ML20206E176

Forwards Revised TS Pages for Amends 144 & 135 to Licenses DPR-42 & DPR-60,respectively,to Update Controlled Manual or File

ML20206E176
Person / Time
Site:	Prairie Island
Issue date:	04/28/1999
From:	Loesch B, Reinhart L NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 9905050042
Download: ML20206E176 (9)

Text

iA n4 p Mfct hum: 1999 - 0243 Date  : 04/28/99 r

k FROM  : Bruce Loesch/ Linda Reinhart Loc  : Prairie Island TO  : NRC REGION III Copy Num:. 599, . Holder : NRC REGION III SUBJECT : Revisions to CONTROLLED DOCUMENTS oco***************************************************************************

Prccedure # Rev Title 1

1 RIvisions: l 1

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TECH SPECS 144 PRAIRIE ISLAND TECHNICAL SPECIFICATIONS UPDATING INSTRUCTIONS l

PlEce this material in your Prairie Island Controlled Manual or File. Remove revised or cancelled material and recycle it. Sign and date this letter in the space provided below within ten working days and return to Bruce Lossch or Linda Reinhart, Prairie Island Nuclear Plant, 1717 Wakonade Drive E.,

Walch, MN 55089. l Contact Bruce Loesch (ext 4664) or Linda Reinhart (ext 4659) if you have any  !

qutstions.

Raceived the material stated above and complied with the updating instructions Date l

• • Please update your Prairie Island Tech Specs per attached instructions.

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t 9905050042 DR 990428 ADOCK 05000202 PDR ;,,

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1 I 3' Technical Specification Revision 144 License Amendment Number-

. , , . Unit One: 144 / Unit Two: 135 i UPDATING INSTRUCTIONS

1. Replace page 3 of Unit 1 Facility Operating License with the attached page.

2. Replace page 3 of Unit 2 Facility Operating License with the attached page.

3. Insert pages in the Appendix A Technical Specifications as follows:

REMOVE INSERT TS-A TS-A TS-B TS-B TS-M TS-M TS.4.12-4 TS.4.12-4 TS.4.12-5 TS.4.12-5 E

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(4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components:

(5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 10 CFR Parts 30 and 70, to transfer byproduct materials from other NSP job sites for the purpose of volume reduction and decontamination.

C. This amended license shall be deemed to contain and is subject to;the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20. Section 30.34 of Part 30 Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part'70: is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in.effect: and is subject to the additional conditions specified or incorporated below:

/S . (1) -Maximum Power Level

-The licensee is authorized to operate the facility at steady state reector core power levels not in excess of ,

1650 megawatts thermal.

(2) Technical Snecifications I The Technical Specifications contained in Appendix A, as revised through Amendment No. 144, are hereby y incorporated in the license. The licensee shall operate e the facility in accordance with the Technical Specifications.

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, 1 (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any '

by-product, source or special nuclear material without restriction to chemical or physical form, for sample ,

analysis or instrument and equipment calibration or I associated with radioactive apparatus or components; I (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such by-product and special nuclear materials as may be produced by the operation of the facility; (6) Pursuant to the Act and 10 CFR Parts 30 and 70, to transfer byproduct materials from other NSP job sites for the purposes of volume reduction and decontamination.

'C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30 Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70: is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect: and is subject to the additional conditionc specified or incorporated below:

(1) Maximum Powe r Level 7-~

N-- The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 1650 megawatts thermal.

(2) Technical Soecifications The Technical Specifications con +ained in Appendix A, as revised through Amendment No. 135, are hereby U incorporated in the license. The licensee shall operate the facility in accordance with tho Technical jc q

Specifications.

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. TS-A REV 144 4/15/99 p PRAIRIE ISLAND GENERATING PLANT

MEyJU)lX_ A . TECHNICAL SPECIVICATIONS RECORD OF REVISIONS PAGE REV PAGE REV PAGE REV A- 144 3.1-7 91 3.8-2 119

-B 144 3.1-8 91 3.3-3 99 C 141 3.1-9 133 3.8-4 130 D 66 3.1-10 91 FIG 3.8-1 129 E 66 3.1-11 ?1 FIG 3.8-2 129 F 66 3.1-12 92 3.10-1 136 G 66 Fig 3.1-3 . 80 3.10-2 136 H 66 3.2-1 143 3.10-3 136 I 85 3.2-2 91 3.10-4 92 J 101 3.3-1 135 3.10-5 92 K- 117- 3.3-2 91 3.10-6 139 L 133A 3.3-3 135 3.10-6A 139 M 144 3.3-4 '

125 3.10-7 94 i 123 3.3-5 91 3.10-8 92 ii. 91 3.3-6 91 FIG 3.10-1 91 iii 122 3.3-7 131 3.11-1 136 )

iv 139 3.3-8 103 3.12-1 91 j~

v 122 3.4-1 123 3.13-1 91 vi~ 133 3.4-2 134 3.15-1 121 vii 122 3.4-3 91 Tab 3.15-1 (1 of 2) 121 4 viii 126 3.5-1 111 Tab 3.15-1 (2 of 2) 121 ]

ix 122 Tab 3.5-1 (1 of 2) 44 4.0-1. 101 j x 139 Tab 3.5-1 (2 of 2)103 4.1-1 111 1 I\ xi 129 Tab 3.5-2A (1 of 6) 75 Tab 4.1-1A (1 of 5) 111  !

' \~- xii 122 Tab 3.5-2A. (2 of 6)111 Tab 4.1-1A (2 of 5) 111 xiii 135 Tab 3.5-2A (3 of 6)111 Tab 4.1-1A (3 of 5) 111 1-1 111 Tab 3.5-2A (4 of 6)111 Tab 4.1-1A (4 of 5) 111 1-2 111 Tab 3.5-2A (5 of 6)111 Tab 4.1-1A (5 of 5) 111 1-3 122 ' Tab 3.5-2A (6 of 6)111 Tab 4.1-1B (1 of 7) 111 1-4. 135 Tab 3.5-2B (1 of 9)111 Tab 4.1-1B (2 of 7) 111 1-5 122 Tab 3.5-2B (2 of 9)111 Tab 4.1-1B (3 of 7) 111 1-6 122 Tab 3.5-2B (3 of 9)111 Tab 4.1-1B (4 of 7) 111 Tab.1-1 -111 Tab 3.5-2B (4 of 9)111 Tab 4.1-1B (5 of 7) 111 2.1-1 123 Tab 3.5-2B (5 of 9)134 Tab 4.1-1B (6 of 7) 111 FIG 2.1-1 123 Tab 3.5-2B (6 of 9)143 Tab 4.1-1B (7 of 7) 111 ,

2.3-1 91 Tab 3.5-2B (7 of 9)111 Tab 4.1-1C (1 of 4) 111

-2.3-2 123 Tab 3.5-2B (8 of 9)111 Tab 4.1-1C (2 of 4) 121 2.3-3 123 Tab 3.5-2B (9 of 9)143 Tab 4.1-1C (3 of 4) 121 2.3-4 111 3.6-1 107 Tab 4.1-1C (4 of 4) 135 3.0-1 91 3.6-2 91 Tab S.1-2A (1 of 2) 123 3.1 91 3.6-3 91 Tab 4.1-2A (2 of 2) 123 3.1-2 135 3.6-4 91 Tab 4.1-2B (1 of 2) 129 3.143 91 3.7-1 110 Tab 4.1-2B (2 of 2) 129 3.1-4 135 3.7-2 103 4.2-1 60 3.1-5 141 3.7-3 110 4.2-2 41 3.1-6 135 3.8-1 130 4.2-3 41 Tab 4.2-1 70

TS-B REV 144 4/15/99

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PRA'IRIE TSLAND NUCLEAR GENERATING PLANT APPENDIX A TECHNICAL SPECIFICATIONS RECORD OF REVISIONS PAGE REV. PAGE REV EAGE_ REV 4.3-1 116 5.6-3 129 B.2.1-4 123 4.4-1 126 FId 5.6-1 129 B.2.1-5 123 4.4-2 126' FIG 5.6-2 129 Fig B.2.1-1 123 4.4-3 126 FIG 5.6-3 129 B.2.2-1 123 4.4-4 126 FIG 5.6-4 129 B.2.3-1 91 FIG 4.4-1 1 FIG 5.6-5 129 B.2.3-2 111

.4.5-1 116 FIG 5.6-6 129- B.2.3-3 111 4.5-2 103 FIG 5.6-7 129 Title Page 3.0 91 4.5-3. 131 FIG 5.6-8 129 B.3.0-1 91 4.5-4 103 FIG 5.6-9 129 B.3.1-1 91 4.6-1 113 FIG 5.6-10 129 B.3.1-2 123 4.6-2 113 FIG 5.6-11 129 B.3.1-3 135 4.6-3 91 FIG 5.6-12 129 B.3.1-4 106 4.7-1. 91 6.1-1 105- B.3.1-5 135 4.8-1 116 6.1-2 120 B.3.1-6 135 4.8-2 91 6.1-3 120 B.3.1-7 133A 4.9-1 91 6.1-4 105 B.3.1-7a 133A 4.12-1 132 Tab 6.1-1 105 B.3.1-8 106 24.12-2 137 6.2-1 73 B.3.1-9 106 i 4.12-3 -133 6.2-2 10 B.3.1-10 106 l

-s 4.12-4 144 6.2-3 105 B.3.2-1 91 l 4.12-5 144 6.2-4 105 B.3.3-1 91 l

[\, -) 4.12-6 137 6.2-5 105 B.3.3-2 135 4.12 137 6.2-6 120 B.3.3-2a 135 Tab 4.12-1 137 6.2-7 96 B.3.3-3 125 Tab 4.12-2 132 6.3-1 25 B.3.3-4 142 4.13-1 98 6.5-1 80 B.3.4-1 123 4.13-2 98 6.5-2 122 B.3.4-2 123 4.13-3 98 6.5-3 122 E.3.5-1 143 Tab 4.13-1 (1 of 2) 98 6.5-4 122 B.3.5-2 111 Tab 4.13-1 (2 of 2) 98 6.5-5 122 B.3.5-3 111 4.14-1 91 6.5-6 122 B.3.5-4 143 4.15-1 91 6.5-7 122 B.3.5-5 143 4.18-1 141 6.5-8 126 B.3.5-6 143

! 4.19-1 99 6.6-1 8 B.3.6-1 107 l- -4.20-1 129 6.6-2 80 B.3.6-2 107 l 5.1-1 80 6.7-1 91 B.3.6-3 107 L 5.1-2 91 6.7-2 91 B.3.7-1 103 l 5.2' 1 0' 6.7-3 122 B.3.7-2 103 l 5.2 0 6.7-4 135 B.3.8-1 119 S.2-3 80 6.7-5 122 B.3.8-2 130 5.2-4' 80 6.7-6 122 B.3.8-3 129 5.3-1 108 Title Page 2.0 91 B.3.8-4 129 5.4-1 131 B.2.1-1 123 B.3.8-5 129A 5.6-1 129 B.2.1-2 123 B.3.10-1 111 5.6-2 108 B.2.1-3 123 B.3.10-2 111 B.3.10-3 92 B.3.10-4 92 J

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. TS-M J REV 144 4/15/99 r3 PRAIRIE ISLAND NUCLEAR GENERATING PLANT (v) RECORD OF TECHNICAL SPECIFICATION CHANGES AND LICENSE AMENDMENTS NSF Revision Date of License Amendment No.

(REV) No. Issue DPR-42 DPR-60 Remarks 135 5/4/98 135 127 Update to Heatup/Cooldown Limitations and Incorporation of Pressure and Temperature Limits Report 136 7/28/98 136 -

Reduction in the Required Number of

• • Incore Detectors for Remainder of Operating Cycle 19 137 8/13/98 137 128 EF* Steam Generator Alternate Repair Criteria 133A 8/26/98 Bases Change Allowable Leakage Past Reactor Vessel Head Penetration Seal Welds 138 9/22/98 138 129 . Authorization of Modification to AMSAC System to Install a Diverse Scram System rh (m, 139 10/30/98 139 130 Inoperable Rod Position Indicator Channels 140 11/4/98 140 131 Cooling Water System Emergency Intake Basis 12/7/98 141 132 Conformance of Administrative Controls Section 6 to Guidance of Standard Technical Specifications (Not Distributed. To be Implemented By 9/1/99) 141 12/17/98 142 133 Reactor Coolant Head Vent Surveillance Requirements 142 11/21/98 Bases Change Cooling water suoply to safeguards I bay l

143 3/17/99 143 134 Boric Acid Storage Tank Level Instrumentation

/T 144 4/15/99 144 135 Incorporation of Combustion

( _) Engineering Topical . Report CEN-629-P, " Repair of Westinghouse Series 44 and 51 Steam Generator l Tubes Using Leak Tight Sleeves,"

l Revision 3.

, TS.4.12-4 REV 144 4/15/99 f-sg D. Accentance Criteria 1.'Ais used in this Specification:

(a) Innerfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be

' considered as imperfections.

m (b) Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.

(c) -Degraded Tuhm means a tube containing imperfections 220% of the nominal wall thickness caused by degradation.

(d)' % Degradatign means the percentage of the tube wall thickness affected or removed by degradation.

(e) Dafact means an imperfection of such severity that it exceeds the repair limit. A tube containing a defect is defective.

(f) Reoair Limit means the imperfection depth at or beyond which

( the tube shall be removed from service by plugging or repaired by sleeving because it may become unserviceable prior to the l next inspection and is equal.to 50% of the' nominal tube wall l thickness. If significant general tube thinning occurs, this g criteria vill be reduced to 40% wall penetration. This I

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(, definition does not apply to the portion of the tube'in the tubesheet below the F* or EF* distance provided the tube is not

i. degraded (i.e., no indications of cracks) within the'F* or EF*

l distance for F* or EF* tubes. The repair limit for the pressure boundary region of any sleeve is 25% of the nominal l sleeve wall thickness. This definition does not apply to tube support plate intersections for which the voltage-based repair j criteria are being applied. Refer to Specification 4.12.D.4 for the repair limit applicable to these intersections.

(g) Unserviceable describes the condition of a tube if it leaks or' contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break.

(h) Tube Insonetion means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.

(i) Sleevino is the repair of degraded tube regions.using a new Alloy 690 tubing sleeve inserted inside the parent tube and sealen at each end by welding or by replacing the lower weld in a full depth tubesheet sleeve with a hard rolled joint. The new sleeve becomes the pressure boundary spanning the original s degraded tube region.

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.*'* TS.4.12-5 REV 144 4/15/99

, ~x (j) F* Distance is the distance from the bottom of the hardroll i

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transition toward the bottom of the tubesheet that has been conservatively determined to be 1.07 inches (not including eddy current uncertainty). The F* distance applies to roll expanded regions below the midplane of the tubesheet (k) F* Tube is a tube with degradation, below the F* distance, equal to or greater than 40%, and not degraded (i.e., no indications of cracking) within the F* distance.

(1) EF* Distance is the distance from the bottom of the upper hardroll transition toward the bottom of the tubesheet that has been conservatively determined to be 1.62 inches (not including eddy current uncertainty). EF* distance applies to roll expanded regions when the top of the additional roll expansion is 2.0 inches or greater down from the top of the tubesheet 1

(m) EF* Tube is a tube with degradation, below the EF* distance. J equal to or greater than 40%, and not degraded (i.e., no indications of cracking) within the EF* distance.

2. The steam generator shall be determined OPERABLE after completing the 4 corresponding actions (plug or repair by sleeving all tubes exceeding j the repair limit and all tubes containing through-wall cracks or  !

classify as F* or EF* tubes) required by Tables TS.4.12-1 and l TS.4.12-2.

3. Tube repair, after April 1, 1999, using Combustion Engineering l

(N welded sleeves shall be in accordance with the methods described in

(/ the following:

CEN-629-P, Revision 03-P " Repair of Westinghouse Series 44 and 51 l l Steam Generator Tubes Using Leak Tight Sleeves": 1

4. Tube Suecort Plate Reoair Limit is used for the disposition of a l steam generator tube for continued service that is experiencing predominantly axially oriented outside diameter stress corrosion cracking confined within the thickness of the tube support plates. l At tube support plate intersections, the repair limit is based on maintaining steam generator serviceability as described below: )

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a. Steam generator tubes, whose degradation is attributed to outside l diameter stress corrosion cracking within the bounds of the tube I support plate with bobbin voltages less than or equal to 2.0 volts will be allowed to remain in service,

b. Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube support plate with a bobbin voltage greater than 2.0 volts, will be repaired or plugged, except as noted in Specification 4.12.D.4.c below.

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