ML20236V410
| ML20236V410 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/18/1987 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co |
| Shared Package | |
| ML20236V413 | List: |
| References | |
| TAC 66056, DPR-65-A-122 NUDOCS 8712040285 | |
| Download: ML20236V410 (11) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION -
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NORTHEAST NUCLEAR E,N,ERGY_ C_0,M,PANY THE CONNECTICUT LIGHT AND POWER COMPANY.-
THE WESTERN PASSAChDSE11S ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE' NUCLEAR POWER STA,,T,I,06 UNIT NO. 2' AMENDMENT TO FACILITY OPERATING LICENSE Amendment; No.122
-License No.-DPR 1.
The Nuclear Regulatory Comission (the Comission) has found that:
1 A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated August 28,-1987 complies with;the-'
j standards and requirements of the Atomic Energy Act of 1954,'as' D
amended (the Act).-and the Commission's rules and regulations set forth in 10 CFR Chapter I; j
B.
The facility will operate in conformity with'the application, the provisions of the Act, and the rules and. regulations of the j
Comission; C.
There is reasonable assurance'(1) that the activities authorized by-this amendment can be conducted without endangering the health and-l safety of the public, and (ii) that such activities will be-conducted in compliance with the Comission's regulations; i
D.
The issuance of this amendment will not be inimical to the common i
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 of the Comission's regulations and all applicable requirements have been satisfied.
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l 8712040285 871118 PDR ADOCK 05000336 p
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2.
Accordingly, the license is amended by. changes to the Technical Specifications as indicated in the attachment to this license amendn.er.t.
I and paragraph ?..C.(2) of Facility Operating License Nc. DPR-65 is hereby j
amended to read as follows:
)
(2) Technical Specifications
. 1 The Technical Specifications contained in. Appendix A, as revised
)
through Amendment No.122, are hereby incorporated. in the license.
(
'The licensee shall operate the facility in accordance with the 1
Technical Specifications.
)
3.
This license' amendment is effective upon issuance.
1 THE NUCLEAR R ULATORY COWISSION NY r
F. Stolz, Direc) 4 oh Pr ject Directorate.
l ision of Reactor Projects I/II 1
Attachment:
Changes to the Technical Specifications Date of Issuance: g 3g g S
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ATTACHMENT TO LICENSE AMENDMENT N0.122 i
FACILITY OPERATING LICENSE NO. DPR-65 l
DOCKET NO. 50-336-s Replace the following pages of the Appendix A Technical Specifications with I
the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of' change. The corresponding
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l overleaf pages are provided to maintain document completeness.
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Skl013Vd NOl1V1NEWDfW MILLSTONE - UNIT 2 3/42-4 Amendment N(, )$, 52, ($, Vf,99 1
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POWER DISTRIBUTION LIMITS
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TOTAL PLANAR RADIAL PEAKING FACTOR - Fly LIMITING CONDITION FOR OPERATION
'l 3.2.2 Meet either of 3.2.2.1 or 3.2.2.2.
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3.2.2.1 The calculated value of Ph, defined as Fiv** = Fxy (1+Tq), shall be limited to.61.62 with the AXIAL SMAPE INDEX afarm setpoints adjusted consistent with the limits shown on Figure 3.2-2a, or 3.2.2.2 The calculated value of F1 defined as FI ** = Fxy (1+Tq), shall be.
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limited to 41.719 with the AXIAL 5,HAPE INDEX Earm setpoints adjusted 3
l consistent with the limits shown on Figure 3.2-2b.
APPLICABILITY: MODE 1.*
ACTION:
With Fly > 1.62 and the AXIAL SHAPE INDEX alarm setpoints adjusted 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 THERMAL POWER to bring the combination of THERMAL POWER and Fly to within the limits of Figure 3.2-3a and withdraw the full length CEAs to or beyond the Long Term Steady State Insertion Limit of Spec'afication 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 AX1AL SHAPE INDEX alarm j
setpoints consistent with the limits shown on Figure 3.2-2b, or 3)
Be in at least HOT STANDBY.
b.
With Fly > 1.719 and the AXIAL SHAPE INDEX alarm setpoints adjusted 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 corhbination of THERMAL POWER and Fly to within the limits of Figure 3.2-3b and withdraw the fulllength 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.
i See Special Test Exception 3.10.2
- For Cycle 8 only, whenever the core average burn-up is3m 9500 MWD /MTU, an additional multiplier of 1.115 shall be used in the calculation. Therefore, for these conditions, Fly = 1.115 Fxy (1+T ),
q MILLSTONE - UNIT 2 3/42-5 AmendmentNo.)d,5/,7/,%,[,%,122
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POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 1
4.2.2.1 The provisions of Specification 4.0.4 are not applicable.
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= Fxy (1+Tq) and Fl 4.2.2.2 Fly shall be calculated by the expression Fly
- following intervals: y shall be determined to be within its limit at the Prior to operation above 70 percent of RATED THERMAL POWER i
a.
af ter each fuel loading, b.
At least once per 31 days of accumulated operation in MODE 1, and
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c.
Within four hours if the AZIMUTHAL POWER TILT (T )is) 0.02.
q l
xy shall be determined each time a calculation of Fly is required
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4.2.2.3 F
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 i
existing Reactor Coolant Pump combination. This determination shall be limited 5
to core planes between 15% and 85% of full core height inclusive and shall E
exclude regions influenced by grid effects.
4.2.2.4 T shall be determined each time a calculation of Fly s required and.
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the value of T used to determine Fly shall be measured value of T.
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i For Cycle 8 only, whenever the core average burn-up is 9500 MWD /MTU, an additional multiplier of 1.115 shall be used in the calculation. Therefore, for these conditions, FxyT = 1.113 Fxy (1 + T ).
q MILLSTONE - UNIT 2 3/42-6 AmendmentNo,M.)d,k,122
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. p FIGURE 3.2-3a.
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MILLSTONE - UNIT 2 3/4 2 Amendment No. 99
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Amendment No. 34,%,}4,96,cpy.p 1/3,122 i
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3/4.2 POWER DISTRIBUTION LIMITS BASES l
1 3/4.2.1 LINEAR HEAT RATE The limitation on linear heat rate ensures that in the event of a LOCA, the peak temperature of the fuel cladding will not exceed 22000F.
'Either of the two core power distribution monitoring systems, the Excore-Detector Monitoring System and the Incore Detector Monitoring System, provide' adequate monitoring of the core power distribution and are capable of verifying that the linear heat rate does not exceed its limits.
The Excore Detector Monitoring System performs this function by continuously monitoring the AXIAL SHAPE INDEX with two OPERABLE excore neutron flux detectors and verifying that the AXIAL SHAPE INDEX is maintained within the allowable limits of Figure 3.2-2. In conjunction with the use of the excore monitoring system and in establishing the AXIAL SHAPE INDEX limits, the following assumptions are j
made: 1) the CEA Insertion limits of Specifications 3.1.3.2, 3.1.3.5 and 3.1.3.6 1
are satisfied, 2) the flux peaking augmentation factors are 'as shown in
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Figure 4.2-1,3) the AZIMUTHAL POWER TILT restrictions of Specification 3.2.4
]
are satisfied, and 4) the TOTAL PLANAR RADIAL PEAKING FACTOR'does not exceed the limit:: of Specification 3.2.2.
1
.)
The Incore Detector Monitoring System continuously provides a direct-measure of the peaking factors and the alarms which have been established for the individual incore detector segments ensure that the peak linear heat rates will be maintained within the allowable limits of Figure 3.2-1. The setpoints for these alarms include allowances, set in the conservative' directions, for 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) an allowance of 1.01 for axla! fuel densification and thermal expansion, and 5) a THERMAL POWER measurement uncertainty factor of 1.02.
A reduced linear heat rate limit of 14.0 kW/ft for Cycle 8 operation beyond a core average. burn-up of 9500 MWD /MTU ensures that the 22000F peak fuel cladding temperature limit will not be exceeded in the. event of a LOCA. The value of 9500 MWD /MTU is the predicted end-of-cycle for Cycle 8. Operation beyond the predicted end-of-cycle may require reductions in the reactor coolant-temperatures which can increase the calculated peak clad temperatures. The reduction in the linear heat rate limit will more than compensate for the' effect of the reduction in the reactor coolant temperatures on the LOCA analysis.
3/4.2.2. 3/4.2.3 and 3/4.2.4 TOTAL PLANAR AND INTEGRATED RADIAL PEAKING FACTORS - Fl xy AND F'r AND AZIMUTHAL POWER TILT - Tq The limitations on FTxy and T are provided to ensure that the assumptions q
used in the analysis for establishing the Linear Heat Rate' and Local power Density - High LCOs and LSSS setpoints remain valid during operation at the various allowable CEA group insertion limits.
MILLSTONE - UNIT 2 B3/42-1 Amendment No. 38,52,122-
POWER DISTRIBUTION LIMITS e
BASES The limitations on Ft and T are provided to ensure that the assumptions used in the analysis establishing the DNB Margin LCO, and Thermal Margin / Low r
g Pressure LSSS setpoints remain valid during ogeration at the various allowable CEA group insertion limits. If F x, F r or-T exceed their basic a
T limitations, operation may continue under the affditional restrictions imposed by the ACTION statements since' these additional restrictions provide ' adequate provisions to assure that the assumptions used in establishing the Linear Heat Rate, Thermal Margin / Low Pressure and Local Power Density - High LCOs and An AZIMUTHAL POWER TILT >0.10 is not LSSS setpoints remain valid.
expected and if it should occur, subsequent operation would be restricted to only those operations required to identify the cause of this unexpected tilt.
that must be used in the equation F xy = Fxy (1 + T ) and T
q The value of Tg F r = Fr (1 + T ) is the measured tilt.
T q
T T
Fr and T are The surveillance requirements for verifying that F x q
within their limits provide assurance that the actual values of,F af er each j T,FrT and T T
T do not exceed the assumed values. Verifying F x and F r loading prior to exceeding 75% of RATED THERMAL h0WER provides additional assurance that the core was properly loaded.
For Cycle 8 operation beyond a core average burn-up of 9}00 MWD /MTU, an additional multiplier of 1.115 is used in the calculation of Fxy. This value is The value of proportional to the' reduction in the maximum linear heat rate.
9500 MWD /MTU is the predicted end-of-cycle for Cycle 8.
3/4.2.6 DNB MARGIN The limitations provided in this specification ensure that the assumed margins to DNB are maintained. The limiting values of the parameters in this specification are those assumed as the initial conditions in the accident and transient analyses; therefore, operation must be maintained within the specified limits for the accident and transient analyses to remain valid.
MILLSTONE - UNIT 2 B3/42-2 Amendment No. 38,52,122
.