ML20205N639
| ML20205N639 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/08/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205N642 | List: |
| References | |
| NUDOCS 9904190058 | |
| Download: ML20205N639 (5) | |
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t UNITED STATES j
j NUCLEAR REGULATORY COMMISSION o
C WASHINGTON, D.C. 2055MKc1 4
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9 FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF EUSHNELL CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION.
CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEMINOLE ELECTRIC COOPERATIVE. INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.172 License No. DPR-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power Corporation, et al. (the licensees), dated October 1,1997, as supplemented April 23 and November 17, 1998 and February 19, ~1999, 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 con. mon defense and security nr to the health and safety of the public; and 9904190058 99040s PDR ADOCK 05000302 P
, E.
The issuance of this amenoi. 'nt is in accordance with 10 CFR Part 51 of the Commission's regu!stions and an 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 amendment, and paragraph 2.C(2) of Facility Operating License No. DPR 72 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.172, are hereby incorporated in the Ilicense. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION b
.h Sheri R. Peterson, Chief, Section 2 i
Project Directorate 11 Division of Project Licensing Management i
Office of Nuclear Reactor Regulation 1
Date of issuance: April 8,1999 i
i
ATTACHMENT TO LICENSE AMENDMENT NO.172 T_O FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contains vertical lines indicating the area of change.
Remove Paae Insert Paae 5.0-17 5.0-17 5.0-29 5.0-29 i
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- Procedures, Programs and Manuals 5.6 5.6 Procedures, Programs and Manuals 5.6.2.10 OTSG Tube Surveillance Program (continued) 8.
Plugging / Sleeving Limit means the extent of degradation beyond which the tube shall be restored to serviceability by the installation of a sleeve or removed from service because it may become unserviceable prior to the next inspection and is equal to 40% of the nominal tube or sleeve wall thickness.
No more than five'thousand sleeves may be installed in each OTSG.
9.
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 loss-of-coolant accident, or a. main steam line or feedwater line break, as specified in 5.6.2.10.3-c. above.
10.
Tube Inspection means an inspection of the entire OTSG tube as far as possible, b.
The OTSG shall be ' determined OPERABLE after completing the corresponding actions (plug or sleeve all tubes exceeding the plugging / sleeving limat and all tubes containing through-wall cracks) required by Table 5.6.2-2 (and Table 5.6.2-3 if the provisions of Specification 5.6.2.10.2.d are utilized).
Defective tubes may be repaired in accordance with the B&W process (or method) equivalent to the method described in report BAW-2120P.
There are a number of OTSG tubes that have th=' limit as potential to exceed the tube plu a result of tube end anomalies. gging/ sleeving Defective tubes will be repaired or plugged during the next outage of sufficient duration. An evaluation has been performed which confirms that operability of the CR-3 OTSGs will not be impacted with those tube inservice.
c.
Inservice tubes with pit-like IGA indications in the "B" OTSG first span shall be monitored for growth of these indications by using a test probe equivalent to the high frequency bobbin probe used in the 1997 inspection. The indicated percentage throughwall value from the current inspection shall be compared to the indicated percentage throughwall value from the 1997 inspection.
5.6.2.11 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibit steam generator tube degradation and low pressure turbine disc stress corrosion cracking.
The program shall include:
a.
Identification of a sampling schedule for the critical variables and control pints for these variables; b.
Identification of the procedures used to measure the values of the critical variables; (continued)
Crystal River Unit 3 5.0-17 Amendment No.172 L..
Reporting Requirements 5.7 i
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i 5.7 Reporting Requirements 5.7.2 Special Reports (continued)
The following Special Reports 1 hall be submitted:
a.
When a Special Report is required by Condition B or F of LCO 3.3.17, " Post Accident Monitoring (PAM)
Instrumentation," a renort shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of mor.itoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
b.
Any abnormal degradation of the containment structure l
detected during the tests required by the Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken.
Following each inservice inspection of steam generator c.
(OTSC) tubes, the NRC shall be notified of the following prior to ascension into MODE 4:
1.
Number of tubes plugged and sleeved j
2.
Crack-like indications in the first span 3.
An assessment of growth in the first span indications, and l
4.
Results of in-situ pressure testing, if performed.
t 1
The complete results of the OTSG tube inservice inspection shall be submitted to the NRC within 90 days after breaker i
closure following restart. The report shall include:
1.
Number and extent of tubes inspected.
2.
Location and percent of wall-thickness penetration for each indication of an imperfection, 3.
Location, bobbin coil amplitude, and axial and I
circumferential extent (if determined) for each first i
span IGA indication, and 4.
Identification of tubes plugged and tubes sleeved.
(continued)
Crystal River Unit 3 5.0-29 Amendment No.172 i
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