ML17333A250
| ML17333A250 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/04/1996 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17333A251 | List: |
| References | |
| NUDOCS 9601160076 | |
| Download: ML17333A250 (13) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1
,AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 205 License No.
DPR-58 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
Irhe application for amendment by Indiana Michigan Power Company (the llicensee) dated April 13, 1995 and supplemented August 28 and October 27,
- 1995, complies with the standards and requirements of the R'bomic Energy Act of 1954, as amended (the Act), and the Commission's muilI es and regulations set forth in 10 CFR Chapter I; B.
7k@.facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the ICemmission; C.
There is reasonable assurance (i) that the activities authorized by ChIIs amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted
%a compliance with the Commission's regulations; D.
Yihe 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.
like issuance of this amendment is in accordance with 10 CFR Part 51 of
<he Commission's regulations and all applicable requirements have been satisfied.
960ii60076 960i04 PDR ADQCK 050003i5 P
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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-58 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 205
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications'.
This license amendment is effective as of the date of issuance, with full implementation within 45 days FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 4,
1996 ohn B. Hickman, Project Manager Project Directorate III-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
~ g I
TTACHMENT TO LICENSE AMENDMENT NO. 205 TO FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 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 3/4 4-7 3/4 4-8 3/4 4-9 3/4 4-10 3/4 4-11 3/4 4-12 B 3/4 4-2b INSERT 3/4 4-7 3/4 4-8 3/4 4-9 3/4 4-10 3/4 4-11 3/4 4-12 B 3/4 4-2b
3/4 LIMITINGCONDITIONS FOR OPERATION ANDSURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM STBAM GBNBRATORS LIMITINGCONDITIONFOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With one or more steam generators inoperable, restore the inoperable generator(s) to OPERABLE status prior to increasing T, above 200'F.
SURVEILLANCERE UIREMENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirement of Specification 4.0.5.
4.4.5.1 Steam Generator Sam le Selection and In tion - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.
4.4.5.2 Steam Generator Tube Sam le Selection and In tion - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2.
The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4.
When applying the exceptions of 4.4.5 2~ through 4.4.5.2.e, previous defects or imperfections in the area repaired by sleeving are not considered an area requiring reinspection.
The tubes selected for each inservice inspection shall include at least 3'fthe total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% ofthe tubes inspected shall be from these critical areas.
b.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
1.
Alltubes that previously had detectable wall penetrations (greater than or equal to 20%) that have not been plugged or repaired by sleeving in the affected area.
This Specification does not apply in Mode 4 while performing crevice flushing as long as Limiting Conditions for Operation for Specification 3.4.1.3 are maintained.
COOK NUCLEAR PLANT-UNIT1 Page 3/4 4-7 AMENDMENT4N, 466, %0, 205
I t
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM SURVEILLANCERE UIREMENTS (continued) 2.
Tubes in those areas where experience has indicated potential problems.
3.
A tube inspection (pursuant to Specification 4.4.5.4.a.8) shall be performed on each selected tube. Ifany 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.
Tubes left in service as a result of application of the tube support plate plugging criteria shall be inspected by bobbin coil probe during all future refueling outages.
c.
In addition to the sample required in 4.4.5.2.b.1 through 3, all tubes which have had the F* criteria applied will be inspected in the roll expanded region.
The roll expanded region of these tubes may be excluded from the requirements of 4.4.5.2.b.l.
d.
The tubes selected as the second and third samples (ifrequired by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:
The tubes selected for the samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.
The inspections include those portions of the tubes where imperfections were previously found.
e.
Implementation of the steam generator tube/tube support plate plugging criteria for one fuel cycle (Cycle 15) requires a 100 percent bobbin coil inspection for hot-leg tube support plate intersections and cold-leg intersections down to the lowest cold-leg tube support plate with known outside diameter stress corrosion cracking (ODSCC) indications.
The determination of tube support plate intersections having ODSCC indications shall be based on the performance of at least a 20 percent random sampling of tubes inspected over their full length.
f.
Inspection of sleeves will follow the initial sample selection (1" sample) and sample expansion requirements of Table 4.4-2.
The results of each sample inspection shall be classified into one of the following three categories:
CategoO Ins ection 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.
COOK NUCLEAR PLANT-UNITI Page 3/4 4-8 AMENDMENT484, 446, XVV,K8, AO, 205
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM SURVEILLANCERE UIREMENTS (continued) 4.4.5.3 Note:
In all inspections, previously degraded tubes or sleeves must exhibit significant (greater than or equal to 10%) further wall penetrations to be included in the above percentage calculations.
I Ins ection Fre uencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:
The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality. Subsequent inservice inspections shall be perforined at intervals of not less than 12 nor more than 24 calendar months after the previous inspection. If two consecutive inspections followingservice under AVTconditions, not including the preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended.to a maximum of once per 40 months.
Ifthe results of inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40 month intervals fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months.
The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 4.4.5.3.a; the interval may then be extended to a maximum of once per 40 months.
C.
Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown
.subsequent to any of the following conditions:
Primaty-to-secondary tubes leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2.
2.
A seismic occurrence greater than the Operating Basis Earthquake.
3.
A Iosswf-coolant accident requiring actuation of the engineered safeguards.
4.
A main steam line or feedwater line break.
COOK NUCLEARPLANT-UNITI Page 3/4 4-9 AMENDMENT98 446, %0, 265
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM SURVEI LANCE RE UIREMENTS (continued) 4.4.5.4 Acce tance Criteria As used in this Specification:
~tm erfeaion means an exception to the dimensions, finish or contour of a tube or sleeve 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.
~De radation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve.
De raded Tube or Sleeve means an imperfection greater than or equal to 20% of the nominal wall thickness caused by degradation.
1 Percent De radation means the amount ofthe tube wall thickness affected or removed by degradation.
5.
Defect means an imperfection of such severity that it exceeds the repair limit.
Re air/Plu in Limit means the imperfection depth at or beyond which the tube or sleeved tube shall be repaired or removed from service.
Any tube which, upon inspection, exhibits tube wall degradation of40 percent or more ofthe nominal tube wall thickness shall be plugged or repaired prior to returning the steam generator to service.
This definition does not apply to the portion of the tube in the tubesheet below the F*
distance for F* tubes.
Any sleeveexcept laser welded sleeves, which upon inspection exhibits wall degradation of29 percent or more of the nominal wall thickness, shall be plugged prior to returning the steam generator to service.
In addition, any sleeve, except laser welded sleeves, exhibiting any measurable wall loss in sleeve expansion transition or weld zones shall be plugged.
This definition does not apply to tube support plate intersections for which the voltage.-based plugging criteria are being applied.
Refer to 4.4.5.4.a.10 for the plugging limitapplicable to these intersections.
For a tube that has been sleeved with a laser welded sleeve, through wall penetration of greater than or equal to 23% of sleeve nominal wall thickness requires the tube to be removed from service by plugging.
7.
Unserviceable describes the condition of a tube or sleeve ifit 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 as specified in 4.4.5.3.c, above.
~tns ection determines the condition of the steam generator tube or sleeve from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
For a tube in which the tube support plate elevation interim plugging limit has been
- applied, the inspection wiH include all the hot leg intersections and all cold leg intersections down to, at least, the level of the last crack indication.
COOK NUCLEAR PLANT-UNIT1 Page 3/4 4-10 AMENDMENT98, ~, 446, 4-'Pp %0, 205
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM SURVEILLANCERE UIREMENTS (continued) 9.
~gteevin a tube is permiued with tube support plate sleeves and with tubesheet sleeves.
Tube support plate sleeves are centered about the tube support plate intersection.
Tubesheet sleeves start at the primary fluid tubesheet face and extend to the free span region of tube above the tubesheet.
10.
Tube Su ort Plate Re air Limitis used for the disposition of a steam generator tube for continued service that is experiencing outside diameter stress corrosion cracking (ODSCC) confined within the thickness of the tube support plates. At tube support plate intersections, the repair limitis based on maintaining steam generator tube serviceability as described below:
a.
Degradation attributed to ODSCC within the bounds of the tube support plate with bobbin voltage less than or equal to 2.0 volts willbe allowed to remain in service.
b.
Degradation attributed to ODSCC within the bounds of the tube support plate with a bobbin voltage greater than 2.0 volts willbe repaired or plugged except as noted in 4.4.5.4.a.10.c below.
Indications of potential degradation attributed to ODSCC within the bounds of the tube support plate with a bobbin voltage greater than 2.0 volts but less than or equal to 5.6 volts may remain in service ifa rotating pancake coil inspection does not detect degradation.
Indications of ODSCC degradation with a bobbin voltage greater than 5.6 volts willbe plugged or repaired.
11.
Fd'istance is the distance from the bottom of the hardroll transition toward the bottom of the tubesheet that has been conservatively determined to be 1.11 inches (not including eddy current uncertainty).
12.
Fd'ube is a tube with degradation, below the Fd'istance, equal to or greater than 40%,
and not degraded (i.e., no indications of cracking) within the Fd'istance.
13.
~Tube Re air refers to steering as described by the reports listed in 4.4.5.4.c which are used to maintain a tube in service or return a tube to service.
Tubes with degradation indications of less than the plugging limit may be preventively sleeved at the Owner's discretion.
This includes removal of plugs that were installed as a corrective or preventive measure.
A tube inspection per 4.4.5.4.a.8 is required prior to returning previously plugged tubes to service.
Further restrictions regarding identified indications and their proximity to the joint areas of various sleeving processes may be applicable.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plugging or sleeving all tubes exceeding the repair limit and all tubes containing through-wall cracks) required by Table 4.4-2.
Steam generator tube repairs may be made in accordance with the methods described in either WCAP-12623, WCAP-13088 (Rev. 3), or CEN-313-P.
COOK NUCLEAR PLANT-UNIT1 Page 3/4 4-11 AMENDMENT48k, 466, 4-'P, K8, AO, 205
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM SURVEILLANCERE UIREMENTS (continued) 4.4.5.5
~Re ops Following each inservice 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.
The complete results of the steam generator tube inservice inspection shall be included in the Annual Operating Report for the period in which this inspection was completed.
This report shall include:
1.
Number and extent of tubes and sleeves inspected.
2.
Location and percent ofwall-thickness penetration for each indication ofan imperfection.
3.
Identification of tubes plugged or sleeved.
C.
Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the Commission shall be reported pursuant to Specification 6.9.1 prior to resumption ofplant operation.
The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
For implementation of the voltage-based repair criteria to tube support plate intersections, notify the staff prior to returning the steam generators to service should any of the following conditions arise:
1.
Ifestimated leakage based on the actual measured end-of-cycle voltage distribution would have exceeded the leak limit(for the postulated main steam line break utilizing "Standard Review Plan - NUREG-0800" assumptions) during the previous operating cycle.
If circumferential crack-like indications are detected at the tube support plate intersections.
Ifsignificant indications are identified that extend beyond the confines ofthe tube support plate.
4.
Ifthe calculated conditional burst probability, as calculated per WCAP-14277, exceeds 1x10~, notify the NRC and provide an assessment of the safety significance of the occurrence.
COOK NUCLEAR PLANT-UNIT1 Page 3/4 4-12 AMENDMENT403 446, XVV,K8, ZOO, 2OE
'V
3/4 BASES 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.5 STEAM'GENERATORS TUBE INTEGRITY Continued Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be promptly reported to the Commission pursuant to Specification 6.9.1 prior to resumption ofplant operation. Such cases willbe 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.
To determine the basis for the sleeve plugging limit, the minimum sleeve wall thickness was calculated in accordance with Draft Regulatory Guide 1.121 (August 1976).
In addition, a combined allowance of 20 percent of wall thickness is assumed for eddy current testing inaccuracies and continued operational degradation per Draft Regulatoty Guide 1.121 (August 1976).
The following sleeve designs have been found acceptable by the NRC staff:
1.
Westinghouse Mechanical Sleeves (WCAP-12623) 2.
Combustion Engineering Leak Tight Sleeves (CEN-313-P) 3.
Westinghouse Laser Welded Sleeves (WCAP-13088, Rev. 3)
Descriptions of other future sleeve designs shall be submitted to the NRC for review and approval in accordance with 10 CFR 50.90 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.
COOK NUCLEAR PLANT-UNIT1 Page B 3/4 4-2b AMENDMENT4Q, 4R, 446, 200 205