Letter Sequence Other |
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Results
Other: ML20133M553, ML20149E597, ML20195G420, ML20196B807, ML20205E992, ML20211B270, ML20211E923, ML20212E535, ML20234D659, ML20236K392, ML20236U336, ML20236V796
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MONTHYEARML20133M5451985-10-18018 October 1985 Application for Amend to License DPR-54,consisting of Proposed Amend 138,changing Offsite & Onsite Organization Charts.Fee Paid Project stage: Request ML20133M5531985-10-18018 October 1985 Proposed Tech Specs,Changing Offsite & Onsite Organization Charts 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 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 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 ML20209B6361987-01-15015 January 1987 Forwards Request for Addl Info Re 860812 & 1017 Proposed Rev 1 to Amend 138 to License DPR-54 Concerning Organizational Revs & Changes to Responsibilities of Plant Review Committee.Description of NRC Concerns Re Changes Also Encl Project stage: RAI ML20212E5351987-01-29029 January 1987 Matls-Chemistry Assessment for Internal Vent Valve 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 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 Project stage: Other ML20236U3241987-11-25025 November 1987 Suppl 1 to 860922 Application for Amend to License DPR-54, Consisting of Proposed Amend 145,adding Wording to Tech Spec Page 1-2b Re Surveillance of Internal Vent Valves to Cycle 8 Refueling Outage Project stage: Request ML20237B3961987-12-0707 December 1987 Forwards Amend 92 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Redefine Refueling Interval to Make Definition Consistent W/Sts & Extends Surveillance Interval of Vent Valves to Cycle 8 Refueling Project stage: Approval 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 ML20149E5971988-01-0606 January 1988 Proposed Tech Spec 3.6,consolidating Applicability Requirement for Containment Integrity in Applicability Statement 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 ML20196B8071988-02-0101 February 1988 Proposed Tech Spec Figure 6.2-2, Nuclear Organization Chart Project stage: Other ML20246M1741989-05-0808 May 1989 Submits Addendum to Safety Evaluation Supporting Amend 92 to License DPR-54,per Util 881129 Request to Revise Safety Evaluation.Approval to Extend Refueling Interval as Applies to Reactor Vessel Vent Valve Granted Project stage: Approval 1987-11-25
[Table View] |
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,RespectivelyML20236K392 |
Person / Time |
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Site: |
Rancho Seco |
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Issue date: |
11/02/1987 |
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From: |
SACRAMENTO MUNICIPAL UTILITY DISTRICT |
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To: |
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Shared Package |
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ML20236K379 |
List: |
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References |
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TAC-60162, NUDOCS 8711090210 |
Download: ML20236K392 (3) |
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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 ML20044F1091993-05-14014 May 1993 Proposed Permanently Defueled TS Section D6.0 Re Administrative Controls ML20127N3671993-01-19019 January 1993 Proposed Tech Specs Section D6.0,administrative Controls for Proposed Amend 186 ML20042F5091990-04-30030 April 1990 Proposed Tech Specs Re long-term Defueling ML20034A2741990-04-12012 April 1990 Proposed Tech Specs Re Hpi,Chemical Addition & Low Temp Overpressure Protection Sys 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 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 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 ML20236U0821987-11-25025 November 1987 Proposed Tech Specs,Consisting of Suppl 1 to Rev 0 to Proposed Amend 164 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 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 1993-05-14
[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 ML20044F1091993-05-14014 May 1993 Proposed Permanently Defueled TS Section D6.0 Re Administrative Controls ML20127N3671993-01-19019 January 1993 Proposed Tech Specs Section D6.0,administrative Controls for Proposed Amend 186 ML20012G6061992-12-31031 December 1992 Rev 3 to Odcm ML20059E0191990-08-0303 August 1990 Rev 0 to CAP-0002, Odcm ML20043A0881990-04-30030 April 1990 Rev 1 to CAP-0002, Odcm ML20042F5091990-04-30030 April 1990 Proposed Tech Specs Re long-term Defueling ML20043B2551990-04-26026 April 1990 Rev 0 to Technical Svcs Administrative Procedure TSAP-4400, Environ Qualification Program ML20034A2741990-04-12012 April 1990 Proposed Tech Specs Re Hpi,Chemical Addition & Low Temp Overpressure Protection Sys ML20059E0141990-01-31031 January 1990 Rev 0,App a to CAP-0002, Odcm ML20011E1741990-01-29029 January 1990 Rev 1 to Technical Svcs Administrative Procedure TSAP-4124, Sys Layup Program ML20011E1731990-01-11011 January 1990 Rev 0 to Procedure NDP-039, Sys Required to Support Defueled Mode ML20005E8781989-12-31031 December 1989 Revised Rancho Seco Physical Security Plan,Training Program & Emergency Plan ML20005E3641989-12-28028 December 1989 Rev 1 to CAP-0002, Odcm ML20005E3651989-12-27027 December 1989 Process Control Program ML20005E3621989-12-21021 December 1989 Rev 4 to Radiological Environ Monitoring Program, Incorporating Provisions of Generic Ltr 89-01 in Support of Submittal of Tech Spec Proposed Amend 182 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 ML20005G5121989-06-0707 June 1989 Mgt Rancho Seco Contingency Plan 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 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 ML20245G1941989-02-28028 February 1989 Procurement Engineering Assessment Plan Final Rept 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 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 1997-08-19
[Table view] |
Text
-_
RANCH 0'SECO-UNIT 1.
I TECHNICAL SPECIFICATIONS 7
Administrative' Controls TABLE 6.2-1
~
1384- -
SHIFT CREH PERSONNEL AND. LICENSE REQUIREMENTS
-COLD
-0THER THAN
-138-~
POSITION-SHUT 00HN COLD SHUTDOHN i
Shift Supervisor 1-SL 1-SL 1384 Asst. Shift Supervisor or Control Room Operator 2-L 1-SL, 2-L Non-Licensed Operator 1
3 Shift Technical Advisor 0
__1 138*-
Minimum Total Personnel 4
8 1384-In the event that any member of a minimum shift crew is absent or, incapacitated due. to illness or injury, a qualified replacement shall be designated to report on site within two hours.
SL - NRC Senior Licensed Operator L - NRC Licensed Operator l
8711090210 871102 l
PDR-ADOCK 05000312 P-pyg Proposed Amendment No. 138, Rev.;2,' Supplement 1 6 *
.__=_______-w
l RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS
~
Administrative Controls 6.5.2.4 MEETING FRE00ENCY 138-The MSRC shall meet at least once per calendar quarter and as convened by the MSRC Chairman or as directed by the CEO, Nuclear.
OUORUM i
138-6.5.2.5 A quorum of MSRC shall consist of a majority of the members listed in Specification 6.5.2.2, including the chairman or alternate l
chairman.
No more than two alternates shall participate in MSRC l
activities at any one time for the purpose of establishing a quorum.
No more than a minority of the quorum shall have line. responsibility for operation.of the unit.
REVIEW 138-6.5.2.6 The MSRC shall be responsible for review of:
a.
The safety evaluation for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provisions of 10 CFR 50.59 to verify that such actions c'o not constitute an unreviewed safety question, b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
c.
Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59.
d.
Proposed changes in Technical Specifications or the Operating License.
e.
Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal j
procedures or instructions having nuclear safety significance.
i f.
Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.
g.
Licensee Event Reports as defined by 10 CFR 50.73 and NUREG 1022.
h.
Any indication of an identified significant deficiency in the design or operation of safety-related structures, systems, or components.
1
.i.
Reports and meeting minutes of the Plant Review Committee.
- j. Any facility activity brought to the attention of the MSRC by the District's executive management which may be indicative of.
conditions adverse to nuclear safety, i
Proposed Amendment No. 138, Rev. 2, Supplement 1 6-7
RANCHO SECO UNIT 1.
TECHNICAL SPECIFICATI0NS'
.j Administrative Controls.
138*
k.
The MSRC shall provide oversight review'of:
1 1
The District Quality Program, including the' Audit. Program
- d content and implementation, and audit reports.
1 i
The Radioactive Haste Control Program.
)
e Effectiveness of the Licensee Event. Report Program per
-]
Specification 6.6.l.
i 138-AUTHORITY
)
6.5.2.7 The MSRC shall:
i a.
Report to and advise the CEO, Nuclear, of those areas of responsibility specified in Specification:6.5.2.6.
b.
Recommend to the CEO, Nuclear, other areas of facility operation for which the MSRC has determined the need for additional auditing per Specification 6.5.4g.
c.
Advise the CEO, Nuclear, of the need for independent auditing of facility operations.
RECORDS 138--
6.5.2.8 Records of MSRC activities shall be prepared, approved, and distributed as indicated below:
138-a.
Minutes of each MSRC meeting and separate documentation of' reviews encompassed by Specifications 6.5.2.6d,e f,g and h' shall be prepared, approved, and forwarded to the CEO,-
Nuclear, within fourteen (14) days following each meeting.
138-6.5.3 TECHNICAL REVIEW AND CONTROL Activities which affect nuclear safety shall be conducted as I
follows:
a.
Procedures required by Tech'nical Specification 6.8 and other.
procedures which affect plant nuclear; safety,.and changes thereto, shall be prepared, reviewed and approved.
Each such procedure or procedure change shall be reviewed by an individual (s) other than the preparer, but who may be from the-same organization as the individual (s) that; prepared the procedure or procedure change.
Procedures other than plant' administrative procedures will be approved as delineated in-writing by the AGM, Nuclear Power Production, but not lower-than the department ~ manager level.
Such procedures shall be reviewed periodically in accordance with administrative procedures'.
Proposed Amendment No. 138, Rev. 2, Supplement'1 l
'6-8
+
3
_