ML20077R522

Proposed Tech Specs Re Post Accident Monitoring

ML20077R522
Person / Time
Site:	Prairie Island
Issue date:	01/10/1995
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20077R511	List: ML20077R505 ML20077R515 ML20077R522
References
NUDOCS 9501200316
Download: ML20077R522 (24)

Text

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LICENSE AMENDMENT REQUEST DATED January 10, 1995 Post Accident Monitoring Technical Specifications Conformance to Standard Technical Specifications EXHIBIT B Appendix A, Technical Specification Pages ,

Marked Up Pages i t

TS-iv TS-xii TS.3.15-1 L TS.3.15-2 Table TS.3.15-1 Table TS.3.15-2 Table TS.3.15-3 new Table TS.3.15-1 (Page 1 of 2) new Table TS.3.15-1 (Page 2 of 2)

Table TS.4.1-1C (Page 2 of 4)

Table TS.4.1-1C (Page 3 of 4)

Table TS.4.1-1C (Page 4 of 4)

B.3.15-1 l

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9501200316 950110 PDR ADOCK 05000282 P, PDR

TS-iv TABLE OF CONTENTS (Continued) f TS SECTION TITLE PAGE 3.10 Control Rod and Power Distribution Limits TS.3.10-1 A. Shutdown Margin TS.3.10-1 B. Power Distribution Limits TS.3.10-1 C. Quadrant Power Tilt Ratio 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. Contral Rod Operability Limitations TS.3.10-7 H. Rod Drop Time TS.3.10-7 I. Monitor Inoperability Requirements TS.3.10-8 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 A Control Room Special Ventilation System TS.3.13-1 1

3.14 Fire Detection and Protect.on Systems TS.3.14-1  ;

A. Fire Detection Instru.nentation TS.3.14-1 l 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 An P:::::: M: nit::: TS.3.15 1 S. R dicti:n "::it::: 'TE.3.15-1 C. n;;;t r '.' :::1 L;c;l In;t;;;;nt; tion @Gv3.15 2 i

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. , TS-xii TECHNICAL SPECIFICATIONS LIST OF TABLES TS TABLE TITLE  ;

1-1 Operational Modes 3.5-1 Engineered Safety Features Initiation Instrument Limiting l

Set Points 3.5-2A Reactor Trip System Instrumentation  !

3.5-2B Engineered Safety Feature Actuation System Instrumentation 3.9-1 Radioactive Liquid Effluent Monitoring Instrumentation 3.9-2 Radioactive Gaseous Effluent Monitoring Instrumentation 3.14-1 Safety Related Fire Detection Instruments  !

3.15-1 Event Monitoring Instrumentation 0;::::: O C:xt ri-- - .t  !

2.15-2 .;nt M it: ring In:tr--- ;t:tien P.2fictic:

4.1-1A Reactor Trip System Instrumentation Surveillance {

Requirements

, 4.1-1B Engineered Safety Feature Actuation System Instrumentation l Surveillance Requirements -

4.1-1c Miscellaneous Instrumentation Surveillance Requirements 4.1-2A Minimum Frequencies for Equipment Tests 4.1-2B Minimum Frequencies for Sampling Tests ,

4.2-1 Special Inservice Inspection Requirements 3 4.10-1 Radiation Environmental Monitoring Program (REMP) Sample Collection and Analysis

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4.10-2 RFMP - Maximum Values for the Lower 4.10-3 RFMP - Reporting Levels for Radioactivity Concentrations in Environmental Samples ,

4.12-1 Steam Generator Tube Inspection 4.13-1 Snubber visual Inspection Interval 4.17-1 Radioactive Liquid Effluent Monitoring Instrumentation  ;

Surveillance Requirements 4.17-2 Radioactive Gaseous Effluent Monitoring Instrumentation l Surveillance Requirements 4.17-3 Radioactive Liquid Waste Sampling and Analysis Program '

4.17-4 Radioactive Gaseous Waste Sampling and Analysis Program ,

5.5-1 Anticipated Annual Release of Radioactive Material in Liquid  !

Effluents From Prairie Island Nuclear Generating Plant I (Per Unit) ,

5.5-2 Anticipated Annual Release of Radioactive Nuclides in f' caseous Effluent From Prairie Island Nuclear Generating Plant (Per Unit) 6.1-1 Minimum Shift Crew Composition ,

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d TABLE TS.4.1-1C (Page 2 of4) -

MISCELLANEOUS INSTRUMENTATION SURVEILLANCE REOUIREMENTS FUNCTION 6L RESPONSE MODES FORWHICH FUNCT10NAL UNIT CHECK CALIBRATE TEST TEST SURVEILLANCE IS REOUIRED

13. Containment Sump A, B and C NA R R N.A. 1, 2, 3, 4 IM

14. Accumlator Level and S R R N.A. 1, 2, 3, 4 Pressure

15. Turbine First Stage S R Q N.A. 1 Pressure

16. E..w.ge.g Plan Radiation M R M N.A. 1,2,3,4,5,6 l Instruments *)

l

17. Seismic Monitors R R N.A. N.A. ,1,2,3,4,5,6 i8. Coolant Flow- RTD S R M N.A. 1, 2, 3 *)

Bypass Flowmeter l

19. CRDM Cooling S N.A. R N.A. 1,2,35),45) ,55) l Shroud Exhaust AirTemperature

20. Reactor Gap Exhaust Air S N.A. R N.A. 1, 2, 3, 4 Temperature

21. Post-Accident Monitoring Imuw-.s M R N.A. N.A. 1, 2 (Table TS.3.15-1)*)

22.NO N M a r d _'.; . D R M N-A- 4,-2 P " w.'..; _. _

U i '; ' " .3.15 3)

SN a.<

u?

a 51.$

3:.

o

i TABLE TS.4.1-1C (Page 3 of 4) -

l MISCELLANEOUS INSTRUMENTATION SURVEILLANCE REOUTREMENTS 4

FUNCTIONAL EESPONSE MODES FOR WHICH FUNCTIONAL UNIT CHECK CALIBRATE TEST TEST SURVEILLANCE IS emm REOUIRF,D 23.IDeletedi

Pr ^.d.,L..; '.L. :_ .; M R NA NA h4

' = .. : :: =.

(Tah'5.3.153)

24. Steam Exclusion Actuation W Y M NA 1, 2, 3

25. Overpressure Mitigatum NA R R NA 4*,5

26. Auxiliary Feedwater NA R R N.A. 1, 2, 3 Pump Suction Pressure

27. Auxiliary Feedwater N.A. R R N.A. 1, 2, 3 Pump Dbdsge Pressure

28. NaOH Caustic Stand Pipe W R M NA 1, 2, 3, 4 I m et

29. Hydrogen Monitors S Q M N.A. 1, 2 i

30. ContainmentTemperature M R NA N.A. 1, 2, 3, 4 Monitors

31. Turbine C.mM N.A. R M N.A. 1 PmkciniTrip Charmel

.i 9,e, a

k*a .

b i-o

- - _ _ _ _ - - _ _ . . - . _ _ _ _ . . _ . -n-- .. -c. , , _ , , , . - . . , . - , , . , , - - , ,. . . - , . . . . . - . - , . , . , . , _ . , . . . - , . . ,, . , , , ,,, - . . , .

s -

• i TABLE 4.1-1C (Page 4 of 4)

TABLE NOTATIONS I

FREQUENCY NOTATION NOTATION FREOUENCY S Shift D Daily W Weekly M Monthly Q Quarterly

~

S/U Prior to each startup Y Yearly R Each refueling shutdown N.A. Not Applicable TABLE NOTATION (30) Prior to each startup following shutdown in (36) Except for containment hydrogen monitors excess of two days if not done in previous 30 Ind re ssGs53istjiQsf6EagiFisnQ1~ sis!

days. whi}ch (are separately specifled in this table.

(31) When the reactor trip system breakers are closed (37) When RHR is in operation.

and the control rod drive system is capable of rod withdrawal.

(32) Following rod motion in excess of six inches (38) When the reactor coolant system average when the cceputer is out of service. temperature is less than 3108F.

(33) Transfer logic to Refueling Water Storage Tank. (39) Whenever CONTAINMENT INTEGRITY.is required.

(34) When either main steam isolation valve is open. _q (35) Includes those instruments named in the 50 o-emergency prodedure. **

• 0 R-.

k O

. _ . - . - - - _ - - - _ _ _ _ _ _ _ _ _ - . _ . _ . . . - , . . . . . . . . . - . -. . . . _. .-. . . - . . ~ . ._ . , . . . . . . - . - . . . . . . - . . , . .., ._

f 815 B.3.15-1 3.15 EVENT MONITORING INSTRUMENTATION ,

Pases 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-0578j and-NUREG-0737 g g y jEilkt} g g y,4f g j{Vs15&}t g uf g ijj{

{slji$idjfhiE@ntatioJ).

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- ;m--  :

eh. uex

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circ _u>.a

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n-

m. x m -

reportish._cemy,~tlin.,e,u_a ..

nned:;3 tornategne et iippl.is, i,b_liBN.,h,;e$.cy alliou n . w t M ii -u ..  :;

.ss.propla,t.

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ilsil

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t,ali.nu %

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t d f ,

The following core exit thermocouples are included in the center core region 3.15.^. 3. referenced in [sble]le is not listed below,TgE11GlffMp13pjptisf.siinsytl((Spreific If a thermocoup it is located in the t outside core region.

Thermocouple Core Number Location 9 D-5 10 D-7 12 E-4 13 E-6 14 E-10 16 F-7 18 G-4 19 G-6 22 H-5 23 H-9 28 I-4 29 I-8 30 I-10 32 J-6 33 J-8 34 J9 Core exit thermocouple readings necessary to meet the requirements of Specification 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 equipment readings from the Core Exit Thermocouple Junction Boxes. <

l

9 LICENSE AMENDMENT REQUEST DATED January 10, 1995 Post Accident Monitoring Technical Specifications Conformance to Standard Technical Specifications EXHIBIT C f

Appendix A, Technical Specification Pages Revised Pages TS-iv TS-xii TS.3.15-1 Table TS.3.15-1 (Page 1 of 2)

Table TS.3.15-1 (Page 2 of 2)

Table TS.4.1-lC (Page 2 of 4)

Table TS.4.1-lc (Page 3 of 4)

Table TS.4.1-1C (Page 4 of 4)

B.3.15-1

m -e -

TS-iv i

TABLE OF CONTENTS (Continued)

TS_SECTION TITLE PAGE l

3.10 Control Rod and Power Distribution Limits TS.3.10-1 A. Shutdown Margin TS.3.10-1 B. Power Distribution Limits TS.3.10-1 C. Quadrant Power Tilt Ratio 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. Control Rod Operability Limitations TS.3.10-7 H. Rod Drop Time TS.3.10-7 I. Monitor Inoperability Requirements TS.3.10-8 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  ;

A Control Room Special Ventilation 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.3.34-3 E. Fire Hose Stations TS.3.14-3 F. Yard Hydrant Hose Houses TS.3.14-4 C. Penetration Fire Barriers TS.3.14-4 '

3.15 Event Monitoring Instrumentation TS.3.15-1 l 1

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. . TS-xii TECHNICAL SPECIFICATIONS LIST OF TABLES TS TABLE TITLE 1-1 operational Modes 3.5-1 Engineered Safety Feetures Initiation Instrument Limiting Set Points 3.5-2A Reactor Trip System Instrumentation 3.5-2B Engineered Safety Feature Actuation System Instrumentation 3.9-1 Radioactive Liquid Effluent Monitoring Instrumentation 3.9-2 Radioactive Gaseous Effluent Monitoring Instrumentation 3.14-1 Safety Related Fire Detection Instrumente 3.15-1 Event Monitoring Instrumentation l

4.1-1A Reactor Trip System Instrumentation Surveillance Requirements 4.1-1B Engineered Safety Feature Actuation System Instrumentation Surveillance Requirements 4.1-3C Miscellaneous Instrumentation Surveillanco Requirements 4.1-2A Minimum Frequencies for Equipment Teste 4.1-2B Minimum Frequencies for Sampling Tests 4.2-1 Special Inservice Inspection Requirements 4.10-1 Radiation Environmental Monitoring Program (REMP) Sample Collection and Analysis 4.10-2 RFMP - Maximum Values for the Lower 4.10-3 RFMP - Reporting Levels for Radioactivity Concentrations in Environmental Samples 4.12-1 Steam Generator Tube Inspection 4.13-1 Snubber Visual Inspection Interval 4.17-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 4.17-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 4.17-3 Radioactive Liquid Waste Sampling and Analysio Program 4.17-4 Radioactive Gaseous Waste Sampling and Analysis Program 5.5-1 Anticipated Annual Release of Radioactive Material in Liquid Effluents From Prairie Island Nuclear Generating Plant (Per Unit) 5.5-2 Anticipated Annual Release of Radioactive Nuclides in Gaseous Effluent From Prairie Island Nuclear Generating Plant (Per Unit) 6.1-1 Minimum Shift Crew Composition

. . TS.3.15-1 o

3.15 EVENT HONITORING INSTRUMENTATION Applicability Applies during MODES 1, and 2.

Obiective 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.

Specification A. Event monitoring instrumentation shall be OPERABLE as specified in Table TS.3.15-1.

B. Action statements applicable by reference from Table TS.3.15-1.

C. MODES 1, and 2 may be entered when a LIMITING CONDITION FOR OPERATIO. is

, not met.

D. The provisions of specification 3.0.C are not applicable.  !

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TABLE TS.3.15-1 (Page 1 of 2)

EVENT MONITORING INSTRUMENTATION -

Function Required Channels Action (*)

1. Power Range Neutron Flux (Logarithmic Scale) 2 1, 2

2. Source Range Neutron Flux (Logarithmic Scale) 2 1, 2

3. Reactor Coolant System (RCS) Hot Leg Temperature 2 1, 2

4. RCS Cold Leg Temperature 2 1, 2

5. RCS Pressure (Wide Range) 2 1, 3

6. Reactor Vessel Water Level 2 1, 3

7. Containment Sump Water Level (Wide Range) 2 1, 3

8. Containment Pressure (Wide Range) 2 1, 2

9. Containment Isolation Valve Position 2 per penetration 0'H') 1, 3

10. Containment Area Radiation (High Range) 2 1, 3

11. Hydrogen Monitors 2 1, 3

12. Steam Cenerator Water Level (Wide Range) 2 per steam 1, 2 generator

13. Condensate Storage Tank Level 2 1, 2

14. Core Exit Thermocouples 4 per core 4, 5 ,, g quadrant  ? @.

5W

15. Refueling Water Storage Tank Level 2 1, 2 -, g oa

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TABLE TS.3.15-1 (Page 2 of 2) .

EVENT MONITORING INSTRUMENTATION (a) Action Statements Separate Action Statement entry is allowed for each Function.

1. With one required channel inoperable, either restore the required channel to OPERABLE status within 30 days, or submit a report to the Commission within the following 14 days.

2. With two required channels inoperable, either restore one channel to OPERABLE status within 7 days or be in at least MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

3. With two required channels inoperable, either restore one chan ;e1 to OPERABLE status within 7 days, or submit a report to the Commission within the following 14 days.

4. With the number of OPERABLE channels for the core exit thermocouples less than the Required Channels shown on Table TS.3.15-1, but with greater than or equal to 4 core exit thermocouples OPERABLE in the center core region and greater than or equal to one core  ;

exit thermocouple OPERABLE in each quadrant of the outside core region, restore the j inoperable channels to OPERABLE status within 30 days, or submit a report to the '

Commission within the next 14 days. As a minimum, the Required Channels will be restored f prior to startup following the next refueling outage.

5. With the less than two core exit thermocouple channels OPERABLE in one or more quadrants, and with either less than 4 core exit thermocouples OPERABLE in the center region or less than one core exit thermocouple OPERABLE in each quadrant of the outside core region, restore the inoperable channels to OPERABLE status within 7' days, or be in at least MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

(b) Not required for isolation valves whose associated penetration is isolated by at least one mg closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with p g.

I flow through the valve secured. %7 us (c) Only one position indication is required for penetrations with only one control room indication, a 72 my L

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TABLE TS.4.1-1C (Page 2 of 4)

• MISCELLANEOUS INSTRUMENTATION SURVEILLANCE REOUIREMENTS .

FUNCTIONAL RESPONSE MODES FOR WHICH FUNCTIONAL UNIT CHECK CALIBRATE TEST TEST SURVEILLANCE IS REOUTRED

13. Cteninmerrt Sump A, B and C N.A. R R N.A. 1, 2, 3, 4 IwJ

14. AccumlatorIzveland S R R N.A. I, 2, 3, 4 Pressure

15. Turbine First Stage S R Q N.A. 1 Pressure

16. Emergency Plan F=Aiatina M R M N.A. I,2,3,4,5,6 Insh mi. cats *)

17. Seismic Monitors R R NA N.A. 1,2,3,4,5,6

18. Coolant Flow-RTD S R M N.A. 1, 2, 3 *)

, Bypass Flowmater

19. CRDM Cooling S N.A. R N.A. 1, 2, 353,45) ,55 )

Shroud Exhaust Air Te.igsure

20. Reactor Gap Exhaust Air S N.A. R N.A. 1, 2, 3, 4 Temperature

21. Post-Accident Monitoring Instruments M R N.A. N.A. 1, 2 (Table TS.3.15-1)*)

22. Deleted s

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. o, TABLE TS.4.1-1C (Page 3 of 4) .

MISCELLANEOUS INSTRUMENTATION SURVEILLANCE REOUIREMENTS FUNCTIONAL RESPONSE MODES FOR WHICH FUNCTIONAL UNTT CHECK CALIBRATE TEST TEST SURVEILLANCE IS REOUIRED

23. Deleted

24. Steam Exclusion Actuation W Y M N.A. 1, 2, 3

25. Overpressure Mkiptiaa N.A. R R N.A. 4",5

26. Auxiliary Fdem N.A. R .R N.A. 1, 2, 3, Pump Suction Pressure

27. Auxiliary Feedwater N.A. R R N.A. 1, 2, 3 Pump Discharge Pressure

28. NaOH Caustic Stand Pipe W R M N.A. 1, 2, 3, 4 Ixvel

29. Hydrogen Monitors S Q M N.A. 1, 2 j 30. ContainmentT_w4.re M R N.A. N.A. I, 2, 3, 4 Monitors

31. Turbine O...W N.A. R M N.A. 1 Protection Trip Channel l

d 1

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15 A u ca 9.$

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TABLE 4.1-1C (Page 4 of 4)

TABLE NOTATIONS '

i FREOUENCY NOTATION l

NOTATION TREQUENCY

S Shift D Daily 1

W Weekly M Monthly Q Quarterly ,

4 S/U Prior to each startup Y Yearly R Each refueling shutdown N.A. Not Applicable 3

TABLE NOTATION '

(30) Prior to each startup following shutdown in (36) Except for contairunent hydrogen monitors -

excess of two days if not done in previous 30 and refueling water storage tank level l ,

days. which are separately specified in this table. *

(31) When the reactor trip system breakers are closed (37) When RHR-is in operation.

and the control rod drive system is capable of rod withdrawal.

(32) Follo+ing roi motion in excess of six inches (38) When the reactor coolant. system average when the computer is out of service. temperature is less than 310*F.

(33) Transfer logic to Refueling Water Storage Tank. (39) Whenever ColtTAINMENT INTEGRITY is i required. -

(34) When either main steam isolation valve is open. _

(35) Includes those instruments named in the Eeo E.-

emergency prodedure.

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'o B.3.15-1 3.15 EVENT MONITORING INSTRUMENTATION Bases 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, NUREG-0737 and the Regulatory Guide 1.97 evaluation of Prairie Island instrumentation.

The Action Statements for one or more inoperable channels in some circumstances require submittal of a report to the Commission. The report shall outline preplanned alternate meahod of monitoring as applicable, the cause of the inoperability, and the plans and schedule for restoring the instrument channels of the Function to OPERABLE status.

The following core exit thermocouples are included in the center core region referenced in Table TS.3.15-1, Action Statement 4. If a l thermocouple is not listed below, it is located in the outside core region.

Thermocouple Core Number Location 9 D-5 10 D-7 12 E-4 13 E-6 14 E-10 16 F-7 18 G-4 19 G-6 22 H-5 23 H-9 28 I-4 29 I-8 30 I-10 32 J-6 33 J-8 34 J-9 Core exit thermocouple readings necessary to meet the requirements of Specification 3.15.A are available from the Plant Process Computer, the Control Room Core Exit Thermocouple Display or if no other readout is i l

available, from test equipment readings from the Core Exit Thernocouple Junction Boxes.

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