ML20206A234
| ML20206A234 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/15/1999 |
| From: | Dick G NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206A238 | List: |
| References | |
| NUDOCS 9904280107 | |
| Download: ML20206A234 (10) | |
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1 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. assgHest NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 144 License No. DPR-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northem States Power Company (the licensee) dated February 5,1999, as supplemented March 1,1999, 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 cf 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-42 is hereby amended to read as follows:
DR P
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
144
, 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 w
Geo
. Dick, Jr.,
eting Chief, Section 1 Project Directorate lli Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: April 15,1999 G
1 j
ATTACHMENT TO LICENSE AMENDMENT NO. 144 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 verticallines indicating the area of change.
REMOVE INSERT TS.4.12-4 TS.4.12-4 TS.4.12.5 TS.4.12.5
TS.4.12-4 D.
Accentance Criterie
- 1. As used in this Specification:
(a)
Tmeerfection 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.
(b)
Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
(c)
Ragraded Tube means a tube containing imperfections 220% of the nominal wall thickness caused by degradation.
(d)
% Deeredation means the percentage of the tube wall thickness affected or removed by degradation.
(e)
Defect means an imperfection of such severity that it exceeds the repair limit. A tube containing a defect is defective.
(f)
Renair TA=4t 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 next inspection and is equal to 50% of the nominal tube wall thickness.
If significant general tube thinning occurs, this criteria vill be reduced to 40% wall penetration. This definition does not apply to the portion of the tube in the tubesheet below the F* or EF* distance provided the tube is not degraded (i.e., no indications of cracks) within the F* or EF*
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 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 it 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 Inaneetion 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) slaavine is the repair of degraded tube regions using a new Alloy 690 tubing sleeve inserted inside the parent tube and sealed at each and 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 degraded tube region.
i Amendment No. 144
lb
.?
TS.4.12-5 (j)
F* Distance is the distance tros the bottom of the hardroll 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 j
eddy current uncertainty).
EF* distance applies to roll I
expanded regions when the top of the additional roll expansion I
is 2.0 inches or greater down from the top of the tubesheet l
(m)
EF* Tube is a tube with degradation, below the EF* distance, equal to or greater than 40%, and not degraded (i.e., no indications of cracking) within the EF* distance.
1
- 2. The. steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair by sleeving all tubes exceeding
)
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 I
TS.4.12-2.
- 3. Tube repair, after April 1, 1999, using Combustion Engineering l
welded sleeves shall be in accordance with the methods described in
)
the following:
CEN-629-P. Revision 03-P. "Repeir of Westinghouse Series 44 and 51 l
Steam Generator Tubes Using Leak Tight Sleeves":
- 4. Tube Suneort Plate Renair L4mit is used for the disposition of a 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.
At tube support plate intersections, the repair limit is based on maintaining steam generator serviceability as described below:
- a. Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube 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 j
below.
1 Amendment No. 144 n
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k UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASNNGToN, D.C. 30006 0001 I
NORTHERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE
)
i Amendment No 135 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 licensee) dated February 5,1999, as supplemented March 1,1999, 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; l
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 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. OPR-60 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 135
, 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 2
Geo F. Dick, Jr., Acting Chief, Section 1 Project Directorate ill Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 15, 1999
ATTACHMENT TO LICENSE AMENDMENT NO.135 FACILITY OPERATING LICENSE NO. DPR-60 DOCKET NO. 50-306 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.4.12-4 TS.4.12-4 TS.4.12.5 TS.4.12.5
=,
TS.4.12-4 D.
Accentance criteria
- 1. As used in this Specification:
(a)
Imoerfection 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.
(b)
Degradation means a service-induced cracking, vastage, wear or general corrosion occurring on either inside or outside of a tube.
(c)
Darraded Tube means a tube containing imperfections 220% of the nominal vall thickness caused by degradation.
(d)
% Darradation means the percentage of the tube wall thickness affected or removed by degradation.
(e)
Defect means an imperfection of such severity that it exceeds the repair limit. A tube containing a defect is defective.
(f)
Ranmar L4=4t 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 next inspection and is equal to 50% of the nominal tube wall thickness. If significant general tube thinning occurs, this criteria will be reduced to 40% wall penetration. This definition does not apply to the portion of the tube in the tubesheet below the F* or EF* distance provided the tube is not degraded (i.e., no indications of cracks) within the F* or EF*
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 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 feedvater line break.
(h)
Tuba Insnaetion means an inspection of the steam generator tube from the point of entry (hot les side) completely around the U-bend to the top support of the cold leg.
(i) sleeving is the repair of degraded tube regions using a new Alloy 690 tubing sleeve inserted inside the parent tube and sealed at each end by welding or by replacing the lower veld in a full depth tubesheet sleeve with a hard rolled joint. The new sleeve becomes the pressure boundary spanning the original degraded tube region.
Amendment No.135
~
TS.4.12-5 (j)
F* Distanea is the distance from the bottom of the hardroll 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 ap,nlies 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 :o 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 (m)
EF* Tube is a tube with degradation, below the EF' distance, 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 corresponding actions (plug or repair by sleeving all tubes exceeding 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 TS.4.12-2.
- 3. Tube repair, after April 1. 1999. using Combustion Engineering l
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
Steam Generator Tubes Using Leak Tight Sleeves"
- 4. Inha suenort Plate Reemir L4m4t is used for the disposition of a steam generator tube for continued service that is experiencing predominantly axially oriented outside diameter stress corr'osion cracking confined within the thickness of the tube support plates.
At tube support piste intersections, the repair limit is based on maintaining steam generator serviceability as described below:
- a. Steam generator tubes, whose degradation is attributed to outside diameter stress corrosion cracking within the bounds of the tube 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.
Amendment No. 135 0