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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] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20206C5821999-04-20020 April 1999 Rev 4 to RW-C-100, Solid Radwaste Sys Process Control Program (Pcp) 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 ML20206C5711998-04-16016 April 1998 Rev 11 to ODCM for Pbaps,Units 1 & 2 ML20141J0311997-05-0808 May 1997 Rev 7 to Pump & Valve IST Program Third Ten Yr Interval ML20217M8301997-01-30030 January 1997 Rev 10 to ODCM, for Peach Bottom Atomic Power Station Units 1 & 2 ML20138B0081996-09-27027 September 1996 Rev 3 to Solid Radwaste Sys Process Control Program (Pcp) ML20107L9271996-01-0303 January 1996 Offsite Dose Calculation Manual,Rev 9,Peach Bottom Atomic Power Station Units 2 & 3 ML20095G0791995-09-22022 September 1995 Addendum 1 to Rev 2 to ISI Program Second Ten Yr Interval Units 2 & 3 for Peach Bottom Atomic Power Station ML20092C6141995-08-23023 August 1995 Rev 2 to Fabrication Spec 25A5601, Fabrication of Shroud Stabilizer ML20086A5531994-09-29029 September 1994 Rev 6 to GP-23, Diesel Generator Outages ML20073J7701994-09-24024 September 1994 Rev 0 to Installation Spec 25A5581, Stabilizer Installation ML20073J7311994-09-24024 September 1994 Rev 1 to Fabrication Spec 25A5601, Fabrication of Shroud Stabilizer ML20073J7251994-09-24024 September 1994 Rev 1 to Core Design Spec 25A5580, Shroud Stabilizers ML20073J7171994-09-24024 September 1994 Rev 1 to Design Spec 25A5579, Shroud Stabilizer Hardware ML20086A5211994-09-16016 September 1994 Rev 5 to Administrative Guideline Procedure AG-43, Guideline for Performance of Sys Outages ML20073F5541994-09-12012 September 1994 Shroud Stabilizers Legend or Description of Groups ML20073F5441994-09-12012 September 1994 Shroud Stabilizer Hardware Legend or Description of Groups ML20073F5671994-09-0909 September 1994 Fabrication of Shroud Stabilzer Legend or Description of Groups ML20073F5331994-08-31031 August 1994 Rev 0 to GENE-771-54-0894, Project Instruction Shroud Repair for H1 Through H7 Welds for PECO Energy Peach Bottom Atomic Power Station ML20073F6811994-08-29029 August 1994 Draft Rev 0 to Installation Spec 25A5581, Stabilizer Installation ML20056G0941993-07-0101 July 1993 Rev 5 of ODCM for Pbaps,Units 2 & 3 ML20056G0981992-12-28028 December 1992 Rev 0 to Procedure RW-C-100, Solid Radwaste Sys Pcp. Procedure Supersedes RW-800 at LGS & RW-120 & RW-121 at PBAPS ML20085E4601991-07-12012 July 1991 Rev 2 to M-710, Peach Bottom Atomic Power Station Units 2 & 3 Spec for Pump & Valve Inservice Testing Program Second 10-Yr Interval ML20082L8791991-06-0606 June 1991 Rev 4 to ODCM ML20062G4691990-07-0303 July 1990 Inservice Insp Program Second 10-Yr Interval ML20151Z3911988-08-23023 August 1988 Restart Power Testing Program (Power Ascension) ML20153G0551988-06-28028 June 1988 Rev 2 to Offsite Dose Calculation Manual ML20151D0531988-04-0808 April 1988 Rev 1 to Section I, Corporate Action, of Plan for Restart of Peach Bottom Atomic Power Station ML20151G4601988-04-0808 April 1988 Rev 1 to Section II, Peach Bottom Atomic Power Station Action, of Plan for Restart of Peach Bottom Atomic Power Station ML20196C6811988-02-12012 February 1988 Section II of Plan for Restart of Peach Bottom Atomic Power Station ML20236T0751987-11-25025 November 1987 Plan for Restart of Peach Bottom Atomic Power Station, Section I:Corporate Action ML20235Z1971987-10-0808 October 1987 Public Version of Rev 17 to EP-102, Unusual Event Response, Rev 16 to EP-103, Alert Response, Rev 17 to EP-104, Site Emergency Response, Rev 16 to EP-105, General Emergency Response & Rev 18 to App P of EP-209 ML20237L4991987-08-10010 August 1987 Public Version of Emergency Plan Implementing Procedures, Including Rev 16 to EP-102, Unusual Event Response, Rev 15 to EP-103, Alert Response & Rev 16 to EP-104, Site Emergency Response. W/870826 Release Memo ML20236L7911987-08-0707 August 1987 Commitment to Excellence Action Plan ML20237K1741987-06-17017 June 1987 Rev 4 to Solid Radwaste Sys Process Control Program ML20214V2951987-04-28028 April 1987 Description of Plans for Recirculation & RHR Sys Piping Replacement at Peach Bottom Unit 3 ML20212R1161987-03-31031 March 1987 Public Version of Revs to Emergency Plan Implementing Procedures,Including Rev 15 to EP-102, Unusual Event Response & Rev 2 to EP-205A.2, Obtaining Drywell Gas Samples from Containment Atmosphere Dilution Cabinets ML20237K1301987-03-13013 March 1987 Rev 1 to Offsite Dose Calculation Manual ML20237K1511987-03-11011 March 1987 Rev 3 to Solid Radwaste Sys Process Control Program ML20210T9101987-01-0606 January 1987 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 14 to EP-102, Unusual Event Response, Rev 14 to EP-103, Alert Response & Rev 15 to EP-104, Site Emergency Response ML20215N4241986-10-21021 October 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 4 to EP-205A.13, Sample Preparation & Handling of Highly Radioactive Liquid & Gas Samples ML20214E6191986-10-0707 October 1986 Public Version of Emergency Plan Implementing Procedures, Including Rev 16 to EP-101, Classification of Emergencies, Rev 13 to EP-102, Unusual Event Response & Rev 13 to EP-103, Alert Response. W/Dh Grimsley 861118 Release Memo ML20203G4661986-07-15015 July 1986 Public Version of Emergency Plan Implementing Procedures, Including Rev 18 to EP-209,App D-3, Fire & Damage Team & Rev 20 to EP-209,App I-2 Chemistry & Health Physics Contractor Call List. W/860728 Release Memo ML20203J7851986-06-17017 June 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 19 to EP-209,App D-2, Dose Assessment Team & Rev 22 to EP-209,App D-4, Personnel Safety Team ML20203E9111986-03-29029 March 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Index,Rev 12 to EP-209 App a, Immediate Notification Call List & Rev 19 to EP-209 App C. W/860423 Release Memo ML20141F5891986-02-0404 February 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Emergency Plan Procedures Index & Rev 15 to EP-101 Re Classification of Emergencies ML20137Z5041985-11-18018 November 1985 Public Version of Emergency Plan Implementing Procedures, Including Rev 8 to EP-201, Technical Support Ctr Activation & Rev 8 to EP-202, Operations Support Ctrs Activation ML20198B8381985-10-31031 October 1985 NRC-Observed Emergency Response Exercise Manual,Peach Bottom Power Station ML20133H2261985-09-18018 September 1985 Public Version of Revs to Emergency Plan Implementing Procedures,Including Rev 14 to EP-101 Re Classification of Emergencies,Rev 11 to EP-102 Re Unusual Event Response & Rev 13 to EP-209 App D-5 Re Security Team 1999-04-20
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T A'TACHMENT 3 GEN ER AL O iticiaic
.. .. NUCLEAR ENECOY 1 BUSINESS OPERATIONS REV
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Procedure for Evaluating & Documenting Potential ALARA Mitigating Actions ,
for '
Peach Bottom Atomic Power Station - Unit 2
_ Recirculation 8 RHR Piping Replacement Program 1.0 PURPOSE This procedure implements an ALARA program at the Peach Bottom Atomic Power Station in accordance with the Referenced Regulatory Guide for the replacement of the Recirculation and Residual Heat ,
Removal piping.
2.0 SCOPE 2.1 General Electric Company, Chicago Bridge and Iron and Philadelphia Electric Company shall utilize this procedure to evaluate and document potential mitigating actions to minimize the radiation
( exposure ( ALARA) during the piping replacement program. ALARA must be considered in the development of engineering and '
construction for:
o Reactor Vessel Set-Up o Drywell Set-Up !
o Drywell work required for the piping removal and ,
replacement o Maintenance in Vessel and Drywell
3.0 REFERENCES
3.1 USNRC Regulatory Guide 8.8, Information Relevant to Ensuring that O'
c cupational Radiation Exposure at Nuclear Power Station will be as low as is reasonably achievable (ALARA), Rev. 3 June 1978.
3.2 General Electric Company Specification 22A4159ZA Regulatory Guide Implementation Position- 8.8.
' 3.3 Philadelphia Electric Company, Peach Bottom Units 2 and 3, ALARA Program Administration Procedure, A-83.
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.- NUCLEAR ENERGY BUSINESS OPERATIONS GENER AL $ ELECTRIC REV 1
4.0 PROCEDURE 4.1 Responsible organization (GE or CB&I) will designate a responsible engineer to complete the ALARA checklist in Section 5.0 below.
4.2 The responsible engineer will describe the task in sufficient detail to permit evaulation of the work location, the method of operation, egress routes and the length of operation.
4.3 An estimate of existing exposure and radiation levels along with the sources must be detailed, a sketch showing work location and sources is suggested. A second estimate of the exposure reduction after implementation of the ALARA recommendation shall also be provided.
4.4 PECO planning and scheduling shall provide to the responsible engineer the estimated impact of implementing the recommended ALARA action.
4.5 The responsible engineer shall present the completed ALARA f checklist to the ALARA committee for review.
4.6 The ALARA committee (GE/CB&I/PECO) will review the ALARA guidance and advise on, consent with, or document reason for rejection of the recomendation; the responsible engineer will submit the check list to PECO for approval.
4.7 PECO concurrence with the recommendation shall be documented by signature /date on the checklist; if PECo rejects the ALARA guidance the reason for rejection shall be stated.
5 h
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NUCLEAR ENERLY BUSINESS OPERATIONS GENERALOitiernic CEV
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( !
h 5.0 ALARA CHECKLIST l
' Each ALARA Checklist documenting the mitigating measu'res shall be numerically sequenced. The Checklist (see Attachment) shall i
have the following information:
5.1 Task and
Purpose:
Describe task, purpose of the ALARA guidance, expected impact, alternatives considered, guidance provided at ;
other sites, advantages / disadvantages.
5.2 Exposure Estimate: Identify radiation levels, background and hot spot sources, date of radiation survey, radiation level reductions due to ALARA or other considerations, expected exposure hours, estimated exposure with and without ALARA guidance.
5.3 Schedule Impact: Estimated duration to implement ALARA guidance, estimate critical path impact, describe potential schedule improvement achievable using ALARA guidance.
5.4 Cost: Estimated cost to implement ALARA guidance, describe potential cost saving achievable using ALARA guidance.
5.5 Project Concurrence: Sign off by PECO coordinator, Planning &
Scheduling, Construction.
5.6 Reasons for Rejection: ALARA connittee or PECO Project state reason that ALARA guidance is not accepted.
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NUCLEAR ENER2Y SUSINESS OPERATIONS GENERALOitiernic REV t
ALARA CHECKLIST Mitigating Measure: [
l i
Task and
Purpose:
i
+
i Exposure Estimate. i l
Schedule Impact:
t Cost:
1 I
ALARA Comittee ,
Chairman /Date ALARA Coordinator /Date Planning & Scheduling /Date Construction /Date Reason for Rejection:
?
i I.
No 807 (mtv to/st) i 1
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