ML20128D276
| ML20128D276 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/19/1985 |
| From: | Butcher E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128D267 | List: |
| References | |
| TAC-56814, NUDOCS 8507050072 | |
| Download: ML20128D276 (17) | |
Text
- _
[
UNITED STATES g
3 NUCLEAR REGULATORY COMMISSION D
j WASHINGTON, D. C. 20665
%,*...*/
i NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. DPR-65 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated February 6, 1985 as supplemented June 5 and June 11, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; l
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 l
of the Comission's regulations and all applicable requirements have been satisfied.
l 0507050072 850619 ADOCK 050 6
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 99, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION N
Edward J. Butcher, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 19, 1985
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ATTACHMENT TO LICENSE AMENDMENT NO. 99 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 j
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number rnd contain vertical lines indicating the area of change. The corresponding overleaf pages are provided to maintain document completeness.
Remove Pages Insert Pages IV IV 3/4 2-1 3/4 2-1 1
3/4 2-2 3/4 2-2 3/4 2-4 3/4 2-4 3/4 2-5 '
3/4 2-5 3/4 2-6 3/4 2-6 4
3/4 2-7 3/4 2-7 3/42-7(a) 3/4 2-8 3/4 2-8 2-8(a) 3/4 2-9 3/4 2-9 A
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY...........................................
3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTR0L.....................................
3/4 1-1 Shutdown Margi n - T,yg > 200 F.......................
3/4 1-1 Shutdown Margin - T,yg < 200*F.......................
3/4 1-3 Boron Dilution......................................
3/4 1-4 Moderator Temperature Coefficient (KTC)..............
3/4 1-5 Minimum Temperature for Criticality..................
3/4 1-7 3/4.1.2 B0' RATION SYSTEMS.....................................
3/4 1-8 Fl ow Pa th s - S hu tdown................................
3/4 1-8 Flow Paths - Operating...............................
3/4 1-10 C ha rgi n g P ump - S hu tdown............................. 3/4 1-12 C ha rgi n g P ump s - O pe ra t i ng........................... 3/4 1-13 Bo ri c Aci d Pumps - Shu tdown..........................
3/4 1-14 Bori c Aci d Pumps - Operati ng.........................
3/4 1-15 Borated Water Sources - Shutdown..................... 3/4 1-16 Borated Water Sources - Operating.................... 3/4 1-18 3/4.1.3 MOVABLE CONTROL ASSEMBLI ES........................... 3/4 1-20 Full Length CEA Group Position.......................
3/4 1-20 Posi tion Indi cator Channel s.......................... 3/4 1-24 CEA Drop Time........................................
3/4 1-26 Shutdown C EA Insertien Limit......................... 3/4 1-27 Regulating CEA Insertion Limits......................
3/4 1-28 1
MILLSTONE - UNIT 2 III Amendment No. 38
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 1
SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE......................................
3/4 2-1 T
3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACTOR - Fxy..............
3/4 2-5 l
T 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - Fr...........
3/4 2-9 3/4.2.4 AZIMUTHAL POWER TI LT..................................
3/4 2-10 3/4.2.5 FUEL RESIDENCE TIME...................................
3/4 2-12 3/4.2.6 DN B MA RG I N............................................
3 / 4 2-1 3 3/4.3 INSTRUMENTATION 3/4. 3.1 REACTOR PROTECTIVE INSTRUMENTATION....................
3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.....................................
3/4 3-10 3/4.3.3 MONITORING INSTRUMENTATION............................
3/4 3-26 Radiation Monitoring..................................
3/4 3-26 Inco re Detecto rs......................................
3/4 3-30 Seismic Instrumentation...............................
3/4 3-32 Meteorological Instrumentation........................
3/4 3-36 Remote Shutdown Instrumentation.......................
3/4 3-39 Chlorine Detection Systems............................
3/4 3-42 Fi re Detection Instrumentation........................
3/4 3-43 Accident Moni to ring...................................
3/4 3-4 6 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION.................
3/4 4-1 Sta rtup and Power Ope ration...........................
3/4 4-1 Hot Standby...........................................
3/4 4-la Shutdown...........................................~...
3/4 4-lb 3/4.4.2 SAFETY VALVES.........................................
3/4 4-2 3/4.4.3 RELIEF VALVES.........................................
3/4 4-3 MILLSTONE - UNIT 2 IV Amendment No. 35, 38. 56. 44 99
3/4.2 POWER DISTRIBUTION LIMITS LINEAR HEAT RATE LIMITING CONDITION FOR OPERATION 3.2.1 The linear heat rate shall not exceed the limits shown on Figure 3.2-1.
APPLICABILITY: MODE 1.
ACTION:
During operation with the linear heat rate being monitored by the Incore Detector Monitoring System, comply with the following ACTION:
With the linear heat rate exceeding its limit, as indicated by four or more coincident incore channels, within 15 minutes initiate corrective action to reduce the linear heat rate to within the limits and either:
a.
Re' store the linear heat rate to within its limits within I hour, or b.
Be'in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
During operation with the linear heat rate being monitored by the Excore Detector Monitoring System, comply with the following ACTIONS:
With the linear heat rate exceeding its limit, as indicated by the AXIAL SHAPE INDEX being outside of the power dependent limits on the Power Ratio Recorder and with the THERMAL POWER:
a.
Above 100% of the allowable power level determined by Specifica-tion 4.2.1.2.c. within 15 minutes either restore the AXIAL SHAPE INDEX to within the allowable limits as required per Technical Specification 3.2.2 or reduce THERMAL POWER to 1 100% of the allowable power level determined by Specification 4.2.1.2.c.
b.
< 100% of the allowable power level detennined by Specification T.2.1.2.c, either restore the AXIAL SHAPE INDEX to within the allowable limits as required per Technical Specification 3.2.2 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from initially exceeding the linear heat rate limit or be in HOT STANDBY within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.2.1.1 The linear heat rate shall be detennined to be within.its limits by continuously monitoring the core power distribution with either the excore detector monitoring system or with the incore detector monitoring system.
MILLSTONE - UNIT 2 3/4 2-1 Amendment No. 21,75,52,99
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.1.2 Excore Detector Monitoring System - The excore detector monitoring system may be used for monitoring the core power distribution by:
a.
Verifying at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that the full length CEAs are withdrawn to and maintained at or beyond the Long Term Steady State Insertion Limits of Specification 3.1.3.6.
b.
Verifying at least once per 31 days that the AXIAL SHAPE INDEX alarm setpoints are adjusted to within the allowable limits as required per Technical Specification 3.2.2.
c.
Verifying at least once per 31 days that the AXIAL SHAPE INDEX is maintained within the allowable limits as required per Technical Specification 3.2.2, where 100 percent of the allowable power represents the maximum THERMAL POWER allowed by,the existing Reactor Coolant Pump Combination.
I 4.2.1.3 Incore Detector Monitorinq System - The incore detector monitoring system may be used for monitoring ;he core power distribution by verifying that the incore detector Local Power Density alams:
a.
Are adjusted to satisfy the requirements of the core power distribution map which shall be updated at least once per 31 days.
b.
Have their alam setpoint adjusted to less than or equal to the limits shown on Figure 3.2-1 when the following factors are appropriately included in the setting of these alarms:
1.
Flux peaking augmentation factors as shown in Figure 4.2-1, 2.
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 densification and thermal expansion, and 5.
A THERMAL POWER measurement uncertainty factor of 1.02.
MILLSTONE - UNIT 2 3/4 2-2 Amendment No. 2J 38, 52.99
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1 y POWER DISTRIBUTION LIMITS TOTALPLANARRADIALPEAKINGFACTOR-h LIMITING CONDITION FOR OPERATION
~
3.2.2 Meet either of 3.2.2.Y or13.2.2.2.
J ThecalculatedvalueofFfy,definedasFfy=F 0+T ), shall be 3.2.2.1 xy q
limited to < 1.62 with the AXIAL SHAPE INDEX alarm setpoints adjusted consistent with the limits shown on Figure 3.2-2a, or ThecalculatedvalueofFfy,definedasFfy=F 0 +T ), shall be
'3.2.2.2 xy q
limited to < 1.719 with the AXJAL; SHAPE INDEX alarm setpoints adjusted consistent with the limits shown,on Eigure 3.2-2b.
APPLICABILITY: MODE 1*.
- i. e ACTION:
WiIh Ffy > 1.62 and the AXIAL SHAPE INDEX alarm setpoints adjusted y'
a.
consistent with the limits shown on Figure 3.2-2a, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either:
- 1) Reduce THERML POWER to bring the combination of THERMAL POWER and F['y to within the limits of Figure 3.2-36 and withdraw the full length CEAs to or beyond the Long Term Steady State Insertion Limit of Specification 3.1.3.6, or
~
- 2) Apply the limits of Specification 3.2.2.2 and Figure 3.2-3b and within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> adjust the AXIAL SHAPE INDEX alarm set-points consistent with the limits shown on Figure 3.2-2b, or
- 3) Be in at least HOT STANDBY.
T b.
With F
> 1.719 and the AXIAL SHAPE INDEX alann setpoints adjusted y
consistent with the limits shown on Figure 3.2-2b, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either:
- 1) Reduce THERMAL POWER to bring the combination of THERMAL POWERandFfy to within the limits of Figure 3.2-3b and withdraw the full length CEAs to or beyond the Long Term Steady State Insertion Limit of Specification 3.1.3.6, or
- 2) Be in at least HOT STANDBY.
3
- See Special Test Exception 3.10.2.
MILLSTONE - UNIT 2 3/4 2 5 Amendment No. 38,52/7),pp,9J,99
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.
F[y shallbecalculatedbytheexpressionF[y=Fxy(1+T)andFfy 4.2.2.2 q
shall be determined to be within its limit at the following intervals:
a.
Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading, b.
At least once per 31 days of accumulated operation in MODE 1, and c.
Within four hours if the AZIMUTHAL POWER TILT (T ) is > 0.02.
q shallbedeterminedeachtimeacalculationofFfy is required 4.2.2.3 Fxy by using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Term Steady State Insertion Limit for the existing ~ Reactor Coolant Pump combination. This determination shall be limited to core planes between 15% and 85% of full core height inclusive and shall exclude regions influenced by grid effects.
T 4.2.2.4 T shall be determined each time a calculation of F is required q
y usedtodetermineFfy shall be measured value of T.
and the value of T q
q l
t MILLSTONE - UNIT 2 3/4 2-6 Amendment No. 38, 79,99
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MILLSTONE - UNIT 2 3/4 2-8(a)
Amendment No. 38,52179,99,97,99
[
POWER DISTRIBUTION LIMITS T
TOTAL INTEGRATED RADIAL PEAKING FACTOR - F r LIMITING CONDITION FOR OPERATION ThecalculatedvalueofFf,definedasFf=F(1+T)shallbe' limited 3.2.3 r
q to 1 1.565.
APPLICABILITY: MODE 1*.
ACTION:
With Ff > 1.565, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either:
a.
Reduce THERMAL POWER to bring the combination of THERMAL POWER T
and F to within the limits of Figure 3.2-3b and withdraw the i
p full length CEAs to or beyond the Long Term Steady State Insertion Limits of Specification 3.1.3.6; or b.
Beiin at least HOT STANDBY.
SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.
FfshallbecalculatedbytheexpressionF =F(1+T)andFfshall 4.2.3.2 r
7 q
be determined to be within its limit at the following intervals:
a.
Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading, b.
At least once per 31 days of accumulated operation in MODE 1, and c.
Within four hours if the AZIMUTHAL POWER TILT (T ) is > 0.020.
q shallbedeterminedeachtimeacalculationofFfisrequiredby 4.2.3.3 Fr using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump Combination.
shallbedeterminedeachtimeacalculationofFfisrequired 4.2.3.4 Tq used to determine Ff shall be the measured value of T.
and the value of Tq q
- See Special Text Exception 3.10.2.
4 MILLSTONE - UNIT 2 3/4 2-9 Amendment No. 3,52,7),90, 99
POWER DISTRIBUTION LIMITS AZIMUTHAL POWER TILT - Tq LIMITING CONDITION FOR OPERATION 3.2.4 The AZIMUTHAL POWER TILT (T ) shall not exceed 0.02.
q APPLICABILITY: MODE 1 above 50% of RATED THERMAL POWER *.
l ACTION:
a.
With the indicated AZIMITHAL POWER TILT determined to be > 0.02 but < 0.10, either correct the power tilt within two hours or determine within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and at least once per sub-sequent 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, that the TOTAL PLANAR RADIAL PEAKING FACTOR (Ffy) and the TOTAL INTEGRATED RADIAL PEAKING FACTOR (F ) are within the limits of Specifications 3.2.2 and 3.2.3.
r b.
With the indicated AZIMUTHAL POWER TILT determined to be > 0.10, operation may proceed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided that the TOTAL T
INTEGRATED RADIAL PEAKING FACTOR.(F ) and TOTAL PLANAR RADIAL 7
PEAKING FACTOR (F,T ). are within the limits of Specifications y
3.2.2 and 3.2.3.
Subsequent operatton for the purpose of measurement and to identify the cause of the tilt is allowable provided the THERMAL POWER level ts restricted to < 20% of the maximum allowable THERMAL POWER level for the exisOng Reactor Coolant Pump combination.
SURVEILLANCE REQUIREMENT 4.2.4.1 The provisions of Specification 4.0.4 are not applicable.
4.2.4.2 The AZIMUTHAL POWER TILT shall be detemined to be within the limit by:
a.
Calculating the tilt at least once per 7 days when the Channel High Deviation Alarm is OPERABLE, See Special Test Exception 3.10.2.
i MILLSTONE - UNIT 2 3/4 2-10 Amendment No. 5, S, 90
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