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| {{#Wiki_filter:rr~t!y~y cGN~RQ4~c~~MCPR OPERATING LIMITS MCPR Operating 1 imit, Uo to 106M Core Flow 2.3.Cycl e Exposure gg5'o 0 MMD-~X MMD HIU HTU g750 NMO" FOC MMO NTU Mt Lf+750 WD-EOC MMO biTU HTU Equipment Status Hormal scram times"" Control rod insertion bounded by Tech.Spec.limits (3.1.3.4-p 3/4 1-7)G Fuel/.Vo AHF Fuel/,3//.3$'.5'o 1,37 g1$'o 4.~MMD-EOC MMD Hl U HK p 750 5.~~0'MO" EOC MMO HTU NIU RPT inoperable Hormal scram times/.55 RPT inoperable Control rod insertion bounded by Tech.Spec.limits (3.1.3.4-p 3/4 1-7)goC~~FFTR/~DR~WC.gCnA e~f kfpS~~-In this portion of the fuel cycle, operaiion with the given MCPR operating limits is allowed for boih normal and Tech.Spec.scram times and for both RPT oper able and inoperable. | | {{#Wiki_filter:~y cGN ~RQ4~c~ |
| "."These MCPR values are based on the AHF Reload Safety Analysis performed using the control rod insertion times shown below (defined as normal scram)~In the event that surveillance 4.1.3.2 shows these scram insertion times have been exceeded, the plant thermal limits associated with normal scram times default to the values associated with Tech.Spec.scram times (3.1.3.4-p 3/4 1-7), and the scram insertion times must meet ihe requirements of Tech.Spec.3.1.3.4.AV OS U1%OO ,QOw Inuv~t3%V Position Inserted From Full Mithdrawn Slowest measured averaae control rod insertion times io specified notches for all operable control rods for each group of 4 control rods arranged in a a two-bv-two arraY (seconds).404:eeo l.504 2 624 Hotch 45 Hotch 39 Hotch 25 otc 5 wmO NX 4 7, 5oc P~F'p 7 W coArtR04 Ro I hJSGB.v ioV fiouVDBO~8p'"'Ecru. | | ~ MCPR OPERATING LIMITS rr t!y |
| 5PEc.Lim(ry (y./, p.4W 7/V Si MGC.B/oo P o PERE TsoLt RP~Pen.egg.9'A 2 342-f EMP/U6 NRC P/'Phovhl. | | ~ |
| o/=F-/=7m>~~~.PE+a/M C Ngc p/'('Rovh/- | | MCPR Operating 1 imit, Uo to 106M Core Flow Cycl e Equipment Exposure Status G Fuel AHF Fuel gg5'o 0 MMD - ~X MMD HIU HTU g750 /. Vo /,3/ |
| oF 5/QG/-/=0 z-v)(40~l'~>>r\v/,yT menamen.45 g/gE~5'/AJG p pr!EV(/HEARST | | : 2. NMO " FOC MMO Hormal scram times"" |
| /ODP g((Eu5/uG 8//EMPIRE/JT l V~~OIL CO Z Z Q 0 Z Z C o m Zl C Z 70 60 I Q;K 50 40 l 1 30 L 0'O j 20 10 j".~j 0 30 40 50 Core Flow (%Rated)60 70 880197.5M Thermal Power Limits of Specification 3.3.10-1 Fi g ure 3.3.10-1 i 4 I~1l,a | | NTU Mt Lf |
| ~'>'",>~>>>>>W yaw>>>j L>>L k>'>j*~>>('>.of Pated Thermal Power$10, WNP-2 Power History<Cycle 3)POHER 1P0.90'8 78, 60'0.20.$~~0.;JUll JUL AUG SEP FEB HAR APR HAY OCT WOV DEC JAN JUAe 3'o l'lay 88 Figure 3.1 Power History For MNP-2 For Cycle 3}} | | +750 /.3$ |
| | : 3. WD - EOC MMO Control rod insertion biTU HTU bounded by Tech. Spec. |
| | limits (3.1.3.4-3/4 1-7) |
| | : 4. ~ |
| | g1$ 'o MMD Hl U |
| | - EOC MMD HK p |
| | RPT inoperable Hormal scram times 5'o |
| | /. 55 1,37 p 750 |
| | : 5. ~~0'MO " EOC MMO RPT inoperable HTU NIU Control rod insertion bounded by Tech. Spec. |
| | limits (3. 1.3.4-3/4 1-7) goC ~~ p FFTR |
| | ~ DR~WC. gCnA e ~f kfpS ~ ~ |
| | / |
| | -In this portion of the fuel cycle, operaiion with the given MCPR operating limits is allowed for boih normal and Tech. Spec. scram times and for both RPT oper able and inoperable. |
| | ". "These MCPR values are based on the AHF Reload Safety Analysis performed using the control rod insertion times shown below (defined as normal scram) ~ In the event that surveillance 4. 1. 3. 2 shows these scram insertion times have been exceeded, the plant thermal limits associated with normal scram times default to the values associated with Tech. Spec. scram times (3.1.3.4-p 3/4 1-7), |
| | and the scram insertion times must meet ihe requirements of Tech. Spec. |
| | 3.1. 3. 4. |
| | AV OS Slowest measured averaae control rod U1% insertion times io specified notches OO for all operable control rods for each |
| | ,QOw Position Inserted From group of 4 control rods arranged in a Inuv |
| | ~t3% Full Mithdrawn a two-bv-two arraY (seconds) |
| | V Hotch 45 . 404 Hotch 39 :eeo Hotch 25 l. 504 NX 4 otc 5 2 624 7, 5oc wmO F'p 7 W coArtR04 Ro 0 pr!EV(/HEARSTl' I hJSGB.v ioV v |
| | ~ |
| | ~ >> r\ |
| | 5PEc. Lim(ry (y./, p. 4W 7/V z-v) fiouVDBO~8p'"'Ecru. |
| | P ~ |
| | Si RP~ |
| | MGC.B / oo P o PERE TsoLt Pen.egg. 9 'A |
| | ( 40 /,yT 2 342- menamen . 45 f EMP/U6 NRC P/'Phovhl. o/= F-/=7m g /gE ~5'/AJG p |
| | > ~~~. PE+a/M C Ngc p /'('Rovh/- oF 5/QG/-/= /ODP g((Eu5/uG 8//EMPIRE/JT |
| | |
| | l V |
| | ~ ~ OIL |
| | |
| | CO Z |
| | Z 70 Q |
| | 0Z Z |
| | C o 60 m |
| | Zl I Q C |
| | Z ; K 50 40 l |
| | 1 30 L |
| | 0 O |
| | j 20 10 0 |
| | j".j 30 40 50 60 70 |
| | ~ |
| | Core Flow (% Rated) 880197.5M Thermal Power Limits of Specification 3.3.10-1 Fi g ure 3.3.10-1 |
| | |
| | i 4 |
| | I ~ 1l,a |
| | |
| | ~ ' >'", > ~ >>>>>W yaw >> >j L >> L k> '> j * ~ >>('>. |
| | WNP-2 Power History <Cycle 3) of Pated Thermal Power |
| | $ 10, POHER 1P0. |
| | 90 |
| | '8 78, 60 |
| | '0. |
| | 20. |
| | ~ ~ |
| | : 0. APR HAY |
| | ; JUll JUL SEP OCT WOV DEC JAN FEB HAR AUG JUAe 3'o l'lay 88 Figure 3.1 Power History For MNP-2 For Cycle 3}} |
|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17284A9121999-10-13013 October 1999 Proposed Tech Specs 3.3.6.1,Table 3.3. 6.1-1, Primary Containment Isolation Instrumentation. ML17284A8521999-07-29029 July 1999 Proposed Tech Specs 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17284A8491999-07-29029 July 1999 Proposed Tech Specs,Revising SR 3.5.2.2 Re Condensate Storage Tank Water Level ML17284A8461999-07-29029 July 1999 Proposed Tech Specs,Revising Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & E.A. ML17284A8421999-07-29029 July 1999 Proposed Tech Specs Revising SR of TS 3.8.4, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17333A0021999-04-20020 April 1999 Proposed Tech Specs Section 3.4.11,replacing Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6341999-04-0707 April 1999 Proposed Tech Specs Modifying MCPR Safety Limits to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B4881998-12-17017 December 1998 Proposed Tech Specs SR 3.8.1.8,allowing Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML20198A7051998-11-30030 November 1998 Revs 8 Through 13 to TS Bases & Revs 12 Through 15 of Licensee Controlled Specs ML17284A7181998-08-0505 August 1998 Proposed Tech Specs SR 3.8.4.7,allowing Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7071998-07-17017 July 1998 Proposed Tech Specs Modifying SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc,Battery E-B1-2 ML17292B2831998-03-0909 March 1998 Proposed Tech Specs Establishing Interim SLMCPR for Siemens Power Corp ATRIUM-9X Fuel Applicable to Cycle 14 Only ML17292B1321997-12-0404 December 1997 Proposed Tech Specs Modifying Min Critical Power Ratio Safety Limits ML17292B0281997-08-14014 August 1997 Proposed Tech Specs Revising TS 5.5.6 by Adding Note That Would Extend Interval Requirement to Perform Full Stroke Exercise Testing of TIP-V-6 Until 1998 Refueling Outage ML17292A9691997-08-12012 August 1997 Proposed Tech Specs Supporting Request for Enforcement Discretion for Period of 45 Days from TS Action 3.6.1.3.A Required Actions to Isolate Purge Line & Verify Penetration Flow Path Isolated Every 31 Days ML17292A9421997-07-16016 July 1997 Proposed Tech Specs Adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 EFPYs ML17292A8901997-06-0606 June 1997 Revised Tech Spec Page 2.0-1 Modified to Indicate That SLMCPR for ATRIUM-9X Fuel Applies Only to Cycle 13 & Corresponding Bases Pages ML17292A8651997-05-20020 May 1997 Proposed Tech Specs,Requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A7631997-03-24024 March 1997 Rev 7 to Licensee Controlled Specs. ML17292A7621997-03-24024 March 1997 Rev 5 to TS Bases. ML17292A7581997-03-22022 March 1997 Proposed Tech Specs Modifying Response Time Testing SR for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A7531997-03-20020 March 1997 Proposed Tech Specs Re Response Time Testing Requirements ML17292A6591997-01-14014 January 1997 Proposed Tech Specs Reflecting Compilation of TS Change Requests Submitted to NRC in Ltrs Dtd 951208,960709 & 1212 ML17292A6341996-12-12012 December 1996 Proposed Tech Specs Requesting Conversion Based Upon NUREG-1434,rev 1 ML17292A5511996-10-15015 October 1996 Proposed Tech Specs Re Secondary Containment & SGTS to Reflect Revised Secondary Containment Drawdown & post- Accident Analyses Results ML17292A5411996-10-10010 October 1996 Proposed Tech Specs Requesting Addition of Section 2B(6) Re Storage of Byproduct,Source & Special Nuclear Materials ML17292A4501996-09-0606 September 1996 Proposed Tech Specs,Containing Corrections to Factual Statements & Proposed Info to Clarify Evaluations ML17292A4111996-08-0909 August 1996 Proposed Tech Specs,Revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 ML17292A3561996-07-0909 July 1996 Proposed Tech Specs,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of NSHC or Environ Assessment Provided Rev a ML20107M3391996-04-24024 April 1996 Proposed Tech Specs,Modifying TS to Support Cycle 12, Scheduled to Begin Subsequent to Spring 1996 Outage ML17292A1511996-04-22022 April 1996 Proposed Tech Specs,Supplementing TS That Describes Administrative & Editorial Changes to Section 6.0, Administrative Controls. ML17291B2801996-03-19019 March 1996 Proposed Tech Specs Re Containment Leakage Testing ML17291B2491996-02-26026 February 1996 Proposed Tech Specs,Submitting Revised Copy of TS Bases Which Include Minor Changes & Clarifications Made Per Requirements of 10CFR50.59 ML17333A0201996-01-19019 January 1996 Proposed Tech Specs Re Primary Containment Leakage Testing ML17291B0941995-10-26026 October 1995 Proposed Tech Specs,Replacing Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A9911995-08-16016 August 1995 Proposed Tech Specs Page 3/4 4-4,incorporating Surveillance Notes in Front of Surveillances 4.4.1.2.1 & 4.4.1.2.2 for Jet Pump Operability to Clarify That Notes Apply to Each Surveillance ML17291A8441995-06-0606 June 1995 Proposed Tech Specs Section 6.0, Administrative Controls. ML17291A8401995-06-0606 June 1995 Proposed Tech Specs Index,Deleting Ref to Bases Pages ML17291A8371995-06-0606 June 1995 Proposed Tech Specs Section 6.9.3.2,adding Ref to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications ML17291A7561995-04-25025 April 1995 Proposed Tech Specs,Adding RWCU Sys High Blowdown Containment Isolation Trip Function & Associated LCO & SRs to Tables 3.3.2-1,3.3.2-2 & 4.3.2.1-1 ML17291A6541995-02-10010 February 1995 Proposed Tech Specs,Modifying Surveillance Acceptance Criteria from 10% to 20% for Individual Jet Pump diffuser- to-lower Plenum Differential Pressure Variations of Individual Jet Pump from Established Patterns ML17291A4811994-10-31031 October 1994 Proposed Tech Spec Relocating Safety/Relief Valve Position Indication Instrumentation Requirements ML17291A4781994-10-31031 October 1994 Proposed Tech Spec 3/4.1.3.1, Reactivity Control Sys. ML17291A4451994-10-12012 October 1994 Corrected Proposed TS Bases 3/4.2.6, Power/Flow Instability. ML17291A4221994-09-26026 September 1994 Proposed Tech Specs,Reflecting Use of Siemens Power Corp Staif Code for Stability Analysis,Per Ieb 88-007,Suppl 1 ML17291A3981994-09-18018 September 1994 Proposed TS Table 3.6.3-1 Re Primary Containment Isolation Valve Requirements ML17291A3191994-08-0808 August 1994 Proposed Tech Specs 4.0.5 Re Guideliness for Inservice Insp & Testing Program ML17291A2171994-07-12012 July 1994 Proposed Tech Specs for Relocation of TS Tables for Instrument Response Time Limits ML17291A2221994-07-0808 July 1994 Proposed TS W/Regard to Control Rod Scram Insertion Testing Under Emergency Circumstances ML17291A1561994-06-23023 June 1994 Proposed Tech Specs Re Supporting Hydrostatic Testing 1999-07-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17284A9121999-10-13013 October 1999 Proposed Tech Specs 3.3.6.1,Table 3.3. 6.1-1, Primary Containment Isolation Instrumentation. ML17284A8761999-08-27027 August 1999 Replacement Page 9 of 9 to Attachment 4 of Procedure 13.10.6 ML17284A8491999-07-29029 July 1999 Proposed Tech Specs,Revising SR 3.5.2.2 Re Condensate Storage Tank Water Level ML17284A8421999-07-29029 July 1999 Proposed Tech Specs Revising SR of TS 3.8.4, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17284A8461999-07-29029 July 1999 Proposed Tech Specs,Revising Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & E.A. ML17284A8521999-07-29029 July 1999 Proposed Tech Specs 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17333A0021999-04-20020 April 1999 Proposed Tech Specs Section 3.4.11,replacing Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6341999-04-0707 April 1999 Proposed Tech Specs Modifying MCPR Safety Limits to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B5731999-03-0101 March 1999 ODCM for WNP-2 ML17292B4881998-12-17017 December 1998 Proposed Tech Specs SR 3.8.1.8,allowing Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML20198A7051998-11-30030 November 1998 Revs 8 Through 13 to TS Bases & Revs 12 Through 15 of Licensee Controlled Specs ML17284A7181998-08-0505 August 1998 Proposed Tech Specs SR 3.8.4.7,allowing Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7071998-07-17017 July 1998 Proposed Tech Specs Modifying SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc,Battery E-B1-2 ML17284A6431998-05-29029 May 1998 Revised Plant Procedure Sys for Site Wide Procedures, Replacing Pages Located in Manual W/Pages in Package ML17292B2831998-03-0909 March 1998 Proposed Tech Specs Establishing Interim SLMCPR for Siemens Power Corp ATRIUM-9X Fuel Applicable to Cycle 14 Only ML17292B2591998-01-31031 January 1998 Offsite Dose Calculation Manual. ML17292B1321997-12-0404 December 1997 Proposed Tech Specs Modifying Min Critical Power Ratio Safety Limits ML17292B0281997-08-14014 August 1997 Proposed Tech Specs Revising TS 5.5.6 by Adding Note That Would Extend Interval Requirement to Perform Full Stroke Exercise Testing of TIP-V-6 Until 1998 Refueling Outage ML17292A9691997-08-12012 August 1997 Proposed Tech Specs Supporting Request for Enforcement Discretion for Period of 45 Days from TS Action 3.6.1.3.A Required Actions to Isolate Purge Line & Verify Penetration Flow Path Isolated Every 31 Days ML17292A9421997-07-16016 July 1997 Proposed Tech Specs Adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 EFPYs ML17292A8901997-06-0606 June 1997 Revised Tech Spec Page 2.0-1 Modified to Indicate That SLMCPR for ATRIUM-9X Fuel Applies Only to Cycle 13 & Corresponding Bases Pages ML17292A8651997-05-20020 May 1997 Proposed Tech Specs,Requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A8301997-03-31031 March 1997 Wppss WNP-2 RPV Surveillance Matls Testing & Analysis. ML17292A7621997-03-24024 March 1997 Rev 5 to TS Bases. ML17292A7631997-03-24024 March 1997 Rev 7 to Licensee Controlled Specs. ML17292A7581997-03-22022 March 1997 Proposed Tech Specs Modifying Response Time Testing SR for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A7531997-03-20020 March 1997 Proposed Tech Specs Re Response Time Testing Requirements ML17292A6591997-01-14014 January 1997 Proposed Tech Specs Reflecting Compilation of TS Change Requests Submitted to NRC in Ltrs Dtd 951208,960709 & 1212 ML17292A6341996-12-12012 December 1996 Proposed Tech Specs Requesting Conversion Based Upon NUREG-1434,rev 1 ML17292A6161996-11-19019 November 1996 Rev 1 to WNP-2 IST Program Plan (Pumps & Valves) 2nd Interval (941213-041212). ML17292A5511996-10-15015 October 1996 Proposed Tech Specs Re Secondary Containment & SGTS to Reflect Revised Secondary Containment Drawdown & post- Accident Analyses Results ML17292A5411996-10-10010 October 1996 Proposed Tech Specs Requesting Addition of Section 2B(6) Re Storage of Byproduct,Source & Special Nuclear Materials ML17292A4501996-09-0606 September 1996 Proposed Tech Specs,Containing Corrections to Factual Statements & Proposed Info to Clarify Evaluations ML17292A4111996-08-0909 August 1996 Proposed Tech Specs,Revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 ML17292A3561996-07-0909 July 1996 Proposed Tech Specs,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of NSHC or Environ Assessment Provided Rev a ML17292A7241996-05-31031 May 1996 Offsite Dose Calculation Manual. ML17292A2741996-04-25025 April 1996 Rev 0 to UT-WNP2-208V0, Exam Summary Sheet. ML20107M3391996-04-24024 April 1996 Proposed Tech Specs,Modifying TS to Support Cycle 12, Scheduled to Begin Subsequent to Spring 1996 Outage ML17292A1511996-04-22022 April 1996 Proposed Tech Specs,Supplementing TS That Describes Administrative & Editorial Changes to Section 6.0, Administrative Controls. ML17291B2801996-03-19019 March 1996 Proposed Tech Specs Re Containment Leakage Testing ML17291B2491996-02-26026 February 1996 Proposed Tech Specs,Submitting Revised Copy of TS Bases Which Include Minor Changes & Clarifications Made Per Requirements of 10CFR50.59 ML17333A0201996-01-19019 January 1996 Proposed Tech Specs Re Primary Containment Leakage Testing ML17291B1751995-12-31031 December 1995 Reactor Power Uprate Startup Test Rept, for WNP-2. W/951215 Ltr ML17291B0941995-10-26026 October 1995 Proposed Tech Specs,Replacing Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A9911995-08-16016 August 1995 Proposed Tech Specs Page 3/4 4-4,incorporating Surveillance Notes in Front of Surveillances 4.4.1.2.1 & 4.4.1.2.2 for Jet Pump Operability to Clarify That Notes Apply to Each Surveillance ML17291A9591995-07-28028 July 1995 Operations Instructions OI-23,Rev a to, Human Performance Improvement Program. ML20087E2831995-07-26026 July 1995 Performance Enhancement Strategy 1995 ML17291A8401995-06-0606 June 1995 Proposed Tech Specs Index,Deleting Ref to Bases Pages ML17291A8371995-06-0606 June 1995 Proposed Tech Specs Section 6.9.3.2,adding Ref to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications ML17291A8441995-06-0606 June 1995 Proposed Tech Specs Section 6.0, Administrative Controls. 1999-08-27
[Table view] |
Text
~y cGN ~RQ4~c~
~ MCPR OPERATING LIMITS rr t!y
~
MCPR Operating 1 imit, Uo to 106M Core Flow Cycl e Equipment Exposure Status G Fuel AHF Fuel gg5'o 0 MMD - ~X MMD HIU HTU g750 /. Vo /,3/
- 2. NMO " FOC MMO Hormal scram times""
NTU Mt Lf
+750 /.3$
- 3. WD - EOC MMO Control rod insertion biTU HTU bounded by Tech. Spec.
limits (3.1.3.4-3/4 1-7)
- 4. ~
g1$ 'o MMD Hl U
- EOC MMD HK p
RPT inoperable Hormal scram times 5'o
/. 55 1,37 p 750
- 5. ~~0'MO " EOC MMO RPT inoperable HTU NIU Control rod insertion bounded by Tech. Spec.
limits (3. 1.3.4-3/4 1-7) goC ~~ p FFTR
~ DR~WC. gCnA e ~f kfpS ~ ~
/
-In this portion of the fuel cycle, operaiion with the given MCPR operating limits is allowed for boih normal and Tech. Spec. scram times and for both RPT oper able and inoperable.
". "These MCPR values are based on the AHF Reload Safety Analysis performed using the control rod insertion times shown below (defined as normal scram) ~ In the event that surveillance 4. 1. 3. 2 shows these scram insertion times have been exceeded, the plant thermal limits associated with normal scram times default to the values associated with Tech. Spec. scram times (3.1.3.4-p 3/4 1-7),
and the scram insertion times must meet ihe requirements of Tech. Spec.
3.1. 3. 4.
AV OS Slowest measured averaae control rod U1% insertion times io specified notches OO for all operable control rods for each
,QOw Position Inserted From group of 4 control rods arranged in a Inuv
~t3% Full Mithdrawn a two-bv-two arraY (seconds)
V Hotch 45 . 404 Hotch 39 :eeo Hotch 25 l. 504 NX 4 otc 5 2 624 7, 5oc wmO F'p 7 W coArtR04 Ro 0 pr!EV(/HEARSTl' I hJSGB.v ioV v
~
~ >> r\
5PEc. Lim(ry (y./, p. 4W 7/V z-v) fiouVDBO~8p'"'Ecru.
P ~
Si RP~
MGC.B / oo P o PERE TsoLt Pen.egg. 9 'A
( 40 /,yT 2 342- menamen . 45 f EMP/U6 NRC P/'Phovhl. o/= F-/=7m g /gE ~5'/AJG p
> ~~~. PE+a/M C Ngc p /'('Rovh/- oF 5/QG/-/= /ODP g((Eu5/uG 8//EMPIRE/JT
l V
~ ~ OIL
CO Z
Z 70 Q
0Z Z
C o 60 m
Zl I Q C
Z ; K 50 40 l
1 30 L
0 O
j 20 10 0
j".j 30 40 50 60 70
~
Core Flow (% Rated) 880197.5M Thermal Power Limits of Specification 3.3.10-1 Fi g ure 3.3.10-1
i 4
I ~ 1l,a
~ ' >'", > ~ >>>>>W yaw >> >j L >> L k> '> j * ~ >>('>.
WNP-2 Power History <Cycle 3) of Pated Thermal Power
$ 10, POHER 1P0.
90
'8 78, 60
'0.
20.
~ ~
- 0. APR HAY
- JUll JUL SEP OCT WOV DEC JAN FEB HAR AUG JUAe 3'o l'lay 88 Figure 3.1 Power History For MNP-2 For Cycle 3