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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211E7151999-08-20020 August 1999 Proposed Tech Specs,Incorporating Many Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0831999-06-29029 June 1999 Proposed Tech Specs Page 3.4-3,reflecting Implementation of BWROG Enhanced Option I-A,reactor Stability long-term Solution ML20196G7131999-06-23023 June 1999 Proposed Tech Specs Revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5361999-05-0606 May 1999 Proposed Tech Specs Pages,Changing SLMCPR ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20154Q4511998-10-16016 October 1998 TS Bases Update for Period of 970410 Through 981015 ML20236T1661998-07-20020 July 1998 Proposed Tech Specs 3.2.4,3.3.1.1,3.3.1.3,3.4.1,5.6.5, B 3.2.4,B 3.3.1.1,B 3.3.1.3 & B 3.4.1,enabling Full Implementation of Enhanced Option I-A Long Term Solution to Address Neutronic/Thermal Hydraulic Instability Issue ML20198J3581998-01-0909 January 1998 Proposed Tech Specs,Providing Certain Clarifications to Amend & Adding Restriction to Allowed Interval Extensoions ML20198N3941997-10-28028 October 1997 Proposed Tech Specs Implementing Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20211M8481997-10-0606 October 1997 Proposed Tech Specs Replacement Bases Pages Associated W/Proposed Amend to License Re Response Time Testing ML20210V5581997-09-18018 September 1997 Proposed Tech Specs Reflecting Decrease of Two Recirculation Loop SLMCPR Limit to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12 ML20210H0871997-08-0606 August 1997 Proposed Tech Specs Changing TS 3.8.1, AC Sources Operating. Removal of Accelerated Testing Requirements for Standby DGs as Advised by GL 94-01 ML20141A1681997-05-0707 May 1997 Proposed Tech Specs Re Eliminating Selected Response Time Testing Requirements ML20140E3211997-04-18018 April 1997 Proposed Tech Specs,Revising TS Bases to Include Changes Made Since Rev 1 Was Sent to NRC 960201 ML20134N7841996-11-21021 November 1996 Proposed Tech Specs Pp 5.0-20 & 5.0-21,revised by Adding Footnote Indicating Proposed Change Applicable Only for Cycle 9 ML20134N7611996-11-20020 November 1996 Proposed Tech Specs Re MCPR Limits for Two Recirculation Loop Operation ML20134E1261996-10-22022 October 1996 Proposed Tech Specs Revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Procedure, Curves Using Methodology of NRC Reg Guide 1.99, Rev 2, Radiation Embrittlement of Reactor Vessel Matls ML20128M5681996-10-0909 October 1996 Proposed Tech Specs 3.8.1.14 Re Surveillance Requirements ML20117P4461996-09-19019 September 1996 Proposed Tech Specs Re Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117M7021996-09-0505 September 1996 Proposed Tech Specs Re Min Critical Power Safety Limit ML20117G6781996-08-27027 August 1996 Proposed Tech Specs Re Surveillance Requirements for Safety/Relief Valves ML20116F0211996-07-31031 July 1996 Proposed Tech Specs Required to Support Cycle 9,reload 8 ML20113B7381996-06-20020 June 1996 Proposed Tech Specs,Redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20117F4661996-05-0909 May 1996 Proposed Tech Specs,Modifying SRV Surveillance Test for Relief Mode of Operation ML20117D6941996-05-0909 May 1996 Proposed Tech Specs Required to Support Unit 1 Cycle 9, Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits.Addl Methodology Ref in Various TS Bases Revised to Reflect GE Methodologies ML20111B2701996-05-0808 May 1996 Proposed Tech Specs,Placing Containment Purge Valves W/ Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3591996-05-0606 May 1996 Proposed Tech Specs Re Change in Co Name from Mississipi Power & Light to Entergy Mississippi,Inc ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20100J8391996-02-22022 February 1996 Proposed Tech Specs Re Safety Setpoint Tolerance Requirements for Safety/Relief Valves ML20097C3541996-02-0101 February 1996 Proposed Tech Specs,Revising TS Bases to Include Changes Since 950221 Approval of TS Bases ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20087B5061995-08-0404 August 1995 Proposed Tech Specs Assoc W/Various ESF Sys Following Design Basis Fuel Handling Accident ML20082K3451995-04-13013 April 1995 Proposed Tech Specs Re Change to Be Reduced to Leave in TS Requirement to Test Outboard MSIV LCS Blowers ML20078S5141995-02-14014 February 1995 Proposed TS Consisting of Changes to SR 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6611995-02-10010 February 1995 Proposed Tech Specs Supporting Performance of Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4501994-11-0909 November 1994 Proposed Tech Specs Associated W/Various ESF Systems Following Design Basis Fuel Handling Accident ML20070C9751994-06-24024 June 1994 Proposed TS Pages 3/4 6-4 & 3/4 6-6 Associated W/Proposed Exemption to 10CFR50,App J ML20065L4971994-04-15015 April 1994 Proposed Tech Specs Re Administrative Controls ML20059H6061994-01-13013 January 1994 Proposed Tech Specs,Removing 2,324 Spent Fuel Pool Storage Limit ML20058D3911993-11-23023 November 1993 Proposed Tech Specs Bases Pages Re Cycle 7 Reload ML20059A4871993-10-22022 October 1993 Proposed Tech Specs Modifying Testing Frequencies for Drywell Test & Airlock Tests ML20059B0351993-10-15015 October 1993 Proposed Tech Specs Converting Current GGNS TS to TS Based Largely on NUREG-1434,Rev 0 ML20057C7281993-09-23023 September 1993 Proposed Tech Specs Removing Surveillance Requirement 4.4.1.2.2 Due to Problems Encountered W/Jet Pump Differential Pressure Instrumentation Measurements ML20056E4511993-08-12012 August 1993 Proposed Tech Specs 3/4 6-3,6-4,6-4a,6-6,6-12 Re Exemption to 10CFR50,App J, Primary Reactor Containment..., for Local Leak Rate ML20056D5621993-08-11011 August 1993 Proposed Tech Specs Section 3/4.3.7.5 Reflecting Relocation of Certain Accident Monitoring Instrumentation to Administrative Control ML20046D2081993-08-11011 August 1993 Proposed Tech Specs Section 3/4.3.7.10, Loose Part Detection Sys, Relocating Loose Part Detection Instrumentation from TS to Administrative Control ML20046D1961993-08-11011 August 1993 Proposed Tech Specs Supporting Compliance W/New Requirements of 10CFR20 & 10CFR50.36a ML20056C7141993-07-15015 July 1993 Proposed Tech Specs Removing Operability Requirements for auto-test Feature of Load Shedding & Sequencing Sys & Increase AOT for Inoperable Load Shedding & Sequencing Sys from Eight to Twelve 1999-08-20
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211E7151999-08-20020 August 1999 Proposed Tech Specs,Incorporating Many Generic Improvements Agreed Upon Between Industry & NRC Since GGNS Conversion to ITS ML20196K0831999-06-29029 June 1999 Proposed Tech Specs Page 3.4-3,reflecting Implementation of BWROG Enhanced Option I-A,reactor Stability long-term Solution ML20196G7131999-06-23023 June 1999 Proposed Tech Specs Revising TS Associated with Various Esfss Which Need No Longer Be Credited Following Design Basis Fuel Handling Accident ML20206K5361999-05-0606 May 1999 Proposed Tech Specs Pages,Changing SLMCPR ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20154Q4511998-10-16016 October 1998 TS Bases Update for Period of 970410 Through 981015 ML20236T1661998-07-20020 July 1998 Proposed Tech Specs 3.2.4,3.3.1.1,3.3.1.3,3.4.1,5.6.5, B 3.2.4,B 3.3.1.1,B 3.3.1.3 & B 3.4.1,enabling Full Implementation of Enhanced Option I-A Long Term Solution to Address Neutronic/Thermal Hydraulic Instability Issue ML20198J3581998-01-0909 January 1998 Proposed Tech Specs,Providing Certain Clarifications to Amend & Adding Restriction to Allowed Interval Extensoions ML20210F6651997-12-22022 December 1997 Redeacted Version of Test Rept M-J5.08-Q1-45161-0-8.0-1-0, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators for Entergy Operations ML20217H6211997-12-15015 December 1997 Rev 21 to Odcm ML20199L5711997-11-26026 November 1997 Rev 8 to Program Plan GGNS-M-189.1, Grand Gulf Nuclear Station Pump & Valve IST Program - Safety Related ML20198N3231997-11-0606 November 1997 Rev 11 to GGNS-M-489.1, Program Plan for ASME Section XI ISI Plan ML20198N3941997-10-28028 October 1997 Proposed Tech Specs Implementing Option B & Ref SE Issued by NRR for Ggns'S App J Exemption as Implementing Document for performance-based Leakage Testing Program ML20211M8481997-10-0606 October 1997 Proposed Tech Specs Replacement Bases Pages Associated W/Proposed Amend to License Re Response Time Testing ML20210V5581997-09-18018 September 1997 Proposed Tech Specs Reflecting Decrease of Two Recirculation Loop SLMCPR Limit to 1.11 & Single Recirculation Loop SLMCPR Limit to 1.12 ML20210H0871997-08-0606 August 1997 Proposed Tech Specs Changing TS 3.8.1, AC Sources Operating. Removal of Accelerated Testing Requirements for Standby DGs as Advised by GL 94-01 ML20141A1681997-05-0707 May 1997 Proposed Tech Specs Re Eliminating Selected Response Time Testing Requirements ML20140E3211997-04-18018 April 1997 Proposed Tech Specs,Revising TS Bases to Include Changes Made Since Rev 1 Was Sent to NRC 960201 ML20134N7841996-11-21021 November 1996 Proposed Tech Specs Pp 5.0-20 & 5.0-21,revised by Adding Footnote Indicating Proposed Change Applicable Only for Cycle 9 ML20134N7611996-11-20020 November 1996 Proposed Tech Specs Re MCPR Limits for Two Recirculation Loop Operation ML20134E1261996-10-22022 October 1996 Proposed Tech Specs Revising TS Figure 3.4.11-1, Minimum Reactor Vessel Metal Temperature Vs Reactor Vessel Procedure, Curves Using Methodology of NRC Reg Guide 1.99, Rev 2, Radiation Embrittlement of Reactor Vessel Matls ML20128M5681996-10-0909 October 1996 Proposed Tech Specs 3.8.1.14 Re Surveillance Requirements ML20117P4461996-09-19019 September 1996 Proposed Tech Specs Re Containment Purge Valves W/Resilient Seals on Performance Based Leakage Testing Frequency ML20117M7021996-09-0505 September 1996 Proposed Tech Specs Re Min Critical Power Safety Limit ML20117G6781996-08-27027 August 1996 Proposed Tech Specs Re Surveillance Requirements for Safety/Relief Valves ML20116F0211996-07-31031 July 1996 Proposed Tech Specs Required to Support Cycle 9,reload 8 ML20113B7381996-06-20020 June 1996 Proposed Tech Specs,Redefining Secondary Containment Boundary to Allow Encl Bldg to Be Inoperable During Upcoming Refueling Outage ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20117D6941996-05-0909 May 1996 Proposed Tech Specs Required to Support Unit 1 Cycle 9, Including Changes to SLMCPR & Ref for Analytical Methods Used to Determine Core Operating Limits.Addl Methodology Ref in Various TS Bases Revised to Reflect GE Methodologies ML20117F4661996-05-0909 May 1996 Proposed Tech Specs,Modifying SRV Surveillance Test for Relief Mode of Operation ML20111B2701996-05-0808 May 1996 Proposed Tech Specs,Placing Containment Purge Valves W/ Resilient Seals on Performance Based Leakage Testing Frequency ML20108E3591996-05-0606 May 1996 Proposed Tech Specs Re Change in Co Name from Mississipi Power & Light to Entergy Mississippi,Inc ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20100J8391996-02-22022 February 1996 Proposed Tech Specs Re Safety Setpoint Tolerance Requirements for Safety/Relief Valves ML20097C3541996-02-0101 February 1996 Proposed Tech Specs,Revising TS Bases to Include Changes Since 950221 Approval of TS Bases ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20087B5061995-08-0404 August 1995 Proposed Tech Specs Assoc W/Various ESF Sys Following Design Basis Fuel Handling Accident ML20082K3451995-04-13013 April 1995 Proposed Tech Specs Re Change to Be Reduced to Leave in TS Requirement to Test Outboard MSIV LCS Blowers ML20108A2691995-03-10010 March 1995 Rev 17 to ODCM ML20078S5141995-02-14014 February 1995 Proposed TS Consisting of Changes to SR 4.4.1.4.a.1 & 4.6.1.4.a.2 ML20078N6611995-02-10010 February 1995 Proposed Tech Specs Supporting Performance of Drywell Bypass Leakage Rate Surveillance on Performance Based Interval ML20079B4501994-11-0909 November 1994 Proposed Tech Specs Associated W/Various ESF Systems Following Design Basis Fuel Handling Accident ML20070C9751994-06-24024 June 1994 Proposed TS Pages 3/4 6-4 & 3/4 6-6 Associated W/Proposed Exemption to 10CFR50,App J ML20065L4971994-04-15015 April 1994 Proposed Tech Specs Re Administrative Controls ML20059H6101994-01-14014 January 1994 Cycle 7 Startup Physics Test Summary Rept for Physics Testing Completed on 931220 ML20059H6061994-01-13013 January 1994 Proposed Tech Specs,Removing 2,324 Spent Fuel Pool Storage Limit ML20029D6451993-11-30030 November 1993 Reactor Containment Bldg 1993 Integrated Leakage Rate Test. ML20058D3911993-11-23023 November 1993 Proposed Tech Specs Bases Pages Re Cycle 7 Reload ML20059A4871993-10-22022 October 1993 Proposed Tech Specs Modifying Testing Frequencies for Drywell Test & Airlock Tests 1999-08-20
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(MIS $1SS!PP! POWER &LIGHTCOMPANY SYSTEF ENERGY RESOURCES INC.
$0VTH MIS $155fPPI ELECTRIC POWER A550CIAT10N i
DOCKET N0. 50-416 1: !
GRAND GULF NUCLEAR STATION, UNIT 1 FACILITY OPERATING LICENSE License No. NPF-29 {
- 1. The Nuclear Regulatory Comission (the Comission or the NRC) has found that: ;
, A. The application for license filed by Mississippi Power & Light Company (MP&L), for itself and Middle South Energy, Inc., (now renamed System Energy Resources, Inc. (SERI)) and South Mississippi Electric Power Associationpereinafter referred, !
to as the licensees) complies with the standards and require-ments cf the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's regulations set forth in 10 CFR Chapter I, and all required notifications to other a9encies or bodies have I been duly made; S. Censtruction of the Grand Gulf Nuclear Station, Unit 1 (the facility), has been substantially completed in conformity with i -
l Construction Pemit No. CPPR-118 and the application, as amended, the provisions of the Act, and the regulations of the Comission; ,
C. The facility will operate in confomity with the application, as amended, the provisions of the Act, and the regulations of the Commistion (except as exempted from compliance in Section 2.0. t below); i D. There is reasonable assurance: (1)thattheactivitiesauthorized by this operating license can be conducted without endangerino the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CfR Chapter I (except as exempted from compliance in Section 2.D. below);
Enf*Nr E. .,j;ytemAwat70'n.5, Ene, u = = sei, &. CEQX)ns a . (SERI)* is technically qualified I to engage in the activities authorized by this operating license in accordance with the Comission's regulations set forth in 10 CFR Chapter I;
.- .. ....<__,__; .. ... ,__ 1.._,, __; ,__ mu __2 m_ __.i... . . . .
m A ed Iid . .J m a i .a .L_ mL la i __ .a J .m Am amM
.'...E. . ; ; ; ;_ . ' I', E. ' R. . . . I. L., ". ~ ' " ' ' "' ' ' ' ' ' ' "" ' ' " ' ' ' "" ' " " ' ' ' ' ' " ' ' " '
Amendment No. 27) l
. -- . _ _ . . - _ _ ~ . - - _ . - . . - - - - _ - . - - -
7 (13)4.4.<,,
L(5ection 5ER)C ro Stability Analysis and Prohibition of Natural Circulat
]
(a) Prior to startup following the first refueling outage. l shall submit a new core stability analysis for operation beyond cycle 1.
(b) Natural circulation shall be prohibited as an operating !
mode. '
(14) Loose Parts Monitorino (Section 4.4.1, SER) jp ;
Prior to startup following the first refueling outage, I shall submit an evaluation of the Loose Parts Monitoring System to address conformance to R.G. 1.133. Rev. 1, dated May 1981.
(15) Scram Discharge Volume (Sections 4.6,SER)
Prior to startup following the first refueling outage I shall incorporate the following additional modifications into the scram discharge volume system:
(i) Redundant vent and drain valves, and
! (11) Diverse and redundant scram ir.strumentation for each instrumented volume, including both delta pressure sensers and float sensors.
(16)ContainmentPurce(Section6.2.4,SSER#5) gp Prior to startup following the first refueling outage, shall b provide for NRC review a reevaluation of the need to use the con-tainment purge mode of the containment cooling system. This study should include, but is not limited to, data qathered during the first fuel cycle related to airborne activity ' evel (ALARA),
overall containment air cuality and personnel access to contain-i l
g/ ment. Based on the above cited study,A4EM- shall propose the g-purge criteria to be used for the remainder of the plant life. .
(17)ContainmentPressureSoundary(Section6.2.8,SER)
Prior to startup following the first refueling outage,A66A+ shall !
replace the feedwater check valve disc with a disc made from a
, suitable material.
(18) Pressure Interlocks on Yalves Interfacino at low and Hioh Pressure _
(Section 6.3.4, 55ER #2)
Prior to startup following the first refueling outage, tm,,Jnna shall implement isolation protection against overpressurization l>
of the low pressure emergency core cooling systems (RHR/LP I and LPCS) at the high and low pressure interface containing a check valve and a closed motor-operated valve.
Amendment No. 23 l' l -
Novemb e r 1, 1944.
i d l
. APPENDIX C ANTITRU$7 CONDITION $
CPERuinc, Lugnst no, ner.29
- c ~Ose.isem 1% sees 4 ppeda b rvae.rs %wP4< 45ek.r.) .
MFAL and $ER%shall comply with the following antitrust conditions:
I. DEFIN! TION $
(a) ' Western Mississippi Area' means the counties of: Walthall, Lawrence, Jefferson Davis, Covington, Simpson, Smith, Scott, Leake Atta14 Choctaw, Montdomery, Grenada Yalobusha, Panola, Tate, DeSoto, Pike Amite, W' Ikinson, Adams, Franklin, Lincoln, Copiah, Jefferson, Claiborne, Hinds, Rankin Nadison, Yazoo, l i
Warren, Issaquena, Sharkey, Humphreys, Holmes, Carroll, Leflore, Sunflower Washington, Bolivar. Tallahatchie Quitman, Coahoma, and Tunica. An entity shall be deemed to be in the ' Western I Mississippi Area' if it has electric power generation, transmis-sion, or distribution facilities located in whole or in part in the above described area.
(b) ' Sulk Power' means the electric power, and any attendant energy, supplied or made available at transmission or subtransmission voltage by one entity to another.
(c)
- Entity" means a person, a private or public corporation, a municipality, a cooperative, an association, a joint stock association or business trust owning, operating or proposing to own or operate equipment or facilities for the generation, trans-
- mission or distribution of electricity, provided that, except for municipalities or rural electric cooperatives ' entity" is restricted to those which are or will be public utilities under the laws of the state in which the entity trsnsacts or will transact business or under the Federal Power Act, and are or will be providing electric service under a contract or rate schedule on file with and subject to the regulation of a state regulatory commission or the Federal Power Commission. .
(d) ' Cost" means any operating and maintenance expenses involved together with any ownership costs which are reasonably allocable to the transaction consistent with power pooling practices (whereapplicable). No value shall be included for loss of revenues from sale of power at wholesale or retail by one party .
to a customer which another party might otherwise serve. Cost shail include a reasonable return on Licensees' investment. The sale of a portion of the capacity of a generating unit shall be upon the basis of a rate that will recover to the seller the pro rata part of the fixed costs and operating and maintenance .
Amendment No. 27 3
_. l
. i ADMINISTRATIVE CONTROLS
, 6.5.2 SAFETY REVIEW COMITTEE (SRC)
FUNCTION 6.5.2.1 The SRC shall function to provide independent review and audit of designated activities in the areas of: '
- a. nuclear power plant operations -
- b. nuclear engineering '
- c. chemistry and radiochemistry
- d. metallurgy
- e. instrumentation and control
- f. radiological safety
- g. mechanical and electrical engineering
- h. quality assurance practices COMPOSITION Edugor dsts,Mc. .
6.5.2.2 The SRC shall be composed of a Chairman and nine voting members. Two l
'--- ~ "- ,
or more additional voting members shall be consultants tog P-4M. consistent with the recommendations of the Advisory Coimmittee on Reactor- ---- l Safeguards letter, Mark to Palladino dated October 20, 1981.
The Chairman and members shall meet the qualifications below.
The SRC Chairman shall hold a Bachelor's degree in an engineering or physical science field or an equivalent and a minimum of six years of professional level managerial experience in the power field. In addition, the Chairman shall have the necessary overall nuclear background to determine when to call consultants and contractors for dealing with complex problems beyond the scope4of .,. _ ..... . ........., .. ,. expertise. {g g y Opexdo'ns, Tnc]
The SRC members shall hold a Bachelor's degree in an engineering or physical ,
science field or equivalent experience and a minimum of five years of technical 1 i
experience of which a minimum of three years shall be in one or more of the disciplines of 6.5.2.la through h. In the aggregate, the membership of the committee shall provide specific practical experience in the majority of the disciplines of 6.5.2.la through h.
ALTERNATES l
6.5.2.3 All alternate members shall be appointed in writing by the SRC I Chairman to serve on a temporary basis; however, no more than two alternates I shall participate as voting members in SRC activities at any one time.
l I
GRAND GULF-UNIT 1 6-9 Amendment No. 64,_
1