|
|---|
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
[Table view] |
Text
P '
4
-s n ot r ,
a +
& f, PROCEDURE QUALITY NUMBER:
ASSURANCE j 19 Rev' 1 r $' SMUD , ,
SACRAMENTO MUNIC PAL uTIUTY OtSTRICT ' EFFECTIVE DATE: August 10, 1984 RANCHO SECo NuCL!AR GENERAT!NG STATION ! l
.l l APPROVED: , l ,
j QUALITY ASSURANCE PROGRAM ! CUR MCED: Ibt. /
m m .. u m m .. u s l
SYSTEM AUDITING L Q) y,,,,,,, y,,,, l l 'j' .l
{ PURPOSE: This procedure establishes and defthes the program for auditing theoperation, maintenance,repairandmodificationoftheRancho; Seco Nuclear Generating Station No. 1, l
?
GENERAL REQUIREMENTS: '
j
- 1. The Management Safety Review Committee establishes a schedule!
for auditing of the operating, maintenance, repair and modi !
fication of the generating plant. i
- 2. The Manager of Quality Assurance assigns the personnel to audit those activities necessary to provide confidence that the plant is operated and maintained in a satisfactory man- ,
ner. The audit personnel shall be trained and qualified in !
accordance with Section 2.2.2 of Quality Control Instruction (QCI) No. 2. ,
i(s'-
'! 3. Audits shall be performed on elements of the nuclear opera-tions by Quality Assqrance in conformance to 10CFR50, Appen-dix B; ANSI N18.7-1972, Administrative Controls for Nuclear Power Plants; and ANSI N45.2.12, Requirements for Auditing l of Quality Assurance Programs for Nuclear Power Plants. l
- 4. Audits shall be conducted in accordance with the detailed instructions and schedules provided by Quality Control In- i struction No. 2. .
i 5. Each audit report shall' include the standard audit cover
! sheet (Figure 19-1) which shall include all applicable infor; mation.
l l l 6. Published audit findings shall be, as a minimum, distributed I
! to the Executive Director, Nuclear; Managers of Quality Assur-l j ance, Nuclear Operations, Nuclear Engineering; MSRC members;;
. and the Quality Assurance Documentation Control Center (QA-DCC).
i 7 Audits defining Technical Specifications violations shall b e ',
j sent to PRC' members by filing an 00R.
- 8. All organizations shall provide. prompt corrective action to '
rectify quality assurance inadequacies. QCI No. 2 shall N !
, 1g-1
, 1:a .
e QUALITY ASSURANCE PROCEDURE NO. 19 specify those methods that will help to ensure that cor-rective actions are handled promptly.
- 9. Followup audits shall be performed to determine the ade-quacy and effectiveness of the corrective actions ,taken.
- 10. The MSRC shall direct an independent audit of the Imple-mentation of the Quality Assurance Audit Program at least once per year.
- 11. Auditors will review all QA surveillance reports applicable j to the functional area being audited. Pertinent surveil-lances will be included as part of the auoit report.
QUALITY ASSURANCE AUDIT PROGRAM The MSRC Quality Assurance Audit Program shall consist of the following four audit groups:
- 1. Regular Quality Assurance Audits - All audits specifically identified on the. MSRC Quality Assurance Audit Program Schedule found in Attachment No. 1 of QCI NO. 2, other than I. the Operational QA Program (MSRC Item # 5) and the Vendor
~ (A-- Audit Program (MSRC #44) audits.
- 2. Operational Quality Assurance Audits - Audits of confor-mance of facility operation to all provisions contained within the Technical Specifications and applicable license conditions at'least once per year.
- 3. Vendor Audits - Audits directed by the Manager of Quality Assurance to verify the qualifications of vendors to pro-vide goods and/or services for Rancho Seco Nuclear Genera-ting Station Unit No. 1.
4 Special Audits - Audits specifically directed by the MSRC, Executive Director, Nuclear or the Manager of Quality Assurance which are separate from the audit groups listed above.
(
19-2 L-.
, t a a
RANCHO SECO AUDIT REPORT Activity Checklist No.
Auditor (s) Audit Date Distr. Cate Signature (s) Response Oue Organizations Aucited:
Individuals Contacted:
i.
Audit Description and Comments:
Summary:
lk O
Corrective Action Requested:
Corrective Action Cometeted:
Manager, Quality Assurance Date ec: J.J. MattimoeiR.J. Rodriguez;0.G. RaaschiR. Cclombo/L.R. KeilmaneR.P. Cubre'!J.V. McColligan/
R.A. Dieterichil.G. Schwieger'J.S. SullivansG.A. Cow arc!J. Field /N. BrocksR. Lawrenceio. Comstock/
R. Miller /S. CrunkiS. Recexer swo.e. o s.
l Figure 19-1 m___ .