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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20077L3581994-10-25025 October 1994 Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny ML20071Q2491994-07-31031 July 1994 Rev 3 to Shoreham Decommissioning Project Termination Survey Plan ML20063D0261993-12-31031 December 1993 Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan ML20059K1061993-08-25025 August 1993 Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny ML20073E9171993-07-0707 July 1993 Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa ML20063D0121993-04-30030 April 1993 Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan ML20128P6781993-02-17017 February 1993 Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation ML20128P6981993-02-0909 February 1993 Rev 1 to 67X001.10, Termination Survey Design ML20128P6571993-02-0202 February 1993 Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure ML20128P6661993-01-29029 January 1993 Rev 0 to 67X001.03, Termination Survey Quality Control ML20128P7011993-01-19019 January 1993 Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations ML20128P6941993-01-0808 January 1993 Rev 1 to 67X001.09, Termination Survey Background Assessment ML20128P6831993-01-0808 January 1993 Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt ML20128P6751993-01-0707 January 1993 Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt ML20128P6701993-01-0606 January 1993 Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure ML20127B8101993-01-0505 January 1993 Plan for Phased Decommissioning of Liquid Radwaste Sys ML20125D5071992-12-14014 December 1992 Proposed Tech Specs Re Deletion of AC Sources & Onsite Power Distribution Sys Requirements & Changing Frequency of Radiological Effluent Release Reporting Requirements ML20128P6881992-12-10010 December 1992 Rev 0 to 67X001.08, Survey Unit Classification Description ML20128P7211992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20128P7151992-10-22022 October 1992 Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description ML20128P6471992-10-0101 October 1992 Rev 0 to 67X001.01, Termination Survey History File Content & Preparation ML20094M7681992-03-27027 March 1992 Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992 ML20086K0981991-12-0505 December 1991 Proposed Tech Spec Section 6.5.1 Re Site Review Committee & 6.5.2 Re Independent Review Panel ML20079N0681991-11-11011 November 1991 Excerpts from Shoreham Solid Waste Process Control Program ML20079P3981991-10-31031 October 1991 Proposed Tech Specs 6.5.1 & 6.5.2 Re Site Review Committee & Independent Review Panel,Respectively ML20090A8321991-08-0707 August 1991 Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm ML20082K9491991-05-31031 May 1991 Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual ML20070H6191991-03-11011 March 1991 Proposed Tech Specs Removing License Condition 14 from License NPF-82 ML20070D4921991-02-26026 February 1991 Proposed Tech Specs Re Seismic Monitoring Instrumentation Surveillance Requirements,Radiation Monitoring Instrumentation & Administrative Controls ML20058E3051990-10-30030 October 1990 Proposed Tech Specs Replacing Pages 3/4 4-1 & 3/4 4-3 of Defueled Tech Specs ML20059G3701990-08-30030 August 1990 Revised Tech Specs Re Limiting Conditions for Fuel Handling Operation ML20056B5081990-08-21021 August 1990 Proposed Tech Specs,Deleting Section 6.2.3, Independent Safety Engineering Group (Iseg) & Associated Administrative Controls ML20058N5431990-08-10010 August 1990 Proposed Tech Specs Re Defueled SAR ML20044A8011990-06-28028 June 1990 Proposed Tech Specs Designating Long Island Power Authority as Plant Licensee Upon or After NRC Amends License to Nonoperating Status ML20006F4711990-02-20020 February 1990 Proposed Tech Specs Conforming to Guidance of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent Tech Specs in Administrative Controls Section of Tech Specs & Relocation of Procedural.... ML20006F4881990-02-20020 February 1990 Draft Odcm. ML20064A3381990-01-31031 January 1990 Rev 15 to 4170002, Odcm ML20005F2481990-01-0505 January 1990 Proposed Tech Specs Re Defueled Facility OL SNRC-1620, Suppl 15 to Startup Rept for Period 890501-08011989-08-15015 August 1989 Suppl 15 to Startup Rept for Period 890501-0801 ML20246N9731989-07-13013 July 1989 Proposed Tech Specs Removing Inconsistency in Plant Procedural Change Approval Process SNRC-1597, Suppl 14 to Startup Rept for Period 890201-05011989-05-0101 May 1989 Suppl 14 to Startup Rept for Period 890201-0501 ML20246E5891989-04-30030 April 1989 Technical Specifications for Shoreham Nuclear Power Station, Unit 1.Docket No. 50-322.(Long Island Lighting Company) ML20246N4871989-01-31031 January 1989 Rev 14 to Offsite Dose Calculation Manual SNRC-1513, Suppl 12 to Startup Rept for Period Aug-Nov 19881988-11-0909 November 1988 Suppl 12 to Startup Rept for Period Aug-Nov 1988 SNRC-1509, Proposed Tech Spec Table 1.2, Operational Conditions1988-10-19019 October 1988 Proposed Tech Spec Table 1.2, Operational Conditions ML20235U9341988-09-13013 September 1988 Rev 5 to Solid Waste Process Control Program SNRC-1484, Suppl 11 to Startup Rept for May-Aug 19881988-08-0303 August 1988 Suppl 11 to Startup Rept for May-Aug 1988 ML20151D7141988-07-15015 July 1988 Proposed Tech Specs Re Test Frequency of Emergency Diesel Generators ML20151D6081988-07-13013 July 1988 Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures ML20151D4191988-07-13013 July 1988 Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution 1994-07-31
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20077L3581994-10-25025 October 1994 Proposed Confirmatory Survey Plan for Reactor Bldg,Shoreham Nuclear Power Station,Brookhaven,Ny ML20071Q2491994-07-31031 July 1994 Rev 3 to Shoreham Decommissioning Project Termination Survey Plan ML20063D0261993-12-31031 December 1993 Revised Rev 2 to Shoreham Decommissioning Project Termination Survey Plan ML20059K1061993-08-25025 August 1993 Proposed Confirmatory Survey Plan for Shoreham Nuclear Power Station Brookhaven,Ny ML20073E9171993-07-0707 July 1993 Rev 0 to Operations Plan for Marine Transportation of Fuel Shipment from Shoreham,Ny to Eddystone,Pa ML20063D0121993-04-30030 April 1993 Revised Rev 1 of Shoreham Decommissioning Project Termination Survey Plan ML20128P6781993-02-17017 February 1993 Rev 1 to 67X001.06, Termination Survey Release Record Content & Preparation ML20128P6981993-02-0909 February 1993 Rev 1 to 67X001.10, Termination Survey Design ML20128P6571993-02-0202 February 1993 Rev 0 to 67X001.02, Shoreham Decommissioning Project Termination Survey Procedure ML20128P6661993-01-29029 January 1993 Rev 0 to 67X001.03, Termination Survey Quality Control ML20128P7011993-01-19019 January 1993 Rev 0 to 67X001.12, Termination Survey Section Conduct of Operations ML20128P6941993-01-0808 January 1993 Rev 1 to 67X001.09, Termination Survey Background Assessment ML20128P6831993-01-0808 January 1993 Rev 0 to 67X001.07, Termination Survey Document Control & File Mgt ML20128P6751993-01-0707 January 1993 Rev 1 to 67X001.05, Termination Survey Data Receipt & Mgt ML20128P6701993-01-0606 January 1993 Rev 0 to 67X001.04, Termination Survey Unit Turnover & Control Procedure ML20127B8101993-01-0505 January 1993 Plan for Phased Decommissioning of Liquid Radwaste Sys ML20128P6881992-12-10010 December 1992 Rev 0 to 67X001.08, Survey Unit Classification Description ML20128P7211992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20128P7151992-10-22022 October 1992 Rev 1 to PDXOM-01, Nuclear Organization Mgt Control Program for Decommissioning Termination Survey Program Description ML20128P6471992-10-0101 October 1992 Rev 0 to 67X001.01, Termination Survey History File Content & Preparation ML20094M7681992-03-27027 March 1992 Joint Contingency Plan of Long Island Lighting Company & Long Island Power Authority Required by NRC Order Approving Shoreham License Transfer-Feb 29, 1992 ML20079N0681991-11-11011 November 1991 Excerpts from Shoreham Solid Waste Process Control Program ML20090A8321991-08-0707 August 1991 Rev 18 to 4170002, Shoreham Nuclear Power Station Unit 1 Odcm ML20082K9491991-05-31031 May 1991 Shoreham Nuclear Power Station - Unit 1 Offsite Dose Calculation Manual ML20006F4881990-02-20020 February 1990 Draft Odcm. ML20064A3381990-01-31031 January 1990 Rev 15 to 4170002, Odcm ML20246N4871989-01-31031 January 1989 Rev 14 to Offsite Dose Calculation Manual ML20235U9341988-09-13013 September 1988 Rev 5 to Solid Waste Process Control Program ML20151D4191988-07-13013 July 1988 Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution ML20151D5931988-07-13013 July 1988 Rev 2 to Plant-Specific Technical Guideline 10, Level/ Power Control ML20151D6081988-07-13013 July 1988 Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures ML20151D5621988-07-13013 July 1988 Rev 2 to Plant-Specific Technical Guideline 7, Emergency Depressurization ML20151D6971988-06-20020 June 1988 Rev 9 to Procedure 29.023.01, Reactor Pressure Vessel Control Emergency Procedure. W/One Oversize Encl ML20151D6281988-06-10010 June 1988 Rev 1 to Procedure 3.04, Developing Written Tests ML20151D6481988-06-10010 June 1988 Rev 1 to Procedure 5.01, Counseling Trainees & Providing Remedial Training Plan ML20151D6791988-06-10010 June 1988 Rev 2 to Procedure 8.01, Simulator Exam Evaluation ML20151D6581988-06-10010 June 1988 Rev 0 to Procedure 5.02, Formulating Tests from Question & Answer Banks & Administering Tests ML20151D5821988-05-11011 May 1988 Rev 1 to Plant-Specific Technical Guideline 9, Reactor Pressure Vessel Flooding ML20151D4981988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 5, Radioactive Release Control ML20151D5691988-05-11011 May 1988 Rev 0 to Plant-Specific Technical Guideline 8, Steam Cooling ML20151D6041988-05-11011 May 1988 Rev 0 to Plant-Specific Technical Guideline 12, Figure ML20151D5481988-05-11011 May 1988 Rev 1 to Plant-Specific Technical Guideline 6, Alternate Level Control ML20151D4471988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 3, Primary Containment Control ML20151D4251988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 2, Reactor Pressure Vessel Control ML20151D5971988-05-11011 May 1988 Rev 1 to Plant Specific Technical Guideline 11, Primary Containment Flooding ML20151D4901988-05-11011 May 1988 Rev 0 to Plant Specific Technical Guideline 4, Secondary Containment Control ML20196A9081988-01-25025 January 1988 Rev 3 to 80A8614, Inservice Insp Program Plan,Core Spray Sys,Shoreham Nuclear Power Plant Unit 1. W/One Oversize Drawing ML20196A9601988-01-25025 January 1988 Rev 2 to 80A8619, Inservice Insp Program Plan,Crd Sys, Shoreham Nuclear Power Plant Unit 1 ML20196A9911988-01-25025 January 1988 Rev 3 to 80A8621, Inservice Insp Program Plan,Containment Penetration Flued Heads,Shoreham Nuclear Power Plant Unit 1 ML20196A9471988-01-25025 January 1988 Rev 2 to 80A8618, Inservice Insp Program Plan,Rwcu Sys, Shoreham Nuclear Power Plant Unit 1 1994-07-31
[Table view] |
Text
^ 1 mr DOCUMENT NO. REV, 5 NUCt. EAR ENERGY SERVICES, INC. PAGE nF 9
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INSERVICE INSPECTIOf 8 PROGRAM PLAN QUALITY GROUP C SYSTEMS SHOREHAM NUCLEAR POWER PLANT l UNIT 1 I
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l SOA8620 1 DOCUMENT NO.
i PAGE OF NUCLEAR ENERGY SERVICES, INC.
l l
TABLE OF CONTENTS PAGE
- 1. INTRODUCTION 4
- 2. CLASSIFICATION 4 1
- 3. EXENtPTIONS 4
- 4. EXCEPTIONS 5
- 5. CALIBRATION STANDARDS 5
- 6. PROGRAhi PLAN AND SCHEDULE 5
- 7. PRESSURE TESTS 5
- 8. ISOAiETRIC FIGURES AND SKETCHES 5
- 9. AUGNiENTED REQUIREMENTS 5 l I Tables 3-1 6-1 ExemptionsSection XI Examination Schedule 6[
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FORM : NES 205 2/80
"""'" "^"2 ggg REVISION l.00 NUCLEAR ENERGY SERVICES, INC. PAGE OF DATE DESCRIPTION APPROVAL 1 7/10/84 -
See CRA 4455 Revision includes g/)
editorial changes and the addition ,
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80A8620 DOCUMENT NO.
PAGE OF NUCLEAR ENERGY SERVICES, INC. -
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- 1. INTRODUCTION This document presents the Inservice Inspection Requiremeats for Quality Group C Components of the Shoreham Nuclear Power Plant as required by subsection IWD of Section XI.
The General Text, NES Document Number SOAS60S presents the bases for the Inservice Inspection Program and a more detailed description of the Inservice 1 Inspection Prograni Plan ths.n is contained in this document.
- 2. CLASSIFICATION Table 3-1 lists the systems that have been reviewed for Quality Group C piping, as defined in Regulatory Guide 1.26 Rev. 3.
l } 3. EXEMPTIONS The Quality Group C portions of the systems listed in Table 3-1 were reviewed and found to be exempt from the visual examination VT-3 requicements of Table IWD-2590-1 in Section XI.
l TABLE 3-1 b EXEMPTIONS Basis for System P&lD Exemption Fuel Pool Cooling and Cleanup System FM-19A&B IWD-1220.2 Condensate Transfer System FM-42A IWD-1220.2 Fuel Oil System FM-44 A IWD-1220.2 Diesel Generator Air System FM-44B IWD-1220.1 0
FORM 8 NES 205 2/80
30AS620 DOCUMENT NO, 11 W NUCLEAR ENERGY SERVICES, INC. OF
- 4. EXCEPTIONS There are no exceptions for Quality Group C components.
- 5. CALIBRATION STANDARDS No calibration standards are required for Quality Group C components.
- 6. PROGRAM PLAN AND SCHEDULE The specific Quality Group C ISI examination requirements are defined in Table 6-1.
As allowed by the Code, where multiple loops exist only those intergrally welded '
attachments on one loop are included. All the welded attachments listed in Table 6-1 are required to be examined in the first 10 year interval following the schedule presented in Table 2-2 of the General Text (Document #80AS608). i l l l
- 7. PRESSURE TESTS l In accordance with Section XI all Class 3 pressure retaining components require a leakage test every period, and a hydrostatic test once during the interval (10 year).
The leakage test is to be done in accordance with IWD-3221, and the hyerostatic test in accordance with IWD-3223. For additional information, refer to the Pressure Test Program.
- 8. ISOMETRIC FIGURES AND SKETCHES l
There are no isometric figures or sketches for the Quality Group C piping.
- 9. AUGMENTED REQUIREMENTS There are no augmented requirements that apply to Quality Group C.
O FORM
, DOCUMENT NO.
NUCLEAR ENERGY SERVICES, INC.
Table 6-1 b Section XI Examination Schedule Reactor Building Closed Loop Cooling Water System Support Number Line Number Examination Method P42-PSA 0068 10"-R L C-509-3 VT-3 P42-PSA 0074 6"-R C L-506-3 V T-3 P42-PSA 0122 6"-R C L-508-3 VT-3 P42-PSA 0125 6"-R C L-503-3 VT-3 P42-PSA 0144 6"-R C L-508-3 VT-3 P42-PSA 01S3 8"-R C L- 198-3 V T-3 P42-PSR 0187 8"-RC L- 198-3 VT-3 P42-PSA 0191 8"-R C L- 198-3 VT-3 P42-PSA 0123 14"-R C L-192-3 VT-3 P42-PSA 0204 8"-RCL-004-3 VT-3 P42-PSR 0213 3"-R C L-004-3 VT-3 P42-PSA 0215 6"-R C L-032-3 VT-3 P42-PSSH 0230 6"-R C L-032-3 VT-3 P42-PSR 0240 8"-RCL-202-3 VT-3 P42-PSR 0242 3"-RCL-19S-3 VT-3 P42-PSSH 0249 6"-R C L-015-3 YT-3 P42-PSA 0264 10"-RCL-509-3 VT-3 P42-PSSH 0268 14"-RC L-511-3 VT-3 P42-PSR 0270 14"-RCL-511-3 VT-3 P42-PSSH 0271 14"-RC L-S i l-3 VT-3 P42-PSR 0272 14"-RC L-511-3 VT-3 P42-PSR 0273 14"-RCL-511-3 VT-3 P42-PSST 0275 14"-R C L-511-3 VT-3 P42-PSA 0329 14"-RCL-512-3 VT-3 P42-PSSH 0550 8"-R C L- 198-3 VT-3 O
FORY a NES 205 2iB0
DOCUMENT NO,
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PAGE OF NUCLEAR ENERGY SERVICES, INC.
Table 6-1 (Cont'd)
Section XI Examination Schedule RBSYS & CRAC Chilled Water System Support Number Line Number Examination Method M50-PSA 0010 10"-C W-007-3 VT-3 M50-PSA 0012 10"-C W-008-3 VT-3 M50-PSA 0013 8"-C W-0 09-3 VT-3 M50-PSA 0014 8-C W-009-3 V T-3 M50-PSA 0023 S"-C W-013-3 VT-3 M50-PSR 0024 8"-C W-01 S-3 VT-3 M50-PSA 0025 8"-C W-018-3 YT-3 J M50-PSA 0026 8"-C W-018-3 VT-3 M50-PSR 0057 10"-C W-008-3 VT-3 M50-PSR 0063 S"-C W-013-3 VT-3 l I M50-PSA 0064 8"-C W-013-3 VT-3 M50-PSA 0068 10"-C W-020-3 V T-3 M50-PSA 0071 3"-C W-021 3 VT-3 M50-PSA 0072 3"-C W-0 21 -3 VT-3 M50-PSA 0073 S"-C W-021 -3 VT-3 M50-PSR 0161 10"-C W-024-3 VT-3 M50-PSR 0162 10"-C W-024-3 VT-3 M50-PSA 0164 10"-C W-024-3 VT-3 M50-PSR 0168 10"-C W-007-3 VT-3 M50-PSR 0169 10"-C W-007-3 VT-3 M50-PSA 0171 10"-C W-007-3 VT-3 M50-PSA 0631 6"-C W-002-3 VT-3 M50-PSA 0632 6"-C W-099-3 VT-3 M50-PSA 0633 6"-C W- 107-3 YT-3 M50-PSA 0634 6"-C W-028-3 VT-3 M50-PSA 0643 6"-C W-001 -3 VT-3 i I FOR*,4 s NES 205 2/80
80A8620
, DOCUMENT NO.
NUCLEAR E'NERGY SERVICES, INC.
< i Table 6-1 (Cont'd)
Section XI Examination Schedule Service Water System Support Number Line Number Examination Method P41-PSR 0002 20"- WS-24 2-3 VT-3 P41-PSA 0012 20"-WS-211-3 V T-3 P41-PSSH 0029 20"-WS-24 7-3 VT-3 P41-PSR 0030 20"-WS-247-3 VT-3 P41-PSSH 0031 20"-W S-247-3 VT-3 !
P41-PSR 0034 20"-W S-247-3 VT-3 l
P41-PSR 0042 16"-WS-220-3 VT-3 P41-PSR 0044 16"-WS-214-3 VT-3 i P41-PSR 0046 20"-W S-211 -3 VT-3 P41-PSR 0056 20"-W S-211 -3 VT-3 )
P41-PSR 0057 20"-WS-211 -3 VT-3
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P41-PSR 0058 24"-W S-209-3 VT-3 i P41-PSA 0103 8"-WS-231 -3 VT-3 I i
P41-PSSH 0104 1Cd-WS-230-3 VT-3 P41-PSR 0105 10"-WS-230-3 VT-3 P41-PSR 0106 12"-WS-233-3 VT-3 P41-PSR O!!O 8"-WS-231 -3 VT-3 P41-PSR 0137 6"-WS-261 -3 VT-3 l
P41-PSR 0165 6"-WS-274-3 VT-3 P41-PSA 0173 6"-WS-2 74-3 VT-3 P41-PSR 0526 10"-WS-252-3 VT-3 P41-PSR 0627 10"-WS-252-3 VT-3 P41-PSR 0628 10"-WS-252-3 VT-3 P41-PSR 0630 10"-WS-254-3 VT-3 P41-PSR 0650 8"-WS-231 -3 VT-3 P41-PSSD 0801 20"-W S-249-3 VT-3 P41-PSSP 0802 20"-WS-249-3 VT-3
) P41-PSSP 0805 16"-WS-217-3 VT-3 P41-PSSP 0813 20"-WS-247-3 VT-3 FOAV s NES 205 2/80
i DOCUMENT NO.
m NUCLEAR ENERGY SERVICES, INC.
PAGE OF I I Table 6-1 (Cont'd)
Section XI Examination Schedule Service Water System Support Number Line Number Examination Method P41-PSSP 0814 20"-W S-24 7-3 VT-3 P41-PSSP 0315 20"-WS-24 7-3 VT-3 P41-PSSH 0372 10"-WS-450-3 VT-3 l
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FORM s NES 205 2/80
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