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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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) 6.5.1.6 Continued
- 1. Review of the Plant Security Plan, and shall submit recommended changes to the Plan to the Plant Manager and the !nsclea? Review
- Board.---
-j. Review of_the Emergency Plan, and shall submit recosamended changes to the Plan to the Plant Manager and the Nuclear Review '
Board.
- k. Review of every unplanned release reportable under 10CfR 50.72 and 50.73 of radioactive material to the environs; evaluate the event; specify remedial action to prevent recurrence; and document the event description, evaluation, and corrective
' action and the disposition of the corrective action in the
' plant records.
Authority 6.5.1.7 The Plant Operations Review Committee shall:
- a. Recommend in writing, to the Plant Manager, for his approval or disapproval of items considered under 6.5.1.6(a) through (d) above.
- b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(b)-through (e) above l constitutes.an unreviewed' safety question, as defined in 10 CFR 50.59.
- c. Provide tussediate written notification to the Vice President.
Peach Bottom' Atomic Power Station, or in his absence, the Senior Vice President - Nuclear and the Nuclear Review Board of l disagreement _between the PORC and the Plant Manager; however, the Plant Manager shall_have. responsibility for resolution of such disagreements pursuant to 6.1.1 above.
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Unit 2.
PBAPS
- c. At[dit r.eports encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Vice President-Nuclear, and to the management positions responsible for the (
areas audited within 30 days after completion of the audit.
6.5.3 Procedure Review e g Approval 6.5.3.1 Each new procedure and procedure change shall be reviewed by a Station
_ Qualified Reviewer (SQR) and then by a Superintendent designated as responsible for the procedure. Administrative procedures (and changes thereto) shall be reviewed by PORC prior to approval by the Plant Manager or his designated alternate in accordance with Specification 6.1.1 The SQR shall not be the. individual who prepared the new procedure or procedure change, he may however be from the same organization as the preparer, in addition to performing procedure reviews, the responsible Superintendents shall ensure that a sufficient complement of SQR's for their functional area is maintained. PORC shall have the option to review new procedures or procedure changes without the prior review and approval of the SQR and responsible Superintendent. Procedures reviewed in this manner will be approved by the Plant Manager.
6.5.3.2 Unless preempted by PORC as described in 6.5.3.1, the SQR shall review each new procedure or procedure change. The SQR shall render a determination in writing of whether or not a cross-disciplinary review of the new procedure or procedure change-is necessary. If such a review is determined to be necessary, it shall be performed by the appropriate personnel. Upon completio' of the SQR review, each new procedure or procedure change shall be reviewed by the Superintendent designated by Administrative procedures as the responsible Superintendent for that procedure. The Superintendent shall, as part of his review, decide whether or not a 10 CFR 50.59 Safety Evaluation is required. If a Safety Evaluation is not required, the new procedure or procedure change t .1 be approved by the responsible Superintendent or the Plant Manager prior to implementation.
6.5.3.3 If the responsible Superintendent determines that a new procedure or procedure change requires a 10 CFR 50.59 Safety Evaluation, the responsible Superintendent shall render a determination in writing of whether or not the new procedure or procedure change involves an Unreviewed Safety Question (USQ). The responsible Superintendent shall then forward the new procedure or procedure change with the associated Safety Evaluation to PORC for review.
If an USQ is involved, prior NRC approval is required per 10 CFR 50.59 before implementation of the new procedure or procedure change.
- 6. 5. 3. 4 - Personnel recommended-to perform the function of SQR shall be approved and designated as such by the PORC Chairman. The SQR shall be an individual from the responsible organization and knowledgeable in the functional area affected. The individual shall meet the qualifications of ANSI /ANS-3.1-1981, Selection, Qualification and Training of Personnel for Nuclear Power Plants, Section 4, excluding subsection 4.5. Individuals who do not possess the formal educational requirements specified shall not be automatically l eliminated where other factors provide sufficient demonstration of their l abilities. These factors, as listed in subsection 4.1 of ANSI /ANS-3.1,_shall be evaluated on a case-by-case basis and approved and documented by the PORC Chairman.
6.5.3.5 Temporary procedure changes shall be reviewed and approved in accordance with Specification 6.8.3.
6.5.3.6 Record:, documenting the activities performed under Specification 6.5.3.1 through 6.5.3.5 shall be maintained in accordance with Specification 6.10.
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Unit 2 PtlAPS 9
6.8.2 Lach procedure and administrative policy of lechnical Specification 6.8.1 and changes thereto, and any other procedure or procedure change that the Plar,t Manager detennines to affect nuclear safety shall be reviewed and approved in accordance with lechnical Specification 6.5.3 (and 6.S.I.6.a and 6.b.l.7.a. if required) prior to implementation.
Each procedure of Technical Specification 6.8.1 shall also be reviewed periodically as set forth in Administrative procedures.
6.8.3 Temporary changes to procedures of Technical Specification 6.8.1 above l may be made, provided:
- a. the intent of the original procedure is not altered.
- b. The change is optroyed by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
- c. Within 14 days of implementation, the change is documented, reviewed by an SQR in accordance with Technical Specification 6.5.3.1, and approved by either the Plant Manager (or his designated alternate in accordance with Technical Specification 6.1.1) or the Superintendent designated by Administrative procedures as the responsible Superintendent for that procedure.
6.8.4 (Relocated into 6.8.1.c) 6.9 Reporting Requirements in addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the NRC in accordance with 10 CfR 50.4, " Written Communications",
t
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Unit 3
. PBAPS 6.5.1.6 Continued
- 1. _ Review of the Plant Security Plan, and shall submit recommended changes to the Plan to the Plant Manager and the Nuclear Review Board.
- j. Review of the Emergency Plan, and shall submit reconnended changes to the Plan to the Plant Manager and the Nuclear Review Board.
- k. Review of every unplanned release reportable under 10CfR 50.72 and 50.73,-of radioactive material to the environs; evaluate the event; specify remedial actica to prevent recurrence; and document the event description, evaluation, and corrective action ard the disposition of the corrective action in the plant records.
Authority
-6.5.1.7 The Plant Operations Review Committee shall:
-a. Recommend.in writing, to the Plant Manager, for his approval or disapproval of items. considered under 6.5.1.6(a) through (d) above,
- b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(b) through (e) above. l i
constitutes an unreviewed safety question, as defined in 10 CFR 50.59.
- c. Provide inmediate written notification to the Vice President, Peach Bottom Atomic Power Station, or in his' absence, the Senior Vice President - Nuclear and the Nuclear Review Board of disagreement between the PORC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
t
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l
Unit 3 PBAPS
- c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Vice President-Nuclear, and to the management positions responsible for the l areas audited within 30 days after completion of the audit.
6.5.3 Procedure Review and Approval 6.5.3.1 Each new procedure and procedure change shall be reviewed by a Station Qualified Reviewer (SQR) and then by a Superintendent designated as responsible for the procedure. Administrative procedures (and changes thereto) shall be reviewed.by PORC prior to approval by the Plant Manager or his-designated alternate in accordance with Specification 6.1.1 The SQR shall not be the individual who prepared the new procedure or procedure change, he may however be from the same organization as the preparer, in addition to performing procedure reviews, the responsible Superintendents shall ensure that a sufficient complement of SQR's for their functional area is maintained. PORC shall have the option to review new procedures or procedure changes without the prior review and approval of the SQR and responsible Superintendent. Procedures reviewed in this manner will be approved by the Plant Manager.
6.5.3.2 Unless preempted by PORC as described in 6.5.3.1, the SQR shall review each new procedure or procedure change. The SQR shall render a determination in writing of whether or not a cross-disciplinary review of the new procedure or procedure change is necessary, if such a review is determined to be necessary, it shall be performed by the appropriate personnel. Upon completion of the SQR review, each new procedure or procedure change shall be reviewed by_the Superintendent designated by Administrative procedures as the responsible Superintendent for that procedure. The Superintendent shall, as part of his review, decide whether or not a 10 CFR 50.59 Safety Evaluation is required. If a Safety Evaluation is not required, the new procedure or procedure change shall be approved by the responsible Superintendent or the Plant Manager prior to implementation.
6.5.3.3 If the responsible Superintendent determines that a new procedure or procedure change requires a 10 CFR 50.59 Safety Evaluation, the responsible Superintendent shall render a determination in writing of whether or not the new procedure or procedure change involves an Unreviewed Safety Question (USQ). The responsible Superintendent shall then forward the new procedure or procedure change with the associated Safety Evaluation to PORC for review.
If an USQ.is involved, prior NRC approval is required per 10 CFR 50.59 before implementation of the new procedure or procedure change.
6.5.3.4 Personnel recommended to perform the function of SQR shall be approved and designated as such by the PORC Chairman. The SQR shall be an individual from the responsible organization and knowledgeable in the functional area affected. The individual shall meet the cualifications of ANSI /ANS-3.1-1981, Selection, Qualification and Training of Personnel for Nuclear Power Plants, Section 4, excluding subsection 4.5. Individuals who do not possess the formal educational requirements specified shall not be automatically eliminated where other factors provide sufficient demonstration of their abilities. These factors, as listed in subsection 4.1 of ANSI /ANS-3.1, shall be evaluated on a case-by-case basis and apy oved and documented by the PORC Chairman.
6.5.3.5 Temporary procedure changes shall be reviewed aid upproved in accordance with Specification 6.8.3.
6.5.3.6 Records documenting the activities performed under Specification 6.5.3.1 through 6.5.3.5 shall be maintained in accordance with Specification 6.10.
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Unit 3 PBAPS 6.8.2 Each procedure and administrative policy of Technical Specification 6.8.1 and changes thereto, and any other procedure or proceduie change that_the Plant Manager determines to affect nuclear safety shall ie reviewed and approved in accordance with Technical Specification 0.5.3 (and 6.5.1.6.a and 6.5.1.7.a,_if required) prior to luplementation.
Each procedure of Technical Specification 6.8.1 shall also be reviewed periodically as set forth in Administrative procedures.
6.8.3 lemporary changes to procedures of Technical Specification 6.8.1 above l may be made, provided:
- a. -The intent of the original procedure is not altered.
- b. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
- c. Within 14 days of implementation, the change is documented, reviewed by an SQR in accordance with Technical Specification 5.5.3.1, and approved by either the Plant Manager (or his designated clternate in accordance with Technical Specification 6.1.1) or the Superintendent designated by Administrative procedures as the responsible Superintendent for that procedure.
6.8.4 (Relocated into 6.8.1.c) 6.9 Reporting Requirements Ir addition to the applicable reporting requirenents of iltle 10, Code t
l of feueral Regulations, the following identified reports shall be submitted to the NRC in accordance with 10 CfR S0.4 " Written Communications".
\.
l l
l-
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