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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20138Q3871985-12-13013 December 1985
Ack Receipt of 851115 IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. Valve Operability Program & Rept Scheduled to Be Completed Prior to OL Issuance
ML20127N3891985-01-31031 January 1985
Rev 1 to Midland Energy Ctr Project Shutdown Plan
ML20127N3941985-01-31031 January 1985
Rev 0 to Midland Energy Ctr,Surveillance & Maint Plan
ML20092C8541984-06-15015 June 1984
Midland Idcvp Auxiliary Feedwater Sys Performance Requirements
ML20093D2131984-04-30030 April 1984
Rev 18 to Procedure RS-084-01, Interface Control for Interorganizational Processes
ML20084E1701984-04-27027 April 1984
Instruction Manual for Model DSRV-12-4 Diesel Engine/ Generator,Midland Plants 1 & 2
ML20081C4031984-03-0707 March 1984
Plan to Conduct Independent Mgt Appraisal of Midland Nuclear Project
ML20081A5991983-08-26026 August 1983
Rev 1 to Procedure ATP-12-Q, Procedure for Performing Calculations & Technical Studies
ML20081A6141983-08-26026 August 1983
Rev 1 to Procedure 8301 WTP-4-Q, Procedure for Resolution of Spatial Sys Interaction Program/Seismic Postulated Interactions
ML20081A6261983-08-26026 August 1983
Rev 1 to Procedure ATP-13-Q, Procedure for Preparation of Project Technical Repts
ML20078K2841983-08-0505 August 1983
Rev 1 to third-party Const Implementation Overview Approval
ML20078K2941983-08-0505 August 1983
Rev 1 to Quality Control Instruction 15.01, Nonconformance Identification & Reporting
ML20078K3061983-08-0505 August 1983
Rev 1 for third-party Const Implementation Overview Re QA Plan
ML20078K2781983-07-21021 July 1983
Rev 0 to Verification Attribute Checklist P-2.20V, Pipe Supports
ML20024F6111983-07-15015 July 1983
Rev 4 to Project QA Plan for Midland Independent Design Const & Verification Program.
ML20076N1401983-07-15015 July 1983
Rept of Overhead Fluid Grouting Test Program
ML20024F6171983-07-15015 July 1983
Rev 3 to Engineering Program Plan Project Instruction P1-3201-009 Midland Independent Design & Const Verification Program.
ML20080A2521983-07-0505 July 1983
Rev 1 to Third-Party Const Implementation Overview Procedure
ML20077D5271983-07-0505 July 1983
Rev 1 to Third-Party Const Implementation Overview
ML20024C0941983-06-30030 June 1983
Core Damage Assessment Procedure Station 9918.1, Estimation of Extent of Core Damage.
ML20072L2411983-06-30030 June 1983
Offsite Dose Calculation Manual for Midland Plant
ML20078K2701983-06-27027 June 1983
Rev 1 to Quality Control Instruction 10.01, Const Implementation Overview Assessment
ML20024B6221983-06-27027 June 1983
Rev 1 to QC Instruction Qci 10.01, Const Implementation Overview Assessment.
ML20072J4681983-06-10010 June 1983
Rev 1 to Const Completion Program. Viewgraphs Encl
ML20072J4781983-06-10010 June 1983
Rev 2 to Quality Verification Program
ML20076G0401983-06-0606 June 1983
Rev 1 to Program Manual Spatial Sys Interaction Program/ Seismic Midland Energy Ctr
ML20072A8501983-06-0303 June 1983
Const Completion Program
ML20076G2591983-06-0101 June 1983
Rev 1 to ATP-10-Q, Procedure for Document Control
ML20076G2431983-06-0101 June 1983
Rev 2 to ATP-8-Q, Procedure for Control of Computer Programs
ML20076G2211983-06-0101 June 1983
Rev 2 to ATP-7-Q, Procedure for Training Mgjec Audit Team Members
ML20076G2671983-06-0101 June 1983
Rev 1 to ATP-11-Q, Procedure for Identification, Documentation & Corrective Action for Nonconformances
ML20076G2041983-06-0101 June 1983
Rev 2 to ATP-6-Q, Procedure for Performing Internal QA Audits
ML20076G1391983-06-0101 June 1983
Rev 3 to ATP-2-Q, Procedure for Distribution & Verifying Implementation of Quality Related Procedures
ML20076G1211983-06-0101 June 1983
Rev 2 to 8301-WTP-3-Q, Procedure for Performing Walkdowns of Ssip/S Targets
ML20076G1061983-06-0101 June 1983
Rev 2 to 8301-WTP-2-Q, Procedure for Training of Ssip/S Walkdown Team Members
ML20076G0851983-06-0101 June 1983
Rev 2 to STD-1-Q, Qualifications of QA Audit Personnel
ML20076G0671983-06-0101 June 1983
Rev 2 to 8301-PIP-1-Q, Procedure for Project Interface Control
ML20072B2521983-06-0101 June 1983
Rev 2 to Field Instruction FIC-5.100, Excavation Permit Sys
ML20076G0941983-06-0101 June 1983
Rev 2 to 8301-WTP-1-Q, Procedure for Documentation of Postulated Interactions
ML20076G1371983-05-26026 May 1983
Rev 2 to ATP-1-Q, Procedure for Control of Project Correspondence
ML20076G2521983-05-26026 May 1983
Rev 1 to ATP-9-Q, 10CFR21-Procedure for Reporting of Defects & Noncompliance
ML20023D5201983-05-18018 May 1983
Rev 2 to Engineering Program Plan Project Instruction PI-3201-009 Midland Independent Design & Const Verification Program,Project 3201.
ML20023D1331983-05-0505 May 1983
Evaluation of Pressures in Lines of Grouting Equipment - Crack Repair Borated Water Storage Tank Foundations.
ML20081J6571983-04-12012 April 1983
Test Program Status & Rev 12 - Test Schedule
ML20071D6161983-03-0909 March 1983
Reactor Protection Sys Setpoint Methodology
ML20071D6371983-03-0909 March 1983
Safety-Related Instrument Setpoint Methodology for Balance of Plant Equipment
ML20072B2031983-02-0909 February 1983
Engineering Program Plan,Project Instruction PI-3201-009, Midland Independent Design & Const Verification Program, Project 3201. Corrected Pages Encl
ML20071D9361983-02-0202 February 1983
Rev 1 to Hydraulic Snubbers
ML20071D9271983-02-0202 February 1983
Rev 1 to Reactor Bldg Spray Sys Hydrazine Addition Positive Displacement Pump
ML20071D9031983-02-0202 February 1983
Rev 1 to Reactor Bldg Spray Sys Centrifugal Pump
1985-12-13
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20138Q3871985-12-13013 December 1985
Ack Receipt of 851115 IE Bulletin 85-003, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings. Valve Operability Program & Rept Scheduled to Be Completed Prior to OL Issuance
ML20127N3891985-01-31031 January 1985
Rev 1 to Midland Energy Ctr Project Shutdown Plan
ML20127N3941985-01-31031 January 1985
Rev 0 to Midland Energy Ctr,Surveillance & Maint Plan
ML20092C8541984-06-15015 June 1984
Midland Idcvp Auxiliary Feedwater Sys Performance Requirements
ML20093D2131984-04-30030 April 1984
Rev 18 to Procedure RS-084-01, Interface Control for Interorganizational Processes
ML20084E1701984-04-27027 April 1984
Instruction Manual for Model DSRV-12-4 Diesel Engine/ Generator,Midland Plants 1 & 2
ML20081C4031984-03-0707 March 1984
Plan to Conduct Independent Mgt Appraisal of Midland Nuclear Project
ML20081A5991983-08-26026 August 1983
Rev 1 to Procedure ATP-12-Q, Procedure for Performing Calculations & Technical Studies
ML20081A6141983-08-26026 August 1983
Rev 1 to Procedure 8301 WTP-4-Q, Procedure for Resolution of Spatial Sys Interaction Program/Seismic Postulated Interactions
ML20081A6261983-08-26026 August 1983
Rev 1 to Procedure ATP-13-Q, Procedure for Preparation of Project Technical Repts
ML20078K2841983-08-0505 August 1983
Rev 1 to third-party Const Implementation Overview Approval
ML20078K2941983-08-0505 August 1983
Rev 1 to Quality Control Instruction 15.01, Nonconformance Identification & Reporting
ML20078K3061983-08-0505 August 1983
Rev 1 for third-party Const Implementation Overview Re QA Plan
ML20078K2781983-07-21021 July 1983
Rev 0 to Verification Attribute Checklist P-2.20V, Pipe Supports
ML20024F6111983-07-15015 July 1983
Rev 4 to Project QA Plan for Midland Independent Design Const & Verification Program.
ML20024F6171983-07-15015 July 1983
Rev 3 to Engineering Program Plan Project Instruction P1-3201-009 Midland Independent Design & Const Verification Program.
ML20077D5271983-07-0505 July 1983
Rev 1 to Third-Party Const Implementation Overview
ML20080A2521983-07-0505 July 1983
Rev 1 to Third-Party Const Implementation Overview Procedure
ML20072L2411983-06-30030 June 1983
Offsite Dose Calculation Manual for Midland Plant
ML20024C0941983-06-30030 June 1983
Core Damage Assessment Procedure Station 9918.1, Estimation of Extent of Core Damage.
ML20024B6221983-06-27027 June 1983
Rev 1 to QC Instruction Qci 10.01, Const Implementation Overview Assessment.
ML20078K2701983-06-27027 June 1983
Rev 1 to Quality Control Instruction 10.01, Const Implementation Overview Assessment
ML20072J4681983-06-10010 June 1983
Rev 1 to Const Completion Program. Viewgraphs Encl
ML20072J4781983-06-10010 June 1983
Rev 2 to Quality Verification Program
ML20076G0401983-06-0606 June 1983
Rev 1 to Program Manual Spatial Sys Interaction Program/ Seismic Midland Energy Ctr
ML20072A8501983-06-0303 June 1983
Const Completion Program
ML20076G0851983-06-0101 June 1983
Rev 2 to STD-1-Q, Qualifications of QA Audit Personnel
ML20076G0941983-06-0101 June 1983
Rev 2 to 8301-WTP-1-Q, Procedure for Documentation of Postulated Interactions
ML20076G1061983-06-0101 June 1983
Rev 2 to 8301-WTP-2-Q, Procedure for Training of Ssip/S Walkdown Team Members
ML20076G1211983-06-0101 June 1983
Rev 2 to 8301-WTP-3-Q, Procedure for Performing Walkdowns of Ssip/S Targets
ML20076G1391983-06-0101 June 1983
Rev 3 to ATP-2-Q, Procedure for Distribution & Verifying Implementation of Quality Related Procedures
ML20076G0671983-06-0101 June 1983
Rev 2 to 8301-PIP-1-Q, Procedure for Project Interface Control
ML20076G2041983-06-0101 June 1983
Rev 2 to ATP-6-Q, Procedure for Performing Internal QA Audits
ML20076G2211983-06-0101 June 1983
Rev 2 to ATP-7-Q, Procedure for Training Mgjec Audit Team Members
ML20076G2431983-06-0101 June 1983
Rev 2 to ATP-8-Q, Procedure for Control of Computer Programs
ML20076G2591983-06-0101 June 1983
Rev 1 to ATP-10-Q, Procedure for Document Control
ML20076G2671983-06-0101 June 1983
Rev 1 to ATP-11-Q, Procedure for Identification, Documentation & Corrective Action for Nonconformances
ML20072B2521983-06-0101 June 1983
Rev 2 to Field Instruction FIC-5.100, Excavation Permit Sys
ML20076G2521983-05-26026 May 1983
Rev 1 to ATP-9-Q, 10CFR21-Procedure for Reporting of Defects & Noncompliance
ML20076G1371983-05-26026 May 1983
Rev 2 to ATP-1-Q, Procedure for Control of Project Correspondence
ML20023D5201983-05-18018 May 1983
Rev 2 to Engineering Program Plan Project Instruction PI-3201-009 Midland Independent Design & Const Verification Program,Project 3201.
ML20071D6161983-03-0909 March 1983
Reactor Protection Sys Setpoint Methodology
ML20071D6371983-03-0909 March 1983
Safety-Related Instrument Setpoint Methodology for Balance of Plant Equipment
ML20072B2031983-02-0909 February 1983
Engineering Program Plan,Project Instruction PI-3201-009, Midland Independent Design & Const Verification Program, Project 3201. Corrected Pages Encl
ML20071D9361983-02-0202 February 1983
Rev 1 to Hydraulic Snubbers
ML20071D9271983-02-0202 February 1983
Rev 1 to Reactor Bldg Spray Sys Hydrazine Addition Positive Displacement Pump
ML20071D9031983-02-0202 February 1983
Rev 1 to Reactor Bldg Spray Sys Centrifugal Pump
ML20076G1841983-01-28028 January 1983
Rev 1 to ATP-5-Q, Procedure for Providing Project Orientation
ML20076G1651983-01-28028 January 1983
Rev 1 to ATP-4-Q, Procedure for Providing Mgjec QA Program
ML20069Q4131982-10-25025 October 1982
to QA Dept Procedure B-3M-1, Qualification & Certification of Insp & Test Personnel
1985-12-13
[Table view] |
Text
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ATTACIIMENT A
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i PREL]M8 MARY HYDRAZINE SPRAY SYSThi REQUIRDIENTS l
CONSUMERS POWER COMPANY MIDLAND PLANT UNITS 1 AND 2 1
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PR10MDERY TABLE OF CONTENTS / EFFECTIVE PAGE LIST _
SECTION TITLE PAGE 1.0 SYSTDI CRITERIA 1 2.0 1 REQUIRD!ENTS FOR TIIE REACTOR BUILDING l SPRAY SYSTDi 3.0 APPLICABLE NRC REGULATORY GUIDES 3 1
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50 330 REC: BOYD R S ORG: HOWELL S H DOCDATE: 02/16/78 NRC CONSUMERS PWR DATE RCVD: 02/17/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 ADVISING THAT APPLICANT IS CONSIDERING A DESIGN CHANGE IN THE IODINE REDUCTION PORTIONS IN THE REACTOR BUILDING SPRAY SYSTEM.
PLANT NAME: MIDLAND - UNIT 1 REVIEWER INITIAL: XRL MIDLAND - UNIT 2 DISTRIBUTER INITIAL:
o*oo************* DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
PSAR/FSAR AMDT9 AND RELATED CORESPONDENCE (DISTRIBUTION CODE BOO 1)
FOR ACTION: ASST DIR VASSALLO**LTR ONLY BRANCH CHIEF VAROA**LTR ONLY PROJ MGR HOOD **W/ ENCL LIC ASST SERVICE **LTR ONLY INTERNAL: ( hEG LE* W NRC PDR**W/ ENCL i _ W W M ENCL OELD**LTR ONLY.
P. COLLINS **W/ ENCL HOUSTON **W/ ENCL HELTEMES**W/ ENCL CASE **LTR ONLY MIPC**LTR ONLY KNIGHT **LTR ONLY BOSNAK**W/ ENCL SIHWEIL**W/ ENCL PAWLICKI**W/2 ENCL ROSS*r TR ONLY NOVAK**W/ ENCL ROSZTOCZY**W/ ENCL CHECK **W/ ENCL TEDESCO**LTR ONLY BENAROYA**W/ ENCL LAINAS**W/ ENCL IPPOLITO**W/ ENCL F. ROSA **W/ ENCL GAMMILL**W/2 ENCL VOLLMER**LTR ONLY DUNCH**W/ ENCL J. COLLINS **W/ ENCL KREGER**W/ ENCL KIRKWOOD**W/ ENCL EXTERNAL: LPDR'S MIDLAND, MI**W/ ENCL TIC **W/ ENCL NSIC**W/ ENCL ACRS CAT A**W/16 ENCL DISTRIBUTION: LTR 54 ENCL 44 CONTROL NBR: -7999 BON 5 SIZE: 1P+7P #A o**o******************************* THE END ******************************s **$
el D 1.0 SYSTEM CRITERIA Section 6.2.2.1 of the FSAR defines the design criteria for the reactor building spray system. The following is a summary of the requirements which result from the adaptation of a hydrazine spray aystra in place of the sodium hydroxide, sodium thiosulfate cy:Lem as described in the current revision of the FSAR.
2.0 REQUIREMENTS FOR THE REACTOR BUILDING SPRAY SYSTEM 2.1 Design Bases 2.1.1 The design bases as submitted in Subsection 6.2.2.1.1 of the FSAR apply for the proposed hydrazine spray system.
2.1.2 An additional safety design basis is required to ensure that adequate net positive suction head (npsh) exists at the suction of the positive displacement hydrazine pumps during all reactor building spray system operating modes.
2.2 Sizing Requirements 2.2.1 The reactor building spray system shall be designed under the sizing criteria set forth in FSAR Section 6.2.2.1.
2.2.2 The hydrazine addition pumps shall each be capable of supplying a useful flow of 0.3 gpm to the suction of the reactor building spray pumps which have a design flowrate of 1,300 gpm to ensure a minimum of 50 ppm hydrazine at the spray nozzles.
2.2.3 The chemical added to the containment spray for iodine removal shall be supplied from the hydrazine storage tank.
2.2.4 Disodium phosphate or trisodium phosphate shall be available in the reactor building to provide the required sump solution pH (7.0 - 7.5) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> post-accident.
2.2.5 The amount of hydrazine stored in the hydrazine storage tank shall be sufficient to provide continuous injection for at. least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
2.3 Sampling Requirements 2.3.1 A sample line shall be provided for evaluating the ccadition of the hydrazine in the hydrazine storage tank. Provisions shall be made for tank drainage and replenishment as required to maintain the correct hydrazine concentret_on in the tank.
2 I
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as 2.4 Testing Requirements 2.4.1 Testing shall be as submitted in Subsection 6.2.2.1.4 of the FSAR
. with the exception that Paragraph e will be replaced with appropriate test procedures for the hydrazine pumps.
2.5 Electrical Requirements 2.5.1 The hydrazine pumps are powered from redundant, Class lE, onsite emergency power systems.
2.5.2 All electrical equipment required for the hydrazine pumps shall be designed in accordance with the applicable IEEE standards.
2.6 Instrumentation and Control Requirements 2.6.1 The hydrazine addition pumps shall be actuated by reactor building high-high pressure (30 peig).
2.6.2 The hydrazine storage tank shall provide : remote readout in the control room for the following instrumentation:
- a. Redundant level instrumentation which includes redundant level sensors, redundant level indicators, and redundant high and low level alarms. . .
- b. Pressure instrumentation which includes pressure sensors, pressure indication, and high- and low-pressure alarms.
2.6.3 'The low level alarms shall be set so that the tank level does not fall below the minimum required to ensure that adequate hydrazine is available for injection into the system.
2.6.4 The hydrazine storage tank shall have a single pressure relief valve to prevent overpressurization and twc redundant vacuum breakers to prevent a vacuum from being induced in the tank.
2.7 Water Chemistry Requirements 2.7.1 The hydrazine shall be stored as a 35 wt% aqueous solution. The net tank inventory shall be sufficient to supply hydrazine to the suction of the reactor building spray pump for a minimum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
2.7.2 Disodium phosphate or trisodium phosphate shall be stored in the reactor building for use in neutralizing the boric acid such that the pH of the sump is greater than 7.0 but less than 7.5, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> post-accident. The chemicals shall be stored in a powdered or granular condition and provisions made for ctorage to ensure that the chemicals go into. solution.
1
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2.7.3 To determine the pH range of . the eump uolution, the recirculating inventory shall be calculated considering both minimum and eaximum boric acid concentrations and solution quantities for the rollowing:
- a. Borated water storage net inventory
- b. Reactor coolant system inventory (hot =45 lbs/ft )
- c. Core flooding system inventory
- d. Net storage inventory of chemicals in 2.7.1 and 2.7.2 above 2.7.4 The hydrazine shall be injected directly into the suction piping of the reactor building opray pump.
2.7.5 The hydrazine concentration in"the solution at the spray nozzles shall be no less than 50 ppm at all times during the hydrazine injection period.
2.7.6 The hydrazine storage tank atmosphere shall be inerted with nitrogen so that the tank contents remain at a slight positive gage pressure during normal storage to prevent air leakage from c,ontaminating or degrading the hydrazine.
2.7.7 All water used to prepare solutions for this system shall be reactor grade makeup water.
2.8' Material Requirements -
2.8.1 Stainless steel shall be the principal material of construction for the entire spray system with the hydrazine storage tank being 304L stainless steel which has been acid etched and passivated to ensure the removal of all residual free iron.
3.0 APPLICABLE NRC REGULATORY GUIDES RG 1.1 Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal System Pumps RG 1.4 Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Pressurized Water Reactors RG 1.26 Quality Group Classification and Standards 1 RG 1.29 Seismic Design Classification I
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