ML20214Q156
| ML20214Q156 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 11/18/1986 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214Q151 | List: |
| References | |
| NUDOCS 8612050007 | |
| Download: ML20214Q156 (15) | |
Text
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'g UNITED STATES y
p, NUCLEAR REGULATORY COMMISSION
j WASHINGTON, D. C. 20555 5(
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-295 ZION NUCLFAR POWER STATION, UNIT 1 I
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.98 License No. DPR-39 1.
The Nuclear Regulatory Commission (the Comission1 has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated April 24, 1986, supplemented ilune 16, and y
September 2, 1986, 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 confomity 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 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 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-39 is hereby amended to read as follows:
8612050007 861118* '
PDR ADOCK 05000295 P
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(2) Technical-Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.98
, 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.
F0 THE NUCLEAR REGULATORY COMISSION
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5, irec. r v
WR Project Directora 3
Division of PWR Licens
-A, NRR y
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 18, 1986 t
[(j>REGgss ( [ g v
I UNITED STATES g
NUCLEAR REGULATORY COMMISSION 5i*
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E fASHINGTON, D. C. 20555
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1 COMMONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION NUCLEAR POWER STATION, UNIT 2 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. DPR-48 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.'
The application for amendment by Commonwealth Edison Ccmpany (the licensee) dated April 24, 1986, supplemented June 16, and b
September 2, 1986, 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 (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 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.
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-48 is hereby amended to read as follows:
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 88, 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 k-3 a g'a i
tor PWR Project Direct rate #3 Division of PWR Lic ing-A, NRR f
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 18, 1986
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UNITED STATES" v
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j WASHINGTON, D. C. 20555
%,.....f ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 98 FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO. 88 FACILITY OPERATING LICENSE N0. DPR-48 f
DOCKET NOS. 50-295 AND 50-304 s.
I Revise Appendix A as follows:
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I I.lM111NG CONDlil0N FOR OPERAll0N SURVEll. LANCE REQUIREMEN1 4.3.1.B.2 a.
Where experience in similar plants with l
similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.
i b.
1he first sample inspection during each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
1.
All nonplugged tubes that previously had detectable wall penetrations (> 20%) and 2.
Tubes in those areas where experience has indicated potential problems.
4 c.
The second and third sample inspections during each inservice inspection may be less than a full tube inspection by concentrating the inspection on those areas of the tube sheet array and on those portions of the tubes where tubes with imperfections were previously found.
Amendment Nos. 98 & 88 d.
The tube inspection shall be conducted according to 4.3.1.B.4.A'.B.
. inspections, where applicable, shall be.
i I
conducted according to 4.3.1.B.4.A.9.
If a tube does not permit the passage of the eddy a
current inspection probe the entire length and through the U-bend; this shall be recorded and an adjacent tube shall be inspected.
The tube which did not allow passage of the eddy current probe shall be considered degraded.
10500/10510 74a O
i 9
LIMillNG CONDil10N FOR OPERA 110N SURVLILLANCE REQUIREMLN1 4.3.1.8.2 (Continued) e.
lhe tube inspections will include at least 3%
of the total number of sleeved tubes in all 4 steam generators or all of the sleeved tubes in the generator chosen for the inspection 3
program, whichever is less.
These inspections will include both the tube and the sleeve.
lhe results of each sample inspection shall be classified into one of the following three categories:
Category insp.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, nut 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 i
defective.
N01E:
In all inspections, previously degraded tubes must exhibit significant (> 10%) further wall Amendment Nos. XXX&X7?AA111XMA%WFMNK penetrations to be included in the above Amendment Nos. 98 & 88 percentage calculations.
4.3.1.B.3 Inspection Frequencies lhe above required inservice inspections of steam generator tubes shall be 10500/10510 74b performed at the following frequencies:
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I IM111NG CONDll10N 10R Ol'LRAIION SURVEllIANCE REQUIREMEN1 1.
Imperfection means an exception to the dimensions, finish or contour of a tube from that' required by f abrication drawings or specifications.
Eddy-c.urrent testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
2.
Degradation means a service induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
3.
Degraded Tube means a tube containing imperfections > 20% of the nominal wall thickness caused by degradation.
4 4.
% Degradation means the percentage of the tubc wall thickness affected or removed by degradation.
5.
Defect means an imperfection of such severity that it exceeds the Plugging or Repair Limit. A tube Amendment Nos. 98 & 88 containing a defect is defective.
09/H0/09/90 74e
I IfilIIOG CilHilll ION I UR OPLHAIION SilHVLILi ANCL HL()UIREMENI
~
6.
plugging or Repair Limit means the imperfection depth at or beyond which the tube shall be repaired (ie. sleeving) or removed from service by plugging because it may become unserviceable prior to the, next inspection and is 1 40% of the nominal tube wall thickness.
Plugging Limit for sleeves means:
a.
for the area in the upper weld. joint, any imperfection produced by degradation shall be plugged unless it can be clearly demonstrated by a ylidiified Not technique that the imperfection is < 33% of the nominal wall thickness for I.D. imperfections or <40% thickness of the tube for 0.D.
imperfections.
b.
for the area below the upper weld joint any imperfection 2 33% of the nominal sleeve thickness shall be i
plugged; e
c.
for the area of the tube behind the Amendment Nos. 98 & 38 sleeve and above the upper weld joint, any imperfection produced by degradation shall be plugged unless it c d fl be Clearly demonstrated by a qualified NUE technique that the imperfection is < 40% of the nominal wall thickness.
7.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural x
Integrity in the event of an Operating Basis Farthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.3.1.B.3.C jab,0 ve.
i.. i n lof
-_ J
LIMillNG COND1110N FOR OptRA110N SURVEILI.ANCE REQUIREMEN1 s
8.
Tube Insp_ection 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.
9.
Sleeve Inspection means an inspection of the sleeved portion of the. tube.
This inspec.tlon will in'clude the upper weld which' forms the new pressure boundary and the s.leeve paterial below the upper weld.
'10.ejepaired Tube means a tube that has
. undergone a process that re-establishes its serviceability.
The Combustion Engineering welded sleeve process will be used per Report CEN-331-P,' Revision 1-P.
4 Amendmsnt Nos. 98 & 88 4
I
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A l.lHillNG CONDil10N FOR OPERAll0N SURVEILLANCE REQUIREMENT B.
The steam generator shall be determined OPERABIL after completing the corresponding action (plug or repair all tubes exceeding plug or repair limit and all tubes containing through-wall cracks) required by Table 4.3.B-2.
4.3.1.B.5
.Repo r_t s i
A.
Following each inservice inspection of steam generator tubes, the number of tubes repaired or plugged in each steam generator shall be reported to the Commission within 15 days.
B.
The completed results of the steam generator tube inservice inspection shall be included in the SPECIAL REPORI pursuant to Specification 6.6.3.(c).
lhe SPECIAL REPORI shall be submitted within 12 months following completion of the inspection.
This report shall include:
1.
Number and extent of tubes inspected.
2.
Location and percent of wall Amendment Nos. 98 & 88 thickness penetration for each indication of an imperfection.
3.
Identification of tubes repaired or plugged.
3
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091H0/09/90 749
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l.lMillNG CONill110N FOR OPERA 110N SURVEILLANCE REQUIREMENT C.
Results of steam generator tube inspections which fall in to category C-3 and require prompt notification of the Commission shall be reported pursuant to Specification 6.6.2 prior to resumption of plant operation. The written follow up of this report shall provide a description of investigation conducted to determine the cause of the tube degradation and corrective measures taken to prevent recurrence.
P Amendment Nos. 98 & 88 (19/1111/1191911 74h U
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l ABl E 4.3.B -2 *
-e SILAM GENERA 10R lilBL INSPECil0N s
ISI SAMPIL INSPECil0N 2ND SAMPLE INSPEC110N 3RD SAMPLE INSPLCil0N C l' ~dide
~~
C -1 None C-1 None C -2
. Plug or repair _ _. _
C -2 Plug or repair C2 Plug or repair defective tubes and defectives tubes and defective tubes inspect additional 25 inspect additional 45 tubes in this S.G.
tubes in this S.G.
I f
'A C-3 Inspect all tubes in C -3 Perform action for C-3 C-3 Perform action for C-3 this S.G. plug or result of first sample result of first sample repair defective tubes and inspect 25 tubes in each other S.G.
I l Sample Size All other S.G.'s None A minimum of Prompt notification to are C-1 S.
lobes per NRC pursuant to S.G.
Specification 6.6.2 Same S.G. 's C -2 Perform action for but no additional C-2 result of S.G. are C-3 second sample I I 4 L Additional S.G.
Inspect all tubes is C-3 in each S.G. and plug or repair defective tubes.
Prompt notification to NRC pursuant to specification 6.6.2 S--3N,%
Where N is the number of steam generators in the unit and n is the number of steam generators n
inspected during an inspection 09/00/09/90 Amendment Nos. 98 8 88
.,. e t
Bases:
3.3.1 Steam Generators a
4.3.1 lhe Surveillance Requirements for inspection of primary to-secondary leakage less than this limit the steam generator tubes ensure that the during operation will have an adequate margin of structural integrity of this por tion of the RCS safety to withstand the loads imposed during normal will be maintained.
lhe program for inisrvice operation and by postulated accidents. Operating inspectio'n for steam generator tubes is based on plants have demonstrated that primary-to-secondary a modification of Regulatory Guide 1.83, leakage of 500 gallons per day per steam generators Revision 1.
Inservice inspection of steam can readily be detected by radiation monitors of generator tubing is essential in order to steam generator blowdown.
leakage in excess of this maintain surveillance of the conditions of the limit will require plant shutdown and an unscheduled tubes in the event that there is evidence of inspection, during which the leaking tubes will be mechanical damage or progressive degradation due located and plugged.
to design, manufacturing errors, or inservice conditions that lead to corrosion.
Inservice Wastage-type defects are unlikely with proper inspection of steam generator tubing also chemistry treatment of the secondary coolant.
provides a means of characterizing the nature However, even~if a defect should develop in service,,
and cause of any tube degradation so that it will be found during scheduled inservice steam corrective measures,can be taken, generator tube examination.
Plugging or repairs will be required for all tubes with imperfections lhe plant is expected to be operated'in a manner exceeding the > 40% limit of the tube nominal wall such that the secondary coolant will be-thickness. Steam generator tube inspections of maintained Within those chemistry limits found operating plants have demonstrated the' capability to to result in negligible corrosion of the steam reliably detect degradation that has penetrated 20%
generator tubes.
If the secondary coolant of the original tube wall thickness.
chemistry is not neintained within these limits,
. localized corrosion may likely result in stress Whenever the results of any steam generator tubing corrosion _ cracking. The extent of cracking inservice inspection fall into Category 0-3, these during plant operation would be limited by the results will be promptly reported to the Commission limitation of steam generator tube leakage pursuant.to Specification 6.6.2 prior to resumption between the primary coolant system and the of plant-operation.
Such cases will be considered by secondary coolant system (primary to-secondary the Commission on a case-by-case basis and may result leakage 500 gallons per day per steam in a requirement for analysis, laboratory.
generator). Cracks having a examinations, tests, addillonal eddy-current inspection, and revision of the lechnical Specifications, if necessary.
78a Amendment Nos. 98 & 88 09 nul/0919f)
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