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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML20211B7351999-05-31031 May 1999 Cycle 7 Colr ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 ML20084K7441995-03-13013 March 1995 COLR for Cycle 6 Operation ML20078N4921995-01-31031 January 1995 COLR Cycle 13, Rev 0 ML20059L2641993-08-31031 August 1993 Cycle 5 Colr ML20106E3311992-10-30030 October 1992 Rev 5 to Millstone Unit 2 Cycle 12 Colr ML20091A5481992-03-23023 March 1992 Rev 4 to Millstone Unit 2,Cycle 11 Core Operating Limits Rept ML20087B4721992-01-31031 January 1992 Revised Millstone Nuclear Power Station Unit 3,Startup Test Rept,Cycle 4 ML20086T2581991-12-24024 December 1991 Revised Tables to Core Operating Limits Rept for Cycle 4 Operation, Consisting of Control Rod Bank Insertion Limits Vs Thermal Power four-loop Operation & three-loop Operation ML20085L1121991-10-31031 October 1991 Rev 3 to Millstone Unit 2,Cycle 11 Core Operating Limits Rept ML20077H0421991-06-30030 June 1991 Rev 2 to Millstone Unit 2 Cycle 11 Core Operating Limits Rept ML20070Q1771991-03-21021 March 1991 Core Operating Limits Rept for Cycle 4 Operation, Addressing Both Three & Four Loop Operation ML20065N6041990-11-30030 November 1990 Rev 1 to Millstone Unit 2 Cycle 11 Core Operating Limits Rept ML20065K0821990-11-30030 November 1990 Rev 0 to Millstone Nuclear Power Station,Unit 2 Cycle 11 Core Operating Limits Rept ML20058E6341990-10-31031 October 1990 Rev 0 to Millstone,Unit 2 Cycle 11 Core Operating Limits Repts ML20011F4361990-02-28028 February 1990 Rev 0 to Millstone Unit 3 Cycle 3 Core Operating Limits Rept. ML20247N0741989-05-31031 May 1989 Rev 1 to, Reload Safety Evaluation for Millstone Unit 3 Cycle 3 ML20244B4821989-04-30030 April 1989 Reload Safety Evaluation,Millstone Unit 3,Cycle 3 ML20155J4711988-10-31031 October 1988 Cycle 10 Sar ML20155G5911988-10-0404 October 1988 Small Break LOCA Analysis ML20153F8271988-08-31031 August 1988 Large Break Loca/Eccs Analysis ML20235R4491987-07-31031 July 1987 Errata & Addenda 1 to 23A4845, Supplemental Reload Licensing Submittal for Millstone Unit 1,Reload 11 ML20214L6861987-05-21021 May 1987 Rev 0 to Supplemental Reload Licensing Submittal ML20215N8271986-09-30030 September 1986 Rev 2 to Reload Safety Evaluation,Millstone Nuclear Power Station,Unit 2 Cycle 8 ML20134K4241985-08-31031 August 1985 Rev 0 to Supplemental Reload Licensing Submittal for Millstone Unit 1,Reload 10 ML20126J1811985-06-30030 June 1985 Cycle 7 Final Reload Safety Analysis ML20073M2451983-04-30030 April 1983 Reload Safety Analysis 1999-05-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 ML20211N8401999-09-0202 September 1999 Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10 B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20211A6561999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2 B17858, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With B17856, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With ML20210J0311999-07-21021 July 1999 Rev 20,Change 10 to QAP 1.0, Organization ML20210E5931999-07-19019 July 1999 Revised Page 16 of 21,to App F of Northeast Util QA Program Plan ML20210C5911999-07-15015 July 1999 Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes ML20210A0411999-07-15015 July 1999 Rev 20,change 10 to Northeast Util QA Program Tr B17814, Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start1999-07-12012 July 1999 Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start ML20209D1881999-07-0101 July 1999 Rev 20,change 9 to Northeast Util QA Program Tr ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20211A6751999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level & Operating Data Rept ML20196A8451999-06-30030 June 1999 Post Shutdown Decommissioning Activities Rept ML20209J0541999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Unit 2 B17830, Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With ML20196K1791999-06-30030 June 1999 Addendum 6 to Millstone Unit 2 Annual Rept, ML20196J1821999-06-30030 June 1999 Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr B17833, Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With ML20195H1011999-06-11011 June 1999 Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20211A6631999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level,Operating Data Rept & Unit Shutdowns & Power Reductions B17808, Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With ML20211B7351999-05-31031 May 1999 Cycle 7 Colr B17804, Monthly Operating Rept for May 1999 for Mnps,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 2.With B17807, Monthly Operating Rept for May 1999 for Mnps,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 1.With ML20209J0661999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206J8351999-05-0707 May 1999 Rev 20,Change 7 to QAP-1.0, Northeast Utls QA Program (Nuqap) Tr ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 B17782, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With ML20205R3531999-04-30030 April 1999 Addendum 4 to Annual Rept, B17775, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With ML20205K6141999-04-30030 April 1999 Non-proprietary Version of Rev 2 to Holtec Rept HI-971843, Licensing Rept for Reclassification of Discharge in Millstone Unit 3 Spent Fuel Pool ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 B17777, Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with ML20205Q5891999-04-0909 April 1999 Rev 20,change 6 to QAP-1.0,Northeast Utils QA Program TR ML20205R8751999-04-0909 April 1999 Provides Commission with Staff Assessment of Issues Related to Restart of Millstone Unit 2 & Staff Recommendations Re Restart Authorization for Millstone Unit 2 ML20206T3991999-03-31031 March 1999 First Quarter 1999 Performance Rept, Dtd May 1999 B17747, Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With 1999-09-30
[Table view] |
Text
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Docket No. 50-336 Millstone Unit No. 2 Cycle 11 Core Operating Limits Report Revision 1 l
November,1990 9,gg21ggj(( $O0b g6 P
Fage 1
- 1. CORE OPERATING LIMITS REPORT This Core Operating Limits Report for Millstone 2 has been prepared in accordance with the requirements of Technical Specification 6.9.1.7. The Technical Specifications affected by this report are listed below:
Section Snecification 2.1 3/4.1.1.1 SHUTDOWN MARGIN - T v, > 200*F 2.2 3/4.1.1.2 SHUTDOWN MARGIN - T v, s 200*F 2.3 3/4.1.1.4 Moderator Temperature Coefficient 2.4 3/4.1.3.6 Regulating CEA Insertion Limits 2.5 3/4.2.1 Linear Heat Rate 2.6 3/4.2.3 Total Integrau _ Radial Feaking Factor - F[
2.7 3/4.2.6 DNB Margin Terms appearing in capitalized type are DEFMED TERMS as defined in Section 1.0 of the Technical Specifications.
- 2. OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC. approved methodoligies specified in Technical Specification 6.9.1.7, 2.1 SHUTDOWN MARGIN - T.,, > 200*F (Specification 3/4.1.1.1)
The SHUTDOWN 14ARGIN shall be 2 3.6% AK/K 2.2 SHUTDOWN MARGIN - Tov, s 200*F (Specification 3/4.1.1.2)
The SHUTDOWN MARGIN shall be 2 2.0% AK/K 2.3 Moderator Ten.perature Coefficient (Specification 3/4.1.1.4)
The moderator tem.pern:ure coefficient shall be:
- a. Less positive than 0.7 x 10-d AK/K/*F whenever THERMAL POWER is s 70% of RATED THERMAL FOWER,
- b. Less positive than 0.4 x 10-4 AK/K/*F whenever THERMAL POWER is > 70% of RATED THERMAL POWER,
- c. Less negative than -2.8 x 10-4 AK/K/*F at RATED THERMAL POWER.
November.1990
" i-i Page 2 ;
'2,4 : - Regulating CEA Insertion Limits (Specification 3/4.1.3.6) l The regulating CEA groups shall be limited to the withdrawal sequence and i to the insertion limits shown in Figure 2.4-1 CEA insertion between the Long Term Steady State Insertion Limits and the Transient insertion Limits is restricted to:
- a. s 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval, j
- b. - s 5 Effective Full Power Days per 30 Effective Full Power Day interval, and c
- c. 's 14 Effective Full Power Days per calendar year.
2.5 . Linear Heat Rate (Specification 3/4.2.1)
The Linear heat rate, including heat generated in the fuel, clad and
~ moderator,'shall not exceed:' 1
- a. .15.1-kw/ft when the reactor coolant flow rate measured per Specification:4.2.6.12 340,000 gpm. i
- b. 14.5 kw/ft when the reactor coolant flow rate measured per !
Specification 4,2.6.1 2 325,000 gpm and < 340,000 gpm.
- During operation with the linear heat rate being. monitored by the Excore Detector Monitoring System, the AXIAL SHAPE INDEX shall remain' within the limits of Figure ?2.5-1. 9 During. operation with the linear heat rate being monitored by the incore Detector Monitor System, the alarm setpoints shall be adjusted to less than '
or equal t_o the liniit when the .following factors are appropriately _ included sin the setting of the alarms:
,1.* Flux peaking augmentation factors as shown in Figure 2.5-2,
- 12. -A measurement-calculational uncertainty factor of 1.07,
- 3. - An engineering uncertainty factor of 1.03, 4
- A linear heat rate uncertainty factor of 1,01 due to axial fuel dendfication and thermal expansion, and r
- 5. A THERMAL POWER measurement uncertainty factor of 1.02. ,
- These factors _ 'are only appropriate to fuel batches "A" through "L".'
November,1990
- . . -_ , - +4 . _ - .
Papa. 3 I
2.6 Total Integrated Radial Peaking Factor - Ff (Specification 3/4.2.3)
The calculated value of Ff, defired as Ff = Fr(1+T q), shall be limited to:
- a. 0.90 < PF s 1.00 Ff s 1.790 - (0.15 x PF)
- b. 0.80 < PF s 0.90 Pf s 1.925 - (0.30 x PF)
- c. 0.70 < PP s 0.80 Pf s 2.205 - (0.65 x PF)
- d. PF s 0.70 Ff s 1.750 where, PF = THERMAL POWER divided by RATED THERMAL POWER 2.7 DNF. Margin (Specification 3/4.2.6)
The DNB margin shall be preserved by maintaimng the cold leg temperature, pressurizer pressure, reactor coolant flow rate, and AXIAL SHnPE INDEX within the following limits:
Parameter Limits Four Reactor Coolant Pumos Onerations
- a. Cold Leg Tempereture s 549'F
- b. Pressurizer Pressure 2 2225 psia *
- c. Reactor Coolant Flow Rate 2 325,000 ppm
- d. AXIAL SHAPE INDEX FIGURE 2.7-1
- Limit not applicable during either a THERMAL POWER ramp increase in excess of Src of RATED THERMAL POWER per minute or a THERMAL POWER step increase of greater than 10% of RATED THERMAL POWER.
l November.1990
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-0.6 -0,4 -0.2 0 0.2 0.4 0.6 Axial Shape Index FIGURE 2.7-1 AXIAL SHAPE INDEX Operating Limits with Four Reactor Coolant Pumps Operating MILLSTONE - UNIT 2 November,1990