ML20083M753
| ML20083M753 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/15/1995 |
| From: | Wetzel B NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20083M755 | List: |
| References | |
| NUDOCS 9505220041 | |
| Download: ML20083M753 (2) | |
Text
.
e %q s
ge UNITED S'!ATES 2
E NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 3086H001 NORTHERN STMES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 118 License No. DPR-42 3.- The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated January 9,1995, as supplemented February 7, March 15, March 22, April 3, and April 20, 1995, 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-42 is hereby amended to read as follows:
9505220041 950515 PDR ADOCK 05000282 P
(E j
~'
0;
-* l 3
i Technical Specifications i
The Technical Specifications contained in Appendix A, as revised through Amendment No.118 ~,: are hereby incorporated in the license.
l The licensee shall operate the facility in accordance with the Technical Specifications.
j 3.
This license amendment is effective as of the date of issuance, with full implementation within 30 days.
l FOR THE NUCLEAR REGULATORY COMMISSION-
~
l b.
u Beth A. Wetzel, Project Manager
~
Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 15, 1995
- s A;
uf ATTACHMENT TO LICENSE AMENDMENT NO. 118 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 4.12-2 TS 4.12-2 TS 4.12-4 TS 4.12-4 TS 4.12-5 TS 4.12-5 B 4.12-2 B 4.12-2 B 4.12-3 I
F
TS.4.12-2 2.
The first sample of tubes selected for each in-service inspec-tion (subsequent to the preservice inspection) of each steam generator shall include:
(a) All tubes that previously had detectable wall penetrations
(>20%) that have not been plugged or sleeve repaired in the affected area.
(b) Tubes in those areas where experience has indicated potential problems.
(c) A tube inspection (pursuant to Specification 4.12.D.1.(h))
shall be performed on each selected tube.
If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.
3.
In addition to the sample required in Specification 4.12.B.2.a through c, all tubes which have had the F* criteria applied will be inspected in the F* regions of the roll expanded region. The roll expanded region of these tubes may be excluded from the requirements of 4.12.B.2.a.
4.
The tubes selected as the second and third samples (if required by Table TS.4.12-1) during each inservice inspection may be subjected to a partial tube inspection provided:
(a) The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.
(b) The inspections include those portions of the tubes where imperfections were previously found.
The results of each sample inspection shall be classified into one of the following three categories:
Category Inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C-2 One or more tubes, but not more than 16 of the total tubes inspected are defective, or between St and 10%
of the total tubes inspected are degraded tubes.
C-3 More than 10% of the total tubes inspected are degraded tubes or more that it of the inspected tubes are defective.
Note:
In all inspections, previously degraded tubes must exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations.
Prairie Island Unit 1 Amendment No. 31, 76, 118 Prairie Island Unit 2 Amendment No. 26, 69, 111
- p;,.
q, TS.4.12 i
[
D.- Acceptance' Criteria-
=
.As used in this Specification:
- 1. -
(a).lmverfection means an exception to the dimensions, finish or contour of a tube' from. that required by fabrication drawings or specifications.
Eddy-current testing indica-tions.below 20% of the nominal tube wall thickness, if detectable, may be' considered as imperfections.
(b) Derradation means a service-induced ' cracking, wastage, wear or igeneral corrosion occurring on either inside or outside of-a tube.
(c) Derraded Tube means a tube containing imperfections h20t' of the nominal wall thickness caused by degradation.
(d) % Derradation means the percentage of the tube wall thickness affected or removed by degradation.
i (e) Defect means an imperfection of such severity that it exceeds the repair limit. A tube containing a defect is defective.
(f) Repair 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 next inspection and'is equal to 50tiof 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* distance provided the.
tube is not degraded (i.e., no. indications of cracks) within the F* distance for F* tubes.
(g) Unserviceabla 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 Insoection 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 (i) Sleevine means that tube sleeving is permitted only in areas where the sleeve spans the tubesheet area and whose lower joint is at the primary fluid tubesheet face.
(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).
l (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.
Prairie Island Unit 1 Amendment No. 31. 76,118 Prairie Island Unit 2 Amendment No. gE, gg,111
4 TS.4.12-5
~
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* tubes) required by Table TS.4.12-1.
E.
Reports 1.
Following each in-service inspection of steam generator tubes, if there are any tubes requiring plugging or sleeving, the number of tubes plugged or sleeved in each steam generator shall be reported to the Commission within 15 days.
2.
The results of steam generator tube inservice inspections shall be included with the summary reports of ASME Code Section XI inspections submitted within 90 days of the end of each refueling outage. Results of steam gen?.rator tube inservice inspections not associated with a refueling outage shall be submitted within 90 days of the completion of the inspection. These reports shall include: (1) number and extent of tubes inspected, (2) location and percent of wall-thickness penetration for each indication of an imperfection and (3) identification of tubes plugged or sleeved.
3.
Results of steam generator tube inspections which fall into Category C-3 require notification to the Commission prior to resumption of plant operation, and reporting as a special report to the Commission within 30 days. This special report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
4.
The results of inspections performed under Specification 4.12.B for all tubes that have defects below the F* distance, and were not plugged, shall be reported to the Commission within 15 days following the inspection. The report shall include:
1.
Identification of F* tubes, and 2.
Location and extent of degradation, i
Prairie Island Unit 1 Amendment No. 31. 71, 73, 76,11 8 !
Prairie Island Unit 2 Amendment No. 25, 66, 69,111 !
l
.+
,1 q
B.4.12-2 1
l 4.12 STEAM GENERATOR TUBE SURVEILIANCE Bases continued plants have demonstrated the capability to reliably ' detect wastage type defects that have penetrated 20% of the original 0.050-inch wall thickness _(Reference 2).
Plugging or sleeving is not required for tubes meeting the.F* criteria.
The F* distance will be controlled by a combination of addy current inspection and/or process control.
For a new additional roll expansion, the requirement will be at least 1.2 inches of new hard roll. This is controlled by the length of the rollers (1.25. inch effective length).
The distance from.the original roll transition zone is also controlled by.
the process in that the lower end of the new roll expansion is located one inch above the original roll expansion.
In the case of the new roll, eddy current examination will confirm there are no indications in the new roll region and that there is a new roll region with well defined upper and lower expansion transitions.
When eddy current examination, alone, uust determine the F* distance,-
such as in the existing hard roll region, or when multiple lengths of additional hard rolls have been added, the eddy current uncertainty.is qualified by testing against known standards. That value is expected to be 0.18 inches. Therefore, the F* distance measured by eddy current (sum of 1.07 and 0.18) will be conservatively set at 1.3 inches.
~'
When more than one Alternate Repair Criteria are used, the summation of leakage from all tubes left in service by all repair criteria must:be less than the allowable leakage for the most limiting of those Alternate Repair Criteria.
Whenever the results of any steam generator tubing in-service inspection fall into Category C-3, these results will'be promptly reported to the-Commission prior to resumption of plant operation. Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy current inspection, and revision of the Technical Specifications, if necessary.
Degraded steam generator tubes may be repaired by the installation of' sleeves which span the section of degraded steam generator tubing. A steam generator tube with a sleeve installed meets the structural requirements of tubes which are not degraded.
The following sleeve designs have been found acceptable by the NRC Staff:
a.
Westinghouse Mechanical Sleeves (WCAP 10757) b.
Westinghouse Brazed Sleeves (WCAP-10820) c.
Combustion Engineering Leak Tight Sleeves (CEN-294-P)
Prairie Island Unit 1 Amendment No. 97,118 Prairie Island Unit 2 Amendment No. 54,111
e B.4.12-3 4.12 STEAM GENERATOR TUBE SURVEIlllNCE
. Bases continued Descriptions of other future sleeve designs shall be submitted to the NRC for review and approval prior to their use in the repair of degraded steam generator tubes. The submittals related to other sleeve designs shall be made at least 90 days prior to use.
References 1.
Testimony of J Knight in the Prairie Island Public Hearing on 1/28/75 2.
Testimony of L Frank in the Prairie Island Public Hearing on 1/28/75 Prairie Island Unit 1 Amendment No. PJ,118 Prairie Island Unit 2 Amendment No. SJ,j11
p* #f ou lt UNITED STATES y-j NUCLEAR REGULATORY COMMISSION
'* ~
g WASHINGTON, D.C. 20046-0001
"%...../
NORTHERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 2 SMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 111 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 January 9, 1995, as supplemented February 7, March 15, March 22, April 3, and April 20, 1995 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 2.0.(2) of Facility Operating License No. DPR-60 is hereby amended to read as follows:
i Jechnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.111, 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 b
Beth A. Wetzel, Project Manager Project Directorate 111-1 Division of Reactor-Projects - III/IV i
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 15, 1995 l
- ,.; ;i if-v ATTACHMENT TO LICENSE AMENDMENT NO. 111 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 cur,tain vertical lir.es indicating the area of change.
REMOVE INSERT TS 4.12-2 TS 4.12-2 TS 4.12-4 TS 4.12-4 TS 4.12-5 TS 4.12-5 B 4.12-2 B 4.12-2 B 4.12-3
..f TS.4.12-2 a"
2.
The first sample of tubes selected for each in-service inspec-tion (subsequent to the preservice inspection) of each steam.
generator shall include:
(a) All tubes that previously had detectable wall penetrations
(>204) that have not been plugged or sleeve repaired in the affected area.
(b) Tubes in those areas where experience has indicated potential problems.
l (c) A tube inspection (pursuant to Specification 4.12.D.l.(h))
shall be performed on each selected tube.
If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.
3.
In addition to the sample required in Specification 4.12.B.2.a through c, all tubes which have had the F* criteria applied will be inspected in the F* regions of the roll expanded region. The roll expanded region of these tubes may be excluded from the requirements of 4.12.B.2.a.
4.
The tubes selected as the second and third samples (if required-by Table TS.4.12-1) during each inservice inspection may be subjected to a partial tube inspection provided:
(a) The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.
(b) The inspections include those portions of the tubes where imperfsetions were previously found, i
The results of each sample inspection shall be classified into one
{
of the following three categories:
'l Category Inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between St and 106 of the total tubes inspected are degraded tubes.
1 C-3 More than 10% of the total tubes inspected are j
degraded tubes or more that 14 of the inspected tubes are defective.
i Note:
In all inspections, previously degraded tubes must exhibit significant (>104) further wall penetrations to be included in the above percentage calculations.
Prairie Island Unit 1 Amendment No. 31, 76, 118 j
Prairie Island Unit 2 Amendment No. 25 O,111 1
d r-i
=l
,e TS -. 4.12.i i
'D.
Accentance' Criteria' j
i 1.
As used in this Specification:
(a) lEperfection means_an exception to the'dimensionsi finish or contour. of a tube from that required by fabrication -
drawings or specifications.
Eddy-current testing indica-t tions below 20% of the nominal tube wall thickness, if detectable, may be' considered as imperfections.
t
'(b)- Derradation means a service-induced cracking, wastage, sear or general corrosion occurring on either:inside.or'outside of a' tube.
(c) Derraded Tube means a tube containing imperfections k204 of the nominal wall thickness caused by degradation.
l l
(d) t Derradation means the percentage of the tube wall l
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.
1 (f) Reoair Limit means the imperfection depth at or beyond which the tube shall be removed from service by plugging.
j 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 y
penetration. This definition does not apply to the portion of the tube in the tubesheet below the F* distance provided the j
tube is not degraded-(i.e., no indications of cracks) within the F* distance for F*-tubes.
(g) Unserviceable describes the condition of a' tube if it leaks l
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.
v f
(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) Sleevine means that tube sleeving is permitted only in areas where the sleeve spans the tubesheet area and whose lower Joint is at the primary' fluid tubesheet face.
i (j )
F* Distance is the distance from the bottom of the hardro11~
[
transition toward the bottom of the tubesheet that has been conservatively determined to be 1.07 inches (not includin5. eddy current uncertainty).
(k)
F* Tube is a tube with degradation, below the F* distance, equal-to or greater than 404, and not degraded (i.e., no indications of cracking) within the F* distance.
Prairie Island Unit 1 Amendment No. 31, 76,118 Prairie' Island Unit 2 Amendment No. g), pp,lil-
~
7 X.
TS.4.12-5 1
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* tubes) required by Table TS.4.12-1.
E.
Reports 1.
Following each in-service inspection of steam generator tubes, if there are any tubes requiring plugging or sleeving, the number of tubes plugged or sleeved in each steam generator shall be reported to the Commission within 15 days.
2.
The results of steam generator tube inservice inspections shall be included with the summary reports of ASME Code Section XI inspections submitted within 90 days of the end of each refueling outage. Results of steam generator tube inservice inspections not associated with a refueling outage shall be submitted within 90 days. of the completion of the inspection. These reports shall include: (1) number and extent of tubes inspected, (2) location and percent of wall-thickness penetration for each indication of an imperfection and (3) identification of tubes plugged or sleeved.
'3.
Results of steam generator tube inspections which fall into Category C-3 require notification to the Commission prior to resumption of plant operation, and reporting as a special report to the Commission within 30 days. This special report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
4.
The results of inspections performed under Specification 4.12.B for all tubes that have defects below the F* distance, and were not plugged, shall be reported to the Commission within 15 days following the inspection.
The report shall include:
1.
Identification of F* tubes, and 2.
Location and extent of degradation.
Prairie Island Unit 1 Amendment No. 37, 77, 73, 76.118 Prairie Island Unit 2 Amendment No. 25, 66, 69.111
w a
O 4
B.4.12-2' l
2i 4.12 STEAM CENERATOR TUBE SURVEILIANCE j
Bases continued plants have demonstrated the capability to reliably detect wastage type defects that have penetrated 20% of the original 0.050 inch wall i
thickness (Reference 2).
Plugging or sleeving is not required for tubes meeting the F* criteria.
The F* distance will be controlled by a combination of eddy current inspection and/or' process control. For a new additional. roll expansion, the. requirement will be at least 1.2 inches ' of new hard roll. This is controlled by the length of the rollers (1.25 inch effective length).
The distance from the original roll transition zone is also controlled by the process in that the lower end of the new roll expansion is located l
one inch above the original roll expansion. In the case of the new roll, l
eddy current examination will confirm there are no indications in the new roll region and that there is a new roll region with well defined upper and lower expansion transitions.
When eddy current examination, alone, must determine the F* distance, such as in the existing hard roll region, or when multiple lengths of additional hard rolls have been'added, the eddy current uncertainty is qualified by testing against known standards.
That value is expected to l
be 0.18 inches. Therefore, the F* distance measured by addy current (sum -
of 1.07 and 0.18) will be conservatively set at 1.3 inches.
When more than one Alternate Repair Criteria are used, the summation of leakage from all tubes left in service by all repair criteria must be less than the allowable leakage for'the most limiting of those Alternate Repair Criteria.
I Whenever the results of any steam generator tubing in service inspection fall into Category C-3, these-results will be promptly reported to the Commission prior-to resumption of plant operation. Such cases will be considered by the Commission on a~ case-by-case basis and may result' in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
Degraded steam generator tubes may be repaired by the installation of sleeves which span the section'of degraded steam generator tubing. A steam generator tube with a sleeve installed meets the structural requirements of tubes which are not degraded.
The following sleeve designs have been found acceptable by the NRC Staff:
a.
Westinghouse Mechanical Sleeves (WCAP 10757) b.
Westinghouse Brazed Sleeves (WCAP-10820) c.
Combustion Engineering Leak Tight Sleeves (CEN-294-P) i Prairie Island Unit 1 Amendment No. 91,118 Prairie Island Unit 2 Amendment No. $f,111
y i B.4.12-3 4.12 STEAM CENERATOR 1UBE SURVEILIANCE i
Bases continued Descriptions of other future sleeve designs shall'be submitted to the NRC for review and approval prior to their use in the repair of degraded steam generator tubes. The submittals related to other sleeve designs shall be made at least 90 days prior to use.
i 1
t Re ference s 1.
Testimony of J Knight in the Prairie Island Public Hearing on 1/28/75 2.
Testimony of L Frank in the Prairie Island Public Hearing on 1/28/75 Prairie Island Unit 1 Amendment No. PJ,118 Prairie Island Unit 2 Amendment No. SJ,111
.