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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217B9061999-10-0101 October 1999 Proposed Tech Specs Re Control Rod Block Instrumentation ML20212H5261999-09-27027 September 1999 Proposed Tech Specs Pages,Revising TS Re Loss of Power Setpoints for 4 Kv Emergency Buses ML20210N0801999-08-0606 August 1999 Proposed Tech Specs Incorporating Note Which Will Permit one-time Exemption Until 990930,from 90 F Limit Stated in SR 3.7.2.2 ML20210E6001999-07-21021 July 1999 Proposed Tech Specs,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20209F7751999-07-12012 July 1999 Proposed Tech Specs Sections 2.1.1.2 & 5.6.5,incorporating Revised SLMCPR Due to Use of Cycle Specific Analysis & Deleting Previously Added Footnotes Which Are No Longer Necessary ML20209D9861999-07-0808 July 1999 Proposed Final Tech Spec Pages Correcting Minor Administrative Errors in Figure Showing Site & Exclusion Boundaries & Two SRs ML20209B9211999-07-0101 July 1999 Proposed Tech Specs,Reflecting Change in Corporate Structure ML20196A5441999-06-14014 June 1999 Proposed Final Tech Spec Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware ML20195B8271999-05-25025 May 1999 Proposed Final Tech Specs Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20205F6391999-03-29029 March 1999 Proposed Tech Specs Pages,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20207E2551999-03-0101 March 1999 Proposed Tech Specs Supporting PBAPS Mod P00507 Which Will Install Power Range Neutron Monitoring Sys Incorporate long-term T/H Stability Solution Hardware ML20198N2531998-12-24024 December 1998 Proposed Tech Specs Revising Setpoints & Limits of Allowable Values for LOP Instrumentation for 4kV Emergency Buses Contained in TS Table 3.3.8.1-1, LOP Instrumentation ML20154C8271998-09-29029 September 1998 Proposed Tech Specs SR 3.6.4.1.2,revising Wording to Maintain Requirement That Secondary Containment Is Not Breached at Any Time When Secondary Containment Is Required ML20151Y3841998-09-14014 September 1998 Revised Proposed Final TS Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Units 2 & 3 ML20151Y3711998-09-11011 September 1998 Proposed Final TS Pages for License Change Application ECR 98-01403,revising SLMCPRs for Unit 2 ML20151Y3651998-09-11011 September 1998 Proposed Final TS Pages for License Change Applications ECR 96-02324 & 98-00499,revising MSIV Leakage & Safety Relief Valve Surveillance Testing ML20151T0421998-08-31031 August 1998 Proposed Final Tech Specs Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Plant ML20236W2201998-07-29029 July 1998 Proposed Tech Specs,Supporting Installation of Mod P00271 for Unit 2 Re Replacement of Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20236R3121998-07-10010 July 1998 Proposed Tech Specs Pages for License Change Application ECR 98-01403,revising TS Section 2.0.W/non-proprietary Addl Info Re 1.10 Cycle Specific SLMCPR Cycle 13 ML20236P7531998-07-0909 July 1998 Proposed Tech Specs Supporting Installation of Mod P00271, for Unit 2 Re Facility Operating License Change Request 93-18 ML20247C2611998-05-0101 May 1998 Proposed Tech Specs Deleting Requirements for Functional Testing of SRVs During Each Unit Startup ML20217K3651998-04-28028 April 1998 Proposed Tech Specs Bases Through Unit 2 Bases Rev 17 & Unit 3 Bases Rev 19 ML20217G7531998-03-20020 March 1998 Proposed Tech Specs Re end-of-cycle Recirculation Pump Trip Sys at Plant ML20217Q4711998-03-0202 March 1998 Proposed Tech Specs Adding Requirements to Achieve Compliance w/10CFR50.36a, TS on Effluents from Nuclear Power Reactors ML20202F4201998-02-0404 February 1998 Proposed Tech Specs Revising SR 3.6.4.1.2 & Associated Bases to Reflect Changes in Requirements for Secondary Containment Doors ML20211H9281997-09-26026 September 1997 Proposed Tech Specs,Replacing Page 2.0-1 & Adding Page 5.0-21 for Unit 3 ML20211F4001997-09-22022 September 1997 Proposed Tech Specs Replacing Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20141G4871997-06-30030 June 1997 Proposed Tech Specs,Revising TS Section 2.0, Safety Limits to Incorporate Revised SLMCPRs Due to Use of GE13 Fuel Product Line & cycle-specific Analysis Performed by GE ML20140D8601997-06-0404 June 1997 Proposed Tech Specs,Revising Section 3.8.2.1 to Eliminate Inconsistency Between Requirements for ECCS Operability & auto-start & Trip Bypass of of EDGs on ECCS Initiation Signal During Listed Events in Application ML20141L0111997-05-23023 May 1997 Proposed Tech Specs Revising Section 5.5.12 to Exclude Measured Main Steam Isolation Valves Leakage from Total Type B & C Local Leak Rate Test Results ML20141E0801997-05-0909 May 1997 Proposed Tech Specs 3.6.1.3.16,replacing Frequency of Primary Containment Purge & Exhaust Valve Inflatable Seals ML20137P7561997-03-31031 March 1997 Proposed Tech Specs,Extending Surveillance Interval for Calibr of Average Power Range Monitor Flow Bias Instrumentation from 18 Months to 24 Months ML20134F6121996-10-30030 October 1996 Proposed Tech Specs,Section 2.0,revising Slmcprs Due to GE Determination That Previous Calculation Is Nonconservative ML20117L2891996-09-0606 September 1996 Proposed Tech Specs 3.3.5.1, ECCS Instrumentation, & 3.8.1, AC Sources-Operating ML20117F9471996-08-27027 August 1996 Proposed Tech Specs Re CRD Charging Water Header Pressure for Shutdown Margin Test ML20117H6761996-08-23023 August 1996 Proposed Tech Specs 2.0 Re Safety Limits ML20117M7041996-06-13013 June 1996 Proposed Tech Specs,Sr 3.3.1.1.12,for APRM Flow Biased High Scram Function,Allowing SR to Be Performed W/O Entering Associated Conditions & Required Actions for Up to Six H Provided Core Flow at or Above 82% ML20101K8131996-03-25025 March 1996 Proposed Tech Specs Section 2.0 Re Safety Limits ML20100J7591996-02-15015 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20096F1481996-01-16016 January 1996 Proposed Tech Specs Base Changes Re Implementation of Main Stack & Vent Stack Radiation Monitoring Sytems ML20095L0231995-12-22022 December 1995 Proposed Improved TS & Bases,Allowing Flexibility to Install Main Stack Rms (Mod 5386) W/O Need for Addl Licensing Actions & Addressing Annotations to Reflect pre- & post-mod Scenarios,Respectively ML20095J1321995-12-21021 December 1995 Proposed Tech Specs,Consisting of Change Request 95-08, Eliminating Outdated Matl from FOLs & Making FOL for Unit 2, Consistent W/Fol for Unit 3 ML20095J7011995-12-19019 December 1995 Proposed Tech Specs Re Administrative Change to Ventilation Filter Testing Program ML20095A1731995-11-30030 November 1995 Proposed Tech Specs,Changing Minimum Allowable Control Rod Scram Accumulator Pressure & Charging Water Header Pressure from Value of 955 Psig to Value of 940 Psig ML20094R2971995-11-22022 November 1995 Revised,Proposed TS Pages 147,157 & 158 Re Early Implementation of Improved TS Section 3.4.3 ML20094Q6801995-11-21021 November 1995 Proposed Tech Specs Re SR for High Pressure Test of HPCI & B 3.5-14 & B 3.5-28.Administrative Change Proposed to Eliminate Ref to Section Previously Eliminated ML20092A2141995-09-0101 September 1995 Proposed Tech Specs,Consisting of Change Request 95-07, Deleting License Condition 2.C ML20092A2841995-08-30030 August 1995 Proposed Tech Specs,Requesting Enforcement Discretion from Portion of FOL Condition 2.C ML20092B9871995-08-28028 August 1995 Proposed Improved Tech Specs ML20087E8881995-08-0404 August 1995 Proposed Tech Specs Re Implementation of New SR Associated W/Conversion to TS 1999-09-27
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B9061999-10-0101 October 1999 Proposed Tech Specs Re Control Rod Block Instrumentation ML20212H5261999-09-27027 September 1999 Proposed Tech Specs Pages,Revising TS Re Loss of Power Setpoints for 4 Kv Emergency Buses ML20210N0801999-08-0606 August 1999 Proposed Tech Specs Incorporating Note Which Will Permit one-time Exemption Until 990930,from 90 F Limit Stated in SR 3.7.2.2 ML20210E6001999-07-21021 July 1999 Proposed Tech Specs,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20209F7751999-07-12012 July 1999 Proposed Tech Specs Sections 2.1.1.2 & 5.6.5,incorporating Revised SLMCPR Due to Use of Cycle Specific Analysis & Deleting Previously Added Footnotes Which Are No Longer Necessary ML20209D9861999-07-0808 July 1999 Proposed Final Tech Spec Pages Correcting Minor Administrative Errors in Figure Showing Site & Exclusion Boundaries & Two SRs ML20209B9211999-07-0101 July 1999 Proposed Tech Specs,Reflecting Change in Corporate Structure ML20196A5441999-06-14014 June 1999 Proposed Final Tech Spec Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware ML20195B8271999-05-25025 May 1999 Proposed Final Tech Specs Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20206C5821999-04-20020 April 1999 Rev 4 to RW-C-100, Solid Radwaste Sys Process Control Program (Pcp) ML20205F6391999-03-29029 March 1999 Proposed Tech Specs Pages,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20207E2551999-03-0101 March 1999 Proposed Tech Specs Supporting PBAPS Mod P00507 Which Will Install Power Range Neutron Monitoring Sys Incorporate long-term T/H Stability Solution Hardware ML20202E6251998-12-31031 December 1998 PBAPS Unit 2 Cycle 13 Startup Rept. with ML20198N2531998-12-24024 December 1998 Proposed Tech Specs Revising Setpoints & Limits of Allowable Values for LOP Instrumentation for 4kV Emergency Buses Contained in TS Table 3.3.8.1-1, LOP Instrumentation ML20195J1651998-11-16016 November 1998 Rev D to LGS Emergency Preparedness NUMARC Eals ML20195J1541998-11-16016 November 1998 Rev D to PBAPS Emergency Preparedness NUMARC Eals ML20154C8271998-09-29029 September 1998 Proposed Tech Specs SR 3.6.4.1.2,revising Wording to Maintain Requirement That Secondary Containment Is Not Breached at Any Time When Secondary Containment Is Required ML20151Y3841998-09-14014 September 1998 Revised Proposed Final TS Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Units 2 & 3 ML20151Y3711998-09-11011 September 1998 Proposed Final TS Pages for License Change Application ECR 98-01403,revising SLMCPRs for Unit 2 ML20151Y3651998-09-11011 September 1998 Proposed Final TS Pages for License Change Applications ECR 96-02324 & 98-00499,revising MSIV Leakage & Safety Relief Valve Surveillance Testing ML20151T0421998-08-31031 August 1998 Proposed Final Tech Specs Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Plant ML20236W2201998-07-29029 July 1998 Proposed Tech Specs,Supporting Installation of Mod P00271 for Unit 2 Re Replacement of Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20236R3121998-07-10010 July 1998 Proposed Tech Specs Pages for License Change Application ECR 98-01403,revising TS Section 2.0.W/non-proprietary Addl Info Re 1.10 Cycle Specific SLMCPR Cycle 13 ML20236P7531998-07-0909 July 1998 Proposed Tech Specs Supporting Installation of Mod P00271, for Unit 2 Re Facility Operating License Change Request 93-18 ML20247C2611998-05-0101 May 1998 Proposed Tech Specs Deleting Requirements for Functional Testing of SRVs During Each Unit Startup ML20217K3651998-04-28028 April 1998 Proposed Tech Specs Bases Through Unit 2 Bases Rev 17 & Unit 3 Bases Rev 19 ML20206C5711998-04-16016 April 1998 Rev 11 to ODCM for Pbaps,Units 1 & 2 ML20217G7531998-03-20020 March 1998 Proposed Tech Specs Re end-of-cycle Recirculation Pump Trip Sys at Plant ML20217Q4711998-03-0202 March 1998 Proposed Tech Specs Adding Requirements to Achieve Compliance w/10CFR50.36a, TS on Effluents from Nuclear Power Reactors ML20202F4201998-02-0404 February 1998 Proposed Tech Specs Revising SR 3.6.4.1.2 & Associated Bases to Reflect Changes in Requirements for Secondary Containment Doors ML20202H4141998-01-31031 January 1998 Cycle 12 Startup Rept Unit 3 ML20211H9281997-09-26026 September 1997 Proposed Tech Specs,Replacing Page 2.0-1 & Adding Page 5.0-21 for Unit 3 ML20211F4001997-09-22022 September 1997 Proposed Tech Specs Replacing Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20141G4871997-06-30030 June 1997 Proposed Tech Specs,Revising TS Section 2.0, Safety Limits to Incorporate Revised SLMCPRs Due to Use of GE13 Fuel Product Line & cycle-specific Analysis Performed by GE ML20140D8601997-06-0404 June 1997 Proposed Tech Specs,Revising Section 3.8.2.1 to Eliminate Inconsistency Between Requirements for ECCS Operability & auto-start & Trip Bypass of of EDGs on ECCS Initiation Signal During Listed Events in Application ML20141L0111997-05-23023 May 1997 Proposed Tech Specs Revising Section 5.5.12 to Exclude Measured Main Steam Isolation Valves Leakage from Total Type B & C Local Leak Rate Test Results ML20141E0801997-05-0909 May 1997 Proposed Tech Specs 3.6.1.3.16,replacing Frequency of Primary Containment Purge & Exhaust Valve Inflatable Seals ML20141J0311997-05-0808 May 1997 Rev 7 to Pump & Valve IST Program Third Ten Yr Interval ML20137P7561997-03-31031 March 1997 Proposed Tech Specs,Extending Surveillance Interval for Calibr of Average Power Range Monitor Flow Bias Instrumentation from 18 Months to 24 Months ML20217M8301997-01-30030 January 1997 Rev 10 to ODCM, for Peach Bottom Atomic Power Station Units 1 & 2 ML20134A6751997-01-24024 January 1997 Cycle 12 Startup Rept Unit 2 ML20134F6121996-10-30030 October 1996 Proposed Tech Specs,Section 2.0,revising Slmcprs Due to GE Determination That Previous Calculation Is Nonconservative ML20138B0081996-09-27027 September 1996 Rev 3 to Solid Radwaste Sys Process Control Program (Pcp) ML20117L2891996-09-0606 September 1996 Proposed Tech Specs 3.3.5.1, ECCS Instrumentation, & 3.8.1, AC Sources-Operating ML20117F9471996-08-27027 August 1996 Proposed Tech Specs Re CRD Charging Water Header Pressure for Shutdown Margin Test ML20117H6761996-08-23023 August 1996 Proposed Tech Specs 2.0 Re Safety Limits ML20117M7041996-06-13013 June 1996 Proposed Tech Specs,Sr 3.3.1.1.12,for APRM Flow Biased High Scram Function,Allowing SR to Be Performed W/O Entering Associated Conditions & Required Actions for Up to Six H Provided Core Flow at or Above 82% ML20101K8131996-03-25025 March 1996 Proposed Tech Specs Section 2.0 Re Safety Limits ML20100J7591996-02-15015 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20096F1481996-01-16016 January 1996 Proposed Tech Specs Base Changes Re Implementation of Main Stack & Vent Stack Radiation Monitoring Sytems 1999-09-27
[Table view] |
Text
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PEACH BOTTOM ATOMIC POWER STATION L UNITS 2 AND 3 -!
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Docket Nos. 50-277 3 50-278 License Nos. DPR-44 DPR-56 '
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TECHNICAL SPECIFICATION CHANGES Unit 2 1
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Unit 2 l g,. 5.2.3 Independent Safety Enoineerino Group (ISEc) '
Function- i
'6.2.3.1 The ISEG shall function to responsively and proactively examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design and. operating experience.
information, including units of similar design, which may indicate areas for improving unit safety. The ISEG shall make detailed recommendations for '
revised procedures, equipment modifications, maintenance activities.-
operations activities, or other means of improving unit safety. Such '
recommendations shall be submitted through the General Manager, Nuclear Quality Assurance to the Executive Vice President-Nuclear. !
Composition 6.2.3.2 The Peach Bottom ISEG shall be composed of at least five dedicated, full- '
time engineers, including the ISEG Superintendent, located onsite. The Peach Bottom ISEG shall meet all of the following qualification requirements:
- a. Each member shall have a bachelor's degree in engineering or related ;
science. '
- b. The ISEG Superintendent shall have at least six years of full-time :
commercial nuclear experience.
- c. Each of the members shall have at least two years of full-time commercial nuclear experience.
- d. Not more than one of the members shall have less than three years of i" full-time commercial nuclear experience.
- e. Excluding the experience of the Superintendent, the members collectively shall have at least 16 years of full-time commercial i nuclear experience.
- f. The ISEG (Superintendent included) collectively shall have the broad range of knowledge and experience necessary to perform the functions-
.and responsibilities specified in 6.2.3.1 and 6.2.3.3.
Responsibilities 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
Authority
- 6.2.3.4 The ISEG reports to the General Manager, Nuclear Quality Assurance. If any significant nuclear quality concern identified by the ISEG is not adequately resolved, the General Manager, Nuclear Quality Assurance shall notify the Nuclear Review Board, the Executive Vice President-Nuclear or the Nuclear Committee of the Board. If the ISEG is not satisfied with the resolution of -
any significant nuclear quality concern by the General Manager, Nuclear Quality Assurance, the ISEG shall notify the Nuclear Review Board of that Concern.
Records 6.2.3.5 Records of activities performed by the ISEG shall be prepared, maintaincd, and forwarded each calendar month to the General Manager, Nuclear Quality Assurance.
l *Not responsible for sign-off function 1
-245b-l
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6 .
PBAPS -
L 6.5.2 Nuclear Review Board Function 6.5.2.1 The Nuclear Review Board (NRB) shall function to t' provide independent review and audit of designated activities in the area of: '
o
- 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 The members of the NRB will be competent in the area of quality assurance practice and cognizant of the Quality Assurance requirements of 10 CPR ,
50, Appendix B. Additionally, they will be rognizant of the corporate Quality Assurance Program and will have the corporate Quality Assurance organization available to them.
Organization 6.5.2.2 The Chairman, members and alternate members of the NRB shall be appointed in writing by the Executive Vice President - Nuclear, and shall have an academic degree in an engineering or physical science field and in.
addition, shall have a minimum of five years technical experience, of which a minimum of three years shall be in one or more areas given in 6.5.2.1.
The NRB shall be composed of at least five members who are Philadelphia Electric Company (PECo) employees and l at least two outside members who are not PECo employees.
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Unit.2
, .PBAPS-N 1 Alternates ~ '
t 26.5.2.3 A current list of alternates shall be maintained-in l 0 NRB' records. Each alternate member will' serve on a continuing basis. Alternates shall vote only in the g k absence,of that member for whom they_are the '
designated alternate, v
I' Consultants D
6.5.2.4' Consultants shall be utilized as determined by the NRB p Chairman to provide expert advice to the NRB. '
i Meeting Frequency b l6'.5.2.5' The NRB shall meet at least once per calendar quarter. l Quotum 6.5.2.6 A quorum of the.NRB shall consist of the Chairman or Vice Chairman or their designated alternates:and four members or their alternates.' No more than a' minority of the quorum shall have line responsibility for operation of the facility.- ;
Review p
6.5.2.7- The NRB shall review:
- a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of 10 CPR 50.59, to verify that such actions did not constitute an unreviewed safety question.
E
- 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.
-250-
Unit 3 pj '*a6.2.3f Independent Safety Engineerino Group (ISEG)
Function J}
6.2.3.1 The ISEG shall function to responsively and proactively examine unit operating characteristics NRC issuances. industry advisories, Licensee
, Event Reports', and other sources of unit design and operating experience information, including units of similar design, which may. indicate areas for improving unit safety. The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving unit safety. Such recommendations shall be submitted through the General Manager, Nuclear Quesity Assurance to the Executive Vice President-Nuclear.
Composition 6;2.3.2 The Peach Bottom ISEG shall be composed of at least five dedicated, full-time engineers, including the ISEG Superintendent, located onsite. The Peach Bottom ISEG shall meet all of the following qualification requirements:
- a. Each member shall have a bachelor's degree in engineering or related science.
- b. The ISEG Superintendent shall_have at least six years of full-time commercial nuclear experience.
- c. Each of the members shall have at least two years of full-time commercial nuclear experience,
- d. Not more than one of the members shall have less than three years of full-time commercial nuclear experience.
- e. Excluding the er. ice of the Superintendent, the members collectively sb ve at least 16 years of full-time commercial nuclear experie f.- The ISEG (Superinu . dent included) collectively shall have the broad range of knowledge and experience necessary to perform the functions and responsibilities specified in 6.2.3.1 and 6.2.3.3.
Responsibilities 6.2.3.3 The ISEG 2 hall be responsible for maintaining surveillance of unit activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
Authority -
6.2.3.4 The ISEG reports to the General Manager, Nuclear Quality Assurance. If.any significant nuclear quality concern identified by the ISEG is not adequately resolved, the General Manager, Nuclear Quality Assurance shall notify the Nuclear Review Board, the Executive Vice President-Nuclear or the Nuclear Committee of the Board. If the ISEG is not satisfied with the resolution of any significant nuclear quality concern by the General Manager, Nuclear Quality Assurance, the ISEG shall notify the Nuclear Review Board of that concern.
Records 6.2.3.5 Records of activities performed by the ISEG shall be prepared, maintained, and forwarded each calendar month to the General Manager, Nuclear Quality Assurance.
- Not responsible for sign-off function l l
-245b-
. . . . . . . . . . . . . _ . . . . . -~
-' 1 F:Vrq. C 7 Unit 3 PBAPS' -
1 6.5.2 Nuclear Review Board Function
)
6.5.2.1 The Nuclear Review Board (NRB) shall function to provide independent review and audit of designated activities in the area of:
- a. nuclear power plant operations
- b. nuclear engineering i
- c. chemistry and radiochemistry
- d. metallurgy 3
- e. instrumentation and control
- f. radiological safety
- g. mechanical and electrical engineering
- h. quality assurance practices The members of the NRB will be competent in the area of quality assurance-practice and cognizant '
of the Quality Assurance requirements of 10 CFR 50, Appendix B.- Additionally, they will be cognizant of the corporate Quality Assurance ..
Program and will have the corporate Quality Assurance organization available to them.
Organization 6.5.2.2 The Chairman, members and alternate members of the NRB shall be appointed in wr1*ing by the Executive Vice President - Nuclear, and snall have an academic degree in an engineering or physical science field and in addition, shall have a minimum of five years technical experience, of which a minimum of three years shall be in one or more areas given in 6.5.2.1.
The NRB shall be composed of at least five members who are Philadelphia Electric Company (PECo) employees and at least two outside members who are not PECo i employees.
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pee?ne - .> 3 , - i
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Unit 3 PBAPS f
s L
Alternates 6.5.2.3 A current list of alternates shall be maintained in i NRB records. Each alternate member will serve on a os continuing basis. Alternates shall vote only in the absence.of that member for whom they are the designated alternate, c;
.. Consultants 6.5.2.4 Consultants shall be utilized as determined by the NRB
' Chairman to provide expert advice to the NRB.
Meeting Frequency 6.5.2.5 The NRB shall meet at least once per: calendar quarter. [
L Ouorum 6.5.2.6' A quorum of the NRB shall consist of the Chairman or I-
'Vice Chairman or their designated. alternates and'four members or their alternates. No more than a minority.
of the quorum.shall have line responsibility for
_ operation of the facility.
Review P
6.5.2.7 The NRB shall review:
- a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did 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.
-250-