ML20205E783
| ML20205E783 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 10/11/1985 |
| From: | Butcher E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205E787 | List: |
| References | |
| TAC-57847, TAC-57848, NUDOCS 8510170466 | |
| Download: ML20205E783 (12) | |
Text
[
0, UNITED STATES g
NUCLEAR REGULATORY COMMISSION C
"[
WASHINGTON, D. C. 20555
\\...../
N6RTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 License No. DPR-42 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated May 17, 1985, supplemented June 3 and August 2,1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act)..and the Comission'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 Comission; C.
There is reasonable assurance (1) 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
8510170466 851011 PDR ADOCK 05000282 P
m '
2.
Accordingly, the license is amended by changes to the Technical Specifications as ir.dicated in the attachment to this license 1
amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-42 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 76, are hereby incorporated in the license. The licensee shall operate the facility in accordence with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMISSION Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 11, 1985
~
8 UNITED STATES
[
p, NUCLEAR REGULATORY COMMISSION I
L
- j WASHINGTON, D. C. 20555
\\...+/
+
NORTHERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.69 License No. DPR-60 i
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated May 17, 1985, supplemented June 3 and August 2,1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.
There is reasonable assurance (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
1 n
o s
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:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 69, 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 its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Edward J. Butcher, Acting Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 11, 1985 i
I b
ATTACHMENT TO LICENSE AMENDMENTS NOS. 76 AND 69 TO FACILITY OPERATING LICENSE NOS. DPR-42 AND DPR-60 DOCKET NOS. 50-282 AND 50-306 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of changes.
Remove
- Insert, 4
a TS 4.12-2 TS 4.12-2 TS 4.12-4 TS 4.12-4 TS 4.12-5 TS 4.12-5 TS 4.12-6 TS 4.12-6 TS 4.12-7 TS 4.12-7 Table TS 4.12-1 Table TS 4.12-1 l
TS 6.7-2 TS 6.7-2 l
t i
i
b 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.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.
The tubes selected aa 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.
i (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 1% of the total tubes inspected are defective, or between 5% 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 than 1% 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, 71, 76 Prairie Island Unit ' 2 - Amendment No.13, 69
TS.4.12-4 D.
Acceptance 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 specifications. Eddy-current testing indica-tions 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 >20%
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 l
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 50% of the nominal tube wall thickness.
If significant general tube i
thinning occurs, this criteria will be reduced to 40% wall penetration.
(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
,g.
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) Sleeving 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.
Prairie Island Unit 1 - Amendment No. 31, 76 Prairie Island Unit 2 - Amendment No. 25, 69
1 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) 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 I
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
- i determine cause of the tube degradation and corrective measures taken to prevent recurrence.
Prairie Island Unit 1 - Amendment No. 31, 71, 73, 76 Prairie Island Unit 2 - Amendment No. 25, 66, 69
-.L%--#--*
TS.4.12-6 1
BASIS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
In-service inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or in-service conditions that lead to corro-sion.
In-service inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tu've degradation so that corrective measures can be taken.
The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those parameters found to result in negligible corrosion of the steam generator tubes. If the secondary coolant chemistry is not maintained within these parameters, localized corrosion would most likely result in stress corrosion cracking. The extent of cracking during plant operation would be limited by the limitation of steam generator leakage between the primary coolant system and the secondary coolant system o
(primary-to-secondary leakage = 1.0 gpm). Cracks having a primary-to-secondary leakage less than 1.0 gpm during operation will have an adequate marginofgafetyagainstfailureduetoloadsimposedbydesignbasis accidents.
Operating plants have demonstrated that primary-to-secondary leakage as low as 0.1 gpm will be detected by radiation monitors of steam generator blowdown. Leakage in excess of 1.0 gpm will require plant shut-down and an unscheduled eddy current inspection, during which the leaking i
tubes will be located and plugged or sleeved.
l Wastage-type defects are unlikely with proper chemistry treatment of secondary coolant. However, even if this type of defect occurs it will be found during scheduled in-service steam generator tube inspections. Repair or plugging will be required of all tubes with imperfections that could develop defects having less than the minimum acceptable wall thickness prior to the next inservice inspection which, by the definition of Specifica-tion 4.12.D.l.(f), is 50% of the tube or sleeve nominal wall thickness.
I Wastage type defects having a wall thickness greater than 0.025 inches will have adequate margins of safety against failure due to loads imposed by normal plant operation and design basis accidents.1 Steam generator tube inspections of operating plants have demonstrated the capability to reliably detectvastagetypejefectsthathavepenetrated20%oftheoriginal0.050-inch wall thickness.
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.
l Prairie Island Unit 1 - Amendment No. 31, 76 Prairie Island Unit 2 - Amendment No. 25, 69
TS.4.12-7 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, it 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-NP)
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.
l I
l Prairie Island Unit 1 - Amendment No. 31, 76 Prairie Island Unit 2 - Amendment No. 25, 69 l
i l
TABLE TS.4.12-1 STEAM GENERATOR TUBE INSPECTION IST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE TNSPECTTON Sampit Size Result Action Required Result Action Required Result Action Required A cinimum of C-1 None N/A N/A N/A N/A S Tub:s per S.G.
C-2 Plug or sleeve defec-l tive tubes and inspect C-1 None N/A N/A additional 2S tubes in this S.G.
C-2 Plug or sleeve defective C-1 None l
tubes and inspect addi-C-2 Plug or sleeve defective l
tional 4S tubes in this tubes S.G.
C-3 Perform action for C-3 result of first sample C-3 Perform action for N/A N/A C-3 result of first sample C-3 Inspect all tubes in All other None N/A N/A this S.G., plug or S.C.s are 3
sleeve defective tubes C-1 g
and inspect 2S tubes Some S.G.s Perform action for N/A N/A in each other S.G.
C-2 but no C-2 result of second p
Prompt notification additional sample g!
to NRC.
S.G. are M
C-3 g
Additional Inspect all tubes in N/A N/A S.G. is C-3 each S.G. and plug or l "7 sleeve defective tubes.
Prompt notification to NRC.
S=3%; When two steam generators are inspected during that outage.
S=6%; When one steam generator is inspected during that outage.
Unit 1-AmendmentNo.31,h/I',69 76 -
Unit 2-AmendmentNo.25,[Ig j
TS.6.7-2 2.
Occupational Exposure Report.
An annual report of occupational exposure covering the previous calendar year shall be submitted prior to March 1 of each year.
The report should tabulate on an annual basis the number of station, utility and other personnel (including con-tractors) receiving exposures greater than 100 mrem /yr and their associated man-rem exposure according to work and job functions, e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80%
of the total whole body dose received from external sources shall be assigned to specific major work functions.
3.
Monthly Operating Report. A monthly report of operating statistics and shutdown experience covering the previous month shall be submitted by the 15th of the following month to the Office of Management and Program Analysis, U. S. Nuclear Regulatory Commission, Washington, DC 20555.
(1) This report supplements the requirements of 10 CFR 20, Section 20.407.
If 10 CFR 20, Section 20.407 is revised to include such information, this Specification is unnecessary.
Unit 1 - Amendment No. 31, 5 9, 76 Unit 2 - Amendment No. 25, 5 3, 69
.