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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20153G9561998-09-25025 September 1998
Nonproprietary Figure 1-3 of PCS-T2R-050, Large-Scale Test Data Evaluation
ML20236F6911998-05-29029 May 1998
Rev 6 to AP600 Emergency Response Guidelines, Including Guidelines SDG-1,SDG-2,SDG-3 & Change Pages for Background Documents AE-1,SDF-0.1,SDG-1,SDG-2 & SDG-3
ML20198S7471997-10-31031 October 1997
Rev 5 to AP600 Emergency Response Guidelines
ML20212A9081997-10-16016 October 1997
Proposed Tech Specs 3.7.9 Re Fuel Storage Pool Makeup Water Sources
ML20198S8741997-08-31031 August 1997
Proposed Tech Specs,Incorporating NRC Comments Resolved During 971027 Telcon
ML20202B4411997-08-31031 August 1997
Proposed Tech Specs 3.3.1 & 3.3.2 Re Changes to Reflect Ssar Chapter 15 Analyses Setpoints
ML20216C2581997-08-31031 August 1997
Proposed Tech Specs 3.4.10 Re RCS Leakage Detection Instrumentation
ML20211M9021997-08-31031 August 1997
Proposed Tech Specs 3.7.2 Re MSIVs
ML20216D2331997-08-29029 August 1997
Proposed Tech Specs,Providing Draft RCS PIV Integrity TS
ML20216D2511997-08-28028 August 1997
Proposed Tech Specs,Modifying SR 3.6.9.4 & SR 3.6.9.2, Consistent W/Nrc Example Provided in Question 68 & Consistent w/NUREG-1432
ML20198G5641997-08-27027 August 1997
Proposed Tech Specs Pages 5.0-15,5.0-21 & IV to Reporting Requirements 5.6.1 to Be Incorporated in Rev 7 of AP600 TS to Be Transmitted to NRC on 970902
ML20198G5951997-08-27027 August 1997
Proposed Tech Specs Re Response to NRC Reactor Sys Branch RAI Re AP600 TS
ML20210P2921997-08-19019 August 1997
Proposed Tech Specs,Reflecting Responses to Comments on AP600 TS Containment Sys
ML20210P4181997-08-19019 August 1997
Proposed Tech Specs 3.8.1 & 3.8.5,documenting Changes Agreed Upon W/Nrc Re Electrical Power Sys
ML20210Q0581997-08-19019 August 1997
Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & Engineered Safety Features Actuation
ML20149H5111997-07-0101 July 1997
Rev 4 to GW-GJR-100, AP600 Emergency Response Guidelines
ML20140C4571997-06-0606 June 1997
Proposed Tech Specs Providing Explanation for AP600 TS Completion Times & Surveillance Frequencies Which Are Not Identical to Standardized TS Completion Times & Surveillance Frequencies
ML20141B6551997-05-31031 May 1997
to AP600 Emergency Response Guidelines
ML20141H1501997-05-16016 May 1997
Rev 3 to DE-AC03-90SF18495, Simplified Passive Advanced LWR Plant Program,AP600 Certified Design Matl
ML20141C6961997-05-0909 May 1997
Proposed Tech Specs LCO 3.0.2 & 3.0.3,reflecting Compliance W/Nrc Staff Position of Ltr
ML20137C6781997-03-19019 March 1997
Proposed Tech Specs Rev Re LCO 3.0.3,Key Licensing Issue 19 Deleting Exemption for Entry
ML20134A5621997-01-15015 January 1997
Rev 2 to Design Reviews
ML20141B1351996-08-31031 August 1996
Proposed Tech Specs Re Advance Markup of AP600
ML20141K2571996-08-31031 August 1996
Proposed Tech Specs 3.7.6 Re Main Room Habitability Sys
ML20117J1071996-08-30030 August 1996
Revised Background Info for AP600 Emergency Response Guidelines,Including Rev 1A to EA-1,Rev 1A to AES-1.1,Rev 1A to AES-1.2 & Rev 1A to AE-2
ML20116A4421996-07-31031 July 1996
Westinghouse AP600 Chapter 14,Initial Test Program
ML20116J8331996-07-31031 July 1996
Rev 2 to SDG-6, AP600 Response to Unexpected RCS Temp Changes During Shutdown
ML20116J8231996-07-31031 July 1996
Rev 2 to SDG-5, AP600 Response to Cold Overpressure During Shutdown
ML20116J8151996-07-31031 July 1996
Rev 2 to SDG-4, AP600 Response to Increasing Nuclear Flux During Shutdown
ML20116J8101996-07-31031 July 1996
Rev 2 to SDF-3, AP600 Response to High Containment Radiation During Shutdown
ML20116J7941996-07-31031 July 1996
Rev 2 to SDF-0.1, AP600 Shutdown Safety Status Tree During Shutdown
ML20116J8031996-07-31031 July 1996
Rev 2 to SDG-2, AP600 Response to Loss of Rns During Shutdown
ML20116J8001996-07-31031 July 1996
Rev 2 to SDF-1, AP600 Response to Loss of RCS Inventory During Shutdown
ML20111B0501996-05-0101 May 1996
Proposed Tech Specs 5.1,5.2 & 5.3
ML20107C7421996-04-0808 April 1996
Non-proprietary Man-In-The-Loop Test Plan Description
ML20107C7401996-04-0808 April 1996
Non-proprietary Programmatic Level Description of AP600 Human Factors Verification & Validation Plan
ML20101N8341996-03-31031 March 1996
Non-proprietary Version of AP600 Reactor Internals Flow-Induced Vibration Assessment Program
ML20096F1261996-01-15015 January 1996
Revised Pages 1-3 & 1-4 of Rev 1 to AP600 SPES-2 Test Analysis Rept
ML20095E6721995-12-0808 December 1995
Plan to Resolve AP600 PRA MAAP4 Success Criteria Issues
ML20091M3831995-07-31031 July 1995
SPES-2 Hot Preoperational Test H-06 Inadvertent ADS Stage 1 Actuation (with No ADS Stage 4)
ML20134A5501995-06-0101 June 1995
Rev 2 to AP600 Sys Specification Documents
ML20134A6001995-06-0101 June 1995
Rev 1 to Control of Subcontractor Submittals
ML20083R3451995-05-31031 May 1995
Nonproprietary Large-Scale Test Data Evaluation
ML20085E4261995-05-31031 May 1995
AP600 Emergency Response Guidelines
ML20083B8901995-02-28028 February 1995
Rev 3 to Simplified Passive Advanced Light Water Reactor Plant Program AP600 Probabilistic Risk Assessment
ML20073C9101994-08-26026 August 1994
Rev 2 to WCAP-13234, Test Spec for Long-Term Cooling Test
ML20065M2971994-05-31031 May 1994
Draft Advanced Reactor Research & Development Programs 5-Yr Plan for Advanced Reactor Activities Under Energy Policy Act of 1992
ML20069A3761994-05-0606 May 1994
Rev 6 to AP600 Design Certification Test Program Overview
NRC-94-4120, Rev 0 to in Situ Check Valve Test Rept (Fall Outage 93)1994-04-27027 April 1994
Rev 0 to in Situ Check Valve Test Rept (Fall Outage 93)
NRC-94-4116, Nonproprietary Passive Containment Cooling Sys Bench Scale Wind Tunnel Test1994-04-21021 April 1994
Nonproprietary Passive Containment Cooling Sys Bench Scale Wind Tunnel Test
1998-09-25
[Table view]
Category:TEST REPORT
[Table view] |
Text
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LARGE-SCALE TEST DATA EVALUATION a,b ass,ar m 4rj l
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i 19 9809300274 980925 PDR ADOCK 05200003 A PDR Mgure 13 Large-Scale PCS Instrumentation Elevations nw19:5w.wpt st450595 1.g - N Ncwsasts. f b
. - - - - - - . - . - . . - . - . -. - _ . . .- - - . . - - ~ ~ . - . - -
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Westinghouse Enefgy Systems e= 355 '
Electric Cofporation Pin 10urgt Pennsyhama 1$230 0355 DCP/NRCl420 NSD-NRC 98 5761 .I Docket No.: 52-003 August 19,1998 Document Control Desk Uc S. Nuclev Regulatory Commission Washington, DC 20555 ATTENTION: T. R. QUAY l
SUBJECT:
RESPONSE TO NRC LETTERS CONCERNING REQUESTS FOR WITHHOLDING INFORMATION
Reference:
- 1. Letter, Jackson to Liparuto, " Request for withholding information from public !
disclosure for Westinghouse AP600 design letter of May 15,1995," dated !
January 22,1996.
- 2. Letter, Jackson to McIntyre, " Request for withholding information from pubisc :
disclosure for Westinghouse AP600 design letter of October 28,1996," dated
, Februa y 19, 1997.
- 3. Letter, McIntyrc. to Quay, " Nonproprietary versions of material provided by Westinghouse letter NSD-NRC 96-486,4, dated May 16,1997.
, " Request for withholding information from l- public disclosure for Westinghouse..AP600 design letters," dated July 14,1998.
- 5. Lener, McIntyre to Quay, " Response to NRC letter of August 23,1995,
( ' Request for withholding information in the design certification application for i
I the AP600,'" DCP/NRCl400, dated Jaly 22,1998.
Dear Mr. Quay:
Reference I sets forth the NRC assessment of the Westinghouse claim for treatment of proprietary information submitted by Westinghouse in a letter dated May 15,1995, which letter provided
- Westinghouse report PCS T2R 050, "Large Scale Test Data Evaluation, May 1995." The NRC
- assessment was that with the exception of Figure 13, "Large scale PCS instrumentation Elevations" located on page 18, the material identified as~ proprietary would be withheld. De staff claimed that
- ' the identified figure was available to the public through other Westinghouse reports. In a telephone call with Ms. Jackson on January 29,1996, Westinghouse agreed that the identified figure was not 0- proprietary. Ms. Jackson indicated that the identified figure would be placed in the Public Document ._
Room. His letter provides written confirmation that the identified figure is not considered proprietary by Westinghouse. ,
f 1 .
ns- x
. .s l
l ** C00*30ed 10101 **
( -
l 1
DCP/NRC1420 NSD-NRC 98-5761 l August 19,1998 Reference 2 sets forth the NRC assessment of the Westinghouse claim for treatment o l
informat::e *. ibmitted by Westinghouse in a letter dated October 28,1996, which letter pr formal documentation of informal correspondence sent to the NRC by Westinghouse September 23,1996 through October 24,1996. ne NRC assessment was that the nonprl ,
l Sersion of the document was not acceptable. A revised nonproprietary version of the attachment l Reference 2 was provided in Reference 3. This revised ncnproprietary version of the documen included summaries of the proprietary material in those few instances where it had been remo Reference 4 sets forth the NRC assessment of the Westinghouse claim for treatment of p information submitted by Westinghouse in a letter dated October 16,1996, which letter provided fission product transport calculations and fission product source rates for the AP600. The NRC assessment was no inforTnation was identified as being proprietary and that no nonproprietary version of the document was provided. He information provided in the Westinghouse letter of Octobe 1996, was similar to that provided in the AP600 probabilistic risk assessment on June 26,1992. The proprietary information in that report, and subsequent u Reseguasp44phemisedeiadorestkWntasd16'ftsin , ates3 wggesscqinjcr d'eflranspdsSiculM$ergc,e 5. fan 8Ts's1&~
produx seurth WMiMft**AP600 h MtcWijkF6"ofisid6ted proprietary and the Octow 16/1996, letter *
- can be placed in the public document room, ,
1 L //PS Brian A. McIntyre, Manager i
Advanced Plant Safety and Licensing jml cc: J. W. Roe - NRC/NRR/DRPM J. M. Sebrosky - NRC/NRR/DRPM W. C. Huffman NRC/NRR/DRPM H. A. Sepp Westinghouse 1
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