Letter Sequence Other |
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MONTHYEARML20133M5531985-10-18018 October 1985 Proposed Tech Specs,Changing Offsite & Onsite Organization Charts Project stage: Other ML20133M5451985-10-18018 October 1985 Application for Amend to License DPR-54,consisting of Proposed Amend 138,changing Offsite & Onsite Organization Charts.Fee Paid Project stage: Request ML20205E9921986-08-12012 August 1986 Proposed Tech Specs,Changing Corporate Organizations That Provide Support to Nuclear Safety & Revising Shift Crew Personnel Complement for Compliance w/10CFR50.54(m)(2)(i) Project stage: Other ML20205E9791986-08-12012 August 1986 Application for Rev 1 to Proposed Amend 138 to License DPR-54,changing Corporate Organizations That Provide Support to Nuclear Safety & Revising Complement of Shift Crew Personnel for Compliance w/10CFR50.54(m)(2)(i) Project stage: Request ML20211E9231986-10-17017 October 1986 Forwards Updated Interim Organizational Charts for Nuclear Restart Implementation & Nuclear Plant Dept & Tabular Listing of Interim Corporate & Onsite Positions as Compared to Tech Spec Figures 6.2-1 & 6.2-2 Project stage: Other ML20211B2701987-02-11011 February 1987 Forwards Target Nuclear Organization for Restart (Transition Plan) for Review.Plan Provided to Facilitate Transition from Interim (Prestart) to Ultimate Nuclear Organization. Organizational Chart,Resumes & Position Descriptions Encl Project stage: Other ML20195G4201987-09-16016 September 1987 Rev 2 to Proposed Amend 138,revising Tech Specs to Reflect Addl Organizational Changes Due to Need for Addl Mgt Staffing for Present Outage & from Expansion of long-term Mgt Function Project stage: Other ML20234D6591987-09-16016 September 1987 Proposed Tech Specs,Reflecting Addl Organizational Changes Due to Need for Addl Mgt Staffing for Present Outage & from Expansion of long-term Mgt Function Project stage: Other ML20236K3921987-11-0202 November 1987 Proposed Tech Spec Table 6.2-1, Shift Crew Personnel & License Requirements & Pages 6-7 & 6-8,adding non-licensed Personnel,Statement Re Limiting Representation to Minority of Quorom & Lers,Respectively Project stage: Other ML20236K3761987-11-0202 November 1987 Application for Amend to License DPR-54,consisting of Proposed Amend 138,Rev 2,Suppl 1,adding non-licensed Personnel to Tech Spec Table 6.2-1,limited Representation to Tech Spec 6.5.2.5 & LERs to Tech Spec 6.5.2.6 Project stage: Request ML20236V7961987-11-25025 November 1987 Proposed Tech Spec Figures 6.2-1 & 6.2-2,reflecting Util Corporate Support of Nuclear Safety & Nuclear Organization Chart,Respectively Project stage: Other ML20236V5821987-11-25025 November 1987 Application for Amend to License DPR-54,consisting of Suppl 2 to Rev 2 to Proposed Amend 138,changing Tech Spec Figures 6.2-1 & 6.2-2 to Assign Nuclear Security Manager & Staff Directly to Nuclear Power Production Project stage: Request ML20149E5971988-01-0606 January 1988 Proposed Tech Spec 3.6,consolidating Applicability Requirement for Containment Integrity in Applicability Statement Project stage: Other ML20149E5881988-01-0606 January 1988 Supplemental Application for Amend to License DPR-54, Consolidating Applicability Requirement for Containment Integrity in Tech Spec 3.6 Applicability Statement Project stage: Supplement ML20196B8071988-02-0101 February 1988 Proposed Tech Spec Figure 6.2-2, Nuclear Organization Chart Project stage: Other ML20196B7981988-02-0101 February 1988 Application for Proposed Amend 138 to License DPR-54.Amend Revises Nuclear Organization Chart,Figure 6.2-2 as Listed Project stage: Request 1987-11-25
[Table View] |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20059C1861993-12-22022 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 ML20246F1241989-07-0505 July 1989 Proposed Tech Specs,Deleting App B in Entirety ML20245H5781989-06-22022 June 1989 Proposed Tech Specs for Amend 109 to License DPR-54 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 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 ML20155B4591988-09-30030 September 1988 Proposed Tech Spec Sections 1,3,4,5 & 6,reflecting Numerous Editorial Corrections & Administrative Changes 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 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 ML20207C0831988-07-27027 July 1988 Revised Proposed Tech Specs,Consisting of Rev 1 to Proposed Amend 102,deleting App B 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 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 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 ML20148J3531988-01-13013 January 1988 Proposed Tech Specs,Consisting of Proposed Amend 165,adding Ventilation Radiation Monitor to Interim Onsite Storage Bldg.Related Info Encl ML20149E5971988-01-0606 January 1988 Proposed Tech Spec 3.6,consolidating Applicability Requirement for Containment Integrity in Applicability Statement ML20149E1591987-12-23023 December 1987 Proposed Tech Specs Incorporating Accident Monitoring Instrumentation Recently Installed or Upgraded ML20149E8591987-12-22022 December 1987 Proposed Tech Specs,Establishing New Set Lower Limits of Detection for Prebatch Release & Composite post-release Analyses ML20237D1171987-12-15015 December 1987 Proposed Tech Spec Section 3.5.5, Accident Monitoring Instrumentation & Table 3.5.5-1, Accident Monitoring Instrumentation Operability Requirements, Changing Page Ref & Wording,Respectively ML20236W8671987-12-0303 December 1987 Proposed Tech Spec,Combining Tech Specs 3.3.1.E & 3.3.1.F for Nuclear Svc Cooling & Raw Water ML20236V7961987-11-25025 November 1987 Proposed Tech Spec Figures 6.2-1 & 6.2-2,reflecting Util Corporate Support of Nuclear Safety & Nuclear Organization Chart,Respectively ML20236U3361987-11-25025 November 1987 Proposed Tech Specs Page 1-2b,adding Words to Effect That 3.25 Factor Applicable to Three Consecutive Time Intervals Will Be Reset to Begin After Next Surveillance ML20236U0821987-11-25025 November 1987 Proposed Tech Specs,Consisting of Suppl 1 to Rev 0 to Proposed Amend 164 ML20236S0881987-11-17017 November 1987 Proposed Tech Specs,Consisting of Suppl 2 to Rev 2 to Proposed Amend 147,concerning Diesel Generators ML20236P3511987-11-0606 November 1987 Proposed Tech Specs Re Limiting Condition for Operation of Instrumentation Sys ML20236K3921987-11-0202 November 1987 Proposed Tech Spec Table 6.2-1, Shift Crew Personnel & License Requirements & Pages 6-7 & 6-8,adding non-licensed Personnel,Statement Re Limiting Representation to Minority of Quorom & Lers,Respectively ML20236D6601987-10-23023 October 1987 Proposed Tech Specs,Providing Exception to Requirement That key-operated Shutdown Bypass Switch Not Be Used During Reactor Power Operation ML20235R4261987-10-0303 October 1987 Proposed Radiological Effluent Tech Specs,Incorporating Clarifications & Correcting Editorial Errors ML20235Q5111987-10-0101 October 1987 Proposed Tech Specs Re Comparison of Plant Tech Specs to STS ML20235F5301987-09-22022 September 1987 Proposed Tech Specs Consisting of Supplemental Info to Proposed Amend 147,Rev 2 Re Diesel Generator Outages ML20235F4641987-09-21021 September 1987 Proposed Tech Specs Changing Requirements Re Concentration of Oxygen in Waste Gas Holdup Sys to Provide for When Sys Free of Potentially Explosive Gases,For Example,During Maint ML20234D6591987-09-16016 September 1987 Proposed Tech Specs,Reflecting Addl Organizational Changes Due to Need for Addl Mgt Staffing for Present Outage & from Expansion of long-term Mgt Function ML20238E8351987-09-0808 September 1987 Corrected Tech Spec Page 4-47c to Proposed Amend 151 to License DPR-54,adding ...Will Be Exceeded Prior to Next Scheduled Snubber Svc Life... to Last Paragraph of Tech Spec 4.14f ML20236M3531987-07-31031 July 1987 Proposed Tech Specs,Clarifying Proposed Limiting Conditions of Operation & Addl Surveillance Requirements for Emergency Feedwater Initiation & Control Sys 1993-12-09
[Table view] 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] |
Text
.--. .__ _ . . . . _ . __ __ _ _ . _ .. _ . . __ _ _ _ . _ _ _ _ ,
d RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS
, LIST OF FIGURES (Continued) l Figure 3.5.2-7 Core Imbalance vs. Power Level, O to 40 EFPD
! 3.5.2-8 Core Imbalance vs. Power Level, af ter 30 EFPD 1
3.5.2-9 Core Imbalance vs. Power Level, after 300 EFPD with APSRs i Withdrawn j 3.5.2-10 Deleted
, 3.5.2-11 Deleted i 3.5.2-12 Deleted i
3.5.4-1 Incore Instrumentation Specification Axial Imbalance Indication ,
3.5.4-2 Incore Instrumentation Specification Radial Flux Tilt Indication l 3.5.4-3 Incore Instrumentation Specification 3.18-1 Ger.eral Layout of Site
- 4.13-1 Main Steam Inservice Inspection
- 4.13-2 Main Feedwater Inservice Inspection I 4.13-3 Main Steam Dump Inservice Inspection L
! 138>< 6.2-1 SMUD Nuclear Safety Organization Chart
- 6.2-2 Plant Organization Chart l
l 1
I l
l i
l rao2 an $dh" P
e i
! Proposed Amendment No. 138 xit
' _ _ _ _ _ _ _ _ . _ _ _ . . , . _ _ _ _ . _ , . _ . ~ . . . ... _ . _ . _ .__.__ _ . _ _ . _ __.
RANCllO SECO UNIT I
TECIINICAL SPECIFICATIONS Administrative Controls FIGURE 6.2-1 I
BOARD SMUD NUCLEAR SAFETY ORGANIZATION CllART OF DIRECTORS e
GENERAL MANAGER INDEPENHir 03DA,-
MANAGEMENT TNTIS PFR10DIC SAFEIY SAFETY REVIEW AUDIT OF RN U D SEW ;
COMMITTEE Ol'ERATIGIS I
i
- ACM NUCLEAR *ACM OPERATIONS *ACM ENGINEERING *ACM SERVICES i
i NUCLEAR DISTRIntITION ENGINEERING PUltCilASES i ENGINEERING CONSTRUCTION & STORES i
I QUALITY DISTRIBUTION SECURITY OPERATIONS ,_
1 l
- ACM -- Assistant Ceneral Manager
- NUCLEAR ** Responsible for Fire Protection
.ICENSING OPERATIONS Program Proposed Amendment No. 138
Figure 6.2-2 RANCil0 SECO UNIT 1 Administrative Controls TECilNICAL SPECIFICATIONS l
! PLANT ORGANIZATION CHART
!i MANAGER * -
! NUCLEAR l OPERATIONS i
I ASST MANAGER REGULATORY
- SCllEDULING ADMINISTRATION NUCLEAR COMPLIANCE l
OPERATIONS SUPERVISOR
! I I INCIDENT REGULATORY
! ANALYSIS COMPLIANCE STAFF TECilNICAL *
SR POWER PLANT
- SilIFT TECilNICAL ASSISTANT TO
- ENGINEER ADVISORS PLANT j NUCLEAR / MECH /ELEC SUPERVISOR SUPERINTENDENT l
f !
l NUCLEAR NUCLEAR
- NUCIEAR NUCLEAR CitEM-RAD
- MECilANICAL OPERATIONS ELECTRICAL I&C SUPERINTENDENT SUPERINTENDENT SUPERINTENDENT
- l SUPERINTENDENT SUPERINTENDENT i
. ASSISTANT CONTROL ROOM OPERATIONS OPERATIONS SUPERINTENDENT STAFF
. ._ - _ . _ _ - .- - =_. . - _ _ . _ - - - - - . .- -
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum ,
qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the (Chemical-Radiation Superintendent) who shall meet or exceed the qualifications of Regulatory Guide 1.8 September 1975, and (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline. The STA shall receive specific training in plant design, and response and analysis of the plant for transients and accidents.
l 6.4 TRAINING l 6.4.1 A retraining and replacement training program for the operating staff shall be maintained under the direction of the Training Superintendent and shall meet or exceed the requirements and
! recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR, Part 55.
l 6.4.2 A training program for the Fire Brigade shall be maintained under the
- direction of the Safety Technician and shall meet or exceed the requirements of Section 27 of the NFPA Code - 1975, except refresher i classroom training shall be on a quarterly schedule.
6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC)
FUNCTION 1
6.5.1.1 The Plant Review Committee shall function to advise the Manager of '
Nuclear Operations on all matters related to nuclear safety.
COMPOSITION i
6.5.1.2 The Plant Review Committee shall be composed of the:
Chairman: Regulatory Compliance Supervisor Member: Superintendent Nuclear Operations 138>< Member: Technical Support Superintendent Member: Nuclear Mechanical Maintenance Superintendent 138>< Member: Nuclear I and C Superintendent Member: Chemical and Radiation Superintendent Member: Shif t Technical Advisor Supervisor i
- Proposed Amendment No. 138
- 6-3 3
I
_ . _ - - - , __ ~ . . _ _ _ _ _
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls N
COMPOSITION i
6.5.2.2 The MSRC shall be composed of the:
138>< Assistant General Manager, Nuclear Chairman
- Assistant General Manager, Engineering Alternate Chairman Regulatory Compliance Supervisor Manager, Nuclear Engineering Department Manager, Nuclear Operations Department Principal Project Engineer Supervising Licensing Engineer 138>< Manager, Quality Department Quality Assurance Engineer Plant Superintendent Quality Assurance Engineer Secretary (non-voting member) 138> From time to time the General Manager may add additional members when it appears the additional members will strengthen the safety perspectives of the MSRC. The provisions of Section 6.5.2.6 will
< apply.
ALTERNATES 6.5.2.3 A current list of alternates approved by the General Manager shall be maintained by MSRC Secretary. In case of the absence of both the Chairman and the Alternate Chairman as provided in 6.5.2.2, a Temporary Alternate Chairman may be designated in writing by the '
General Manager. No more than two alternates shall participate in MSRC activities at any one time.
d CONSULTANTS I 6.5.2.4 Consultants shall be utilized as determined by the MSRC Chairman to provide expert advice to the MSRC.
MEETING FREQUENCY 6.5.2.5 The MSRC shall meet at least once per calendar quarter during the
, initial year of facility operation following fuel loading and at least once per six months thereaf ter.
QUORUM 6.5.2.6 A quorum of MSRC shall consist of the Chairman or his designated alternate and a majority of the MSRC members including alternates.
No more than a minority of the quorum shall have line responsibility for operation of the facility.
i l
I
! Proposed Amendment No.138 6-7
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.. - .. _ =. - ._ - _.
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls AUTHORITY 6.5.2.9 The MSRC shall report to and advise the General Manager on those areas of responsibilty specified in Section 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records of MSRC activities shall be prepared, approved, and
. distributed as indicated below:
I
- a. Minutes of each MSRC meeting shall be prepared, approved and forwarded to the General Manager within 14 days following each meeting.
- b. Reports of reviews encompassed by Section 6.5.2.7 e, f, g, and h above, shall be prepared, approved, and forwarded to the General Manager within 14 days following completion of the review,
- c. Audit reports encompassed by Section 6.5.2.8 above, shall be
- forwarded to the General Manager and to the management positions ;
responsible for the areas audited within 30 days after '
completion of the audit. !
- 1 6.6 LICENSEE EVENT REPORT ACTION l 1 r 6.6.1 The following actions shall be taken should an Event require a l Licensee Event Report (LER)* l
- a. The Commission shall be notified pursuant to the requirements of Section 73 to 10 CFR Part 50, and i
- b. Each event requiring an LER, per Section 73 to 10 CRF Part 50, !
l shall be reviewed by the PRC and the resulting LER shall be t submitted to the Manager of Nuclear Operations or the Plant 138>< Superintendent, and the Assistant General Manager, Nuclear, or !
the General Manager prior to its submittal to the Commission.
i l
i 1
Proposed Amendment No. 138 l
l
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