ML20087F357

Proposed Tech Specs Table TS 3.15-1,Pages 1 & 2 & Bases Page B.3.15-1 Marked Up to Implement License Amend Request

ML20087F357
Person / Time
Site:	Prairie Island
Issue date:	08/09/1995
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20087F343	List: ML20087F341 ML20087F357
References
NUDOCS 9508150239
Download: ML20087F357 (7)

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B.3.15-1 3.15 EyENT MONITORING INSTRUMENTATION Bases The OPERABILITY of the event monitoring instrumentation ensures that sufficient information is available on s21ected plant parameters to monitor and assess these variables during and following an accident. This capability is consistent with the recommendations of NUREG-0578] and NUREG-0737 kW{jh~ji[Rfggli6[f36Qlsg}J{sy~sg6WJgg6;fpg'iligg{@

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The fo11owin5 core exit thermocouples are included in the center core region referenced in M151sR$13II,53Me"jp^g$yMsfe'WQ[Specificatier 3.15. ^_. 3.

If a 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 available, from test equipment readings from the Core Exit Thermocouple Junction Boxes.

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i SUPPLEMENT to LICENSE AMENDMENT REQUEST Dated January 10,1995 Post Accident Monitoring Technical Specification Conformance to Standard Technical Soecifications ATTACHMENT 2 l

l Appendix A, Technical Specification Revised Pages i

TABLE TS.3.15-1 Page 1 9

TABLE TS.3.15-1 Page 2 i

B.3.15-1

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

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EVENT MONITORING INSTRUMENTATION Function Reauired Channels Action ('3 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, 2 6.

Reactor Vessel Water level 2

1, 3 7.

Containment Sump Water Level (Wide Range) 2 1, 2 8.

Containment Pressure (Wide Range) 2 1, 2 9.

Automatic Containment Isolation Valve Position 2 per penetration 1, 2 flow path (bice) 10.

Containment Area Radiation (High Range) 2 1, 3 11.

Hydrogen Monitors 2

1, 4 12.

Pressurizer Level 2

1, 2 13.

Steam Generator Water Level (Wide Range) 2 per steam 1, 2 generator

^a 14.

Condensate Storage Tank Level 2

1, 2 y g.

Ye 15.

Core Exit Thermocouples 4 per core 5, 6 gg quadrant o,m m,w 16.

Refueling Water Storage Tank Level 2

1, 2

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TS.3.15.

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 channel to OPERABLE status within 7 days, or submit a report to the Commission within the following 14 days.

4.

With two required channels inoperable, either restore one channel to OPERABLE status 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 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 />.

5.

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 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 prior to startup following the next refueling outage.

6.

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

,s g the outside core region, restore the inoperable channels to OPERABLE status within y g.

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 />, g7 "d

S 'w (b)

Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, or blind flange.

t3 e-(c)

Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

a

'.3.15-1 I

3.15 $ VENT MONITORING INSTRUMENTATION I

Bases j

The OPERABILITY of the event monitoring instrumentation ensures that sufficient information is available on selected plant parameters to moattor 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 method 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.

Some containment penetration flow paths may have one valve with position indication based on the justification that another mechanism is provided to assure containment integrity is maintained. In the event the position indication on the one valve fails, the justification for the penetration to have a single valve with position indication is assumed to remain valid. Since another mechanism continues to provide containment integrity, the applicable action is Action Statement 1.

The following core exit thermocouples are included in the center core region referenced in Table TS.3.15-1, Action Statement 5. If a 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 1-10 32 J-6 33 J-8 34 J-9 i

Core exit thermocouple readings necessary to meet the requirements of I

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.

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