ML20209F988

Amends 77 & 70 to Licenses DPR-42 & DPR-60,respectively, Revising Inadequate Core Cooling Instrumentation Sys Subcooling Margin monitors,core-exit Thermocouples & Reactor Vessel Level Instrumentation Sys

ML20209F988
Person / Time
Site:	Prairie Island
Issue date:	08/28/1986
From:	Di Ianni D, Diianni D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20209F993	List: ML20209F988 ML20209G003
References
TAC-62137, TAC-62138, NUDOCS 8609120338
Download: ML20209F988 (11)

Text

[f UNITED STATES o

3w'g NUCLEAR REGULATORY COMMISSION

.E WASHINGTON, D. C. 20555 5?oh

%..u. f NGETFERN STATES F0WER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 77 License No. DPR-42 1.

The Nuclear Regulatory Consnission (the Conr11ssion) has found that:

A.

The application for amendment by Northern States Power Company (the licensee) dated June C, 1986 conplies with the standards and recuire-ments of the Atomic Energy Act of 1954, as amended (the Act), anc the Commission's rules and regulations set forth in 10 CFR Chapter I; E.

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 (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 Commission's regulations; D.

The issuance of this amendment will not be inimical to the conren defense and security or to the health and safety of the public; and E.

The issuance of this amendaent is in accordance with 10 CFR Part 51 of the Commission's regulations ar.d all applicable requircn;ents have been satisfied.

0609120338 86032s DR ADOCK 05000202 PDH

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. 2.

Accordingly, the licenses are amended by changes to the Technical Specifications as indicated in the attachment to this license amendmerit, and paragraph 2.C.(2) of Facility Operating License fic. DPR-42 are hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.77

, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Techr.ical Specifications.

3.

This license amendment is effective as of the date of its issuur.ce.

FOR THE hUCLEAR REGULATORY C0PMISSION

^ - "

<W Dominic C. Dilanni, Project Manager Project Directorate #1 Division of PWR Licensing-A

Attachment:

Changes to the Technical Specificctions Cate of Issuance:

August 28, 1986

[

UNITED STATES

.? '

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NUCLEAR REGULATORY COMMISSION C

WASHINGTON, D. C. 20555 g..v

,/

NORTHERN STATES POWER COMPAN)

DOCKET NO. 50-306 PPA!RIE ISLAND NUCLEAR GENEPATING PLANT UNIT NC. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment f.'o.

70 License No. DPR-60 1.

The Nuclear Regulatory Comission (the Consnission) has found that:

A.

The applicatior, for amendaent by Northern States Power Compan,y (the licensee) dated June 6, 1986 cwplies with the standards and reouire-ments of the Atomic Energy Act cf 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 Commission; 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 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 amendnent is in accordance with 10 CFR Part 51 of the Commission's regulatier.s and all applicable recuirements have heen satisfied.

=

. - _ =. =

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. 1 2.

Accordingly, the licenses are 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-60 are hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appanoix A, as revised through Amendment No. 70, 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 its issuance.

FOR THE NUCLEAR REGULATORY C0FMISSION w

Le M

Doninic C. Dilanni, Project Manager i

Project Directorate #1 Division of PWR Licensing-A i

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 28, 1986 i

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1 ATTACHMENT TO LICENSE AMENDMENT N05. 77 AND 70 TO FACILITY OPERATING LICENSE NOS. OPR-42 AND DPR-60 DOCKET NOS. 50-282 AND 50-306 l

Replace the following pages of the Appendix A Technical Specifications l

with the enclosed pages as indicated.

The revised pages are identified by amendment number and contain vertical lines indicating the area of changes.

Remove Insert TS-iii TS-iii TS.3.15-1 TS.3.15-1 TS.3.15-2 TS.3.15-2 Table TS.3.15-1 Table TS.3.15-1 Table TS.3.15-3 Table TS.4.1-1 (Page 4 of 5) Table TS.4.1-1 (Page 4 of 5)

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TS-iii REV TABLE OF CONTENTS TS SECTION TITLE PAGE 3.5 Instrumentation System TS.3.5-1 3.6 Containment System TS.3.6-1 A. Containment System Integrity TS.3.6-1 B. Containment Internal Pressure TS.3.6-3 C. Containment and Shield Building Air Temperature TS.3.6-3

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D. Containment Shell Temperature TS.3.6-3 E. Emergency Air Treatment Systems TS.3.6-3A F. Electric Hydrogen Recombiners TS.3.6-3A 3.7 Auxiliary Electrical Systems TS.3.7-1 3.8 Refueling and Fuel Handling TS.3.8-1 D. Spent Fuel Pool Special Ventilation System TS.3.8-3 3.9 Radioactive Effluents TS.3.9-1 A. Liquid Effluents TS.3.9-1 B. Gaseous Effluents TS.3.9-3 C. Solid Radioactive Waste TS.3.9-6 D. Dose from All Urtnium Fuel Cycle Sources TS.3.9-7 E. Radioactive Liquid Effluent Monitoring TS.3.9-7 Instrumentation F. Radioactive Caseous Effluent Monitoring TS.3.9-8 Instrumentation 3.10 Control Rod and Power Distribution Limits TS.3.10-1 A. Shutdown Reactivity TS.3.10-1 B. Power Distribution Limits TS.3.10-1 C. Quadrant Power Tilt Limits TS.3.10-4 D. Rod Insertion Limits TS.3.10-5 E. Rod Misalignment Limitations TS.3.10-6 F. Inoperable Rod Position Indicator Channels TS.3.10-6 G. Inoperable Rod Limitations TS.3.10-6 H. Rod Drop Time TS.3.10-7 I. Monitor inoperability Requirements TS.3.10-7 J. DNB Parameters TS.3.10-8 3.11 Core Surveillance Instrumentation TS.3.11-1 3.12 Snubbers TS.3.12-1 3.13 Control Room Air Treatment System TS.3.13-1 3.14 Fire Detection and Protection Systems TS,3.14-1 A. Fire Detection Instrumentation TS.3.14-1 B. Fire Suppression Water System TS.3.14-1 C. Spray and Sprinkler Systems TS.3.14-2 D. Carbon Dioxide System TS.3.14-3 E. Fire Hose Stations TS.3.14-3 F. Yard Hydrant Hose Houses TS.3.14-4 G. Penetration Fire Barriers TS.3.14-4 3.15 Event Monitoring Instrumentation TS.3.15-1 A. Process Monitors TS.3.15-1 B. Radiation Monitors TS.3.15-1 C. Reactor Vessel Level Instrumentation TS.3.15-2 l

Unit No.1 - Amendment No./77. JA. 77 Unit No. 2 - Amendment No. 44, 41, 70

TS.3.15-1 REV 3.15 EVENT MONITORING INSTRUMENTATION Applicability i

Applies to plant instrumentation which does not perform a protective function, but which provides information to monitor and assess important parameters during and following an accident.

Objectives To ensure that sufficient information is available to operators to determine the effects of and determine the course of an accident to the extent required to carry out required manual actions.

2 Specification 4

4 A. Process Monitors l

1. The event monitoring instrumentation channels specified in Table TS.3.13-1 shall be Operable.

a

2. With the number of Operable event monitoring instrumentation i

channels less than the Required Total Number of Channels shown

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on Table TS.3.15-1, either restore the inoperable channels to Operable status within seven days, or be in at least Hot Shut-down within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

I 1

3. With the number of Operabic event monitoring instrumentation channels less than the Minimum Channels Operable requirements of Table TS.3.15-1, either restore the minimum number of channels 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 be in 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 />.

l 2

B.

Radiation Monitors i

1. The event monitoring instrumentation channels specified in l

Table TS.3.15-2 shall be Operable.

i

2. With the number of Operable event monitoring instrumentation 1

channels less than the Required Total Number of Channels shown on Table TS.3.15-2, either restore the inoperable channels to operable status within seven days, or prepare and submit a special report to the Commission within 30 days outlining the i

action taken, the cause of the inoperability, the plans 'and the schedule for restoring the system to Operable status.

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3. With the number of Operable event monitoring instrumentation channels less than the Minimum Channels Operable requirement of Table TS.3.15-2, initiate the preplanned alternate method of monitoring the appropriate parameters in addition to submitting f

the report required in (2) above.

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Unit No.1 - Amendment No. /MS,40, AMC l

Unit No. 2 - Amendment No. AMD, 51, ff, ;

TS.3.15-2 REV C.

Specification - Reactor Vessel Level Instrumentation

1. The reactor vessel level instrumentation channels specified in Table TS.3.15-3 shall be operable

2. With the number of Operable reactor vessel level instrumentation channels less than the Required Total Number of Channels shown on Table TS.3.15-3, either restore the inoperable channels to Operable status within fourteen days, or be in 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 />.

3. With the number of Operable reactor vessel level instrumentation channels less than the Minimum Channels Operable requirements of Table TS.3.15-3, either restore the minimum number of channels 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 be in at least flot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Baois The operability of the event monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident. This capability is consistent with the recommendations of NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short Tern Recommandations."

Core exit thermocouple readings necessary to meet the requirements of Specifica-tion 3.15.A are available from the Plant Process Computer, the Control Room Core Exit Thermocouple Display or if no other readout is available, from test equip-ment readings from the Core Exit Thermocouple Junction Boxen.

Unit No. 1 - Amendment No. Af, f3,77 Unit No. 2 - Amendment No. 40, 57.7C

_. _ _.. _ _ _. _. _ _ _ _ _ _ - = _ _. - _ _ _ _ _ _..

TABLE TS,3.15-1 EVENT MONITORING INSTRI' MENTATION - PROCESS & CONTAINMENT

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Required Total No.

Minimum Channels' Instrument of Channels Operable

1. Pressurizer Water Level 2

1

2. Auxiliary Feedwater Flow to Steam Generators 2/ steam gen 1/ steam gen (One Char.nel Flow and One Channel Wide Range i

Level for Each Steam Generator)

3. Reactor Coolant System Subcooling Margin 2

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4. Pressurizer Power Operated Relief Block Valve Position 2/ valve 1/ valve l

(One Comunon Channel Temperature, One Channel l

Limit Switch per Valve, and One Channel Acoustic Sensor per valve *)

l S. Pressurizer Power Operated Relief Block Valve Position 2/ valve I/ valve 1

(One Common Channel Temperature, One Channel Limit Switch per Valve, and One Channel Acoustic Sensor j

per Valve *)

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6. Pressurizer Safety Valve Position 2/ valve 1/ valve l

(One Channel Temperature per Valve and Cosunon j

Acoustic Sensor **)

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{E7.a.ContainmentWaterLevel(wide. range) 2 1

ne 22

b. Containment Water Level (narrow range) 2 1

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8. Containment Hydrogen Monitor (2 sensors per Channel) 2 1

co e e

>> 9. Containment Pressure (wide range) 2 1

85

$U E EIO. Core Exit Thermocouples 4/ core quadrant 2/ core quadrant aa to SS Hp

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- A comanon acoust.ic sensor provides backup position indication for each pressurizer power operated h

ww relief valve and its associated block valve.

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- The acoustic sensor channel is corunon to both valves. When operable, the acoustic sensor may be g,

considered as an operable channel for each valve.

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TABLE TS.3.15-3 l

EVENT MONITORING INSTRUMENTATION - REACTOR VESSEL LEVEL l

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Required Total No.

Minimum Channels Instrument of Channels Operable l

l 1.

Reactor Vessel Level Instrumentation

• 2 1

CC 11 ne z --

PP ru -

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o H 33 D1 4 a

mo s

55

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PP C;

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• Includes the full range and dynamic head range

TABLE TS.4.1-1 (Peg 2 4 of 5)

MINIMUM FREQUENCIES FOR CliECKS, CALIBRATIONS AND l

TEST OF INSTRUMENT CHANNELS Channel Functional Reepen=c Description Check Calibratc Test Test Remarks 26 d. Reactor Trip Bypass NA NA M(1)

R(2)

1) Manually trip the undervoltage trip l

Breaker attachment remotely (i.e. from the protection system racks).

2) Automatically trip the undervoltage trip attachment 27.

Turbine Overspeed NA R

M NA l

Protection Trip Channel 28.

Deleted 29.

Deleted 30.

Deleted 31.

Seismic Monitors R

R NA NA 32.

Coolant Flow - RTD S

R M

NA Bypass Flowmeter 33.

CRDM Cooling Shroud S

NA R

NA FSAR page 3.2-56 c[ cf 34.

Reactor Gap Exhaust Air S

NA R

NA Temperature

(( gy 35a. Post-Accident Monitoring M

R NA NA Includes all those in Table TS.3.15-1 Inst ruments (except for containment hydrogen monitors which are separately

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specified in this table)

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b. Post-Accident Monitoring D

R M

NA Includes all those in Table TS.3.15-2

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Radiation Instruments

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c. Post-Accident Monitoring M

R NA NA Includes all those in Table

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Reactor Vessel I.evel TS.3.15-3 mo yg Instrumentation oy 0-

, 36.

Steam Exclusion Actuation W

Y M

NA See FSAR Appendix I,Section I.14.6 m p-g;;;?

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System 37 w.

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Overpressure Mitigation NA R

R NA Instrument Channels for PORV Control

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System Including Overpressure Mitigation la,

System In 2"

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