ML20100Q250
| ML20100Q250 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/03/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20100Q251 | List: |
| References | |
| NUDOCS 9202060435 | |
| Download: ML20100Q250 (10) | |
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CONSUMERS POWER COMPANY DOCKET NO. 50-255 PALISADE 1 PLANT AMENDHENT TO FACILITY OPERATING LICENSE Amendment No.
141 License No. DPR-20 1
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated October 22, 1990, 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; 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 the license amendment and Paragraph 2.C.2 of Facility Operating License No. DPR-20 is hereby amended to read as follows:
9202060435 920203 l
PDR ADOCK 05000255 l
P PDR
Technical Specifications The Technical Specifications contained in A>pendices A and B, as revised through Amendment No.141
, are iereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION L. B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects 111/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 3.1992
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ATTACHMENT TO LICENSE AMENDMENT NO.141 FACILITY OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise Appendix A Technical S>ecifications by removing the piges identified below and inserting the attacied pages. The revised pages a e identified by the amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 4-66 4-66 4-67 4-67 4-68 4-68 4-68a 4-69 4-68b 4-69a 4-68c 4-69b 4-68d 4-69c 4-69
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4.14 M.Qi[RIULINSERVICE INSP_EITION PROGRAM FOR ATEAM GENERATORS 4.14.1 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.b.
4.14.2 Steam GentaipdErlLitlection ind_.lmpnuca Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generaters specifi Table 4.14 1.
4.14.3 11nm Generstonly)x ; ole Seltttip3.Jnd Insoection - The steam generator t e minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.14 2.
The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.14.4 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.14.5.
The tubes selected for each inservice inspection shall include at least 3% of the totsi number of tubes in all steam generators; the tubes seleded for these inspections shall be selected on a random basis except; a.
Where experience in similar plants with similar water chemistry indicates r.ritical areas to be inspected, then at le;st 50% of the 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, All nonplugged tubes that previously had detectable wall penetrations greater than 20%.
Tubes in those area where experience has indicated 2.
s potential problems.
3.
A tube inspection (pursuant to Specification 4.14.5.a.8) 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.
L c.
The tubes selected as the second and third samples (if required by Table 4.14-2) during each inservice inspection may be subjected to a partial tube inspection provided:
1.
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.
4 66 Amendment No. g,97,,q i
4.14 AVGMENTED INSERVICE INSPECTION PROGRAM FOR STEAM GENERATORS s
(Cont'd) 2.
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:
Cateoorv Insoection Results C1 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 (greater than 10%) further wall penetrations to be included in the above percentage calculations.
4.14.4 Inspection Freauencies The above required inservice inspection of steam generator tubes shall be performed at the following frequencies:
a.
The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of inaugural criticality for the steam generators.
Subsequent inservice inspections shall be performnd at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.
If two consecutive inspections following service under AVT conditions, not including the preservice inspection, result in all inspections 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.
b.
If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.14 2 at 40 month intervals fall into Category C-3, the inspection freauency shall be increased to at least once per 20 months.
4-67 Amendment No. 6,141
4.14 AMMENTED INSERVICE INSPECTION PROGRAM JOR STEAM GENERATORS (Cont'd)
The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Sp6cification 4.14.4.a; the interval may then be extended to a maxinium of once per 40 months.
c.
Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first s$mple inspection specified in Table 4.14 2 during the shutdown subsequent to any of the following conditions:
1.
Primary-to secondary tube leaks (not including leaks originating from tube to tube sheet welds) in excess of the limits of Specification 3.1.5.
2.
A seismic occurrence greater than the Operating Basis Earthquake.
3.
A loss of coolant accident resulting in initiation of flow of the engineered safeguards.
4.
A main steam line or main feedwater line break.
4.14.5 Acceptance Criteria a.
As used in this Specification 1.
Jmoerfection means an exception to the dimensions, finish or contour of a tube from that required fabrication drawings or specifications.
Eddy current testing indications below 20% of the nominal tube wall thickness, if detectable, inay be considered as imperfections.
2.
Deoradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
3.
01qn ded Tu'oe means a tube containing imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation.
4.
% Deoradation means the percentage of the tube wall thickness affected or removed by degradation.
5.
Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.
6.
Pluacina limit means the imperfection depth at or beyond which the tube shall be removed from service and is equal to 40% of the nominal tube wall thickness.
4-68 Amendment No.13, 72, TN.112.172,141
4.14
$UGMENTED INSERM INSPECTION PROGRAM FORJTEAM GENERATQRS (Cont'd) f 7.
Unserviceable Jescribed the condition of a tube if it y
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 bre:k as specified in 4.14.4.c, above.
8.
Tube insoecti+n means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U 5end to the top supyt of the cold leg.
W Qf 9.
Preservice inspection means an inspection of the full
.gp length of each tube in steam generator porformed by eddy current techniques prior to service to establish a
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h baseline condition of the tubing. This inspection shall be performed after the shop hydrostatic test and prior to initial POWER OPERATION using the equipment ano technic,aes expec%d to be used during subsequent inservice inspections, b.
The steam generator shall be determined OPERABLE after ampleting the corresponding actions (plug all tubes exceeding c
the plugging limit and all tubes containing tnrough-wall E
cracks) required by Table 4.14-2.
4.12.6 Reports a.
Within 15 days following the completion of each inservice
'spection of steam generator tubes, the number of tubes lugged in each steam generator shall be reported to the f
Commission in s ipecial Report pursuant to Specification 6.9.3.3b.
q b.
The complete results of the steam generatnr tube inaervice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.3.3b within 12 months following completion of the inspection.
This Special Report shall include:
1.
Number and extent of tubes inspected.
)
2.
Location and percent of wall-thickness penetration for each indication of an imperfection.
3.
Identification of tubes plugged c.
Results of steam gent.rator tube inspections that fall into Category C-3 shall require 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> verbal notification to the NRC prior to resumption of plant operation. A written followup within the next 30 days shall provide a description of investigations and r.orrective measures taken to prevent recurrence.
4-69 Amendment No. R, f2, H2,141 t
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Table 4.14-I-MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION Preservice Inspection Yes No. of Steam Generators per Unit Two
- l First Inservice Inspection One Second &' Subsequent Inservice Inspections -
One 2
b Table Notation 1 t
I. -The inservice inspection may be limited to one steam generator on a rotating schedule
' encompassing 6% of the tubes if the results of previous inspections indicate that all steam generators are performing in a like manner. Note that under some circumstances, the l
operating conditions in one or more steam generators may be found to be more severe thatt those ir. other steam generators. 'Under such circumstances the sample sequence shall be modiffer' to inspect the most severe conditions.
i i
4.69a Amendment No.141 t
a
TABLE 4.14. STEAM GENERATOP. TUBE INSPECTION 3
IST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPEE INSPECTION
' Sample Size Result Action Required Result Action Required Result iction Required A minimum of C-1 None N/A N/A N/A N/A S Tubes per S.G.
C-2 Plug defective tubes C-1 None N/A N/A and inspect additional 25 tubes in this S.G.
C-2 Pla) defective tubes C-1
.None and' inspect additional 45 tubes in this S.G.
C-2 Plug defective tubes l
C-3 Perform action for
.i C-3 result of first Sample l
C-3 Perform action for C-3 result of first N/A N/A Sampie C-3 Inspect all tubes in All other None N/A N/A this S.G., plug de-S.G.s are fective tubes and C-1 j
inspect 25 tubes in each other S.G.
Some S.G.s Perform action for N/A N/A C-2 but no C-2 result of second i
additional sample 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> verbal S.G. are notificaticn to NRC C-3 j
with written follow i
up within next Additional Inspect all tubes 30 days S.G. is each S.G. and plug L
C-3 defective tubes.
N/A N/A I
s 5-3f%
Where N is the number of steam generators in the unit, and n is the number of sten generators inspected dur%; an inspection 4-69b Amendment No.141 l
l l
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4.14 MGMENTED INSERVICE INSPECTION PROGRAM FOR STLAM GENERATORS Basis (Cont'd)
The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the PCS will be maintained.
The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice 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 inservice cond:tions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube 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 chemittry limits found to result in negligible corrosion of the steam generator tubes.
If the secondary coolant chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking.
The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage limit between the primary coolant system and the secondary coolant system that is stated in Technical Specifications 3.1.5. Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents. Operating experience has demonstrated that primary-to-secondary leakage in excess of the limits stated in Technical Specification 3.1.5 can readily be detected by radiation monitors of steam generator blowdown or condenser off-ga:;.
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged.
Waste-type defects are unlikely with proper chemistry treatment of the secondary coolant. However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations.
Plugging will be required for all tubes with imperfections exceeding the plugging limit of 40% of the tube nominal wall thickness (ASME B&PV Code,Section XI, IWB 3521). Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect Agradation that has penetrated 20% of the original tube wall thickness.
Whenever.the results of any steam generator tubing inservice inspection fall into category C-3, these results will be promptly reported to the Commission prior the resumption of plant operation. Such cases will be considered by the Comission 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.
'9c Amendment No. m