ML20148T501

Forwards Amend 46 to Std Safety Analysis Rept.Requests That NRC Conduct 1 Review of NSSS Designs for Each of 3 Gessars Because They Are Identical.Fees Should Not Be Assessed for Estensions,In Order to Foster Standardization

ML20148T501
Person / Time
Site:	05000447
Issue date:	11/30/1978
From:	Sherwood G GENERAL ELECTRIC CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20148T502	List: ML20148T501 ML20148T503
References
NUDOCS 7812050220
Download: ML20148T501 (11)

Text

I

~

..t wuC' era suenov GEN ER AL h ELECTRIC PROJECTS DIVISION GENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE, CAUFORNIA 95125 MC682,(408)925-5040 MFN 424-78 November 30, 1978 U._S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation )

Washington, D. C. 20555 '

Attention: H. R. Denton, Director )

Gentlemen:

SUBJECT:

IN THE MATTER OF EXTENSION OF PRELIMINARY DESIGN APPROVAL FOR THE GENERAL ELECTRIC STANDARD SAFETY ANALYSIS REPORT (GESSAR), DOCKET NO. STN 50-447

Reference:

1) Letter to Edson G. Case from Glenn G. Sherwood, j March 20, 1978, Application for Extension of Pre- l 11minary Design Approvals

2) Letter to Glenn G. Sherwood from Roger S. Boyd, October 13, 1978 Extension Review Matters' for Preliminary Design Approvals Enclosed,pleasefindthree-(3)originalcopies(transmittedunder separate cover are 60 conformed copies) of Amendment No. 46 to the General Electric Standard Safety Analysis Report (238 Nuclear Island l GESSAR) for the above numbered application. I In GE's letter of March 20,1978 (Reference 1), General Electric re-quested an extension of the Preliminary Design Approvals (PDA's) for each of the GESSAR dockets.

On October 13, 1978, theNRCissuedaletter(Reference 2)statingthat each application for a PDA extension will be subject to an assessment of the design with respect to regulatory guidance issued since the regu-latory requirements cutoff date for the PDA in question. This letter included a tabulation of each Category I II, III and IV matters approved since the March 1,1974, the regulatory requirements cutoff date for the GESSAR-238 Nuclear Island.

0 9 p ,o 4 .r8120 son o 3 4 L . i

GENER AL h ELECTRIC Mr. H. R. Denton Page 2 November 30, 1978 This amendment contains General Electric's assessments of the Category I, II, III and IV matters ag-inst the GESSAR-238 Nuclear Island Design in the form of a new Appendix C. We have also provided a listing of these matters in Attachment 1 which identifies their applicability to the NSSS scope. In view of the fact that the 251 and 238 size BWRs contain identical NSSS designs (except for size differences), and since the regulatory guide cutoff date of October 1975 has been applied to each of the NSSS designs, we request that the NRC Staff conduct one review of the NSSS for each of the three GESSARs (238 NI, 251 NSSS, and 238 NSSS). Accordingly, submittal of the 238 Nuclear Islard assessment package (Appendix C) will provide the basis for the NRC Staff granting l extensions of PDA-1, PDA-9, and PDA-10. We believe conducting a common j review of the three identical NSSS designs on the NI GESSAR docket I optimizes the staff review time and furthers the benefits of standardization.

As you recall, the Nuclear Island GESSAR incurred the most thorough, exhaustive, and detailed review ever conducted on the BWR. It is not smprising, then, that our review of the Category I, II, III and IV macters revealed that each of the matters were previously treated during the PDA review. We have found that the Nuclear Island GESSAR design incorporates resolution of the concerns enumerated in the Staff regu-latory guidance provided in the enclosure to the October 13, 1978 letter.

We have found the design to be acceptable as demonstrated in the assess-ments contained in Appendix C without requiring design changes to our previously reviewed GESSAR designs.

Your letter of October 13, 1978, states that the Commission has under consideration the matter of whether licensing fees will be assessed for PDA extensions. General Electric strongly believes that fees should not be assessed. It is now apparent that, because of the low number of new applications submitted to the NRC during the approval period, the present three year approval duration does not allow a reasonable return on investment. Both the staff and the industry have invested substan-tial resources to stabilize the licensing process through standardi-zation. Accordingly, we believe the Commission should encourage further use of standardization by not assessing fees for extending the current PDA's to a full five year duration.

We believe Amendment 46 contains sufficient information as required to enable the staff to issue PDA extensions for all three GESSARs prior to December 22, 1978, the expiration date for the Nuclear Island GESSAR.

.ameesame

GENER AL h ELECTRIC Mr. H. R. Denton Page 3 November 30, 1978 In addition, we would be pleased to meet with members of your staff to discuss the procedural requirements for extending the PDAs and to obtain clarification of the fee aspects of the PDA extensions. It is our desire that this meeting be held in early December 1978.

Very truly yours, Glenn G. Sherwood, Manager Safety & Licensing Operation GGS:mh/1652-1654 Attachment cc: R. S. Boyd (w/o Attachment)

R. J. Mattson (t//v Attachment)

C. J. Heltemes (w/o Attachment)

W. F. Kane L. S. Gifford w,r.

. _ . _ _ . . ~ . _ _ . . . . _ _ _ . . _ _ _ _ _ _ - _ . _ _ __ _ _ _ _ _ . _ . _ _ _ _ _ _ .._.

ATTACHMENT I LIST OF PDA ASSESSMENT MATTERS-AND l THEIR SCOPE )

Category I Matters Scope Regulatory Guide No. & Title NSSS NI 3.7 Control of Combustible Gas X 1.9 Diesel-Generator Design X 1.20 . Preop Vibration Testing of RPV Interna's X X 1.28 Quality Assurance Program Requirements (Design & Constr.) X X 1.29 Seismic Design Classification X X 1.31 Control of Ferrite in Welds X X- 1 1.32 Electric Power Systems X X 1.33 QA Program Requirements (Operation) X X 1.35 Inspection of Prestressed Concrete NA 1.38 QA (Packaging, Shipping, etc.) X X 1.39 Housekeeping (Applicant) 1.52 Criteria for ESF Filter Systems X 1.63 Containment Electric Penetrations X X 1.64 QA Requirements for Design X X 1.68 Initial Preop and Starup Tests X X 1.68.1 Test of Feedwater System X X 4 1.72 Spray Pond Plastic Piping Applicant 1.84 Code Case Acceptability (Design) X X 1.85 Code Case Acceptability (Material) X X 1.90 Inspection Prestressed Concrete NA i

a Category I Matters (Con't) Scope .

Regulatory Guide No. & Titic. NSSS NI 1.92 Combining Seis,aic Responses and Special X X Components 1.94 QA - Structural Concrete & Steel X 1.95 Control Room Protection - Chlorine X 1.99 RPV Radiation Damage X X 1.100 Seismic Qualification of Electric Equipment X X 1.103 Post Tensioned Core Stressed Concrete NA 1.106 Thermal Overload Protection, Valve Motors X X 1.107 Qualifications for Cement Grouting NA j 1.116 QA - Mechanical Equipment X X 1.118 Testing of Electric Power & Protection X X 1.120 Fire Protection X X 1.122 Flo,r Design Response Spectro X X 1.126 Analysis Methods for Full Densification X 1.128 Storage Batteries (' Design) X X 1.129 Storage Batteries (Maintenance) X X 1.131 Tests of Electric Cables, Splices & Applicant Connections 1.134 Medical. Certification for Operators Applicant 1.135 Normal Water Level & Discharge X 1.136 Material for Conrete Containments NA 1.137 fuel Oil System for Diesels X NUREG-0102 Int'rfaces for Standard Designs X X (SRPl.8) 1.138 Soil nalysis Applicant 1.XXX Permanent Dewatering Systems Applicant

..*e.- - - - . - - - ,y -- ,--,-e.. .- - - - - - , - - , -

Category I Hatters (Cont'd) Scope Regt atory Guide No. & Title NSSS NI 1.140 Design and Testing of Normal Vent X 1,142 Safety Related Concrete Structures X X 8.19 Occupatonal Dose X X RSBS-2 Reactor Coolant Overpressure Protection NA 1

9 8

i e

I 1 I F

l I

Category II Matters Scope Regulatory Guide No. & Title, NSSS NI 1.27 Ultimate Heat Sink X l

1.52 Criteria for ESF Filter Systems X 1.59 Design Basis Floods X 1.91 Transportation Route Explosions X -

, 1

.1.97 Post-Accident Instrumentation X X l

1.102 Flood Protection X j 1.105 Instrument Setpoints (' X X 1.108 Diesel Generator Testing J

1.115 Protection Against Turbine Missiles X 1.117 Tornado Design Classification X 1.124 Design of Class I Linear Components X X 1.130 Class I Plate & Shell Component Supports X X  !

1.137 Fuel Oil Systems for Diesels X 8.8 Occupational Radiation (ALARA) X X BTP-9.5-1 Guidelines for Fire Protection X X BTP-MTLB 5 Stress Corrosion Cracking X X

/

o;

Category III Matters Scope Regulatory Guide No. & Title NSSS NI 1.56 Maintenance of Water Purity X X 1.68.2 Demonstrate Remote Shutdown X X 1.99 RPV Radiation Damage X X 1.101 Emergency Planning Applicant 1.114 Guidance on Being Operator X X 1.121 Plugging PWR Steam Generator Tubes NA l 1.127 Inspection of Water Control Structures Applicant SRP-5.4.7 Residual Heat Removal System X X 1.141 Primary Containment Isolation X X

.158-5-2 Overpressure Protection PWR's NA 1

A D

l l

fi. ,,

l Category IV Matters Scope Regulatory Guide No. & Title NSSS NI 1.12 Instrumentation for Earthquakes X X 1.13 Input Fuel storage Facility X 1.14 Reactor Coolant Pump Flywheel Integrity NA 1.75 Physical Independence of Electrical Systems X X 1.76 Design Basis Tornado X l 1.79 ECCS Testing - PWR's NA i 1.80 Preop Test instrument Air X  !

1 1.82 Containment Sumps X 1.83 Inspection of Steam Generator Tubes NA 1.89 Qualification of IE Equipment X X, 1.93 Availability of Electric Power Sources X 1.104 Overload Cranes X SRP 5.4.2.1 PWR Water Chemistry NA 6.2.1 Containment Functional Design X 6.2.5 Combustible Gas Control In Containment X 6.2.3 Secondary Containment Functional Design X 6.2.4 Containment Isolation System X 9.1.4 Overhead Fuel Handling System X X 10.4.9 Auxiliary Feedwater System (PWR) NA 4 3.5.5 8arrier Design Procedure X 3.7.1 Seismic Input X X 3.7.2 Seismic System Analysis X X 3.7.3 Seismic Subsystem Analysis X X 3.8.1 Concrete Containment NA I

Category IV Matters (Cont'd) Scope Regulatory Guide No. & Title NSSS NI 3.8.2 Steel Containment X 3.8.3 Concrete & Steel Internal Structures in X X Containment 3.8.4 Other Seismic Category I Structures X 3.8.5 Design Criteria for Foundations X

3. 7 Seismic Design Requirements X X 3.3.2 Tornado Loads Effects X X 3.4.2 Dynamic Effects of Wave Action X X 10.4.7 Water Hammer for Steam Generators N/A )

4.4 Thermal-Hydraulic Stability X l

l 5.2.5 Reactor Core Pressure Boundary Leakage -

l Detection X X t 3.2.2 MSIV Leakage Control Systems X 3.5.3 Quality of Reinforced Concrete Steel X 3.7.1 Response Spectra in Vertical Direction X 3.8.1 BWR Mark III Containment Pool Dynamics X 3 8'.4 Air Blast Loads X X 3.5.3 Tornado Missile Impact X 6.3 .

Passive failures During Long Term Cooling LOCA X X 15.1.5 Long Term Recovery from Steam Line Break X X i

5.4.6 Pump Operability Requirements X X 3.5.1 Gravity Missiles Inside Containment X 4.4 Core Thermal Hydraulic Analysis X 8.3 Degraded Grid Voltage Conditions Applicant 6.2.1.2 Asymmetric Loads on Containment Subcompartments X

Category IV Matters (Cont'd) Scope I Regulatory Guide No. & Title NSSS NI 6.2.6 Containment Leak Testing X i l

6.2.1.4 Containment Response Due to Main Steam Line Break X l Without MSLIV Closure 3.6.1 Main Steam & Feedwater Pipe Failures X X 9.222 Design Requirements for Cooling Water )

to Pumps X X j 10.4.7 Water Hammer - Steam Generators N/A 3.11 Environmental Control System for Safety Related Equipment X X

.