ML20126F653

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Amend 73 to License NPF-49,revising TS to Extend,On one- Time Basis,Latest Date for Required Testing of Emergency DG from 921225 to 1993 Refueling Outage,But No Later than 930930
ML20126F653
Person / Time
Site: Millstone Dominion icon.png
Issue date: 12/23/1992
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Northeast Nuclear Energy Co (NNECO)
Shared Package
ML20126F657 List:
References
NPF-49-A-073 NUDOCS 9212310042
Download: ML20126F653 (5)


Text

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UNITE D STATES

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NUCLEAR REGULATORY COMMISSION

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No....+l NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.

QQCKET NO. 50-40 tillLST0DE NUCLEAR POWER STAT 10N. UNIT NO. 3 f

AMENDMENT T0 fAC.lLITY OPERATJf1(LLICENSE Amendment No. 73 License No. NPF-49 1.

The Nuclear Regulatory Connission (the Commission) has found that:

A.

The application for amendment by Northeast Nuclear Energy Com)any, et al. (the licensee) dated October 22, 1992, complies with tie 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 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.

Tb issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the pablic; 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.

9212310042 921223 PDR ADOCK 05000423 p-PDR

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)llows:of Facility Operating License No. NPF-49 is hereby amended to read as fo (2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised-throuch Amendment No. 73

, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the licenso.

The-licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGVLATORY COMMISSION r

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Stolz, Direc. r Pr ject Directorate

-4 vision of Reactor Projects.- 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

December.23, 1992

ATTACHMENT TO LICENSE AMENDMENT NO.73 FACILITY OPERATING l.ICENSE NO, NPF-49

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DOCKET NO. 50-423 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, fLtap_y.g Insert 3/4 0-3 3/4 0-3 3/4 8-5 3/4 8-5 l

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APPLICABILITY

.. LIMITING CONDITION FOR OPERATION (Continued) i d.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirementst l

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Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

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ELECTRICAL POWER SYSTEMS SURVElllANCE RE0VIREMENTS fContinuM) b)

A kinematic viscosity at 40'C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 centistokes (alternatively, Saybolt viscosity, SUS at 100'F of greater than or equal to 32.6, but not less than or equal to 40.1), if gravity was not determined by comparison with the supplier's certification; c)

A flash point equal to or greater than 125'F; and d)

A clear and bright appearance with proper color when tested in accordance with ASTH D4176-82.

2)

By verifying within 30 days of obtaining the sample that the other properties specified in Table 1 of ASTH D975 81 are met when tested in accordance with ASTM 0975 81 except that the analysis for sulfur may be performed in accordance with ASTH-D1552-79, ASTH D2622 82 or ASTH 04294-83.

f.

At least once every 31 days by obtaining a sam)1e of fuel oil in accordance with ASTH D2276-78, and verifying t1at total particulate contamination is less than 10 mg/ liter when checked in accordance with ASTM D2276-78, Method A; g.

At least once per 18 months, during shutdown, by:

1)

Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service;*

2)

Verifying the generator capability to reject a load of greater than or equal to 595 kW while maintaining voltage at 4160 1 420 volts and frequency at 60 i 3 Hz; 3)

Verifying the generator capability to reject a load of 4986 kW without tripping.

The generator voltage shall not exceed 4784 volts during and following the load rejection; 4)

Simulating a loss-of offsite power by itself, and:

a)

Verifying deenergization of the emergency busses and load shedding from the emergency busses, and b)

Verifying the diesel starts on the auto-start signal, energizes the emergency busses with )ermanently connected loads within 11 seconds, energizes tse auto-connected shutdown loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After energization, the steady-state voltage and frequency of the emergency busses shall be maintained at 4160 420 volts and 60 0.8 Hz during this test.

  • Except that the Surveillance Recuirement inspection due no later than December 25, 1992 may be deferred until the next refueling outage, but no later than September 30, 1993 or whichever is earlier.

MILLSTONE - UNIT 3 3/4 8-5 Amendment No f, JS, Ef,73 0007

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