ML20151K891
| ML20151K891 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/22/1988 |
| From: | Perkins K Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151K895 | List: |
| References | |
| NUDOCS 8808030311 | |
| Download: ML20151K891 (5) | |
Text
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TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Anendment No.113 License No. NPF-3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Toledo Edison Company and The Cleveland Electric Illuminating Company (the facility) dated January 11, 1988 as supplemented April 14, 1988, complies with the stardards 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 license amendment will not be inimical to the comon 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.
8808030311 880722 PDR ADOCK 05000346 p
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. i 2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
(a) Technical Specifications The Technical Specifications contained in Appendix A and B, as revised through Amendment No.113. are hereby incorporated in the license. The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
The license ar.endment is effective as of its date of issuance and shall be implemented not later than Septanber 6,1988 FOR THE NUCLEAR REGULATORY COMMISSION hAS/CY
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M KennethE.Perkins, Direct'pr Project Directorate III-3 Division of Reactor Projects - III, IV, V, & Special Projects Office of Nuclear Peactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 22, 1988
ATTACHMENT TO LICENSE AMENDMENT NO.113 FACILITY OPERATING LICENSE NO NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 4-7 3/4 4-7
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Co i
Notes:
(1)
In all inspections, previously degraded tubes must exhibit significant (> 10%) further wall penetrations J
to be included in the above percentage calculations.
l l
(2) Where special inspections are performed pursuant to 4.4.5.2.b, defective or degraded tubes found as a result of the inspection shall be included in determining the Inspection Results Category for that seecial inspection but need not be included in determining the Inspection Results Category for the general steam generator inspection.
4.4.5.3 Inspection Frequencies - The above required inservice inspections of steam F5erator tubes shall be performed at the following frequencies:
The baseline inspection shall be performed to coincide with the a.
first scheduled refueling outage but no later than April 30, 1980.
Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.
If the results of two consecutive inspec-tions for a given group
- of tubes following service under all
)
volatile treatment (AVT) conditions fall into the C-1 category j
or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional 1
degradation has occurred, the inspection interv l for that group may be eatended to a maximum of 40 months.
b.
If the results of the inservice inspection of a steam generator performed in accordance with Table 4.4-2 at 40 month intervals for a given group
- of tubes fall in Category C-3, subsequent inservice inspections shall be performed at intervals of not less than 10 nor more than 20 calendar months after the previous inspection.
The increase in inspection frequency shall apply until a subsequent inspection meets the conditions specified in 4.4.5.3a and the interval can be extended to 40 monthm.
Additional, unscheduled inservice inspections shall be c.
performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 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 3.4.6.2.
- A group of tubes means:
(a) All tubes inspected pursuant to 4.4.5.2.b, or (b) All tubes in a steam generator less those inspected pursusnt to 4.4.5.2.b.
DAVIS-BESSE, UNIT 1 3/4 4-8 Amendment No. 21
SURVEILLANCE REQUIREMENTS (Continued) 3.
A tube inspection (pursuant to Specification 4.4.5.4.a.8) i shall be performed on each selected tube.
If any selqcted tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an 1
adjacent tuba shall be selected and subjected to a tube inspection.
b.
Tubes in the following groups may be excluded from the first random sample if all tubes in a group in both steam generators are inspected. No credit will be taken for these tubes in i
meeting minimum sample size requirements.
1.
Group A-1: Tubes within one, two or three rows of the open inspection lane.
2.
Group A-2: Tubes having a drilled opening in the 15th support plate.
3.
Group A-3: Tubes included in the rectangle bounded by rows 62 and 90 and by tubes 58 and 76, excluding tubes included in Group A-1.*
The tubes selected as the second and third samples (if required c.
by Table 4.4-2) during each inservice inspection may be subjected to less than a full 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.
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:
Category Inspection 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, 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.
Tubes in Group A-3 shall not be excluded after completion of the fifth refueling outage.
DAVIS-BESSE, UNIT 1 3/44-7 Amendment No. 21,?.113
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