ML20116K203
| ML20116K203 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/10/1992 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO), Connecticut Light & Power Co, Western Massachusetts Electric Co |
| Shared Package | |
| ML20116K209 | List: |
| References | |
| DPR-65-A-164 NUDOCS 9211170064 | |
| Download: ML20116K203 (7) | |
Text
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i no trog'o UNITED STATES
~g NUCt. EAR REGULATORY COMMISSION c
WASHINGTON, D. C. 20555
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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 m
Amendlent No. 164 License No. OPR-65 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated August 12, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the.',ct), 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-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-conducted in compliance with the Commission's regulations; 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 aniandment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is amended by changes to the Technical i
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:
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(2) Technical Soecifications 1
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.The Technical Specifications contained in Appendix A, as revised-through Amendment No.164, are hereby _ incorporated in the license.
1 The licensee shall operate the f acility in accordance with the Technical Specifications, i
l 3.
This license amendment is effective as of the date of issuance, r
FOR THE NUCLEAR REGULATORY COMMISSION 4 hn F.
tolz, Director i
h oject Directorate I-4 l
61 vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications i
Date of Issuance:
November 10, 1992 i
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t ATTACHMENT TO LICENSE AMENDMENT NO.164 FACILITY OPERATING LICENSE NO. DPR.,
DOCKET NO. 50-336.
't Replace the following pages of the Appendix A Technical Specifications with-the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert f
3/4 2-9 3/4 2-9 3/4 3-30 3/4 3-30 l
3/4 3-31 3/4 3-31 1
2-7 2-7 i
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POWER DISTR _IBUTION LIMITS T
TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR - Fy 2
LIMITING CONDITION FOR OPERATION T
I 3.2.3 The calculated value of f shall be within tge 100% power limit l
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specifiedintheCOREOPERATINGLIIllTSREPORT. The F value shall include the r
effect of AZIMUTHAL POWER Till, 2
APPLICABILITY: MODE 1*.
l ACTION:
T With F exceeding the 100% power limit within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either:
l 7
R duce THERMAL POWER to bring the enmbination of THERMAL POWER and a.
9 F to within the power dependent limit specified in the CORE 0EERATINGLIMITSREPORTandwithdrawthefulllengthCEAstoor beyond the Long Term Steady State Insertion Limits of Specification 3.1.3.6; or 4
b.
Be in at least HOT STANDBY.
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}JLR,yFTLLANCE RE0VIREMENT 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.
T 4.2.3.2 F shall be determined to be within the 100% power limit at the j
followingiEtervals:
a.
Prior to operation above 70 percent of RATED THERMAL POWER after each fuel lor. ding, 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.
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4.2.3.3 F shall be determined by using the incore detectors to obtain a T
power distribution map with all full length CEAs at or above the Long Term Steady State Insertion Limit' for the existing Reactor Coolant Pump l
Combination.
- See Special Test Except' ion 3.10.2 r
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MILLSTONE - UNIT 2 3/4 2-9 Amendment No. JE, E2, 79, 99, j
" 58 99,113,139, 195,155,164 g-
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INSTRUMENTATION
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INCORE DETECTORS LIMITING CONDITION FOR-OPERATION--
3.3.3.2 The incore detection system shall be OPERABLE with:
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a.
At least 75% of all incore detector locations, and i
b.
A minimum of two quadrant symmetric in: ore detector locations pcr core quadrant, and c.
A minimum of 9 OPERABLE incore detector segments at each detecto:
i 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 saall consist of a string in which at l
least three of the four incore detector segments are OPERABLE.
APPLICABILITY: When the incore detection system is used for:
j a.
Monitoring the AZIMUTHAL POWER TILT, b.
Recalibration of the excore neutron flux detection system, or c.
Monitoring the TOTAL UNRODDED INT.EGRATED RADIAL PEAKING FACTOR or j
the linear heat rate.
ACTION:
i With the incore detection system inoperable, do not use the system for the above i
applicable monitoring or calibration functisns. 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 l
use and at least once per 7 days thereafter when required for:
1.
Monitoring the AZIMUTHAL POWER TILT.
Recalibration of the excore neutron flux detection system.
2.
i 3.
Monitoring the TOTAL UNR00DED INTEGRATED RADIAL PEAKING FACTOR.
j-or the linear heat rate, t
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.
e MILLSTONE - UNIT 2 3/4 3-30 Amendment No. JE, /E, i
0068 JJ9, JEE 164 1
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MILI. STONE _ UNIT 2 2-7 Amendment No.. 38, 52, 164 r
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