ML20203A218
| ML20203A218 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/05/1999 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20136E819 | List: |
| References | |
| NUDOCS 9902090312 | |
| Download: ML20203A218 (12) | |
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Exhibit B Prairie Island Nuclear Generating Plant License Amendment Request Dated February 5,1999 Proposed Changes Marked Up On Existing Technical Specification Pages Exhibit B consists of existing Technical Specification pages with the proposed changes highlighted on those pages. The pages affected by this License Amendment Request are listed below:
TS.4.12-4 TS.4.12-5 9902090312 990205 gDR ADOCK0500g282
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TS.4.12-4 REV D. Accentance Criteria
- 1. As used in this Specification:
(a) Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or i 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) Degraded Tube means a tube containing imperfections h20% of the nominal wall thickness caused by degradation.
(d) % Deiradation means the percentage of the tube wall thickness 1 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. l l
(f) Repair Limit means the imperfection depth at or beyond which l the tube shall be removed from service by plugging or repaired
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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 i 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 4 pressure boundary region of any sleeve is 34]E% of the nominal 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. l (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 Inspection means an inspection of the steam generator tube j from the point of entry (hot leg side) completely around the l U-bend to the top support of the cold leg.
i (i) Sleevinn is the repair of degraded tube regions using a new 1 Alloy 690 tubing sleeve inserted inside the parent tube and l sealed 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 degraded tube region.
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TS.4.12-5 REV (j) F* Distance 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 applies to roll expanded regions below the midplane of the tubesheet 4
(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 1 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 j (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 l indications of cracking) within the EF* distance. I
- 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. I
- 3. Tube repair, after Get+ber 1. 1007[f15HMMMM, using Combustion Engineering welded sleeves shall be in accordance with the methods described in the following:
CEN-629-P, Revision EUREE, " Repair of Westinghouse Series 44 and 51 Steam Generator Tubes Using Leak Tight Sleeves":
CE1F520-P, f.ddendum 1. Revision 1, "Repcir of Ucstinghouac Scrica 45 ;
and 51 Steam Cencrator Tubc Using Leak Tight Sleevca" !
- 4. Tube Suoport Plate Repair 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.
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 i 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. l I
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i Exhibit C Prairie Island Nuclear Generating Plant License Amendment Request Dated February 5,1999
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i Revised Technical Specification Pages l
Exhibit C consists of revised pages for the Prairie Island Nuclear Generating Plant Technical Specifications with the proposed changes incorporated. The revised pages are listed below:
TS.4.12-4 TS.4.12-5 1
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m TS.4.12-4 REV 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) Dagradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
(c) Degraded Tube meano a tube containing imperfections 220% of the nominal wall thickness caused by degradation.
(d). % Degradation 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.
l (f) Reomir Limit.means the imperfection depth at or beyond which the tube shall be temoved from service by plugging or repaired i by aleeving 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 cracku) 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 i support plate intersections for which the voltage-based repair i criteria are being applied. Refer to Specification 4.12.D.4 i 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 Inspection 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) Sleevinn 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.
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TS.4.12-5 REV tj) F* Distance is the distance from the bottom of the hardrol.1 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 j 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 t 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, 1998, using Combustion Engineering l velded sleeves shall be in accordance with the methods described in the following:
CEN-609-P, Revision 03-P " Repair of Westinghouse Series 44 and 51 l Steam Generator Tubes Using Leak Tight Sleeves";
- 4. Tube Support Plate Reoair Limit is used for the disposition of a I 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. 1 At tube support plate intersections, the repair limit is based on l 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 l will be allowed to remain in service. l l
- b. Steam generator tubes, whose degradation is attributed to outside ;
diameter stress corrosion cracking within the bounds of the tube i 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.
Exhibit D Prairie Island Nuclear Generating Plant License Amendment Request Dated February 5,1999 Affidavit: Combustion Engineering Affidavit Pursuant to 10 CFR 2.790
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l AFFIDAVIT PURSUANT TO 10 CFR 2.790 l
1, l.C. Rickard, depose and say that I am the Director, Nuclear Licensing, of Combustion Engineering, Inc., duly authorized to make this affidavit, and have reviewed or caused to have reviewed the information which is identified as proprietaiy and referenced in the paragraph immediately below. I am submitting this affidavit in conjunction with the
- application of Northem States Power Company and in conformance with the provisions of 10 CFR 2.790 of the Commission's regulations. )
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- The information for which proprietary treatment is sought is contained in the following f document
CEN-629-P, Rev. 03-P, " Repair of Westinghouse Series 44 and 51 Steam Generator Tubes Using Leaktight Sleeves," September,1998.
This document has been appropriately designated as proprietary.
I have personal knowledge of the criteria and procedures utilized by Combustion Engineering in designating information as a trade secret, privileged or as confidential commercial or financial information. l Pursuant to the provisions of paragraph (b) (4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining l whether the information sought to be withheld from public disclosure, included in the above referenced document, should be withheld.
- 1. The infonnation sought to be withheld from public disclosure, is owned and has been held in confidence by Combustion Engineering. It consists of information concerning the steam generator tube repair process of sleeving, including qualification program results and analyses.
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- 2. The information consists of test data or other similar data concerning a process, method or component, the application of which results in substantial competitive advantage to Combustion Engineering.
- 3. The information is of a type customarily held in confidence by Combustion Engineering and not customarily disclosed to the public. Combustion Engineering has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The details of the aforementioned system were provided to the Nuclear Regulatory Commission via letter DP-537 from F. M. Stern to Frank Schroeder dated December 2,1974. This system was applied in determining that the subject document herein is proprietary.
- 4. The information is being transmitted to the Commission in confidence under the provisions of 10 CFR 2.790 with the understanding that it is to be received in confidence by the Commission.
- 5. The information, to the best of my knowledge and belief, is not available in public sources, and any disclosure to third parties has been made pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence.
- 6. Public disclosure of the information is likely to cause substantial harm to the competitive position of Combustion Engineering because:
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- a. A similar product is manufactured and sold by major pressurized water reactor competitors of Combustion Engineering.
- b. Development of this information by Combustion Engineering required millions of dollars and thousands of manhours of i effort. A competitor would have to undergo similar expense in generating equivalent information.
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- c. In order to acquire such infoimation, a competitor would also require considerable time and inconvenience to develop an understanding of welded steam generator tube sleeve installation problems and evaluate specific examples based on test or pulled steam generator tube data and develop and qualify a steam generator tube sleeving program.
- d. The information consists of a description of the steam generator tube repair process of sleeving, including qualification program results and analyses, the application of which provides a competitive economic advantage. The availability of such information to competitors would enable them to modify their product to better compete with Combustion Engineering, take marketing or other actions to improve their product's position or impair the position of Combustion Engineering's product, and avoid developing similar data and analyses in support of their processes, methods or apparatus.
- e. In pricing Combustion Engineering's products and services, significant research, development, engineering, analytical, l
manufacturing, licensing, quality assurance and other costs and expenses must be included. The ability of Combustion Engineering's competitors to utilize such information without i
similar expenditure of resources may enable them to sell at prices reflecting significantly lower costs. j
- f. Use of the information by competitors in the international l marketplace would increase their ability to market nuclear steam supply systems by reducing the costs associated with their technology development. In addition, disclosure would have an adverse economic impact on Combustion
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j j Engineering's potential for obtaining or maintaining foreign I l
l licensees. l l I I
Further the deponent sayeth not. -
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i 1.b rector I Nuclear Licensing i I
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i Sworn to before me i this M
- day of 6t> .1998 j '. l j -) A l
No ry Publi 4
My commission expires: F 3/ 79 i
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M LEGAL NOTICE I l
THIS REPORT WAS PREPARED AS AN ACCOUNT OF WORK SPONSORED BY ABB !
COMBUSTION ENGINEERING. NEITHER ABB COMBUSTION ENGINEERING NOR i ANY PERSON ACTING ON ITS BEHALF: i A. MAKES ANY WARRANTY OR REPRESENTATION, EXPRESS OR IMPLIED I INCLUDING THE WARRANTIES . OF FITNESS FOR A PARTICULAR ;
PURPOSE OR MERCHANTABILITY, WITH RESPECT TO THE ACCURACY, !
COMPLETENESS, OR USEFULNESS OF THE INFORMATION CONTAINED l l
IN THIS REPORT, OR THAT THE USE OF ANY INFORMATION, l APPARATUS, METHOD, OR PROCESS DISCLOSED IN THIS REPORT MAY 1 NOT INFRINGE PRIVATELY OWNED RIGHTS; OR
! B. ASSUMES ANY LIABILITIES WITH RESPECT TO THE USE OR FOR l DAMAGES RESULTING FROM THE USE OF, ANY INFORMATION, l APPARATUS, METHOD OR PROCESS DISCLOSED IN THIS REPORT. i i
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