutes First Step in Updating Module 2.Proprietary Rept Withheld ML20154F0511988-05-13013 May 1988 Requests That Amends 1a & 3 to Proprietary Wapwr RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys Be Withheld from Public Disclosure (Ref 10CFR2.790) NRC-88-3340, Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Amend Withheld (Ref 10CFR2.790)1988-05-13013 May 1988 Forwards Proprietary & Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 13, Auxiliary Sys. Proprietary Amend Withheld (Ref 10CFR2.790) NRC-88-3335, Forwards Amends 1a & 3 to Proprietary & Nonproprietary Wapwr RESAR-SP/90 Module 1, Primary Side Safeguards Sys. Application for Withholding Proprietary Info from Public Disclosure & Affidavit Encl1988-05-13013 May 1988 Forwards Amends 1a & 3 to Proprietary & Nonproprietary Wapwr RESAR-SP/90 Module 1, Primary Side Safeguards Sys. Application for Withholding Proprietary Info from Public Disclosure & Affidavit Encl NRC-88-3339, Requests Withdrawal of All Copies & Attachments of Licensee Ltr NS-NRC-88-3325 to L Rubenstein Re Amend 2 to Wapwr RESAR-SP/90 Pda Module 13, Auxiliary Sys. Request for Withdrawal Necessary to Correct Amend Number1988-05-13013 May 1988 Requests Withdrawal of All Copies & Attachments of Licensee Ltr NS-NRC-88-3325 to L Rubenstein Re Amend 2 to Wapwr RESAR-SP/90 Pda Module 13, Auxiliary Sys. Request for Withdrawal Necessary to Correct Amend Number ML20154K8841988-05-13013 May 1988 Requests That Proprietary Addendum 4 to RESAR-SP/90, Request for Addl Info Be Withheld from Public Disclosure Per 10CFR2.790(a) NRC-88-3337, Forwards Proprietary & Nonproprietary Amend 1 to Wapwr RESAR-SP/90 PDR Module 4, Rcs1988-05-13013 May 1988 Forwards Proprietary & Nonproprietary Amend 1 to Wapwr RESAR-SP/90 PDR Module 4, Rcs NRC-88-3336, Forwards Proprietary & Nonproprietary Amend 1a to RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Amend Withheld (Ref 10CFR2.790)1988-05-13013 May 1988 Forwards Proprietary & Nonproprietary Amend 1a to RESAR-SP/90 Pda Module 3, Introduction & Site. Proprietary Amend Withheld (Ref 10CFR2.790) 1991-07-01
[Table view] Category:NRC TO VENDOR/MANUFACTURER
MONTHYEARML20247H2791989-09-12012 September 1989 Grants Request for Withholding of Response to NRC Draft SER Open Issues 1-41 Re Review of RESAR SP/90 Pda Application, Per 10CFR2.790(b)(5) ML20246H2151989-07-0606 July 1989 Approves Request to Withhold Amends 1a & 2 to Westinghouse Advanced PWR RESAR SP/90 Preliminary Design Approval Module 7, Structural/Equipment Design, (Ref 10CFR2.790) ML20236B3571989-03-0909 March 1989 Forwards Proprietary Draft SER Re Status of Review of Pda Application for RESAR SP/90.Encl Withheld (Ref 10CFR2.790) ML20195H1161988-11-22022 November 1988 Provides Guidance Re Scope of Design & NRC Review of RESAR SP/90 Design.Westinghouse Intends to Apply for Design Certification for RESAR SP/90 Design Currently Inhouse for Preliminary Design Approval Review NUREG/CR-5177, Forwards Proprietary Vols 1 & 2 to NUREG/CR-5177 Re Review of Westinghouse Advanced PWR Probabilistic Safety Study,For Review.Repts Withheld (Ref 10CFR2.790)1988-07-29029 July 1988 Forwards Proprietary Vols 1 & 2 to NUREG/CR-5177 Re Review of Westinghouse Advanced PWR Probabilistic Safety Study,For Review.Repts Withheld (Ref 10CFR2.790) ML20151Y1651988-04-28028 April 1988 Discusses Resolution of USIs & Medium & High Priority Generic Safety Issues for RESAR SP/90 Design.Westinghouse Should Reassess & Update Responses Provided in Module 2 & Address Any Addl Issues Prioritized Since 1983 to Present ML20153H5131988-04-25025 April 1988 Forwards Request for Addl Info Re Radiological Consequences of DBA for Response within 30 Days in Order to Complete Review of RESAR SP/90 Application ML20151H6521988-04-14014 April 1988 Forwards Request for Addl Info Re RESAR SP/90.Resolvability of Issues During Pda Phase of Review Concluded.Meeting Between NRC & Westinghouse to Discuss & Resolve Issues Prior to Issuance of Final SER Proposed ML20151L3131988-04-14014 April 1988 Forwards Request for Addl Info on RESAR SP/90 Re Radiological Consequences of Design Basis Accident,To Complete Review.Response Requested within 30 Days of Ltr Date ML20151Y0941988-03-28028 March 1988 Forwards BNL Draft Proprietary Rept, Independent Assessment of Severe Accident Risks for Westinghouse Advanced PWR Design (SP/90) Re Review of Module 16, Probabilistic Safety Study of RESAR SP/90.Encl Withheld (Ref 10CFR2.740) ML20151B0181988-03-21021 March 1988 Forwards Proprietary Draft SER Re PRA for Westinghouse RESAR SP/90.Open Issues Noted Which May or May Not Be Resolvable During Preliminary Design Approval Stage of Review.Draft SER Withheld (Ref 10CFR2.790) ML20153B1831988-03-15015 March 1988 Forwards Questions 440.245 & 440.249 from NRC 880302 Request for Addl Info Re Reactor Sys Aspects of RESAR SP/90 Design. Response Requested within 30 Days ML20150C7491988-03-15015 March 1988 Informs of Relocation of NRR to One White Flint North, Rockville,Md.Official Mailing Address Unchanged.Project Managers Have New Locations & Phone Numbers.Tj Kenyon Still Project Manager for Facility ML20196G0451988-03-0202 March 1988 Forwards Request for Addl Info Re Review of Questions Q440.242 & 440.262 to RESAR SP/90 Pda Application.Response Requested within 60 Days of Ltr Date ML20149M1641988-02-19019 February 1988 Forwards Request for Addl Info Based on Review of Chapter 11.5 of Westinghouse Advanced PWR Fsar.Specific Location Info Re Effluent Monitoring Sys Also Required ML20149F6691988-02-11011 February 1988 Forwards Request for Addl Info,Consisting of Questions 280.1 Through 280.13 Re Fire Protection,To Complete Review of Section 9.5.1 of RESAR SP/90 Application ML20147C2941988-01-12012 January 1988 Approves Westinghouse 871217 Request for Withholding of Amend 3 to RESAR-SP/90 Pda Module 9, Instrumentation & Controls & Electric Power, Per 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954 as Amended ML20234E0171987-12-29029 December 1987 Advises That Proprietary Matl Provided at 871119 Meeting Re Advanced Control Room Design for RESAR SP/90 Will Be Treated as Proprietary Info Per 10CFR2.790 ML20234D9971987-12-29029 December 1987 Advises That Amend 2 to RESAR SP/90 Pda Module 1, Primary Side Safeguards Sys & Amend 1 to RESAR SP/90 Pda Module 13, Auxiliary Sys, Marked as Proprietary Will Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20237D5721987-12-17017 December 1987 Forwards Request for Addl Info Re Westinghouse Advanced PWR RESAR SP-90.Response Requested within 90 Days of Ltr Date ML20237B5121987-12-0909 December 1987 Forwards Request for Addl Info Re Pda Modules 1-16 of RESAR SP/90 ML20236Y5391987-12-0707 December 1987 Advises That 871026 Application Re Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 3, Introduction & Site, Marked as Proprietary,Should Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20236X4461987-12-0707 December 1987 Advises That Proprietary Amend 1 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 2, Regulatory Conformance, Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954 ML20236X3971987-12-0707 December 1987 Advises That 871008 Application Re Amend 3 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 16, Probabilistic Safety Study, Marked as Proprietary,Should Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20236D9051987-10-26026 October 1987 Forwards Safety Evaluation & Request for Addl Info Re Module 1,RESAR Section 6.5.4. Re Fracture Prevention of Containment Pressure Boundary.Module 4,Section 5.4.1.1 on Reactor Coolant Pump Flywheel Integrity Acceptable ML20236C8421987-10-23023 October 1987 Forwards Request for Addl Info Re Electrical Engineering Aspects of Design of Pda Module 9 of RESAR SP/90.Response Requested within 90 Days of Ltr Date ML20235S1641987-10-0101 October 1987 Approves Request for Withholding Westinghouse Comments on Draft Bnl/Nrc Rept on PRA for RESAR SP/90 from Public Disclosure,Per 10CFR2.790 ML20235R2891987-09-29029 September 1987 Discusses Operating Basis Earthquake Zero Period Acceleration Value for RESAR SP/90.Addl Justification to Support Exemption Request to Section V.2 of 10CFR100,App a or Commitment to Comply W/Regulation Requested ML20235F9581987-09-22022 September 1987 Forwards Request for Addl Info on Pda Module 7 of RESAR SP/90 Application in Order to Complete Review of Structural Aspects of Design.Response Requested within 90 Days ML20236K0301987-07-30030 July 1987 Advises That Application for Withholding Westinghouse 870615 Comments on Draft Bnl/Nrc Rept on PRA for RESAR SP/90,per 10CFR2.790,approved ML20236D2441987-07-24024 July 1987 Forwards Request for Addl Info Re Probabilistic Safety Study for RESAR SP/90 Applications.Response Requested within 60 Days ML20235E4611987-07-0606 July 1987 Forwards Request for Addl Info Re RESAR SP/90 Sabotage Protection Features,As Result of Review of Modules 2 & 3 Against Physical Protection Requirements of Current Regulations.Response Requested within 90 Days ML20215M0811987-06-22022 June 1987 Informs of Recent Reorganization of Nrr.Licensing of RESAR SP/90 Design Will Be Performed Through Standardization & Nonpower Reactor Project Directorate.Project Manager Will Be T Kenyon ML20216C1631987-06-19019 June 1987 Discusses Review Approach & Schedule for RESAR SP/90 Application.Integrated Review Rather than Modular Review Appropriate.Project Will Be Given Sufficient Priority to Meet Review Dates Listed in Encl Rev to Review Schedule ML20213G5901987-05-13013 May 1987 Informs That Proprietary Wapwr RESAR-SP/90 Pda Module 10, Containment Sys Should Be Withheld from Public Disclosure, Per Review of Application & 10CFR2.790 Criteria ML20210C3771987-04-30030 April 1987 Requests Review of Encl Draft Repts Entitled, Review of Westinghouse Advanced PWR (Wapwr) Probabilistic Safety Study & Assessment of Core Melt Progression & Fission Product Releases for Wapwr .... within 60 Days.W/O Encls ML20210R0401987-02-10010 February 1987 Advises That Based on Review of Amend 2 to Westinghouse Advanced PDR RESAR-SP/90 Pda Module 16, Probabilistic Safety Study, Per 861030 Submittal,Amend Will Be Withheld from Public Disclosure Per 10CFR2.790 ML20213A5631987-01-27027 January 1987 Grants Request for Withholding Amend 1 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 6/8, Secondary Side Safeguards Sys/Steam & Power Conversion, from Public Disclosure (Ref 10CFR2.790) ML20212F1741987-01-0202 January 1987 Approves 860829 Application to Withhold Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Preliminary Design Approval Module 9, Instrumentations & Controls & Electric Power, from Public Disclosure (Ref 10CFR2.790) ML20212H7731986-08-0505 August 1986 Approves Withholding Amend 3 to Westinghouse Advanced PWR RESAR-SP/90 Preliminary Design Approval Module 5, Reactor Sys (Ref 10CFR2.790),per 860604 Application & 821101 Affidavit ML20212G9141986-07-19019 July 1986 Approves Withholding of Amend 1 to Westinghouse Advanced PWR RESAR SP-90 Preliminary Design Approval Module 1, Primary Side Safeguards Sys (Ref 10CFR2.790), Per 860609 Application & 821101 Affidavit ML20211P1751986-07-11011 July 1986 Forwards Request for Addl Info Re RESAR-SP/90 Module 16 to Support back-end PRA Analysis.Info Requested within 30 Days of Ltr Date ML20195D4761986-05-28028 May 1986 Forwards Request for Addl Info Re RESAR-SP/90 Pda Module 16. Response within 30 Days of Ltr Date Requested ML20133C3821985-10-0202 October 1985 Forwards Questions Resulting from Review of Westinghouse Advanced PWR,RESAR-SP/90,Module 11 ML20136G3161985-08-13013 August 1985 Advises That RESAR-SP/90 Module 16, Probabilistic Safety Study & Module 11, Radiation Protection, Deemed Proprietary & Will Be Withheld from Public Disclosure Per 10CFR2.790,in Response to 850628 & 0712 Affidavits ML20133L6181985-08-0505 August 1985 Advises That Amend 2 to RESAR-SP/90 Preliminary Design Approval,Module 5, Reactor Sys, Will Be Withheld from Public Disclosure (Ref 10CFR2.790),per 850416 Request. Reasons Listed ML20133L6351985-08-0202 August 1985 Advises That RESAR-SP/90 Preliminary Design Approval,Module 9, Instrumentation & Controls & Electric Power, Will Be Withheld from Public Disclosure (Ref 10CFR2.790),per 850227 Request.Reasons Listed ML20132G9641985-07-19019 July 1985 Grants 850131 Request to Withhold RESAR-SP/90 Preliminary Design Approval Module 7, Structural/Equipment Design, from Public Disclosure Per 10CFR2.790 ML20132G6231985-07-10010 July 1985 Notifies That 850130 Request That Amend 1 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 3, Introduction & Site, Be Withheld (Ref 10CFR2.790) Granted 1989-09-12
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20247H2791989-09-12012 September 1989 Grants Request for Withholding of Response to NRC Draft SER Open Issues 1-41 Re Review of RESAR SP/90 Pda Application, Per 10CFR2.790(b)(5) ML20246H2151989-07-0606 July 1989 Approves Request to Withhold Amends 1a & 2 to Westinghouse Advanced PWR RESAR SP/90 Preliminary Design Approval Module 7, Structural/Equipment Design, (Ref 10CFR2.790) ML20236B3571989-03-0909 March 1989 Forwards Proprietary Draft SER Re Status of Review of Pda Application for RESAR SP/90.Encl Withheld (Ref 10CFR2.790) ML20195H1161988-11-22022 November 1988 Provides Guidance Re Scope of Design & NRC Review of RESAR SP/90 Design.Westinghouse Intends to Apply for Design Certification for RESAR SP/90 Design Currently Inhouse for Preliminary Design Approval Review NUREG/CR-5177, Forwards Proprietary Vols 1 & 2 to NUREG/CR-5177 Re Review of Westinghouse Advanced PWR Probabilistic Safety Study,For Review.Repts Withheld (Ref 10CFR2.790)1988-07-29029 July 1988 Forwards Proprietary Vols 1 & 2 to NUREG/CR-5177 Re Review of Westinghouse Advanced PWR Probabilistic Safety Study,For Review.Repts Withheld (Ref 10CFR2.790) ML20151Y1651988-04-28028 April 1988 Discusses Resolution of USIs & Medium & High Priority Generic Safety Issues for RESAR SP/90 Design.Westinghouse Should Reassess & Update Responses Provided in Module 2 & Address Any Addl Issues Prioritized Since 1983 to Present ML20153H5131988-04-25025 April 1988 Forwards Request for Addl Info Re Radiological Consequences of DBA for Response within 30 Days in Order to Complete Review of RESAR SP/90 Application ML20151L3131988-04-14014 April 1988 Forwards Request for Addl Info on RESAR SP/90 Re Radiological Consequences of Design Basis Accident,To Complete Review.Response Requested within 30 Days of Ltr Date ML20151H6521988-04-14014 April 1988 Forwards Request for Addl Info Re RESAR SP/90.Resolvability of Issues During Pda Phase of Review Concluded.Meeting Between NRC & Westinghouse to Discuss & Resolve Issues Prior to Issuance of Final SER Proposed ML20151Y0941988-03-28028 March 1988 Forwards BNL Draft Proprietary Rept, Independent Assessment of Severe Accident Risks for Westinghouse Advanced PWR Design (SP/90) Re Review of Module 16, Probabilistic Safety Study of RESAR SP/90.Encl Withheld (Ref 10CFR2.740) ML20151B0181988-03-21021 March 1988 Forwards Proprietary Draft SER Re PRA for Westinghouse RESAR SP/90.Open Issues Noted Which May or May Not Be Resolvable During Preliminary Design Approval Stage of Review.Draft SER Withheld (Ref 10CFR2.790) ML20153B1831988-03-15015 March 1988 Forwards Questions 440.245 & 440.249 from NRC 880302 Request for Addl Info Re Reactor Sys Aspects of RESAR SP/90 Design. Response Requested within 30 Days ML20150C7491988-03-15015 March 1988 Informs of Relocation of NRR to One White Flint North, Rockville,Md.Official Mailing Address Unchanged.Project Managers Have New Locations & Phone Numbers.Tj Kenyon Still Project Manager for Facility ML20196G0451988-03-0202 March 1988 Forwards Request for Addl Info Re Review of Questions Q440.242 & 440.262 to RESAR SP/90 Pda Application.Response Requested within 60 Days of Ltr Date ML20149M1641988-02-19019 February 1988 Forwards Request for Addl Info Based on Review of Chapter 11.5 of Westinghouse Advanced PWR Fsar.Specific Location Info Re Effluent Monitoring Sys Also Required ML20149F6691988-02-11011 February 1988 Forwards Request for Addl Info,Consisting of Questions 280.1 Through 280.13 Re Fire Protection,To Complete Review of Section 9.5.1 of RESAR SP/90 Application ML20147C2941988-01-12012 January 1988 Approves Westinghouse 871217 Request for Withholding of Amend 3 to RESAR-SP/90 Pda Module 9, Instrumentation & Controls & Electric Power, Per 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954 as Amended ML20234D9971987-12-29029 December 1987 Advises That Amend 2 to RESAR SP/90 Pda Module 1, Primary Side Safeguards Sys & Amend 1 to RESAR SP/90 Pda Module 13, Auxiliary Sys, Marked as Proprietary Will Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20234E0171987-12-29029 December 1987 Advises That Proprietary Matl Provided at 871119 Meeting Re Advanced Control Room Design for RESAR SP/90 Will Be Treated as Proprietary Info Per 10CFR2.790 ML20237D5721987-12-17017 December 1987 Forwards Request for Addl Info Re Westinghouse Advanced PWR RESAR SP-90.Response Requested within 90 Days of Ltr Date ML20237B5121987-12-0909 December 1987 Forwards Request for Addl Info Re Pda Modules 1-16 of RESAR SP/90 ML20236Y5391987-12-0707 December 1987 Advises That 871026 Application Re Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 3, Introduction & Site, Marked as Proprietary,Should Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20236X4461987-12-0707 December 1987 Advises That Proprietary Amend 1 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 2, Regulatory Conformance, Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954 ML20236X3971987-12-0707 December 1987 Advises That 871008 Application Re Amend 3 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 16, Probabilistic Safety Study, Marked as Proprietary,Should Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20236D9051987-10-26026 October 1987 Forwards Safety Evaluation & Request for Addl Info Re Module 1,RESAR Section 6.5.4. Re Fracture Prevention of Containment Pressure Boundary.Module 4,Section 5.4.1.1 on Reactor Coolant Pump Flywheel Integrity Acceptable ML20236C8421987-10-23023 October 1987 Forwards Request for Addl Info Re Electrical Engineering Aspects of Design of Pda Module 9 of RESAR SP/90.Response Requested within 90 Days of Ltr Date ML20235S1641987-10-0101 October 1987 Approves Request for Withholding Westinghouse Comments on Draft Bnl/Nrc Rept on PRA for RESAR SP/90 from Public Disclosure,Per 10CFR2.790 ML20235R2891987-09-29029 September 1987 Discusses Operating Basis Earthquake Zero Period Acceleration Value for RESAR SP/90.Addl Justification to Support Exemption Request to Section V.2 of 10CFR100,App a or Commitment to Comply W/Regulation Requested ML20235F9581987-09-22022 September 1987 Forwards Request for Addl Info on Pda Module 7 of RESAR SP/90 Application in Order to Complete Review of Structural Aspects of Design.Response Requested within 90 Days ML20236K0301987-07-30030 July 1987 Advises That Application for Withholding Westinghouse 870615 Comments on Draft Bnl/Nrc Rept on PRA for RESAR SP/90,per 10CFR2.790,approved ML20236D2441987-07-24024 July 1987 Forwards Request for Addl Info Re Probabilistic Safety Study for RESAR SP/90 Applications.Response Requested within 60 Days ML20235E4611987-07-0606 July 1987 Forwards Request for Addl Info Re RESAR SP/90 Sabotage Protection Features,As Result of Review of Modules 2 & 3 Against Physical Protection Requirements of Current Regulations.Response Requested within 90 Days ML20234B1231987-06-29029 June 1987 Final Response to FOIA Request.App C Documents Re Evaluation of RESAR-SP/90 Completely Withheld (Ref FOIA Exemption 5) ML20215M0811987-06-22022 June 1987 Informs of Recent Reorganization of Nrr.Licensing of RESAR SP/90 Design Will Be Performed Through Standardization & Nonpower Reactor Project Directorate.Project Manager Will Be T Kenyon ML20216C1631987-06-19019 June 1987 Discusses Review Approach & Schedule for RESAR SP/90 Application.Integrated Review Rather than Modular Review Appropriate.Project Will Be Given Sufficient Priority to Meet Review Dates Listed in Encl Rev to Review Schedule ML20215E8481987-06-17017 June 1987 Partial Response to FOIA Request for Records.Apps a & B Documents Available in Pdr.App B Document Encl ML20213G5901987-05-13013 May 1987 Informs That Proprietary Wapwr RESAR-SP/90 Pda Module 10, Containment Sys Should Be Withheld from Public Disclosure, Per Review of Application & 10CFR2.790 Criteria ML20210C3771987-04-30030 April 1987 Requests Review of Encl Draft Repts Entitled, Review of Westinghouse Advanced PWR (Wapwr) Probabilistic Safety Study & Assessment of Core Melt Progression & Fission Product Releases for Wapwr .... within 60 Days.W/O Encls ML20210R0401987-02-10010 February 1987 Advises That Based on Review of Amend 2 to Westinghouse Advanced PDR RESAR-SP/90 Pda Module 16, Probabilistic Safety Study, Per 861030 Submittal,Amend Will Be Withheld from Public Disclosure Per 10CFR2.790 ML20213A5631987-01-27027 January 1987 Grants Request for Withholding Amend 1 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 6/8, Secondary Side Safeguards Sys/Steam & Power Conversion, from Public Disclosure (Ref 10CFR2.790) ML20212F1741987-01-0202 January 1987 Approves 860829 Application to Withhold Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Preliminary Design Approval Module 9, Instrumentations & Controls & Electric Power, from Public Disclosure (Ref 10CFR2.790) ML20212H7731986-08-0505 August 1986 Approves Withholding Amend 3 to Westinghouse Advanced PWR RESAR-SP/90 Preliminary Design Approval Module 5, Reactor Sys (Ref 10CFR2.790),per 860604 Application & 821101 Affidavit ML20212G9141986-07-19019 July 1986 Approves Withholding of Amend 1 to Westinghouse Advanced PWR RESAR SP-90 Preliminary Design Approval Module 1, Primary Side Safeguards Sys (Ref 10CFR2.790), Per 860609 Application & 821101 Affidavit ML20211P1751986-07-11011 July 1986 Forwards Request for Addl Info Re RESAR-SP/90 Module 16 to Support back-end PRA Analysis.Info Requested within 30 Days of Ltr Date ML20195D4761986-05-28028 May 1986 Forwards Request for Addl Info Re RESAR-SP/90 Pda Module 16. Response within 30 Days of Ltr Date Requested ML20133C3821985-10-0202 October 1985 Forwards Questions Resulting from Review of Westinghouse Advanced PWR,RESAR-SP/90,Module 11 ML20136G3161985-08-13013 August 1985 Advises That RESAR-SP/90 Module 16, Probabilistic Safety Study & Module 11, Radiation Protection, Deemed Proprietary & Will Be Withheld from Public Disclosure Per 10CFR2.790,in Response to 850628 & 0712 Affidavits ML20133L6181985-08-0505 August 1985 Advises That Amend 2 to RESAR-SP/90 Preliminary Design Approval,Module 5, Reactor Sys, Will Be Withheld from Public Disclosure (Ref 10CFR2.790),per 850416 Request. Reasons Listed ML20133L6351985-08-0202 August 1985 Advises That RESAR-SP/90 Preliminary Design Approval,Module 9, Instrumentation & Controls & Electric Power, Will Be Withheld from Public Disclosure (Ref 10CFR2.790),per 850227 Request.Reasons Listed ML20132G9641985-07-19019 July 1985 Grants 850131 Request to Withhold RESAR-SP/90 Preliminary Design Approval Module 7, Structural/Equipment Design, from Public Disclosure Per 10CFR2.790 1989-09-12
[Table view] |
Text
I
.
+ UNITED STATES
! g NUCLEAR REGULATORY COMMISSION
+
- WASHINGTON. D. C. 20666 L :j k . o. . . p# November 22, 1988 Docket No. 50-601 l Mr. W. J. Johnson Nuclear Safety Department Westinghouse Electric Corporation Water Reactor Division Box 355 Pittsburg, Pennsylvania 15230
Dear Mr. Johnson:
SUBJECT:
SCOPE OF DESIGN AND SCOPE OF STAFF REVIEW CF RESAR SP/90 Although not formally documented, it is the staff's understanding that Westinghouse intends to apply for design certification for the RESAR SP/90 design currently inhouse for a Preliminary Design Approval (PDA) review. This letter provides guidance regarding the scope of the design and the scope of the staff's review should you decide to pursue such an application. We request that you use it in preparing the application for an FDA and the accompanying Licensing Review Basis.
Scope of Design In the proposed regulation 10 CFR Part 52, the staff has defined the desired scope of designs for standard plants requesting certification. The proposed regulation states that "Ideally, the designs for which certification is sought will be for essentially complete plants." It also states that "the NRC will give priority in allocation of resources to support reviews and approval of applications for essentially corplete plants."
Should you decide to pursue the application for design certification of RESAR SP/90, we request that the application be for a design whose scope is essentially complete and consistent with the proposed 10 CFR Part 52 in order for us to give appropriate priority to your application's review.
Scope of Staff Review The staff will be considering issues that may go beyond the Standard Review Plan involving such subjects as fire protection, electrical systems and others.
Some of these items are briefly discussed in the enclosure to this letter.
The draft and final SER regarding the review of the PDA application for RESAR SP/90 subjectsmay(already reflect staff i.e.,fireprotection). Theseconsideration ofaddressed issues will be these issues for certain in the Licensing Review Basis document after the decision on the PDA application is reached.
$$k $(($ b!bb i d n o I
L
Mr. 'W. J. Johnson November 22, 1988 a' Because your position concerning design certification of the RESAR SP/90 has not been formally documented, we request you inform us of ycur intentions in this matter along with your schedule for submitting your application, including the submittal of the Final Reference Safety Analysis Report, and the scope of
- the design within 30 days from receipt of this letter. The schedule may be discussed in terms of receipt of the PDA for the facility design.
i Sincerely, I
j Dennis M. Crutchfield
, Acting Associate Dir tor for Projects
! Office of Nuclear Reactor Regulation
Enclosure:
As stated i cc w/ enc 1:
j- See next page 6
k i
!l I
i l
Mr.'W. J. 'ohnson Docket No. 50-601 RESAR-SP/!t ec:
Trevor Pratt Brookhaven National Laboratory Building 130 Upton, New York 11973 Mr. William Schivley Westinghouse Electric Corporation ECE-410 Mail Stop 4-08 Box 355 Pittsburgh, Pennsylvania 15230
ENCLOSURE POTENTIAL REVIEW SUBJECTS FOR STANDARD PLANT DESIGNS The staff met to discuss major issues related to the review of advanced light water reactor applications. Included in the discussions were issues in which the scope of the staff's acceptance criteria may go beyond that of the current Standard Review Plan to e mure improved design, construction, and/or operation of these advanced plants. The staff's positions on these matters will be .
l finalized during the development of the Licensing Review Basis (LRB) for the Westinghouse designs. The following are brief discussions of the staff's current views on some of these matters.
i
- 1. 60 YEAR LIFE:
For applications proposing a 60-year deitgn life, the staff would review the designs for a 60-year life notwithstanding the fact that a 40-year license term limitation is presently in the regulations. It is the applicants' responsibility to identify the components and systems which '.
are affected. Applications for design certific3 tion will have to provide information and programs to support design life, and the reviews for such issues as fatigue, corrosion and themal aging.
- 2. FIRE PROTECTION:
Improved fire protection criteria are needed in view of the significant ,
contribution of fires to core melt probability. The current Appendix R -
and BTP 9-5.1 requirements (e.g. 20 ft, separation) should be replaced by ;
a requirement for safe shutdown capability in the event of a corplete loss of any fire area.
- 3. TECHNICAL SPECIFICATIONS:
The staff considers that (1) proposed Technical Specifications should be developed as early as practicable, but be submitted no later than the FDA application,(2)proposedlechnicalSpecificationsrepresentativeofthe design should be submitted for review and approval by the staff as part of the FDA submittal, and will be included in the Design Certification process, and (3) applicants should identify design features that are necessary for testing and maintenance during operation without challenging safety systems.
The Technical Specifications should be developed, where practicable, based upon risk and reliability considerations.
- 4. TESTING AND MAINTENANCE:
1 Certification of a design will be based in part upon a probabilistic risk assessment of that design. In that the validity of a PRA is highly dependent on the reliability of systems, structures and components, the
. staff requires assurance that programs will be implemented which will ensure that the reliability of those systems, structures and components l (assured in analyses) will be maintained throughout plant life. There-fore, a program to assure design reliability must be provided as part of ;
i the FDA application. This program which will be certified as part of the design should address items such as (1) the Technical Specifications and ISI/IST,(2)theMaintenanceProgram,(3)PlantProcedures,and(4)
Security.
- 5. INDUSTRY USE OF MAAP:
Review of the NAAP code is unnecessar MELCOR and Source Term Code STCP) Package (y since codes the staff can apply its own in its evaluations. ,
- 6. STATION BLACKOUT AND ELECTRICAL SYSTEM:
Future ALWRs should adopt improved electrica, systemt to ensure a safe shutdown of the reactor. These systems should provide, in part, for diverse power sources in order to eliminate the concerns related to !
station blackout. General guidelines will be developed and finalized '
during development of the LRB.
- 7. LEAK BEFORE BREAK:
Leak before break can be considered where justified. Where applicable, designs must address good practices in order to maintain steam generator tube integrity. Also, designs should address issues of material embrittle-ment associated with current vessel materials and vessel supports. l A new rule and draf t SRP Section 3.6.3 have been issued. The EPRI design requirements has adopted these criteria. ,
- 8. SOURCE TERMS:
The staff is concerned that the licensing basis source term "TID 14844' is not consistent with current knowledge. Therefore, with EPRI input, realistic source terms will be established to be uniformly applied to future ALWRS.
- 9. PHYSICAL SECURITY:
Sabotage should be addressed in all future ALWRS applications. As a i minimum, infornation should be provided to demonstrate the existence of adequate physical barriers to protect vital equipment in accordance with 10 CFR 73.55(c) in accordance with and to identify 10 CFR 73.05 d).(access control points to all vital areas [
4
- 10. O_BE/0YNAMIC ANALYSIS HETH005:
The staff agrees that the OBE should not control the design of safety 4 systems as now required by 10 CFR 100 Appendix A. The staff will take
- this issue under consideration as part of the design certification f
- process.
1
i 11. TYPE C CONTAINMENT LEAKAGE RATE:
Containment leakage is acknowledged by the staff as being a function of containment pressure.
- 12. HYDROGEN GENERATION:
10 CFR 50.34(f) related to the issue of a 100% r,etal water reaction will be invoked for ALWRs consistent with Commission Policy and proposed 10 CFR Part 52.
1 I
re, < #l Mr. W. J. Johnson November 22, 1988 Because your position concerning design certification of the RESAR SP/90 has not been formally documented, we request you inform us of your intentions in this matter along with your schedule for submitting your application, including the submittal of the Final Reference Safety Analysis Report, and the scope of the design within 30 days fron receipt of this letter. The schedule may be discussed in terms of receipt of the PDA for the facility design.
Sincerely,
/s/
Dennis M. Crutchfield Acting Associate Director for Projects Office of Nuclear Reactor Regulation
Enclosure:
As stated i cc w/ enc 1:
See next page DISTRIBUTION:
Docket File NRC PDR PDSNP R/F EHylton TKenyon EJordan BGrimes OGC-Rockville ACRS (10)
LRubenstein GHolahan DCrutchfield l
l i
4 i
1 (WSCOPE) *SEE PREVIOUS C0hCURRENCE
! ig6h}un LRubenstein GHolahan chfield 11/15/88 11/15/08 11/16/88 11/16/88 11/16/88 DCx{/CE 11//
i
- r
. i
- Mr. W. J. Johnson i 1 i
- Because your position concerning design certification of the RESAR SP/90 has i not been formally documented, we request you inforin us of your intentions in '
this matter along with your schedule for submitting your application, including
'l the submittal of the Final Reference Safety Analysis Report, and the scope of ,
4 the design within 30 days from receipt of this letter. Tne schedule may be ;
i discussed in terms of receipt of the PDA for the facility design. !
l i j Sinewely, l
4 i
Dennis M. Crutchfield j Acting Associate Director for Projects
- Office of Nuclear Reactor Regulation ;
4 i
Enclosure:
j As stated !
cc: See next page
. DISTRIBUTION: I
- Docket File !
! NRC PDR j PDSNP R/F Elfylton TKenyon
! EJordan BGrimes
! OGC-Rockville r i
ACRS(10) i
! LRubenstein l GHolahan i 0Crutchfield 1
5P F$ SNP 0:PDb ADR p 0:DR$P (A)ADP {
on TKe'nyon Chiller LRubenstc'n Holahan 0CRutchfield i 11/fy/88 11&f/88 11//c /88 11/<'4 /88 114b /88 11/ /88 {
l.7t'u H L l 1
I I
i
_ _ _ _ . _ _ _ _ -'