ML20245L227

Amend 140 to License DPR-65,incorporating Limiting Conditions for Operation & Surveillance Requirements for Reactor Vessel Coolant Level Instrumentation in Tech Spec 3/4.3.3.8, Accident Monitoring

ML20245L227
Person / Time
Site:	Millstone
Issue date:	04/21/1989
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245L210	List: ML20245L208 ML20245L227 ML20245L252
References
NUDOCS 8905050333
Download: ML20245L227 (8)

Text

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, UNITED STATES f p, - NUCLEAR REGULATORY COMMISSION l- 5- l WASHINGTON, D, C. 20555

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NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.

DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE-Amendment No140 License No. DPR-65

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Northurt Nuclear Energy Company,-

et al.-(the licensee), dated October 14, 1986, July 21, 1987 and January 12, 1989, 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) 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 emendment 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 been satisfied.

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8905050333 PDR 890421ADOCK PNU 05000336 P

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

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.140 . are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications. .

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3. This license amendment is effective as of the date of issuance, to be ir.plemented within 30 days of issuance.

i' FOR THE NUCLEAR REGULATORY COMMISSION J hn F. Sto z, Di or roj t Directorate I-4 ion of Reactor Projects I/II .

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical  !.

Specifications Date of Issuance: April 21, 1989  !

A ATTACHMENT TO LICENSE AMENDMENT P:0.140 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 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. The corresponding overleaf pages are provided to maintain document completeness.

Remove Insert 3/4 3-47 3/4 3-47 3/4 3-48a 3/4 3-48a B3/4 3-49 B3/4 3-49

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TABLE 3.3-11 (Continued)

ACTION STATEMENTS ,

ACTION 1 - With the number of OPERABLE channels less than the : l MINIMUM CHANNELS OPERABLE requirements of Table 3.3-11, either restore the inoperable channel (s) to OPERABLE status within 30 days or be in HOT STANDBY -

within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 2 - With the number of channels OPERABLE less than the l MINIMUM CHANNELS OPERABLE, determine the subcooling marsin once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 3 - With any individual valve position indicator inoperable, obtain quench tank temperature, level and pressure information, and

, monitor discharge pipe temperature once per shif t to determine valve position. This action is nct required if the PORY block valve is closed with power removed in accordance with Specification 3.4.3.a or 3.4.3.b.

ACTION 4 - a. With the number of OPERABLE accident monitoring instrumentation channels less than the total number of channels shown in Table 3.3-11, restore the inoperable channel (s) to OPERABLE status within 7 days, or submit a special report to the Commission pursuant to l Specification 6.9.2 within the next 10 days outlining the cause of the malfunction, the plans for restoring the  !

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- channel (s) to OPERABLE status, and any alternate methods in affect for estimating the app!! cable parameter I

during the interim.

- b. With the number of OPERABLE accident monitoring instrumentation channels less thah the MINIMUM l CHANNELS OPERABLE requirements of Table 3.3-11,  !

restore the inoperable channel (s) to OPERABLE status j within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or submit a specla! report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction, the plans for restoring the channel (s) to OPERABLE status, and any alternate methods in affect for estimating the ,

applicable parameter during the interim. l I

MILLSTONE - UNIT 2 3/4 3 4g Amendment No. 120

F.

With the number of OPERABLE accident. monitoring instrumentation

. ACTION'5 -

channels less than the MINIMUM CHANNELS OPERABLE requirements

- of Table 3.3-11, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or begin at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 6 - With any channel of radiation monitoring, instrumentation inoperable, portable hand-held radiation detection equipment will be used to assess radiation releases from the atmospheric dump valves and steam generator safeties subsequent to a steam -

generator tube rupture.

ACTION 7 - Restore the inoperable system to OPERABLE status within 7 days .

or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. (See the

ACTION statement in Technical Specification 3.4.6.1.)".

ACTION 8 - With the number of OPERABLE Channels one less than the MINIMUM CHANNELS OPERABLE in Table 3.3-11, either restore the .

inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible without shutting down or:

Prepare and submit a Special Report to the Commission

, 1.

pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring tha system to OPERABLE status; and 2 .' . Restore the'syster to OPERABL(' status at the next scheduled refueling; and , ,

3. Initiate an alternate method of monitoring the Reactor Vessel inventory.

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MILLSTONE - UNIT 2 . 3/4 3-48a Amendment"No. JN 140

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INSTRUMENTATION '

RADIOACTIVE LIOUID'EFFLUERT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION ,

3.3.3.9' The radioactive liquid effluent senitoring instrumentation ' channels shown in Table 3.3-12 shall be OPERABLE with applicable alam/ trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.

The setpoints shall be determined in accordance with methods and parameters as described in the ODCM.

APPLICABILITY: As shown in Table 3.3-12.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alam/ trip setpnint less conservative than required by the above specification, without delay suspend the release ,

of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

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WiththeneberofchannelslessthantheminNaunchannels operable requirement, take the ACTION shown in Table 3.3-12.

Exert best efforts to restore the inoperable monitor to OPERABLE I status within 30 days and, if unsuccessful, explain in the'next #

5esiannual Effluent Report why the inoperability was not corrected in a timely manner. Releases need not be terminated after 30 days pm vided the specified actions are continued.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicabfe.

SURVEILLANCE RE@!REMEhTS z=

4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channe1 shall ha demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECX, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12.

a MILLSTONE - UNIT 2 3/4 3-50 Amendment No. 104 4

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