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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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n PROCURENENT ENGINEERING ASSESSMENT PLAN OUTLINE I. BACKGROUND / INTRODUCTION II. TASK ACTION PLAN
- 1. PURPOSE
- 2. PROJECT SCOPE
- 3. EVALUATION TECHNIQUES
- 4. PROJECT ORGANIZATION 1
III. SCHEDULE IV. RESOURCES V. ATTACHMENT
- 1.
SUMMARY
OF DISTRICT COMMITMENTS 8G0216025G 880203 PDR ADOCK 05000312 R PDR_
Rev. 2, 1/27/88
Revision History PROCUREMENT ENGINEERING ASSESSMENT PLAN ,
REVISION DATE DESCRIPTION OF CHANGES Original 1/21/88 (Version informally discussed with the NRC.)
Rev. I 1/21/88 Minor editorial changes (spelling / sentence structure / references). Added page numbers.
II.2.2 D Updated to show current practices.
II.2.2 F Revised surveillance performance ,
from "each action" to "specified actions".
Figure 2-2 Revised to reflect actual sample plan.
Rev. 2 1/27/88 Revised I to add "Background" section.
Revised II.2.2 D to reflect actual conditions and revised commitment on future actions.
Minor editorial changes II.2.2 F.
Revised Functional Organizational Chart to ,
reflect current personnel and projects.
III.2.5 indicated that only specified actions would be subject of surveillances.
Deleted Attachment 1 (3 pages) since it was out-dated. The attachment was a copy of material previously furnished to the NRC during the January 1988 inspection.
Clarified "Summary of District's Commitments" to incorporate subsequent discussions and evaluations.
Rev. 2, 1/27/88 i
j PROCURDfBNT ENGINEERING ASSESSNENT PLAN I
1
- 1. BACKGROUND In its continuing effort to review & upgrade Rancho Seco programs and Practices, the District formed a Material Control Assessment Team composed of representatives form Materials Management, Maintenance, Nuclear Engineering, Nuclear Licensing..and Quality Assurance. One of the principal areas that this team has been focusing on is the past practice of procuring items on a "Like-for-Like" basis. The following background discussion on Commercial Dedication characterizes the overall concern and introduces the actions currently in process.
Based on a number of programs and activities completed in 1987, Rancho Seco management has adequate confidence that items procured from unapproved suppliers which are installed in Class-1 systems will perform satisfactorily in service. In addition, based on the changes made in materials management and procurement practices along with concomitant revision to engineering proce-dures, Rancho Seco management is confident that controls relative to commercial grade item procurement, storage, and dedication meet the requirements of 10CFR21 and 10CFR50, Appendix B.
Many items procured as commercial grade which were installed in Class-1 systems were also entered into warehouse stock. A program of re-verification of warehouse items in this category, underway and scheduled for completion by 9/30/88, is verifying that these items will meet the current Rancho Seco controls applied to commercial grade items. Any items found unacceptable by this program will cause an investigation to determine if a similar part is installed in the plant. Before items will be issued from the warehouse for use in Class-1 systems, they will have completed the re-verification process, and will have been dedicated for the intended application.
Although management has the adequate confidence required by 10CFR50, Appendix B that structures, systems and components will perform satisfactorily in service, additional confidence is desired since it is acknowledged that commercial grade dedication
- practices in the past were not as strong as current practices.
Although numerous independent reviews and tests have evaluated structures, systems or components, these reviews did not focus specifically on commercial grade item dedication (CGID).
Audits by the NRC. INPO, utility groups, and Rancho Seco QA on controls previously in place, while demonstrating overall adequacy, may also lack specific focus on verification of the dedication of commercial grade items installed in Class-1 systems.
Rev. 2, 1/27/R8 1
However the primary reason why additional confidence is desired stems for the commitment of Rancho Seco and the SMUD to restart and operate the plant in a manner which goes beyond meeting the minimum requirements. It is the commitment to excellence which is the most compelling reason for initiating this Rancho Seco Action Plan for Commercial Grade Items Installed in Class-1 Systems.
An example of that commitment to excellence is the direction of the CEO to implement this Plan.
I.1 PLAN INTRODUCTION During the period of January 4-14, 1988, the NRC conducted an inspection of Procurement and Materials Control Practices at Rancho Seco. This inspection concentrated on past as well as current practices. During internal evaluations made in preparation for the NRC inspection, SMUD identified certain weaknesses in past Material Control practices. In response, a draft assessment plan was developed and presented to the NRC at the inspection entrance meeting on January 4, 1988. The assessment plan was reviewed by the NRC Inspections Team and compared to their findings.
This Procurement Engineering Assessment Plan expands on the assessment plan discussed previously, taking into consideration j the comments and findings of the NRC Inspection Team. The actions deset ibed herein provide a comprehensive plan to address concerns and observations expressed during the inspection. The i primary objectives of this action plan are:
l l o Provide a high degree of confidence that the as-installed configuration of Rancho Seco is consistent with safety
- operability goals for restart; I
l o Address concerns identified by the NRC Procurement and j
Materials Control Inspection.
! This action plan addresses both specific and generic actions, on
- both a restart and long-range action basis. The primary restart concerns relate to four key issues:
o Commercial Grade Item Dedication (CGID),
o Seismic qualification (SEQ) of relays in the Reactor Protection System and Safety Features Actuation System (SFAS),
o Piece-parts environmental qualification (EQ),
o Enhancement of existing procedures / processes.
Each of these issues is addressed, along with necessary support tasks, in Section II. The schedule and resource requirements for project completion are addressed in Sections III and IV respectively.
Rev. 2, 1/27/88 2
i h
II. TASK ACTION PLAN r 11.1 PURPOSE I
Define the assessment program initiated by SMUD to evaluate current and past Material Control practice at Rancho Seco. This task Action Plan was modified following the NRC Procurement Inspection performed during the period of January 4-14, 1988.
This assessment will focus on the purchase of Commercial Grade Items used in safety-related applications. The evaluation results must provide Management with confidence that installed equipment will provide for safe operation or additional actions will be initiated.
II.2 PROJECT SCOPE Il.2.1 INITIAL PROGRAM Prior to the NRC Inspection, SMUD prepared a "Rancho Seco Assessment of Commercial Grade Items Installed in Class I Systems." This approach was initially based on:
A) The results of technical programs completed as described in the Engineering report "Engineering Evaluation of the Suitability of Installed Equipment."
Other programs related to Procurement and Material Control were included in a SMUD report "Assessment of Materials Management Practices at Rancho Seco" (previously provided to the NRC). A comprehensive Stock Material Reverification effort is underway and is targeted for completion by September 30, 1988.
B) An evaluation to consider the adequacy of installed Commercial Grade Items. The evaluation included two phases:
o A review of plant problem reports to determine if Commercial Grade Item failures caused or contributed to past operational problems and, o A review of Class I Serialized Work Requests involving the installation of Commercial Grade Items in Class I systems. A Commercial Grade Item Dedication Evaluation was to be accomplished on a sampling basis using today's methodology.
Rev. 2, 1/27/88 3
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