Text

Amend 76 to License NPF-49,revising TS Re Reactor Vessel Water Level Instrumentation by Incorporating Changes Generically Accepted by NRC
	ML20128N864
Person / Time
Site:	Millstone
Issue date:	02/18/1993
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Northeast Nuclear Energy Co (NNECO)
Shared Package
ML20128N869	List: ML20128N864; ML20128N871;
References
	NPF-49-A-076 NUDOCS 9302240004
	Download: ML20128N864 (8)
	v • d • e

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'g UNITED STATES

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g NUCLEAR REGULATORY COMMISSION r,

.p WASHINGTON,3 C. 20555

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NORTHEAST NUCLEAR ENERGY COMPANY. ET Al.

DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACIllTY OPERATING llCENSE Amendment No. 76 License No. NPF-49 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 July 27, 1992, 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; 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 amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license anendment, and paragraph 2.C.(2) of facility Operating License No. NPF-49 is hereby amended to read as follows:

(2) Technical Soecifications lhe Technical Specifications contained in Appendix A, as revised through Amendment No. 76

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

hereby incorporated in the license. 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 REGULATORY COMMISSION

/

wK John F. Stolz, Director'-

Pre)ctDirectorate1-4 DJVisionofReactorProjects-1/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: February 18, 1993

9 4 -

ATTACHMENT T0 LICENSE AMENDMENT NO. 76 FACILTlY OPERATING LICENSE NO. NPF 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, Remove Insert 3/4 3-59 3/4 3-59 3/4 3-59a 3/4 3-59a 3/4 3-61 3/4 3 3/4 3-63 3/4 3-63 B3/4 3-5 B3/4 3-5

INSTRUMENTATION ACCIDENT HONITORING INSTRUMENTATION

/

LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPL [CABILITY: MODES 1, 2, and 3.

ACTION:

a.

With the number of OPERABLE accident monitoring instrumentation channels except the containment area high range radiation monitor, the containment hydrogen monitor, and reactor vessel water level, l

1ess than the Total Number of Channels shown in Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in at least HOT STANDBf within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

With the number of OPERABLE accident monitoring instrumentation channels except the containment area-high range radiation monitor, the containment hydrogen monitor, and reactor vessel water level less than the Minimum. Channels OPERABLE requirements of-Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , c.

With the number of OPERABLE channels for the containment area-high range radiation monitor less than required by either the total.or the Minimum Channels OPERABLE. requirements, initiate an alternate method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and either restore the inoperable channel (s) to OPERABLE status within 7 days or prepare and submit a Special Report to the Commis-sion, pursuant to Specification 6.9.2, within 14 days that provides actions taken, cause of the inoperability, and the plans and sched-ule for restoring the channels to OPERABLE status.

d.

With the number of OPERABLE channels for the enntainment hydrogen monitors less than the total number of channels shown in Table 3.3-10, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . With the number of operable channels for the containment hydrogen monitors less than the minimum channels OPERABLE requirement of Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at lea:t HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

e.

With the number of OPERABLE channels for the reactor vessel water level monitor less than the Total number of Channels shown in Table 3.3-10, either restore the inoperable channel to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the MILLSTONE - UNIT 3 3/4 3-59 Amendment No. #, p 76 0040

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LJMITING CONDITION FOR OPERATION (Continued) action taken, the; causet of :the inoperability, and theLplans; and-

-schedule for restoring the channel to. OPERABLE status. -

4 f.

With the number of-OPERABLE channels for the-: reactor = vessel water level monitor -less than the minimum-channels OPERABLE: requirements of Table 3.3-10, either restore the inoperable' channel (s) to OPERA-BLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months if repairs are-feasible without shutting-down or:-

1.

Initiate an alternate method of monitoring the reactor vessel' inventory; 2.

Prepare and submit a Special Report to the Comission 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 the channel (s).to OPERABLE status; and 3

3.

Restore the channel (s) to OPERABLE status ~ at:the next scheduled refueling.

g.

Entry 'into an OPERATIONAL MODE is pet.ditted while subject to these, ACTION _ requirements.

' SURVEILLANCE RE0VIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be-demon,

strated OPERABLE by performance of-the CHANNEL ~ CHECK and CHANNEL CALIBRATION ~

at the frequencies shown in Table 4.3-7.

AmendmentNo.?p/pf,76 MILLSTONE - UNIT 3' 3/4.3-59a 0040'

TABLE 3.3-10 (Continued) 3f!

ACCIDENT MONITORING INSTRUMENTATION

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TOTAL MINIMUM 2:

NO. OF CHANNELS INSTRUMENT CHANNELS OPERABLE E

16. Containment Area - High Range Radiation Monitor 2

1 us

17. Reactor Vessel Water Level 2*

1*

18. Containment Hydrogen Monitor 2

1

19. Neutron Flux.

2 1

A channel. consists of eight sensors in a probe. A channel is operable if four or more sensors, half or more in

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the upper head region and half or more in the upper plenum region, are operable.

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' TABLE 4.3-7'(Continued)

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ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

.U CHANNEL CHANNEL-E INSTRUMENT CHECK CALIBRATION E.'

16. Containment Area ~- High Range Radiation Monitor M

R*

w

17. Reactor Vessel. Water Level M

R**

18. Containment Hydrogen Monitor M

R-

19. Neutron Flux M-R

CHANNEL CALIBRATION may consist of an electronic calibration of the channel, not including the detector, for; j'

range decades above 10 R/h ~and a.one point calibration check' of the detector below 10 R/h with an installed or.

portable gama -' source.

b

- Electronic calibration from the ICC cabinets only.

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INSTRUMENTATION-BASES REMOTESHUTDOWNINSTRUMENTATION(Continued) instrumentation, control, and power circuits and transfer switches necessary.

to elin:inate effects of the fire and allow operation of instrumentation, con-trol and power circuits required to achieve and maintain a safe shutdown con-dition are independent of areas where a fire could damage systems normally used to shut down the reactor.

This capahtlity is consistent with General Design Criterion 3 and Appendix R to 10 CFR Part 50.

3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

The instrumentation in-cluded in this specification are those instruments provided to monitor key-variables, desig:ated as Category 1 instruments following the guidance for classification contained in Regulatory Guide 1.97, Revision 2, "Instrumenta-tion for Light-Water-Cooled Nuclear Power Plants To Assess -Plant and Environs Conditions During and following an Accident."

In the event more than four sensors in a Reactor Vessel Level channel are inoperable, repairs may only be possible during the next refueling outage.

This is because the sensors are accessible only after t'a missile shield and reactor vessel head are removed.

It is not feasibit

.o repair a channel except during a refueling outage when the missile shield and reactor vessel head are removed to refuel the core.

If only one channel.is inoperable, it should be restored to OPERABLE status in a refueling outage as soon as reason-ably possible.

If both channels are inoperable, at least one channel shall be restored to OPERABLE status in the nearest refueling outage.

3/4.3.3.7 FIRE DETECTION INSTRUMENTATION The OPERABILITY of the fire detection instrumentation ensures that both adequate warning capability is available for prompt detection of fires and that fire Suppression Systems, that are actuated by fire detectors, will discharge extinguishing agents in a timely manner.

Prompt detection and suppression of fires will reduce-the potential for damage to safety-related equipment and is an integral element in the overall facility Fire Protection l

Program.

Fire detectors that are used to actuate Fire Suppression Systems repre-sent a more critically important component of a plant's Fire Protection-Program than detectors that are installed solely for early fire warning and notification.

Consequently, the minimum number of OPERABLE fire detectors must be greater.

The loss of detection capability for Fire Suppression Systems, actuated by fire detectors, represents a significant degradation of fire protection for any area.

As a result, the establishment of a fire watch patrol must-be initiated at an earlier stage than would be warranted for the loss of detec-tors that provide only early fire warning. The establishment of frequent fire patrols in the affected areas is required to provide detection capability

-until the inoperable instrumentation is restored to OPERABILITY.

MILLSTONE - UNIT 3 B 3/4 3-5 Amendment No. 3,76 0017

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ML20128N864

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