Similar Documents at Hatch |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212J2721999-10-0101 October 1999 Proposed Tech Specs,Modifying DG Fuel Oil Storage Requirements ML20210G2971999-07-29029 July 1999 Proposed Tech Specs LCO 3.1.7 Re Standby Liquid Control Sys ML20203C5931999-02-0505 February 1999 Proposed Tech Specs Pages Revising TS to Implement Previously Approved Generic Changes ML20199J9081999-01-21021 January 1999 Proposed Tech Specs Increasing Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors ML20197H5171998-12-0404 December 1998 Proposed Tech Specs Section 2.1.1.2,deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & TS Section 5.6.5.b.2 ML20236U2551998-07-22022 July 1998 Proposed Tech Specs Increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors ML20197K1861997-12-18018 December 1997 Marked-up Pages to Licenses DPR-57 & NPF-5,respectively. Proposed Changes Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends 208 & 150 to Manual Holders ML20211A2301997-09-19019 September 1997 Proposed Tech Specs Page 2.0-1 & Corresponding mark-up Page Re SLMCPR ML20210J0491997-08-0808 August 1997 Proposed Tech Specs,Allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8% ML20141B8561997-05-0909 May 1997 Proposed Tech Specs,Revising Operability Requirements for Rod Block Monitor Sys ML20141B7591997-05-0909 May 1997 Proposed Tech Specs 2.1.1.2,revising Safety Limit Minimum Critical Power Ratio to Reflect Results of Cycle Specific Calculation Performed for Unit 1 Operating Cycle 18,expected to Commence in Nov 1997 HL-5376, Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-29029 April 1997 Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits ML20133F3641997-01-0707 January 1997 Proposed Tech Specs Providing Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done ML20132G2261996-12-17017 December 1996 Proposed Tech Specs Re pressure-temp Limits ML20132E0161996-12-13013 December 1996 Proposed Tech Specs Re Physical Security & Contigency Plan & Guard Training & Qualification Plan ML20135D4881996-12-0303 December 1996 Proposed Tech Specs Revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE-13 Fuel in Next Cycle 14 ML20129H9181996-10-29029 October 1996 Proposed Tech Specs,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term Stability Solution Hardware ML20128M8701996-10-0707 October 1996 Proposed Tech Specs to Licenses DPR-57 & NPF-5,increasing Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV & Associated Functions Inoperable ML20113F5541996-09-19019 September 1996 Proposed Tech Specs,Clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves ML20117M2251996-09-11011 September 1996 Proposed Tech Specs,Authorizing Southern Nuclear to Become Licensed Operator & to Have Exclusive Responsibility & Control Over Physical Const,Operation & Maint of Plant ML20115J4861996-07-16016 July 1996 Proposed Tech Specs,Reflecting Changes Through June 1996, Satisfying Requirements of 10CFR50.71 ML20117H1391996-05-21021 May 1996 Proposed Tech Specs 3.5.2,ECCS - Shutdown & 3.5.2.2.b SR for Units 1 & 2 Revise to Change Unit 1 CST Water Level Requirement from 12 Feet to 13 Feet & Change Unit 2 CST Water Level Requirement from 12 Feet to 15 Feet ML20100H7431996-02-21021 February 1996 Proposed Tech Specs,Revising Changes of Drywell Air Temp LCO from 350 F to 150 F ML20094K3831995-11-10010 November 1995 Proposed Tech Specs,Reflecting Implementation of 10CFR50,App J,Option B ML20085K4011995-06-20020 June 1995 Proposed Tech Specs for Power Uprate ML20085A1661995-06-0606 June 1995 Proposed Tech Specs Re Secondary Containment Draw Down & Vacuum Surveillance Requirement Acceptance Criteria ML20082V3791995-05-0404 May 1995 Proposed Tech Specs,Minimizing Thermal Stratification Events ML20082L3331995-04-14014 April 1995 Proposed Tech Specs Re Elimination of Selected Response Time Testing Requirements from TS ML20081F3471995-03-14014 March 1995 Proposed Improved Ts,Permitting Drywell & Wetwell Purge Valves Isolated by Drywell Radiation Monitor Signal to Be Opened W/Inoperable Drywell Radiation Monitor ML20077S0331995-01-13013 January 1995 Proposed Tech Specs Allowing Plant to Operate at Uprated Power Level of 2558 Mwt ML20077D8921994-12-0202 December 1994 Proposed Deleted ETS ML20078G7161994-11-0101 November 1994 Proposed Tech Specs,Converting Current TSs to Improved TS Consistent w/NUREG-1433 ML20076L6911994-10-19019 October 1994 Proposed Improved Tech Specs,Rev F ML20149G3751994-10-13013 October 1994 Proposed Tech Specs,Lowering ATWS-RPT Setpoint by Approx 2 Ft 2 Inches Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained ML20073G9631994-09-23023 September 1994 Proposed Improved Ts,Rev E ML20073D3231994-09-20020 September 1994 Proposed Tech Specs Change to Unit 1 TSs Re EDG Operability Requirements During Reactor Shut Down Conditions ML20072V3641994-08-31031 August 1994 Proposed Tech Specs Re Improved Standard Ts,Rev D ML20072H0571994-08-16016 August 1994 Proposed TS 3.9.C,allowing Shutdown Operations W/Only One of Two Required EDGs Aligned to Corresponding Core or Containment Cooling Sys ML20072E4021994-08-0808 August 1994 Proposed Tech Specs Re Rev Insertion Instructions Rev C ML20072B7541994-08-0404 August 1994 Proposed Tech Specs Re Traversing Incore Probe Operability Requirements ML20071H8381994-07-19019 July 1994 Proposed TS 3.3.6.6,allowing Less than Four Traversing in- Core Probe Machines to Be Operable ML20071H6851994-07-0808 July 1994 Proposed Tech Specs Re Improved Std Insertion Instructions, Consistent w/NUREG-1433 ML20069J3101994-06-0707 June 1994 Proposed Tech Specs Allowing Planned Testing at Plant to Demonstrate Capability to Operate Plant Up to Core Power Level of 2,558 Mwt ML20059E9231994-01-0606 January 1994 Revised Proposed TS Pages for Increase in Allowable MSIV Leakage Rate & Deletion of MSIV Leakage Control Sys ML20059L2051993-11-0909 November 1993 Proposed Tech Specs Changing Unit 1,Section 4.9 & Unit 2, Section 4.8 Re Diesel Generator Testing Under Hot Initial Conditions ML20058P8881993-10-19019 October 1993 Proposed Tech Specs Re Time Delay for RPS Electric Power Monitoring Sys Trips ML20046B6061993-07-30030 July 1993 Proposed Tech Specs for Implementation of New 10CFR20 Requirements ML20046B5561993-07-27027 July 1993 Proposed Tech Specs Showing Original & Unrelated Changes Re Removal of Main Steam Line Radiation Monitor Trips ML20045E7281993-06-28028 June 1993 Proposed TS 3.7.A.4 & 3.6.4.1 for Units 1 & 2,respectively, Allowing One or More Suppression chamber-drywell Vacuum Breakers to Open During Surveillance Testing 1999-07-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212J2721999-10-0101 October 1999 Proposed Tech Specs,Modifying DG Fuel Oil Storage Requirements ML20210G2971999-07-29029 July 1999 Proposed Tech Specs LCO 3.1.7 Re Standby Liquid Control Sys ML20210A4041999-07-15015 July 1999 Ei Hatch Nuclear Plant Unit 1,Extended Power Uprate Startup Test Rept for Cycle 19 ML20204J6031999-03-19019 March 1999 Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15 ML20203C5931999-02-0505 February 1999 Proposed Tech Specs Pages Revising TS to Implement Previously Approved Generic Changes ML20199J9081999-01-21021 January 1999 Proposed Tech Specs Increasing Allowable Values for Reactor Bldg & Refueling Floor Ventilation Exhaust Radiation Monitors ML20197H5171998-12-0404 December 1998 Proposed Tech Specs Section 2.1.1.2,deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & TS Section 5.6.5.b.2 ML20236U2551998-07-22022 July 1998 Proposed Tech Specs Increasing Allowable Values for High Radiation Trip for Reactor Bldg & Refueling Floor Ventilation Exhaust Monitors ML20217A0861998-04-30030 April 1998 Ei Hatch Nuclear Plant,Units 1 & 2,Process for Implementing Technical Requirements of 10CFR54,License Renewal Rule HL-5558, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 181998-02-17017 February 1998 Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 18 ML20197K1861997-12-18018 December 1997 Marked-up Pages to Licenses DPR-57 & NPF-5,respectively. Proposed Changes Delete or Modify Existing License Conditions,Surveillance Requirements That Have Been Completed & Exemptions That Are No Longer in Effect ML20211J1861997-10-0101 October 1997 Corrected TS Pages Unit 1 & 2 Page 3.4-8,Unit 1 Page 3.5-6 & Unit 2 Page 3.5-5 Provided in Order for Util to Issue Amends 208 & 150 to Manual Holders ML20211A2301997-09-19019 September 1997 Proposed Tech Specs Page 2.0-1 & Corresponding mark-up Page Re SLMCPR ML20210J0491997-08-0808 August 1997 Proposed Tech Specs,Allowing Plant to Operate at Uprated Power Level of 2763 Mwt Which Represents Power Level Increase of 8% HL-5438, Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 141997-07-21021 July 1997 Ei Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Rept for Cycle 14 ML20141B7591997-05-0909 May 1997 Proposed Tech Specs 2.1.1.2,revising Safety Limit Minimum Critical Power Ratio to Reflect Results of Cycle Specific Calculation Performed for Unit 1 Operating Cycle 18,expected to Commence in Nov 1997 ML20141B8561997-05-0909 May 1997 Proposed Tech Specs,Revising Operability Requirements for Rod Block Monitor Sys HL-5376, Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits1997-04-29029 April 1997 Proposed Tech Specs 3.4.9 Re Reactor Coolant Sys Pressure & Temp Limits ML20133F3641997-01-0707 January 1997 Proposed Tech Specs Providing Alternate Method of Testing S/Rvs During Shutdown Conditions Rather than During Unit Startup as Is Currently Done ML20138G6271996-12-19019 December 1996 Rev 11 to ODCM for Ei Hatch Nuclear Plant ML20132G2261996-12-17017 December 1996 Proposed Tech Specs Re pressure-temp Limits ML20132E0161996-12-13013 December 1996 Proposed Tech Specs Re Physical Security & Contigency Plan & Guard Training & Qualification Plan ML20135D4881996-12-0303 December 1996 Proposed Tech Specs Revising SLMCPR Values Based Upon Unique plant-evaluations for Current Cycle 13 & Use of GE-13 Fuel in Next Cycle 14 ML20129H9181996-10-29029 October 1996 Proposed Tech Specs,Associating Changes W/Installation of Digital Power Range Neutron Monitoring Sys & Incorporation of long-term Stability Solution Hardware ML20128M8701996-10-0707 October 1996 Proposed Tech Specs to Licenses DPR-57 & NPF-5,increasing Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV & Associated Functions Inoperable ML20113F5541996-09-19019 September 1996 Proposed Tech Specs,Clarifying Applicability of Certain Surveillances Addressing Rvp & Temp Limits & Replacing Vessel Pressure & Temp Limit Curves W/New Curves ML20117M2251996-09-11011 September 1996 Proposed Tech Specs,Authorizing Southern Nuclear to Become Licensed Operator & to Have Exclusive Responsibility & Control Over Physical Const,Operation & Maint of Plant HL-5192, Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 171996-07-18018 July 1996 Edwin I Hatch Nuclear Plant,Unit 1,Power Uprate Startup Test Rept for Cycle 17 ML20115J4861996-07-16016 July 1996 Proposed Tech Specs,Reflecting Changes Through June 1996, Satisfying Requirements of 10CFR50.71 ML20212C1491996-05-31031 May 1996 Stability Monitor ML20117H1391996-05-21021 May 1996 Proposed Tech Specs 3.5.2,ECCS - Shutdown & 3.5.2.2.b SR for Units 1 & 2 Revise to Change Unit 1 CST Water Level Requirement from 12 Feet to 13 Feet & Change Unit 2 CST Water Level Requirement from 12 Feet to 15 Feet ML20100P1041996-03-0404 March 1996 Ei Hatch Nuclear Plant Unit 2 Power Uprate Startup Test Rept for Cycle 13 ML20100H7431996-02-21021 February 1996 Proposed Tech Specs,Revising Changes of Drywell Air Temp LCO from 350 F to 150 F ML20094K3831995-11-10010 November 1995 Proposed Tech Specs,Reflecting Implementation of 10CFR50,App J,Option B ML20093G9401995-10-0505 October 1995 Inservice Insp Program Third 10-Year Interval for Ei Hatch Nuclear Plant Units 1 & 2 ML20092H6461995-07-24024 July 1995 Ei Hatch Nuclear Plant Units 1 & 2 IST Program ML20085K4011995-06-20020 June 1995 Proposed Tech Specs for Power Uprate ML20086E8471995-06-19019 June 1995 Rev 0 to Field Disposition Instruction (Fdi) HT2-0121-12900. Fdi Documents Design Requirements & Matl Required to Install Stabilizers for Shroud Horizontal Welds ML20086E8311995-06-0909 June 1995 Rev 0 to Fabrication Spec 25A5719, Fabrication of Shroud Stabilizer ML20086E8141995-06-0606 June 1995 Rev 1 to Code Design Spec 25A5717, Shroud Stabilizers ML20085A1661995-06-0606 June 1995 Proposed Tech Specs Re Secondary Containment Draw Down & Vacuum Surveillance Requirement Acceptance Criteria ML20086E8121995-05-17017 May 1995 Rev 0 to Design Spec 25A5718, Shroud Repair Hardware ML20082V3791995-05-0404 May 1995 Proposed Tech Specs,Minimizing Thermal Stratification Events ML20082L3331995-04-14014 April 1995 Proposed Tech Specs Re Elimination of Selected Response Time Testing Requirements from TS ML20081F3471995-03-14014 March 1995 Proposed Improved Ts,Permitting Drywell & Wetwell Purge Valves Isolated by Drywell Radiation Monitor Signal to Be Opened W/Inoperable Drywell Radiation Monitor ML20077S0331995-01-13013 January 1995 Proposed Tech Specs Allowing Plant to Operate at Uprated Power Level of 2558 Mwt ML20077D8921994-12-0202 December 1994 Proposed Deleted ETS ML20078G7161994-11-0101 November 1994 Proposed Tech Specs,Converting Current TSs to Improved TS Consistent w/NUREG-1433 ML20076L6911994-10-19019 October 1994 Proposed Improved Tech Specs,Rev F ML20149G3751994-10-13013 October 1994 Proposed Tech Specs,Lowering ATWS-RPT Setpoint by Approx 2 Ft 2 Inches Allowing Restarting Recirculation Pump Following RPT When Temp Differential Between Coolant at Reactor Bottom Head & Reactor Steam Dome Cannot Be Obtained 1999-07-29
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4 I
s-O ENCLO'.URF ^
PLANT hah H - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
TOP OF ACTIVE FUEL R EiRENCE 4
PAGE CHANGE INSTRUCTIONS AND REVISED TECHNICAL SPECIFICATIONS PAGES AND CORRESPONDING MARKUPS HL-2335 000950
$k SDo!K 0$ p P
k 4
- ENCLOSURI 3 5
REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
TOP OF. ACTIVE FUEL REFERENCE- .
PAGE CHANGE INSTRUCTIONS l
s 4
UNIT 1 Remove Pace Insert Paae Figure 2.1-1 Figure 2.1-1 UNIT 2 Remove Pace Insert Paae B 3/4 3-6 B 3/4 3-6 i
1 i
I HL-2335 000950 i
- T NOTE. SCALE IN INCHES ASOVE VESSEL ZERO s
WATER LEVEL NOMENCLATURE HEIGHT ABOVE 800 - - VESSE L ZERO g 44NCwt s) R E ADING INST R UM E NT
- 18) 573.5 + 56.5 BARTOL MOSEMOUNT 750 -- (7) 559 +42 GE/MAC tal 49 +2 - CEMAC 722.75 FLANGE- (3) 517 P.0 BARTON/ROSEMOUNT 700 - - 121 ;470 47 BARTOWROSEMOW (1) 404 113- BARTON/ROSEMOUNT 101 315 -202 SARTON/ROSEMOUNT 650 - -
_ MAIN STE AM 600 - -
,. 577
- 573.5 18l +6 0 - - +60 + 60 - - . +60 T-(8)- 56.5
% - 559 178 gy3 ,47g,agagg
$50 -e 549(41 HPCI 8. idl '32 LO AL ARM BOTTOM OF STE AM .
RCIC TRIPS
-ORvER SKIRT 517(3lNS RUMEM 0 - 0(3) 0-- 0{3)-- RE ACTOR SCRAM
~ ~~ FEEO 500 -- CONTRituTE TO AOS -
,vas gg - 443.5
- LOW (LEVEL 31 3
- 470 (2) -. 47 OW LOW REVEL 2F
-4E ~ CORE g SPRAY INITI ATE HPCI RCIC.
450 - -
~
400 - ~
~ -113 LOW LOvs LOW (LEVEL 11
- 367 -150.. INITIATE RHR, C.S.,
350 L358,56 START OlESEL AND CONTRIBUTE TO A.D,5.
2/3 CORE . CLOSE MSIV%
-202 -- MEIGHT . 315(0)
P E RMISSIVE 300 - -
(LEVEL 01 ACTIVE FUEL j 250 - -
-317 -- 200 208 56
-178 56 -DtSCH ARG E RECIRC SUCTlON - 161.5 NOZZL E NOZZLE 150 --
100 - --
50 --
~
0.
9380I 2 '
FIGURE 2.1-1 REACTOR-VESSEL WATER LEVEL
- liATCH - UNIT 1 techsp\h\92-04BUl\l73-
'0T NOTE: SCALE IN INCHES ABOVE VESSEL 'ERO e
WATER LEVEL NOMENCLATURE HEIGHT ABOVE -
800 -- VESSEL ZERO . ..
g i s N C H E Sl __ RE ADING INSTRUMENT 101 - 573.5 + 56.5 B A RTON/RUSEMOUNT .
750 - - 171 559 +42 GE/MAC VESSEL-~ 141 549 +32 GE/MAC
_ 722.75 F L ANC E '
(3) 517 0.0 BARTON/ROSEMOUNT
- 12: 470 47 BARTON/ROSEMOUNT 00 --
(1) 404 '.113 SARTON/ROSEMOUNT 101 - 315 207 BARTON/ROSEMOUNT 650-
<- 640 - LINE F
600 --
- f715 ISI
+60 - - +60 - -
+60 - + 60 - -
9 - 559 171 (g3- 56.5 . (7) 42 H1 ALARM 550 -r 549(4) HPCI& 141 '32 LO ALARM BOTTOM OF STE AM U" N
- ORYER SKIRT 517(3lNS 0- 0(3) 0-- 0(3F- RE ACTOR SCRAM .
~ ~ FEED -- 443 5 500 --
E
[ CONTRIBUTE TO AOS LOW (LEVEL 31 -
waygg - 470 (2) CORE *
- 465 g INITIATE HPCI. RCIC.
SPR AY 450--
,_ 04 (1) 4g ,
- ~113 LOW LOW LOW (LEVEL 11
- 367 -150 - 1NITIATE HHR, C.S.,
f 350 " 358.56 "
START OIESEL ANO CONTRIBUTE TO A.D.S.
2/3 CORE CLOSE MSIV) '
- 202 HEIGHT 315 (0)
PE AMISSIVE - 300 (LEVEL 01 ACTIV E FUEL' 2So . .
-317 - - 200 208 56 .
j RECIRC -1b $6 OISCHARGE
- Recirculation Pump Trip NO22LE Analytical Limit is 68 inches SUCTlON - 161.5 NOZ2LE - _150 --
100 --
(
3 1
50--
-l 0.
9380-2
' BASES FIGURE B 3/4 3-1 REACTOR VESSEL WATER LEVEL HATCH - UNIT 2- B 3/4 34 .techsp\h\92-04AU2\113
9007 NOTE. SCALE IN INCHES A80VE VESSEL ZERO i .32 WATEft LEVEL NOMENCLATURE -
HEIGHT ABOVE 800 - - VGSSEL ZERO
$ ilNCH E S) R E ADING INSTRUMENT ,
t 81 573.5 +56.5 BARTON/ROSEMOUNT 750 - - (7) 553 +42 GE/MAC
'i 723.56 -. VE SSE~L (4) 54f 42 CE/MAC FLANGE tal 517 0.0 BARTON/ROSEMOUNT ~)
~~ (2) 470 47 BARTON/ROSEMOUNT til '404 113 BARTON/ROSEMOUNT 106 315 +202 BARTON/ROSEMOUNT 650 *
-- 640 -
LINE f
600 - -
,, 577
- 573.5 (8) +60 - - +60 +60 - +60 - -
1 9 - 559 (7) (8)- 56.5 (7) 42HIALARM
$50,-= $49(4)
HPCI& 14) '32 LO ALARM BOTTOM OF STE AM -
RCIC TRIPS
- ORYER SKIRT 517-
/
, 0 - 0(3) 0-- 0(31 -- R EACTOR SCRAM 17 - - FEEO ~ 500 - - CONTRIBUTE TO AOS LOW (LEVEL 3)
WATER - 470 (2) '
% --47 LOW LOW (LEVEL 2)
(465 - QRE Spgay p INITI ATE HPCI, RCtC, 450 - -
400 --~ 4C4 (1i
- -113 LOW LUW LOW (LiVEL 11
- 367 1 ;#, f 4 - 150 -- INITIATE RHR, C.S., f 350 -uM244 START OIESEL AND CONTRIBUTE TO A.O.S.
2/3 CORE CLOSE MSIV's
- 202 H EIGHT 315 (0)
P E RMIS$4V E 300 - -
(LEVEL 0) ACTIVE FUEL 250 --
-317 -- 200 = 2c0 56 RECIRC
"' ' -OISCH ARGE
-SUCTION - 161.5 NO22LE NO22LE 150 - -
100 --
50 --
0.-
9300 2 i
FIGURE 2.11 REACTOR VESSEL WATER LEVEL
)
HATCH - UNIT 1 Amendment No.14h 141, K4,173 1
l
\
900 T*
NOTE. SCALEININCHES ABOVE VESSEL ZERO 9
WATER LEVEL NOMENCLATURE ,
HEIGHT ABOVE 800 - - VESSEL ZERO NO. IINCHFSI RE ADING INST R UM E NT
- 18) $T3 5 +56.5 BARTON/ROSEMOUNT
+
750 -- lyn 559 +42 OE/MAC tal 54 9 +32 Q F,/MAC
_ 22J5 , VESSEL ggggg
- 43) 517 0.0 BA'xiON/ROSEMOUNT (2) 470 . 47 BARTON/ROSEMOUNT 7g . _ '
til 404 -113 SARTON/ROSEMOUNT tot 315 2G BARTON/ROSFMOUNT 650 - - MAIN STE AM
<-- 640 - gg 600 - -
~ 73.5 681 *60 -- +60 - *60 - +60 - -
- 559 175 (81 . 56.5 t yl
550 - 2 549(4) HPCI& (4) '32 LO ALARM' BOTTOM OF STE AM .
SCIC TRW /
-ORYER SKIRT - 517(3) STRUMENT 0 ~ 0(3r 0-- Ot3h REACTOt JCRAM 2 CONTRIBUTE TO ADS LOW (LEVEL 31
--- FEED 500 - -
-'*** - 470 (2) m e mn 2r wA7tR CORE % - d' 2,N g INITIATE HPCI, RCIC, SPRAY 450 --
UI 400 .~
- -113 LOW LUW LOW (LEVEL 11 INITI ATE RH R. C.S., ,_
- 367 .D #,a c, - 150 --
k 33, .. 35 ;5g START OlESEL ANO
" CONTRIBUTE TO A O.S. .
2/3 CORf CLOSE MSivi
-302 HEICHT 315 (01 P E RMISSIV E 300 --
{LEVELO) ACTfvE FUEL 250 - -
-317 - - 200 = 208.56
-1 8 6 -OISCH A RG g %Mata Nmp Np RECIRC Analytical Limit is . 58 inches SUCT TON - 161.5 NOZZLE NO22LE 150 - -
100 - -
50 -
0.
9340 2 -
BASES FIGURE B 3/4 31 !
REACTOR VESSEL WATER LEVEL B 3/4 3-6 Amendment No. 4 , G , 113 q HATCH - UNIT 2
_ _ o