ML20012D882
| ML20012D882 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/22/1990 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20012D883 | List: |
| References | |
| NUDOCS 9003290044 | |
| Download: ML20012D882 (6) | |
Text
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~ NUCLEAR REGULATORY COMMISSION
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SOUTH CAROLIllA' ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY 1
1 DOCKET fl0. 50-395 -
l VIRGIL C. SUMER NUCLEAR STATION, UNIT NO.1=
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AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No. 91 License No. NPF-12.-
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A. -
The application for amendnent by South Carolina Electric & Gas Company (the licensee), dated. Septenber-19,1989,.as supplemented Decenber 11, 1989,- and January 16,.1990, complies with the standards and requirenents 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 o)erate in-conformity with the application, the provisions of tw Act, and the rules and regulations of the Commiss. ion; C.
' There is reasonable assurance (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 conpliance with the Comission's regulations;-
D.
The issuance of this amendnent will not be inimical to the connon defense and security or to the health and safety of the public;.
and E.
The issuance of this amendnent 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 amendnent; and paragraph 2.C.(2) of Facility Operating License No. NPF-12.is hereby amended to read as follows:
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(2) -Technical: Specifications and Envimnmental Protection Plan
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The Technical Specifications contaired in Appendix A, as revised i
p through; Amendnent No. 91
, and the Environmental Protection Plan contained in Appendix ~ B, are hereby incorporated in the license.
South-Carolina Electric & Gas Company-shall operate the facility j
in accordance with the Technical Specifications and the Environnental Protection Plan.
3.
This amendrent is effective as of its date of issuance,'and shall-be implemented within 30 days of issuance.
1 FOR THE NUCLEAR REGULATORY COMMISSION i
Original Signed By.
Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications I ate of Issuance: March 22, 1990 D
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k ' 'c ATTACHMENT TO LICENSE AMEN 0 MENT NO.'91 -
J TO FACILITY OPERATING LICENSE NO. NPF-12 l
DOCKET NO. 50-395
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' Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. -The revised pages are identified by amendment number and contain vertical lines indicating the areas of change, j
. Remove Pages Insert Pages-3/4.4-14 3/4'4-14 3/4 4-14a 3/4/ 4-14a 3/4 4-15 3/4 4-15
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_ REACTOR C00LANT SYSTEM
-SURVEILLANCE REQUIREMENTS (Continued) t
.4.4.5.4 Acceptance criteria a.-
As used in this Specification:
1.
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.
2.
Dearadation means a service-induced cracking,
wastage, wear or general corrosion occurring on either inside or outside of a tube.
L 3.
Degraded Tube means a tube containing imperfections greater h
than or equal to 20% of the nominal wall thickness caused by 1
L
. degradation.
l 4.
% Degradation means-the percentage of the tube wall thickness i
I af fected or removed by degradation.
L 5.
Defect means an imperfection of such severity that it exceeds l3 the plugging or repair limit.
A tube containing a defect is defective.
6.
Tube Plugaina or Repair Limit means the imperfection. depth at'or l
-beyond which the tube shall be repaired (i.e. sleeving) or removed from service by plugging and is equal to 40% of the norinal-tube wall thickness..This definition does not apply to the area of_the tubesheet region below the F* distance provided L
the tube -is not degraded (i.e., no indications of cracking)-
within the F* distance.
7.
Sleeve Pluaging or Repair Limit For the area in the' upper weld joint,~any degradation shall a.
be plugged unless it can be clearly demonstrated by.a quali-i, L
fied NDE technique that the degradation is less than-40% of L
the nominal wall thickness of the sleeve for ID imperfec-l tions or less than 40% nominal wall thickness-of the tube for 0.D. imperfections.
b.
For the area of the tube behind the sleeve and above the upper weld joint tubes with any degradation shall be e
plugged unless it can be clearly demonstrated by a qualified L
NDE. technique, that the degradation is less than 40% of the nominal wall thickness, For the area below the upper weld joint, any defect greater c.
than 40% of the nominal sleeve wall thickness shall be plugged.
F SUMMER - UNIT 1 3/4 4-14 Amendment No. 54, AB, 91
7.
I' l
'RfACTOR COOLANT SYSTEM
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i SURVEILLANCEREQUIREMENTS(Coginued) 8.
Unserviceable describes the condition of a tube if it leaks or l
i contains a defect large enough to affect its structural i
integrity in the event of an Operating Basis Earthquaka, a loss-of coolant accident, or a steam line or feedwater line i
break as specified in 4.4.5.3.c, above.
l 9.
Tube Inspection means an inspection of the steam generator tube l'
from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
10.
Sleeve Inspection means an inspection fo the sleeved portion of the tube.
This inspection will include 3 inches of the parent l
tube directly above the upper weld, the upper weld which forms the new pressure boundary, and the sleeve material below the upper weld.
11.
Repaired tube means a tube that has undergone a process that re-establishes its serviceability.
One or more of the following will be used when sleeving a steam gelierator tube:
The Combustion Engineering Inc. weld sleeve process will be i
used per report CEN-337-P.
The Babcock & Wilcox Kinetic sleeve process will be used per report BAW-2045 P.
i P
St.M4ER - UNIT 1 3/4 4-14a Amendment No. 59. 91
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SURVEILLANCE REQUIREMENTS (Continued)
- 12. _Preservice Inspection means an inspection of the full length of l-each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing.
This inspection shall be performed after the i
field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
i 13.
F* Distance is the distance into the tubesheet from the face l
of the tubesheet or the top of the last hardroll, whichever is lower (further into the tubesheet) that has been conservatively i
chosen to be 1.6 inches.
14.
F* TUBE is the tube with degradation, below the F* distance, l
l equal to or greater than 40%, and not degraded (i.e., no indica-tions of cracking) within the F* distance.
j b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the plugging limit) required by Table 4.4-2.
4.4.5.5 Reports Within 15 days following the completion of each inservice inspection a.
of steam generator tubes, the number of tubes plugged or repaired in each steam generator shall be reported to the Commission in a Special l
Report pursuant to Specification 6.9.2.
i l
b.
The complete results of the steam. generator tube inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection.
This Special Report shall include:
1 1.
Number and extent of tubes inspected.
L Location and percent of wall-thickness penetration for each indication of an imperfection.
l-3.
Identification of tubes plugged or repaired.
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c.
Results of steam generator tube inspections which fall into L
Category C-3 and require prompt notification of the Commission shall L
be reported pursuant to 10 CFR 50.72(b)2(i) prior to resumption of plant operation.
A report pursuant to 10 CFR 50.73(a)2(ii) shall be i
submitted to provide a description of investigations conducted to i
determine cause of the tube degradation and corrective measures taken l-to prevent recurrence, d.
The results of inspections of F* tubes shall be reported to the Commission in a report to the Director, ONRR, prior to the restart of the unit following the inspection.
This report shall include:
1.
Identification of F* tubes, and 2.
Location and size of the degradation NRC approval of this report is not required prior to restart.
SUMMER - UNIT 1 3/4 4-15 Amendment No. 35, 54, 59, 91
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