ML20091B941
| ML20091B941 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/30/1992 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co |
| Shared Package | |
| ML20091B943 | List: |
| References | |
| DPR-65-A-155 NUDOCS 9204020160 | |
| Download: ML20091B941 (9) | |
Text
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UNIT ED $T ATES
$\\ ay ' 'g, NUCLE AR REGULATORY COMMISSION E
W ASHINQiON, D, C. 70$%
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j-tiORIl1[AST NUCLINLffffaQY C0_MPAfit THE CONNECTI.[VT LIGHT AND POWER COMPANY lijfjLSTERN MAS 1A[lh!SETTS ELECTRIL(OMPANY DQCKfLE_AMM MILLSTONE NUCLEAR POWER STAUD!Ly!iU_ NO. 2 MilliDHENT T0 FACILITY OPERATING LICIHS1 Amendment No.155 License No. OPR-65 1.
The Nuclear Regulatory Commission (the Con..ilssion) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated June 14, 1991, 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; C.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) 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 l
conducted in compliance with the Commission'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 of the Commission's regulations and all applicable requirements have been satisfied.
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l 9204020160 920330 DR ADOCK 0500033o 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 amendment, and paragraph 2.C.(2) of facility Operating License No. OPR-65 is hereby kmended to read as follows:
(2)
Igchnical Spesific31toni The Tech..ical Specifications contained in Appendly A, as revised through Amendment No.155, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Techrical Spacifications.
3.
This license amendment is effective as of the date of issuance, to be impicmented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION s
t oh F. Stolz, Direct joct Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuanca:
March 30, 1992 t
i.
4 AHAQM[NT TQ_ LICENSE AMBDMUILt10.155
[AClll1Y OPERAllllE.1] CENSE NO. DPil ~i E0ELLtt0m.10-lM Replace the following pages of t'e Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendment nut.aber and contain vertical lines indicating the areas of change.
Remove in;fr1 1-6 1-6 3/4 2-9 3/4 2-9 3/4 2-10 3/4 2-10 3/4 3-30 3/4 3-30 3/4 3-31 3/4 3-31 B 3/4 2-1 B 3/4 2-1 B 3/4 2-2 8 3/4 2-2
DEFINITIONS J
fMI E ERINGSAFETY FEATURE Resp 0 M E TIME (Continued) performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays where applicable.
PillEKLIIIIS 1.28 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and
- 1) described in Chapter 13.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.
T TOTAL UNRC3DED INTEGRATED RADIAL PEAKING FACTOR - F
- 1. 5 The TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR is the ratio of the peak pin power to the average pin powe', in an unrodded core.
This value includes the effect of AZIMUTHAL POWER TILT.
SOURCE CHECK 1.30 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to radiation.
RADIOLOGICAL EFFLUENT MORITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 00CM) 1.31 A RADIOLOGICAL EFFLUENT MONITORING MANUAL shall be a manual containing the site and environmental sampling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and 'for those radionuclines which lead to the highest potential. radiation exposures to individuals from station operation. An 0FFSITE DOSE CALCULATION MANUAL shall be a manual containing the methodolagy and parameters to be used in the calculation of offsite doses due to radioactive gaseous rad liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation al m / trip setpoints. Requirements of the REMODCM are provided in Specification 6.16.
RADI0 ACTIVE WASTE TREAIM.RJJi'Dili
.l.33 RADI0 ACTIVE WASTE fREKir4ENi SYSTEMS are those liquid, gaseous and solid waste systems which are required to maintain control over radioactive material in order to meet'the LCOs set forth in these specifications.
EURGE - PURGING 1.'i4 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a menner that replacement air or gas is required to purify th? containment.
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MILLSTONE - UNIT 2 1-6 Amendment No JE, Jpf,155 0026
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'n o v-POWER DISTRIBUTION LIMITS-9>1
-TOTAL ~UNRODDEDINTEGRATEDRADIALPEAKINGFACTE.Ff MMITINGCONDITIONFOROPERATION I
3.2.3
' The-c.alculated valui of Fr yhall be within the limit Lspecified in the CORE OPERATING LIMITS REPORT) lhe f7 value shall-include the effect of AZIMUTHAL POWER TILT.
$PpLICABIL111: MODE.l*.
ACIl0N:
T
.-With F exceeding its limit within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either:
7 R9 duce THERMAL POWER to bring the combination of THERMAL POWER and a.
LF. to within the limit and withdraw the full length CEAs to or thond the Long Term Steady State Insertion Limits of Specification 3.1.3.6; or b.
Be in at least HOT STANDBY.
SURVElllANCE REQUIREMENT 4.2.3.1
.The provisions of Specification 4.0.4 are not applicable.
Ff shall be determined to be within its limit at the following 4.2.3.2 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 or-ration in Mode 1 and
=c.
Within four hours if the AZIMUTHAL POWER TILT (T ):is > 0.020.-
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T
-4 ? 2..i F shall be tietermined by using the incore detectors to obtain a l
- c. w, c.rfbution map with all full length CEAs at or above the Long Term ytoir P ete_ Insertion Limit for_the existing Reactor-Coolant Pump t ar mn ' e n,
i M e E F.cial Test Exception 3.10,2 r
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a MILLSTONE - UNIT 2 3/4 2-9 Amendment No. JS, E2, 79, SS, oon -
99,JJ),Jgy,Jpg,15_3
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iE0WERDISTRIBUTIONLIMITS AZIMUTHAL POWER TILT T
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LIMITING CONDITION FOR OPERATION 3.2.4 The-AZIMUTHAL. POWER TILT (T ) shall not exceed 0.02.
q A_PPLICABIL ITY: MODE 1 -above 50% of RATED THERMAL POWER *.
- ACTION:
a.-
With the indicated AZIMUTHAL POWER TILT determined to be 2 0.02 but 1 0.10, either correct the power tilt within two hours _or determine withinthenext2hoursandatleastoncepersubsequent8gours, that the TOTAL UNRODDLD INTEGRATED RADIAL-PEAKING FACTOR (F ) is 7
within the limit of Specification 3.2.3.
b.
With the indicated AZIMUTHAL POWER TILT detcrmined to ba > 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 /> prov UNR000E0INTEGRATEDRADIALPEAKINGFACTOR(F{ded Subsequent operatioE)for. the purpose of-
.is within the limits of Specification 3.2.3.
measurement and to identify the cause of the tilt is allowable provioed the THERMAL POWER level is restricted to s 20% of the maximum allowable THERMAL POWER level for the existing Reactor
. Coolant Pump' combination.
SURVEILLANCE RE0VIREMENT 4.2.4.I' The provisions of Specification 4.0.4 are not applicable.
4;2.4.2 The AZIMUTHAL POWER TILT shall be determined 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.
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-MILLSTONE - UNIT 2 3/4 2 10 Amendment No. JS, 52, 99, ocu JJJi,155
n INSTRUMENTATION INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERABLE with at least one OPERABLE detector segment in each core quadrant on each o f.
the four axial elevations containing incore detectors and as further specified below:
a.
For monitoring the AZIMUTHAL POWER TILT:
At least two quadrant symmetric incore detector segment groups at each of the four axial elevations containing incore detectors in the outer 188 fuel assemblies with sufficient (GERABLE detector segments in these detector groups to compute et least two AZIMUTHAL POWER TILT values at each of the four axial elevations containing incore detectors.
b.
For recalibration of the excore neutron flux detection system:
1.
At least 75% of all detector segments, 2.
A minimum of 9 OPERABLE incore detector segments at each
- detector segment level, and 3..
A minimu;n of 2 OPERABLE detector segments in the inner 109 fuel assemblies and 2 OPERABLE segments in the outer 108 fuel assemblies at each segment level.
c.
For monitoring the TOTAL UNR000E0 INTEGRATED RADIAL PEAKING FACTOR or the linear heat rate:
1.
At least 75% of all incore detector locations, 2.
A minimum of 9 OPERABLE incore detector segments at-each detector segment level, and 3.
A minimum of 2 OPERABLE detector segments in the inner 109 fuel assemblies and 2 OPERABLE segments in the outer 108 fuel assemblies at each segment level.
An OPERABLE incore detector segment shall consist of an OPERABLE rhodium detector constituting one of the segments in a fixed detector string.
An OPERABLE incore detection location shall consist of a string in which at least three of the four incore detector segments are OPERABLE.
MILLS 70NE --UNIT 2 3/4 3-30 Amendment No. JE, M,
ocu Up, 155
INSTRIIMENTATig 1.lMITING CONDITION FOR OPERATION (Continued)
An OPERABLE quadrant symmetric inenre detector segment group shall consist of a minimum of three OPERABLE rhodium incore detector segments in 90'F symmetric fuel assemblies.
APPLICABILITY: When the incore detection system is used for:
a.
Monitoring the AZIMUTHAL POWER TILT, b.
Recalibration of the excore neutron flux detection system, or c.
Monitoring the TOTAL UNR000ED INTEGRATED RADIAL PEAKING FACTOR or the linear heat rate.
ACTION:
With the incore detection system inoperable, do not use the system for the abo.e applicable monitoring or calibration functions. The provisions of specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE0VIREMENT 4.3.3.2 The incore detection system shall be demonstrated OPERABLE:
a.
By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to its use and at least once per 7 days thereafter when required for:
1.
Monitoring the AZIMUTHAL POWER TILT.
2.
Recalibration of the excore neutron flux detection system, i
3.
Monitoring the TOTAL UNR000E0 INTEGRATED RADIAL PEAKING FACTOR or the linear heat rate, b.
At least once per 18 months by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but includes all electronic components. The neutron detectors shall be calibrated prior to installation in the reactor core, l
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MILLSTONE - UNIT 2 3/4 3 31 bendment No f), JJJ,155 1
0028
3/4.2 POWER,QlSTRIBUTION LIMITS BASES 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 cledding will not exceed 2200'F.
t Either of the two core power distribution monitoring systems, the Excore Detector Monitoring System and the Incore Detector Monitoring System, provide adequate monitoring of tha core power distribution and are cappble of verify-ing that the linear heat rate does not exceed its limits.
The Excore Detector Monitoring System performs this function by continuously monitoring the AX1AL SHAPE INDEX with two OPERABLE excere neutron flux detectors and verifying that the AXIAL SHAPE INDEX is maintained within the allowable limits of Figure
~
3.2 2 using the Power Ratio Recorder. The power dependent limits of the Power Ratio Recorder are less than or equal to the limits of Figure 3.2-2.
In conjunction with the ust of the excore monitoring system and in establishing the AX1AL SHAPE INDEX limits, the following assumptions are made:
- 1) the CEA insertion limits of Specifications 3.1.3.2, 3.1.3.5 and 3.1.3.6 are satisfied,
- 2) the flux peaking augmentation factors are as shown in Figure 4.2-1, 3) the AZIMUTHAL POWER Titi restrictions of Specification 3.2.4 are satisfied, and
- 4) the TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR does not exceed the limits of Specification 3.2.3.
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 3.21.
The setpoints for these alarms include allowances, set in the conservative directions, for
- 1) flux peaking augmentation factors as shown in Figure 4.21, 2) a measure-ment-calculational uncertainty factor of 1.07, 3) an engineering uncertainty f actor of 1.03, 4) an allowance of 1.01 for axial fuel densification and thermal expansion, and 5) a THERMAL POWER measurement uncertainty factor of 1.02.
Note the items (1) and (4) above are only applicable to fuel batches "A" through "L".
T 3/LL3 and 3/4.2.4 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTORS F gg y
AZIMUTHAL POWER TILT - Tq I
The limitations on F and T are provided to 1) ensure that the assump-tions used in the analysis for %stablishing the Linear Heat R&te and Local power Density - High LCOs and LSSS setpoints remain valid during operation at the various allowable CEA group insertion limits, and, 2) ensure that the
~
assumptions used in the analysis establishing the DNB Margin LCO, and Thermal Margin / Low Pressure LSSS setpoints remain valid during operation at the T
various allowable CEA group insertion limits, if F or 1 exceed their basic limitations, operation may continue under the additSonal 9estrictions imposed by the ACTION statements since these additional restrict 1ons 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 LSSS MILLSTONE - UNIT 2 8 3/4 2-1 Amendment No. JE, 52, 122 Jy,Jpg.1$5 om
+
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POWER DISTRIBUTION QM_lli BASUS setpoints remain valid. An AZIMUTHAL POWER TILT > 0.10 is not expected and if it should occur, subsequent operation would be restricted to only those operations required to identify the cause of this unexpected tilt.
The surveillance requirements for verifying that FT an T
are within their limits provide assurance that the actual values if F ar0f T do not T
exceed the assumed values.
Verifying F after each fuel foading Srlor to exceeding 75% of RATED THERMAL POWER pr[vides additional assurance that the coret was properly loaded.
12,4,2,6 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 speci-fied limits for the accident and transient analyses to remain valid.
HILLSTONE - UNIT 2 8 3/4 2 2 Amendment No. 38, J2, J22, con JJp, 155
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