Text

Amends 112 & 105 to Licenses DPR-42 & DPR-60,respectively, Requesting Changes to Core Exit Thermocouple Action Statements
	ML20072S668
Person / Time
Site:	Prairie Island
Issue date:	09/07/1994
From:	Marsh L; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20072S671	List: ML20072S668; ML20072S672;
References
	NUDOCS 9409140191
	Download: ML20072S668 (10)
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i UNITED STATES

g)'%s NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055MXX)1 j

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NORTHERN STATES POWER COMPANY

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DOCKET N0. 50-282 1

PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 1

' AMENDMENT TO FACILITY OPERATING LICENSE 4

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Amendment No. 112 i

License No. DPR-42 l

1.

The Nuclear Regulatory Commission (the Commission) has found that:

4 A.

The application for. amendment by Northern States Power Company (the licensee) dated January 29, 1993, as revised June 15, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, 1

as amended (the Act), and the Commission's rules and regulations set l

forth in 10 CFR Chapter I; f

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 i

safety of the public, and (ii) that such activities will be conducted i

in compliance with the Commission's regulations;-

]

D.

The issuance of this amendment will not be inimical to the common i

defense and security or to the health and safety of the public; and 1

i 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 j

satisfied.

2.

Accordingly, the license is amended by changes to the Technical t

Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License'No. DPR-42 is hereby amended to read as follows:

i 9409140191 940907 i

PDR ADOCK 05000282 P

PDR

4

. Technical Specifications The Technical Specifications contained 'in Appendix A, as revised through Amendment No.112, 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 issuance.

FOR THE NUCLEAR REGULATORY COMMISSION L. B. Marsh, Director-Project Directorate III-I Division of Reactor Projects - III/IV Office' of Nuclear Reactor Regulation

Attachment:

Changes to the Technical-Specifications Date of Issuance: September 7, 1994 a

l l

ATTACHMENT TO LICENSE AMENDMENT N0.112 FACILITY OPERATING LICENSE NO. DPR-42 DOCKET NO. 50-282 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

REMOVE INSERT TS.3.15-1 TS.3.15-1 B.3.15-1 B.3.15-1 l

l

TS.3.15-1 l

l 3.15 EVENT M0JITORING INSTRUMENTATION Applicability J

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

Obiective l

To ensure that sufficient information is available to operators to deter-l mine the effects of and determine the course of an accident to the extent l

required to carry out required manual actions.

1 i

i Specification i

A.

Process Monitors l

1.

The event nonitoring instrumentation channels specified in Table TS.3.15-1 shall be OPERABLE.

2. With the number of OPERABLE event monitoring instrumentation channels, except the core exit thermocouples, less than the Required l

Total Number of Channels shown on Table TS.3.15-1, either restore the inoperable channels to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l l

3. With the number of OPERABLE channels for the core exit thermocouples less than the Required Total Number of Channels shown on Table TS.3.15-1, but with greater than or equal to 4 core exit i

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 prepare and submit a Special Report to the Commission pursuant to Technical Specification 6.7.B.2 within the next 14 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to l

OPERABLE status. As a minimum, the Required Total Number of Channels will be restored prior to startup following the next refueling outage.

4. With the number of OPEFAB12 channels for the core exit thermocouples l

less than the Required Total Number t Channels shown on Table l

TS.3.15-1, and with either less than 6 core ex.c thermocouples OPERABLE in the center region or less than one core exit thermocouple OPERABLE in each quadrant of the outside core region, restore the I

inoperable channels to OPERABLE status within 7 days, or be in at least HOT THUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

5. With the number of OPERABLE event monitoring instrumentation channels less than the Minimum Channels Operable requirements of Table TS.3.15-1, either restore the minim 2m number of channels to l

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 SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

PRAIRIE ISLAND UNIT 1 - AMENDMENT NO. p6, fd, 7J, pf,112 PR.AIRIE ISLAND UNIT 2 - AMENDMENT NO. 95, yl, p6, %,105 l

~

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 tTUREG-0578 and NUREG-0737.

The following core exit thermocouples are included in the center core region referenced in Specification 3.15.A.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 I

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.

PRAIRIE ISLAND UNIT 1 - AMENDMENT NO. jd',112 PRAIRIE ISLAND UNIT 2 - AMENDMENT NO. p4, 105

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UNITED STATES 5

"I NUCLEAR REGULATORY COMMISSION k..... j/

WASHiteCTON, D.o. 20555-0001 NORTHERN STATES POWER COMPANY

)

l DOCKET NO. 50-306 l

PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT N0. 2 l

AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No.105 l

License No. DPR-60 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Northern States Power Company (the i

licensee) dated January 29, 1993, as revised June 15, 1994, complies l

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 ir. 10 CFR Chapter I; B.

The facil n / 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 l

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.

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-60 is hereby amended to read as follows:

l

. i Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.105, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the i

Technical Specifications.

j 3.

This license amendment is effective as of the date of issuance.

)

i FOR THE NUCLEAR REGULATORY COMMISSION i

L. B. Marsh, Director-Project Directorate III-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation j

I

Attachment:

Changes to the Technical

[

Specifications j

Date of Issuance: September 7, 1994

)

l l

l

i i

=

l ATTACHMENT TO LICENSE AMENDMENT NO. 105 FACILITY OPERATING LICENSE NO. DPR-60 DOCKET NO. 50-306 l

l Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

i REMOVE INSERT TS.3.15-1 TS.3.15-1 B.3.15-1 d.3.15-1 i

t l

r f

(

TS.3.15-1 j

3.15 EVENT MONITORING INSTRUMENTATION l

Applicability Applies to plant instrumentation which does not perform a protective func-tion, but which provides information to monitor and assess important l

parameters during and following an accident.

Obiective i

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

l Specification A.

Process Monitors 1.

The event monitoring instrumentation channels specified in Table TS.3.15-1 shall be OPERABLE.

2. With the number of OPERABLE event monitoring instrumentation channels, except the core exit thermocouples, less than the Required l

Total Number of Channels shown on Table TS.3.15-1, either restore the j

inoperable channels to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l

3. With the number of OPERABLE channels for the core exit thermocouples less than the Required Tots 1 Number of 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 prepare and submit a Special Report to ti.e Com=ission pursuant to Technical Specification 6.7.B.2 within the next 14 days outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.

As a minimum, the Required Total Number of Channels will be restored prior to startup following the next refueling outage.

4. With the number of OPERABLE channels for the core exit thermocouples less than the Required Total Number of Channels shown on Table TS.3.15-1, and with either less than 4 core exit thermocouples OPERABLE in the center region or less than one core exit thermocouple OPERABil in each quadrant of the outside core region, restore the inoperable channels to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

5. With the number of OPERABLE event monitoring instrumentation enannels 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

PRAIRIEISLANDUNIT1-AMENDMENTNO.f6,FI,75,M(,,112 PRAIRIE ISLAND UNIT 2 - AMENDMENT NO pd, >1, p6, S 105

B.3.15-1 l

I 3.15 EVENT MONITORING INSTRUMENTATION Bases The OPERABILITY of the event monitoring instrumentation ensures that j

sufficient information is available on selected plant parameters to l

monitor and assess these variables during and following an accident.

l This capability is consistent with the recommendations of NUREG-0578 l

and NUREG-0737.

The following core exit thermocouples are included in the center core region referenced in Specification 3.15.A.3.

If a thermocouple is not listed below, it is located in the outside core region.

Thermocouple Core Nurber Location 9

D-5 10 D-7 12 E-4 13 E-6 l

14 E-10 l

16 F-7

(

18 C-4 19 C-6 l

22 H5 l

23 H-9 l

28 I-4 29 I-8 30 I-10 l

32 J-6 33 J-8 l

34 J-9 l

l Core exit thermocouple readings necessary to meet the requirements of l

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

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

i PRAIRIE ISLAND UNIT 1 - AMENDMENT NO. Jd',112 PRAIRIE ISLAND UNIT 2 - AMENDMENT NO. p4,105 i

i

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ML20072S668

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