ML20202B708

Amends 134 & 126 to Licenses DPR-42 & DPR-60,respectively, Revising TS 3.4.B, Afs, to Provide Specific Guidance for Conducting post-maint Operational Testing of turbine-driven Afp & Associated Sys Valves

ML20202B708
Person / Time
Site:	Prairie Island
Issue date:	11/25/1997
From:	Wetzel B NRC (Affiliation Not Assigned)
To:
Shared Package
ML20202B713	List: ML20202B708 ML20202B721
References
NUDOCS 9712030159
Download: ML20202B708 (10)

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t UNITED STATES

,g NUCLEAR REGULATORY COMMISSION 2

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NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 FRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.134 License No. DPR 42 1.

The Nucle.1r Regulatory Commission (the Commission) has found that:

A.

Th3 application for amendment by Northem States Power Company (the licensee) dated September 26,1997, 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 snd regulations of the Commission:

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l 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 ampliance 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.

j 2.

Accordingly, the license is amended by charTes to the Technical 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 react as follows:

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l 9712030159 971125 PDR ADOCK 03000282 P

PDR

2 Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No334, are hereby incorporated in the license. The licensee shah operate the fadlity in acco tlance with the Technical Specifications.

3.

This license amendment is effective % r.J tho date of issuance, with full implementation within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION h

sfr Beth A. Wetzel, Senior Project Manager Project Directorate ill-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: November 25, 1997 l

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ATTACHMENT TO LICENSE AMENDVENT NO.134 FACILITY OPERATING LICENSE NO. PR42 DOCKET NO. 50-282 Revise Appendix A Technical Specifications by removing the pages identifed below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

BliMQVE INSERT TS.3.4-2 TS.3.4-2 Table TS.3.5-2B Table TS.3.5-2B (Page 5 of 9)

(Page 5 of 9) i

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4 TS.3.4-2 3.4.B.1.

d.

A minimum of 100,000 gallons of water is available in the condensate storage tanks and a backup supply of river water is available through the cooling water system.

e.

Motor operated valves MV-32242 and MV-32243 (Unit 2 valves MV-32248 and MV-32249) shall have valve position monitor lights OPERABLE and shall be locked in the open position by having the motor control center supply breakers physically locked in the off position.

f.

Manual valves in the above systems that could (if ons is im-properly positioned) reduce flow below that assumed for accident analysis shall be locked in the proper position for emergency use. During POWER OPERATION, changes in valve position will be under direct administrative control.

g.

The condensate supply cross connect valve C-41-2, to the auxiliary feedwater pumps shall be blocked and tagged open.

Any changes in position of thio valve shall be under direct administrative control.

2.

During STARTUP OPERATION or POWER OPERATICN, any one of the following conditions of inoperability may exist for each unit provided STARTUP OPERATION is discontinued (except as noted in l

3.4.B.2.a) until OPERABILITY is restored.

It OPERABILITY is not restored within the time specified, place the affected unit (or either unit in the case of a motor driven AFW pump inoperability) in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce reactor coolant system average temperature below 350*F within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

a.

A Turbine Driven AFW pump, system valves and piping may be inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

STARTUP OPERATION may continue with a Turbine Driven AFW Pump and/or associated system valves inoperable based solely on the In-Service testing requirements of TS section 4.2.A.2 and flow verification having not been met, provided all other requirements for operability are satisfied. The pump and/or associated system valves must be tested and operable prior to exceeding 10% reactor power or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from increasing RCS temperature above 350'F.

b.

A motor driven AFW pump, system valves and piping may be inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

c.

The condensate storage tanks may be inoperable for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided the cooling water system is available as a backup supply of water to tne auxiliary feedwater pumps.

d.

The backup supply oE river water provided by the cooling water system may be inoperable for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided a minimum of 100,000 gallons of water is available in the condensate storage tanks.

The valve position monitor, lights for motor operated valves e.

MV-32242 and MV-32243 (Unit 2 valves MV-32248 and MV-32249) may be inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided the associated valves' positions are verified to be open once each shift.

Prairie Island Unit 1 Amendment No. 91, 107, 134 Prairie Island Unit 2 Amendment No. $4, J0h, 126

,o,m Table TS.3.5-2B (Page 5 of 9) 8$

ENGINEERED SAFETY FZATURE AC1UATION TABLE INSTRUMENTATION 4

YY MINIMUM II FUNCTIONAL UNIT TOTAL NO.

CHANNELS CHANNELS APPLICABLE di OF CHANNELS TO TRIP OPERABLE MODES FACTION-7.

AUXILIARY FEEDNATER ce a.

Manua.1 2

1 2

1, 2, 3 26' b.

Steam Generator Lo-Lo 3/SG 2/SG in 2/SG in 1, 2, 3 24 Water Level any SG each S G c.

Undervoltage on 4.16kV Buses 2/ bus 1/ bus on 2 on one 1, 2 29 11 and 12 (Unit 2: 21 and 22) both bus (Start Turbine Driven Pump buses only) d.

Trip of Both Main Feedwater Pumps 1.

Turbine Driven 2

2 2

1, 2

• 26 2.

Motor Driven 2

2 2

1, 2*

26 e.

Saiety Injectlov s= r.re.as tm n m n, as w % meeshg Asteau ed W I

f.

Automatic Actuation Logic 2

1 2

1, 2, 3 30 and Actuation Relays 1

2= 2-3 9 The Auxiliary Feedwater auto start of the Turbine and Motor Driven AFW pumps caused by the Trip of Both Main Qg Feedwater Pumps maybe hvpassed during Startup and Shutdown Operations when the Main Feedwater Pumps are not gg required to supply feeowater to the Steam Generators.

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t UNITED STATES i

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,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. SeteH001 o

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N_. BTHERN STATES POWER COMPANY Q

DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.126 Licenso No. DPR-60 1.

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

A.

The application for amendment by Northern States Power Company (the licensee) dated September 26,1997, 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.

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:

. Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.126, 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, with full implementation within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION Ac.

L 0

Beth A. Wetzel, Senior Project Manager Project Directorate lil-1 Division of Reactor Projects -lil/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: November 25, 1997 N

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4 12G 2-ATTACHMENT TO LICENSE AMENDMENT NO.126 FACILITY OPERATING LICENSE NO. DPR 60 DOCKET NO. 50-306 Revise Appendix A Technical Specifications by removing the pages identified beicw 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.3.4 2 TS.3.4-2 Table TS.3.5 2B Table TS.3.5-2B (Page 5 of 9)

(Page 5 of 9)

TS.3.4.

3.4.3.1.

d.

A minimum of 100,000 gallons of water is available in the condensate storage tanks and a backup supply of river water is PM ilable through the cooling water system.

e.

Motor operated valves MV-32242 and MV-32243 (Unit 2 valves-MV-32248 and MV-32249) shall have valve position sonitor lights OPERABLE and shall be locked in the cpen position by having the motor control center supply breakers physically locked in the off position.

f.

Manual valves in the above systems that could (if one is sm-properly positioned) reduce flow below that assumed for accident analysis shall be locked in the proper positis

.br emergency use. During POWER OPERATION, changes in valv position will be under direct administrative control.

g.

The condensate supply cross connect valve C-41-2, to the auxiliary feedwater pumps shall be blocked and tagged open.

Any changes in position of this valve shal'. de under direct administrative control.

2.

During STARTUP OPERATION or POWER OPERATION, any one of the following conditions of inoperability may exist for each unit provided STARTUP OPERATION is discontinued (except as noted in l

3.4.B.2.a) until OPERABILITY is restored. If CPERABILITY is not

• restored within the time specified, place the affected unit (or either unit in the case of a motor driven AFW pumt inocerability) in at least NOT SRUIDOWN within the next 6 hourc and reduce resetor coolant system average temperature below 350'F within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, A Turbine Driven AFW pump, system valves and piping may be s.

inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. STARTUP OPERATION may continue with a Turbine Driven AFW Pump and/or associated system valves inoperable based solely on the In-Service testing requirements of TS section 4.2.A.2 and flow verification having not been met, provided all other requirements for operability are satisfied. The pump and/or associated system valves must be tested and operable prior to exceeding 10% reactor power or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from increasing RCS temperature above 350*F.

b.

A motor driven AFW pump, system valves and piping may be j.

inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

c.

The condensate storage tanks may be inoperable for de hours provided the cooling water system is available as a backup supply of water to the auxiliary feedwater pumps.

d.

The backup supply of river water provided by the cooling water system may be inoperable for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided a minimum of 100,000 gallons of water is available in the condensate storage tanks.

The valve position monitor lights for motor operated valves e.

MV-32242 and MV-32243 (Unit 2 valves MV-32248 and MV-32249) may be inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided the associated valves' positions are verified to be open once each shift.

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Prairie. Island Unit 1 Amendment No. 97, 101. 134 Prairie Island Unit 2 Amendment No. 14, )lhD. 126 i

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Table TS.3.5-29 (Page 5 of 9)

-51 88 ltNGINEERED SAFETY FEATURE ACTUATION TABLE IrvsauvriosanTION ee MINIMUM II FUNCTIONAL UNIT TUTAL NO.

CHANNETS CHANNELS AFPLICABLE di OF CHANNELS TO TRIP OPERA 3LE MODES ACTION EE 7.

AUXILIARY FREDNATER 3;

a.

Manual 2

1 2

1, 2, 3 26 b.

Steam Generator Lo-Lo 3/SG 2/SG in 2/90 in 1, 2, 3

24 Nater Level any SG each S G c.

Undervoltage on 4.16kV Buses 2/ bus 1/ bus on 2 on one 1, 2 29 11 and 12 (Unit 2: 21 and 22) both bus (Start Turbine Driven Pump buses only) d.

Trip of Roth Main Feedwater Pumps 1.

Turbine Driven 2

2 2

1, 2

• 26 2.

Motor Driven 2

2 2

1, 2

• 26 e.

Safety Injection so we w inn a e me as asas, mee eensee mmes aus e e

f.

Automatic 7.ctuation Logic 2

1 2

1, 2, 3 30 and Actuation Relays 3> 3=

• $ 3 The Auxiliary Feedwater auto start of the Turbine and Motor Driven AFN pumps caused by the Trip of Both Main pQ Feedwater Pumps maybe bypassed during Startup and Shutdown Operations when the Main Feedwater Punips are not gg required to supply feedwater to the Steam Generators.

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