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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20212E9031999-09-30030 September 1999 FPC Crystal River Unit 3 Plant Reference Simulator Four Year Simulator Certification Rept Sept 1995-Sept 1999 ML20211L1321999-08-31031 August 1999 EAL Basis Document ML20212C1501999-08-31031 August 1999 Non-proprietary Version of Rev 0 to Crystal River Unit 3 Enhanced Spent Fuel Storage Engineering Input to LAR Number 239 ML20209F5601999-07-31031 July 1999 EAL Basis Document, for Jul 1999 ML20155F4071998-10-31031 October 1998 Rev 2 to Pressure/Temp Limits Rept ML20236W6501998-07-31031 July 1998 Emergency Action Level Basis Document ML20236V8801998-07-30030 July 1998 Control Room Habitability Rept ML20217B1731998-04-16016 April 1998 FPC Crystal River,Unit 3,Tendon Surveillance Program Engineering Evaluation of Sixth Tendon Surveillance ML20203K1521998-02-28028 February 1998 Post-LOCA Boron Concentration Mgt for CR-3 ML20203K4991998-02-16016 February 1998 Boron Dilution by RCS Hot Leg Injection ML20202J4291998-02-13013 February 1998 Rev 2 to MPR-1887, Crystal River 3 Reactor Bldg Cooling Fan Logic Mod Failure Modes & Effects Analysis ML20198J8181998-01-10010 January 1998 Assessing Performance & Organizational Roles ML20198J8371998-01-10010 January 1998 Engineering ML20198J8621998-01-10010 January 1998 Maintenance ML20198J8821998-01-10010 January 1998 Licensing ML20198J7501998-01-10010 January 1998 Corrective Action Program Overview ML20198J7811998-01-10010 January 1998 Design & Licensing Basis ML20198J8041998-01-10010 January 1998 Integrated Verification Team Rept ML20198J7291998-01-10010 January 1998 Overall Restart Readiness ML20198J8571998-01-10010 January 1998 Operations ML20198J8881998-01-10010 January 1998 Training ML20198H5071997-12-31031 December 1997 Rev 5 to Justification for Continued Operation for CR Emergency Ventilation Sys & Control Complex Habitability Envelope ML20197B2911997-12-11011 December 1997 Generic Operability Evaluation for Large Bore Safety Related Piping at Crystal River-3 ML20198K4451997-11-30030 November 1997 Reactor Bldg Cooling Fan Logic Mod Failure Modes & Effects Analysis, Rev 0 ML20202D4161997-11-26026 November 1997 Mod Outage Integrated Verification Team Rept ML20199K4731997-11-24024 November 1997 Sys Readiness Review Summary Rept ML20212F4191997-10-31031 October 1997 Revised Boron Dilution by RCS Hot Leg Injection ML20199D5751997-10-30030 October 1997 Overview of Safety Related Large Bore Piping & Piping Support Design & Construction Currently Existing at Crystal River-3 Nuclear Power Plant, Rev 0 ML20198T1051997-10-25025 October 1997 Tracer Gas Air Inleakage Measurements within Crystal River Unit 3 Control Complex Habitability Envelope, Summary Rept ML20211N1771997-10-11011 October 1997 Rev 1 to Pressure/Temp Limits Rept ML20210T9421997-08-29029 August 1997 B Dilution by Hot Leg Injection ML20148K7961997-06-12012 June 1997 Safety Analysis Input to Startup Team Safety Assessment Rept ML20148J3821997-05-23023 May 1997 Rev 16 to PSA F Annunciator Response ML20141D9401997-04-16016 April 1997 Summary Document for Pressurizer NDE Development for FPC Crystal River Unit 3 ML20132F4861996-12-0303 December 1996 Restart Panel ML20133B2711996-10-31031 October 1996 Monthly Trend Rept for Oct 1996 ML20199D5431996-10-28028 October 1996 Evaluation of Piping & Support Documentation for Crystal River 3 ML20134K9581996-10-15015 October 1996 Independent Design Review Panel Rept on 961015 ML20117C6431996-07-25025 July 1996 FPC Crngp Unit 3 Graded Approach Methodology for Instrument Uncertainty ML20101F6081996-02-29029 February 1996 Iga & Wear Voltage Correlations & Uncertainty Analysis ML20100G4141996-02-29029 February 1996 Input to Items a & C of NRC Questions on Relief Request for Insp of Transition Piece to Bottom Head Weld at Crystal River Unit 3 ML20100G4281996-02-0101 February 1996 Flaw Acceptance Handbook for Crystal River Unit 3 RPV & Nozzle Weld Insps ML20095L1461996-01-0202 January 1996 Seismic Evaluation Rept for USI A-46, Rev 0 ML20098A4571995-09-19019 September 1995 Plant Ref Simulator Four Yr Simulator Certification Rept ML20101F6001995-06-30030 June 1995 Alternate Disposition Strategy for Low Vol OTSG Eddy Current Indications ML20092M2061995-06-27027 June 1995 Pyrolysis Gas Chromatography Analysis of 3 Thermo-Lag Fire Barrier Samples ML20084L6931995-05-31031 May 1995 Exam of Crystal River-3 Pulled SG Tubes Final Rept B51956, 8R/9R Bobbin Voltage (S/N) Growth Rate Calculations1995-05-31031 May 1995 8R/9R Bobbin Voltage (S/N) Growth Rate Calculations ML20092M2051995-05-11011 May 1995 Pyrolysis Gas Chromatography Analysis of 5 Thermo-Lag Fire Barrier Samples ML20080T4661995-02-27027 February 1995 Final Rept One & Three H Fire Endurance Tests & Hose Stream Tests Thermal Barrier Sys for Electrical Components 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G0191999-10-15015 October 1999 Safety Evaluation Concluding That Licensee Followed Analytical Methods Provided in GL 90-05.Grants Relief Until Next Refueling Outage,Scheduled to Start on 991001.Temporary non-Code Repair Must Then Be Replaced with Code Repair 3F1099-19, Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated1999-10-13013 October 1999 Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated ML20217B0931999-10-0606 October 1999 Part 21 Rept Re Damaged Safety Grade Electrical Cabling Found in Supply on 990831.Damage Created During Cabling Process While Combining Three Conductors Just Prior to Closing.Vendor Notified of Reporting of Issue ML20212L0881999-10-0404 October 1999 SER Accepting Licensee Requests for Relief 98-012 to 98-018 Related to Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp for Crystal River Unit 3 ML20212J8631999-10-0101 October 1999 Safety Evaluation Supporting Licensee Proposed Alternatives to Provide Reasonable Assurance of Structural Integrity of Subject Welds & Provide Acceptable Level of Quality & Safety.Relief Granted Per 10CFR50.55a(g)(6)(i) ML20212E9031999-09-30030 September 1999 FPC Crystal River Unit 3 Plant Reference Simulator Four Year Simulator Certification Rept Sept 1995-Sept 1999 3F1099-02, Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With ML20212E6911999-09-21021 September 1999 Safety Evaluation Supporting Proposed EALs Changes for Plant Unit 3.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20211L1321999-08-31031 August 1999 EAL Basis Document 3F0999-02, Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With ML20212C1501999-08-31031 August 1999 Non-proprietary Version of Rev 0 to Crystal River Unit 3 Enhanced Spent Fuel Storage Engineering Input to LAR Number 239 ML20211B7291999-08-16016 August 1999 Rev 2 to Cycle 11 Colr ML20210P1111999-08-0505 August 1999 SER Accepting Evaluation of Third 10-year Interval Inservice Insp Program Requests for Relief for Plant,Unit 3 ML20210U5341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Crystal River,Unit 3 ML20209F5601999-07-31031 July 1999 EAL Basis Document, for Jul 1999 3F0799-01, Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With ML20210U5411999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Crystal River,Unit 3 3F0699-07, Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With ML20210U5601999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Crystal River,Unit 3 ML20195C6271999-05-28028 May 1999 Non-proprietary Rev 0 to Addendum to Topical Rept BAW-2346P, CR-3 Plant Specific MSLB Leak Rates ML20196L2031999-05-19019 May 1999 Non-proprietary Rev 0 to BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs 3F0599-04, Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With ML20210U5631999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Crystal River,Unit 3 3F0499-04, Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With ML20204D9661999-03-31031 March 1999 Non-proprietary Rev 1,Addendum a to BAW-2342, OTSG Repair Roll Qualification Rept 3F0399-04, Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease1999-03-10010 March 1999 Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease 3F0399-03, Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With ML20203A4381999-02-0303 February 1999 Safety Evaluation Supporting EAL Changes for License DPR-72, Per 10CFR50.47(b)(4) & App E to 10CFR50 ML20206E9891998-12-31031 December 1998 Kissimmee Utility Authority 1998 Annual Rept ML20206E9021998-12-31031 December 1998 Florida Progress Corp 1998 Annual Rept ML20206E9701998-12-31031 December 1998 Ouc 1998 Annual Rept. with Financial Statements from Seminole Electric Cooperative,Inc 3F0199-05, Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With ML20206E9261998-12-31031 December 1998 Gainesville Regional Utilities 1998 Annual Rept 3F1298-13, Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With 3F1198-05, Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With ML20155F4071998-10-31031 October 1998 Rev 2 to Pressure/Temp Limits Rept ML20155J2701998-10-28028 October 1998 Second Ten-Year Insp Interval Closeout Summary Rept 3F1098-06, Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With ML20206E9461998-09-30030 September 1998 Utilities Commission City of New Smyrna Beach,Fl Comprehensive Annual Financial Rept Sept 30,1998 & 1997 ML20206E9561998-09-30030 September 1998 City of Ocala Comprehensive Annual Financial Rept for Yr Ended 980930 ML20206E9101998-09-30030 September 1998 City of Bushnell Fl Comprehensive Annual Financial Rept for Fiscal Yr Ended 980930 ML20206E9811998-09-30030 September 1998 City of Tallahassee,Fl Comprehensive Annual Financial Rept for Yr Ended 980930 ML20195E3121998-09-30030 September 1998 Comprehensive Annual Financial Rept for City of Leesburg,Fl Fiscal Yr Ended 980930 3F0998-07, Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With ML20236W6501998-07-31031 July 1998 Emergency Action Level Basis Document 3F0898-02, Monthly Operating Rept for Jul 1998 for Crystal River,Unit 11998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Crystal River,Unit 1 ML20236V8801998-07-30030 July 1998 Control Room Habitability Rept 3F0798-01, Monthly Operating Rept for June 1998 for Crystal River Unit 31998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Crystal River Unit 3 ML20236Q4611998-06-30030 June 1998 SER for Crystal River Power Station,Unit 3,individual Plant Exam (Ipe).Concludes That Plant IPE Complete Re Info Requested by GL 88-20 & IPE Results Reasonable Given Plant Design,Operation & History 3F0698-02, Monthly Operating Rept for May 1998 for Crystal River Unit 31998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Crystal River Unit 3 1999-09-30
[Table view] |
Text
. = _ _ _ - -. .
l -
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l.. ,
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 -
I r
I i- PRESSURE / TEMPERATURE LIMITS REPORT o
l REVISION 0 !
Referencing Revised Standard Technical Specifications t
s9080gggj$$$ ohio PDC 2
PDR .
P
1.0 Pressure / Temperature Limits This Pressure-Temperature Limits Report for CR3 has been prepared in accordance with the requirements of Technical Specification Section 1.1.
The pressure / temperature (P/T) limits have been developed using the methodology provided in the references.
The following pressure-temperature limits are included in this report:
- 1) Allowable plant heatup and cooldown rates
- 2) Plant heatup P/T curve
- 3) Plant cooldown P/T curve
- 4) Plant inservice leak and hydrostatic testing P/T curve r
2.0 References
- 1. B&W Fuel Company, topical report BAW-10046A, Rev. 2, " Methods of Compliance With Fracture Toughness and Operational Requirements of 10CFR50, Appendix G," June 1986.
I l
I d
P/T LIMITS REPORT Page 2 of 7
- TABLE OF CONTENTS Page Allowable Pressure / Temperature Rates .. ............ ................................ 4 Pl an t H e a t up Cu rve ..................................................................................... 5 Plan t Cool d own Cu rve .......... ........................................................ ............. 6 Plant Inservice Leak and Hydrostatic Testing Curve............................. 7 l
e i
I i
i i
P/T LIMITS REPORT Page 3 of 7 i
l
ALLOWABLE HEATUP AND COOLDOWN RATES -
- a. A maximum heatup of 1000F in any one hour period,
- b. For the temperature ranges specified below, the cooldown -
rates should be as specified below in any one hour period:
- 1. T > 270 0F - 1 100 F/Hr, ii. 0 150 F Hr, 270 F 2. T > 170 F iii. 170 F 2. T 1 10 0 Hr -
and,
- c. - A maximum temperature change ofless than or equal to 5 F in any one hour period during h
~ above system design pressure. ydrostatic testing operation These limits are referred to by Technical Specification LCO 3.4.9.1 i
l P/T LIMITS REPORT Page 4 of 7
_ - - - _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ . - b
REACTOR COOLANT SYSTEM P/T CURVE FOR HEATUP FOR -
FIRST 8 EFPY-1600 l li ;
i .
THE REGIONS OF ACCEPTABLE OPERA- '
1 1
TION ARE BELOW AND TO THE RIGHT '
i .
0F THE LIMIT CURVES. MARGINS ARE ' '
2400 INCLUDED FOR THE PRESSURE DITTER-INTIAL BETWEEN POINT OF SYSTEM ,[
+ ,
PRESSURE MEASUREMENT AND THE PRES -
SURE ON THE REACTOR VESSEL REGION ,, i 2200 CONTROLLING THE LIMIT CURVE.
MARGINS OF 25 PSIG AND 10 F ARE , [ '
INCLUDED FOR POSSIBLE INSTRUMENT ' ' '
ERROR.
- l. . l ,
2000 * ' i
'l
- i I'
2 l This curve
isoo I referred to by 2 Technical ,
i,/ s
- Specification l
- LCO 3.4.9.1 _l r .
n Isoo -
g
.l m . l A , ,1 i ,.
a
" 1400 w
g
,/: ; i D + i M izoo
' l
m '
i W ./ .
x .
/
A looo i
,/ ,; ,
' i m ,*
,1 f
?
9 , ,
E soo i 1-4- c . .- ... . . .. .
'f APPLICABLE FOR P.EATUP RATES OT 4 100 T/BR (1 50 F IF soo L' ANY 1/2 EDUR PERIOD). '
, i ;
p- e B i i
- . /C POINT TEMPERATUFI PPISSURE 400 !
l' A 70 300 ,
B 157 300
, ,1 - @;. C 236 528 200 D 260 528 f I 266 730
.i.e . '. . .
T 377 2250 l ,
i - , , ,,,. . ,,,,. . , , , , ,,;1. ,
I I ' ' iiii r i e i
, ii[ , l l o too too soo 4o0 soo 600 RCS TEMPERATURE, Te(*F)
P/T LIMITS REPORT Page 5 of 7 l
_ _ _ __ _ - _ - - - _ - _ -- I
I
~~ '
~ i REACTOR COOLANT SYSTEM P/T CURVE FOR COOLDOWN FOR l FIRST 8 EFPY
[
' 7E I " . THE REGIONS OT ACCEPTABLE ,,, , , , ,/ ,, ,,,, ,,, , , , ,, ,
DPERATION ARE BELOW AND 70 a: 1 i TE RIGHT OF THE LIMIT . 'i ' . i/ . . .
CURVES. MARGINS ARE IN- i.
/ ' ' '
2000 CLUDED FOR THI PRESSURE
/
DIFFERENTIAL BETWEEN P0lNT ' '
j ' '
OF SYSTEM PRESSURE AND TE - 1 PRESSURE ON THE P2 ACTOR VEE- l', .'f9,.'l ;.l,, ,ll ;
SEL REGION CONTROLLING THE
3* LIMIT CURVE. MARGINS OF ' '
l' ' ' ' ' * ' ' ' ' '
25 PSIG AND 10 F ARE IN- ,I' l :l, :
CLUDED FOR POSSIBLE INSTRU- -yr 4l ;',,,,,', J MENT ERROR. l,; 'l '
$ i isoo ' '
This curve b 1.
l'. I'4
referred to by = .
WEN TE DECAY HEAT RE- l , Technica! 4 1 C
NOVAL SYSTEM IS OPERATING l
Specification !
WITH NO RC PUMPS OPER- ! ' "-+
LCO 3.4.9.1 C i
- 14oo ATING, THE INDICATED DHR , F--
CD SYSTEM RETURN TEMPERATURE j'lj
, M . ',
Z,*
TO THE REACTOR VESSEL .t g , ., . , ,
y SHALL BE USED. + e i m, .,w.. ..+ . . . .
W 1200 2. AMAXIMJMSTEPTEMgER- l 7-~
g ATURE CHANGE OF 75 F IS ./ , , , ,,, ,
O ALLO 11ABLE WEN REMOVING '- ' '
'O ALL RC PUMPS FROM OPER- E' h
g Coo ATION KITH THE DHR SYS-TEM OPERATING. THE STEP j/ '
A TEMPERATURE CHANGE IS / , , ,
DEFINED AS THE RC TEMP, r- ' - m CO Tc, (PR"DP TO STOPPING I '
O ALL RC PUMPS) MINUS THE / '
E
(AFTER STOPPINi AIS%, [
i RC PUMPS).
l/
..i , APPLICABLE FOR COOLDOWN RATES OT:
1 i of .
,,,;,, j, , , [' T > 270 F 100 F/HR ti ++.>* >4 + ,*. N 270,F > T > 170 F 50 F/HR
l + f: '
X R. 170 F>T 10 F/HR l,
' ~
';. . . ' f : :
4,3 ,,,,.g .
. ,f i . . . . ,
j ...... ......i. ..
g , _._
d,.,w,,,n,
., iM i .i. PCINT TEMPERATURE PRESSURE-~'
i 1 ,
,, ,4 . ,
A 70
,, 325 200 ' '
B 197 473 C 215 525
': l'l l D
326 1840
'!ll4 ,ll .i ... l '. ' :
l l , ,'
, , , i ,
E 377
, i, >l i 2250 6 ..iiii ,
g ([, I i 't I ! 3 t I ! I i iI i ie i , I i 4 I i 1 t il I f
- 8 0 soo soo m 4oo too soo RCS TEMPE ~ TURE, Tc PF)
P/T LIMITS REPORT Page 6 of 7
r REACTOR COOLANT SYSTEM P/T CURVE FOR HEATUP AND COOLDOlVN FOR INSERVICE LEAK AND IIYDROSTATIC TESTS FOR FIRST 8 EFPY rooo . 1 .. 1 THE FICIONS OF ACCEPTABLE OPERA- : HEATUPj. ,llC00LD0tr . '
8 l,
f 1 1 , ,J#- _IF - s
' + m-TION API BELOW AND TO THE RIGHT ,i i
-+
' ' i OF THE LIMIT CURVES. MARGINS
' 1 i
'# ARE INCLUDED FOR THE PRESSURE -)
I DIITERENTIAL BETkTIN POINT OF ; f l ,
SYSTEM PRESSUFI MEASUREMENT AND ,' 'T
' ' i m THE PRESSURE ON THE REACTOR VES- ,
l ./'
SEL REGION CONTROLLING THE LIMIT l r' CURVE. HARGINS OF 25 PSIC AND 1 IO< '
o
' +i 10 F ARE INCLUDED FOR POSSIBLE !'
i e' 'm I
', , , i,,.
. . . ii i,
i!
I goon INSTRUMENT ERROR. i i [f i f1
. _i i>.,. . . . .. .
1 . .Ii FOR COOLDOWN, NCTES 1 & 2 ON l i y f. , ; , , ,j,jj , , , , ;
FIGURE 3.4-3 ARE APPLICABLE.
' i ! ' - 'i - ' '- 'i >i I i r I 1 1 1 1930 r
,! l ; +
_.,m., i i .' . .
i .
i1
,1 n,,
l
-, i'> ,i i , i,, , , 1 I 1 I, , , ,i i 1 , j
.isoo This ctirve ,
- i. .'
.- . .r i .,
i
, i.
referred to be t ._
G : Technical ' __ ll. : , ,
g :. Specification '
c' '
, . l, o., goo ' LCO.3.4.9.1 'l :
- . i ,
/ , ,
La . 1, g - - '
y ,
D i zoo - - , . ,
.v. APPLI p/HR LE FOR MIATUP RATES OF t u.!
- ,; ,/ 5 100 F ( 150'T IN ANY 1/2"
- ; l y- HvUR PERIOD) AND FOR C00LDOWN 0- 1000
'/ "
RATES OF:
.i I , r ,j cn i i , i i i'; i
, 4 O
T > 270OF 100 F/HR ~ ~M O v' i iii
- . . . .i i 1,
. , u ,- i 270 F > T > 170 F 50 F/HR
" 800 170 F > T 10 F/ER [
i 41 4
- 4 .- . . iii.i ,, ii ,,i,,, , ,,,,,,,, i,i i i . 4
~ m i
, gon .
i1 1
i i
.t1 . l j .'.i..,.,...
i l , ,,
_ i . , _ o _ , ,
POINT TEMPERATURE PRESSURE .
i
,A. mu - C 1 i
ll 5---
- =-i l" l
, , A 70 473 , ,
i e A 'S' B 146 473 i i . .,
',, C 191 545 .
.( g_4 1
1 i , , ,
i i i, i 4 D 235 545
, , i i , i, i. .,
E 241 B20 ,, 1 200
' ' ' ' ' ' * ' F 331 1880 i H ;
- ,,, - r
- C 362 2500 -
> i l B 407 2500 ,,;
4 ,,,,, 1
, ,i: , 4 l ' ' ! 'I'!! ! ' A ! l 0 -
0 800 2co soo P- 500 soo l l
l RCS TEMPERATURE, Tc(*F) {
! l Pfr LIMITS REPORT Page 7 of 7 j l
1 i
E____________ J