ML17221A472
| ML17221A472 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 10/15/1987 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17221A474 | List: |
| References | |
| NUDOCS 8710270460 | |
| Download: ML17221A472 (7) | |
Text
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UNITED STATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER 5 LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF THE CITY OF ORLANDO, FLORIDA AND FLORIDA MUNICIPAL POWER AGENCY DOCKET NO. 50-389 ST.
LUCIE PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
24 License No.
NPF-16 I.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power 8 Light Company, et al. (the licensee),
dated September 4, 1987, as supplemented by letters dated September 11 and 15, 1987, complies with the standards and requirements o+ the Atomic Energy Act of 1954, as amended (the Act), and the Coaeission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the app1ication, the provisions of the Act, and the rules and regulations of the Commission; C.
D.
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 wil1 be conducted in compliance with the Commission's regulations; 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.
8710270460 87l.0i 5l P
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2.
Accordingly, Facility Operating License No.
NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.2 to read as follows:
2.
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 24
, 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.
~0 THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
october 15>
1987 erbert N. Ber kow, Director Project Directorate IJ-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO. 24 TO FACILITY OPERATING LICENSE NO.
NPF-16 DOCKET NO. 50-389 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 area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Pa es 3/4 4-1P.
Insert Pa es 3/4 4 1P 3/4 4-12a
REACTOR COOLANT SYSTEM 3/4.4.5 STEAM GENERATORS LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With one or more steam generators inoperable, restore the inoperable generator(s) to OPERABLE status prior to increasing T
above 200 F.
avg SURVEILLANCE RE UIREMENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program.
4.4. 5. 1 Steam Generator Sam le Selection and Ins ection Each steam generator shall be determined OPERABLE during shutdown by selectir g and inspecting at least the minimum number of steam generators specified in Table 4.4-1.
4.4.5.2 Steam Generator Tube Sam le Selection and Ins ection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2
~
The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified.acceptable per the acceptance criteria of Specification 4.4.5.4.
The. tubes selected for each inservice inpection shall include at least 3X of.
the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
a.
Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50K of the tubes inspected shall be from these critical areas.
b.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
ST.
LUCIE - UNIT 2 3/4 4-11
REACTOR COOLANT SYSTEM SUR~.'EILLANCE RE UIREMENTS (Continued l.
All nonplugged tubes that previously had detectable wall penetrations (greater than 20Ã).
2.
Tubes in those areas where experience has indicated potential problems.
3.
A tube inspection (pursuant to Specification 4.4.5.4.ae8) shall be performed on each selected tube.
If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.
c.
The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to partial tube inspection provided:
1.
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes wtih imperfections were previously found.
2.
The inspections include those portions of the tubes where imperfections were previously found.
- d.
Tubes within the following region may be excluded from the first sample:
All nonplugged tubes contained within the bounds of line 66 to line 102 will be inspected nominally 14 to 16 rows from the untubed region adjacent to the tubesheet stay cap. All nonplugged tubes in lines 65 and 103 will be inspected from row 21 to row 35.
No credit shall be taken for these tubes, if all tubes within the region are inspected, in meeting the minimum sample size requirements.
The results of each sample inspection shall be classified into one of the following three categories:
~Cate or C-1 Ins ection Results Less than 5X of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C-2 One of more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10K of the total tubes inspected are degraded tubes.
ST.
LUCIE - UNIT 2 3/4 4-12 Amendment No 24
REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued
~Cate or C-3 Ins ection Results More than 10Ã of the total tubes inspected are degraded tubes or more than lX of the inspected tubes are defective.
Note:
(1} In all inspections, previously degraded tubes must exhibit
."significant (greater than 10'5) further wall penetrations to be i'ncluded in the above percentage calculations.
- (2) The results of the 4.4.5.2.d examinations will not be included in the above percentage calculations in cases involving batwing and vertical strap wear.
- Applicable only during the Cycle 3 refueling outage.
ST.
LUCIE - UNIT 2 3/4 4-12a Amendment No.
24