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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 ML20151D4191988-07-13013 July 1988 Rev 1 to Plant Specific Technical Guideline 1, Introduction & Operator Precaution ML20151D6081988-07-13013 July 1988 Rev 1 to Procedure 21.009.02, Technical Review of New or Revised Symptom Oriented Emergency Operating Procedures 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
M NUCLEAR ENERGY SERVICES DOCUMENT NO. SOA3621 REV.1 PAGE I OF 10 _
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INSERVICE INSPECTION PROGRAM PLAN CONTAINMENT PENETRATION FLUED HEADS SHOREHAM NUCLEAR POWER PLANT UNIT 1 i
Prepared For N
LONG ISLAND LIGHTING COMPANY Vr ,,, Aponcanon copy No Assigneo To !
I 5535 APPROVALS TITLE / DEPT. SIGN ATURE D ATE l insp. Prog. Project REV NO PREPARED BY Manager Manager QA Manager -.
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g gg REVISION LOG NUCLEAR ENERGY SERVICES,INC.
c="T "o-PAGE 8 ^8'2 2 OF ,
{ d' DATE f".I[ DESCRIPTION APPROVAL 1 6/28/84 See CRA 4407 Revision includes [g [. h [
editorial changes and the additier t of new information ,
2 5/8/85 5.8 See CRA 5297. [b - ,h 3 1/25/88 4,5,C See CRA 6727 [, /)
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' ' SOA8621
, DOCUMENT NO.
U O' -
NUCLEAR ENERGY SERVCES l I TABLE OF CONTENTS PAGE
- 1. INTRODUCTION 4
- 2. CLASSIFICATION 4
- 3. EXEMPTIONS 4
- 4. EXCEPTIONS 4
- 5. CALIBRATION STANDARDS '4
- 6. PROGRAM PLAN AND SCHEDULE 7 Tables 6-1 Flued Head Examination Schedule S 8621-1 Flued Head Detail 10 l I O
% 8NES 205 2/80
DOCUMENT NO. 20AS621 MGE 60F M
="
- NUCt. EAR ENERGY SERVICES l I
- 1. INTRODUCTION This document presents the Inservice inspection Requirements for the containment Penetration Flued Heads of the Shoreham Nuclear Power Plant.
The General Text, NES Document Number 80A860S presents the basis for the Inservice Inspection Program and a more detailed description of the Inservice inspection l Program than is contained in this document.
- 2. CL ASSIFICATION l
The Containment Penetration Flued Heads are either Class 1 or 2.
- 3. EXEMPTIONS There are no Exemptions. l 9 4. EXCEPTIONS l
Because of the configuration of the Containment Penetration Flued Head's (see Fig.
8621-1) the Section XI required surf ace examination cannot be done, in lieu of the required examinations a surf ace examination will be done of the outer weld and a leak test will be done of the annulus between the inner and outer weld. (See Relief g l Requests 8621-R1 and 8621-R2.) l
- 5. CALIBRATION STANDARDS There are no Calibration Standards required for the Containment Penetration Flued Heads.
u _
FORM e NES 205 2.80
30A3621 j DOCUMENT NO.
PAGE OF NUCLEAR ENERGY SERVCES ,
1 l l !
RELIEF REQUEST /3\
3621-R 1 1
i System s: Main Steam, Feedwater, Reactor Water Cleanup, Residual Heat )
Removal, High Pressure Coolant injection, Reactor Core I isolation Cooling, Core Spray, Standby Liquid Control. i Category: B-K-1 l Quality Group: A Com ponent
Description:
Containment Penetrations Flued Head integrally welded attachments at Penetrations X-1 A, B, C, D; X-2A, B; X-3; X-4, .
X-3; X-6A, B; X-12; X-16; X-20A, B; and X-36. l l
Code Requirement: Surface examination of liner sleeve to flued head and flued i head to process pipe welds.
Basis for Relief: The liner sleeve to flued head welds are located under a containment test channel which makes them inaccessible for surf ace examination. The inner flued head to process pipe 4 g welds are inaccessible for surf ace examination. The flued head to process pipe welds are unique because of an annulus between ]
the process pipe, as shown in fig. 8621-1. A leak test capability has been incorporated to monitor the condition of the flued j head welds.
Alternating Tes ting: A leakage test will be performed during the first refueling outage and then once during each period for a total of 4 tests in the first interval. The outer flued head to process pipe welds will be surf ace examined. l l
9 FORM :NES 205 2/80 l
'
me 1 w NUCLEAR ENERGY SERVCES U'
I I RELIEF REQUEST [A\
8621-R2 System s: High Pressure Coolant injection, Reactor Core Isolation Cooling, Residual Heat Removal.
Category: C-C Quality Group: B Component
Description:
Containment Penetrations Flued Head integrally welded attachments at peneetrations X-13, X-17 and XS-5.
Code Requirement: Surface examination of liner sleeve to flued head and flued head to process pipe welds Basis for Relief: The liner sleeve to flued head welds are located under a containment test channel which makes them inacessible for surf ace examination. The inner flued head to process pipe g welds are inaccessible for surface examination. The flued head to process pipe welds are unique because of an annulus between the process pipe, as shown in fig. 8621-1. A leak test capability has been incorporated to rnonitor the condidtion of the flued head welds.
Alternate Testing: A leakage test will be performed during the first refueling outage and then once during each period for a total of 4 tests in the first interval. The outer flued head to process pipe welds will be surface examined.
O FOW s NES 205 2/80
DOCUMENT NO. 80A8621 m " "W NUCLEAR ENERGY SERVtCES l l
- 6. PROGRAM PLAN AND SCHEDULE The Flued Heads shown in Fig. 3621-1 exists only in Type 1, 2, 3 and 6 penetrations (see Drawing M-10172-12 (FV-lG-12), M-10173-10 (FV-lH-10) and M-10174-9 (FV 9)). Table 6.1 lists all of the Type 1,2, 3 and 6 containment Penetrations, required to be examined by Section XI, with the associated system, procedure and examination method. All Flued Heads will receive a surface exam of the outer weld and a leak test j of the annules between the inner and outer weld.
These examinations are to be done during the first refueling outage and then once during each period for a total of 4 examinations in the first interval.
TABLE 6-1 )
l l
Flued Head Examination Schedule Penetration Procedure Exam l Num ber System Number Method X-1A Main Steam SOA3132 PT Later Leak Test X-1B Main Steam 30A3132 PT l 1
Later Leak Test !
X-lC Main Steam 80A3132 PT Later Leak Test X-lO Main Steam 80A3132 PT Later Leak Test X-2A Feedwater 80A3132 PT Later Leak test FORM sNES 205 2/80
1 DOCUMENT NO, 30A8621 l m
PAGE ~lOF-- 10~
NUCLEAR ENERGY SERVICES l l TABLE 6-1 cont.
Flued Head Examination Schedule Penetration Procedure Exam Number System Number Method X-2B Feedwater 30A3132 PT Later Leak Test X-3 Main Steam 80A3132 PT Later Leak Test X-4 Reactor Water 80A3132 PT Cleanup Later Leak Test X-3 Residual Heat 80A3132 PT Removal Later Leak Test X-6 A Residual Heat 80A3132 PT Removal Later Leak Test X-6B Residual Heat SOA3132 PT Removal Later Leak Test l
X-12 High Pressure 30A3132 PT Coolant injection Later Leak Test X-13 High Pressure 80A3132 PT Coolant injection Later Leak Test l
X-16 Reactor Core Isolation 80A3132 PT l Cooling Later Leak Test FogM NES 205 2/80
DOCUMENT NO. SOAS621 l ay
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11 NUCLEAR ENERGY SERVICES PAGE 905 10 l > l TABLE 6-1 cont. l Flued Head Examination Schedule Penetration Procedure Exam Number System Number Method X-17 Reactor Core Isolation SOA3132 PT Cooling Later Leak Test 1 X-20A Core Spray SOA3132 PT Later Leak Test X-20B Core Spray SOA3132 PT Later Leak Test X-36 Standby Liquid SOA3132 PT Control Later Leak Test XS-5 Residual Heat SOA3132 PT Removal Later Leak Test l
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0 roc # s r4S 205 2/60
M DOCUMENT NO. 80A8621 i 1 NUCLEAR ENERGY SERVICES. INC.
PAGE 'n-
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Figure 8621-1 Flued Head Detail Ref. Dwgs : M-10172-12, M-10173-10, & M-10174-9 d ,
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FORM 8 NES 205 2/80
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