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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20203H7501997-08-19019 August 1997 Rev 10 to Radiological Environ Monitoring Program Manual ML20203H7351997-02-10010 February 1997 Rev 9 to CAP-0002, Off-Site Dose Calculation Manual ML20203H7231997-01-21021 January 1997 Rev 9 to Radiological Environ Monitoring Program Manual ML20059C1861993-12-22022 December 1993 Proposed Tech Specs Amend 186,rev 1 Re Nuclear Organizational Changes ML20058L4371993-12-0909 December 1993 Proposed Tech Specs Amend 187 Including Changes Making PDTS Consistent W/New 10CFR20 Regulations ML20127N3671993-01-19019 January 1993 Proposed Tech Specs Section D6.0,administrative Controls for Proposed Amend 186 ML20059E0191990-08-0303 August 1990 Rev 0 to CAP-0002, Odcm ML20059E0141990-01-31031 January 1990 Rev 0,App a to CAP-0002, Odcm ML20059E0241989-11-22022 November 1989 Rev 3 to Environ Monitoring & Emergency Preparedness ML20246A4081989-08-16016 August 1989 Rev 5 to Inservice Testing Program Plan ML20245L7281989-07-18018 July 1989 Rev 5 to Administrative Procedure RSAP-0101, Nuclear Organization Responsibilities & Authorities ML20246F1241989-07-0505 July 1989 Proposed Tech Specs,Deleting App B in Entirety ML20246A5221989-06-30030 June 1989 Closure Plan ML20245H5781989-06-22022 June 1989 Proposed Tech Specs for Amend 109 to License DPR-54 ML20246E8551989-04-30030 April 1989 Analysis of Capsule RS1-F Smud Reactor Vessel Matl Surveillance Program ML20245L0461989-04-27027 April 1989 Proposed Tech Specs for Proposed Suppl 1 to Amend 134 Re Application for Amend to License DPR-54,clarifying Unacceptability of Analysis Allowing Imperfections Greater than 40% of Nominal Tube or Sleeve Wall Thickness ML20235Y6071989-03-0606 March 1989 Proposed Tech Spec Page 4-17,including one-time Extension for Certain Surveillances Required to Be Performed by 890329 ML20245G1941989-02-28028 February 1989 Procurement Engineering Assessment Plan Final Rept ML20245H8911989-02-28028 February 1989 Revised Proposed Tech Specs,Including Pages 3-30a,3-30b, 3-40a,3-45,3-46,4-18a & 4-75 Re Addition of Operating Requirements Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations ML20195F7701988-11-18018 November 1988 Proposed Tech Spec Section 3.4, Steam & Power Conversion Sys ML20206F2881988-11-15015 November 1988 Proposed Tech Specs 4.6.4.f (Page 4-34i) Re Surveillance of Equipment Required to Verify Vital 120 Volt Ac Bus Operability ML20205R8681988-11-0404 November 1988 Proposed Tech Specs Re Local Leakage Rate Tests & Reactor Bldg Containment Integrity ML20205M8971988-10-28028 October 1988 Proposed Tech Specs Re Nuclear Svc Battery Operability & Surveillance Requirements ML20205L2661988-10-25025 October 1988 Proposed Tech Spec Table 3.14-3, Carbon Dioxide Suppression Zones ML20155G2201988-10-0707 October 1988 Proposed Tech Specs Clarifying Operational Mode Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Sys Train ML20155B8481988-09-30030 September 1988 Proposed Tech Specs Re Reactor Protection Sys Trip Setting Limits,Rcs High Point Vents,Leakage & Leak Detection,Reactor Coolant Inventory & Auxiliary Electric Sys ML20155B4591988-09-30030 September 1988 Proposed Tech Spec Sections 1,3,4,5 & 6,reflecting Numerous Editorial Corrections & Administrative Changes ML20206A8151988-09-28028 September 1988 Rev 0 to, Effluents & Water Mgt Project Action Plan ML20154J5611988-09-19019 September 1988 Proposed Tech Specs,Changing Local Leak Rate Test Requirements for Containment Penetrations ML20154D7591988-09-0808 September 1988 Proposed Tech Specs Re Administrative Controls,Onsite & Offsite Organizations & Facility Staff ML20153E6481988-08-31031 August 1988 Proposed Tech Specs on Limiting Condition for Operation Re Containment Isolation Valves ML20151K1041988-07-28028 July 1988 Rev 0 to Special Test Procedure STP.668, EFIC High/Medium Decay Heat Test ML20207C0831988-07-27027 July 1988 Revised Proposed Tech Specs,Consisting of Rev 1 to Proposed Amend 102,deleting App B ML20151H6131988-07-15015 July 1988 Rev 0 to Matl Control Dept Action Plan for Rancho Seco Nuclear Generating Station ML20196A2281988-06-21021 June 1988 Proposed Tech Specs Providing Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation & Modifying Existing Purge Sys Operation Requirement ML20155K0971988-06-14014 June 1988 Proposed Tech Specs Making Minor Corrections to Table 3.5.5-1, Accident Monitoring Instrumentation,Items 5 & 14 & Table 4.1-1 Items 65 & 92 & Adding Second Note to Table 4.1-1,Item 80 ML20195J4921988-06-10010 June 1988 Proposed Tech Spec Pages 4-69 Through 4-85a,modifying Radiological Effluent Tech Specs to Reduce Count Time Required for prebatch-release Sample Analysis ML20151R0641988-04-15015 April 1988 Rev 0 to STP.1154, Remote Shutdown Panel Test ML20151X3211988-04-0606 April 1988 Rev 1 to Procedure Development Project Action Plan for Temporary & Interim Procedure Change Incorporation as Procedure Rev ML20151V5871988-04-0202 April 1988 Rev 1 to Sys Engineering Action Plan SYSTEM-012, CRD Breaker Action Plan ML20151X2871988-03-31031 March 1988 Rev 0 to Sys Engineering Action Plan SYSTEM-009, Letdown Cooler Thermal & Hydraulic Shock Prevention ML20150D1861988-03-17017 March 1988 Proposed Tech Specs,Correcting Typos & Making Further Editorial Changes to Proposed Amend 139,dtd 860129 ML20196G5131988-03-0101 March 1988 Proposed Tech Specs,Revising Tech Spec 4.1-1,Item 44.c & Tech Spec 4.10.1.E.2 Re Total Quantity of Gaseous Chlorine in Restricted Area ML20147F0771988-02-25025 February 1988 Revised Proposed Tech Spec Table 4.1-1 & Tech Spec 4.10.1.E.2,requiring Performance of Surveillances Only When Gaseous Chlorine Onsite ML20147B1761988-02-15015 February 1988 Rev 0 to RECM-6878, Radiological Effluent Control Manual ML20148D9931988-02-12012 February 1988 Post-Trip Transient Investigation,Assessment & Reporting ML20149K8621988-02-12012 February 1988 Proposed Tech Spec 6.5.1.6.d,identifying Items Not Requiring Plant Review Committee Review ML20196D9091988-02-11011 February 1988 Proposed Tech Specs,Adding Term Dewatering to Process Control Program ML20149G1781988-02-0808 February 1988 Proposed Page 3-19 to Tech Spec 3.3, Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Sys ML20196B8071988-02-0101 February 1988 Proposed Tech Spec Figure 6.2-2, Nuclear Organization Chart 1997-08-19
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20203H7501997-08-19019 August 1997 Rev 10 to Radiological Environ Monitoring Program Manual ML20203H7351997-02-10010 February 1997 Rev 9 to CAP-0002, Off-Site Dose Calculation Manual ML20203H7231997-01-21021 January 1997 Rev 9 to Radiological Environ Monitoring Program Manual ML20059E0191990-08-0303 August 1990 Rev 0 to CAP-0002, Odcm ML20059E0141990-01-31031 January 1990 Rev 0,App a to CAP-0002, Odcm ML20059E0241989-11-22022 November 1989 Rev 3 to Environ Monitoring & Emergency Preparedness ML20246A4081989-08-16016 August 1989 Rev 5 to Inservice Testing Program Plan ML20245L7281989-07-18018 July 1989 Rev 5 to Administrative Procedure RSAP-0101, Nuclear Organization Responsibilities & Authorities ML20246A5221989-06-30030 June 1989 Closure Plan ML20245G1941989-02-28028 February 1989 Procurement Engineering Assessment Plan Final Rept ML20206A8151988-09-28028 September 1988 Rev 0 to, Effluents & Water Mgt Project Action Plan ML20151K1041988-07-28028 July 1988 Rev 0 to Special Test Procedure STP.668, EFIC High/Medium Decay Heat Test ML20151H6131988-07-15015 July 1988 Rev 0 to Matl Control Dept Action Plan for Rancho Seco Nuclear Generating Station ML20151R0641988-04-15015 April 1988 Rev 0 to STP.1154, Remote Shutdown Panel Test ML20151X3211988-04-0606 April 1988 Rev 1 to Procedure Development Project Action Plan for Temporary & Interim Procedure Change Incorporation as Procedure Rev ML20151V5871988-04-0202 April 1988 Rev 1 to Sys Engineering Action Plan SYSTEM-012, CRD Breaker Action Plan ML20151X2871988-03-31031 March 1988 Rev 0 to Sys Engineering Action Plan SYSTEM-009, Letdown Cooler Thermal & Hydraulic Shock Prevention ML20147B1761988-02-15015 February 1988 Rev 0 to RECM-6878, Radiological Effluent Control Manual ML20148D9931988-02-12012 February 1988 Post-Trip Transient Investigation,Assessment & Reporting ML20196B6901988-01-31031 January 1988 Rev 0 to Radiological Effluents Action Plan ML20149E2771988-01-29029 January 1988 Rev 4 to Inservice Testing Program Plan for Pumps & Valves ML20196C8521988-01-27027 January 1988 Rev 2 to Procurement Engineering Assessment Plan ML20148T0071988-01-20020 January 1988 Rev 1 to STP.961, Loss of Offsite Power ML20147H9261988-01-13013 January 1988 Rev 2 to Monthly Surveillance Test of Control Room/ Technical Support Ctr Essential Ventilation Sys Loop A. W/One Oversize Drawing ML20147H8771988-01-13013 January 1988 Rev 3 to Refueling Interval,Special Frequency Control Room/ Technical Support Ctr Essential HVAC Sys Actuation by Rad Monitors & Chlorine Detectors Train a ML20234F4601987-12-21021 December 1987 Rev 5 to AP.310, Offsite Dose Calculation Manual ML20236U1391987-11-20020 November 1987 Emergency Operating Procedure Technical Basis EOP POM-248 ML20236P5221987-11-13013 November 1987 Rev 0 to Special Test Procedure STP.961, Loss of Offsite Power Test ML20236Q0601987-11-10010 November 1987 Rev 1 to Radiological Environ Monitoring Program Manual ML20236X3591987-10-31031 October 1987 Rev 3 to Wire & Cable Program Rept ML20236L1481987-10-30030 October 1987 Rev 4 to Procedure AP.310, Offsite Dose Calculation Manual ML20236P1941987-10-14014 October 1987 Rev 1 to STP.660, Integrated Control Sys Tuning at Power ML20236D3191987-10-0707 October 1987 Rev 0 to Radiological Environ Monitoring Program Manual ML20236B7491987-09-23023 September 1987 Rev 1 to D-0050, Engineering Action Plan ML20235Q7561987-09-0303 September 1987 Twelve Sys Expanded Assessment of Expanded Augmented Sys Review & Test Program Rept ML20234C2331987-09-0101 September 1987 Motor-Operated Valves Program ML20235Z5811987-08-31031 August 1987 Rev 2 to Wire & Cable Program Rept ML20235N8631987-08-26026 August 1987 Rev 0 to Surveillance Procedure SP.486, Monthly Control Room/Technical Support Ctr Ventilation Gas Monitor Test ML20238E2451987-08-24024 August 1987 Rev 1 to Maint Administrative Procedure MAP-0009, Preventive Maint Program ML20235U0581987-08-18018 August 1987 Procedure AP.2.07, Verification of Emergency Operating Procedures ML20235U0461987-08-18018 August 1987 Procedure AP.2.06, Validation of Emergency Operating Procedures ML20237L6371987-08-12012 August 1987 Sys Review & Test Program Mgt Overview Manual ML20238D5981987-08-0606 August 1987 Rev 0 to ADM-0037, Maint Administrative Procedures Manual ML20235N5461987-08-0606 August 1987 Rev 1 to Surveillance Procedure SP.485A, Refueling Interval,Special Frequency Control Room/Technical Support Ctr Essential HVAC Sys Actuation by Rad Monitors & by Chlorine Detectors Train a ML20236J7071987-07-15015 July 1987 Expanded Augmented Sys Review & Test Program (Easrtp) Evaluation Plan ML20236J6921987-07-15015 July 1987 Expanded Augmented Sys Review & Test Program Methodology Guidelines ML20216H8221987-06-25025 June 1987 Rev 3 to Inservice Testing Program Plan,Rancho Seco Nuclear Generating Station ML20238E2501987-06-23023 June 1987 Rev 3 to Inservice Testing Program Plan for Pumps & Valves ML20214K3051987-04-24024 April 1987 Nuclear Records Mgt ML20214K2981987-04-24024 April 1987 QA Records 1997-08-19
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-MECHANICAL PROJECT CLASSIFICATION OF EQUIPMENT 1.0 PURPOSE This section provides direction for' project classification of equipment..
Project classifications are a shorthand method of indicating the quality and seismic categories and the code under which design, procurement, manufacture,.
fabrication, erection and installation are to take place.
2.0 SCOE The classification system covers all equipment in the plant. From a practical standpoint .it covers any item which has a tag number.
3.0 DEFINITIONS Not Applicable- --
4.0 COVERNING CODES AND INDUSTRY STANDARDS Not Applicable
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5.0 DESIGN CRITERIA The project classifications for piping, valves .snd equipment consist of a combination of digits and letters. The first digit represents the quality class; the second digit indicates seismic class and the third' indicates the applicable code.
When a nuclear code is involved, an "N" between the second and third digits designates that the component is part of a safety system and all the requirements of the applicable nuclear code class apply. The code class in nuclese components is indicated by the third digit.
The quality classes are indicated by numbers 1 or 2 as defined in the Rancho Seco Quality Assurance Program Manual Section 3', and FSAR Appendix LB. A 3 in the quality class position indicates no quali*.y assurance is required and commercial quality control practice is adequate.
The seismic categories are indicated by numbers 1, 2, or 3 representing the three seismic categories defined in FSAR Appendix 5B.
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5.1 CODES The last digit of all equipment project classifications, regardless of whether nuclear or nonnuclear, represents the applicable code under which design, procurement, manufacture, fabrication, erection and installation are made.
The following is, the definition of these numbers:
Equipment Design Classification Last Digit Applicable Code L,. 2, o r 3 See Design criteria 5108.2 for definitions 4 ASME B&PV Code,Section I 5 TEMA, Heat Excha'nge Institute Standards 6 American Petroleum Institute-7 Hydraulic Institute Standards 8 ASME B&PV Code,Section VIII 9 Other 9A ASHRAE, AMCA X Manufacturer's Standard (No applicable code) 5.1 EXAMPLES The following are examples of project classification use:
(1) Nuclear Equipment Classification The following example would be interpreted as follows: ,
Seismic Category I- Nuclear equipment (ASME III, B3* .7, or ASME Pump and Valve ,
Code, whichever is applicable)
Quality Class 1 1 L N 2 .
I Nuclear Class B or 2 (whichever is applicable) 2 1754V Initial Issue SMuo 84S7e asas
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5101.1
]e i,SMUD eama"MO GAUaSOPAL UTEJTY DESTWICT DESIGN CRITERIA _.1 wo-MECHANICAL (1) Nonnuclear Equipment Classification 1' The- following example would be interpreted as. follows:
Seismic Category I ASME B&PV Code.Section VIII Quality Class I
L L 8-8 A
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