ML20072Q073
| ML20072Q073 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/26/1990 |
| From: | Vissing G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072Q075 | List: |
| References | |
| NUDOCS 9011300108 | |
| Download: ML20072Q073 (5) | |
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UNITED STATES ys
' n NUCLE AR REGULATORY COMMISSION -
L WASHINGTON, D. C. 20055 s ~....,
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. 150 License No. DPR-65 1.
The Nuclear Regulatory Comission (the Comission) has found that:
The app (lication for amendment by Northeast Nuclear Energy Company, A.
et al.
the licensee), dated August 7, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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; l
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 Comission'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 amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have l
been satisfied.
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901130010e 901126 PDR ADOCK 050 6
P
. 1 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, I
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 Appendix A, as revised through Amendment No.150, 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, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
.Y oh F. Stolz, Directo Pr ject Directorate.I-4 vision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 26, 1990
ATTACHMENT _T0_ LICENSE _ AMENDMENT _NO._150 FACILITY 0PERATING_ LICENSE NO.-DPR-65 DOCKET _N0_._50-336 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
_I n sert.
3/4 9-3a 3/4 9-3a B 3/4 9-1 B 3/4 9-1 i
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REFUEllNG OPERATIONS SPENT FUEL POOL TEMPERATURE LIMITING CONDITION FOR OPERATION 3.9.3.2 The spent fuel pool bulk temperature shall be maintained at less than or equal to 140'F.
APPllCABillTY: Whenever irradiated fuel.is stored in the spent fuel pool.
ACTION:
With the above conditions not satisfied; a.
Imediate 111tiate actions to restore the spent fuel pool tempera-ture to les ; than or equal to 140'F, and b.
Within one hour, suspend. all fuel movement in the spent fuel pool, and c.
Within one hour, isolate the spent fuel pool cleanup demineralizers, and d.
At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, record the spent fuel pool bulk tempera-ture.
3 SURVEILLANCE REQUIREMENTS 4.9.3.2 The spent fuel pool bulk temperature shall be verified to be less than or equal to 140*F at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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MILLSTONE - UNIT 2 3/4 9-3a Amendment No. JJA l
3/4.9 REFUELING OPERATIONS-BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:
- 1) the reactor will remain suberitical during CORE ALTERATIONS, and 2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel.
These limitations are consistent with the initial conditions assumed for the boron dilution incident in the accident analyses.
3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensures that redundant monitoring capability.is available-to detect changes in the reactiv-ity condition of the core.
3/4.9.3 DECAY TIME The -minimum requirement for reactor subcriticality prior to movement of irradiated fuel ensures that sufficient time has elapsed to allow the radioac-tive decay of the short-lived fission products. This decay time is consistent i
with the assumptions used in the accident analyses.
The requirement that the spent fuel pool bulk temperature be maintained below 140'F ensures that high water temperature will not degrade resin in the spert fuel pool deminert.lizers and that the temperature and humidity above the pool are compatible with personnel comfort and safety requirements. Addition-ally, the requirement ensures that the design temperature of the fuel pool cooling system, line / building structures, and racks are not exceeded.
The requirement for the reactor. to remain in MODE 5 or 6' until the most recent 1/3 core offload has decayed 504 hours0.00583 days <br />0.14 hours <br />8.333333e-4 weeks <br />1.91772e-4 months <br /> ensures that alternate cooling is available during this time to cool the spent fuel pool should a failure occur in the spent fuel pool cooling system.
The shutdown cooling (SDC) system is a high capacity system; that is, one' train is sufficient to cool both the core and the spent fuel pool should a failure occur in the spent fuel pool cooling system within 504 hours0.00583 days <br />0.14 hours <br />8.333333e-4 weeks <br />1.91772e-4 months <br /> from reactor shutdown.
3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPERABILITY ensure that a release of radioactive material within containment will be restricted from leakage to the environment.
The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release -from a fuel element rupture based upon the lack of containment pressurization poten-tial while in the REFUELING MODE.
3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during fuel or CEA. movement within the reactor pressure vessel.
I MILLSTONE - UNIT 2 B 3/4 9-1 Amendment No. 72, W
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