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FOR OCONEE 1-2-3 REACTOR COOLANT SYSTEM -~ | FOR OCONEE 1-2-3 REACTOR COOLANT SYSTEM -~ | ||
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i DUKE POWER COMPANY . | i DUKE POWER COMPANY . | ||
ENGINEERING DEPARTMENT MECHANICAL DESIGN SECTION, MECHANICAL DIVISION CHARLOTTE, NORTH CAROLINA f E b E b $..d.Y-du[ C$yT]jl {} | ENGINEERING DEPARTMENT MECHANICAL DESIGN SECTION, MECHANICAL DIVISION CHARLOTTE, NORTH CAROLINA f E b E b $..d.Y-du[ C$yT]jl {}((g FILE NO. 05-278 s 3 'y . | ||
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THERMAL MOVEMENT MONITORING PROGRAM FOR OCONEE l-2-3 REACTOR COOLANT SYSTEM DUKE POWER COMPANY DESIGN ENGINEERING DEPARTNENT MECHANICAL DESIGN SECTION, hi'HANICAL AND NUCLEAR DIVISION CHARLOTTE, NORTH CAROLINA FILE 05-278 Duke Power Conoany 0uali tv Assurance Statement: | THERMAL MOVEMENT MONITORING PROGRAM FOR OCONEE l-2-3 REACTOR COOLANT SYSTEM DUKE POWER COMPANY DESIGN ENGINEERING DEPARTNENT MECHANICAL DESIGN SECTION, hi'HANICAL AND NUCLEAR DIVISION CHARLOTTE, NORTH CAROLINA FILE 05-278 Duke Power Conoany 0uali tv Assurance Statement: | ||
This cccument includes engineering design of items related to nuclear safety, in ac:ordance with established procedures. Its quality has been assured. | This cccument includes engineering design of items related to nuclear safety, in ac:ordance with established procedures. Its quality has been assured. | ||
| Line 78: | Line 55: | ||
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TABLE OF CONTENTS S,ection Title Pajun 1 | TABLE OF CONTENTS S,ection Title Pajun 1 | ||
i INTRODUCTION AND PURPOSE lNTER-COMPANY DIVISION OF RESPONSIBILITY 2 ll Ill DETERMINATION OF MONITORING POINT LOCATIONS 3 INSTALLATION METHODS FOR MONITORING POINT 4 IV HARDWARE SYSTEM TEST SEQUENCE AND DESCRIPTION 5 V | i INTRODUCTION AND PURPOSE lNTER-COMPANY DIVISION OF RESPONSIBILITY 2 ll Ill DETERMINATION OF MONITORING POINT LOCATIONS 3 INSTALLATION METHODS FOR MONITORING POINT 4 IV HARDWARE SYSTEM TEST SEQUENCE AND DESCRIPTION 5 V | ||
6 VI ENGINEERING LIMITATIONS AND PRECAUTIONS Vil DATA RECORDED 7 Vill COMPARISON OF ANALYTICAL AND TEST RESULTS 8 IX CONCLUSIONS 9 X APPLICABILITY OF TEST TO UNITS 2 & 3 11 APPENDIX - | 6 VI ENGINEERING LIMITATIONS AND PRECAUTIONS Vil DATA RECORDED 7 Vill COMPARISON OF ANALYTICAL AND TEST RESULTS 8 IX CONCLUSIONS 9 X APPLICABILITY OF TEST TO UNITS 2 & 3 11 APPENDIX - | ||
4 m e-- = , e - -- -+ | 4 m e-- = , e - -- -+ | ||
: l. INTRODUCTION AND PURPOSE As the result of discussions in the 124TH Duke-ACRS Meeting held on August 13, 1970, Duke Power Company agreed to monitor the thermal expansion movement of the Unit 1 Reactor Coolant System #50. The purpose of the monitoring program is two-fold: | : l. INTRODUCTION AND PURPOSE As the result of discussions in the 124TH Duke-ACRS Meeting held on August 13, 1970, Duke Power Company agreed to monitor the thermal expansion movement of the Unit 1 Reactor Coolant System #50. The purpose of the monitoring program is two-fold: | ||
: 1) To determine the movement of the system piping during the hot functional test period as described in Section V of this report. | : 1) To determine the movement of the system piping during the hot functional test period as described in Section V of this report. | ||
: 2) To review recorded data to assure that. thermal stresses and movements within the system are compatible with analytical predictions. | : 2) To review recorded data to assure that. thermal stresses and movements within the system are compatible with analytical predictions. | ||
e t | e t | ||
l II. INTER-COMPANY DIVISION OF RESPONSIBILITY , | l II. INTER-COMPANY DIVISION OF RESPONSIBILITY , | ||
Responsibility for the implementation of the monitoring program is shared by the Duke Power Company Design Engineering, Constructime and Steam Pro-duction Departments as outilned below. | Responsibility for the implementation of the monitoring program is shared by the Duke Power Company Design Engineering, Constructime and Steam Pro-duction Departments as outilned below. | ||
: 1) Design Engineering Department | : 1) Design Engineering Department | ||
: a. Establish need for program as described in 1. of this report end Appendix A | : a. Establish need for program as described in 1. of this report end Appendix A | ||
: b. Citablish monitoring point locations based on analytical results ; | : b. Citablish monitoring point locations based on analytical results ; | ||
and as described in Section lli of this report | and as described in Section lli of this report I | ||
I | |||
: c. Establish installation methods of monitoring devices as described in Section IV of this report | : c. Establish installation methods of monitoring devices as described in Section IV of this report | ||
: d. Establish Engineering limitations and precautions as described in Section VI of this report l | : d. Establish Engineering limitations and precautions as described in Section VI of this report l | ||
: e. Establish data to be recorded during test as described in Sec-tion VII of this report | : e. Establish data to be recorded during test as described in Sec-tion VII of this report | ||
: f. Make engineering comparison and evaluation of analytical versus actual test data as described in Section Vill of this report | : f. Make engineering comparison and evaluation of analytical versus actual test data as described in Section Vill of this report | ||
| Line 120: | Line 83: | ||
: a. Installation of monitoring point hardware at locations described in Section ill and in accordance with methods described in Sec-tion IV of this report | : a. Installation of monitoring point hardware at locations described in Section ill and in accordance with methods described in Sec-tion IV of this report | ||
: b. Assist Steam Production Department in the surveillance and record-Ing of data as requested | : b. Assist Steam Production Department in the surveillance and record-Ing of data as requested | ||
: 3) Steam Production Department | : 3) Steam Production Department Develop a procedure for monitoring the thermal expansion of the Reactor Coolant System as required by Design Engineering , Appendix A | ||
Develop a procedure for monitoring the thermal expansion of the Reactor Coolant System as required by Design Engineering , Appendix A | |||
: b. Coordinate and schedule with the Construction Department as necessary for the installation of monitoring hardware and data-recording | : b. Coordinate and schedule with the Construction Department as necessary for the installation of monitoring hardware and data-recording | ||
: c. Documentation of monitoring program results in accordance with Oconee Nuclear Station Test Procedure TP i A 60014 5 (See Appendix A) | : c. Documentation of monitoring program results in accordance with Oconee Nuclear Station Test Procedure TP i A 60014 5 (See Appendix A) | ||
: d. Transmittal of monitoring data to the Engineering Department for i cvicw anil approval and subsequent preparation of Thermal Monitoring R e p. . t | : d. Transmittal of monitoring data to the Engineering Department for i cvicw anil approval and subsequent preparation of Thermal Monitoring R e p. . t | ||
Ill. DETERMINATION OF MONITORING POINT LOCATIONS Monitoring points in general are located at positions undergoing measurable expansion movements shown on Figure 1 and 2 in accordance with B & W analy-tical predictions. Specifically, monitoring point locations are defined on Drawing PO-187 (Figure 3) and as listed herein. 1 1 | |||
Ill. DETERMINATION OF MONITORING POINT LOCATIONS | |||
Monitoring points in general are located at positions undergoing measurable expansion movements shown on Figure 1 and 2 in accordance with B & W analy-tical predictions. Specifically, monitoring point locations are defined on Drawing PO-187 (Figure 3) and as listed herein. 1 1 | |||
Monitoring Point Data Required Attachment Location & Quantity b | Monitoring Point Data Required Attachment Location & Quantity b | ||
i Movement of RC pumps in On support lug located 180* | i Movement of RC pumps in On support lug located 180* | ||
| Line 139: | Line 95: | ||
(one required) 19 Pressurizer surge line On bottom, top, west and east nozzle Y & Z movement centerlines of butt weld to at RC System hot leg con- nozzle. (Four required x's nection on pipe assembly I nozzle.) | (one required) 19 Pressurizer surge line On bottom, top, west and east nozzle Y & Z movement centerlines of butt weld to at RC System hot leg con- nozzle. (Four required x's nection on pipe assembly I nozzle.) | ||
A-33 20 X, Y & Z RC System hot On north, south, east and west leg movement at top of centerlines of tangent point straight run - 180' Ell weld. (Four required x's one tangent point weld) 21 X Y & Z RC System cold On reessure tap connection leg movement. (Long and of ti.s 1A1 and 1A2 RC pump short RC pump discharge discharge line. (One required line) x's 2 lines) 4 | A-33 20 X, Y & Z RC System hot On north, south, east and west leg movement at top of centerlines of tangent point straight run - 180' Ell weld. (Four required x's one tangent point weld) 21 X Y & Z RC System cold On reessure tap connection leg movement. (Long and of ti.s 1A1 and 1A2 RC pump short RC pump discharge discharge line. (One required line) x's 2 lines) 4 | ||
a , | a , | ||
l IV. INSTALLATION METHODS FOR MONITORING PolNT HARDWARE A description of the hardware and method of attachment of monitoring points hardware is shown on Drawing PO-187 (Figure 3) except for location number 1 which does not require attachments to the piping or vessels. At monitoring location 1, a 1/2" hex nut was welded to a 1/4" plate and bolted to the sup-port lug on the pump casing. All other monitoring locations as' described in 111 above require attachments to the piping or vessels. | l IV. INSTALLATION METHODS FOR MONITORING PolNT HARDWARE A description of the hardware and method of attachment of monitoring points hardware is shown on Drawing PO-187 (Figure 3) except for location number 1 which does not require attachments to the piping or vessels. At monitoring location 1, a 1/2" hex nut was welded to a 1/4" plate and bolted to the sup-port lug on the pump casing. All other monitoring locations as' described in 111 above require attachments to the piping or vessels. | ||
The welding of attachments directly to piping or vessels was not permissible. | The welding of attachments directly to piping or vessels was not permissible. | ||
| Line 149: | Line 102: | ||
Target studs were removed af ter the monitoring program and properly stored. | Target studs were removed af ter the monitoring program and properly stored. | ||
\ _ | \ _ | ||
-4 | -4 | ||
V. SYSTEM TEST SEQUENCE AND DESCRIPTION in an effort to meet the Duke Design Engineering Department quality Assur-ance Inspection for harigers, restraints and suppressors as described in FSAR IC.3.7 and obtain data suitable for the preparation of this report, the Oconee Nuclear Station Steam Production Department prepared and executed ' | V. SYSTEM TEST SEQUENCE AND DESCRIPTION in an effort to meet the Duke Design Engineering Department quality Assur-ance Inspection for harigers, restraints and suppressors as described in FSAR IC.3.7 and obtain data suitable for the preparation of this report, the Oconee Nuclear Station Steam Production Department prepared and executed ' | ||
test procedure TP 1 A 600 14 5, " Pipe and Component Hanger Hot Deflection | test procedure TP 1 A 600 14 5, " Pipe and Component Hanger Hot Deflection | ||
| Line 160: | Line 109: | ||
Duke's Design Engineering Department reviewed and accepted the test proce-dure prior to its initial use. | Duke's Design Engineering Department reviewed and accepted the test proce-dure prior to its initial use. | ||
i 1 | i 1 | ||
I l | I l | ||
) | ) | ||
l | l l | ||
l | |||
VI. ENGINEERING LIMITATIONS AND PRECAUTIONS Any restrictions or deflection limits imposed on the Reactor Coolant System or its hangers, restraints and supports are included in test procedure TP 1 A 600 14 5 and were established in accordance with manu-facturer and Duke Design Engineering Department requirements. | VI. ENGINEERING LIMITATIONS AND PRECAUTIONS Any restrictions or deflection limits imposed on the Reactor Coolant System or its hangers, restraints and supports are included in test procedure TP 1 A 600 14 5 and were established in accordance with manu-facturer and Duke Design Engineering Department requirements. | ||
Approximate predicted movements for the Reactor Coolant System as listed on Drawing PO-187 (Figure 3) were established as limiting criteria for system movements. Steam Production Department personnel were to check and obtain Design Engineering approval if any of the predicted movements were exceeded during the system heat-up prior to escalating system temperature. | Approximate predicted movements for the Reactor Coolant System as listed on Drawing PO-187 (Figure 3) were established as limiting criteria for system movements. Steam Production Department personnel were to check and obtain Design Engineering approval if any of the predicted movements were exceeded during the system heat-up prior to escalating system temperature. | ||
1 | 1 | ||
. , - +-n , m m | . , - +-n , m m | ||
, , ) | , , ) | ||
Vil. DATA RECORDED l | Vil. DATA RECORDED l | ||
| Line 187: | Line 124: | ||
Data recorded either meets or exceeds the information required for this report and Ic in accordance with manufacturer and/or Duke Design Engi-neering Department requirements. | Data recorded either meets or exceeds the information required for this report and Ic in accordance with manufacturer and/or Duke Design Engi-neering Department requirements. | ||
In an effort to make this report more meaningful and brief, only the information required to confirm and satisfy the purpose of the report is tabulated in Appendix C along with the predicted analytical Infor-mition for comparative purposes. | In an effort to make this report more meaningful and brief, only the information required to confirm and satisfy the purpose of the report is tabulated in Appendix C along with the predicted analytical Infor-mition for comparative purposes. | ||
7 | 7 | ||
Vill. CDMPARISON OF ANALYTICAL VERSUS TEST RESULTS A comparison of analytical uavements versus the actual measured movements is made for each point of Interest in Appendix C. The comparison is pre-sented in the form of Percentage Difference such that the overall accuracy of readings versus analytical predictions can be reviewed and determined. | Vill. CDMPARISON OF ANALYTICAL VERSUS TEST RESULTS A comparison of analytical uavements versus the actual measured movements is made for each point of Interest in Appendix C. The comparison is pre-sented in the form of Percentage Difference such that the overall accuracy of readings versus analytical predictions can be reviewed and determined. | ||
Review of the data in Appendix C Indicates that the horizontal movement of Reactor Coolant Pump 1A2 exceeded the approximate limiting criteria established on Drawing P0-187 (Figure 3) in one direction. Steam Produc-tion Department contacted the Design Engineering Department once the i | Review of the data in Appendix C Indicates that the horizontal movement of Reactor Coolant Pump 1A2 exceeded the approximate limiting criteria established on Drawing P0-187 (Figure 3) in one direction. Steam Produc-tion Department contacted the Design Engineering Department once the i | ||
| Line 198: | Line 131: | ||
; could continue to be heated up as long as the maximum limiting criteria were not violated. | ; could continue to be heated up as long as the maximum limiting criteria were not violated. | ||
A review of the variation at monitoring point I has been conducted with results as described in MDS-JR-52 (Appendix D). | A review of the variation at monitoring point I has been conducted with results as described in MDS-JR-52 (Appendix D). | ||
i l | |||
i | l l | ||
l | |||
IX. CONCLUSIONS l Based on the information presented in Appendix C and as summarlzed in Section Vill of this report, thermal expansion movements of the Reactor Coolant System exhibitled average % Differences to predicted movements as follows: | |||
IX. CONCLUSIONS l | |||
Based on the information presented in Appendix C and as summarlzed in Section Vill of this report, thermal expansion movements of the Reactor Coolant System exhibitled average % Differences to predicted movements as follows: | |||
% Difference % Difference % Difference X(North-South Direction) Y(Vertical Direction) Z(East-West Direction) 31.57% 6.02% 15 98% | % Difference % Difference % Difference X(North-South Direction) Y(Vertical Direction) Z(East-West Direction) 31.57% 6.02% 15 98% | ||
for an overall average % Difference of 17.86%. These % Differences would be even smaller if the dimensions being examined were of greater magnitude; l however, % Differences experienced are acceptable based on the small dimensions being evaluated. | for an overall average % Difference of 17.86%. These % Differences would be even smaller if the dimensions being examined were of greater magnitude; l however, % Differences experienced are acceptable based on the small dimensions being evaluated. | ||
| Line 222: | Line 145: | ||
restraint was examined by Design Engineering and determined to be free of any restrictions to the proper movement. | restraint was examined by Design Engineering and determined to be free of any restrictions to the proper movement. | ||
9 | 9 | ||
6 s IX. CONCLUSIONS | 6 s IX. CONCLUSIONS | ||
: 5) The variation in the movement of Reactor Coolant Pump IA2 is totally acceptable as described in HDS-JR-52 (Appendix D) and any stiffness in the seismic restraint will improve with cycling of the system. | : 5) The variation in the movement of Reactor Coolant Pump IA2 is totally acceptable as described in HDS-JR-52 (Appendix D) and any stiffness in the seismic restraint will improve with cycling of the system. | ||
The pump returned back to the original cold position with a good degree of accuracy confirming these conclusions. | The pump returned back to the original cold position with a good degree of accuracy confirming these conclusions. | ||
O e | O e | ||
X. APPLICABILITY OF TEST TO UNITS 2 & 3 The Reactor Coolant Systems for all three Oconee units are identical in arrangement, in design conditions and in all physical parameters such as piping wall thickness, materials of construction, support and restraint location, etc., that would have a bearing on the thermal stress analysis. | X. APPLICABILITY OF TEST TO UNITS 2 & 3 The Reactor Coolant Systems for all three Oconee units are identical in arrangement, in design conditions and in all physical parameters such as piping wall thickness, materials of construction, support and restraint location, etc., that would have a bearing on the thermal stress analysis. | ||
Thus, the results of the thermal expansion monitoring test on Unit I are totally acceptable and indicative of results that would be expected from monitoring Units 2 and 3 Since the purpose of this monitoring program was academic in nature, only the Unit i Reactor Coolant System will be monitored. | Thus, the results of the thermal expansion monitoring test on Unit I are totally acceptable and indicative of results that would be expected from monitoring Units 2 and 3 Since the purpose of this monitoring program was academic in nature, only the Unit i Reactor Coolant System will be monitored. | ||
9 i | |||
9 | |||
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O O APPENDIX A OCONEE NUCLEAR STATION TEST PROCEDURE TP 1 A 600 14 5 | O O APPENDIX A OCONEE NUCLEAR STATION TEST PROCEDURE TP 1 A 600 14 5 | ||
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li PIPE & COMPONENT IWiGER HOT DE??ECTION & INSPECTION TEST 9 | li PIPE & COMPONENT IWiGER HOT DE??ECTION & INSPECTION TEST 9 | ||
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OC0hTE. NUCLEAR STATION . 1 | OC0hTE. NUCLEAR STATION . 1 TP 1 A 600 14 5 PIPE AND COMPONENT HANGER HOT DEFLECTION AND INSPECTIO!I* TEST - | ||
TP 1 A 600 14 5 | |||
l 1.0 Purpose , | l 1.0 Purpose , | ||
To verify the predicted load and. travel indications on the following hangers and adjust those not within the required margins: | To verify the predicted load and. travel indications on the following hangers and adjust those not within the required margins: | ||
Reactor Coolant pump constant' load supports (two per pump). OTSC Auxi- | Reactor Coolant pump constant' load supports (two per pump). OTSC Auxi- | ||
., liary Feedwater header hangers (three per header). Pressurizer spray , | ., liary Feedwater header hangers (three per header). Pressurizer spray , | ||
-< s line (two hangers). Points listed on P.O. Dwg. 187 (1) (2) 1-21, RC | -< s line (two hangers). Points listed on P.O. Dwg. 187 (1) (2) 1-21, RC | ||
( , | ( , | ||
pumps LOCA restraints, piping supports, and OTSG supports. *- | pumps LOCA restraints, piping supports, and OTSG supports. *- | ||
i | i 2.0 References 2.1 Drawing No. 1016470, (B&W) Typical Pump and Motor Support Criteria. | ||
2.2 Dra wing No. 129303E, (OTSG No.1) Drawing No. 146403E (OTSG No. 2) 9l Cross sections through Steam Generator (B&W). ,, | |||
2.0 References 2.1 Drawing No. 1016470, (B&W) Typical Pump and Motor Support Criteria. | 2.3 Grinnell Co. Instruction Manuals #52, Model R, Fig. 80V-Type E. | ||
2.2 Dra wing No. 129303E, (OTSG No.1) Drawing No. 146403E (OTSG No. 2) 9l | |||
Cross sections through Steam Generator (B&W). ,, | |||
Constant Support (RC Pumps) Figure 98 No. 6 and Pig. 98 No. 8 Support Hangers (OTSG Aux. FW Headers). , | Constant Support (RC Pumps) Figure 98 No. 6 and Pig. 98 No. 8 Support Hangers (OTSG Aux. FW Headers). , | ||
2.4 B&W TS/1/A/600/4. | 2.4 B&W TS/1/A/600/4. | ||
2.5 B&W Drawing #163356, Reactor Coolant Piping Arrangement Plan. | 2.5 B&W Drawing #163356, Reactor Coolant Piping Arrangement Plan. | ||
2.6 Dwg. No. P.O. 187 (1) -(2) . | 2.6 Dwg. No. P.O. 187 (1) -(2) . | ||
3 2.7 Eng. Letter - File OS-18, OS-27, - Dated 11-1-71. | 3 2.7 Eng. Letter - File OS-18, OS-27, - Dated 11-1-71. | ||
3.0 Time Required Portion of a shift prior to Hot Functional Test, during Hot Functional 3 | 3.0 Time Required Portion of a shift prior to Hot Functional Test, during Hot Functional 3 | ||
Test and following cooldown from Hot Functional Test. | Test and following cooldown from Hot Functional Test. | ||
4.0 Prcrcquisite Tests 9 | 4.0 Prcrcquisite Tests 9 | ||
None | None j | ||
j | |||
~ i l | ~ i l | ||
l l 600/14 Rev. 5 January 26, 1972 , | |||
1 | 1 | ||
. cGotD.-5 t | . cGotD.-5 t | ||
' t; ; 1-26-72 . | ' t; ; 1-26-72 . | ||
* | * | ||
* 4' - | * 4' - | ||
5.0 Test. Equipment * | 5.0 Test. Equipment * | ||
. l 5" outside precision calipers. | . l 5" outside precision calipers. | ||
6" Scale '. . | 6" Scale '. . | ||
Inside Micrometer 3" - 4" range. | Inside Micrometer 3" - 4" range. | ||
Outside knerometer 3" - 4"* range. , | Outside knerometer 3" - 4"* range. , | ||
Hydraulic Jack with 3" - 4" total length, including travel. ;- | Hydraulic Jack with 3" - 4" total length, including travel. ;- | ||
6.0 Limitations and Precautions 6.1 No adjustments to be made to the load supports except as authorized _ | 6.0 Limitations and Precautions 6.1 No adjustments to be made to the load supports except as authorized _ | ||
by the Station Superintendent. , | by the Station Superintendent. , | ||
6.2' 1101/01 - Plant Operating Limits and Precautions. : | 6.2' 1101/01 - Plant Operating Limits and Precautions. : | ||
6.3 Stop RCS heatup if the hanger deflection indicating pin is approaching | 6.3 Stop RCS heatup if the hanger deflection indicating pin is approaching or has contacted its travel hard stop. | ||
or has contacted its travel hard stop. | |||
~ | ~ | ||
6.4 Stop RCS heatup if piping or components come in contact with seismic | 6.4 Stop RCS heatup if piping or components come in contact with seismic restraints, beams, etc. ' ' | ||
restraints, beams, etc. ' ' | |||
7.0 Required Plant Status | 7.0 Required Plant Status | ||
'' g | '' g 7.1 RCS in cold condition. : | ||
7.1 RCS in cold condition. : | |||
8.0 Prerequisite System Conditions , , | 8.0 Prerequisite System Conditions , , | ||
8.1 Alltravelstopsonhangersmu'stberemoved-friortosystemsheat-up. | 8.1 Alltravelstopsonhangersmu'stberemoved-friortosystemsheat-up. | ||
9.0 Test Method ' | 9.0 Test Method ' | ||
9.1 Cold and hot pipe hanger position buttons will t:. observed before - - . . . . _. | 9.1 Cold and hot pipe hanger position buttons will t:. observed before - - . . . . _. | ||
The WHITE button is Cold ~ position, and the and during system heatup. | |||
RED button is hot position. Position indication readings will be taken at 50*F increments during heatup and cooldown. Pipe and e component deflections will be read and recorded at 50*F increments during heatup and cooldown. Seismic restraints will be checked at 200*F, 350*F and 500*F during heatup and cooldown to insure piping. | |||
The WHITE button is Cold ~ position, and the | |||
and during system heatup. | |||
RED button is hot position. Position indication readings will be | |||
taken at 50*F increments during heatup and cooldown. Pipe and e component deflections will be read and recorded at 50*F increments during heatup and cooldown. Seismic restraints will be checked at | |||
200*F, 350*F and 500*F during heatup and cooldown to insure piping. | |||
and compor.ents do not come hard against a restraint. | and compor.ents do not come hard against a restraint. | ||
1 10.0 Data Required | 1 10.0 Data Required | ||
! 10.1 Initial Cold Positions Vs. RCS Temperature. | ! 10.1 Initial Cold Positions Vs. RCS Temperature. | ||
i * * ~- "** *~~savnenre. | i * * ~- "** *~~savnenre. | ||
600/14-5 | 600/14-5 | ||
: e. *. 1-26-72 10.3 Ad[ustments, if any. , | : e. *. 1-26-72 10.3 Ad[ustments, if any. , | ||
10.4 Final Cold Positions Vs. RCS Temperature following Hot Functional Test. . | |||
10.4 Final Cold Positions Vs. RCS Temperature following Hot Functional | |||
Test. . | |||
11.0 Acceptance Criteria .- | 11.0 Acceptance Criteria .- | ||
Position indication readings during and after test stay within the travel range and do not contact the hanger stops. Piping and components do not come in contact with seismic restraints. Piping and component deflections | Position indication readings during and after test stay within the travel range and do not contact the hanger stops. Piping and components do not come in contact with seismic restraints. Piping and component deflections are within design values. | ||
are within design values. | |||
' 12.0 Procedure 12.1 Record all hanger positions on enclosed data sheets prior to Hot Functional Test. | ' 12.0 Procedure 12.1 Record all hanger positions on enclosed data sheets prior to Hot Functional Test. | ||
+12.2 Record all hanger positions,every,50* change of RC temperature | +12.2 Record all hanger positions,every,50* change of RC temperature during heatup for Hot Functional Test. | ||
during heatup for Hot Functional Test. | |||
12.3 Item #6 on PO Dwg.187 (1) (2) to be taken as following: | 12.3 Item #6 on PO Dwg.187 (1) (2) to be taken as following: | ||
1.a. Cold Position o | 1.a. Cold Position o | ||
: b. 200*F , | : b. 200*F , | ||
: c. 350*F l | |||
: c. 350*F | |||
l | |||
: d. 500*F 1 | : d. 500*F 1 | ||
: 2. The reading A, B, & C to be taken with a 6" scale at the - l designated point, with the block away from the OTSC & firm against .e support plate. | : 2. The reading A, B, & C to be taken with a 6" scale at the - l designated point, with the block away from the OTSC & firm against .e support plate. | ||
: 3. The "D" reading to be taken at 500*F with the inside Micrometer | : 3. The "D" reading to be taken at 500*F with the inside Micrometer at the designated' points marked on the blocks, then by the use of the jack the block is firmly pressed against the stationary block on the OTSC. '' | ||
at the designated' points marked on the blocks, then by the use of the jack the block is firmly pressed against the stationary block on the OTSC. '' | |||
12.4 The RCP LOCA restraints, piping supports & OTSG supports to be checked as following: | 12.4 The RCP LOCA restraints, piping supports & OTSG supports to be checked as following: | ||
: a. Cold Position | : a. Cold Position | ||
: b. 200*F l | : b. 200*F l | ||
l | l | ||
600/14-5 | 600/14-5 | ||
, l'26-72 | , l'26-72 | ||
.,c. 350*F - | .,c. 350*F - | ||
: d. 500*F | : d. 500*F | ||
' The data sheets to be checked off as 0.K. or against HARD STOP. - | ' The data sheets to be checked off as 0.K. or against HARD STOP. - | ||
NOTE - If against HARD STOP, notify Shif t Supervisor to stop RC heatup and notify Test Coordinator. | NOTE - If against HARD STOP, notify Shif t Supervisor to stop RC heatup and notify Test Coordinator. | ||
12.5 Upon attaining 532*F adjust load adjustment bolt if hanger is not at hot position until indication is on hot position button. | 12.5 Upon attaining 532*F adjust load adjustment bolt if hanger is not at hot position until indication is on hot position button. | ||
12.6 Record all hanger positions every 50*F change"of RC temperature | 12.6 Record all hanger positions every 50*F change"of RC temperature during cooldown after Hot Functional Test. . | ||
during cooldown after Hot Functional Test. . | |||
f-13.0 Enclosures 13.1 5 ketch of Grinnell Constant Support, Figure 80V-Size 52. | f-13.0 Enclosures 13.1 5 ketch of Grinnell Constant Support, Figure 80V-Size 52. | ||
13.2 Data Sheet - RC Piping , | 13.2 Data Sheet - RC Piping , | ||
13.3 Support Schematics. | 13.3 Support Schematics. | ||
13.4 Data Sheet .- Pump & Miitor Supports | 13.4 Data Sheet .- Pump & Miitor Supports 1325 Data Sheet - RC Piping Restraints , | ||
13.6 Data Sheet - OTSG Lateral Supports 13.7 Data Sheet - Hangers S | |||
1325 Data Sheet - RC Piping Restraints , | 9 l | ||
13.6 Data Sheet - OTSG Lateral Supports 13.7 Data Sheet - Hangers | |||
l | |||
) | ) | ||
l S | |||
e e t + | |||
l | l | ||
. m mo _ _ .m g y .m e , , , _ . . , | . m mo _ _ .m g y .m e , , , _ . . , | ||
.. rro.. so v sizes a to s'' | .. rro.. so v sizes a to s'' | ||
DRARING NUMBE.R y | DRARING NUMBE.R y | ||
. rrez e go.0003- | . rrez e go.0003- | ||
.~ ' | .~ ' | ||
42-99-001-00.- | 42-99-001-00.- | ||
= = | = = | ||
u | u | ||
. y . . | . y . . | ||
u ,. _ _ . | u ,. _ _ . | ||
g - | g - | ||
D . . | |||
D ,. . , . . | D ,. . , . . | ||
.- . ..s, | .- . ..s, | ||
.- [-t- --. . . | .- [-t- --. . . | ||
. A F* -- | . A F* -- | ||
l F-M:, .--. l | l F-M:, .--. l | ||
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T. . | T. . | ||
l.- . | l.- . | ||
,,q ., | ,,q ., | ||
.1 ,l ,* , | .1 ,l ,* , | ||
lli-c . . . /, | lli-c . . . /, | ||
| Line 702: | Line 335: | ||
~P* T. | ~P* T. | ||
g | g | ||
'-N. l J | |||
'-N. l | |||
J | |||
),,. .".n9',' ,. 4 h,' | ),,. .".n9',' ,. 4 h,' | ||
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1-!- r . | 1-!- r . | ||
+T, . - p - | +T, . - p - | ||
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, '.s. . | , '.s. . | ||
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13 .. r . | 13 .. r . | ||
r. | r. | ||
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- :l..i :: 8 | - :l..i :: 8 | ||
~ | ~ | ||
I / ./ + '^I l ' - < | I / ./ + '^I l ' - < | ||
}w.hl .'T. | }w.hl .'T. | ||
. !:? . | . !:? . | ||
I'^/ ,/ } mi!'1 ' A. 4'm | I'^/ ,/ } mi!'1 ' A. 4'm | ||
\ gh /: | \ gh /: | ||
j.j;-Q' ;'5 b : | |||
.1Mt(y *. 8 v ' ": w C | .1Mt(y *. 8 v ' ": w C | ||
: ' ::. : :/b.3 E.J . | : ' ::. : :/b.3 E.J . | ||
,. k .'sJ( | ,. k .'sJ( | ||
FO'#R "0LES '.8 ' ' Ii | |||
:m.-- | :m.-- | ||
1.:..L.. . , ! :j | 1.:..L.. . , ! :j roVR HCLESg Foa ooLTs 2;j s. | ||
roVR HCLESg Foa ooLTs 2;j s. | |||
g " 1 I-';-M - = = '-:-l - | g " 1 I-';-M - = = '-:-l - | ||
l N- 4 \- | l N- 4 \- | ||
Fon 00 CTS T - - | Fon 00 CTS T - - | ||
.'Z | .'Z 5.tp [. 'l- ,.C | ||
:i l jg LI c--p- ;lg. - | |||
:i l jg LI | |||
c--p- ;lg. - | |||
4 3I . . ,l | 4 3I . . ,l | ||
. h' 'O j''*l) .i ~*g Q . | . h' 'O j''*l) .i ~*g Q . | ||
;--c -- :: * | ;--c -- :: * | ||
:- in-'jg r--!N . * ,- C~1 | :- in-'jg r--!N . * ,- C~1 | ||
~' ' | ~' ' | ||
w d _bj.~y..'- | w d _bj.~y..'- | ||
' e '~ | ' e '~ | ||
X J.u ---s- ;hj jg . | X J.u ---s- ;hj jg . | ||
M y i[ . r . | |||
M | |||
i . | i . | ||
* ~ ~ ~ ~ *- | * ~ ~ ~ ~ *- | ||
' ''' ^ | ' ''' ^ | ||
L = | L = | ||
Q. | Q. | ||
TYPE E * . '.' ** TYPE E , | TYPE E * . '.' ** TYPE E , | ||
g | g | ||
==== | ==== | ||
sists at to es | sists at to es | ||
.,. e.sts as to se cg u . | |||
.,. e.sts as to se | |||
cg u | |||
... S/ze .rz . | ... S/ze .rz . | ||
1 . | 1 . | ||
,p. | ,p. | ||
- nl gummmm.nte s sec load travel table in Grinnell hanger catalog for "B" dimension and sizing of constant supports. . fia, D1rsensions (inches) M. | - nl gummmm.nte s sec load travel table in Grinnell hanger catalog for "B" dimension and sizing of constant supports. . fia, D1rsensions (inches) M. | ||
bracket | bracket | ||
. .7-rod hen'ic | . .7-rod hen'ic | ||
.. diam. | .. diam. | ||
* angle hole tor 8 "I"* | * angle hole tor 8 "I"* | ||
| Line 847: | Line 398: | ||
<2G 3 J | <2G 3 J | ||
62 3/8 35 3/4: 3/8 7 1/2 25 3/8 15 3/4 22 3/16 11 1 9/16 14 15/16 3 x35:<3/0 1 5/8 9 1/4 5 3/4 + ??ll.1./.t'il | 62 3/8 35 3/4: 3/8 7 1/2 25 3/8 15 3/4 22 3/16 11 1 9/16 14 15/16 3 x35:<3/0 1 5/8 9 1/4 5 3/4 + ??ll.1./.t'il | ||
,. .: 't i r.2 .1 /2 "a 1/4 l35 3/4 l1 1/2.... 7 1./2 25 3/4 25 5/0 27 3/16 c | |||
il ll 3/4 15 1/2 1 .v. 1x3/0 1 5/it U 7/D L 3/-t + TT[1 1/213 E :' v! t a* - ,u t. =- (0:ctor) :ninus (total t.*.we1 } | |||
,. .: 't | |||
i r.2 .1 /2 "a 1/4 l35 3/4 l1 1/2.... 7 1./2 25 3/4 25 5/0 27 3/16 | |||
E :' v! t a* - ,u t. =- (0:ctor) :ninus (total t.*.we1 } | |||
t . | t . | ||
| Line 867: | Line 407: | ||
~ e e m e | ~ e e m e | ||
~ 2 e | ~ 2 e | ||
e | e w | ||
M 4 | |||
4 | |||
6 n Y | 6 n Y | ||
* f e 8 t | * f e 8 t | ||
o I 1 d y | o I 1 d y | ||
I r . | I r . | ||
7 e . | 7 e . | ||
| Line 886: | Line 422: | ||
s e | s e | ||
T e su S e E Z T | T e su S e E Z T | ||
N ae p | |||
O e | O e I e m. | ||
I e m. | |||
T C 2 e | T C 2 e | ||
m m _ | m m _ | ||
E e P m Y . w S e N t I I _ | E e P m Y . w S e N t I I _ | ||
D N O e | |||
D | A n | ||
o N X i O t I a T t L S E T L GE r1 F :E a E Il i s | |||
et D PSI Z e l i c n !' .A uU0 T N 1 1 CA PD e R c E 1 . | |||
N O | n C o I n Y c M e O ! | ||
t I | |||
T N = | |||
et D PSI Z e l i c n !' .A uU0 T N 1 1 CA PD e R c E 1 . | |||
n C o I n Y c M e | |||
O | |||
t | |||
N = | |||
E N _ | E N _ | ||
O _ | O _ | ||
X | X | ||
=_ | =_ | ||
W O | W O | ||
C D | C D | ||
f R | f R | ||
E p P n I | E p P n I | ||
P e T | P e T | ||
C a p | C a p | ||
g R = | g R = | ||
h m | h m | ||
e | e | ||
= | = | ||
e | e m | ||
m | |||
- 5 o tl | - 5 o tl | ||
~ | ~ | ||
Unit 1 - | |||
PIPE AND COF10NENT HANGER !!OT DEFLECTION AND INSPECIIOS TEST | PIPE AND COF10NENT HANGER !!OT DEFLECTION AND INSPECIIOS TEST 22:e DATA SilEET Data'Re. | ||
22:e DATA SilEET Data'Re. | |||
Tir:e Press RC Tenp Item 5 | Tir:e Press RC Tenp Item 5 | ||
* Item 6 Item 7 X Y Z X Y - | * Item 6 Item 7 X Y Z X Y - | ||
: 7. X Y | : 7. X Y 1 | ||
I t | |||
1 | W 1 | ||
I | |||
W | |||
1 | |||
2 | 2 | ||
%:te: 'See Enclosure 13.3, 1 of 5 | %:te: 'See Enclosure 13.3, 1 of 5 | ||
*:'ote f6 to be taken in: A. col 1 Poultion B. 2000F. C. 3500F 9. 5000F - - | *:'ote f6 to be taken in: A. col 1 Poultion B. 2000F. C. 3500F 9. 5000F - - | ||
: m. o | : m. o | ||
1 5 1 t | 1 5 1 t | ||
a m Y ' , | a m Y ' , | ||
D e . | D e . | ||
t - | t - | ||
I . | I . | ||
X T - | |||
X | |||
T - | |||
S E 7 T | S E 7 T | ||
N O . | N O . | ||
I T 0 C 1 ~ | I T 0 C 1 ~ | ||
E - | |||
P m Y S e N t I | P m Y S e N t I | ||
I | I D | ||
N A . . | |||
A . . | |||
N X . . - | N X . . - | ||
O . | O . | ||
I | I T | ||
C _ | |||
E T _ | E T _ | ||
L E _ - | L E _ - | ||
1F E - | 1F E - | ||
E ! | E ! | ||
s . - | s . - | ||
tD S Z . | tD S Z . | ||
i ._ | i ._ | ||
nT A . - | nT A . - | ||
UO | UO T | ||
T | |||
I A D . | I A D . | ||
R . . | R . . | ||
E - | E - | ||
| Line 1,040: | Line 499: | ||
t . | t . | ||
T I - | T I - | ||
N E - | N E - | ||
N | N O | ||
P X M . | |||
O C | O C | ||
D _ | D _ | ||
N _ | N _ | ||
| Line 1,053: | Line 508: | ||
E P | E P | ||
p m . | p m . | ||
I e P T _. | I e P T _. | ||
C . | C . | ||
R ~ | R ~ | ||
5 - | 5 - | ||
f - | f - | ||
s o s - | s o s - | ||
e | |||
* 1 - | |||
1 - | |||
r . | r . | ||
P , | P , | ||
3 _ | 3 _ | ||
. 3 _ | . 3 _ | ||
_ 1 . _ | _ 1 . _ | ||
e r - | e r - | ||
u . | u . | ||
s . _ | s . _ | ||
o . | o . | ||
_ l . _ . | _ l . _ . | ||
_ e _ c n . | _ e _ c n . | ||
_ E 5 e e | _ E 5 e e | ||
S | S | ||
,l ! :t i. ; lI i:e !i . I !Ii ' : | ,l ! :t i. ; lI i:e !i . I !Ii ' : | ||
e :e | e :e | ||
*_ D . | *_ D . | ||
i i | i i t | ||
a 5 e 1 | |||
5 e 1 | |||
t a m Y D e t . | t a m Y D e t . | ||
I ' | I ' | ||
X | |||
, I T | , I T | ||
S E 7 T | S E 7 T | ||
N . | N . | ||
0 f | 0 f | ||
r 4 C 1 | r 4 C 1 E . | ||
E . | |||
P S m Y N e I t I | P S m Y N e I t I | ||
D . | D . | ||
N A - | N A - | ||
. N X | . N X O ' | ||
O ' | |||
I | I | ||
. T C | |||
. T | |||
C | |||
. E L | . E L | ||
T E | T E | ||
| Line 1,146: | Line 555: | ||
tD Si Z i | tD Si Z i | ||
nT A - | nT A - | ||
7 1 O T | 7 1 O T | ||
! A D | ! A D | ||
R 3 E 1 G - | R 3 E 1 G - | ||
N A m Y ' | N A m Y ' | ||
e t | e t | ||
T I . | T I . | ||
| Line 1,160: | Line 565: | ||
P I . | P I . | ||
F 0 | F 0 | ||
- C | - C D | ||
N . | |||
A E p P | A E p P | ||
I n P e T | I n P e T | ||
C - | C - | ||
R | R 5 | ||
s f s o e | |||
r . | |||
1 P , - | 1 P , - | ||
3 | 3 3 | ||
1 . | |||
. e r | . e r | ||
u s | u s | ||
l o | l o | ||
e c n n . | e c n n . | ||
| Line 1,187: | Line 584: | ||
- S | - S | ||
_ . - I . ~ti~ . i I If \.! .II | _ . - I . ~ti~ . i I If \.! .II | ||
. iIi | . iIi | ||
. e_ | . e_ | ||
t e t | t e t | ||
a t. o C N 1 , . | |||
a t. o C N | |||
1 , . | |||
l ,l l \ | l ,l l \ | ||
]\l i | ]\l i F - _ . | ||
F - _ . | |||
a 9 1 | a 9 1 | ||
t a m Y D e - | t a m Y D e - | ||
t I | t I | ||
X T | |||
S E | |||
T 7 | |||
'N O I | 'N O I | ||
T 8 - | T 8 - | ||
| Line 1,219: | Line 603: | ||
I t I | I t I | ||
D N | D N | ||
A N X | A N X O | ||
I - | |||
T C | T C | ||
E T L E 1F E E il tD S . _ | E T L E 1F E E il tD S . _ | ||
i Z - | i Z - | ||
| Line 1,231: | Line 613: | ||
R 7 . | R 7 . | ||
E 1 . | E 1 . | ||
G . | G . | ||
M m Y - | M m Y - | ||
I I | I I | ||
| Line 1,241: | Line 621: | ||
O P ' | O P ' | ||
M X O | M X O | ||
C | C D | ||
E E .. __ | |||
D | P p I r | ||
E | |||
E .. __ | |||
P p | |||
I r | |||
.P e T . | .P e T . | ||
C . | C . | ||
R ._ | R ._ | ||
5 s f s o - | |||
5 | |||
s f s o - | |||
e . | e . | ||
r - | r - | ||
1 P | 1 P | ||
* 3 3 . | * 3 3 . | ||
~ 1 _ | ~ 1 _ | ||
il e _ | il e _ | ||
r _ | r _ | ||
u . _ | u . _ | ||
- s - _ | - s - _ | ||
- o _ | - o _ | ||
l - - | l - - | ||
? c m n | ? c m n | ||
. E - | . E - | ||
- 2 | - 2 | ||
- a - | - a - | ||
. S | . S | ||
- i'_ . i.e !l . isL.I. !iI!s!. . I! | - i'_ . i.e !l . isL.I. !iI!s!. . I! | ||
_ e e | _ e e | ||
! 0 5 . | ! 0 5 . | ||
Oconce liuclear Station 1-2 Unit 1 . . | Oconce liuclear Station 1-2 Unit 1 . . | ||
. PIPE AND C0FPONENT !! ANGER }!OT DEFf.ECTION AND INSPECTION TEST | . PIPE AND C0FPONENT !! ANGER }!OT DEFf.ECTION AND INSPECTION TEST | ||
__ DATA SilEET Data Reci. | __ DATA SilEET Data Reci. | ||
j Press l RC Ter p Item 21 | j Press l RC Ter p Item 21 | ||
'j X Y Z . | 'j X Y Z . | ||
l - | l - | ||
I I | I I | ||
I i | I i | ||
1 | 1 1 . | ||
1 . | |||
l . | l . | ||
t l | |||
6 l . | |||
l | |||
6 | |||
i | i | ||
:.: I. E:. :lesure 13.3,1 of 5- . . . | :.: I. E:. :lesure 13.3,1 of 5- . . . | ||
- *~ : | - *~ : | ||
1 ci 5 600 tit.,- 5 | 1 ci 5 600 tit.,- 5 | ||
. .: ;'.c.: h;.. . . | . .: ;'.c.: h;.. . . | ||
nelosure 1.,2.3 . | nelosure 1.,2.3 . | ||
126-,2 s r .~ * | 126-,2 s r .~ * | ||
.A ~ .;; n~.,, .:r?:- . . . . | .A ~ .;; n~.,, .:r?:- . . . . | ||
.. ,(s. <, t_. --?. | .. ,(s. <, t_. --?. | ||
*** => b ... | *** => b ... | ||
i | i | ||
.... g. | .... g. | ||
: 9. . ,.. . . . . . . | : 9. . ,.. . . . . . . | ||
t * | t * | ||
. . 4 7; * | . . 4 7; * | ||
. ..._ .- t | . ..._ .- t i | ||
i | |||
~> | ~> | ||
1 .. . | 1 .. . | ||
s .' | s .' | ||
,- . . , y # | |||
,- . . , y # | * 7 .l i e y | ||
7 .l i e | |||
y | |||
: 5 | : 5 | ||
.i. | .i. | ||
3 | 3 | ||
. . . . . <. ; i, . | . . . . . <. ; i, . | ||
:. i. l 3 | :. i. l 3 | ||
,. .:.2 *....-..,_.,: - | ,. .:.2 *....-..,_.,: - | ||
,, I g. l . | ,, I g. l . | ||
s ,. | s ,. | ||
... .: ; . . ,, .. i . | ... .: ; . . ,, .. i . | ||
a.. .,. ... < /. | a.. .,. ... < /. | ||
. .-I . | . .-I . | ||
.; , . i, , | .; , . i, , | ||
. , f. . | . , f. . | ||
. . . . . . s., | . . . . . . s., | ||
...+: | ...+: | ||
. . . . e.- | . . . . e.- | ||
. . .. . 1 . ~ | . . .. . 1 . ~ | ||
. . s . | . . s . | ||
. ./. e. . | . ./. e. . | ||
: 2. - | : 2. - | ||
- 8 . | - 8 . | ||
. *> ~. | . *> ~. | ||
a.. ... - | a.. ... - | ||
.. S . . | .. S . . | ||
o :. s . . _ . . . . .. 4 I' - | o :. s . . _ . . . . .. 4 I' - | ||
: . . . .: i ' \. . , s . | : . . . .: i ' \. . , s . | ||
,..4 i ; .. | |||
,..4 | |||
i ; .. | |||
i U ** * - | i U ** * - | ||
s..e. , | s..e. , | ||
.**.*j | .**.*j | ||
/ - f . p, ,E *e._. ;, | / - f . p, ,E *e._. ;, | ||
. .'~ * . | . .'~ * . | ||
| Line 1,565: | Line 718: | ||
. .:.. .: .. o. s :. | . .:.. .: .. o. s :. | ||
g . 1 . | g . 1 . | ||
, .sI i , | , .sI i , | ||
l ": . | l ": . | ||
* n . % . V. t - | * n . % . V. t - | ||
~.:.--. '.y . | ~.:.--. '.y . | ||
.i ;.> | .i ;.> | ||
....=.:. | ....=.:. | ||
s | s | ||
. O I_e *#.s: | . O I_e *#.s: | ||
s . | s . | ||
e | e | ||
,,l | ,,l | ||
_g . | |||
3,'...,,,, , Q I. I , \ | 3,'...,,,, , Q I. I , \ | ||
I j | I j | ||
l | l | ||
.-s.s. . / | .-s.s. . / | ||
| Line 1,603: | Line 738: | ||
\. | \. | ||
= . l | = . l | ||
. e . . | . e . . | ||
O ; | |||
t | t | ||
. 4 | . 4 | ||
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. ..........-.f. | . ..........-.f. | ||
. . , - s . | . . , - s . | ||
s, . . . | s, . . . | ||
A u . | A u . | ||
i t | |||
j *.- . .. as- | |||
i | |||
.j/. ' | .j/. ' | ||
~ . | ~ . | ||
. f .' | . f .' | ||
. .) .** . | . .) .** . | ||
.t , | .t , | ||
4 's e | 4 's e | ||
n .. _ _ .- . ,~g .. . , | n .. _ _ .- . ,~g .. . , | ||
. . \ | . . \ | ||
, ..._.. g. . .. | , ..._.. g. . .. | ||
: g. .. . .... . .*-\ | : g. .. . .... . .*-\ | ||
j g | j g | ||
,O p,,,.,,. ., .r :,. | ,O p,,,.,,. ., .r :,. | ||
~.c | ~.c | ||
.* l g , | .* l g , | ||
. , j . .. .._ . gi. | . , j . .. .._ . gi. | ||
IC t .. . | IC t .. . | ||
1.. | 1.. | ||
y a ,. ,, g. | y a ,. ,, g. | ||
I | I | ||
,. , , .....f___. . . ,y . | ,. , , .....f___. . . ,y . | ||
, . ,. . s,. | , . ,. . s,. | ||
,. s ; | ,. s ; | ||
.. y nr - 1 . . . l ,' % .*.a. | .. y nr - 1 . . . l ,' % .*.a. | ||
: t. g . .3 * ~ o * | : t. g . .3 * ~ o * | ||
.a | .a | ||
,s . .~.. | ,s . .~.. | ||
*t'{. . | *t'{. . | ||
'') . ~ . . - .. -. | '') . ~ . . - .. -. | ||
. /,ps f (,g s ! .'==i .,.r- ee C. .. | |||
. /,ps f (,g | |||
s ! .'==i .,.r- ee | |||
C. . | |||
i ,,,s..-_. # ' , g | i ,,,s..-_. # ' , g | ||
, , ,[ | , , ,[ | ||
. i | . i 9 | ||
Jg | |||
._ . __ ;:., v , ,'. | ._ . __ ;:., v , ,'. | ||
u . ,, g. . , | u . ,, g. . , | ||
. {. . | . {. . | ||
/ | / | ||
j | j | ||
| Line 1,731: | Line 790: | ||
l, ,. /t* * | l, ,. /t* * | ||
. i | . i | ||
- t.,,s. . | - t.,,s. . | ||
.=. . ~. | .=. . ~. | ||
,.,/. | ,.,/. | ||
. t. ,s. . ~ . .- | . t. ,s. . ~ . .- | ||
I 1, . . . . . . . , | I 1, . . . . . . . , | ||
.s . ..* . | .s . ..* . | ||
.. { , | .. { , | ||
.s - | .s - | ||
'1 .; | '1 .; | ||
- .. .-....3 | - .. .-....3 | ||
.g J | .g J | ||
7.._. . . . | 7.._. . . . | ||
a .. | a .. | ||
o. | o. | ||
.o ** | .o ** | ||
,e s. | ,e s. | ||
s : | s : | ||
e: , ., | e: , ., | ||
u .. | u .. | ||
: g. ,,a . | : g. ,,a . | ||
. - . . . . - ..~. | . - . . . . - ..~. | ||
p . | p . | ||
y *- \ g,,,,.J | y *- \ g,,,,.J | ||
.* a | .* a | ||
* e . . - - . . . .. .. -. . . -, | * e . . - - . . . .. .. -. . . -, | ||
p | p | ||
.. . - . . - | .. . - . . - | ||
* t .\ . | * t .\ . | ||
,.,.g.,. | ,.,.g.,. | ||
a 8 | a 8 | ||
\ ... - . - . | \ ... - . - . | ||
. s i.--. . | |||
. s | |||
i.--. . | |||
_ | _ | ||
* t.*** ' | * t.*** ' | ||
i | i | ||
. . s | . . s | ||
. .. . . . . . ,.* ) | . .. . . . . . ,.* ) | ||
....,......i._..4......J._,.... * | ....,......i._..4......J._,.... * | ||
; h | ; h | ||
. I. . | . I. . | ||
,',t; ; i. 9 ", 9 ,, | ,',t; ; i. 9 ", 9 ,, | ||
,u .: ' ) ,$ i ' 7. - | ,u .: ' ) ,$ i ' 7. - | ||
| Line 1,849: | Line 836: | ||
.- . g . ..tj;.:.-. . p - ;e L ,:u y 1. '3 *' . | .- . g . ..tj;.:.-. . p - ;e L ,:u y 1. '3 *' . | ||
'' 4 'i, | '' 4 'i, | ||
*'_*"n-j ..*$5 '!.l 5g 't' | *'_*"n-j ..*$5 '!.l 5g 't' t'.: 'f,. >.'l... .3. . 3.,....'.; | ||
t'.: 'f,. >.'l... .3. . 3.,....'.; | |||
- < p: ;:. ;. ' | - < p: ;:. ;. ' | ||
2 | 2 | ||
== 2 | == 2 | ||
.i | .i 8. | ||
* 2 f3 ,, cv arn + A J '* an X& | |||
8. | |||
* 2 f3 ,, cv arn + A J '* an | |||
X& | |||
- 5 - | - 5 - | ||
.I (mon co },, | |||
.I | |||
(mon co },, | |||
y | y | ||
_e. | _e. | ||
. i s- | . i s-1., | ||
yl i 'i r.-'~'#'- | |||
1., | |||
yl i 'i | |||
r.-'~'#'- | |||
n.A k | n.A k | ||
-- =5 Q +- - | -- =5 Q +- - | ||
I:t 5 | I:t 5 | ||
.?. | .?. | ||
e i | |||
e | l ii 5 | ||
Y jj ~; y jre&Q ! | |||
ii 5 | |||
Y | |||
jj ~; y jre&Q ! | |||
{ | { | ||
(' t,2 . I E | (' t,2 . I E | ||
e (t523 Y( ... '- | e (t523 Y( ... '- | ||
a a | a a | ||
I g ~ *,,;,. , | I g ~ *,,;,. , | ||
* o w P-saw g ., | * o w P-saw g ., | ||
W I"" ' ' ' i eas On R8% , - ' | W I"" ' ' ' i eas On R8% , - ' | ||
-- ~ C H .?~ , | -- ~ C H .?~ , | ||
,. # %...~., s . | ,. # %...~., s . | ||
., - 5 | ., - 5 | ||
.i g | .i g | ||
. v. f ,-<m i | . v. f ,-<m i | ||
,y-- 4 ..a a - f . i. g | ,y-- 4 ..a a - f . i. g | ||
- T.~"~4 %--.419tvW M 4T14 #2qlpt l | - T.~"~4 %--.419tvW M 4T14 #2qlpt l | ||
;e > a 1 * ; , | ;e > a 1 * ; , | ||
e ,e 2 l | e ,e 2 l | ||
4 4 | 4 4 l | ||
-y 1- . | -y 1- . | ||
,d., : | ,d., : | ||
- . .= 1 % ,I $* J W la #. | |||
- . .= 1 % ,I $* J W | |||
la #. | |||
' E h 5 O} | ' E h 5 O} | ||
m | m | ||
{ io i S | { io i S y-- s-+- | ||
y-- s-+- | |||
's, . | 's, . | ||
:; o i e a | :; o i e a | ||
*,cv s | |||
*,cv | |||
s | |||
v 2 | v 2 | ||
i | i | ||
: a J | : a J | ||
6 2., | 6 2., | ||
p , | p , | ||
p,- 5 ; | p,- 5 ; | ||
, L, 3 j | , L, 3 j | ||
q ' ' | q ' ' | ||
,, v .. | ,, v .. | ||
5 Iy _ | 5 Iy _ | ||
f | f i | ||
a m g-.. c; -- | |||
i | |||
a m | |||
g-.. c; - | |||
l_ ., s ., | l_ ., s ., | ||
* ,o. | * ,o. | ||
: e. . .g.- | : e. . .g.- | ||
:; i . | :; i . | ||
. w.. . . . . . | . w.. . . . . . | ||
,. | ,. | ||
* P s - , .% s s | * P s - , .% s s | ||
,/ A, s , | ,/ A, s , | ||
i i ~ N! ~ | i i ~ N! ~ | ||
~ | ~ | ||
| Line 1,997: | Line 910: | ||
/ \ j | / \ j | ||
. .l i - | . .l i - | ||
.v e % , | .v e % , | ||
. - yt . . 'f ' , | . - yt . . 'f ' , | ||
.. .pn.o | .. .pn.o | ||
'q] <y , | 'q] <y , | ||
,yy I s 1. , | |||
,yy I | |||
s 1. , | |||
. - - ;4 - | . - - ;4 - | ||
t i4 | t i4 | ||
, .' \ _,/ , | , .' \ _,/ , | ||
SP,'TJf:~ W ((''*i'W | SP,'TJf:~ W ((''*i'W | ||
* 9.iuty J;.v.- | |||
9.iuty J;.v.- | |||
). | ). | ||
zz-97.T 'Q C*CI o.tnst u3 G .10 Z S,-'il . ,9 " ey .suf~1 3,vag . . | |||
, , l 4 | , , l 4 | ||
l 1 | l 1 | ||
Enclosure 13.3 .. | Enclosure 13.3 .. | ||
* . l 00/14-5 ~ | * . l 00/14-5 ~ | ||
3'ef"5-e, | 3'ef"5-e, 1-26-72 1 | ||
1-26-72 | |||
1 | |||
. s | . s | ||
: j. @- ** | : j. @- ** | ||
;~. | ;~. | ||
6 N. *. . | 6 N. *. . | ||
fn, | fn, | ||
'{' | '{' | ||
: t - | : t - | ||
t-if; . | t-if; . | ||
/ . J' y | / . J' y | ||
) ~\ | ) ~\ | ||
RESTR AINT3 . - ' | RESTR AINT3 . - ' | ||
s . .. L' , | s . .. L' , | ||
* .._. .. a I I | * .._. .. a I I g PUMP , | ||
g PUMP , | |||
RESTRAINT , | RESTRAINT , | ||
y=1gg.3 b: c | y=1gg.3 b: c i , | ||
i , | |||
/ 3d2y\ . . | / 3d2y\ . . | ||
: t. 1 - , | : t. 1 - , | ||
r , : | r , : | ||
\ _. y' ,2 . | \ _. y' ,2 . | ||
1 | 1 | ||
- )' | - )' | ||
- .s % T ~~ | - .s % T ~~ | ||
8 | 8 | ||
~_ e | ~_ e | ||
.o, ,i 1 | .o, ,i 1 | ||
. l | . l | ||
.- - ,.l . | .- - ,.l . | ||
\ ,, | \ ,, | ||
i ... | i ... | ||
e, | e, | ||
. l | . l | ||
.t | .t | ||
\. ~ | \. ~ | ||
a 4 l | a 4 l | ||
\ s inE '[ , | \ s inE '[ , | ||
. l-l e | |||
. l-l | |||
e | |||
RESTRAINT | RESTRAINT | ||
; ,, . a ; , | ; ,, . a ; , | ||
. . ... 7 - | . . ... 7 - | ||
I REACTOR COOL A NT SYSTEM ARR A N C3 E.M ENT- ELEVATION ' | I REACTOR COOL A NT SYSTEM ARR A N C3 E.M ENT- ELEVATION ' | ||
t | t | ||
< 'g | < 'g | ||
- .e . | - .e . | ||
.~ | .~ | ||
Enclosure 13.3 cf '5 - | |||
600/14-5 I 1- 26= 72 | 600/14-5 I 1- 26= 72 | ||
* 3 l ) | |||
* 3 | |||
l ) | |||
; . / | ; . / | ||
. I | . I | ||
,.-- j. | ,.-- j. | ||
a. | a. | ||
,t | ,t | ||
. 5-a . | . 5-a . | ||
1 s i | 1 s i | ||
.t | .t si , | ||
si , | |||
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;> -w.-------......._. . .a I '. | ;> -w.-------......._. . .a I '. | ||
4 .T *1 .'.e | 4 .T *1 .'.e | ||
- .. l 2 e | |||
- .. l | |||
2 e | |||
>* A. | >* A. | ||
es W fp. 48 O e~ J. . | |||
es W fp. 48 | |||
O e~ J. | |||
I .I.v. t | I .I.v. t | ||
.I | .I | ||
.. m ev | .. m ev u * .. | ||
u * .. | |||
.m. ., ''7* | .m. ., ''7* | ||
y s i . T. '* !, ''.Y | y s i . T. '* !, ''.Y a.. e | ||
a.. e | |||
. 9 | . 9 | ||
.s r , | .s r , | ||
f | f | ||
/../ - | /../ - | ||
4 <f . | 4 <f . | ||
: t. --- | : t. --- | ||
lg | lg | ||
.. c - | .. c - | ||
. W g =. *. | . W g =. *. | ||
.g | .g | ||
.o' .I. | .o' .I. | ||
p * . . | p * . . | ||
4 | 4 d a. .o. .. | ||
d a. .o. .. | |||
l l . . | l l . . | ||
g - _ . ..l O | |||
g - _ . ..l | |||
O | |||
't,, | 't,, | ||
8 0 | |||
* I w | |||
I w | |||
s a ' | s a ' | ||
b . | b . | ||
s . | s . | ||
m e | m e | ||
W W * | W W * | ||
* *E | * *E | ||
* e0 , | |||
4 | |||
* 5 f | |||
e0 , | |||
4 | |||
5 f | |||
c. | c. | ||
e. | e. | ||
C. | C. | ||
N | N | ||
= e 9 | = e 9 | ||
,+O | ,+O | ||
..g'4v'! | ..g'4v'! | ||
3.. 3 ' $,, | 3.. 3 ' $,, | ||
u - | u - | ||
, t | , t | ||
: i. s33.. | : i. s33.. | ||
{* | {* | ||
a | a | ||
* .O, 7.. | * .O, 7.. | ||
t, n. | t, n. | ||
a M. e. | a M. e. | ||
| Line 2,309: | Line 1,046: | ||
L - | L - | ||
t O | t O | ||
, .a cl< , ni | , .a cl< , ni o | ||
w | |||
~ :- | ~ :- | ||
O | O | ||
' /l / | ' /l / | ||
, s h,,'', ",// - | , s h,,'', ",// - | ||
".'I | ".'I | ||
~]_ _ '.:.I | ~]_ _ '.:.I | ||
/ .. | / .. | ||
i | i | ||
, ,s s'.* . | , ,s s'.* . | ||
1 .. | 1 .. | ||
/ | / | ||
/ ... | / ... | ||
i. | i. | ||
e | e | ||
| Line 2,350: | Line 1,069: | ||
1 | 1 | ||
/ | / | ||
/ | / | ||
/ | / | ||
i | i | ||
. n w i. () | . n w i. () | ||
*sl a g o // } | *sl a g o // } | ||
O A u 9 n | |||
'E a | 'E a | ||
/ | / | ||
U a.- | U a.- | ||
f. | f. | ||
| Line 2,373: | Line 1,083: | ||
/ < | / < | ||
/ | / | ||
!.T | !.T 6 | ||
o, | |||
_-- - ll . | _-- - ll . | ||
b> | b> | ||
* o 2 .> | * o 2 .> | ||
3 Y,/ }= 5:-::i::::: d s b - /. . | 3 Y,/ }= 5:-::i::::: d s b - /. . | ||
enn | enn e. | ||
e. | |||
u ' | u ' | ||
/ w w | / w w | ||
.3 1 a> | .3 1 a> | ||
3 . | 3 . | ||
Z j // [f | Z j // [f f5 m- -- <- - | ||
f5 m- -- <- - | |||
/ .- ., it - - t-19 e 3 W // d 4 | / .- ., it - - t-19 e 3 W // d 4 | ||
AAAo fu - | AAAo fu - | ||
| Line 2,409: | Line 1,106: | ||
.) | .) | ||
3 | 3 | ||
! ./ % v | ! ./ % v t | ||
t | |||
/,, . | /,, . | ||
d 4 | |||
d | |||
4 | |||
o / - \-1 ; | o / - \-1 ; | ||
/ | / | ||
. .m. | . .m. | ||
> *a 1 | > *a 1 | ||
| Line 2,430: | Line 1,116: | ||
- ng > | - ng > | ||
O | O | ||
. ,x., e | . ,x., e | ||
. + g | . + g | ||
- <M I o orr | - <M I o orr | ||
.s os 6 St | .s os 6 St | ||
, 1 | , 1 | ||
/ s | / s | ||
,- s | ,- s | ||
| Line 2,448: | Line 1,128: | ||
4- ; ' | 4- ; ' | ||
. ' \ / | . ' \ / | ||
t s../ | |||
/ %. /2'- | / %. /2'- | ||
l A .. - 3 ?! s j | l A .. - 3 ?! s j h(,:1 | ||
h(,:1 | |||
< N | < N | ||
-- $ _ .I. | -- $ _ .I. | ||
g; I | g; I | ||
+ -- | + -- | ||
l-u A | |||
l-u | s K | ||
s ex . | |||
ex . | |||
n | n | ||
\ | \ | ||
. 2/ | . 2/ | ||
| Line 2,481: | Line 1,155: | ||
fs | fs | ||
.+---+.:-+ | .+---+.:-+ | ||
i | |||
% )./ -- | % )./ -- | ||
L | L | ||
.. . \ . | .. . \ . | ||
: g . . . | : g . . . | ||
j.< | j.< | ||
l 92-T ' | l 92-T ' | ||
^ | ^ | ||
's-vT/009 E | 's-vT/009 E | ||
* Et oansopt._ | * Et oansopt._ | ||
5 Jo S | 5 Jo S l | ||
l | |||
% 9 p , | % 9 p , | ||
2 o . | 2 o . | ||
7 t - | 7 t - | ||
- s | - s 6 | ||
2 d | |||
* r . | * r . | ||
1 a * | 1 a * | ||
- h r r e a d e r l o c c | |||
- h r r e a d e | |||
r l | |||
o c c | |||
e 2 . | e 2 . | ||
R 2 # | R 2 # | ||
| Line 2,528: | Line 1,182: | ||
E d f T r o a | E d f T r o a | ||
* N 'h 1 O I r T a . | * N 'h 1 O I r T a . | ||
C e . | C e . | ||
E l P c S . | E l P c S . | ||
N 1 I # | N 1 I # | ||
D p | D p N o A | ||
N o A | |||
. n S t . | . n S t . | ||
yi o N T s . | yi o N T s . | ||
O R . | O R . | ||
nt I O d aa T r pt C P a P h | nt I O d aa T r pt C P a P h o | ||
mS E TU Cr#F 1L E S E r . | |||
a E l R a . | a E l R a . | ||
e retd i | e retd i | ||
S O e eli l T c wcnT AO . ll ouUO TM 2 | S O e eli l T c wcnT AO . ll ouUO TM 2 | ||
* PN ! | |||
PN ! | |||
! A # ~ | ! A # ~ | ||
D & l ee R A . | D & l ee R A . | ||
ke E P l p . | ke E P l p . | ||
un G M o , | un G M o , | ||
'D o N U t h c A P s O I I | |||
'D o N U t h | |||
c A P s O I I | |||
d . | d . | ||
T r | T r | ||
| Line 2,569: | Line 1,213: | ||
. n E | . n E | ||
4 3 | 4 3 | ||
e 1 e | |||
* S e e r m : | * S e e r m : | ||
u i E | u i E | ||
s | s | ||
* T T o O l e N c t n a E D | * T T o O l e N c t n a E D 4 = , | ||
4 = , | |||
4 ); 4 | 4 ); 4 | ||
. v. . . . . , . . . . | . v. . . . . , . . . . | ||
Duke Power Company | Duke Power Company Oconee Nuclear Station 1-26-72 . | ||
Unit #1 PIPE AND COMPONENT IIANGER ll0T DEFLECTION AND INSPE(. TION TEST Date DATA SiiEET Data Recorder Tire Press Temp 1B1 # | |||
Oconee Nuclear Station 1-26-72 . | |||
Unit #1 PIPE AND COMPONENT IIANGER ll0T DEFLECTION AND INSPE(. TION TEST Date DATA SiiEET | |||
Data Recorder | |||
Tire Press Temp 1B1 # | |||
IB2 | IB2 | ||
#1 clear Hard Hard Hard Stop #2 Clear #1 Clear #2 Clear liard Stop Stop Stop NOTE: See Enclosure 13.3, 2 of 5 6 | |||
#1 clear Hard Hard Hard Stop #2 Clear #1 Clear #2 Clear liard Stop Stop Stop | |||
NOTE: See Enclosure 13.3, 2 of 5 | |||
6 | |||
4 a | 4 a | ||
i . | i . | ||
e . _ | e . _ | ||
F 3 .. 9 | F 3 .. 9 a . | ||
a | |||
t , | t , | ||
a | a D | ||
D | |||
h - | h - | ||
_ 2 - | _ 2 - | ||
| Line 2,643: | Line 1,240: | ||
LI s t e | LI s t e | ||
F a | F a | ||
2 | 2 C | ||
S T | |||
O n | |||
n | |||
_ o i "A b t ' | _ o i "A b t ' | ||
' I a t t S n S T T r i _ | ' I a t t S n S T T r i _ | ||
h E eAa r1l E wCr a A l i oOt et R S LLs li T e cnS A R uUE T N R A a D l 6 e G c N n I o P | h E eAa r1l E wCr a A l i oOt et R S LLs li T e cnS A R uUE T N R A a D l 6 e G c N n I o P | ||
- c I O P . | - c I O P . | ||
6 3 | 6 3 | ||
p m | p m | ||
e T | e T | ||
s s 5 e | s s 5 e | ||
r f- | r f- | ||
_ P o | _ P o | ||
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| Line 2,714: | Line 1,275: | ||
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| Line 2,745: | Line 1,293: | ||
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_ uz o e N | _ uz o e N | ||
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sa | |||
cnctoeure s a, o i ct i 600/14-3= - | cnctoeure s a, o i ct i 600/14-3= - | ||
Duke Powar Company . | Duke Powar Company . | ||
1-26-72 - | 1-26-72 - | ||
Oconee Nuclear Station Unit #1 OTSG LATERAL SUPPORT eeA'' "B" Terp Press Time Upper Lateral Upper Lateral | Oconee Nuclear Station Unit #1 OTSG LATERAL SUPPORT eeA'' "B" Terp Press Time Upper Lateral Upper Lateral la 2a 3a 4a 5a Ib 2b 3b 4b Sb Date .. | ||
la 2a 3a 4a 5a Ib 2b 3b 4b Sb Date . | |||
Data Recorder | Data Recorder | ||
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. Oconce Nucicar Station 1 o', | . Oconce Nucicar Station 1 o', | ||
Unit #1 PIPE AND COMPONENT llANGER !!OT DEFLECTION AND INSPECTION TEST | Unit #1 PIPE AND COMPONENT llANGER !!OT DEFLECTION AND INSPECTION TEST | ||
~"'e DATA S!!EET D.ita I:ecorder | ~"'e DATA S!!EET D.ita I:ecorder | ||
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T::0!.0:rJ.:t 13. 7 ,,0conce !!ucicar Station . | T::0!.0:rJ.:t 13. 7 ,,0conce !!ucicar Station . | ||
Unit #1 . _ _ .. . _ . . . . . | Unit #1 . _ _ .. . _ . . . . . | ||
DATA Si1EET Data Recorder , | DATA Si1EET Data Recorder , | ||
Date __- - | Date __- - | ||
OSTC Aux. Fecdwat e r Heade r | OSTC Aux. Fecdwat e r Heade r | ||
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~ l Figure 3 RC System Monitoring Point Location & Installation Details P0-187, Rev. 3 l I | ~ l Figure 3 RC System Monitoring Point Location & Installation Details P0-187, Rev. 3 l I | ||
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| Line 3,385: | Line 1,551: | ||
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x | |||
g .; j "'D 4 4 4[ , | |||
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| Line 3,663: | Line 1,700: | ||
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| Line 3,679: | Line 1,709: | ||
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+ | + | ||
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| Line 3,917: | Line 1,827: | ||
I n. | I n. | ||
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(: t. ;. 'm | (: t. ;. 'm | ||
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I | I | ||
'J | 'J | ||
| Line 4,000: | Line 1,871: | ||
=' g- .f4 a < - | =' g- .f4 a < - | ||
b : | b : | ||
t, *4 ''y s % b. | t, *4 ''y s % b. | ||
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s g .,4 , . - | |||
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:- s ._ - i | |||
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. ,s- t . (s.% . | . ,s- t . (s.% . | ||
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}, | }, | ||
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5..%,1R | 5..%,1R | ||
* y. | |||
y. | |||
: t. , . ' ' (i. | : t. , . ' ' (i. | ||
5j - | 5j - | ||
ii <- fr .:..*.,,*8,de? ' | ii <- fr .:..*.,,*8,de? ' | ||
') 3' 's 8-2, 3 - - | ') 3' 's 8-2, 3 - - | ||
1 D: | |||
.' ..s | .' ..s e | ||
e | |||
"'--3 I | "'--3 I | ||
APPENDIX C OCONEE NUCLEAR STATION UNIT 1 REACTOR COOLANT SYSTEM COMPARISON OF DESIGN VS ACTUAL MOVEMENTS I | APPENDIX C OCONEE NUCLEAR STATION UNIT 1 REACTOR COOLANT SYSTEM COMPARISON OF DESIGN VS ACTUAL MOVEMENTS I | ||
| Line 4,074: | Line 1,913: | ||
l | l | ||
P Considerations Utilized in Comparison Study | P Considerations Utilized in Comparison Study | ||
: 1. Reactor Coolant System Coefficient of linear thermal expansion for carbon steel pipe between ambient temperatures 100*F and 500*F = 0.034 inches / | : 1. Reactor Coolant System Coefficient of linear thermal expansion for carbon steel pipe between ambient temperatures 100*F and 500*F = 0.034 inches / | ||
foot.II) | foot.II) | ||
| Line 4,087: | Line 1,924: | ||
(I} ANSI B31 7 (1969), Table A.5., Coefficients of Thermal Expansion. | (I} ANSI B31 7 (1969), Table A.5., Coefficients of Thermal Expansion. | ||
(2) ANSI B31.1.0 (1967), Appendix B, Thermal Expansion Data. | (2) ANSI B31.1.0 (1967), Appendix B, Thermal Expansion Data. | ||
C-il | C-il l | ||
l | |||
Monitoring Point Location # 1 - Pump 1A1 R. C. System Actual Measurement (Inches) | Monitoring Point Location # 1 - Pump 1A1 R. C. System Actual Measurement (Inches) | ||
Press. (psi) Temp. (*F) X(North) M Z(East) 0 100 2.653 0.597 1.878 500 200 2.545 0 964 1.673 1032 350 2.475 1 378 1.283 2150 500 2.376 1.872 0 752 i | Press. (psi) Temp. (*F) X(North) M Z(East) 0 100 2.653 0.597 1.878 500 200 2.545 0 964 1.673 1032 350 2.475 1 378 1.283 2150 500 2.376 1.872 0 752 i | ||
Design Movement @ E Pump 100*F to 500*F 0.394 1.060 0.880 l. | Design Movement @ E Pump 100*F to 500*F 0.394 1.060 0.880 l. | ||
| Line 4,103: | Line 1,934: | ||
1 (I)l.126 Difference - 0.136 radial expansion = 0 990 C-1 | 1 (I)l.126 Difference - 0.136 radial expansion = 0 990 C-1 | ||
Monitoring Point Location # 1 - Pump 1A2 R. C. Sys tem Acutal Measurement (Inches) | Monitoring Point Location # 1 - Pump 1A2 R. C. Sys tem Acutal Measurement (Inches) | ||
Press. (psi) Temp. (*F) X (South) Y(Up) Z(East) 0 100 1.975 0.202 2.027 500 200 2.062 0.320 1,822 1032 350 2.325 0.790 1.572 2150 500 2.741 1.277 1.262 Design Movement @ [ of pump 100'F to 500*F 0.394 1.060 0.880 Actual Movement @ E of Pump 100*F to 500*F 0.630(y), 1.075 0.765 Difference Between Design & Actual Movement 0.236 0.015 0.115 | Press. (psi) Temp. (*F) X (South) Y(Up) Z(East) 0 100 1.975 0.202 2.027 500 200 2.062 0.320 1,822 1032 350 2.325 0.790 1.572 2150 500 2.741 1.277 1.262 Design Movement @ [ of pump 100'F to 500*F 0.394 1.060 0.880 Actual Movement @ E of Pump 100*F to 500*F 0.630(y), 1.075 0.765 Difference Between Design & Actual Movement 0.236 0.015 0.115 | ||
% Difference 46.1%( l.4% 14.0% | % Difference 46.1%( l.4% 14.0% | ||
II)0.766 difference - 0.136 radial expansion - 0.630 (2)During Hot Functional Test, the target stud was accidently bent during installation of the mirror insulation thereby voiding the initial cold reading. The target stud was realigned for remaining readings and the cold reading was taken again af ter the unit was cooled bac.k down to 130*F. | II)0.766 difference - 0.136 radial expansion - 0.630 (2)During Hot Functional Test, the target stud was accidently bent during installation of the mirror insulation thereby voiding the initial cold reading. The target stud was realigned for remaining readings and the cold reading was taken again af ter the unit was cooled bac.k down to 130*F. | ||
* Value exceeds limiting criteria listed on P0-187 Rev.1 Figure 3 C-2 | * Value exceeds limiting criteria listed on P0-187 Rev.1 Figure 3 C-2 | ||
Monitoring Point location # 2 - OTSG Elevation 849'-8 1/2" R. C. System Actual Measurements (Inches) | Monitoring Point location # 2 - OTSG Elevation 849'-8 1/2" R. C. System Actual Measurements (Inches) | ||
Press. (psi) Temp (*F) X (South) Y(Up) 0 100 1.234 0.982 500 200 1.181 1.590 1032 350 1.065 2.408 2150 500 0.953 3.375 Design Movement @ E of Pipe 0.094 2.212 100*F to 500*F | Press. (psi) Temp (*F) X (South) Y(Up) 0 100 1.234 0.982 500 200 1.181 1.590 1032 350 1.065 2.408 2150 500 0.953 3.375 Design Movement @ E of Pipe 0.094 2.212 100*F to 500*F Actual Movement @ E of Pipe 100*F to 500'F 0.074(2) 2.393 Difference Between Design & Actual 0.020 0.181 Movement | ||
Actual Movement @ E of Pipe 100*F to 500'F 0.074(2) 2.393 Difference Between Design & Actual 0.020 0.181 Movement | |||
% Difference 23.8% 7.9% __ | % Difference 23.8% 7.9% __ | ||
Original readings taken from target studs were erroneous as confirmed by readings taken between tube sheet and seismic stop. The reidings recorded above were taken between the tube sheet and seismic stop and on the South side. | Original readings taken from target studs were erroneous as confirmed by readings taken between tube sheet and seismic stop. The reidings recorded above were taken between the tube sheet and seismic stop and on the South side. | ||
(2) Difference 0.281 minus 0.207 radial expansion = 0.074. | (2) Difference 0.281 minus 0.207 radial expansion = 0.074. | ||
c-3 | c-3 | ||
Monitoring Point Location # 3 - OTSG - F.W. Header Norrie R. C. System F. W. System Temp. (*F) Actual Measurements (Inches) | Monitoring Point Location # 3 - OTSG - F.W. Header Norrie R. C. System F. W. System Temp. (*F) Actual Measurements (Inches) | ||
Press. (psi) Temp. (*F) X (North) Y(Up) 0 100 100 2.033 0.338 500 200 2.013 0 553 1032 350 T.985 0 997 2150 500 350 1.920 1.517 Design Movement e E of F.W. Pipe 0.142 1.154 100*F to 350*F Actual Movement at E of F.W. Pipe 0.113 1.179 100*F to 350*F Difference Between Design & Actual 0.029 0.025 Movement | Press. (psi) Temp. (*F) X (North) Y(Up) 0 100 100 2.033 0.338 500 200 2.013 0 553 1032 350 T.985 0 997 2150 500 350 1.920 1.517 Design Movement e E of F.W. Pipe 0.142 1.154 100*F to 350*F Actual Movement at E of F.W. Pipe 0.113 1.179 100*F to 350*F Difference Between Design & Actual 0.029 0.025 Movement | ||
% Difference 22.7% 2.1% | % Difference 22.7% 2.1% | ||
1 c-4 ) | 1 c-4 ) | ||
l l | l l | ||
Monitoring Point Location # 4 - OTSG Upper Tube Sheet R. C. System Actual Measurements (Inches) | Monitoring Point Location # 4 - OTSG Upper Tube Sheet R. C. System Actual Measurements (Inches) | ||
Press. (psi) Temp. (*F) Y (Up) | Press. (psi) Temp. (*F) Y (Up) 0 100 0.682 - | ||
0 100 0.682 - | |||
500 200 1 315 1032 350 2.110 2150 500 2 960 4 | 500 200 1 315 1032 350 2.110 2150 500 2 960 4 | ||
Design Movement 100*F to 500*F 2.236 | Design Movement 100*F to 500*F 2.236 Actual Mosement 100*F to 500*F 2.278 Difference Between Design & Actual 0.355 Movement | ||
Actual Mosement 100*F to 500*F 2.278 Difference Between Design & Actual 0.355 Movement | |||
% Difference 1.9% | % Difference 1.9% | ||
i | i C-5 | ||
C-5 | |||
_ ~ | _ ~ | ||
Monitoring Point Location #19 - Pressurizer Surge Line Nozzle R. C. System Actual Measurement (Inches) | Monitoring Point Location #19 - Pressurizer Surge Line Nozzle R. C. System Actual Measurement (Inches) | ||
Press. (ps i) Temp. (*F) y b } b p) Z b)(East) i 0 100 1.839 1 776 500 200 1.491 1 994 1032 350 1.084 2.242 2150 500 0.630 2.535 I | Press. (ps i) Temp. (*F) y b } b p) Z b)(East) i 0 100 1.839 1 776 500 200 1.491 1 994 1032 350 1.084 2.242 2150 500 0.630 2.535 I | ||
Design Movement 100*F to 500*F 1.204 0 704 Actual Movement 100*F to 500*F 1.194 (2) 0.774 I3) | Design Movement 100*F to 500*F 1.204 0 704 Actual Movement 100*F to 500*F 1.194 (2) 0.774 I3) | ||
Difference Between Design & Actual 0.010 0.070 Movement | Difference Between Design & Actual 0.010 0.070 Movement | ||
% Difference 0.8% 9.5% | % Difference 0.8% 9.5% | ||
l l | l l | ||
-l I | -l I | ||
) | ) | ||
i U)Y and Z readings reported above are for the top and west monitoring points. | i U)Y and Z readings reported above are for the top and west monitoring points. | ||
Bottom and east readings were discarded as they were less meaningful . | Bottom and east readings were discarded as they were less meaningful . | ||
(2)Dif ference 1.209 minus .- 0.015 radial expansion = 1.194 (3I Di f ference 0.759 plus 0.015 radial expansion = 0.774 | (2)Dif ference 1.209 minus .- 0.015 radial expansion = 1.194 (3I Di f ference 0.759 plus 0.015 radial expansion = 0.774 | ||
) | ) | ||
i | i l | ||
C- 6 l | |||
Monitoring Point Location #20 - 180*E11 Tangent Point at Top of Straight Riser | Monitoring Point Location #20 - 180*E11 Tangent Point at Top of Straight Riser | ||
. C. System Actual Measurements (inches) | . C. System Actual Measurements (inches) | ||
Press. (pal) Temp. (* F) X Horth) Y6Jp) Z 66ast) 0 100 2 559 1.024 2.841 500 200 2.548 1 720 2.770 1032 350 2.515 2.609 2 700 2150 500 2.485 3.515 2.646 Design Movement 100*F to 500*F 0.035 2.250 0.265 Actual Movement 100*F to 500*F 0.023(I) 2.491 0.246 (2) | Press. (pal) Temp. (* F) X Horth) Y6Jp) Z 66ast) 0 100 2 559 1.024 2.841 500 200 2.548 1 720 2.770 1032 350 2.515 2.609 2 700 2150 500 2.485 3.515 2.646 Design Movement 100*F to 500*F 0.035 2.250 0.265 Actual Movement 100*F to 500*F 0.023(I) 2.491 0.246 (2) | ||
Difference Between Design & Actual 0.012 0.241 0.019 Movement | Difference Between Design & Actual 0.012 0.241 0.019 Movement | ||
% Difference 41.4% 10.2% 7.4% | % Difference 41.4% 10.2% 7.4% | ||
O) 074 difference - 0.051 radial expansion - 0.023 | O) 074 difference - 0.051 radial expansion - 0.023 | ||
> ( ) 195 difference + 0.051 radial expansion = 0.246 C-7 i | |||
> ( ) 195 difference + 0.051 radial expansion = 0.246 | |||
C-7 i | |||
Monitoring Point Location #21 - l Al Pump Discharge R. C. System Actual Measurements (inches) | Monitoring Point Location #21 - l Al Pump Discharge R. C. System Actual Measurements (inches) | ||
Press. (psi) Temp. (*F) X (North) Y (up) Z (East) 0 100 0.836 0.834 1.146 500 200 1.102 I.150 1.230 1032 350 1.380 1.500 1.315 2150 500 I.734 1.910 1.432 Design Movement 100*F to 500*F 0.578 1.094 0.459 Actual Movement 100*F to 500*F 0.847 ) 1.076 0.286 Dif ference Between Design r, Actual 0.269 0.010 0.173 Movement | Press. (psi) Temp. (*F) X (North) Y (up) Z (East) 0 100 0.836 0.834 1.146 500 200 1.102 I.150 1.230 1032 350 1.380 1.500 1.315 2150 500 I.734 1.910 1.432 Design Movement 100*F to 500*F 0.578 1.094 0.459 Actual Movement 100*F to 500*F 0.847 ) 1.076 0.286 Dif ference Between Design r, Actual 0.269 0.010 0.173 Movement | ||
% Difference 37.8% 1.7% 46.4% | % Difference 37.8% 1.7% 46.4% | ||
t j | t j | ||
(IIDi f ference 0.898 minus 0.051 radial expansion = 0.847 C-8 | (IIDi f ference 0.898 minus 0.051 radial expansion = 0.847 C-8 | ||
Monitoring Point Location #21 - I A2 Pump Discharge R. C. System Actual Measurements (Inches) | |||
Monitoring Point Location #21 - I A2 Pump Discharge | |||
R. C. System Actual Measurements (Inches) | |||
Press. (ps i) Temp. (*F) X (South) Y OJp) Z (East) 0 100 0 775 0.664 1 553 500 200 0.902 1.112 1.653 1032 350 1.187 1.465 1 787 2150 500 1.494 1.871 1 982 Design Movement 100*F to 500*F 0.578 1.094 0.459 Actual Movement 100*F to 500*F 0.668(I) 1.207 0.429 Di f ference Between Des ign and Actua l 0.090 0.113 0.030 Movement | Press. (ps i) Temp. (*F) X (South) Y OJp) Z (East) 0 100 0 775 0.664 1 553 500 200 0.902 1.112 1.653 1032 350 1.187 1.465 1 787 2150 500 1.494 1.871 1 982 Design Movement 100*F to 500*F 0.578 1.094 0.459 Actual Movement 100*F to 500*F 0.668(I) 1.207 0.429 Di f ference Between Des ign and Actua l 0.090 0.113 0.030 Movement | ||
% Dif ference 14.4% 9.8% 6.8% | % Dif ference 14.4% 9.8% 6.8% | ||
( }0if ference 0.719 minus 0.051 radial expansion = 0.668 C9 i | ( }0if ference 0.719 minus 0.051 radial expansion = 0.668 C9 i | ||
* to APPENDIX D OCONEE NUCLEAR STATION MDS-JR-52 | * to APPENDIX D OCONEE NUCLEAR STATION MDS-JR-52 I | ||
I | |||
~ | ~ | ||
i i | i i | ||
L _ _ . _ . | L _ _ . _ . | ||
OUKE POW 6R LOHi'ANY DESIGN ENGINEERING - MECHANICAL SECTION ENGINEERING J'JSTIFICATION REPORT Date: February 1, 1973 Report No, MOS-J R- 52 To: E. D. Powell/J. E. Smith Originated By: P. N. Hall Station: Oconee 1 Approved By: [ | |||
OUKE POW 6R LOHi'ANY | |||
DESIGN ENGINEERING - MECHANICAL SECTION ENGINEERING J'JSTIFICATION REPORT | |||
Date: February 1, 1973 Report No, MOS-J R- 52 To: E. D. Powell/J. E. Smith Originated By: P. N. Hall Station: Oconee 1 Approved By: [ | |||
L System: Reactor Coolant Sys 50 Sheet I of 1 Mech Sec Group File No: 05-27.4 Variation Reported by a rd Date : Mr. J. E. Smi th, ONS, 1-31-73 Description of Variation: The approximate established. acceptance criteria for thermal movement of Reactor Coolant Pump 1A2 were exceeded during the | L System: Reactor Coolant Sys 50 Sheet I of 1 Mech Sec Group File No: 05-27.4 Variation Reported by a rd Date : Mr. J. E. Smi th, ONS, 1-31-73 Description of Variation: The approximate established. acceptance criteria for thermal movement of Reactor Coolant Pump 1A2 were exceeded during the | ||
~ ~ | ~ ~ | ||
| Line 4,246: | Line 2,012: | ||
This item will be discussed in more detail in Design Engineering's report on RC System thermal moni toring' program. | This item will be discussed in more detail in Design Engineering's report on RC System thermal moni toring' program. | ||
Engineering Regommendations: None required. | Engineering Regommendations: None required. | ||
S.K. Blackley, Jr., Chief Engineer Mechanical & Nuclear Division | S.K. Blackley, Jr., Chief Engineer Mechanical & Nuclear Division By: | ||
By: | |||
PNH:rjd cc: D. G. Beam J. S. Davis R. E. Miller J. L. L. Ostertag | PNH:rjd cc: D. G. Beam J. S. Davis R. E. Miller J. L. L. Ostertag | ||
a ff '/ pf | a ff '/ pf | ||
' REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDSS DISTRIBUT]ON FOR INCOMING MATERIAL 2707297 REC: OREILLY J P ORG: PARKER W O DOCDATE: 08/28/79 NRC DUKE PWR DATE RCVD: 09/11/'i DOC TYPE: LETTER NOTARIZED: NO COPIES RECEIVED SUDJECT: LTR 1 ENCL 1 FORWARDING SUDJECT FACILITY"S SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE AND ENVIRON MONITORING REFT COVERING Tile PERIOD JANUARY 1, 1978 THROUGH JUNE 20, 1970. | ' REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDSS DISTRIBUT]ON FOR INCOMING MATERIAL 2707297 REC: OREILLY J P ORG: PARKER W O DOCDATE: 08/28/79 NRC DUKE PWR DATE RCVD: 09/11/'i DOC TYPE: LETTER NOTARIZED: NO COPIES RECEIVED SUDJECT: LTR 1 ENCL 1 FORWARDING SUDJECT FACILITY"S SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE AND ENVIRON MONITORING REFT COVERING Tile PERIOD JANUARY 1, 1978 THROUGH JUNE 20, 1970. | ||
| Line 4,264: | Line 2,026: | ||
& En*W/2 ENCL EED**W/ ENCL ENVIRO SPEC DR**W/ ENCL EFFLUENT TREAT SYS**W/ ENCL RAD ASSESSMENT BR*nW/ ENCL KASTNER**W/ ENCL EXTERNAL: LPDR'S WALHALLA, SC**W/ ENCL TERAn*W/ ENCL NSIC+*W/ ENCL ACRS CAT Bn*W/ ENCL r | & En*W/2 ENCL EED**W/ ENCL ENVIRO SPEC DR**W/ ENCL EFFLUENT TREAT SYS**W/ ENCL RAD ASSESSMENT BR*nW/ ENCL KASTNER**W/ ENCL EXTERNAL: LPDR'S WALHALLA, SC**W/ ENCL TERAn*W/ ENCL NSIC+*W/ ENCL ACRS CAT Bn*W/ ENCL r | ||
.- ( | .- ( | ||
y1 Dr * | y1 Dr | ||
* DISTRIBUTION: LTR 20 ENCL 20 CONTROL NBR: 782480287 SIZE: 1P+1GP c*0''c****************************** THE END *************************A- ***- | |||
DISTRIBUTION: LTR 20 ENCL 20 CONTROL NBR: 782480287 SIZE: 1P+1GP | |||
c*0''c****************************** THE END *************************A- ***- | |||
012 800 Cp | 012 800 Cp | ||
. .= | . .= | ||
DirKn Powen COMPANY l' owr.w Iltist.n No 422 Sot: Tis Cutincu Srims:T, CliAug.oTTE, N. C. una.u w t LLI AM O. PA R K E R, J R. | DirKn Powen COMPANY l' owr.w Iltist.n No 422 Sot: Tis Cutincu Srims:T, CliAug.oTTE, N. C. una.u w t LLI AM O. PA R K E R, J R. | ||
Vocr Patsf ormt Trit Pa o N t:Aata 704 5 +taan Paoouction 373-4063 August 28, 1978 | Vocr Patsf ormt Trit Pa o N t:Aata 704 5 +taan Paoouction 373-4063 August 28, 1978 Mr. James P. O'Reilly, Director L | ||
Mr. James P. O'Reilly, Director L | |||
" * - * *"= ' I 8 Region II Office of Inspection and Enforcement ' | " * - * *"= ' I 8 Region II Office of Inspection and Enforcement ' | ||
U. S. Nuclear Regulatory Commission Suite 1217 ~ | U. S. Nuclear Regulatory Commission Suite 1217 ~ | ||
230 Peachtree Street, Northwest - | 230 Peachtree Street, Northwest - | ||
Atlanta, Georgia 30303 | Atlanta, Georgia 30303 | ||
==Reference:== | ==Reference:== | ||
Oconee Nuclear Station :; | Oconee Nuclear Station :; | ||
Docket Nos. 50-269, -270, -287 | Docket Nos. 50-269, -270, -287 | ||
==Dear Mr. O'Reilly:== | ==Dear Mr. O'Reilly:== | ||
Pursuant to 10CFR50, 550.36 and Oconee Nuclear Station Technical Specifi-cation 6.6.1.2(c), please find attached data concerning radioactive effluents released from Oconee Nuclear Station. This report covers the period January 1 through June 30, 1978. | Pursuant to 10CFR50, 550.36 and Oconee Nuclear Station Technical Specifi-cation 6.6.1.2(c), please find attached data concerning radioactive effluents released from Oconee Nuclear Station. This report covers the period January 1 through June 30, 1978. | ||
V y truly yours, | V y truly yours, | ||
~ | ~ | ||
j Nu :. d. k' William O. Parker, Jr RLG:vr Attachment cc: Director, Office of Inspection and Enforcement l | |||
j Nu :. d. k' William O. Parker, Jr RLG:vr Attachment cc: Director, Office of Inspection and Enforcement | i 782480287 s | ||
S | |||
782480287 s | \l\ | ||
S | |||
\l\ | ge ATTACHMENT 1 RADIOACTIVE EFFLUENT RELEASES SOLID WASTE | ||
Pt 1 of 4 RADIDACTIVE EFFLUENT RELEASES SOLID WASTE Total volume of solld waste packaged (cubic feet) 26,073.8 Total estimated activity involved (Curies) 752. | |||
ge ATTACHMENT 1 RADIOACTIVE EFFLUENT RELEASES SOLID WASTE | Disposal of materials shioped off-si te: All shipments to Chem-Nuclear Systems Waste Disposal Facility at Barnwell, South Carolina. | ||
DATE CUBIC FT. # OF CURIES 1/3/78 185 2.38 1/6/78 185 2.61 1/7/78 238 1.89 1/9/78 238 1.14E+1 1/10/78 130 1.45 1/12/78 377.4 4.16E-1 1/13/78 205 2.10 1/17/78 205 1.25E+1 1/18/78 235 1.50E+1 1/19/78 205 4.07 1/21/78 238 4.78 1/22/78 238 8.93 1/23/78 766.6 6.88E-1 1/24/78 205 1.86E+1 1/25/78 391.4 2.23 | |||
: 2. 8 C,E+1 1/27/78 185 1/30/78 357.4 2.82E-1 2/1/78 205 9 23 2/2/78 283 5.08 2/6/78 130 5.10E-4 2/7/78 185 3.74 2/9/78 166 , | |||
1.40E-2 2/9/78 80 1.20E-4 2/9/78 80 1.29E-4 2/13/78 185 6.04 | |||
Pt 1 of 4 RADIDACTIVE EFFLUENT RELEASES SOLID WASTE Total volume of solld waste packaged (cubic feet) 26,073.8 Total estimated activity involved (Curies) 752. | Ptg2 2 of 4 DATE CUBIC FT- # OF CURIES 2/15/78 756.2 2.10E-1 2/15/78 60 8.24E-1 2/15/78 - | ||
Disposal of materials shioped off-si te: All shipments to Chem-Nuclear Systems Waste Disposal Facility at Barnwell, South Carolina. | 60 5.55E-5 2/16/78 185 3 02 2/17/73 185 3.49 2/20/78 657.8 3 32E-1 2/22/78 205 6.21 2/27/78 60 1.94E-2 2/27/78 60 6.78E-2 2/27/78 60 5 39E-2 2/27/78 60 2.25E-2 2/27/78 60 6.20E-2 3/1/78 185 7.29 3/3/78 185 8.44E-2 3/5/78 238 1.71E+1 3/8/78 589 4.17E-1 3/10/78 205 6.79 3/14/78 7.4 5.10 3/14/78 205 1.26E+1 3/15/78 637.8 3 38E-1 3/17/78 205 7.39 3/21/78 205 9.43 3/22/78 74 4.08E+1 3/27/78 205 7.82 3/30/78 7.4 ' | ||
DATE CUBIC FT. # OF CURIES 1/3/78 185 2.38 1/6/78 185 2.61 1/7/78 238 1.89 1/9/78 238 1.14E+1 1/10/78 130 1.45 1/12/78 377.4 4.16E-1 1/13/78 205 2.10 1/17/78 205 1.25E+1 1/18/78 235 1.50E+1 1/19/78 205 4.07 1/21/78 238 4.78 1/22/78 238 8.93 1/23/78 766.6 6.88E-1 1/24/78 205 1.86E+1 1/25/78 391.4 2.23 | 1.19 3/31/78 205 7.91 1 | ||
: 2. 8 C,E+1 1/27/78 185 1/30/78 357.4 2.82E-1 2/1/78 205 9 23 2/2/78 283 5.08 2/6/78 130 5.10E-4 2/7/78 185 3.74 | 3/31/78 238 8.23 ) | ||
4/4/78 167 8.10E-1 4/5/78 238 4.23E+1 4/5/78 468.4 5.96E-1 l | |||
2/9/78 166 , | -4/7/78 238 7 29 j 4/7/78 205 1.04E+1 4/11/78 166 3.00E-2 | ||
1.40E-2 2/9/78 80 1.20E-4 2/9/78 80 1.29E-4 2/13/78 185 6.04 | ~ | ||
4/11/78 166 7.00E-2 4/12/78 205 1.17E+1 4/14/78 14.8 1.02 4/14/78 205 9.89 4/18/78 205 7 73 | |||
Ptg2 2 of 4 | , _ Praa 3 of 4 DATE- CUBIC FT. # OF CURIES 4/18/78 14.8 5.10E-1 4/20/78 14.8 2.55 4/20/78 238 4.76 4/21/78 170 4.25 4/21/78 14.8 1.70 4/22/78 512 8.00E-2 4/24/78 592 2 90E-1 4/25/78 205 .' 38 4/25/78 14.8 5 95 4 4/28/78 14.8 6.63 5/1/78 205 3 99 5/3/78 7.4 3.40E+1 5/4/78 537 2 1.03 5/5/78 238 1.09E+1 5/5/78 7.4 1.19 5/6/78 205 9.03 5/7/78 7.4 6.80E-1 5/7/78 238 2.24 5/12/78 238 1.73E+1 5/14/78 130 2.06 5/16/78 130 1.07E+1 5/18/78 238, 1.14 5/18/78 205 3.16 5/19/78 868 2.19 5/19/78 45 8.73E+1 5/22/78 238 3 06 5/23/78 238 1.04 l 5/26/78 238 4.00 5/26/78 576.4 1.78E-1 5/26/78 203 3.19 5/28/78 238 2.43 5/31/78 205 2.66 6/3/78 205 . 3.85 6/4/78 205 . | ||
2.22 l 6/5/78 238 6.51 6/6/78 205 1.96 l l | |||
F 3 4 of 4 DATE' CUBIC FT. # OF CURIES 6/8/78 205 3.32 6/9/78 81.4 3 04 6/9/78 205 2.50 | |||
; 6/9/78 238 2.05 6/12/78 205 7.37 6/12/78 238 1.16 6/14/78- 205 1.06E+1 6/15/78 130 < | |||
1.03E+1 6/16/78 205 1.43E+1 6/16/78 621.6 7.03E-1 6/17/78 130 1.53E+1 6/20/78 205 1.40E+1 6/26/78 130 4.10E-1 6/28/78 205 3.63 6/28/78 205 1.74E+1 6/30/78 238 7.84 6/30/78 562.4 1.84 6/30/78 205 8.09 TOTAL 26073.8 7.52E+2 t | |||
2/15/78 756.2 2.10E-1 2/15/78 60 8.24E-1 2/15/78 - | i | ||
60 5.55E-5 2/16/78 185 3 02 | |||
O e | |||
2/17/73 185 3.49 2/20/78 657.8 3 32E-1 2/22/78 205 6.21 2/27/78 60 1.94E-2 2/27/78 60 6.78E-2 2/27/78 60 5 39E-2 2/27/78 60 2.25E-2 2/27/78 60 6.20E-2 3/1/78 185 7.29 3/3/78 185 8.44E-2 3/5/78 238 1.71E+1 3/8/78 589 4.17E-1 3/10/78 205 6.79 3/14/78 7.4 5.10 3/14/78 205 1.26E+1 3/15/78 637.8 3 38E-1 3/17/78 205 7.39 3/21/78 205 9.43 3/22/78 74 4.08E+1 3/27/78 205 7.82 3/30/78 7.4 ' | ATTACHMENT 2 RAD 10ACTI EFFLUENT RELEASES LIQUID RELEASES l | ||
1.19 3/31/78 205 7.91 1 | i | ||
3/31/78 238 8.23 ) | |||
4/4/78 167 8.10E-1 4/5/78 238 4.23E+1 4/5/78 468.4 5.96E-1 l | |||
-4/7/78 238 7 29 j 4/7/78 205 1.04E+1 4/11/78 166 3.00E-2 | |||
~ | |||
4/11/78 166 7.00E-2 4/12/78 205 1.17E+1 4/14/78 14.8 1.02 4/14/78 205 9.89 4/18/78 205 7 73 | |||
, _ Praa 3 of 4 | |||
4/21/78 170 4.25 4/21/78 14.8 1.70 4/22/78 512 8.00E-2 4/24/78 592 2 90E-1 4/25/78 205 .' 38 | |||
4/25/78 14.8 5 95 4 4/28/78 14.8 6.63 5/1/78 205 3 99 5/3/78 7.4 3.40E+1 5/4/78 537 2 1.03 5/5/78 238 1.09E+1 5/5/78 7.4 1.19 5/6/78 205 9.03 5/7/78 7.4 6.80E-1 5/7/78 238 2.24 5/12/78 238 1.73E+1 5/14/78 130 2.06 5/16/78 130 1.07E+1 5/18/78 238, 1.14 5/18/78 205 3.16 5/19/78 868 2.19 5/19/78 45 8.73E+1 5/22/78 238 3 06 | |||
5/23/78 238 1.04 l 5/26/78 238 4.00 5/26/78 576.4 1.78E-1 5/26/78 203 3.19 5/28/78 238 2.43 5/31/78 205 2.66 6/3/78 205 . 3.85 6/4/78 205 . | |||
2.22 l 6/5/78 238 6.51 6/6/78 205 1.96 l l | |||
F 3 4 of 4 | |||
; 6/9/78 238 2.05 6/12/78 205 7.37 6/12/78 238 1.16 6/14/78- 205 1.06E+1 6/15/78 130 < | |||
1.03E+1 6/16/78 205 1.43E+1 6/16/78 621.6 7.03E-1 6/17/78 130 1.53E+1 6/20/78 205 1.40E+1 6/26/78 130 4.10E-1 6/28/78 205 3.63 6/28/78 205 1.74E+1 6/30/78 238 7.84 6/30/78 562.4 1.84 6/30/78 205 8.09 | |||
TOTAL 26073.8 7.52E+2 | |||
O e | |||
ATTACHMENT 2 RAD 10ACTI EFFLUENT RELEASES LIQUID RELEASES l | |||
%JTUO) | %JTUO) | ||
| Line 4,380: | Line 2,090: | ||
: 5. U 19.H ;;:0-*/ M i! !* SEL2a*E- UO!/ 'L 2.17 3-3 e 7.I42-3J 2.5- M , 2. 75-1v | : 5. U 19.H ;;:0-*/ M i! !* SEL2a*E- UO!/ 'L 2.17 3-3 e 7.I42-3J 2.5- M , 2. 75-1v | ||
;. m.4 : ..; 2 00i'.i1 CI 2 i "iL4/.*I~ UCI/ :L 1.775-07 1.52E-17 a. h 1.hE-J7 | ;. m.4 : ..; 2 00i'.i1 CI 2 i "iL4/.*I~ UCI/ :L 1.775-07 1.52E-17 a. h 1.hE-J7 | ||
: s. s....., s | : s. s....., s | ||
: a. J:lAL f:L:43J O'J 7 E' :.l.E+'t s.odi+31 1.43E+32 3.2 - E+ 32 | : a. J:lAL f:L:43J O'J 7 E' :.l.E+'t s.odi+31 1.43E+32 3.2 - E+ 32 | ||
| Line 4,394: | Line 2,103: | ||
,. ~. .?? >:*.s.. | ,. ~. .?? >:*.s.. | ||
.. a w.mI c e- | .. a w.mI c e- | ||
'.,-i-1 2.1s5-03 6.145-04 4. ,35-94 1.425-33 0- i 1.30E-02 J.I41 *3 1.053 '1 2. , i E-02 | '.,-i-1 2.1s5-03 6.145-04 4. ,35-94 1.425-33 0- i 1.30E-02 J.I41 *3 1.053 '1 2. , i E-02 | ||
:-l'8 7.5t:-02 i.G45-32 1.225-01 2. $ 5-11 | :-l'8 7.5t:-02 i.G45-32 1.225-01 2. $ 5-11 | ||
| Line 4,411: | Line 2,119: | ||
*. 7.325-04 3. l.245-'3 Z.345-JJ | *. 7.325-04 3. l.245-'3 Z.345-JJ | ||
:; . . 3.34E-04 1. 5.535-1o 3.,3E .'v 2 .22 5-35 ,, 2.74E-35 4. 915-M | :; . . 3.34E-04 1. 5.535-1o 3.,3E .'v 2 .22 5-35 ,, 2.74E-35 4. 915-M | ||
-. . d . 3 2 5 5.345-04 3.d2 5-); I.73E-03 M-G | -. . d . 3 2 5 5.345-04 3.d2 5-); I.73E-03 M-G 1.475-Oe C. O. 1.$7E-34 | ||
1.475-Oe C. O. 1.$7E-34 | |||
-t- 1.I25-03 4.402-04 c.195-34 2. $J E-33 w' O. 1. O. 1. | -t- 1.I25-03 4.402-04 c.195-34 2. $J E-33 w' O. 1. O. 1. | ||
:- v 5.53E-04 3. O. 5.53E-34 | :- v 5.53E-04 3. O. 5.53E-34 | ||
| Line 4,419: | Line 2,125: | ||
. -t13' 5.36E-03 1.165-12. 4. 72 E-7 3 2.375-02 | . -t13' 5.36E-03 1.165-12. 4. 72 E-7 3 2.375-02 | ||
;-l iv 3. 3. $.455-0$ 5.-5E-Jo | ;-l iv 3. 3. $.455-0$ 5.-5E-Jo | ||
-n 1.2 E-33 2.7$E-03 7.7IE-34 4.3 i E-13 | -n 1.2 E-33 2.7$E-03 7.7IE-34 4.3 i E-13 3.345-04 d .175-15 7.115-35 5.3 $ E-34 81- Qm o . l' . 3. O. 3. | ||
81- Qm o . l' . 3. O. 3. | |||
;-i % | ;-i % | ||
4-l;7 O h j. | 4-l;7 O h j. | ||
| Line 4,432: | Line 2,134: | ||
( v2 . 5.96E-04 9. 77E-N 2.425-74 1.475-33 I.;- 11 a i | ( v2 . 5.96E-04 9. 77E-N 2.425-74 1.475-33 I.;- 11 a i | ||
: 4. 33 E-35 3. 2.23 E-25 7. % E-M 00-81a 1.575-04 4.615-04 4.40 N 5 s.$25 07-13 C. 1. .9. 3. | : 4. 33 E-35 3. 2.23 E-25 7. % E-M 00-81a 1.575-04 4.615-04 4.40 N 5 s.$25 07-13 C. 1. .9. 3. | ||
il--I 3.2cE-05 d.425-06 3. 4.12 E-35 I O. 1.312-06 0. 1.3tE-Jo AE-:s 5.J I E-03 1.14E-03 2.7$2-04 7.2 3 E-33 3: -125 t 2.165-05 3. 3, ._ . 2.16E-35 | il--I 3.2cE-05 d.425-06 3. 4.12 E-35 I O. 1.312-06 0. 1.3tE-Jo AE-:s 5.J I E-03 1.14E-03 2.7$2-04 7.2 3 E-33 3: -125 t 2.165-05 3. 3, ._ . 2.16E-35 01-13a 3.40E-0$ 1. 3. 3. 435-b U-s $ d.40E-02 v.405-32 4.83c-32 2.2 $ E-31 40-103 2.553-05 i.laE-75 t,ao N 4 f.345-04 33-I25 t.30E-03 2.025-04 4.345-35 1.355-33 32.-125 I.42E-03 S. S. l.425-33 45-13s 0, 1.355-05 0. I .35 E-15 57-1234 9. 1. O. 3. | ||
- F-le 1 3. S. 3. | - F-le 1 3. S. 3. | ||
40-t os t 2. 575-M 1. - 3.44E-05 4.935-05 4E-135 4 ' 1. 1. 3. 1. | 40-t os t 2. 575-M 1. - 3.44E-05 4.935-05 4E-135 4 ' 1. 1. 3. 1. | ||
| Line 4,442: | Line 2,143: | ||
...4 4sw w e en N | ...4 4sw w e en N | ||
Pope 2 of 3 RA !"A07:VE E.::L;E:.7 *ELEAiES YEAA 1878 I* '* I ''' I * '* * | |||
Pope 2 of 3 | |||
RA !"A07:VE E.::L;E:.7 *ELEAiES YEAA 1878 I* '* I ''' I * '* * | |||
~'tS#$ | ~'tS#$ | ||
~ | ~ | ||
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Latest revision as of 17:09, 27 February 2020
| ML19316A237 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/29/1973 |
| From: | Patricia Hall, Mathews D, Miller A DUKE POWER CO. |
| To: | |
| References | |
| PROC-730329, NUDOCS 7912030352 | |
| Download: ML19316A237 (50) | |
Text
{{#Wiki_filter:. . Regulat:r! :../.3t 7:.350-269 l REGULffCXiD0.x ; n_. , __
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EO-287 l THERMAL MOVEMENT MONITORING PROGRAM ' , _ _ ,
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FOR OCONEE 1-2-3 REACTOR COOLANT SYSTEM -~
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THERMAL MOVEMENT MONITORING PROGRAM FOR OCONEE l-2-3 REACTOR COOLANT SYSTEM DUKE POWER COMPANY DESIGN ENGINEERING DEPARTNENT MECHANICAL DESIGN SECTION, hi'HANICAL AND NUCLEAR DIVISION CHARLOTTE, NORTH CAROLINA FILE 05-278 Duke Power Conoany 0uali tv Assurance Statement: This cccument includes engineering design of items related to nuclear safety, in ac:ordance with established procedures. Its quality has been assured.
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TABLE OF CONTENTS S,ection Title Pajun 1 i INTRODUCTION AND PURPOSE lNTER-COMPANY DIVISION OF RESPONSIBILITY 2 ll Ill DETERMINATION OF MONITORING POINT LOCATIONS 3 INSTALLATION METHODS FOR MONITORING POINT 4 IV HARDWARE SYSTEM TEST SEQUENCE AND DESCRIPTION 5 V 6 VI ENGINEERING LIMITATIONS AND PRECAUTIONS Vil DATA RECORDED 7 Vill COMPARISON OF ANALYTICAL AND TEST RESULTS 8 IX CONCLUSIONS 9 X APPLICABILITY OF TEST TO UNITS 2 & 3 11 APPENDIX - 4 m e-- = , e - -- -+
- l. INTRODUCTION AND PURPOSE As the result of discussions in the 124TH Duke-ACRS Meeting held on August 13, 1970, Duke Power Company agreed to monitor the thermal expansion movement of the Unit 1 Reactor Coolant System #50. The purpose of the monitoring program is two-fold:
- 1) To determine the movement of the system piping during the hot functional test period as described in Section V of this report.
- 2) To review recorded data to assure that. thermal stresses and movements within the system are compatible with analytical predictions.
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l II. INTER-COMPANY DIVISION OF RESPONSIBILITY , Responsibility for the implementation of the monitoring program is shared by the Duke Power Company Design Engineering, Constructime and Steam Pro-duction Departments as outilned below.
- 1) Design Engineering Department
- a. Establish need for program as described in 1. of this report end Appendix A
- b. Citablish monitoring point locations based on analytical results ;
and as described in Section lli of this report I
- c. Establish installation methods of monitoring devices as described in Section IV of this report
- d. Establish Engineering limitations and precautions as described in Section VI of this report l
- e. Establish data to be recorded during test as described in Sec-tion VII of this report
- f. Make engineering comparison and evaluation of analytical versus actual test data as described in Section Vill of this report
- g. Define acceptability of results as described in Section IX of this report
- h. Describe applicability of test results with respect to Unit 2 and 3 as described in Section X of this report
- i. Preparation of report for AEC review.
- 2) Construction Department
- a. Installation of monitoring point hardware at locations described in Section ill and in accordance with methods described in Sec-tion IV of this report
- b. Assist Steam Production Department in the surveillance and record-Ing of data as requested
- 3) Steam Production Department Develop a procedure for monitoring the thermal expansion of the Reactor Coolant System as required by Design Engineering , Appendix A
- b. Coordinate and schedule with the Construction Department as necessary for the installation of monitoring hardware and data-recording
- c. Documentation of monitoring program results in accordance with Oconee Nuclear Station Test Procedure TP i A 60014 5 (See Appendix A)
- d. Transmittal of monitoring data to the Engineering Department for i cvicw anil approval and subsequent preparation of Thermal Monitoring R e p. . t
Ill. DETERMINATION OF MONITORING POINT LOCATIONS Monitoring points in general are located at positions undergoing measurable expansion movements shown on Figure 1 and 2 in accordance with B & W analy-tical predictions. Specifically, monitoring point locations are defined on Drawing PO-187 (Figure 3) and as listed herein. 1 1 Monitoring Point Data Required Attachment Location & Quantity b i Movement of RC pumps in On support lug located 180* the X, Y & Z directions from pump 1A1 and 1A2 dis-charge at Elevation 813'-0" (one required x's 2 pumps) 2 OTSG X & Y movement at On east side centerline of top of RC inlet nozzle weld joint at nozzle (one required) 3 OTSG X & Y movement at On outboard side of either feedwater header leg of feedwater inlet piping i' on centerline elevation of butt weld to feedwater ring i header nozzle (one required) 4 OTSG Y movement at upper On 1 1/2" vent and level tube sheet sensing connection at top of tube sheet at Elevation 842'-2 3/4" on IA generator ~ (one required) 19 Pressurizer surge line On bottom, top, west and east nozzle Y & Z movement centerlines of butt weld to at RC System hot leg con- nozzle. (Four required x's nection on pipe assembly I nozzle.) A-33 20 X, Y & Z RC System hot On north, south, east and west leg movement at top of centerlines of tangent point straight run - 180' Ell weld. (Four required x's one tangent point weld) 21 X Y & Z RC System cold On reessure tap connection leg movement. (Long and of ti.s 1A1 and 1A2 RC pump short RC pump discharge discharge line. (One required line) x's 2 lines) 4
a , l IV. INSTALLATION METHODS FOR MONITORING PolNT HARDWARE A description of the hardware and method of attachment of monitoring points hardware is shown on Drawing PO-187 (Figure 3) except for location number 1 which does not require attachments to the piping or vessels. At monitoring location 1, a 1/2" hex nut was welded to a 1/4" plate and bolted to the sup-port lug on the pump casing. All other monitoring locations as' described in 111 above require attachments to the piping or vessels. The welding of attachments directly to piping or vessels was not permissible. Heavy gauge stainless steel banding was used primarily on piping or vessels for the attachment method using a 1/2" stainless steel hex nut welded in position on the band. Target studs protruding thru insulation having a polished end for micrometer readings were held in place by a threaded con-nection with the 1/2" hex nuts. In addition, target studs are marked with location identification if monitoring is ever conducted in the future. Target studs were removed af ter the monitoring program and properly stored.
\ _
-4
V. SYSTEM TEST SEQUENCE AND DESCRIPTION in an effort to meet the Duke Design Engineering Department quality Assur-ance Inspection for harigers, restraints and suppressors as described in FSAR IC.3.7 and obtain data suitable for the preparation of this report, the Oconee Nuclear Station Steam Production Department prepared and executed ' test procedure TP 1 A 600 14 5, " Pipe and Component Hanger Hot Deflection < and Inspection Tett." This procedure is made a part of this report as Appendix A. Duke's Design Engineering Department reviewed and accepted the test proce-dure prior to its initial use. i 1 I l
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l l
VI. ENGINEERING LIMITATIONS AND PRECAUTIONS Any restrictions or deflection limits imposed on the Reactor Coolant System or its hangers, restraints and supports are included in test procedure TP 1 A 600 14 5 and were established in accordance with manu-facturer and Duke Design Engineering Department requirements. Approximate predicted movements for the Reactor Coolant System as listed on Drawing PO-187 (Figure 3) were established as limiting criteria for system movements. Steam Production Department personnel were to check and obtain Design Engineering approval if any of the predicted movements were exceeded during the system heat-up prior to escalating system temperature. 1
. , - +-n , m m
, , ) Vil. DATA RECORDED l The extent of information recorded is described in Test Procedure TP *
- 600 14 5 (Appendix A).
Data recorded either meets or exceeds the information required for this report and Ic in accordance with manufacturer and/or Duke Design Engi-neering Department requirements. In an effort to make this report more meaningful and brief, only the information required to confirm and satisfy the purpose of the report is tabulated in Appendix C along with the predicted analytical Infor-mition for comparative purposes. 7
Vill. CDMPARISON OF ANALYTICAL VERSUS TEST RESULTS A comparison of analytical uavements versus the actual measured movements is made for each point of Interest in Appendix C. The comparison is pre-sented in the form of Percentage Difference such that the overall accuracy of readings versus analytical predictions can be reviewed and determined. Review of the data in Appendix C Indicates that the horizontal movement of Reactor Coolant Pump 1A2 exceeded the approximate limiting criteria established on Drawing P0-187 (Figure 3) in one direction. Steam Produc-tion Department contacted the Design Engineering Department once the i variation was noted. Design Engineering made a simple stress calculation, determined that the variation was acceptable, gave the Steam Production Department the maximum limiting criteria and advised that the system
- could continue to be heated up as long as the maximum limiting criteria were not violated.
A review of the variation at monitoring point I has been conducted with results as described in MDS-JR-52 (Appendix D). i l l l
IX. CONCLUSIONS l Based on the information presented in Appendix C and as summarlzed in Section Vill of this report, thermal expansion movements of the Reactor Coolant System exhibitled average % Differences to predicted movements as follows:
% Difference % Difference % Difference X(North-South Direction) Y(Vertical Direction) Z(East-West Direction) 31.57% 6.02% 15 98%
for an overall average % Difference of 17.86%. These % Differences would be even smaller if the dimensions being examined were of greater magnitude; l however, % Differences experienced are acceptable based on the small dimensions being evaluated. The following conclusions are made as the result of this study.
- 1) All expansion movements were near the actual predicted movement, indicating actual thermal stresses of the system are in acenrd-ance with the design.
- 2) Dif ferences between predicted movements versus actual moveuents are small enough that they can be accounted for by the possible inaccuracles of the monitoring technique and the effect of piping wall thickness manufacturing tolerances on system flexibility.
- 3) The system behaved as predicted by stress analysis techniques except in the case of Reactor Coolant Pump IA2 movement thereby confirming analytical predictions and actual thermal stresses in the system.
- 4) The variation in the movement of Reactor Coolant Pump 1A2 can be explained in that the pump Inlet piping probably has more flexibility than expected. In addition, the movement experienced between 450*F and 500*F was about twice that of other comparable 50*F temperature increases which would Indicate that the pump seismic restraint might possibly be stiffer than expected in the hinged joints. This
~
restraint was examined by Design Engineering and determined to be free of any restrictions to the proper movement. 9
6 s IX. CONCLUSIONS
- 5) The variation in the movement of Reactor Coolant Pump IA2 is totally acceptable as described in HDS-JR-52 (Appendix D) and any stiffness in the seismic restraint will improve with cycling of the system.
The pump returned back to the original cold position with a good degree of accuracy confirming these conclusions. O e
X. APPLICABILITY OF TEST TO UNITS 2 & 3 The Reactor Coolant Systems for all three Oconee units are identical in arrangement, in design conditions and in all physical parameters such as piping wall thickness, materials of construction, support and restraint location, etc., that would have a bearing on the thermal stress analysis. Thus, the results of the thermal expansion monitoring test on Unit I are totally acceptable and indicative of results that would be expected from monitoring Units 2 and 3 Since the purpose of this monitoring program was academic in nature, only the Unit i Reactor Coolant System will be monitored. 9 i
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O O APPENDIX A OCONEE NUCLEAR STATION TEST PROCEDURE TP 1 A 600 14 5
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OC0hTE. NUCLEAR STATION . 1 TP 1 A 600 14 5 PIPE AND COMPONENT HANGER HOT DEFLECTION AND INSPECTIO!I* TEST - l 1.0 Purpose , To verify the predicted load and. travel indications on the following hangers and adjust those not within the required margins: Reactor Coolant pump constant' load supports (two per pump). OTSC Auxi-
., liary Feedwater header hangers (three per header). Pressurizer spray , -< s line (two hangers). Points listed on P.O. Dwg. 187 (1) (2) 1-21, RC
( , pumps LOCA restraints, piping supports, and OTSG supports. *- i 2.0 References 2.1 Drawing No. 1016470, (B&W) Typical Pump and Motor Support Criteria. 2.2 Dra wing No. 129303E, (OTSG No.1) Drawing No. 146403E (OTSG No. 2) 9l Cross sections through Steam Generator (B&W). ,, 2.3 Grinnell Co. Instruction Manuals #52, Model R, Fig. 80V-Type E. Constant Support (RC Pumps) Figure 98 No. 6 and Pig. 98 No. 8 Support Hangers (OTSG Aux. FW Headers). , 2.4 B&W TS/1/A/600/4. 2.5 B&W Drawing #163356, Reactor Coolant Piping Arrangement Plan. 2.6 Dwg. No. P.O. 187 (1) -(2) . 3 2.7 Eng. Letter - File OS-18, OS-27, - Dated 11-1-71. 3.0 Time Required Portion of a shift prior to Hot Functional Test, during Hot Functional 3 Test and following cooldown from Hot Functional Test. 4.0 Prcrcquisite Tests 9 None j
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5.0 Test. Equipment *
. l 5" outside precision calipers.
6" Scale '. . Inside Micrometer 3" - 4" range. Outside knerometer 3" - 4"* range. , Hydraulic Jack with 3" - 4" total length, including travel. ;- 6.0 Limitations and Precautions 6.1 No adjustments to be made to the load supports except as authorized _ by the Station Superintendent. , 6.2' 1101/01 - Plant Operating Limits and Precautions. : 6.3 Stop RCS heatup if the hanger deflection indicating pin is approaching or has contacted its travel hard stop.
~
6.4 Stop RCS heatup if piping or components come in contact with seismic restraints, beams, etc. ' ' 7.0 Required Plant Status
g 7.1 RCS in cold condition. :
8.0 Prerequisite System Conditions , , 8.1 Alltravelstopsonhangersmu'stberemoved-friortosystemsheat-up. 9.0 Test Method ' 9.1 Cold and hot pipe hanger position buttons will t:. observed before - - . . . . _. The WHITE button is Cold ~ position, and the and during system heatup. RED button is hot position. Position indication readings will be taken at 50*F increments during heatup and cooldown. Pipe and e component deflections will be read and recorded at 50*F increments during heatup and cooldown. Seismic restraints will be checked at 200*F, 350*F and 500*F during heatup and cooldown to insure piping. and compor.ents do not come hard against a restraint. 1 10.0 Data Required ! 10.1 Initial Cold Positions Vs. RCS Temperature. i * * ~- "** *~~savnenre.
600/14-5
- e. *. 1-26-72 10.3 Ad[ustments, if any. ,
10.4 Final Cold Positions Vs. RCS Temperature following Hot Functional Test. . 11.0 Acceptance Criteria .- Position indication readings during and after test stay within the travel range and do not contact the hanger stops. Piping and components do not come in contact with seismic restraints. Piping and component deflections are within design values.
' 12.0 Procedure 12.1 Record all hanger positions on enclosed data sheets prior to Hot Functional Test.
+12.2 Record all hanger positions,every,50* change of RC temperature during heatup for Hot Functional Test.
12.3 Item #6 on PO Dwg.187 (1) (2) to be taken as following: 1.a. Cold Position o
- b. 200*F ,
- c. 350*F l
- d. 500*F 1
- 2. The reading A, B, & C to be taken with a 6" scale at the - l designated point, with the block away from the OTSC & firm against .e support plate.
- 3. The "D" reading to be taken at 500*F with the inside Micrometer at the designated' points marked on the blocks, then by the use of the jack the block is firmly pressed against the stationary block on the OTSC.
12.4 The RCP LOCA restraints, piping supports & OTSG supports to be checked as following:
- a. Cold Position
- b. 200*F l
l
600/14-5
, l'26-72
.,c. 350*F -
- d. 500*F
' The data sheets to be checked off as 0.K. or against HARD STOP. - NOTE - If against HARD STOP, notify Shif t Supervisor to stop RC heatup and notify Test Coordinator. 12.5 Upon attaining 532*F adjust load adjustment bolt if hanger is not at hot position until indication is on hot position button. 12.6 Record all hanger positions every 50*F change"of RC temperature during cooldown after Hot Functional Test. . f-13.0 Enclosures 13.1 5 ketch of Grinnell Constant Support, Figure 80V-Size 52. 13.2 Data Sheet - RC Piping , 13.3 Support Schematics. 13.4 Data Sheet .- Pump & Miitor Supports 1325 Data Sheet - RC Piping Restraints , 13.6 Data Sheet - OTSG Lateral Supports 13.7 Data Sheet - Hangers S 9 l
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APPENDIX C OCONEE NUCLEAR STATION UNIT 1 REACTOR COOLANT SYSTEM COMPARISON OF DESIGN VS ACTUAL MOVEMENTS I 1 i l l C-I l l
P Considerations Utilized in Comparison Study
- 1. Reactor Coolant System Coefficient of linear thermal expansion for carbon steel pipe between ambient temperatures 100*F and 500*F = 0.034 inches /
foot.II)
- 2. B & W maximum Reactor Coolant System movements are shown on Drawings 128625E and 128626E, Figures 1 & 2. These movements were converted to approximate movements at 500*F by linear extrapolation.
3 For measurements made perpendicular to piping and vessels, the radial expansion of same is added or subtracted, as the case may be, to the thermal movement for converting to centerline movements.
- 4. Feedwater System coefficient of linear thermal expansion for carbon steel pipe between ambient temperatures 100*F and 350*F = 0.020 inches /footf 2) 5 The directions (North), (South), (East), (West) and (Up) located beside the X, Z, Y coordinates in the following tables indicate the direction of movement of the particular point.
References:
(I} ANSI B31 7 (1969), Table A.5., Coefficients of Thermal Expansion. (2) ANSI B31.1.0 (1967), Appendix B, Thermal Expansion Data. C-il l
Monitoring Point Location # 1 - Pump 1A1 R. C. System Actual Measurement (Inches) Press. (psi) Temp. (*F) X(North) M Z(East) 0 100 2.653 0.597 1.878 500 200 2.545 0 964 1.673 1032 350 2.475 1 378 1.283 2150 500 2.376 1.872 0 752 i Design Movement @ E Pump 100*F to 500*F 0.394 1.060 0.880 l. Actual Movement @ E Pump 100*F to 500*F 0.277 1.275 0 990(I} Difference Between Design & Actual 0.117 0.215 0.110 Movement
% Difference 34.8% 18.4% 11.8%
1 (I)l.126 Difference - 0.136 radial expansion = 0 990 C-1
Monitoring Point Location # 1 - Pump 1A2 R. C. Sys tem Acutal Measurement (Inches) Press. (psi) Temp. (*F) X (South) Y(Up) Z(East) 0 100 1.975 0.202 2.027 500 200 2.062 0.320 1,822 1032 350 2.325 0.790 1.572 2150 500 2.741 1.277 1.262 Design Movement @ [ of pump 100'F to 500*F 0.394 1.060 0.880 Actual Movement @ E of Pump 100*F to 500*F 0.630(y), 1.075 0.765 Difference Between Design & Actual Movement 0.236 0.015 0.115
% Difference 46.1%( l.4% 14.0%
II)0.766 difference - 0.136 radial expansion - 0.630 (2)During Hot Functional Test, the target stud was accidently bent during installation of the mirror insulation thereby voiding the initial cold reading. The target stud was realigned for remaining readings and the cold reading was taken again af ter the unit was cooled bac.k down to 130*F.
- Value exceeds limiting criteria listed on P0-187 Rev.1 Figure 3 C-2
Monitoring Point location # 2 - OTSG Elevation 849'-8 1/2" R. C. System Actual Measurements (Inches) Press. (psi) Temp (*F) X (South) Y(Up) 0 100 1.234 0.982 500 200 1.181 1.590 1032 350 1.065 2.408 2150 500 0.953 3.375 Design Movement @ E of Pipe 0.094 2.212 100*F to 500*F Actual Movement @ E of Pipe 100*F to 500'F 0.074(2) 2.393 Difference Between Design & Actual 0.020 0.181 Movement
% Difference 23.8% 7.9% __
Original readings taken from target studs were erroneous as confirmed by readings taken between tube sheet and seismic stop. The reidings recorded above were taken between the tube sheet and seismic stop and on the South side. (2) Difference 0.281 minus 0.207 radial expansion = 0.074. c-3
Monitoring Point Location # 3 - OTSG - F.W. Header Norrie R. C. System F. W. System Temp. (*F) Actual Measurements (Inches) Press. (psi) Temp. (*F) X (North) Y(Up) 0 100 100 2.033 0.338 500 200 2.013 0 553 1032 350 T.985 0 997 2150 500 350 1.920 1.517 Design Movement e E of F.W. Pipe 0.142 1.154 100*F to 350*F Actual Movement at E of F.W. Pipe 0.113 1.179 100*F to 350*F Difference Between Design & Actual 0.029 0.025 Movement
% Difference 22.7% 2.1%
1 c-4 ) l l
Monitoring Point Location # 4 - OTSG Upper Tube Sheet R. C. System Actual Measurements (Inches) Press. (psi) Temp. (*F) Y (Up) 0 100 0.682 - 500 200 1 315 1032 350 2.110 2150 500 2 960 4 Design Movement 100*F to 500*F 2.236 Actual Mosement 100*F to 500*F 2.278 Difference Between Design & Actual 0.355 Movement
% Difference 1.9%
i C-5 _ ~
Monitoring Point Location #19 - Pressurizer Surge Line Nozzle R. C. System Actual Measurement (Inches) Press. (ps i) Temp. (*F) y b } b p) Z b)(East) i 0 100 1.839 1 776 500 200 1.491 1 994 1032 350 1.084 2.242 2150 500 0.630 2.535 I Design Movement 100*F to 500*F 1.204 0 704 Actual Movement 100*F to 500*F 1.194 (2) 0.774 I3) Difference Between Design & Actual 0.010 0.070 Movement
% Difference 0.8% 9.5%
l l
-l I
)
i U)Y and Z readings reported above are for the top and west monitoring points. Bottom and east readings were discarded as they were less meaningful . (2)Dif ference 1.209 minus .- 0.015 radial expansion = 1.194 (3I Di f ference 0.759 plus 0.015 radial expansion = 0.774
)
i l C- 6 l
Monitoring Point Location #20 - 180*E11 Tangent Point at Top of Straight Riser
. C. System Actual Measurements (inches)
Press. (pal) Temp. (* F) X Horth) Y6Jp) Z 66ast) 0 100 2 559 1.024 2.841 500 200 2.548 1 720 2.770 1032 350 2.515 2.609 2 700 2150 500 2.485 3.515 2.646 Design Movement 100*F to 500*F 0.035 2.250 0.265 Actual Movement 100*F to 500*F 0.023(I) 2.491 0.246 (2) Difference Between Design & Actual 0.012 0.241 0.019 Movement
% Difference 41.4% 10.2% 7.4%
O) 074 difference - 0.051 radial expansion - 0.023 > ( ) 195 difference + 0.051 radial expansion = 0.246 C-7 i
Monitoring Point Location #21 - l Al Pump Discharge R. C. System Actual Measurements (inches) Press. (psi) Temp. (*F) X (North) Y (up) Z (East) 0 100 0.836 0.834 1.146 500 200 1.102 I.150 1.230 1032 350 1.380 1.500 1.315 2150 500 I.734 1.910 1.432 Design Movement 100*F to 500*F 0.578 1.094 0.459 Actual Movement 100*F to 500*F 0.847 ) 1.076 0.286 Dif ference Between Design r, Actual 0.269 0.010 0.173 Movement
% Difference 37.8% 1.7% 46.4%
t j (IIDi f ference 0.898 minus 0.051 radial expansion = 0.847 C-8
Monitoring Point Location #21 - I A2 Pump Discharge R. C. System Actual Measurements (Inches) Press. (ps i) Temp. (*F) X (South) Y OJp) Z (East) 0 100 0 775 0.664 1 553 500 200 0.902 1.112 1.653 1032 350 1.187 1.465 1 787 2150 500 1.494 1.871 1 982 Design Movement 100*F to 500*F 0.578 1.094 0.459 Actual Movement 100*F to 500*F 0.668(I) 1.207 0.429 Di f ference Between Des ign and Actua l 0.090 0.113 0.030 Movement
% Dif ference 14.4% 9.8% 6.8%
( }0if ference 0.719 minus 0.051 radial expansion = 0.668 C9 i
- to APPENDIX D OCONEE NUCLEAR STATION MDS-JR-52 I
~
i i L _ _ . _ .
OUKE POW 6R LOHi'ANY DESIGN ENGINEERING - MECHANICAL SECTION ENGINEERING J'JSTIFICATION REPORT Date: February 1, 1973 Report No, MOS-J R- 52 To: E. D. Powell/J. E. Smith Originated By: P. N. Hall Station: Oconee 1 Approved By: [ L System: Reactor Coolant Sys 50 Sheet I of 1 Mech Sec Group File No: 05-27.4 Variation Reported by a rd Date : Mr. J. E. Smi th, ONS, 1-31-73 Description of Variation: The approximate established. acceptance criteria for thermal movement of Reactor Coolant Pump 1A2 were exceeded during the
~ ~
~
thermal monitoring program. Certify that the exce'ption is accepta'b'le.' Engineering Analysis Required: Analyze the actual movement with respect to establishe'd criteria and certify results to Duke Steam Production for purpose of clearing exception noted in monitoring data. Engineering
Conclusions:
Actual movement was reviewed with respect to its effect on the thermal stresses in both the RC Pump inlet piping and discharge piping. In both cases the resulting stresses are expected to be less than predicted by a factor up to 15%; therefore, the exception to the established criteria is totally acceptable. Engineering Disposition of Variation (List all drawings, specif kations and/or calculations revised by number, name and revision number): This item will be discussed in more detail in Design Engineering's report on RC System thermal moni toring' program. Engineering Regommendations: None required. S.K. Blackley, Jr., Chief Engineer Mechanical & Nuclear Division By: PNH:rjd cc: D. G. Beam J. S. Davis R. E. Miller J. L. L. Ostertag
a ff '/ pf
' REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDSS DISTRIBUT]ON FOR INCOMING MATERIAL 2707297 REC: OREILLY J P ORG: PARKER W O DOCDATE: 08/28/79 NRC DUKE PWR DATE RCVD: 09/11/'i DOC TYPE: LETTER NOTARIZED: NO COPIES RECEIVED SUDJECT: LTR 1 ENCL 1 FORWARDING SUDJECT FACILITY"S SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE AND ENVIRON MONITORING REFT COVERING Tile PERIOD JANUARY 1, 1978 THROUGH JUNE 20, 1970.
(/d b(CN ' PLANT NAME: OCONEE - UNIT 1 REVIEWER INITIAL: XJM OCONEE - UNIT 2 DIGTRIBUTER INITIAL $ M OCONCE - UNIT 3
- &* DISTRIBUTION OF THIS MATERI AL IS AS FOLLOWS *+-****************
NOTES:
- 1. M. CUNNINO! LAM -- ALL AMENDMENTS TO FSAR AND CHANGES TO TECH SPECS ANNUAL ENVIRONMENTAL RPTS (OL STAGE).
(DISTRIDUTION CODE A007) FOR ACTION: DR Cl " ORD#4 DC**W/7 ENCL INTERNAL: sce ._u*W/ ENCL NRC PDR**W/ ENCL
& En*W/2 ENCL EED**W/ ENCL ENVIRO SPEC DR**W/ ENCL EFFLUENT TREAT SYS**W/ ENCL RAD ASSESSMENT BR*nW/ ENCL KASTNER**W/ ENCL EXTERNAL: LPDR'S WALHALLA, SC**W/ ENCL TERAn*W/ ENCL NSIC+*W/ ENCL ACRS CAT Bn*W/ ENCL r
.- (
y1 Dr
- DISTRIBUTION: LTR 20 ENCL 20 CONTROL NBR: 782480287 SIZE: 1P+1GP c*0c****************************** THE END *************************A- ***-
012 800 Cp
. .=
DirKn Powen COMPANY l' owr.w Iltist.n No 422 Sot: Tis Cutincu Srims:T, CliAug.oTTE, N. C. una.u w t LLI AM O. PA R K E R, J R. Vocr Patsf ormt Trit Pa o N t:Aata 704 5 +taan Paoouction 373-4063 August 28, 1978 Mr. James P. O'Reilly, Director L
" * - * *"= ' I 8 Region II Office of Inspection and Enforcement '
U. S. Nuclear Regulatory Commission Suite 1217 ~ 230 Peachtree Street, Northwest - Atlanta, Georgia 30303
Reference:
Oconee Nuclear Station :; Docket Nos. 50-269, -270, -287
Dear Mr. O'Reilly:
Pursuant to 10CFR50, 550.36 and Oconee Nuclear Station Technical Specifi-cation 6.6.1.2(c), please find attached data concerning radioactive effluents released from Oconee Nuclear Station. This report covers the period January 1 through June 30, 1978. V y truly yours,
~
j Nu :. d. k' William O. Parker, Jr RLG:vr Attachment cc: Director, Office of Inspection and Enforcement l i 782480287 s S
\l\
ge ATTACHMENT 1 RADIOACTIVE EFFLUENT RELEASES SOLID WASTE
Pt 1 of 4 RADIDACTIVE EFFLUENT RELEASES SOLID WASTE Total volume of solld waste packaged (cubic feet) 26,073.8 Total estimated activity involved (Curies) 752. Disposal of materials shioped off-si te: All shipments to Chem-Nuclear Systems Waste Disposal Facility at Barnwell, South Carolina. DATE CUBIC FT. # OF CURIES 1/3/78 185 2.38 1/6/78 185 2.61 1/7/78 238 1.89 1/9/78 238 1.14E+1 1/10/78 130 1.45 1/12/78 377.4 4.16E-1 1/13/78 205 2.10 1/17/78 205 1.25E+1 1/18/78 235 1.50E+1 1/19/78 205 4.07 1/21/78 238 4.78 1/22/78 238 8.93 1/23/78 766.6 6.88E-1 1/24/78 205 1.86E+1 1/25/78 391.4 2.23
- 2. 8 C,E+1 1/27/78 185 1/30/78 357.4 2.82E-1 2/1/78 205 9 23 2/2/78 283 5.08 2/6/78 130 5.10E-4 2/7/78 185 3.74 2/9/78 166 ,
1.40E-2 2/9/78 80 1.20E-4 2/9/78 80 1.29E-4 2/13/78 185 6.04
Ptg2 2 of 4 DATE CUBIC FT- # OF CURIES 2/15/78 756.2 2.10E-1 2/15/78 60 8.24E-1 2/15/78 - 60 5.55E-5 2/16/78 185 3 02 2/17/73 185 3.49 2/20/78 657.8 3 32E-1 2/22/78 205 6.21 2/27/78 60 1.94E-2 2/27/78 60 6.78E-2 2/27/78 60 5 39E-2 2/27/78 60 2.25E-2 2/27/78 60 6.20E-2 3/1/78 185 7.29 3/3/78 185 8.44E-2 3/5/78 238 1.71E+1 3/8/78 589 4.17E-1 3/10/78 205 6.79 3/14/78 7.4 5.10 3/14/78 205 1.26E+1 3/15/78 637.8 3 38E-1 3/17/78 205 7.39 3/21/78 205 9.43 3/22/78 74 4.08E+1 3/27/78 205 7.82 3/30/78 7.4 ' 1.19 3/31/78 205 7.91 1 3/31/78 238 8.23 ) 4/4/78 167 8.10E-1 4/5/78 238 4.23E+1 4/5/78 468.4 5.96E-1 l
-4/7/78 238 7 29 j 4/7/78 205 1.04E+1 4/11/78 166 3.00E-2
~
4/11/78 166 7.00E-2 4/12/78 205 1.17E+1 4/14/78 14.8 1.02 4/14/78 205 9.89 4/18/78 205 7 73
, _ Praa 3 of 4 DATE- CUBIC FT. # OF CURIES 4/18/78 14.8 5.10E-1 4/20/78 14.8 2.55 4/20/78 238 4.76 4/21/78 170 4.25 4/21/78 14.8 1.70 4/22/78 512 8.00E-2 4/24/78 592 2 90E-1 4/25/78 205 .' 38 4/25/78 14.8 5 95 4 4/28/78 14.8 6.63 5/1/78 205 3 99 5/3/78 7.4 3.40E+1 5/4/78 537 2 1.03 5/5/78 238 1.09E+1 5/5/78 7.4 1.19 5/6/78 205 9.03 5/7/78 7.4 6.80E-1 5/7/78 238 2.24 5/12/78 238 1.73E+1 5/14/78 130 2.06 5/16/78 130 1.07E+1 5/18/78 238, 1.14 5/18/78 205 3.16 5/19/78 868 2.19 5/19/78 45 8.73E+1 5/22/78 238 3 06 5/23/78 238 1.04 l 5/26/78 238 4.00 5/26/78 576.4 1.78E-1 5/26/78 203 3.19 5/28/78 238 2.43 5/31/78 205 2.66 6/3/78 205 . 3.85 6/4/78 205 .
2.22 l 6/5/78 238 6.51 6/6/78 205 1.96 l l
F 3 4 of 4 DATE' CUBIC FT. # OF CURIES 6/8/78 205 3.32 6/9/78 81.4 3 04 6/9/78 205 2.50
; 6/9/78 238 2.05 6/12/78 205 7.37 6/12/78 238 1.16 6/14/78- 205 1.06E+1 6/15/78 130 <
1.03E+1 6/16/78 205 1.43E+1 6/16/78 621.6 7.03E-1 6/17/78 130 1.53E+1 6/20/78 205 1.40E+1 6/26/78 130 4.10E-1 6/28/78 205 3.63 6/28/78 205 1.74E+1 6/30/78 238 7.84 6/30/78 562.4 1.84 6/30/78 205 8.09 TOTAL 26073.8 7.52E+2 t i
O e ATTACHMENT 2 RAD 10ACTI EFFLUENT RELEASES LIQUID RELEASES l i
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;: -; 7 4.Jo E-04 1.7dE-03 . . 3.4cE-65 2.215-03
- -47 1.2 d E-0 2, 1.17~M I _ l.10E-02 1.405-C1
--133 - 1.055-02 1.55E-13 7.c55-03 1.97E-0 2 3
;-132 .C._ .. C. . C. C. ..
2?-130 2.35 E-63 2. 24 E-03 1.e6E-04 4.755-03 I
. ;--:: C. .Q 2.095-04 2.09 E-C d !
s-1: O. C. 1.015-04 2. ole-04 i
;.. *. i 7.*SE-cd c.5 4 E-14 3.*$E-05 .l .J7 5-C 3 8.- - 4.525-04 1. 09 E-03 3.325-04 t.375-03 I In , i 0. 3.E05-25 2.223-C5 a.22E-05
- i-e -- 4.!JE-63 1.115-13 $.005 ^4 6. 45 E-C3 J-se 0 ._ _- . _ . J0. . 3. .. O. ...
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9 C..
- -l .. 0 ... - . .. 3. . . . -
- s. 9. 73 E-03 3.30 E-0 2 J.53E-02 5.13 E ^2
.. .- 1 3, 1.435-03 1.535-04 1.735-C2 3.3 2E-C3
- -4 s 7.295 63 9.19E-03 $.C9E-od 1. 76 5-C 2 l
?i-2G 3.325-04 3.07E-03 S.955-04 4.20 5-^ 2 l
+:-12r 0. c. 9. O. I l-13: 1.705-04 3.d5E-04 2.715-04 7.55 E-04 I
.-lie C. ,l . 6d 5-^ 3 9.255 65 1.975-C3 l
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E-131 3.
- 5 E-0 2 1. 93 E-0 2 $.455-03 $.435-02 an-4 : ,
0.735 ^3 4.075-03 9.9di-o5 1.29E-Ci
>-239 M, ' ,9.. 4. 65 64 2.54E-14 3.94E ^d 1.115-03 2.-d 7 D @'@i a .a 4.e9E-04 2. nee-02 2.33 E-64 2.225 a3
.' - 9 "J j ;s * .3dE-04 1.725-03 3.c05-ed 2.31E-C3 DslDs- d# O. 2.325-75 1.935-05 4.755-05 A.-i4 T.-II: ; 0. O. O. e.
I-42 2.! 25-04 1.135-04 1.idE-04 f. die ed I -I l5': 3. c. I.645-C5 1.c d E-C-f 2~-ft:
. $.245-05 . 455-05 1.53E 'd 2.cis-04
- =134 9 P. 1 C.
le-41 4.91 E-c 5 2.415-04 9.*l5-05 3.3.7 E-c d I I-134 0. C. O. O. ! C =2 9. 2d E-ed 1.36E-64 3.3di e2 3.45E e2 l 1 -I s S. 6 S. C. 23-13e . 9 2.50 Evo3 9. 5.5 E-c3
- .-t: 9.535 62 2.335-'I 1.Jef I d.05E-^1 3J-l*3 3. *E-03 2.$05-03 3.*$5 65 5.o35-33 35-125 d. 7 5-e s *
- 7. ode 34 * .c3E 35
- 1.34E-r 1 i?-l ia 0. . 9. .
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. 2.37E-03 0. 2.375-C2 1:.-123:: F. *. 9 C.
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. . P.
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,, 2.125-73 0. 2.92E-05
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fe-ci 4.I25-9$ 5.*di-?i '. c.d iE "i i!-e:
*. 3.355-14 2.59 r5 '3.44E-ed f-::
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I. ... !.-... . a -4.m..c ist 292 . u:4 C3 OUA*!Eh ;UA TE Ci.5-T;;.s L*
- 1. 4a435 aM CT f!!Y A. 07AL nELEAfs CLAIE3 !.045 # 0 2.52Ev0 3.53E*00
- 3. 4. ig AJE 0~.'.:E"7n s !!;N :ELEA! . wC r'L 2.975-oc 7. 4* Eec 5.15E-09
. O. tr ;; V: 00..*E.:TaA 7! C:! ,ELEAS C C 0! r". 1.OsEe7 2.3 4E-n 7 1.93 E-C 7 .. .in! ., ..
A. '. l.L .-4 LEASE 0" MIS 3.2*E*02 2.4954 2 5. 73 E+C 2
- . A.iUJi 00. 0Ea fd7! :: AELEA SC LO!< "L 9. 24i-e 7 7.4t'Ee 7 2. 34 E-0 7
- 3. JI 3* * ,-;*, * ;8;E O ui5
- 8. . 1;DL aiLEASE CURIES 2.525-O t 3.01E+^0 3.86E+00 J. A. Iai.e - "-"72)T:::: AELEA!C i.;0 rIL 2.4J H 9 5.9 4 E-0 9 .5.625-09 4 Jr.;!5 ALr-J sA IAO*IVI Y
- s. . .AL n4 LEASE CURIES 0. O. 0..
. AvisAvi C "0E37'AT r 0" lii*EAS C
- UO!rtL 0. O. O.
$. v4*e 'E OF LI i!: ..AS E DI! MAECE IL.AL LCERS 3.55E*07 3.285-07 .. o.3JE:*07 o ,CLs!E OF ;tL;;I::: . A 2R LCE25 3.50E*l l 3.27E-11 6.87E+ 18
- 7. ., ,... .- r. .,
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;-ill 2.8SE-Ol 3.185-01 0.05 E-O t I-123 . l.I9E-02 f .24E-0 2 . 2 ' 4-C 2.
(:-t 22 5.75E-01 2.4CE+00 2.99E+CO
.G-4 35 I .3 0E-02 2.9 7E-02 4.07E-02 05-127 2.39E-01 I.005-01 3.J9 E-01 03-834 L.29E-of 5.93E4 2 1.88E-01
%-60 9. 29 E-02 I .80E-01 2.73E-01 0 -35 1.39E-08 I.25E+00 . l .49 E+00
- e-s1 5.95E-03 I.I3E-01 1.19E-0I T4-54 1.54E-0 2. 2.505-02 4.34 E-0 2
.<r-4 7 3.59E-05 I .34E45 5.435-05 be-4 7 2.29E-04 2. 21 E-03 . . . . 2 44E-02
- S-47 3.3 0E-0 2 .44 E4 : I.77E-01
.G-l 22'A 2.11E-03 I .9 7M2. 2.1 SE-02
;-i32 S.OIE-07 C. 8.0t E-07 03-tJo . l .J 2E-03 4.75E-03 -
- _.. 5.57E-03 G-ISM 2.04E-03 2.09E-04 2.25E-03
.Ca-! d 2.90E-04 2.61 E-04 . 0.515-04 4:i-'si 4.965-05 I .J9EM J I . 44 E-03 Si-Go I.73E-03 I.375-0J 3.oCE-02 3n-G 2 1.67E-04 6.325-05 2.30E-04
;4- 4 4= 2.45E-03 6.4 5E-02 9.135-03 0.-i o 0. O. O.
.i:-0 9 5.53E-04 c. . . . . 5.53 E-04 i--il. O. C. C.
w-t10 2.07E-02 5.I25-0 2 . 7.20 E-02 34-t39 c.455-Oc 3.J 2E-03 3.33E-0 3 i: 4.3IE-03 1.76E-0 2 2.24E-C2
- --se 5. joe-04 4.!"E-03 5.23E-03 53-i ae 0. 0. O. _
I-lJi 7.59E-03 7.855-04 5.655-03
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$-f 3:: 0 O. O.
.i-4 21. : 1.47E-02 $ .4 35-02 7.905-02 Le-os 1.39E-03 I . 29E-92 I.435-02
.e-22; I.7CE-03 I !15-03 2.d I E-0 3
. -:7 3.425-04 2.72E-33 3.0$E-03 70 -4 3.- 1.85E-04 2.51 M 3 2.99E-CJ 0 -24 3.305-05 4.755-05 S.01545
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f-4 4 I.37E-03 5.565-04 2.425-03 IT-t 1:1 7.0$E-C5 I.345-05 a.705-05 I;-Itt o .6 2E-04 2.65E-04 9.275-04 02-124 9. C. C. 1*-41 4.125-05 3.**:-04 4.21E-04
!-tJ& I.31E-Oo C. 1.31E-C$
n *9 7.235-n3 3.455-n2 4.175-r 2 3:.-12':2 2.loE-05 S. 2.12 E-05
- i-t2: ?.415-0$ !.5"E-r3 5.515-C2
<n-4: 2.262-01 4.9 5Es t 7.21E-Ol n=1*3 1.395 nd 5.635<3 , 5.77E ~t3 5:-l2: I.25E-03 I.2EE-03 2.725 a3 3"-l 2: I.425 # 3 F. l. 4 15 " 3
. 44-12: I.355-05 2.J7 --0 3 2.Ji E-03 3' - 12 2 n. o. c. 4-13 1. a. O. E.;15 ~5 W -l.% ' $ .*M *5 2.'2: ^i 15 -1 3: . O. . P. h-41 1.03: 55 S .4 2Es 5 1. 4.t E-c 4
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l ATTACHMENT 3 l RADICACTIVE EFFLUENT RELEASES AIRBORNE RELEASES
IC-LEC*! IC-idF'" CR-i -*
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- 9 50-5 0L
- 5 50-566 *L GC-EEC*9 90-5El*t *C C-t-Y7-YE 40-322*l LO-394*l LD-St9't LEl-SO 90-EtE*e 904 P9'E 532YY OI2tYd C3cV3 Ee $3dCJTS! *c 531500 to-Ett*C ZO-Be9't *4 S.JYY
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- I 00 5It*5 00+395*I *y CL+EEt*E Co-EL9'I lo-EEE*e : f?SYC E7Ecr 00+3EC*9 abCd 11777 779YO!1ddV ?C 1r30- 3d *L E0+30C*t 035/!00 .JYt
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- PADIJA0TIVE IFiLsEa! r.iLEA5Es
!!. Alidhw4 2 ELEAfE5 J,iI 3 Arn!L AAY JJr.. CUS-TCTAL
- 1. TwfAL JJdLE CASE 3 OJnIES n.9dE+03 7.50E+02 3.33 E +03 8.31E+04
- 2. TwfAL aALwJEns OsnIES s.935-02 0.93E-03 1.15E-02 7. ale-02
- 3. TwiAL /AnlICJLAiE Jksis JETA-wA:uA CanIE3 6.405-04 1.05E-0J 6. 99 E-03 5.335-03 4 TOTAL inITIL4 CJAIES 3.05E+0i 4.52E-04 9.1J5 01 l .2JE+02
- s. T0iAL /AnTICJLAi!
sad 55 ALenA A07IVI!( CJnIES 0. C. O. O.
- a. 4AXIm h aw?LE JAS itELEAsi nATE UCI/5E' l.60E+03 l . 60 E+03 1.60!+03 1.00E+03
- 7. rExCE i OF APPLICA3L2 .
LI.411 ?was A. .udki JASE3 % 1.76E+01 1.47E+00 6.53E+00 2.56E+0i
- 3. nAbwCEJ5 1.5eE*04 1.a2E+00 3.12E+00 2.05E+01 C. FAsTIO. LATE 3 7. 63E-02 9.55E-02 a.35E-Cl S.07E-01
- 4. 154Torda TiELIA3E2 OGIE3 fad!IOLLAiE5 0a-131 2. 33E-05 2.c25-05 7.23E-05 1 225-04 5A-LA-4-0 1.095-0s 1.29E-05 2.625-05 5.00E-05 5n--O 2. l o E-07 2.25E-07 2.095-07 6.50E-0 7 04-434 6.7dE-06 3. 77E-Ce 3.0 6E-05 4.J2E-05 Sn-o, 2.92E-06 3.04E-06 2.82E-06 8.78E-06 0.-oo 7.84E-07 7.15E-05 4.725-05 1.19E-04 Ca-lJs 3.95E-06 I.98E-07 2.385-06 a.34E-06 Cs-43a 9.17E-Co 2.ooE-06 5.705-0s 6.895-05 An-o' l . I I E-0 7 8 .35 E-0 7 I . 70E-0 7 4.67E-07
-a-vv 4.32E-Il 2.68E-07 2.22E-03 2.91E-07 na-vs 1.27E-08 1.C35-07 1.2SE-08 1.29E-07 Ca-oO 3.04E-06 2.71E-06 7.34E-06 1.36E-05
.44+ 0. l.07E-07 3.50E-06 8.605-06
^<-il3a 2.09E-05 2.18E-05 5.405-05 9. 66 E-05 C4-o l I .cl E-04 5.33E-05 1.425-04 3.2dE-04 a..-123. C. C. C. O.
TO ve.s 9.8 3E-07 4.045-07 1.45E-06 2. 77E-04 As-lCJ4 1.52E-06 3.3aE-07 2.a55-0$ l.89E-06 ns-ci 3.39 E-04 5.25E-04 3.07E-03 3.93E-03 hr-23, 6.725-05 5.235-05 9.50E-G5 2.15E-04 C;-ils 2.35E-05 2.40E-05 5.2SE-05 1.05E-04 05-4-4 7.2cE-05 4.92E-05 v.9tE-05 2.21E-04 Sa-vi 1.49E-05 1.56E-05 4.llE-05 7. 8 6E-05 Y-98" 0. C. C. Q. xJ-103 6.39E-Il 1.225-07 1.205-08 1.J4E-07 L.. -s o 9.23E-07 2.32E-07 2. 662-09 1.23E-06 , bA-13d 2.44E-06 8.68E-05 1.26E-06 2.04E-05 l s.e-tZam O. C. C. C. 5d-v2 0. l.16E-07 I.33E-05 1.34E-05 Cs-37 4.41E-il 4.09E-07 2.45E-08 4.33E-07 Fs-39 v .56E-07 1.68E-06 7.005-06 9.63E-04 24-95 1.623-05 6.47E4 6 1.565-05 3.83E-05 n5-9 7 6.71E-il I.215-07 4.55E-07 5. 7 6E-07 Zw-97 4. ale-il I .22E-07 2.205-08 1.44E-07 Y-92 6.50E-05 4.54E-05 3.035-03 3. lee-03 a o-12m I.71E-05 2.27E-05 4.05E-05 S.CJE-05 2..-o5 1.54E-ce 5.59E-06 1.56E-05 2.275-05 n-467 1.025-05 1.38E-05 2.385-05 4.79E-05 IN-alsa c.46E-06 8.16E-Oo 5.17E-06 1.98E4 5 iA-22 C. 1.01E-07 8.325-09 8.33E-07 NI-c5 9.63E-06 1.40E-05 3.02E-05 5.38E-05 en-6 44 0. C. C. C. CJ-t o s C. C. O. C. TE-134 c. O. O. 3.
^
zw-loo 0. O. C. ng - r3 T5-434 C. O. O. $$ I
^^L=0EuS W c a .l::s I-131 5.54E-02 4.335-03 9. 00E-03 6.37E-02 1 -4 33 3.34E-03 5.92E-05 2.05E-03 ,
5.452-03 1-13s 4.21E 2.24E-04 5.9TE'-04 f.34E-03~ I-132 2.94E-05 5.65E-05 5.54E-05 1.4tE-04 I-134 4.57E-40 1.595-05 2.56E-07 1.62E-05 F-la 1.39 E-04 2.44E-03 5.14E-05 2.65E-03 GASIS l K4-e5 6.29E*01 7.29 E+01 1. 49E +0i 1.51E+02 XE-13J a.76E+03 6.44E+02 3.15E+03 1.2sE+04 Ka-oS l.83E-Ol 2.24E+00 5.38E+00 7.74E+00 KA-o? 9.83E-02 3.375-01 3.54E-01 8.19E-OL En-ena 2.69E-08 b.57E-01 5.86E+00 6. 69 E+00 IE-13J 5.54E-Cl 4.09 E-02 3.40E-02 6.29E-01 XE-13s= 1.42E-01 6.46E-02 1.135-01 3.205-01 1 XE-133 4.0lE+01 2. ale +00 8.00E+02 1.43E+02 l cn=41 4.43E-02 2. 34 E+00 2.39E+0i 2. 63E *C l ! e rw,ypw - wm m wTr~wt _ J
a ouArmu JI. Al25bdini nELEASE3 - 1st 2nd
' ,J;4tTS Q OUARTER $Ua- M TAL , . _ UARTER ,, , ,
- 1. TJTAL I4 ELE 3AdE5 ' CJn!CS 3.08E+03 L.315+04 I.61E+04
- 2. TJTAL nALOGENS Cud!ES 3.09E-02 7.81 E-02 1.09E-01
- 3. TJTAL # ARTICULATE GnOSS sETA-CAmaA cud!IS 4.90E-03 8. 88 E-03 1.3dE-02 4 h TAL TdITIUJ CJRIES 4.19E-08 1.2JE+02 1.23E42
- 5. T".TAL PAMTIOJLAIZ 04:15 ALadaA ACTIVITY OURIES 0. C. C.
- 4. JAXIsJd 68LE DA$
xELEAan kATE UCI/5EC 1.60E+03 I.60E+03 1.60E+03 7 AdRCI.iT 0/ AdrLICABLE LidIT Fas A. ;J5LE GASE3 % 6.03E+00 2.56E*01 '. 3. 8 6E+0 i
- 5. P.AL GE:.5 *
. 8.12E*00 2.05E 01 2.87E*01
- 0. # ANTIC',LATES
. s 4.53E-01 8.07E-ol 1.26E+00 S. 13 7 /E3 dELEASEO CURIES rAdTIOUuTIS C3-4J7 9.24E-06 1.225-04 1.3 t E-44 dA 8A-4'3 I.225-07 5. 00 E-05 5.01E-05 aa-v0 2.clE-04 6.50E47 2.01 E-04 05-134 2.84E-05 4.325-05 a.45E-05 nic-6v 9.45E-04 8.78E-Ce 9.54E-04
- .k-6 d 7.14E-Co 3.19E-04 1.27E4 4 0:n-4 36 t.565-06 6.34E-Co 7.905-06 03-43e 3.73E-05 6.89E-05 I .00E-04
.4N-o* 3.60E-07 4.67E-07 8.27E-07
.4w-vv C. 2.9 t E-07 2.9tE-07
.8-vs 6.60E-09 I.29E-07 I.35E-07 0:J-oo 2.57E-05 I.3eE-05 3.93E-05
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