Text

Rev a to Book 1 of ASME Section III Analysis of Class 1 Pressurizer Relief Model A,Piping
	ML20212D728
Person / Time
Site:	Davis Besse
Issue date:	05/25/1977
From:	; TELEDYNE ENGINEERING SERVICES
To:	;
Shared Package
ML20212D606	List: ML20212D601; ML20212D728;
References
	1338, E-1495-17, E-1495-17-RA, NUDOCS 8703040186
	Download: ML20212D728 (141)
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{{#Wiki_filter:Docket N2. 50-346 1Lic;nra No. NPF-3 -S3 riel No. 1338 Enclo m e D BECHTEL CORPORATION P.O. B0X 607 15740 SHADY GROVE ROAD GAITHERSBURG, MAP.YLAND 20760 9 !D D TECHNICAL REPORT E-1495-17 REVISION A O DAVIS BESSE NUCLEAR POWER STATION h ASME SECTION III ANALYSIS OF CLASS 1 - PRESSURIZER RELIEF MODEL A, PIPING BOOK 1 0F 2 5' UMc0MTRO SEPTEMBER 14, 1973 (0RIGINAL) MAY 25,1977 (REVISION A) g

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O WT1:1 prTfNE MATERIALS RESEARCH Technical Report E-1495-17. Rev. A D May 25, 1977 3 CERTIFICATION The Pressurizer Relief - Model A - Piping system covered by this Certification is part of Davis Besse Unit No. I at Oak Harbor, Ohio. The Design Specifica-3 tion 7749-it-200 Revis~ ion 3, dated May 5,1977, has been prepared by Bechtel Corporation and certified by Anthony W. Wilk, Professional Engineer, State of Maryland. On the basis of the stress analysis calculations and design drawings set forth in this Stress Report, we certify that to the best of our belief and knowledge J the design of the Pressurizer Relief - Model A - Piping as shown by the draw-ings complies with the requirements for Class 1 piping in Section III of the ASME Boiler and Pressure Vessel Code,1971 Edition, for the design and operat-ing conditions that have been specified by the Owner in the Design Specifica-tion, with the following exceptions or restrictions. ) 1. Bechtel Corporation is responsible for assuring that the following require-ments of the Code are met: a. Design of Welds - tiB-3660 b. Design of Pipe Supporting Elements - NB-3674 Design Requirements Pertaining to Specific Piping Systems - N8-3675 c. 3 2. Analysis and Certification of the flange assemblies: at Pressurizer Safety Valves PSVRCl3-1 and PSVRC-2, Points 935, 940, a. 635, and 640 are based on the fact that these flanges have been in-stalled as 4"-2500 lb. R.F.W.M. flanges (see Bechtel Drawing No. M-230A, i Rev. 7); therefore the 4"-1500 lb. R.F.W.N. flanges specified in Refer-ence 2 have not been evaluated in this report. b. at Pressurizer Relief Valves PSVRC2 and HVRCll, Points 236, 237, 205, 210, 215 and 220 are based on the fact that these flanges have been installed as 2 1/2"-2500 lb. R.F.W.N. flanges (see Bechtel Drawing 9 No. M-230A, Rev. 7); therefore the 2 1/2"-1500 lb. R.F.W.N. flanges specified in Reference 2 have not been evaluated in this report. 3. Analysis and Certification of piping at intermediate anchors PRA-4 and PRA-5, Points 625 and 925, of piping at axial restraint PRH-3, Point 180. 3 4. This Certification is contingent upon the Owner providing trace heating of the Class 1 Piping near Safety Valves PSVRC13-1 and PSVRCl3-2, and the 2

a W1E EDYNE MATERIALS RESEARCH Technical Report E-1495-17, Rev. A O CERTIFICATION (Cont'd) Class 1 Relief Line Piping water loop seal extending to Relief Valve o PSVRC2 to a temperature of 550 F for the safety valve piping and 600 F for the relief valve piping per References 2 and 22. ~ '.s TELEDYNE MATERIALS RESEARCH .'., c,- O / ".C[E i By /mA ,"{ George Moy,[ [ n 2. ua.s ri Registered Professional Engineer , ;. ' :Ill '/ Massachusetts #24236 . t. - 4

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I, , certify that a review of this Stress Report has been conducted and that it satisfies the requirements of the Design Specification. BECHTEL CORPORATION cp By ,, ~, G G O O

Technical Report E-1495-17, Rev. A i 3 RECORD OF REVISIONS TMR Technical Report E-1495-17 (Original) dated September 14, 1973 3 REVISION AND DATE PAGES DESCRIPTION J Addendum 1 New Added analysis and evaluation for NRC February 22,1974 postulated pipe break criteria per Regulatory Guide 1.46 Revision A All Revised NUCPIPE results to include May 25,1977 analysis and certification of inter-mediate anchors, axial restraints, valve flange assemblies and thermal analysis of the loop seals at the C' pressurizer. Revision A document re-1 places Original and Addendum I reports.i i h l O FS 0 i, h c ?

e YM MATERIALS RESEARCH Technical Report E-1495-17, Rev. A D TABLE OF CONTENTS PAGE O

1.0 INTRODUCTION

1

2.0 CONCLUSION

S 2 3.0 DESIGN AND OPERATING CONDITIONS 4 0 4 3.1 Design Conditions 4 3.2 Operating Conditions 9 4.0 ADDITIONAL NRC REQUIREMENTS 10 'a 5.0 FLEXIBILITY ANALYSIS 10 5.1 Hanger Selection and Load Requirements 10

5.2 System Description

18 6.0 THERMAL ANALYSIS '? 18 6.1 Method of Analysis 6.2 Results of Thermal Analysis 38 57 7.0 STRESS ANALYSIS 57 4 7.1 Pressure Design of Components 67 7.2 NUCPIPE Program Input 91 7.3 NUCPIPE Program Results 7.4 Stress Analysis and Code Evaluation of Flange Bolts 98 116 8.0 CODE EVALUATION 116 8.1 Design Conditions 116 8.2 Operating Conditions 116 8.2.1 Normal and Upset Conditions 117 8.2.2 Emergency Conditions 117 8.2.3 Faulted Conditions 117 8.2.4 Testing Conditions 117 8.3 Additional NRC Criteria Evaluation 1 21

9.0 REFERENCES

E) APPENDIX A: TMR DRAWINGS 124 l APPENDICES B - D: MOMENT EXTRACTI 0fl. NUCPIPE COMPUTER SHEETS BOOK 2 AND LION-GEN COMPUTER SHEETS h

D gg Technical Report E-1495-17. Rev. A O

1.0 INTRODUCTION

Bechtel Corporation Agreement for Outside Services dated March 24, C 1972, authorized Teledyne Materials Research (TMR) to analyze the Class 1 Piping for Unit No.1 of the Davis Besse Nuclear Power Station, Oak Harbor, Ohio. O The hanger selection and load requirements for the Pressurizer Re-lief, Model A, System shown on Bechtel Drawing T-230A Revision 2 were presented in TMR Technical Report E-1495-10a (Reference 1). TMR Technical Report E-1495-17 Addendum 1 (Reference 20) reported the results of a O reanalysis of the Pressurizer Relief System because of the postulated pipe break criteria per the directive of Reference 16. The results of TMR Report E-1495-17 Addendum I have been reviewed and validated for all subsequent revisions of Bechtel Drawing M-230A up to and including Re-vision 7. This document (E-1495-17 Revision A) is the Stress Report for the Class 1 Piping of the Pressurizer Relief System - Model A - Piping and includes the heat tracing requirements for the Class 1 piping and the revised thennal analysis addressing the water loop seals in the Class 1 piping at the relief and safety valves. In addition, this re-port contains the Class 1 evaluation of the flange assemblies, axial re-straint pipe attachments and welded ring attachments in the Class 1 piping. rt The Design Criteria consist of: (1) Bechtel Specification 7749-M-200 (Reference 2) 0 (2) Subsection NB-3600 of the ASME Code, Section III 1971 Edition (Reference 3) (3) Babcock & Wilcox Specification CS(F)-3-92/NSS-14 (Reference 4) Q O

TM Technical Report E-1495-17, Rev. A 0

2.0 CONCLUSION

S Based on the results contained in this report and the conditions O specified in the Design Specification, TMR is of the opinion that the design of the Pressurizer Safety and Relief Valve System (TMR Problem No. T-012) satisfies the requirements for Class 1 Piping of the ASME Code, Section III, with the following exceptions or restrictions: O (1) Bechtel Power Corporation is responsible for assuring that the following requirements of the Code are met: a. Design of Welds: NB-3660 q b. Design of Pipe Supporting Elements: NB-3674 c. Design Requirements Pertaining to Specific Piping Systems: NB-3675 3 (2) Analysis and certification of flange assemblies at Pressurizer Safety Valves PSVRCl3-1 and PSVRCl3-2 (Points 935, 940, 635 and 640) are based on the fact that these valves have been installed as 4"-2500 lb. R.F.W.N. flanges. Also,at Pressurizer 3 Relief Valve PSVRC2 (Points 236 and 237) and at Pressure Seal Gage Valve HVRC-11 (Points 205, 210, 215, and 220, the analysis and certification are based on the fact that these valves have been installed as 2 1/2"-2500 lb. R.F.W.N. flanges. Therefore, a the 4"-1500 lb. R.F.W.N. and 2 1/2"-1500 lb. R.F.W.N. flanges specified in Reference 2 are not evaluated in this report. (3) Analysis and certification of piping at Class 1 axial restraint 3 PRH-3 (Point 180) are included in this report. (4) Analysis and certification of piping at Class 1 Welded Ring At-tachments PRA-4 and 5 (Points 625 and 925) are included in this o report. 9

D W TELEDYNE MATERIALS RESEARCH Technical Report E-1495-17, Rev. A ? (5) This certification is contingent upon the Owner providing trace heating of the Class 1 Piping near Safety Valves PSVRCl3-1 and PSVRCl3-2, and the Class 1 Relief Line Piping water loop seal D extending to Relief Valve PSVRC2 to a temperature of 550 F for the safety valve piping and 600 F for the relief valve piping per References 2 and 22. O Satisfaction of the NRC requirements regarding postulated pipe break locations (Reference 15) are included as a part of this report per direc-tive of Bechtel Power Corporation (Reference 16). 9 In addition, TMR is of the opinion that the requirements of the Nuclear Regulatory Commission (NRC) concerning postulated pipe break locations (Para-graph 2 of Reference 15) have been satisfied per the evaluations outlined in Section 8.3 of this report. Piping breaks are postulated to occur at G the following locations which are shown on TMR Drawing DP-1574 Revision 3 in Appendix A of this report. (1) Teminal Ends: Nozzle Points 100, 490 and 790 and Anchor Points 4 625 and 925. (2) Intemediate Locations: Essentially all B.W. returns, elbows, valve / flange junctions and reducers located on the Class 1 Pip-

9 ing of TMR Problem No. T-012.

l 9 I i

TM Technical Report E-1495-17 Rev. A O 3.0 DESIGN AND OPERATING CONDITIONS 3.1 Design conditions v This system was analyzed for the following temperature and pres-sure conditions from the design conditions of Para. 2.14 of the Design Speci-fication (Reference 2). 3 (1) Pressure: 2500 psig (2) Temperature: 670 F (3) Design Mechanical Loads: See Books 1 through 5 of Refer-3 ence 1 for results of weight and seismic and blowdown load-ings on piping components, 3.2 Operating Conditions g The temperature, pressure, and flow rate histogram for the Pres-surizer Relief System - Model A is derived from Babcock & Wilcox Specifica-tion (CS(F)-3-9-92/NSS-14 (Reference 4). The histogram is shown on TMR 3 Drawing BP-1430, two sheets, following this section. The piping from the pressurizer to the relief valves is designed to experience the temperature and pressure variations of the steam com-g partment at the top of the pressurizer. l A thermal schematic flow diagram which includes the components analyzed for the various operating conditions is shown on TMR Drawing BP-3 l 1429 Rev. 1 in Appendix A of this report. The operating conditions' and cycles specified for the Pres-surizer Safety and Relief System in Table I of Reference 4 are presented 3 on page 6. b

TM Technical Report E-1495-17, Rev. A 3 The set pressure of the Pressurizer Safety Valves PSVRC13-1 and PSVRCl3-2 is 2435 psig while the set pressure for the Pressurizer Relief Valve PSVRC2 is 2250 psig. The 2 1/2" Pressure Seal Gate Valve HVRC-ll D is open during normal plant operation. Note that the Design Basis Earth-quake (DBE) is assumed to occur during the reactor trip transient per Reference 5 and that the Loss of Reactor Coolant is a faulted condition per Reference 6. In addition, over-pressurization or blowdown is assumed 3 to occur in the relief piping during normal and emergency conditions when the set pressure of the relief valve is exceeded per Reference 2. Blow-down is assumed to occur in the Safety Relief line during the Reactor Trip per Reference 2. The normal operation of the Pressurizer Safety and Re-D lief Valve Systems is to alleviate the over-pressurization of the pres-surizer when the set pressures of the Relief and Safety Valves are exceeded. Transients listed represent changes in fluid temperature, which result in significant AT's as. described in Reference 7. 3 D f L I l i

P WTm m(NE gL Power and Indntrial MQd Q 8h Specification No. 7749-M-200 Tcchnical Report TABLEI ( E-1495-17 Rev. A DESIGN CONDITIONS REACTOR COOLANT SYSTEM Design pressure, psig 2500 Design temperature, F

For design conditions, the temperature of Pressurizer Relief and Safety System Hot leg 650
i Cold leg 650 is assumed 670 F per Reference 11.

D TRANSIENT DESCRIPTION DESIGN CYCLES FIGURE NO'S NOR3fAL CONDITIONS Heatup and cooldown at 100 F/hr 120 1 A-1, i B-1

~# Heatup at 35 F/hr and cooldown at 100 F/hr 120 1 A-1, I B-1 ~ Power change O to 15% and 15% to 0 1,440 2 A-1, 2B-1 Power loading 8% to 100% power 48,000 3-1 Power unloading 100% to 8% power 48,000 4-1 n 10% step load increase 8,000 5-1 10% step load decrease 8,000 6-1 3 UPSET CONDITIONS Step load reduction (100% to 8% Power) 310 7-1 Reactor trip (types A-40, B 160, and C-88) 288 8-1, 8-4, 8-7 Rapid depressurization 80 9-1 Loss of station power and reactor trip 40 15-1 Rod withdrawal accident and reactor trip 40 11-1 0 Control drop 40 14-1 E5f ERGENCY CONDITIONS Loss of feedwater to one steam generator and reactor trip 20 17A-1 0 Stuckspen turbine bypass valve an ' reactor trip 10 17B-1 Change of flow 20 10-1 FAULTED CONDITIONS O Steam line failure and reactor trip 1 16-1 Loss of coolant and reactor trip (LOCA)** I 21-1 TEST CONDITIONS Hydro 3tatic Test 11eactor Coolant System 20 (3765 psig,135 F) 1 Pressurizer Relief Valve Piping (CCA-8) G (3810 psig,135 F) 20

- LOCA is considered an Upset Condition, or equivalent, but this system is not er. a 4

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TTELEENNE o MATERIALS RESEARCH Technical Report E-1495-17, Rev. A O 4.0 ADDITIONAL NRC REQUIREMENTS Per the directive of Reference 16 this system was analyzed to the follow-ing NRC requirements (Reference 15) concerning postulated pipe breaks: ASME Section III Code Class 1 Piping breaks should be postulated to occur at the following locations in each piping run or branch run: O (1) terminal ends; (2) any intermediate locations between terminal ends where the O primary plus secondary stress intensities Sn(circumferential or longitudinal) derived from an elastic analysis under the loadings associated with one-half safe shutdown earthquake and operational plant conditions exceeds 2.0 S for ferritic m o steel and 2.4 S f r austenitic steel; m (3) any intermediate locations between terminal ends where the cumulative usage factor (U) derived from the piping fatigue analysis and based on all normal, upset, and testing plant conditions exceeds 0.1; and (4) at intermediate locations in addition to those determined by (2) 8 and (3) above, selected on a reasonable basis as necessary to provide protection. As a minimum, there should be two intermediate locations for each piping run or branch run. 0 0 S Apert:re Lara
TM MATERIALS RESEARCH Technical Report E-1495-17, Rev. A O 5.0 FLEXIBILITY ANALYSIS 5.1 Hanger Selection and Load Requirements G These requirements were reported in TMR Technical Report E-1495-10a (Reference 1). The analysis procedures contained in methods report E-1495-1 Revision A (Reference 7 ) describe how the ADLPIPE and 9 STARDYNE Computer Programs (References 8 and 26) are used.
5.2 System Description
D The Pressurizer Safety and Relief Valve Piping, Model A, TMR Problem T-012, is shown on Bechtel Drawings T-230A Revision 2, and on TMR Orawings CP-1575, presented in report E-1475-10a. TMR Drawing DP-1574 Revision 3 given in Appendix A of the report shows the.ASME Section III nodes for this system. The thccmal flexibility runs for the Pressurizer Safety and Relief Valve Systems are outlined on the five flexibility sheets which 4 follow. Only the most severe of Conditions IV, VI, VII, VIII, and IX need Le investigated. The function of the Pressurizer Safety and Relief Valve System P is to relieve the over-r essurization of the Pressurizer. Under normal operation, the pressurizer water level represents a balance of water flow into the Reactor Coolant System and water letdown flow into the Chemical dnd Volume Control System. Therefore, when tne water level begins to change f within the Pressurizer, there exists an unbalance of in and out water flow conditions. The pressurizer is equipped with two sets of relief valves. Safety valves PSVRCl3-1 and PSVRCl3-2 are Code required mechanical safety valves set at design pressure. The second set is composed of motorized 3 relief valve PSVRC2 set at slightly lower pressure and responding to a pressure signal instrumentation system. The relief valve effluent, which I Q
)
W TELEDYNE MATERIALS RESEARCH Technical Report E-1495-17. Rev. A. O is radioactive, is caught in a relief tank filled with quench water and cooled. The relief valves prevent the safety valves from lifting during step load reduction transients. D Intennediate pressure seal gate valve HVRC-ll is open during normal operation and facilitate the accessibility of relief valve main-tenance during shutdown. During normal operation, the Pressurizer 8 Safety Valve system does not experience any flow conditions. System functions and descriptions are taken from References 24 and 25. A sunnary of the latest Bechtel drawings reviewed is given 0 on the following page. 4 O 3 2 U
W TN5TVNE J MATERIALS RESEARCH Technical Report E-1495-17 Rev. A 3
SUMMARY
OF REVISIONS REVIEWED 3 BASIS OF li1R TMR BECHTEL REVISION REVIEWED BECHTEL REVISION OPINION OF NO PROBLEM NO. IN FLEXIBILITY ANALYSIS REVIEWED BY TMR MATERIAL EFFECTS a T-012 M-230A Rev. 1 Reviewed M-230A and Issued in TMR Hanger Revision 7 No chaages af-Report E-1495-10a as fecting analysis T-230A Rev. 1 0* b fe il 2 P D
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O WM MATERIALS RESEARCH Technical Report E-1495-17, Rev. A C 6.0 THERMAL ANALYSIS 6.1 Method of Analysis o A simplified and a detailed themal analysis as described in Paragraphs 5.1 and 5.2 of Reference 7 were used to determine the AT-values for the ASME Code, Section III, analysis of the Pressurizer Re-y" lief System. The thermal components for this system were analyzed with respect to TMR Histogram BP-1430, and are shown on TMR Drawing BP-1429 Rev.1 in Appendix A. The thermal components are described as follows: O Component Description C-1 Refers to all straight pipe and elbows and all girth butt weld junctions on the 3" CCA-8 line. O C-2 Refers to all straight pipe and elbows and all girth butt weld junctions on the 6" CCA-8 lines. C-4 Refers to the body of 4" x 6" Schedule 160 butt welded reducer. O C-6 Represents the junction of 3" Schedule 160 pipe to the 3" Schedule 160 Pressurizer Relief Line. The 3" Schedule 160 pipes are stanchions for the axial restraint at Point 180. Thermal gradients for this component, with the ex-g ception of T -T, are obtained from a one-dimensional LION a b model (as described in Paragraph 5.2.2 of Reference 7 ). The T -T infomation is obtained in a separate analysis a b given on calculation sheets 4 thru 13,following. g C-6 Represents the neck region of a 2 1/2" 2500 lb. RFWN flange. The necessary thermal stresses required for the Section III evaluation were extracted from Reference 27. O C-7 Represents the body region of a 2 1/2" 2500 lb. RFWN flange. The necessary thermal stresses required for the Section III evaluation were extracted from Reference 27. 'O
) TM MATERIALS RESEARCH Technical Report E-1495-17, Rev. A. 3 Component Description C-8 Represents the neck region of a 4" 2500 lb. RFWN flange. The necessary thennal stresses required for the Section D III evaluation were extracted from Reference 27. C-9 Represents the body region of a 4" 2500 lb. RFWN flange. The necessary thermal stresses required for the Section III evaluation were extracted from Reference 27. 3) C-10 Represents Anchors PRA-4 and PRA-5, shown on calculation Sheets 14 thru 16. following, Thennal gradients for these components were obtained from two (2) one-dimensional LION O models. C-ll Represents all straight piping components, reducers and elbows in the heat traced 3" Schedule 160 piping. AT values were obtained from 3" Schedule 160 L-GRID model a of 3" Schedule 160 stanchion. C-12 Represents all straight piping components, reducers and elbows in the heat traced 6" Schedule 120 region of Safety 2p Relief Lines. aT values were obtained from 6" Schedule 120 L-GRID model of anchor ring restraint, thermal com-ponent C-10. Operating conditions for the Pressurizer Safety and Relief Valve g System are described in Section 3.2 of this report. A study of the thermal histogram BP-1430 indicates that the Pressurizer Safety and Relief Valve System experiences flow whenever the set pressures of the relief and safety valves are exceeded. The set pressures of the Pressurizer Relief and 3 Safety Valves are 2250 psig and 2435 psig, respectively per Reference 2. At the time the set pressure is exceeded the Pressurizer Relief System is assumed to experience an injection of 650 F steam. In the case of the j Safety Relief System, a temperature excursion of 670 F steam is assumed, l l P 1 1
3. TM MATERALS RESEARCH Technical Report E-1495-17, Rev. A 3 During normal operation, it is reasonable to assume that steam will rise from the Pressurizer and cause the piping from the inlet nozzles attached to the Pressurizer to the top of the vertical rise to reach the D nonnal operating temperature of 600 F. This region is herein referred to as the heat effective zone of the Pressurizer. For the piping beyond the vertical rise, the temperature decays and it can be shown that the steady-state tempertture of Safety Valves PSVRCl3-1 and PSVRC13-2 during normal D operation is 120 F. For the Relief Valve piping, it is shown that the steady-state temperature decays to 120*F at Relief Valve PSVRC-2. Thus, the piping and fittings which lie well beyond the heat effected zone of the Pressurizer could potentially experience a step change in temperature 9 from 120 F to 650 F in the Relief Line piping and 120 F to 670*F for the Safety Line piping. This temperature distribution is a result of the slug of water O which is assumed to occur when the saturated steam condenses at the top of the vertical rise, and fills the downward run with water. This would occur in the 3" CCA-8 and 6" CCA-8 piping of the Relief Valve Lines. A preliminary analysis found the stress intensities which resulted from these 9 severe thermal loadings to be unacceptable. Thus, TMR requires that trace heating be used to raise to 600 F the steady-state temperature of the Re-lief Valve Piping from the downward run of the 3" CCA-8 to Relief Valve PSVRC-2, inclusive, and to 550 F from the downward run of the 6" CCA-8 of 3 the Safety Valve Piping to Safety Valves PSVRC13-1 and PSVRCl3-2, inclusive, as shown on the calculation sheet 1, following, (from Reference 22). Com-ponents in this system, therefore, experience the following thermal transient: Relief Valve Line Safety Valve Line 650 F 670 F S 600 F 550 F iB a
J WTELED(NE MATERIALS RESEARCH Technical Report E-1495-17, Rev. A 9 The piping components upstream of the heat effected zones were analyzed to experience the temperature excursions of the pressurizer vessel. A simplified analysis as described in Paragraph 5.1 of Refer-3 ence 7 has been perfonned on the more severe transients for the com-ponents in the system. Fluid temperature difference values were applied for the remaining transients. b Transients on THR Histogram BP-1430 which have very slow rates of change (<100 F/hr) produce no significant AT values. It is assumed that temperature variations of the Pressurizer which occur when there is no flow in the Safety and Relief Yalve Piping are experienced by those components within the heat effected zone only. A simplified analysis has been done on transients T-1, T-2, T-3, T-7, T-8 and T-17 (see Drawing BP-1430), reducing the fluid tem-perature difference values for all components C-1 through C-4 in the heat effected zone. The fluid temperature difference values are applied for the remaining transients. The table on Sheet 2, following, lists the type of material, the Biot number, and the discontinuity ratio (b/a) for each component type. Sheet 3 shows the complete tabulation of the reduction of fluid temperature differences by use of the simplified analysis (Reference 7) for the appropriate transients for each component. A detailed thermal analysis has been performed for components C-5 through C-10 which are subject to the excursions of the Pressurizer S Safety and Relief Valves. These components are located in the areas of piping where water slugs are formed and heat tracing of the piping is required. The thermal models for Components C-5 through C-10 appear on calculation sheets 4 through 16, following. b
3 WTELEDfNE ENG#dEERNG SERVICES b2 h DATE Ib D hfo I OF IIe sv SHEET NO. c.u,..,tes o m,2 n, m . c t a=. -n x D 7R E%%VRi ?.ER NEUEF 9/STt'54 - CLA% b %j ~ fd %, %k k % :- x @'c e /fy;g..G *g% 3 '., l~5 c a '94 )/ - '(. t s y ',. g - f) \\ ,/ 4 N ,,/' ~' / b g' U, j 4 9 /; ,'t s. 'J'p,, ,/ g I / f' ' ME*5'E.ORI T.ER, l 4' i 3 1 I NEAT WAC IN G lt PROVIDEC O M w 6. PIP 1M G i I W hic H \\t 9 ARAU E LED P N THE T;;c T"i EQ WOEb a i \\WDiC ATED 'TH E A Ga C N E. SME T C i i. D l HEAT TaAct R t o utR n A cc4T s rca v.tute Lioc P IPt k) G Aet E 600*F. HEAT TRACE RE GuirR e sat 91 t FA SAFE P/ U uE P tD t u G /W.E 550*F. a l9
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- M-o WTA N ENGNEERNG SERVICES b my NN I!I2h~I s0MT NO. OF DATE N9 5 - I //- cano.sv U DATE 5 I'Il PROA. No. g-AY,t AL. 3ESTR A\\wT ON Mf:tCitbRi?_Cr.L "NEU E.F '_Jitat: PRH 6 O THE ' PURPOSE OF THns Ataru.Ns\\ s \\":, To OET;.:t.ta n JE T \\E t\\tT ER t-;t yE 'ta MEAN) 'T EMPER A TOR E, M T u gcta tuc- '5" Sc M.\\t::o 'Pe r r.o e.7_d A RELsEE vatcE. ANO E" scK. g G,o PlPES OStD RL 1TNJC HidM Y rP 90VQ. 9 THE. METHOD OF /sb ACf *5it W\\LL BE SYMi\\ N '. T.3 'TMAT OW LNCD ito DE.*t M L 'ta "T ECH ro t cA.L REPORT E \\495 - \\ 4 REM. A, 'bEC AY HEAT REMo4AL 5WT En4 THE D ETML 5 Howu f%ELOW (1 TAKEQ VFct4 D PACRTEL \\M tJ GT.F. iWMT t'E U\\tL 'i 14C)- M- \\9 0 -irdy..)-TI-y. iWM tw RC6' 30 - CL A.-S - H 2, $go c H \\- t$ct A REV. F2 THE 55" tcH I6o C.C A-8 u ut. t Y SCH 1(oo SThuc Wcto MC "YT N A C D 5 T E.C L, 2 l , l' -O" ~ 02 .QC I ic *~ . g '. t vy ~:.. p..:..,. :- MV j ;., / ,g% .y ya L._ N y
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C' y MATERIALS RESEARCH Technical Report E-1495-17, Rev. A 3, 6.0 (Cont'd) 6.2 Results of Thermal Analysis O The operating conditions specified in Section 3.2 of this re-port have produced up to 26 stress conditions for components C-1 through C-12 as listed on Pl-Forms 1-20, following. These conditions were used o as input to the NUCPIPE program for stress analysis and fatigue evalua-tion. Calculations sheet 9 lists the stress conditions analyzed O representing the specified operating conditions for thermal components C-1 through C-4. e ib it t.4 h 9 /
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gg UPSET CONDITIONS Step load reduction (100% to E Tb 09 8% power) (310) m Q 10, Q u Q 10, Q H g 6 and -88) 88 Rapid Depressurization (80) II. TS Q 12. Q 12. W Tl3 , Q 20,Q 21 Q G,QuiG r act t 0 Rod withdrawal accident and I M W5M reactor trip (40) f Control drop (40) g "lE. Tit Ql7,Ql6 O l'7 Q i6 EMERGENCY CONDITIONS Loss of feedwater to one stm. gener. & react. trip (20 N II5 Tlb DO b i i i viv r ctor er p 0 k; Change of flow (20) E Tc),710 Qt3,Qi4 Qll,Qi4 l FAULTED CONDITIONS Steam line failure 6 rear. Lor trip (1) Loss et coolant and reactor trip (1) M
~~The 115,746 cycles for Normal Operacion represent at least the total possible excursions f rom normal operating pressure or temperature for this system.~~
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O gg MATERIALS RESEARCH Technical Report E-1495-17, Rev. A o 7.0 STRESS ANALYSIS 7.1 Pressure Design of Components (Reference 3, Paragraph NB-3640) O (1) NB-3641.1 - Straight pipe under internal pressure - Minimum wall thickness requirements satisfied on calculation sheets 1-4 following. O (2) NB-3641.2 - Straight pipe under external pressure - No external pressure has been specified. (3) NB-3642.1 - Pipe bends - It is assumed that fabrication techniques result in minimum wall thickness af ter bending. a There are no pipe bends specified for the Class 1 piping of this system. (4) NB-3642.2 - Elbows - Purchased to ANSI B16.9 from Table '} NB-3691.1; hence, minimum thickness requirements are met. (5) NB-3643 - Intersections - Purchased to ANSI B16.9 and B16.11 from Table NB-3691.1; hence minimum thickness requirements are met. See NB-3643.3, following. g (6) NB-3643.2 - Branch Connections - Fittings purchased to ANSI B16.9; hence, requirements for compensation are met. (7) NB-3643.3 - Reinforcement for Openings - (Fabricated branch O connections) - The:e are no fabricated branch connections specified for thie system. (8) NB-3644 - Miters - There are no miters specified for the Class 1 Piping. (9) NB-3654 - Attachments - Attachments included in this report, shown on TMR Drawing DP-1574 Rev. 3 in Appendix A, are as follows: s (a) Intermediate anchor PRA-4 and PRA-5, Points 625 and 925 (see sheets 5 and 6, following). (Reference 29) (b) Axial restraint PRH-3, Point 180 (see sheets 7 and 8, following). (Reference 21) O
O YM Technical Report E-1495-17, Rev. A 0 (10) NB-3646 - Closures - Purchased to the standards listed in Table NB-3691.l; hence, minimum thickness requirements are met, if specified. G (11) NB-3647 - Pressure Design of Flanged Joints and Blanks - Purchased to ANSI B16.5 from Table NB-3691.1; hence, minimum thickness requirements are met. e (12) NB-3648 - Reducers - Purchased to ANSI B16.9 and B16.11 from Table NB-3691.1; hence, minimum thickness requirements are met. 3 G f G 3 cu i 1
3 - 93_ sy %f E-K urg f [ I 5 aMERT No. g ,g 7-7 D-73 Minimum Wall Thickness / 4 #)A -/7 m me, Calculations q */ z (C/)- 8 3 All calculations reference Section III of ASME Boiler and Pressure Vessel Code, 19 71 (NB-3641.1) for Class 1 piping. PD Equation (1) t, pg, p) = + a 3 where: nominal pipe size: 82_ (inches) /bO pipe schedule: 3 pipe material: ib$ ~ 3 7[O, TR 3 / 6 nominal pipe wall thickness: . 3 Y [ (inches) design temperature: G70 r M L = outside diameter of the pipe:
2. b Y [ (inches) a = an additional thickness to: (1) compensate for material removed in threading, (2) provide for corrosion and/or erosion, and (3) to provide for structural strength of the pipe during crection:
C (inches) 9 P = internal design pressure: 2 5 0 0 (psi) S = maximum allowable stress in material caused by internal pressure at design temperature: / ro + 8 O (psi) See Reference Appendix I, Table I O l y =.4 t = the minimum required wall thickness: 2 C b (inches) .2Cb + 0 . 2 O (o (inches) = 3 Evaluation: The nominal pipe wall thickness 3 Y [ s h. less manuf acturer's tolerance on wall thi nness (approximately 12.5%) . O 4 7 /r, which equals . 3 2 8 i.,. is greater i
~~.han the minimum required wall thickness (tm)~~
. 2 O (o for the stipulated l design pressure and design temperature. Therefore, minimum wall thickness l requirements of Paragraph NB-3641.1 are satisfied, b l l TELEDYNE MATERIALS RESEARCH l ENGINEERS WALTHAM, MASSACHUSETTS 1
o' . 2 g syz6//JA/ mm / 2-/ 5~-72 emer no. or ynga, no. / /@I" /7 ,p g g,/2./g.jg Minimum Wall Thickness l Calculations 3 "CCA - 8 C All calculations reference Section III of ASME Boiler and Pressure Vessel Code, 19 71 (NB-3641.1) for Class 1 piping. PD Equation (1) t = + a pg, p) O where: nominal pipe size: 2 (inchas) pipe schedule: /C O '9 pipe material: .................. 3A - 3 7 k 7h 3 / IO nominal pipe wall thickness: . V 38 (inches) cesign temperature: 67O 'F 0 D, = outside diameter of the pipe: 7, [ (inches) a = an additional thickness to: (1) compensate for material removed in threading, (2) provide for corrosion and/or erosion, and (3) to provide for structural strength of the pipe during erection: O (inches) 9 P = internal design pressure: 2 5"dC (psi) S maximun allowable stress in caterial caused by a internal pressure at design temperature: / 6 4 0 C (psi) See Reference Appendix I, Table I y= .4 t = the minimum required wall thickness: .2TO (inches) m .250 + o ,25o cinene,) y = I Evaluation: 1 Tne nominal pipe wall thickness. Nb / t less manufacturer's tolerance on wall l. thidness (approximately 12.5%) o rG r> which equals. 3 8 3rrf is greater PI the the minimum required wall thickness (tm) /2604'1 for the stipulated l aesign pressure and design temperature. Therefore, minimum wall thickness requirements of Paragraph NB-3641.1 are satisfied. I l TEl.EDYNE MATERIALS RESEARCH h { ENGINEERS WALTHAM, MASSACHUSETTS L
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~~' S I 4 W"~ I~7 8""q g.y Minimum Wall Thickness pn0J.100.~~
N" Calculations 4 " CC A - O 9 All calculations reference Section III of ASME Boiler and Preseure Vessel Code, 19 71 (NB-3641.1) for Class 1 piping. PD Equation (1) t, gg, p) + a = O where: nominal pipe size: i (inches) pipe schedule: l ~2 C pipe material: 34 - 3 7Io 3 TP 3/Io nominal pipe wall thickness: .Nb (inches) design temperature: GVO r 3 D = outside diameter of the pipe: Y[ (inches) a = an additional thickness to: (1) compensate for material removed in threading, (2) provide for corrosion and/or erosion, and (3) to provide for structural strength of t'e pipe during erection: O (tuches) n m P = internal design pressure: 2500 (psi) S = maximum allowable stress in material caused by internal pressure at design temperature: / 6 480 (psi) See Reference Appendix I, Table I P y=.4 t = the minimum required wall thickness: .322 (inches) 321 + C . 3 2 E (inches) = = Evaluation: The nominal pipe wall thickness Y 3 b e'n.less manuf acturer's tolerance on wall thickness (approximately 12.5%) . O E S' : n. which equals 3 8 3,'n.is greater than the minimum required wall thickness (tm) 32 2 !h. for the stipulated design pressure and design temperature. Therefore, minimum wall thickness requirements of Paragraph NB-3641.1 are satisfied. AD l TELEDYNE MATERIALS RESEARCH k ENGINEERS WALTHAM, MASSACHUSETTS i t
O . 4 g myffOA/ m a n - N-72 m **- can.svJFK mn /2-/f 72. Minimum Wall Thickness peoA No. / M O f ~ ~ / 7 Calculations (,'CCA-6 O All calculations reference Section III of ASME Boiler and Pressure Vessel Code. 19 71 (NB-3641.1) for Class 1 piping. PD Equation (1) t = + a g3, p) where: nominal pipe size: b (inches) pipe schedule: /2O pipe material: .................. 8A - 3 76, 77# 3/Io nominal pipe wall thickness: 5 ~(o 2 (inches) design temperature: (o 7 C 'F 0 outside diameter of the pipe: [s.[s 2 [ (inches) D = a = an additional thickness to: (1) compensate for material removed in threading, (2) provide for corrosion and/or erosion, and (3) to provide for structural strength of the pipe during erection: O (inches) P = internal design pressure: 2 5 0 O (psi) S maximum allowable stress in material caused by = internal pressure at design temperature: /446O (psi) See Reference Appendix I, Table I ) y =. :. the minimum required wall thickness: , V 7h (inches) t o o W h b ,kb (inches) + = ,) l Evaluation: 1 1 The nominal pipe wall thickness. (>t. m //1 less manufacturer's tolerance on wall em thickness (approximately 12.5%) . A*/,)/ which equals "7' S' 2 r a is greater I. tnr.n the minimum required wall thickness (tm) M 74 n for the stipulated / design pressure and design temperature. Therefore, minimum wall thickness requirements of Paragraph NB-3641.1 are satisfied. .) l TELEDYNE MATERIALS RESEARCH p ENGINEERS WALTHAM, MASSACHUSETTS l t L L
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TN MATERIALS RESEARCH Technical Report E-1495-17, Rev. A 9 7.0 STRESSANA'.YSIS(Cont'd) 7.2 NUCPIPE Program Input O The Section III model for the Pressurizer Relief, Model A, System is shown on TMR Drawing DP-1574 in Appendix A. The flexibility moments (including deadweight, blowdown, thermal, seismic inertia and end effects) are extracted from the computer runs of Reference 1 (TMR Report No. E-1495-10a), and are combined to give the greatest stress range. They are summarized on the moment calculation sheets given in Appendix B (Book 2). By Bechtel directive, the DBE is used for design in the Nuclear Class 1 piping; therefore, for Section III analysis, all DBE values of seismic moments are used. Thermal values, including AT's outlined in Section 6.0 of this report, associated with the applicable stress conditions along with the pressure and number of cycles for each stress condition, are input to the NUCPIPE program. The hydrostatic test condition outlined in References 10 and 11 l h is included as a stress condition in the Section III analysis. l l All significant stress points for the Class 1 piping of the Pres-surizer Relief, Model A, Class 1 piping which experience the worst themal gradients and which have the highest stress indices are analyzed using the NUCPIPE program. Nodes 610, 850, and 910, elbow to elbow buttwelds, are analyzed by multiplying toget.her the stress indices for a butt-welding elbow and an "as welded" girth butt weld per footnote 11 from Table NB-3683.2-1 of Reference 3. Calculation sheet 1, following, shows the com-l putation for these indices. l h i
1) pg MATERIALS RESEARCH Technical Report E-1495-17, Rev. A ') A preliminary NUCPIPE run indicated Equation 9 failures occurring at points 493, 627, and 793, 4" x 6" Schedule 120 reducers. This problem has been resolved by changing all the 4" x 6" reducers to Schedule 160 (References 11 and 12) with the ends machined to Schedule 120. These 4" x 6" Schedule 160 reducers are analyzed by using three nodes for each reducer. A node at each end is input using the moments and geometry (Schedule 120) applicable at each end, and is analyzed as a girth butt weld. A node at the body of the reducer (Schedule 160) is input according to the rules of NB-3683.1(C), and is analyzed as a butt welding reducer. Nozzle attachments are analyzed specifically at nodes 100, 490, and 790. It is assumed that no discontinuities exist on the pressurizer nozzles for at least a distance of M from the end. It is also assumed that no discontinuities exist for at least a distance of E from the ends of the 4" 2,500# RFWN flanges, at flange to reducer butt weld junctions, q The flexibility moments for the additional points of analysis on the Pressurizer Relief line (axial restraint and flange points) were obtained by conservatively extracting maximum moments from the analysis ,3 provided in TMR Report E-1495-10a for nearby points. In addition, the anchor points for the Safety Relief lines (data points 640 and 940) were relocated by Bechtel to the 6" Schedule 120 piping below the safety valve as indicated by Bechtel Drawing C-666 Rev. 2. Moments for the new anchor 9 ring locations (data points 625 and 925) were conservatively taken from the original anchor locations (data points 640E and 940E). Moments for the data points downstream of the new anchor ring locations were extracted from the downstream side of the old anchor locations, data points 640B and 9408. The flexibility moment extractions and combinations are suninarized on calculation sheets 12 through 17, following. Moment extractions for data points of the Pressurizer Relief piping; with the exception of data points 178,179 and 180, appear in Book 2 of this 16 In addition, the moment extractions of data points within the loop report. seals, but upstream of anchor points 625 and 925, and those within the heat af-fected zone of the Pressurizer Safety Piping appear in Book 2 of this report. O
f~ O WTELED(NE MATERIALS RESEARCH Technical Report E-1495-17, Rev. A O Calculation sheet 7 gives the stress indices for full anchors PRA-4 and PRA-5, Points 625 and 925, to pipe junctions. The method of detennining these indices is presented in TMR Technical Report E-1495-18 O (Reference 14). Conservative methods at the ring to pipe junction due to the axial thrust loads on the ring are shown on sheets 8 throught 12. These moments are combined with existing seismic moments on sheets 12 through 17, and are input to the NUCPIPE program. O Special stress indices were computed for the Class 1 pipe stanchion PRH-3 (Point 180) as shown on calculation sheets 2 and 3, following, using the Reference 14 procedure. In addition, moments at the stanchion to pipe O junction due to axial thrust loads on the ring are shown on calculation sheets 4 thru 6. In order to analyze all the elbows in the system for postulated 4 pipe break, it was necessary to extract the appropriate thermal flexibility moments from the computer runs of TMR Report No. E-1495-10a (Reference 1) and combine them with their relative deadweight, blowdown, seismic inertia and seismic end effect moments. The maximum thermal plus seismic plus blowdown (if applicable) moments from either end of elbows are applied at the crotch of the elbow. In the evaluation for postulated pipe break the primary plus [ secondary stress intensity values are obtained from each stress condition l taken with zero stress condition, and not from ranges of load set pairs l of stress conditions. N The normal procedure for seismic analysis is to input 288 cycles of plus and minus earthquake (DBE) with the reactor trip transient to the NUCPIPE program along with the other operating conditions. This is a l very conservative approach as actually there is only one earthquake event with 200 stress cycles called for (TMR has added 88 cycles of reactor l l
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0 'PPTELEDYNE MATERIALS RESEARCH Technical Report E-1495-17 Rev. A O trip transient to the 200 stress cycles). Therefore, for a less conser-vative analysis the following three steps are done to arrive at a tota 1 value of cumulative usage factor for a point. 9 . ) (1) Input 1 cycle of expansion plus and minus seismic moments (inertia plus end effects) to the program. 0 (2) Input 287 cycles of conditions with expan-sion moments only to the program. O (3) Calculate the usage factor for 287 stress cycles of plus and minus seismic (DBE) moments only, acting with themselves, and add this usage factor to that given by the computer, re-3 sulting in a total cumulative usage factor for a point. The following points in the Class 1 piping of the Pressurizer I$3 Relief System have been analyzed to the requirements of NRC Regulatory Guide 1.46 (Reference 15) for postulated pipe break and Section III re-requirements, including stress and fatigue evaluation. h' Thermal Point No. Component -Description 100 C-1 PRA-1 nozzle to 3" Schedule 160 butt welded pipe junction. 107 C-1 3" 90 long radius elbow CCA-8 123 C-1 3" 90. long radius elbow CCA-8 137 C-1 3" 90 long radius elbow CCA-8 o )
D PTELEDYNE MATERIALS RESEARCH Technical Report E-1495-17, Rev. A ' J - (, Thermal Point No. Component Description o 153 C-1 3" 90 long radius elbow CCA-8 167 C-11 3" 90 long radius elbow CCA-8 178 C-11 3" Schedule 160 pipe at axial stanchion restraint G 179 C-ll 3" Schedule 160 pipe at axial stanchion restraint 180 C-5 3" Schedule 160 pipe stanchion, 3" Schedule 160 pipe junction (see sheet 3 for special stress in-dices) O J 195 C-11 2-1/2" x 3" reducer to 3" Schedule 160 pipe June-tion 200 C-l l 2-1/2" x 3" reducer to 2-1/2" 2'500# RFWN flange rc junction 205 C-6 Neck region, Section 1, of 2-1/2" 2500# welding neck flange attached to valve HVRC-ll (see Reference 19 for special stress indices) 210 C-7 . Body region, Section 2, of 2-1/2" 2500# welding neck flange attached to valve HVRC-ll (see Reference 19 for special stress indices) 0 233 C-ll 3" 90 long radius elbow CCA-8 236/or C-6 Neck region, Section 1, of 2-1/2" 2500# welding neck 220 flange attached to valve PSVRC-2 (see Reference 19 for special stress indices) 0 237/or C-7 Body region, Section 2, of 2-1/2" 2500# welding neck I flange attached to valve PSVRC-2 (see Reference 19 for special stress indices) a 490 C-2 PRA-7 nozzle to 4" x 6" reducer junction (4" schedule 120 nozzle) C
O QM MATERIALS RESEARCH Technical Report E-1495-17, Rev. A o Thermal Point No. Component Description 493 C-4 Body of 4" x 6" Schedule 160 reducer O 495 C-2 4" x 6" reducer to 6" Schedule 120 pipe junction 503 C-2 6" 90* long radius elbow CCA-8 517 C-2 6" 90* long radius elbow CCA-8 O 533 C-2 6" 90* long radius elbow CCA-8 543 C-2 6" 90* long radius elbow CCA-8 567 C-2 6" 90 long radius elbow CCA-8 4 587 C-2 6" 45* long radius, rolled elbow CCA-8 603 C-12 6" 45 long radius, rolled elbow CCA-8 610 C-12 6" 45 long radius rolled elbow to 6" 90 long O radius elbow butt weld 617 C-12 6" 90 long radius elbow CCA-8 625 C-10 Pipe anchor PRA-4, full penetration welded ring to 6" Schedule 120 pipe (see sheet 7 for special S stress indices) 626 C-12 4" x 6" reducer to 6" Schedule 120 pipe junction 627 C-12 Body of 4" x E' 's..hedule 160 reducer 4 630 C-12 4" x 6" ret M r s 4" 2500# RFWN flange butt welded junction 635 C-8 Neck region, Section 1, of 4" 2500# welding neck flange attached to valve PRVRCl3-2 (see Reference 19 for special stress indices) 640 C-9 Body region, Section 2, of 4" 2500# welding neck flange to valve PRVRCl3-2 (see Reference 19 for g, special stress indices) 790 C-2 PRA-3 nozzle to 4" x 6" reducer junction (4" Schedule 120 nozzle) O
TM MATERIALS RESEARCH Technical Report E-1495-17. Rev. A O Themal Point No. Component Description 793 C-4 Body of 4" x 6" Schedule 160 reducer 0 795 C-2 4" x 6" reducer to 6" Schedule 120 pipe junction 803 C-2 6" 90 long radius elbow CCA-8 817 C-2 6" 90* long radius elbow CCA-8 833 C-2 6" 90* long radius elbow CCA-8 843 C-2 6" 90* long radius elbow CCA-8 850 C-2 6" 90* long radius elbow to 6" 90* long radius elbow 0 butt weld 867 C-2 6" 90 long radius elbow CCA-8 887 C-2 6" 45' long radius rolled elbow CCA-8, a 903 C-12 6" 45* long radius rolled elbow CCA-8 910 C-12 6" 45 long radius rolled elbow to 6" 90 long radius elbow butt welded O 917 C-12 6" 90* long radius elbow CCA-8 925 C-10 Pipe anchor PRA-5, full penetration welded ring to 6" Schedule 120 pipe (see sheet 7 for special stress indices) 4 926 C-12 4" x 6" reducer to 6" Schedule 120 pipe junction 927 C-12 Body of 4" x 6" Schedule 160 reducer 930 C-12 4" x 6" reducer to 4" 2500# RFWN flange butt welded g junction 935 C-8 Neck region, Section 1, of 4" 2500# welding neck flange sttached to valve PRVRC13-1 (see Reference 19 for special stress indices) 940 C-9 Body region, Section 2, of 4" 2500# welding neck flange to valve PRVRC13-1 (see Reference 19 for special stress indices) O
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3 W TELEDYNE Technical Report E-1495-17, Rev. A O 7.0 STRESS ANALYSIS (Cont'd) 7.3 NUCPIPE Program Results 9 The computer results from the NUCPIPE run are sumarized in the tables on Sheets 1 through 5, following. Sheets 1 through 5 give the Class 1 stress and fatigue results for ASME Code Section III evaluation O which include the results for postulated pipe break considerations to requirements of the NRC. The Code and NRC criteria evaluations are pre-sented in Section 8.0 of this report. Calculation sheet 6, following, illustrates that there is no additional usage factor due to 287 cycles of seismic stress acting with themselves for analysis Point 180. O The complete NUCPIPE computer output is included in Appendix B, Book 2 of this report. TMR Technical Report E-1495-1 (Reference 7) contains a general O description of the NUCPIPE method of analysis. 4 (? 3 0
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~~-DEN 0TES THAT THE SIMPLIFIED ELASTIC-PLASTIC. ANALYSIS IS REQUIRED TO MEET THE PRIMARY PLUS SECONDARY STRESS INTENSITY RANGE,MD THAT THE REQUIRMENTS OF EQUATIONS 12 AND 13~~
( NS-3653.6 ) HAVE TO BE NET. i 14 O'T E (l') E%CCEDS ALLOWAiEC 07 ?.4% FOR NRC 90STVLATG.D P\\P E T'S*.'.:Ait CR \\T L FL i A N 3T- (?.') 'iG. 9 : E Q. 9 EW62.GDC/ R'd.*WLTL ; ME. MOM C NTL V 'i'ib F G P. %QT'i s l
a "RTFI FDYNE ENGINEERING SERVICES 5 0F av D H DArm Sll7 h7 SHEET NO. E I"S'U ^ DATE E " N /7 ga5sWt EC-R ELicF ""'d " - cxxo.aY 9 $U M M ARM TABLE OF WDCPtPE R E'LO L7 % PO\\NT og S MAX /Psil 3b l.P50 'k r B 24720 %6 liS59 59995 4%Oo N /A .0015 O) gg 35808 3 9E7 2'2 M 7 57695 . %30 ( n) g7g cso is w o inszo N /A . ows (0 512,o l 3 ()n 15')4 0 T3 \\\\ ~/ iH379 (l) g x\\7 o\\ ~ 9'-10 \\5940 y 7313C V .2%t6 ( n) g n; O 3: 0 l s DENOTES THAT THE SIMPLIFIED ELASTIC-PLASTIC. NIALYSIS IS REQUIRED TO MEET THE PRIMARY PLUS SECONDARY STRESS I.'iTINSITY l RANGE AND THAT THE REQUIR.MENTS OF EQUATI0hs 12 AND 13 o (N3-3653.6) HAVE TO BE MET. 14c7 E (0 E%CEEb% ALLOWAEC OF 2 4% FCGt NRC Po5TULATCI:) i PLP E EW,7.R c.RtTtra,i A j N *,T C (?.) E.G. 9 : ti.Q. 9 E1ACMSP.'.tC/ RE'WLTb 'DMS. MOMCNTU 3 V *i'EQ FCR GOTH
a 9PTELEDYfE ENGNEERNG SENACES BPS 5 Ii7 m to 6 m e . #K =_sw77 97- - m '.. N% r / A + METHOD OF CALCULATIN& AbDED USAGE PhCTDR DuE70 287 c4cLEs CF SelSMIC STRESS ACTING WITHTHFMSELVES 0 PEAX STF15(SElsMIC) 3S = Ca.Kz 2 Mt. (FWOM EQ.II REE3) p AND Ft2 FASRICATED BRANCH CONMECTIONS AND TEES Sr= Czal<2h M' + Car k r MI Er WHERE t M's = RESULTANT cF 2 X ( DBE ) SE15MIC INer471A MOMENTS. ( NCLu o I N G E.N D EFFE CTQ Psi (RR E4.14 CONSIDERA FcA Sp < 3% = 60,000 EVALuA50N IS E1ASTIC, AND }<e = 1.0 b S y= /e _f EQuAT10N 14 (SER3') : At '2. I-9.2 IM APPENDl%.T REE 3') FeR STArNLEss STEEL,FOR(Swr < 2s,cooFSI, FRcm FIGURE SA 3'G 7f st6 ) N,, NUf. LEER GF ALLOWED C-/CLES = oo. 714QCF08E FCR m, NUMBER OF ACTUAL CYCLES = 645 $=0 U = *N USAGE FACTOR = 3 ou d CONSEQu CNTL-/ IF Sp < 60,000 Psi AND S LT < 25,000 P.sl A Fcx AN / GiveN ANA'L4 Sis PolNT, TREN THE8E WILL BE No ADDITIONAL CONTRIBUTION TO TOTAt. CuMU LATIVE USAGE FACTOR S/ 157 C/CLES OF SelsMic s7)eess ACT#NG WIT +4 THEMSELVES. O N .Do U PolMT COMPOWEMT C2 1 S ESS 55 3.23 2E \\% 13 Cbt { C i o l 8,0 ',$M My FRU,1 DIE TABLE IT 15 CBVlous THAT T+1ERE 15 N0 ADDITION AL USAGE FAC7c2 tuE TO EST C-/CLES OF SEISMIC STRESS AC71NG wlTH 7t4EMsELVEs FOR THis ANAL'/ SIS PotNT IN THE S-/ STEM. o
WM Technical Report E-1495-17 Rev. A - 7.0 STRESS ANALYSIS (Cont'd) l 7.4 Stress Analysis and Code Evaluation of Flange Bolts I A stress analysis of the flanges (excluding bolts) is included in the previous section, 7.3. NUCPIPE Program Results. Therefore, it is the purpose of this section to analyze the: ) (1) 1 1/8" bolts used with the 2 1/2" - 2500# flanges and (2) the 1 1/2" bolts used with the 4" - 2500# flanges ) in accordance with the requirements of subsubarticle NB-3230 of Section III of the ASME Code, Reference 5. As shown on the following pages (sheets 1 through 17): (1) the Design Conditions Requirements of NB-3231 are satisfied and ) (2) the Nomal Condition Requirements of NB-3232.1, NB-3232.2 and NB-3232.3 are satisfied ~ l for all specified design, nomal, upset and emergency conditions acting on h the flange bolts. I As discussed in Section 8.2.3 of this report, the faulted condi-c l l tions specified in References 2 and 4 are less severe than the specified ) design conditions and no additional mechanical loads are specified; there-fore, the faulted conditions requirements of NB-3235 are assumed to be l l satisfied. [ i
). "/PTELEDYNE ENGINEERING SERVICES f7 by a M oATE 4 /r4./7 SHEET NO. 0F CHKD.BY 9A/ DATE 'N7h 7 =99" PROJ.NO. # 9 5 -/ 7 A O P/P/A-y FLAN E Beus - 2 Y2. wo
~~WW-M/N/ mum 8 0 t_7~~~
~~CR O S S _ SEC Y/O NA L ' A REA i a DE C/GN BOL7 LOAD, Wm . ANMW Ci of Cotr . 'secTion y l i 3 3 75"+ 3 95' _ 3.542.5 Se 2 s as 2h= 3.9 c - 3 3 ?_T =,/g75 - 2. ) P= 2 + 85 P S /s i l m= 3.00~~
~~y..=~~
+,500 ) 785' G *P + (2 4 e 3 M G M P) ~ Wm, = H+ Hp = Nm =. ?fSf3 562 6) ' +ES) -l* [ C./8 75) st 3./f. (3.S&.s)(J)(z +8S') _ 24,757 f / 6 6 // Wmt = 40, J 6 9 'LBS. Wm i = = = __ _ _. _ _..._ __... ) wmz= 3./t LGy W m 2. = 3./4 ( /E'75' (3.5(,.:.S)[f 5'00) 2 Wmz= +, 7 / 9 c ss. Wm= Wn; y =. 4 0, a L B L8$ 9 / )f i
~ 0- 'i WTF1 FDYNE ENGINEERING SERVICES ay A M/ DATE 4 2f. SHEET NO. OF I ceann.es OAV cA&by 7 ~ I00
~~rnos. uo. /4 9A~-1 s A g~~
~~~ ..2.. O Am = W as s4 ---'---*---"$s FO R 'S A T4 4 - GR. 4 3 0 ""~Mit TER/A l ' ~ ~ ' ' Ss = s o. I 'xs.1 -.ca 7eo~~
~~f (REF. 7, W/N. '72 ADD.)~~
~~...........rnsN .e..........._'-..-..-. sto, J cs /. 34 / in~~
5>
A n, = 30,/o0 . __..A c 7'uA L Pa oisio En Bot r AREA y... A b...-_..-_ 2 2 2 50 e # FL ANG E* Fc k. A 57 NDARD /$ ~ - 8 H 8-dot T.S ARE U SED 3 USING 7//E 7 ens / LE AR EA S ,REF.N,P./? 9- (. 7'70 ) = d. 3 2 O /N ~ A = g I) As : C. 3 2 0 IN ' > A m= /. 3 4 / ia
~~AND 7WE M/N/ mum 80LT AAGA rep u/RE -~~
M="N TS oF iQ E }~. 7 ARE S A T/S F/ED. e ~* e g J
) WTELEDYNE ENGNEERNG SERVICES 1 7 0F 6M DATag[t/7'/ sMaaT No. sv cHuo.av M hi AT J/f n -1Ol* PROJ. NO. /4-95 -/ 7 A D i D ?.4 FLANGE SQL 73 ( conc ) w E0! T 6 7*Re C CE i. "jf -- 2 S~CO FL.ANGE BOLTS J AOL T S TPL SSE G !~ a /: .4 2,';
~~5 0 0~~
~~FL A NG C~~
/,I) -FN E CL 7s' A R ii S:/MW/A sc/ 2E D W/7H ) oN P. /57 c l~ R E F. /7 FCA T//E-FOL L O W/WG LOA D S (t ) Pkt L A l.) D (2 ) PRELCAD OLui PRESsuAC ( P = 2+86,vs!) s (.3) PALL OAD P!- u 5 NICMLNT fM = /3, CO O IN~LS) f4) FNLLCAD PLU$ 7)/E R MA.:., " d 7~p:- 7C 'F) = Y 7*HE~4 Ei FC E[ THE /~a: L 6W/N G 7MSLE OF ECL T* S TRESSE C /5 TA KEN f~R ONI 7//E A E e V ri RL. rL k L N CE ]D sol r-srassSES - A X/AL ( >'), P S / FCELSA O ~ PRELCAD FRG LOAo PRESG. McM. rHERMAL e LEMENT PRELoAD + PQESS. + McM. , + TJERMAL CNLY ONLY ONL.Y (l' ~ N55) 2 Ms13,00 cwa \\ AT-70F
~~g,,,,~~
IN S. Surf 5,/57 7, 2. 9G 7/92 G, / 3 5 /,239 /,255 /?C YAwd 27.0 6 7'74 7070 6, '? fB (967 721 3,46o' S,& 74 f.,4 0 9 5,G28 0 222 S,/45 F,277 C,22/ 5,2 54 22 % 4,820 1 { f 80 4 231 938 i i 224-4,494 .C-i.G 5,443 4; c 1/ l D 2= S 'bI;'? I 5,3Sh 4054 4 213 our SURF 4, 00G f,882 +, 5 G 'l f 04] A l'Lt AG E 4,'78 2. G,018 G,0 2 L 5,/07 /,0 % /,0 + 4 /2 S I 0
O WTELEDYNE ENGNEERNG SERVICES av (UNI DATESI'/~1'l N M-IA42 - I M" NJ wo /* Y A caso. av DA DarE o A D JUS 7 lN. THE ABoVE 3 7~RE S SE S FOR O (/) A P/'E.$$URE LCAD CF
~~GC0 Psi h,' A MOMENT LOAD OF 32,700~~
.w-L S AND g ('3) A TPEA M AL FLU /D CHANGE OF D A 7^c. & Ec 'F - 500*F = /5 0 F ' 7"N L F'C L L O W/N C NA /'/o g. W/LL. BE USED 3 En= . ' 500 - = ft) /.006 a+f5 + = . 0 ?> '/O C ..,, gg [2) }?g / 3, 0 0 C f3 ) R 0 - = 2*/4 = yg 70 B OL T S,*RESSEC,,PS/ PRESSURE McMENT THERMA ). enuy enuy onus P = 2 SOO PSI M = E2 70) Ms- = /50 *F 2 MA X. VA ' uc /, 3'f 7 2,!/Z ]?'/ A VG. ;'Autt /, / 0 3 2, b 31 24 8 O O M SEE Sheer 5, "r//ts 2"PoA T Snws ', O
L t e
~~O Yb SY 6/d DATE 5/2 /77 SHEET NO.~~
~~I 0F CHKD. SY M h/ OATg 5/9/77 PROJ.NO- /Y 98' / 7 _I ~ O E MA//MJM M:W/EN o' CH 2, -?,503 f UNG ES i O 7*/l: /v/A X/M UM MOM 7H /~~
~~A c TING 0N THE~~
/
f, ", 2 C00 #' fa.4NGES WILL BE CET:-. K M/NED FRcM THE WCR $ r

.?WlGINA T/ed CF D L AD WEl&H T**
v,, 4E/S M / C AND '7FL 4 MAL.LM Y:NC /.ot / NICMLNT& A c r 'NC CH D A TA PC/NY 205 cre 2 34, OP ri!/S ECp o.t:~. 10 F2eM THE NUC P/PR RUN or 7N/2 REPC.R.T' ~n s WOR S 7' C oMEINA 7 /tw CP THESE LOA D C i ):oic D ATA PciN 7~ z06 )S A.S /~t't L e W S < ct M,.w-:.e M,, :.v -1.s Wl3 swis! Ru mi N i n.IN-L8 CKAD NCthisi 2 // 333 7, C,. // SE I.SM/C
~~s f ? >~~
~~3,834-2.4 '79 6 470 C E.- Cwu 5 S, 8 : 4-8, 0/4 / 7, C 2 9 I 6: E. / 2, 0 J / 12, 2 s i 27,799 ? 2,3:7~~
~~r~ 0.~t l)A TA~~
?' W 7 2.34 5 JM / LA aR L V M _. iN- :.S //13 y /N - L E .2ESULE Ni Mj, w Li z D.- L2.__.. DCAO A' Eta oT 2 II /// 'l C T 1j CEIGMle 3,2 [* ? 3/2 // C 7' L. Cf AS. : /1. 6'4 T J. 8/4 J,. 2.1/ "C /6,J43 .3, '/3 7 7,os? /"I,9'+ ' l. A: 32,7? /N -t i Vo' t. L .S E.. S i.) RR ECL7 372E L; El'AL. O
. _j bb l7 sy 6M DATE (/3 /7 '7 SHEET NO. OF ~8 04 ~ PROJ. NO. /4 96 - / 7 I CHKD. BY DA*/. DATE *. '/ *) P K E O A L) G Tf'L S 5 L $ .2 lf - :Sao FL AME 80L73 O Fa t>.vt .S uc y n. : sp5 c, No. 7 #7 4 7 - g - 453 .~NE EOLTS WIL L BE PREL OA DE D TO A TORQUE V'AL ue oP 56O F T-L8s. WITH THE THREADS T BEIN G WELL /.UBK/ C A TED. lN TLR l'C: ATING TWh DA 7'4 ON P. 32. of REF. 17, WE GE T THA T T///S TOR Q uC VA L. UE WIL t. n ~' ' V Z,'u :. L' AN A X/At.- .' o A D /H THE S TUD, W., OP ?4,,220 LE. t= M AI REF. /S, P. /7 7~H E T E N 5/L.E ARGA -dN T//N E A D /S A. .,790 /N * (' DP A lfg THE N .~ N = P Rii L CAD C ~i*ic L-C S I5 3 4, f 2.:~ .;t. C '/ '7 '03 / O V g) ^ e??C = PJ'EL Cin. ~ g g)V.*.VA. G S~RESS - l ll g N' 5 A - E6-1, G L.:.3 0 E OL T5 + 7.< n.. + 7 wa. C b - 7 -y-7 n c.. nu Q I M SURE M CM ErJr THERM 4 L ,&3/ + 2G 8 .5 4- ?, E 7 '/ l /,/C3 l 2 ('3 C, 500 ) = 4 /, MC }'.5 i E -=
~~J-7,55! ?5/~~
4 :$g O @ ? E : *.s T HL' A L *l P4 6 E S 7^R E C C. / E QlJ/LW MkN Yb 3f~ N2-,1aa:.I A L L' M.E T. G O
f O wm NmMICES av C/V/ DATE f/b '/7 SHEET NO. W CHKD.SV OAL/DATgS // 77 PROJ. NO. /MO/ 7 A O ,v;.M / M uiA $7.cs:CG - /,I/g - iN,hA-sc,-1,GR.G30 sol ris o S= Gea,o G~~~ra x. + G % x. r G%u. 1-ps e. u vxe moucur ree wise. S= 43,5 7'7 + /, J 4 7 + 3,//2 +377 O ,i(so, sco) - 9/.:700 3 =: -/ 5,420 .n~= / 4 3 Ss = (Ccc5e*r l'L/ .~, . '/// MA >'/ mum / S 7"R E S S RE Q Ul2 E WiENTL OF f) NE - 3 2 32. a APL ME 7~ '3 / f.f' - 3N. /; :.,;../ > 6x.GJc 8 ::. 7*C FA 7/&llE 4 NAL :i.' * ~ 7~HE SCLT & TRE L a VAR /A 7* 0N,5 D UR /NG Q P E N A r.'N G .:JN ] / T/.: A :. ARE L MA: A A..: 77/E MAX /M.:.'M ':A n. . '
~~7 1. :. u 2AH6 h~~~
W/LL OCCUR BETM'E CN T//L O //N A :5 LME.'. L :.: .:. ND / ': ' N AND THE N/AX/MU/VI STRESS C e*ND/ 7/nN. F e /2 7*H E l A 7 /6 !./U ANML y' S/ S A S 7.CL L E .7N C L N ;' A A 7.' *.U FA C Te x CF -/- S S Y!L L EL . / LiEO a.- 7.h't. C YClic LCADS ON THE 2 f2 - 2,500 f.: Alvs & S .4k E S 7'A!NL D FRcWI THE NUCPIPE " O .:r CE L' A Tina C 'ND / TI N /NFUT j7R />A 7 A P 3/N Y 235 FRONI 7'///;; D A TA 7//Fft. ARC A 7 "O 7~A L. &F l'I ) 520 (,5Cro /- tic) P P E LS u k !? C YCLfi C O (: ) 8, 7 '? 9 EL wDown
~~Y:LES O~~
O ~ w m N N N ES av 4 AA DAfg </ c/7 7 SHEET NO. W CMKD. SY M / DATg [/ /77 PROJ. NO. N-98 ~ / 'I A 0 (3) 1 BLOWDOK'N PLuS DEE .SE/SMic C.NL E! 't (4) /N A ED / 7/0N 70 TH/S 2.:00 C YCLES OF S LIG M/c G 7X255E S MUS T BE A C C CuN7ED WR AND 3 (S~) AN u,"FE K. .-? C u N D LIM /r CN A S Cc t..'i t '/. / D/S A $S E MBL '/ C )'&LG S CF /20 /,S ./] S&uk/l:D o i A'J T E TWAT N C A 31;t u:T:./j :/S,/]JJ:.^m. / CYCLE /4 A S 5uMED 7't JCCuA L V a' 7*// EACH .? 7*// L. /20 S TA P 7~ uP,/ 5 N.<7C:K N C h'C LE S. I. $ C E 7~C R M iN i/r G s' 'H! PEAlf S TREs t.ES F 'N 7~M C N G C f.'r G
!..c / ?.'A< c,
Al'/rt.*N5 M':
~~a :.~~
?~
~~/. ~THE PEAK S TAESS VA A/A7*/?N ,DRt: G C URt.'.' O A D C g (* *N S EL VA 7*/! 'l a a ' 9 3, 6 ? ( ,r 4 / w,, ay'}p = 4.* 4 8, -/ Oj = 'p =.,~ s. e~~
~~a..~ e~~
/scret den ) 3 4(!'i'420 -i;3/? - ' W ~' ~ 'h = " x 3, H e ? -)! * ^ 5 = 3 2,7c ' < 0L / C2n C '/ C L E 5 = /82,.233 1 g ~ ' p jp., a. 7//t: /3)= Ait' a <# V: VA R /A T/C ti - F L.C W D.n vN 7 h'L ~' M A:. L C A.D L O [ *N $ENE/ 7 ll 7..' / aj ),,, = 4 ('48,4 zo ) = m, a so es ' O
w/ ' /7 BY 6 /V/ DATE3^/5Y'/'/ SHEETNO. OF CHKD. SY MYDATE // 7 ~7 PflOJ. N O. / 4-9 3 - / 7 2 ~ C 1 Y ( $ I. A LC' ~ 70 2 y 's3 4-7 -. 3; > 70 0 - /4, :S." a BL D .' 4 Qu // 2 g,, / 3 y,,pp 3 ?? ) /85 80f S/ ~' DE w.c I 2, 7 'I 9 C Y C L.L S
~
~~Q . r..~~
~~3. T//E~~
~~/]EA L' S7REsS yn pis17 toy -- Et gyiy;,,* FL:/S .' 1.3 c'~~
L/.*.'dit L.*A

;
~~) C.7 N s ER VA T 1,' '!a L Y~~
~~9, s,e %o +~~
~~=: .,l -l E,4 U j = / f 3 c,80 f SI t ' ba s. // f 8 4 20 - 4*o 1,34'7 ?z.7 r - /3> s ?: . // 2 4 Plne x + r'~~
~~2. r00~~
.a .i .-.: 7y / j ]up / 84', 51 G ' j" ; / / C YC L E .l 1 u + 0 8E EE /S M/C LCADS ~l. 7~NE PL-A k S 7 Et 5s & A S //11 /: tl G' C C N SL.4 ?'A l ;i'? L Y l 1 {.f.9 42 r i - / '/3,.; 8 0 PC' So)fSL/C = \\ p' 4-48 420 -
~~(5 ' ;."~~
y ~.7 / / : ~' p )_ g, i y 32' /00 l b 'l, SfC ,f s / 200 C '/ f I l. O ? Npa - OLI,. - ~ ?; i D
WTF1 m(NE ENGNEEREK4 SERVICES /7- [ OF av d AM DATE f /c/1 7 SMEET NO. cuno. av PA DATE b/II/77 ~$ 0 0 ~ FROJ. no, /4 9 T-/7 A O /) SSEMBL 'r'l / S. i /- L-FL A h-STLC 5 4'/)N///7*/Cg ~ /) /.SA S5LE M 3.'.' O / 4 ),,,,, = 4 < %. ) 4 (-/8 42 0) = 19 3, a e a p.t / 'U = Q p/ U 'S 55 7 /.7 0 C yc 4 C, $ U.v' A /A :?! ZJNG 7///* /1.4 0t
~~C Ho'E' GET G~~
m of Sp P S / o cC UR. e.) l'?3> & B Q ?>S+O / 99, /O 203 / F & a c t. E, 7 W /8Y. 59 0 / /?:,c 3C f:: c i:c ..3 No. n, c. y c L t.s Op )g:n.< Sp )u,a S At 7 .V, C YGE S U / /20 ' ? f, 43 0 O 76, $ 4 s //00 0, // Q Z [2C l'?3, o 3 0 // 2. :2 0 C ?:[ > fo # 3 / . ' ? ', t, 6 0 /84,570 4, 545 / /3 ' ') .f-9, ;' ? ? /93,686 /s'5,80 0 3,140 7 /0
O
.S~ .: 0 0 / 9 3,&20 /99,5/ O 2,o65 7 /o ' O 2 C.// ?~ U = c.ll <::. /. O, 7*t/L.c f fv; G i //C ,Ccput2EMENTS ~ O p* NS -3 2 3.?. 3 f c ) ACC M E T'.
"/PTF1 FnYNE ENGINEERING SERVICES /7 By C M DATE 4 /_* ' _ */',' 8HEET NO. OF CHKD. 8Y/'N/ DATE /-? 7' s 7 PaoJ. No. /4 95-/.7 A if w -?!/.HC C b0 L.I { p N,7. ] / 'l /
~~f 4 -2500 Fl. ANG L~~

MINIMUM Bo! T CR o s 5 - SE:. rto NA L AREA G DE C/GN BOLT LOAD, Wg 1/ 5./C75 + GU?? E 43 ?5~ 6- // 2 g = Ct.t75-C.615 - . 2 S~ ' ' ~ ~ ' ~' ~ ~~~ ,is i P= 2f es P S ta h1 = 3.00 y= 4.,soo O . 7?F G *P + (2 4 e 3.!4 G h) P) Nm, = H+ H = p ~ +85 ' + (' (.: 5 } / &i (C f3 75)[J)(; f-!S) n'm i =. 7 5'5(5 -53 7[) j i 5?,G7G -f 3 /, i: 2) Wmg = 99,491
~~t. S S.~~
~~Wm i = O Wm,=~~
~~3. /,i bG y Wm~~
= 3./4 (.250 /(E.4375)[.4,5^o0) \\ m $ i11 2 = f;b0h LS$- 8?,+97 tsS W,n W:n, =- = i l
1 WTF1 FDYNE ENGINEERING SERVICES / 2-oF /7 Sy 4M DATE 4/n /77 SHEET No. CHED. SY d[ DATE /> #> 7 -l l O-PnoJ.No. N 95'- / 7 4 J' i Ad/N/ mum REO u/ RED BOLT A REA,_ A m o I. Am = Wm I Sb i i Se fo A SA 56 4 - GK:'d 3 O MK7ER/KL-g Ss = 30 1 xsi 9 7eo
~~f (R E F. 7, W/N. '72 ado.)~~
~~s //EN. E9,4-9 9 2.973 /N~~
Am
= Jo /oo j . A c.ruA L Pa ouio so BoL T AR EA...y-- A 8 14 F e n. A 37*ANDARD 4 ' '. - 2 Co e FL A NG E' /k -8t/,2A Sot 7' S ARE U SED 8-T US:NG 7//E 7ENstLE AREAS ,REF.N,P./7 V (4 +'? 2) = //. 93 6 IN
A
~~= g A m = 2. 9 73 iN~~
~~As =~~
//. 93C. /r/ ' 'y AND THE M/N/ mum GoLT 4AEA REQ U/AE - MEN 7"S OF A E F. 7 ARE S A T/S F/ED. G l
O WF WNE ENGINEED4G WICES O I M5/77 SHEET NO. W sv ' M M DAT PROJ.NO./4 6 --/7 A CHKD.BY PA Y DATE //b 7 ~ G 't /t 8047 S/A'ES CC = + - 2 5.)C s'~L ANG [ EOL7'S /~ M THE /.Q -8N BOL TS USED n'/ 7N T' C H 4 - 2600 FL AN G E S, 7~N L. S TRE L CEG W/L. L. E E." O BE' A PF.A'O x /M A T[1., E >' C A 7.': % G 7*H 2 / $g' i B rL T* S 7 AL C S !:S F C uNL: CN S//EE: 7~ 4, TH/5 S eTMN. FOR PFL Gu t'E c N t-. y C Y,C.=.. C ES - THE .5rn GSEC A.pt; /. n culaGD T.: E '= /, E /R L-: '.' jCA T/C Ci 7W? E /' C C l l H.= [ 3 . ~CoC /Vic'ML N 7" <///. i i~ T E Z.* S C /* :, - THi! ~ f S 7T E. S5 L A /Oli A ! S u /./'i* D TJ EE~ A
~~.)/ N L C T RA 7'/ C Q ~'~~
~~7 //!.~. A '~ ? A C /t != D P 'l'l=~~
~~IXt Ci: C -~~
~~i ) P* O P. T HF R ! C A L,. CNLY 6 7 A2 L.C W ', THE~~
~~' 7*F'L.C C E C AAF A.' S U M L !.s To E s~~~
A D/ RECT l l .C A T /..' .0i Ti/E /~ L. u/D il T ' - i ..g f3P2 L A D C 7~/R 'CG C L ' ' /.'. ' l-: dALCUL /\\ TED AS S HC n 'N ON SHEC~ /i, YHis l E P O.? 7* 5 E r TirA', ') B CL 7' C TRCC CL C,, FSI ~ ~ I ?M E N ~7'~ 7'HE SM A L. PRE-S i unt N . bs. V Old L Y
~~fd L Y g~~
P - 2 E x p so M =tG.s, 0 0 s Tg - 12 C '~ mar VALUE /,3 + 7 fO59 302 A v6. VALUE /, / C 3 3, + 3 2 2 l4 I
g~ SPTA FnYNE ENGINEERING SERVICES /7 ev_ _ 6 Ad DATE S/2 /77-SHEET NO. OF /496~~/7 N CHMD.SY. A lv DATE I [77 ll 2, = PROJ.NO. l O i MAX /M:JM mow l=N 7* CH 4 -2,500 F2ANGE5 O TH* !: MA X/M uM MCME.'/ 7' A CT/NG 0 // THE 4 " - 2 500
~~f/ ANGES W/L.L.~~
BE DETERM/NED FReM THE W0R $ r " C O M e tH4 7/6M cf D L/:D WE14H G a 4E/S Mi c AND THEkM/L. Eh'PANc /0F/ /VICMENT4 A C 7'/NC 0,4 D A T/; Po/NY 23S** O R. 'I35 0F TN/S REPaRY. s' O F2oM THE NL/C P/PE RUN O l' 7N/ S R EPok.7* s 7*// E WORST COME/lJA TILW OF THESE' L.OA D S foR D AT/r PC/N 7~ 4 3 &~ JS A.S FOLLOW & O /A;, IN*LS /8 y /N-LE /8 oW-G EE 52L% /$ 3y f rV - L B CCAD WDQ/,7 2,493 j,5 */ $ G.) / O 'j S E /.S N1/ C 4+ 7 30,5 7'E.- CcND 6 ; 3g C 34, 2 s,,0: 1 44 90 l 9 E. 37,748 31, s '/-/ 1 0 /, 3 / 3 //2,fo40 i l S / M / L.A R L Y F 6 R. DA TA PC/N 7 93 5 1 O Mj, in-L 3 M:, IN t.S /4 m - LS ECCut.7' NI 3y /h -L) DE AO n'E16H T 3,753 2, j )3 . fC} $CISMic .j.I 23o
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#PTFI FDYNE ENGINEERING SERVICES av_ G M DATESh/7'7 I7 SHEET NO. OF CHKD. 8Y bA/ Da1E dah7 - l 15 - enoA no. /4 er- / 7 A O n PRE L.O A D S TRESS E S [ - 2 So o FL ANGC BOLTS O FROM SBC H TEL SPEC, No.
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7HE BOLTS WIL L BE Prat.oA DE D TO A TORQUE VALUE OF fo 90 FT-L8s. W/TH THE THREADS g BEING WELL l.uBR) C A TED, lN YER POL ATIHG THE DATA ON P. J 2. of l R E F. 17, WE GET THA T TM/S TORQUE VALUE W /L L. m /NDuc2 AN A X/AL. LOAD /H THE 5 7uD, W, of S *7, 430 L ES. PROM R EF. /8 P. /7 THE TENS /L E AREA y n OF A / 2 -8N 7H' READ /s A = 1.49z IN
~~i 4~~
THEN THE P RE L OAD STRES5 1S (PraLcno t.(/ 51 430 38,490 )?S / 2 0 g /+7Z A VE R A G E S TF.E i-S - l// - y if, 3 4 - g s 4., gg,c3o g os.rs l@ b = 7'ECLC A.D r 7 A ve.. + 7 A ve.. + G'~ a va. / f.4EL 5 Uld MOMCNr 7~HERM4 L ~S = 39,490 + /, / 0 2 .F 3,432 + 2 /4 l l I f S := 43,2-/o Ps/ 42S 2 (39 MO) = aa, 6 50 P~s t s = @ S 70*f THE A VERA GE~- STRESS SE Q u/CEMEN 7~S OP NB-3c3C./ ARE ME T. e f I ) I e t
i l \\ WTFi m(NE ENGINEERING SERVICES /7 / OF BY r3 N1 DATE 8 4/?'/ SHEET NO. CHKD.EY OA l DATE //Y'72. "iN* FROJ. NO. /4 9C-/ 7 A O / l/g - B N, 5A - EM J.e.6Lo SM T5 /V/ A t/M UM S TRE SS - 9 C~as x. V~~u. + <iw. S-7l,h ' '., Ab. o + FEeSSURE M J Mar.'T Tite R MAL / S= .38,4'70 + / 3 9 7 /- 4 6 5 7 + 3 0 2. G 3 ('30,3 4 0) = 91,0 z o 5 -= -f f 2 0 0 'f st 3 Ss 4 = (D C. ?o'F fS/ 7"N : /VIAX/ mum iTRERS E L-: j..i!:?EME.'CC OY 's' .4 H - 22 32a7 A RG" M Ml ^. FA T/auE A. VAL. ;' 'i 5 - / / -8M, S A 1, c rP. G - ) 6; OL f*;5 ~ .,) ~;': E x." 75L Ci j'A,C lA TlDH $ ,C Gi?/NG QPE,CA 7.'N.: ~ C.).Vu / Ti::. :. A RE' G E N L A N L >' SMAuLER "rA N '.~s 2 / 'I' E x.', e U SED W / TH TNG 2 V, " - 2. 500 l-- L. 'INGEC 7~N G b./'.!N C YFi v.4 t /MU/,'i P ~A H $ 77f~, RANGE Wil L. CC 'uK a SE T W.! ?/ 7'H E UN U S E!/ h: 1. i G C ON D II"! D*/ A N.D .". / E M A X/?A uf f S TRE CG C C li L l }'la H AND THE USJl C G a FA C TO.V W/L t. EE DETE.V M:.t L: / i.:t. 7// / C RANGr? .4 S ~~.t E S G C ON C EN T*RA 7/ON FA C TCk Cr 4 /S UaE2 /N T/:S /:o t t. opt :N., .!)NAL Y 5 / C a
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o SeTF1 mYNE ENGINEERING SERVICES /7 sv A A// DATE J/ SHEET NO. OF CHKD. SY 8AY DATE 3 Nh 7 "" l 6 ~ PROJ.NO. /4 ~ / 7 'i O .'76,20o e$ sso 7ci Sa- = ..) e 1 N= 130 O c.YCLES J b At/D rHE EG = / 20_ 0 092 4 /. O =. /3 oo THER E50.2 6 7~HE REQu/.tEMEN T S Of e N E - 3 2 3 %. 3 {c) iEE iv' 7. D 1 0
)
e, v Technical Report TR-1495-17, Rev. A -116-O 8.0 CODE EVALUATION 8.1 Design Conditions G The maximum Primary Stress Intensity (Equation 9 of Reference 3, NB-3652) is 24,603 psi at point 180 which satisfies the allowable stress for 1.5 S, of 24,720 psi at the design temperature of 670 F. 9 The computed stresses for Equation 9 are listed for each point in Section 7.3 of this report. G 8.2 Operating Conditions 8.2.1 Normal and Upset Conditions It was necessary to use the simplified elastic-plastic discontinuity analysis procedures of NB-3653.6 (Reference 3) to satisfy the Primary plus Secondary Stress Intensity Range defined by Equation 10 (NB-3653.1). Point 167 has the maximum S range of 80,603 psi and does n G not meet the 3 S limit of 49,800 psi. However, Equations 12 and 13 re-m quirements were met in that maximum stresses of 49,222 and 23,352 psi were calculated and are less than the 3 S criteria. m I8 Fatigue requirements have been satisfied at all points with the largest cumulative usage factor of.4445 occurring at point 180, 3" schedale 160 pipe stanchion to 3" schedule 160 pipe connection, Com-ponent C-5. G The rod withdrawal accident, upset condition, has a speci-fied pressure of 2700 psi; however, this pressure is acceptable under the provisions of NB-3612.3 of Reference 3. O 3 I
TN MATERALS RESEARCH Technicel Report E-1495-17, Rev. A -117-2 8.2.2 Emergency Conditions The maximum Primary Stress Intensity, Equation 9 (NB-3652), 9 was evaluated for emergency conditions using DBE for seismic moments. Since DBE is also used for seismic moments in the evaluation of design conditions, the results are identical, and the maximum value is 24,603 psi at point 180 which satisfies the allowable stress of 2.25 S equal to 37,350 psi, there-m o by meeting the requirements of NB-3655.2. The specified emergency conditions were included as stress conditions in the stress and fatigue evaluation. 8.2.3 Faulted Conditions The faulted conditions specified in References 2 and 4 are less severe than the design conditions evaluated in Equation 9 and the re-quirements of NB-3652 were satisfied; therefore, the requirements of NB-3656 3 No additional mechanical loads were given, and no thermal are also satisfied. stress or fatigue analysis is required or performed for the faulted conditions specified. The plant LOCA condition is not included in the Upset Conditions analysis as discussed in Section 8.3 of this report. 8.2.4 Testing Conditions The evaluation of testing conditions was carried out in q) accordance with NB-3226. Calculation sheets 1 and 2, following, give the ccmputations for satisfaction of the requirements of NB-3226. Ten (10) cycles of Hydrostatic Test were included in the Section III evaluation per NB-3114. 8.3 Additional NRC Criteria Evaluation Additional NRC requirements concerning the functional capability 5 of Type II Safety Related Systems during plant faulted conditions are described in NPC Mechanical Engineering Branch Technical Position MEB-6 (Reference 28). t3
L W TELED(NE Technical Report E-1495-17, Rev. A -118-O TMR has evaluated this system concerning LOCA and considers the effects of this accident negligible for the Pressurizer Relief System. The Pressurizer Relief System is not anchored to the containment vessel, O therefore, the displacements resulting from the LOCA condition are not experienced. As a result of the NRC requirements described in Section 4.0 of this report, piping breaks are postulated to occur at the following loca-tions which are shown on TMR Drawing DP-1574 Revision 3: (1) Tenninal Ends: Nozzle Points 100, 490, 790 G (2) Intermediate Locations: Essantially all B.W. returns, elbow, valve / pipe flange junctions and reducers located on the Class 1 Piping ^ of TMR Problem Number T-012. !D ' 'r 0 D
..~ y -l t 9-8-i-73: sumer me. I w2- + JPR mm .y 1 4 9 5 - l'/ ' cnun sv &) F C u m 8 -7 3 IMESSURIE ERTREL.lEF pasa. = -e(STEM:hp
s
.._..m_ 2 Sail 5 FACTION CF THE REQuITEMENTsi !cp' NB-32'ZG 1 .I M S - 3'2.2to 'niGTinct conditions ~. 'T he e.JAl uetti cn E ~Ted'w Cerd.i'Nani kNS-3tt4) sbo.il be in w'Ah 4hc foliDwin.} greguire medlt:__:. Actt rd ancc a 9 I SirfM'idien60 ShAll Ptl 4XCeN'l $N Pe.)er.tto.\\ invArk yrem orAnEYo.buleded Qeid..dre L ok ted I 90 per cced cf i 4emperLSttre. ; OL.'._ ' ~ ~, 3 Bio % ; TEST "TEVERATttWE..= 135 *F... 7E',T PRE %uRE = D J. Sm: 2t,000 90 FOR SA-31b,"'P 3)fe. FROM APPEubtX 17AELEl-1.2 ~ 3 q OF REF. 3 ; LAR6 EST PIP E IN 6-/6 TEM ~l,6 : /o" SCH.120.,. 15 6 = 1.s (20,000') = 3 0, cob:. U S ._q g=9 sg 9 (30,0 c0) = T7,000f d'.. ~. ~.y = .- p:.. .:N(hece) + 7 (rom.....). S stwtRat twms-/ sigtss luTensix-/ = 4 (sgio)(s. m 0 ( sc') = (.ser) 2 w gauanmexTs me rmT Act =. ~24at,i psi 4 za, con esi...._._y 3 sirecs % w.M.9 .%ti nd t/ cad Gs p ce,d ef -4hc.ypr n.e m -membre (b) % -tab.i -ted -i nf.duic. ac Hns Tuc sr.mturx evs, ecuAcrcht'/i'scwiwiAWTHE-~{ 2 uct nemu memuM RR TRE DEADWEWHT CCNbertow (R-JDR07EST')- REF. I n : -i% m-m, W = 349 in-sb, m, = la to in-vo.. Au. x lo9~10 h-4 Mi : i(!4)* + (Mv)2 + (Mg')2 FRint ArR-(- Mt M8r&h. Plu s, PC.tMM l. BENb1Nf.riSTr2E65. lMTENitT-l...- Pi Mipe (1 Slo)( i.4TE) '. ~ ( f,970)(Z,875) = 17593 es6 -+ = + l -t r.t (.375) '2. ( 31%) l 1 $g ; l5 $m ANb l.E (lfi[] :
~~2. 0274 m ~' Z.02.5(10,000) = 40,500 r%I~~
. NM RfSulRE MENT 5 ARE Mf T As '~ ~ I"7,593 PSI 4. 40;5CO PSI 3 l l I TELEDYNE MATERIALS RESEARCH h ENGINEERS WALTHAM, MASSACHUSETTS
..r,._..._._.J., D-1.._._, - 12 O r r W om 8-1-73 2 ,, 2 my 1496'l7' cum, sv0M5 om 8-2 73 FRFSWRIEER ~ REuEF. m= - ' 'i S~/ STEM *. Ultt ' ' = ~ 0 Nti-32% -[6571NG CONDrT10HS ' ' h I t'. (c) tw ellerno)dderm.pr0Mure shAl\\ nEI yc$td b135 per cged o wiuc med b 4 rv.Itt of Ni$-:3113. g q 7 i R E. IS NO FXTERNAL fWE664RE.. 5RECLEtEh. FOR ~THIS....STS~IEM.,_.d a 1 (d) Tr{k in Nld'ditw "It 'N4 kD [4 T M i b d!.lo 7~ Nf5-lo2*2.7. S be censidct ed in'lk 6diguc enlu~tlew. : ~. '. l 9 MM C-/ctt S OF THE WE.vT-( H'lDROTEST~ C-/CLES SPEC)FtEt> HAVE. .,1) BEEN INCLUDED W rHE FATIG uE EVAt.uNTION. . ~ '. i i ~ a. _3 1'. D ~~ ~ '~ ~~ ~~ ~ 3 TELEDYNE MATERIALS-RESEARCH 3 ENGINEERS WAl. THAM, MASSACHUSETTS i
Technical Report E-1495-17, Rev. A -121-0
~~9.0 REFERENCES~~
(1) TMR Technical Report No. E-1495-10a, " Final Hanger Selection 0 and Load Requirements Pressurizer Relief System, Model A - TMR Problem No. T-012 and Model B - TMR Problem No. T-011 dated July 20, 1973. (2) Bechtel Specification No. 7749-M-200, Revision 3, dated May 5, 1977, " Design Specification for Nuclear Piping Systems for the Toledo Edison Company and the Davis-Besse Nuclear Power Station, Unit 1, Oak Harbor, Ohio." e (3) ASME Boiler and Pressure Vessel Code, Section III,1971 Edi-tion. (4) Babcock and Wilcox Specification No. CS(F)-3-92/NSS-14 dated October 30, 1970. (5) Bechtel 7/31/72 letter to TMR, W. H. Mable to D. F. Landers. (6) Bechtel 1/2/73 letter to TMR, W. H. Mable to R. Wray (7) TMR Technical Report No. E-1495-1 entitled " Davis Besse Nuclear ?* Power Station, Methods of Analysis used for ASME Section III Class 1 Nuclear Piping," issued March 1973. (8) ADLPIPE, " Static, Thermal, Dynamic Pipe Stress Analysis," I. W. Dingwell, Arthur D. Little, Inc., Cambridge, Massachusetts, April 1,1972. (9) LION-4, " Temperature Distributions for Arbitrary Shapes and Com-plicated Boundary Conditions," J. R. Schmid, G. L. Lechliter, and W. W. Fisher, KAPL-M-6532 (LION-3X), December 30, 1969. 3 (10) Bechtel 7/17/73 TWX to TMR, W. H. Mable to R. Wray. (11) Bechtel 8/6/73 TWX to TMR, W. H. Mable to J. Q. Cragin, a (12) TMR 8/14/73 Correspondence No. TMR/DB-035 to Bechtel, R. Wray to W. H. Mable. 3
O TN MATERIALS RESEARCH Technical Report-E-1495-17, Rev. A -122-0 (13) TMR Technical Report No. E-1495-17, "ASME Section III Analysis of Class 1 - Pressurizer Relief Model A, Piping," dated Septem-ber 14, 1973. O (14) TMR Technical Report E-1495-18, " Pipe Anchor Stress Indices for Class 1 Nuclear Piping," dated September 26, 1973, including Revision A dated January 17, 1975. o (15) Nuclear Regulatory Commission Guide 1.46 entitled " Protection Against Pipe Whip Inside Containment,"' issued May 1973. (16) Bechtel 12/26/73 letter to TMR, P. P. Anas to R. Wray. (17) "Flexitallic Spiral-Wound Gaskets," Flexitallic Gasket Company, 9 Camden, New Jersey, Tenth Edition, 1967. (18) " Screw-Thread Standards for Federal Services," H-28, Part I, U. S. Department of Commerce, National Bureau of Standards - 9 1957. (19) TMR Technical Report No. E-1475-41, "ASME Section III Analysis of Flanges on Selected Class 1 Piping," Millstone Point Unit No. 2, Book 1 of 2, dated June 17, 1975. a (20) TMR Technical Report No. E-1495-17, Addendum 1, ASME Section III Analysis of Class 1 - Pressurizer Relief Model A, Piping dated February 22, 1974. 4 (21) Grinnell sketch of axial restraint PRH-3 shown on Drawing 7749-M-190-30A-180-4 last revised May 19, 1975. (22) TMR/Bechtel, April 28, 1977 telecon between D. A. Van Duyne (TMR) and R. Jackson (Bechtel). 9 (23) TMR Technical Report E-1495-19 entitled "ASME Section III Analysis of Full Anchor and Axial Restraint Attachments on Class 1 Piping," dated November 21, 1973. l' (24) " Systems Summary of a Westinghouse Pressurized Water Reactor Nuclear Power Plant," Westinghouse Electric Corporation, August, 1973. 3
O Technical Report E-1495-17. Rev. A -123-3 (25) " Nuclear Power Plant Systems and Equipment" by Kenneth C. Lish, Industrial Press,1972. i O (26) STARDYNE "MRI/STARDYNE Theoretical Manual" Control Data Corpora-tion Publication No. 86603500, May 1973. (27) TMR Technical Report E-1495-20, " Davis Besse Nuclear Power Sta-tion - ASME Section III Stress Indices and Thermal Stresses for 'O Flanges on Pressurizer Relief Lines," dated May 3, 1977. (28) NRC Mechanical Engineering Branch Technical Position MEB-6 dated June 18, 1976. 3 (29) Bechtel Drawing 7749-C-666 Rev. 2 dated August 13, 1976. t 49 0
~~O gg MATEMALS RESEARCH Technical Report E-1495-17, Rev. A.~~
-124- .O O 'O 4 APPENDIX A I l THR Drawing BP-1429 Rev.1 0 TMR Drawing DP-1574 Rev. 3 I i lh li d I l'4 1 i')
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~~Dockst No. 50-346 Licensa Nov NPF-3 Ssrial No. 1338 Enclosure E t!QIQB LQeD SISt!eIUBE GNGLygig VALVE RC11 MWO #~~
1-86-0317-00 DATE 12-07-86 LOADREQUIREDTOOVERCOMEDIFFEREN[IALPRESSURE: ~4889 DELAY TIME: 55ms AVERAGE CLOSE THRESHOLD VALUE : AVERAGE CLOSE MOTOR LOAD VALUE: 2.71v AVERAGE OPEN MOTOR LO'AD VALUE : .185v REASON FOR TEST / COMMENTS: Support TP 851.27, to ensure valve operates at desi~gn condations. This test was performed at pressurizer temperature and pressure.
~~Signature went off scale, threshold value could not be determined.~~
l l l l l I l Data Evaluated By: Al Wise Signature /Date = l _. _ _ _ - ~ _-
MMC Unit CLOSING SIGNATURE TRACE RC11 for TP851.27 December 7, 1986 Full Differential Pressure ~ Torque Switch Trip Margin =40% Vy O. e-7 j T/0 2.500e0 ,T[ TL -2.0480e1 Switch Trace Flow Stopped V/O 1.000e0 l Vy 0.e-7 / i T/D 2.500e0 TL -2.0480e1 Vy j y - (.ARw.n.Fj 1 a 7 Power Trace L, l 1 .y .J L.. l I TL Vx f/ME
MCC Unit Opening Signature Trace RC11 for TP851.27 December 7, 1986 Note - PORV was closed during opening of RC11 i 8 5 g v j V/O 1.000e0 l Vy D.e-7 i i T/0 2.500e0 switch Trace # l TL -2.0480e1 V/O 1.000e0 Vy D.e-7 j T/0 2.500e0 V Vy TL -2.0480e1 'u 1 3 k i I' 1 5 Power Trace l 'U.r ~ -~~ --~--
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i t2DI9B L900 EIEt!AIWBE edeLYEla VALVE RC11 MWO #
~~1-86-0317-00 DATE 12-07-86 LOAD REQUIRED TO OVERCOME DIFFERENTIAL PRESSURE 4889 DELAY TIME:~~
55mm AVERAGE CLOSE THRESHOLD VALUE AVERAGE CLOSE NOTDR LOAD VALUER 2.45v AVERAGE OPEN MOTOR LOAD VALUF_r .174v REASON FOR TEST / COMMENTS: Support TP 851.27, to ensure valve operates at design conditions. This test was performed with no. DP. s
~~Signature went off scale, threshold value could not be-determined.~~
l l i l Data Evaluated By: Al Wise j Signature /Date l
i e MCC Unit Closing Signature Trace RC11 for TP 851.27 December 7, 1986 Zero Differential Pressure l l l l V/O 1.000e0 Y Vy D. e-7 k witch Trace l-T/D 2.500e0 O. ,f' [~ [(,M'1,h, TL -2.0480e1 ^ Power Trace V/O 5.000e-1 i . Vy 0.e-7 4 T/0 2.500e0 4 TL -2.0480e1 j Vy 8 a j g y ,i ) ~ .y ._J i__. l I TL Vx ~ s i
MCC Unit Opening Signature Trace RC11 for TP 851.27 December 7, 1986 Zero Differential Pressure j l i i 1 2 k i 1 V/O 1.000e0 Vy O.e-7 T/0 2.500e0 l TL -2.0480e1 Switch Trace O V/O 1.000e0 Vy O.e-7 T/0 2.500e0 l yy TL -2.0480e1 3 k i i Power Trace s 6 %.~.- ~t ~ 8 l TL Vx Tixe
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ML20212D728

Contents

Text

1.0 INTRODUCTION

2.0 CONCLUSION

5.2 System Description

9.0 REFERENCES

1.0 INTRODUCTION

2.0 CONCLUSION

5.2 System Description

SUMMARY

9.0 REFERENCES

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ML20212D728

Text

1.0 INTRODUCTION

2.0 CONCLUSION

5.2 System Description

9.0 REFERENCES

1.0 INTRODUCTION

2.0 CONCLUSION

5.2 System Description

SUMMARY

9.0 REFERENCES

Navigation menu

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