Errata to SRP for Review of SAR for Nuclear Power Plants. LWR Edition.Proposed Rev 0 to New SRP Section 6.5.5, `Pressure Suppression Pools as Fission Product Cleanup Sys,' Correcting Pages as Listed in EnclML20214B049 |
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Issue date: |
05/08/1987 |
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Office of Nuclear Reactor Regulation |
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References |
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NUREG-0800, NUREG-0800-06.5.5-ER, NUREG-800, NUREG-800-6.5.5-ER, SRP-06.05.05, SRP-6.05.05, NUDOCS 8705200087 |
Download: ML20214B049 (3) |
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Category:NUREG REPORTS
MONTHYEARML20216G0111999-09-30030 September 1999 Year 2000 Readiness in U.S. Nuclear Power Plants ML20211J9931999-08-31031 August 1999 Generic Environmental Impact Statement for License Renewal of Nuclear Plants.Main Report.Section 6.3 - Transportation, Table 9.1 Summary of Findings on NEPA Issues for License Renewal of Nuclear Power Plants.Final Report ML20206N2191999-04-30030 April 1999 Operator Licensing Examination Standards for Power Reactors ML20205A5291999-03-31031 March 1999 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,October-December 1998.(White Book) ML20211K2851999-03-31031 March 1999 Standard Review Plan on Power Reactor Licensee Financial Qualifications and Decommissioning Funding Assurance ML20205A5991999-03-31031 March 1999 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,July-September 1998.(White Book) ML20203D0541999-01-31031 January 1999 Fire Barrier Penetration Seals in Nuclear Power Plants ML20155A9281998-10-31031 October 1998 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,April-June 1998.(White Book) ML20154C2081998-09-30030 September 1998 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,January-March 1998.(White Book) ML20203A1521998-07-31031 July 1998 Assessment of the Use of Potassium Iodide (Ki) as a Public Protective Action During Severe Reactor Accidents.Draft Report for Comment ML20153D3371998-07-31031 July 1998 Assessment of the Use of Potassium Iodide (Ki) as a Public Protective Action During Severe Reactor Accidents.Draft Report for Comment ML20236S9771998-06-30030 June 1998 Knowledge and Abilities Catalog for Nuclear Power Plant Operators.Pressurized Water Reactors ML20236S9591998-06-30030 June 1998 Knowledge and Abilities Catalog for Nuclear Power Plant Operators.Boiling Water Reactors ML20236S9681998-06-30030 June 1998 Evaluation of AP600 Containment THERMAL-HYDRAULIC Performance ML20247E3951998-04-30030 April 1998 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,October-December 1997.(White Book) ML20217F3801998-03-31031 March 1998 Risk Assessment of Severe ACCIDENT-INDUCED Steam Generator Tube Rupture ML20197B2091997-12-31031 December 1997 Standard Review Plan on Antitrust Reviews.Final Report ML20202J3051997-11-30030 November 1997 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,July-September 1997.(White Book) ML20197B0431997-11-30030 November 1997 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,April-June 1997.(White Book) ML20211L2931997-09-30030 September 1997 Aging Management of Nuclear Power Plant Containments for License Renewal ML20210K7801997-08-31031 August 1997 Topical Report Review Status ML20198G2881997-08-31031 August 1997 Environmental Standard Review Plan.Standard Review Plans for Environmental Reviews for Nuclear Power Plants ML20149G9431997-07-31031 July 1997 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,January-March 1997.(White Book) ML20140F0801997-05-31031 May 1997 Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design.Supplement No. 1.Docket No. 52-001.(General Electric Nuclear Energy) ML20140J4301997-05-31031 May 1997 Safety Evaluation Report Related to the Department of Energy'S Proposal for the Irradiation of Lead Test Assemblies Containing TRITIUM-PRODUCING Burnable Absorber Rods in Commercial LIGHT-WATER Reactors ML20210R2131997-05-31031 May 1997 Final Safety Evaluation Report Related to the Certification of the System 80+ Design.Docket No. 52-002.(Asea Brown Boveri-Combustion Engineering) ML20141A5791997-04-30030 April 1997 Proposed Regulatory Guidance Related to Implementation of 10 CFR 50.59 (Changes, Tests, or Experiments).Draft Report for Comment ML20141C2411997-04-30030 April 1997 Circumferential Cracking of Steam Generator Tubes ML20141J9391997-04-30030 April 1997 Safety Evaluation Report Related to the Renewal of the Operating License for the Research Reactor at North Carolina State University ML20137A2191997-03-31031 March 1997 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,October-December 1996.(White Book) ML20135E8131997-02-28028 February 1997 Evaluation Criteria for COMMUNICATIONS-RELATED Corrective Action Plans ML20135D5711997-01-31031 January 1997 Operator Licensing Examination Standards for Power Reactors ML20138J2461997-01-31031 January 1997 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,July-September 1996.(White Book) ML20134L3631997-01-31031 January 1997 Standard Review Plan on Power Reactor Licensee Financial Qualifications and Decommissioning Funding Assurance.Draft Report for Comment ML20134L3601997-01-31031 January 1997 Standard Review Plan on Antitrust.Draft Report for Comment ML20133E9161996-12-31031 December 1996 License Renewal Demonstration Program: NRC Observations and Lessons Learned ML20135A5121996-11-30030 November 1996 Standard Review Plan Maintenance Program Implementing Procedures Document ML20135A4981996-10-31031 October 1996 Historical Data Summary of the Systematic Assessment of Licensee Performance ML20149L8261996-10-31031 October 1996 Reactor Pressure Vessel Status Report ML20058N6411993-11-30030 November 1993 Guidelines for Inservice Testing at Nuclear Power Plants. Draft Report for Comment ML20058N5831993-11-30030 November 1993 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,July-September 1993.(White Book) ML20062J4761993-10-31031 October 1993 Revised Livermore Seismic Hazard Estimates for 69 Nuclear Power Plant Sites East of the Rocky Mountains.Draft Report for Comment ML20057E5921993-09-30030 September 1993 Auxiliary Feedwater System RISK-BASED Inspection Guidance for the DAVIS-BESSE Nuclear Power Plant ML20057E7001993-09-30030 September 1993 Shutdown and LOW-POWER Operation at Nuclear Power Plants in the United States.Final Report ML20149D4111993-08-31031 August 1993 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,April-June 1993.(White Book) ML20057B2491993-08-31031 August 1993 Historical Data Summary of the Systematic Assessment of Licensee Performance ML20128N7781993-01-31031 January 1993 Licensee Contractor and Vendor Inspection Status Report. Quarterly Report,October-December 1992.(White Book) ML20128N2891993-01-31031 January 1993 Operator Licensing Examiner Standards ML20127H0941992-12-31031 December 1992 Improvements to Technical Specifications Surveillance Requirements ML20126F0051992-12-31031 December 1992 Status of Safety Issues at Licensed Power Plants.Tmi Action Plan Requirements.Unresolved Safety Issues.Generic Safety Issues.Other Multiplant Action Issues 1999-09-30
[Table view]Some use of "" in your query was not closed by a matching "". Category:REGULATORY GUIDES & STD. REVIEW PLANS-TEXT
MONTHYEARML20058B9811990-10-31031 October 1990 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 2 to SRP Section 3.6.1,Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside ML20059D3261990-08-31031 August 1990 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 0 to SRP Section 17.3, Quality Assurance Program Description ML20248F3381989-08-31031 August 1989 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,Lwr Edition.Revision 3 to SRP Section 2.4.3, Probable Maximum Flood (PMF) on Streams and Rivers ML20246H1221989-08-31031 August 1989 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 3 to SRP Section 13.1.2-13.1.3, Operating Organization ML20246H0361989-08-31031 August 1989 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 3 to SRP Section 2.4.2, Floods ML20236V6661987-11-30030 November 1987 Rev 1 to Reg Guide 5.62, Reporting of Safeguards Events ML20238E4131987-08-31031 August 1987 for Comment Issue of Draft Reg Guide,Task Ee 006-5, Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants ML20214B0491987-05-0808 May 1987 Errata to SRP for Review of SAR for Nuclear Power Plants. LWR Edition.Proposed Rev 0 to New SRP Section 6.5.5, `Pressure Suppression Pools as Fission Product Cleanup Sys,' Correcting Pages as Listed in Encl ML20213A6781987-04-30030 April 1987 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Proposed Revision 0 to New SRP Section 6.5.5, Pressure Suppression Pools as Fission Product Clean-Up Systems. for Comment ML20212R2681987-04-30030 April 1987 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Proposed Revision 2 to Section 6.5.2, Containment Spray as a Fission Product Cleanup System. for Comment ML20199J1981986-06-30030 June 1986 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 3 to Section 9.2.2, Reactor Auxiliary Cooling Water Systems ML20199J1931986-04-30030 April 1986 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 4 to Section 9.2.1, Station Service Water System ML20137Y7121985-10-31031 October 1985 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 4 to Section 6.2.2, Containment Heat Removal System ML20133Q1961985-07-31031 July 1985 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 1 to Section 13.5.2, Operating and Maintenance Procedures, and Revision 0 of Appendix a to Section 13.5.2, Review.. ML20203C0631981-07-31031 July 1981 Draft Reg Guide,Task CE 301-4, Srp,Missiles Generated by Natural Phenomena ML20213D1411980-02-13013 February 1980 Draft 1 SRP Proposed Revision 2 to Section 4.2, Fuel Sys Design ML20147D2681978-11-30030 November 1978 Srp,Section 5.4.2 Re Steam Generator Matls,Revision 1 ML20150C2411978-10-31031 October 1978 Preparation of Radiological Effluent Tech Spec for Nuc Pwr Plants. Guidance Manual Describing Methods Found Acceptable to NRC Staff for Calculating Key Values ML20148D2201978-10-12012 October 1978 Proposed NRC Reg Guide 2.XXX, Emergency Planning for Research Reactors 1990-08-31
[Table view]Some use of "" in your query was not closed by a matching "". Category:STANDARD REVIEW PLANS
MONTHYEARML20058B9811990-10-31031 October 1990 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 2 to SRP Section 3.6.1,Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside ML20059D3261990-08-31031 August 1990 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 0 to SRP Section 17.3, Quality Assurance Program Description ML20248F3381989-08-31031 August 1989 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,Lwr Edition.Revision 3 to SRP Section 2.4.3, Probable Maximum Flood (PMF) on Streams and Rivers ML20246H1221989-08-31031 August 1989 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 3 to SRP Section 13.1.2-13.1.3, Operating Organization ML20246H0361989-08-31031 August 1989 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 3 to SRP Section 2.4.2, Floods ML20214B0491987-05-0808 May 1987 Errata to SRP for Review of SAR for Nuclear Power Plants. LWR Edition.Proposed Rev 0 to New SRP Section 6.5.5, `Pressure Suppression Pools as Fission Product Cleanup Sys,' Correcting Pages as Listed in Encl ML20213A6781987-04-30030 April 1987 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Proposed Revision 0 to New SRP Section 6.5.5, Pressure Suppression Pools as Fission Product Clean-Up Systems. for Comment ML20212R2681987-04-30030 April 1987 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Proposed Revision 2 to Section 6.5.2, Containment Spray as a Fission Product Cleanup System. for Comment ML20199J1981986-06-30030 June 1986 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 3 to Section 9.2.2, Reactor Auxiliary Cooling Water Systems ML20199J1931986-04-30030 April 1986 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 4 to Section 9.2.1, Station Service Water System ML20137Y7121985-10-31031 October 1985 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 4 to Section 6.2.2, Containment Heat Removal System ML20133Q1961985-07-31031 July 1985 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.Lwr Edition.Revision 1 to Section 13.5.2, Operating and Maintenance Procedures, and Revision 0 of Appendix a to Section 13.5.2, Review.. ML20213D1411980-02-13013 February 1980 Draft 1 SRP Proposed Revision 2 to Section 4.2, Fuel Sys Design ML20147D2681978-11-30030 November 1978 Srp,Section 5.4.2 Re Steam Generator Matls,Revision 1 1990-08-31
[Table view]Some use of "" in your query was not closed by a matching "". |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _
,penauq y I*+. UNITED STATES 4 o NUCLEAR REGULATORY COMMISSION I E Washington, D.C. 20555
/ May 8, 1987 ERRATA SHEET l
Report Number: NUREG-0800 i Report
Title:
Standard Review Plan for the Review of
! Safety Analysis Reports for Nuclear
! Power Plants l
Proposed New Section 6.5.5, Regulatory .
Analysis and Supporting Technical Reports '
Prepared by:
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission l Date Published: April 1987 Instructions: Due to a transmission error, four late changes to the subject Proposed SRP Section did not appear in the printed and distributed copies.
These changes and additions have been identifed on the attached sheet. Due to the necessity for a change page, the coment period has been i exterded from June 5,1987 to July 7,1987. -
i 1
t l
)
8705200087 870508 PDR NUREG 0800 R PDR Division of Publications Services f
ERRATA SHEET Page 2 HUREG-0800
SUBJECT:
ERRATA TO PROPOSED SRP SECTION 6.5.5 Due to an error in transmitting the text four late additions and changes to the subject Proposed SRP Section did not appear in the printed and distributed copies. These changes are:
Page 6.5.5-2, second paragraph under heading II, beginning "Where they can be shown ...." A sentence should be added to the end of this paragraph. This addition is "Other assumptions concerning the release of radioactivity are to be taken from Regulatory Guide 1.3, except for Position C.1.f., which this section replaces."
In specific criterion 3 of the next paragraph, the first sentence should '
read: "For plants which have already received a construction permit, the iodine retention calculated using this section must not be used to ' justify removal of the standby gas treatment or other filtered exhaust system from status as engineered safety features and any change in plant design, proposed testing, surveillance or maintenance must be supported by considerations of lowered operator dose and other projected benefits."
. Page 6.5.5-3, first paragraph under heading 1, Pool decontamination factor, ,
l should read as follows:
"The decontamination factor (DF) of the pool is defined as the ratio of the amount of a contaminant entering the pool to the amount leaving. Decontami-nation factors for each fission product form as functions of time can be calculated by the SPARC Code (Ref. 2). An applicant may use the SPARC Code or other methods to calculate the retention of fission products within the pool, provided these methods are adecuately described in the SAR to pennit review.
If the time-integrated DF values claimed by tN applicant for removal of particulates and elemental iodine are 10 or less for a Mark II or a Mark III BWR; and are 5 or less for a Mark I BWR, the applicant's values may be accepted without any need to perform calculations (Refs. 3, 4). A DF value of 1 (no retention) should be used for noble gases and, unless the applicant demonstrates otherwise, for organic iodides as well. The applicant should provide extensive justification for any DF values greater than those given above."
An additional reference should be added: "4 R. S. Denning et al, "Radionuclide Release Calculations for Selected Severe Accident Scenarios."
NUREG/CR-4624, Vol. 1."
Because of deleys prospective commenters might experience due to these changes, the coninent period will be extended to July 7,1987.
I
l UNITED STATES NUCLEAR REGULATORY COMMIS810N ,,,,, cm .
l WASHINGTON, D.C. 20666 ,oetaos e see mo OFRCIAL BUSINESS E.v o.."o c.
i PENALTY FOR PRIVATE USE, $300 1
120555078877 1 1A011X US NRC-0 ARM-ADM DIV 0F PUB SVCS POLICY & PUB MGT BR-PDR NUREG W-501 WASHINGTON DC 20555
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