ML20094Q707

Amend 192 to License DPR-65,adding Footnotes to TS Action Statement 3.8.1.1.a,requesting one-time AOT Extension for Inoperable Offsite Power Source from 72 H to 7 Days

ML20094Q707
Person / Time
Site:	Millstone
Issue date:	11/22/1995
From:	Mckee P NRC (Affiliation Not Assigned)
To:
Shared Package
ML20094Q711	List: ML20094Q707 ML20094Q720
References
NUDOCS 9512040063
Download: ML20094Q707 (6)

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UNITED STATES y-g j

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20506-0001

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NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY t

THE WESTERE MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 l

i AMENOMENT TO FACILITY OPERATING LICENSE l

Amendment No. 192 License No. DPR-65 t

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

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The application for amendment by Northeast Nuclear Energy i

Company, et al. (the licensee) dated October 6,1995, T

supplemented October 23, November 2, and November 15, 1995, i

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; I

B.

The facility will operate in conformity with the application, the provisiens of the Act, and the rules and regulations of the i

Commission; i

C.

There is reasonable assurance (i) that the activities authorized i

by thic 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; i

i 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; i

and 1

E.

The issuance of this amendment is in accordance with 10 CFR Part j

51 of the Commission's regulations and all applicable i

t requirements have been satisfied.

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PDR

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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. DPR-65 is hereby amended to read as follows:

(2)

Technical Soecifications 4

The Technical Specifications contained in Appendix A, as revised through Arendment No.192, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Techn'. cal 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 COMISSION i

Phillip McKee, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i

Attachment:

Changes to the Technical Spec!fications Date of Issuance:

November 22, 1995 1

ATTACittENT TO LICENSE ANENDNENT NO.192 JfILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Replace the followir.g pages of the Appendix A, Technical Specifications, with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 3/4 8-1 3/4 8-1 B 3/4 8-1 B 3/4 8-1 B 3/4 8-2 I

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3/4.8 ELECTRICAL POWER SYSTEMS j

3/4.8.1 A.C. SOURCES I

j OPERATIM LINITIM COMITIM FOR OPRATION i

3.8.1.1 As a minimum, the following A.C. electrical power sources shall j

be OPERA 8LE:

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Two physically independent circuits between the offsite trans-mission network and the switchyard, and b.

Two separate and independent diesel generators each with a i

i separate fuel oil supply tank containing a minimum of 12,000 j

gallons of fuel.

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l APPLICASILITY: MODES, 1, 2, 3 and 4.

AGIIM:

a.

With one offsite circuit inoperable, demonstrate the OPERASILITY of the remaining A.C. sources by performing Surveillance j

Requirement 4.8.1.1.1 within I hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.

If either diesel generator has not been 4

successfully tested within the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, demonstrate its OPERASILITY by performing Surveillance Requirement 4.8.1.1.2.a.2 i

separately for each such diesel generator within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i Restore the offsite circuit to OPERA 8LE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> **

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or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in j

COLD SHUTDOW within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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b.

With one diesel generator inoperable, demonstrate the OPERA 8ILITY of j

the A.C. offsite sources by performing Surveillance Requirement 4.8.1.1.1 within I hour and at least once >er 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; and if the diesel generator became inoperasle due to any cause other than preplanned preventative maintenance or testing, j

demonstrate the OPERA 8ILITY of the remaining OPERA 8LE diesel generator by performing Surveillance Requirement 4.8.1.1.2.a.2 i

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> *; restore the diesel generator to OPERABLE status i

within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STAND 8Y within the next' l

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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• This test is required to be completed regardless of when the inoperable l

diesel generator is restored to an OPERABLE status.

• • Except that once during the Millstone Unit No.1 Cycle 15 Refueling Outage, l

this 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Allowed Outage Time can be extended to 7 days.

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MILLSTOM - W IT 2 3/4 8-1 Amendment No. M. 177, 192 onst

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l 314.8 ELECTRICAL 70MER SYSTDRS SASES The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will 4

be available to supply the safety related equipment required for 1) the l

safe shutdown of the facility and 2) the aitigation and control of accident conditions within the facility. The minimum specified indepen-dont and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of General Design Criteria 17 of Appendix 'A' j

to 10 CFR 50.

The ACTION requirements specified for the levels of degradation of j

the power sources provide restriction upon continued facility operation i

i commensurate with the leval of degradation. The OPERABILITY of the power sources are consistent with the initial condition assumptions of the l

accident analyses and are based upon maintaining at least one of each of i

the onsite A.C. and D.C. power sources and associated distribution systems j

j OPERABLE during accident conditions coincident with an assumed loss of offsite power and single failure of the other onsite A.C. source.

The OPERA 8ILITY of the minimum specified A.C.and D.C. power sources and associated distribution systems during shutdown and refueling ensures that 1) the facility can be maintained in the shutdown or refueling i

condition for extended time periods and 2) sufficient instrumentation l

and control capability is available for monitoring and maintaining the i

facility status.*

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The non-safety grade ItSV D.C. Turbine Battery is required for accident mitigation for a main steam line break within containment with a coincident loss of a vital D.C. bus. The Turbine Battery provides the alternate source of power for Inverters 1 & 2 respectively via non-safety j

grade Inverters 5 & 6.

For the loss of a D.C. event with a coincident steam line break within containment, the feedwater regulating valves are i

l required to close to ensure containment design pressure is not exceeded.

The feedwater regulating valves require power to close. On loss of a vital D.C. bus, the alternate source of power to the vital A.C. bus via the i

Turbine Battery ensures power is available to the affected feedwater

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regulating valve such that the valve will isolate feed flow into the 4

l faulted generator. The Turbine Battery is considered inoperable when tus 1

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• A probabilistic safety assessment has examined the effect of extending the allowed outage time to seven (7) days for the electrical cross-tie from Unit 1 to Unit I during the Unit 1 Refueling Outage 15.

The results show that the increase in risk is acceptable provided that two diesel generators i

are available.

NI.L.LSTONE LSIIT I B3/44-1 Amendment No. J5 192 i

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3/4 A ELETRICAL POWER SYSTDi$

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voltage is less than 125 volts 0.C, thereby ensurine adecuate casacity for isolation functions via the feedwater regulating valves curing tis onset of i

a steam line break.

The Turbine Battery Charger is not required to be included in j

Technical Specifications even though the Turbine Battery is needed to power backup Inverters 5 & 6 for a stie steam line break inside containment

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coincident with a loss of a Class IE 0.C. bus. This is due to the fact that feedwater isolation occurs within seconds from the onset of the event.

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N.manILLST01E - LulIT 1 53/44-2 Amendment No. Jpp.192 i