ML20207B114

Amend 78 to License DPR-61,revising Tech Specs to Permit Repair of Degraded Steam Generator Tubes by Installing Metal Sleeves,Changing Definition of Tube Degradation & Adding Addl Tube Sleeving Reporting Requirements

ML20207B114
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	07/14/1986
From:	Charemagne Grimes Office of Nuclear Reactor Regulation
To:
Shared Package
ML19292F604	List: ML20207B111 ML20207B114 ML20207B119
References
NUDOCS 8607170431
Download: ML20207B114 (10)

Text

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, . jo,, UNITED STATES y, g y NUCLEAR REGULATORY COMMISSION t j WASHWGTON. O. C. 20666

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l l CONNECTICUT YANKEE ATOMIC POWER COMPANY l

HADDAM NECK PLANT DOCKET NO. 50-213 AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No. 78 l

License No. OPR-61

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Connecticut Yankee Atomic l Power Company (tne licensee) dated December 6, 1985 as modified

! January 7,1986 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 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; 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. '

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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-61 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 78, 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 ChristopherI. Grimes,Direktor Integrated Safety Assessment Project Directorate Division of PWR Licensing - 8

Attachment:

Changes to the Technical Specifications Date of Issuance: July 14,1986

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j ATTACHMENT TO LICENSE AMENDMENT NO. 78 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 i

Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.

i REMOVE INSERT 4-21c 4-21c 4-21d 4-21d l

4-21e 4-21e 4-21f 4-21f 4-21g 6-16 6-16 6-22 6-22 1 1

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{ s a) A seismic occurrence greater than the operating' basis earthquake.

j b) A loss of coolant accident which causes significant deviations in temperature or pressure which affect the j integrity of the steam generator tubes, or requires actuation of the engineered safeguards. '

! c) A major steam line or major feedwater line break.

D. Acceptance Criteria:

1. As used in this Specifications a) Imperfection means an exception to the dimensions, i

finish or contour of a tube from that required by i i

fabrication drawings or specifications. Eddy-current l testing indications below 20% of the nominal tube wall thicimess, if detectable, may be considered as imperfections.

I b) D'e nradation means a service-induced cracking, wastage, a pitting, wear or general corrosion occurring on either I >

inside or outside of a tube. -

! c) Degraded Tube means a tube containing imperfections

{ 20% of the nominal wall thickness caused by degradation.

j d)  % Desradation means the percentage of the tube wall i j thickness af f acted or removed by degradation.

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i e) Defect means an imperfection of such severity that it

exceeds the plugging limit. A tube or sleeve containing l,

- a defect is defective. ,

1 O Plutning Limit means the Imperfection depth at or i

beyond which the tube or sleeve shall be removed from  ;

j service because it may become unserviceable prior to the next inspection and is equal to 30% of the nominal -

tube wall thicimess for tubes.* l t

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• The plugging Ilmit for sleeves will be determined prior to the 1987 refueling outage for Cycle 13.

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I 4-21c 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 a Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in Specification 4.10.1.C.3.

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 af ter 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, with the exception of plugging the tube in Row 37. Column 73 in Steam Generator 2 for

.. Cycle 14.

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E. Following each in;ervice inspection of steam generator tubes, the number of tubes plugged or sleeved in each steam generator shall be t'eported in accordance with Specification 6.9.

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• Tube sleeving shall be performed in accordance with the Connecticut Yankee Steam Generator Sleeving Report, Revision 1, transmitted by letter dated January 7,1986.

j 4-21d o Amendment No. g, g, 78

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l BA5!5 The Surveillance Requirements for inspection of steam generator i tubes ensure that structural integrity of this portion of the reactor

coolant pressure boundary will be maintained. The program for  !

{ inservice inspection of steam generator tubes is based on the following  !

i criteria. .

} a) Modification of Regulatory Guide 1.83, Revision 1. ,

b) On previous Eddy Current Examinations results Inservice Inspection of steam generator tubing is essential in order to

, maintain surveillance of the conditions of tubes in the event that there .

1 is evidence of mechanical damage or progressive degradation due to l design, manufacturing errors, or inservice conditions that lead to l j corrosion, or excess leakage. inservice inspection of steam generator i tubing also provides a means of characterizing the nature and cause of  :

{ any tube degradation so that corrective measures can be taken. l l

,i The plant is expected to be operated in a manner such that the l j secondary coolant will be maintained within those chemistry limits l found to result in negligible corrosion of the steam generator tubes.  ;

5pecified, chemistry treatment of the secondary coolant also limits the  !

! possibility of vastage - type defects. If the secondary coolant  :

chemistry is not maintained within these limits, localized corrosion

' may result in stress corrosion cracking. The extent of cracking during -

plant operation would be limited by the limitation of steam generator  ;

tee leakage between the primary coolant system and the secondary i system imposed in Specification, Section 3.14, Primary System l Leakage. Operating plants have demonstrated that primary to i secondary leakage specified in Specification 3.14 can readily be detected by radiation monitoring of steam generator blowdown.

j If a defect should develop in service, it should be found during .

j sche </uled inservice steam generator tube examinations. Plusq;ing or I

, sleeving will be required for all tubes with imperfections equa, to or  ;

! exceeding the plugging limit of 30% of the tube nominal wall  :

thickness. Tubes containing sleeves with imperfections exceeding the ,

plugging limit will be plugged. Steam generator tube inspections of '

1 operating; plants have demonstrated the capability to reliably detect I degradat en that has penetrated 20% of the original tube wall  !

thickness, o

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 prior to j resumption of plant operation.

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4-21e Am$ndment No. M 78

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TABLE 4.10.1-1 MINIMUM NUMBER OF STEAM CENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION Preservice Inspection None No. of Steam Generators per Unit Four First inservice inspection (2) Att Second & Subsequent inservice inspections one(l)

Table Notation:

(1)

The inservice inspection may be limited to one steam generator on a rotating schedule encompassing 12% of the tubes if the results of the first or previous inspections indicate that all steam generators are performing in a like manner. Note that under some circumstances, the operating conditions in one or more steam generators may be found to be more severe than those in other steam generators. Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.

(2) The first inservice base line inspection was performed in 1975. 1 l

4-21f Amendment No g 78

.s TABLE 4.10.1-2  ;

STEAM GENERATOR TUBE INSPECTION ,

ist SAMPLE INSPECTION 2nd SAMPLE INSPECTION 3rd SAMPLE INSPECTION -

Sample Size Result Action Required Result Action Required Result Action Required i

r A minimum of C-! None N/A N/A N/A N/A.

l 5 Tubes per s.G.

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! C-2 Repair defective tubes C-1 None N/A N/A '

and inspect additional Repair C-1 None 25 tubes in this S.G.* C-2 defective tubes C-2 Repair ,

andinspect defective tubes' ,

additional 45 tubes C-3 Perform action for l in this S.G.* 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 All other tubes in 5.G.s are None N/A N/A this S. G., repair C-1 l defective tubes and Some S.G.s Perform action for N/A N/A inspect 25 tubes in C-2 but no C-2 result of second i r

each other S.G.* additional sample l 5.G. are

• Prompt notification C-3 to NRC pursuant to specification Additional Inspect all 6.9 S.G. is C-3 tubes in each S.G. and repair ,

defective tubes.* l Prompt notification N/A N/A to NRC pursuant ,

to Specification .

I 6.9 S= 12% Where n is the number of steam generators inspected during an inspection.

• R ir of defective tubes shah be limited to plugging with the exception of those tubes which may be sleeved. Tubes with defective sleeves shall be plugged.

Amendment No. [ 78

j - 3) Identification of tubes either plugged or sleeved.

j c. Occupational Exposure Report 4 The annual report shall be submitted prior to March 1 of each year j and shall cover the previous calendar year. The initial report shall i be submitted prior to March I of the year following initial l

, criticality.

This annual report shall in:lude a tabulation on an annual basis of the number of station, utility, and other personnel (including j contractors) receiving exposures greater than 100 mrem /yr. and

, their associated man-rem exposure according to work and job l functions, 4/e.g., reactor operations and surveillance; inservice

' inspection, routine maintenance, special maintenance (describe .

maintenance), waste processing and refueling. The dose j assignment to various duty functions may be estimated based on i 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 sha!! be assigned to specific major work functions.

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d. Monthly Operating Report - Routine reports of operating statistics 4

and shutdown experience sha!! be submitted on a monthly basis to *

! the Director, Office of Management Information and Program j . Control, U. 5. Nuclear Regulatory Commission, Washington, D. C.

20535, with a copy to the appropriate Regional Office, to be

l postmarked no later than the fifteenth of each month following the calendar month covered by the report.

The monthly report shall include a narrative summary of operating

. experience during the report period relating to safe operation of l

the facility, including safety-related maintenance.

e. Reports required as per 10 CFR 50.59b.

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s.9.2 Resortable Occurrences - -

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Reportable occurrences, including corrective actions and measures to prevent reoccurrence, sha!! be repo.ted to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence.

In case of corrected or supplemental reports, a licensee event report j shall be completed and reference sha!! be made to the original report

! date.

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ADMINISTRATIVE CONTROLS SPECIAL REPORTS .

6.9.3 Special reports shall be submitted to the Regional Administrator of the Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a. Inservice inspection results, Specifications (4.10) and (4.12).

b. Primary Containment Leak Rate Results, Specification (4.4).

- c. Reactor Vessel Material Surveillance Specimen Examination, Specification (4.10).

d. Steam Generator Tube Report _

Following each inservice inspection of steam generator tubes, the

- - nuinber of tubes either plugged or sleeved in each steam generator shall be reported to the Commission within 15 days.

e. Post-Accident Instrumentation Operability, Specification (3.23 A and B). -

6.10 RECORD RETENTION .

6.10.1 The followbg records shall be retained for at least five years:

m. Records and logs of f acility operation covering the time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principalitems of equipment related to nuclear safety. .~ ._

c. Reports of all events which are required by regulations and

_- Technical Specifications to be reported to the NRC in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

d. Records of survelliance activities, inspections and calibrations l -

- - - - required by these Technical Specifications.

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6-22 Amendment No. [ [ 78

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