ML20235S525
| ML20235S525 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 09/25/1987 |
| From: | Thomas C Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235S503 | List: |
| References | |
| TAC-67463, NUDOCS 8710090030 | |
| Download: ML20235S525 (6) | |
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9 UNITED STATES 3
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, ( ',g NUCLEAR REGULATORY COMMISSION l
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. -j WASHINGTON, D. C. 20555 j
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i CONNECTICUT YANKEE ATOMIC POWER COMPANY D0_CKET NO. 50-213 q
HADDAM NECK PLANT l
l AMENDMENT TO FACILITY OPERATING LICENSE
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l Amendment No. 96 License No. DPR-61 i
1.
The Nuclear Regulatory Commission (the Comission) has found that:
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A.
The application for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated June 1,1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set I
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 assurancre (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 Commission's regulations; i
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 l
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.
9710090030 % h 13 l
ADOCK PDR l
PDR 1
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, 1 2.
Accordingly, the' license is amended by changes'to the Technical Specifications as indicated in the attachment to this license amendment-
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andParagraph2.C.(2)ofFacilityOperatingLicenseNo.DPR-61ishereby 1
I amended to read as follows:
(2) Technical Specifications I
The Technical Specifications contained in Appendix A, as revised through Amendment No. 96, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the 1
Technical Specifications.
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3.
This license amendment is effective as of the date of its issuance.
J FOR THE NUCLEAR REGULATORY COMMISSION l
GL O. Yswe Cecil 0. Thomas, Director Integrated Safety Assessment i
Project Directorate j
Division of Reactor Projects III/IV/V I
and Special Projects
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Attachment.
Changes to the Technical Specifications Date of Issuance:
September 25, 1987 l
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i ATTACHMENT TO LICENSE AMENDMENT NO. 96 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 4-21c 4-21c 4-21d 4-21d 4-21e 4-21e j
a e
a)
A seismic.occurranca greater than the optrating basis
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b)
A loss of coolant accident which causes significant deviations in temperature or pressure which affect the integrity of the steam generator. tubes, or requires actuation of the engineered safeguards.
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c)
A major steam line or major feedwater line break.
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 indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections, b)
Degradation means a service-induced cracking, wastage, pitting 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 above the tube's rolled region.
Also, a tube with an imperfection in the region one. half inch below the uppermost one inch of sound roll, is considered a degraded
- tube, d)
_96 Duradation means the percentage of the tube wall i
thickness affected or removed by degradation..
e)
Defect means an imperfection of such severity that it exceeds the plugging limit or an imperfection which is located in the uppermost one inch of the tube's sound roll.
A tube er sleeve containing a defect is defective, f)
Plugging Limit means the imperfection depth at or beyond which the tube or sleeve shall be removed from service because it may become unserviceable prior to the next inspection and is equal to 50% of the nominal tube wall thickness for tubes.*
For the rolled region (bottom four inches of the tube), the following criteria apply:
- 1. Any tube containing an imperfection within the uppermost inch of sound ro!! shall be repaired or removed from service.
- 2. Any is acceptable, below the uppermost one inch of sound roll.
- The plugging Ilmit for sleeves will be determined prior to the first refueling i
outage following sleeve installation.
I 4-21c Amendment No. 20, 76, 78, 96 i
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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 i
loss-of-coolant accident, or a steam hne or feedwater line break as specified in Specification 4.10.1.C.3.
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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.
2.
The Steam Generator may be returned to service after completing the corresponding actions (plug or sleeve
- all tubes exceeding the plugging limit and plug all defective sleeves) required by Table 4.10.1-2.
l E.
Following each inservice inspection of steam generator tubes, the i
number of tubes plugged or sleeved in each steam generator shall be l
reported in accordance with Specification 6.9.
i Tube sleeving shall be performed in accordance with the Connecticut Yankee Steam Generator Sleeving Report, Revision 1, transmitted by i
"B11921, Forwards Proprietary Rev 1 to WCAP-11008 & Nonproprietary Rev 1 to WCAP-11009, Connecticnt Yankee Steam Generator Sleeving..., Per 851206 Application to Amend License [[site license" contains a listed "[" character as part of the property label and has therefore been classified as invalid..W/o WCAP-11009.WCAP-11008 Withheld (Ref 10CFR2.790)|letter dated January 7,1986]].
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4-21d Amendr0 erit No. 20,. 7E, 7E, 96
BASIS The Surveillance Requirements for inspection of steam generator tubes ensure that structural integrity of this portion of the reactor
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coolant pressure boundary will be maintained.
The program for 4
inservice inspection of steam generator tubes is based on the following criteria.
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' a)
Modification of Regulatory Guide 1.E3, Revision 1.
b)
On previous Eddy Current Examinations results I
j inservice inspection of steam generator tubing is essential in order to
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maintain surveillance of th6 conditions of tubes in the event that f
there is evidence of mechanical damage or progressive degradation J
due to design, manufacturing errors, or inservice conditions that lead i
to corrosion, or excess leakage.
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 tiose chemistry limits I
found to result in negligible corrosion of the swam generator tubes.
l Specified chemistry treatment of the secondary coolant also limits I
the possibility of wastage - type defects. If the secondary coolant chernistry is not maintained within these limits, localized corrosion may result in stress corrosion cracking.
The extent of cr,acking during plant operation would be limited by the limitation of steam generator tube leakage between the primary coolant system and the 3
secondary system imposed in Specification, Section 3.14, Primary System Leakage. Operating plants have demonstrated that primary to secondary leakage specified in Specification 3.14 can readily be detected by radiation monitoring of steam generator blowdown.
If a defect should develop in service, it should be found during scheduled inservice steam generator t,ube examinations. Plugging or sleeving will be required for all tubes with imperfections equal. to or exceeding the plugging limit defined in Specification Section 4.10.1. D. I.f.
Tubes containing sleeves with imperfections exceeding 1
the plugging limit will be plugged. Steam generator tube inspections of operating plants have demonstrated the capability to reliably j
detect degradation that has penetrated 20% of the original tube wall I
thickness and to axially locate,the degradation in the rolled region with an accuracy of,0.1 inch.
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The plugging limit defined in Specification, Section 4.10.1.D.I.f is based on the requirements set forth in Regulatory Guide 1.121.
These requirements were also the bases for demonstrating that a tube imperfection is acceptable, regardless of depth provided that it is located below one inch of sound roll.
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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 10 CFR 50.72(b)(2) prior to resumption of plant operation.
i 4-21e Amendment No. 20, 78 79, 96 L