ML19337A971
| ML19337A971 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/17/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19337A972 | List: |
| References | |
| TAC-41001, NUDOCS 8010010106 | |
| Download: ML19337A971 (10) | |
Text
UNITED STATES N
NUCLEAR REGULATORY COMMISSION a
WASHINGTON, D. C. 20555 w.... f FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNE1.L 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 SEBRING UTILITIES COMMISSION SEMIN0LE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302
'RYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT
' AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 33 Licei:se No. DPR-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by Florida Power Corporation, et al A.
(the licensees) dated February 15, 1980, 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 appliation, the provisions of the Act, and the rules and regulations of che Comission; C.
There is reasonable assurance (i) that the activities autho..-ized 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 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.
8010010
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ATTACHMENT TO LICENSE AMENDMENT NO. 33 FACILITY OPERATING LI(CNSE N0. DPR-72 DOCKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifi-The revised pages are identified cations with the enclosed pages.
by Amendment number and contain vertical lines indicating the area The corresponding overleaf pages are also provided to of change.
maintain document completeness.
Insert Pages Remove Pages 3/4 4-7 through 3/4 4-10 3/4 4-7 through 3/4 A-10 3/4 4-12a (new page) 8 3/4 4-3 B 3/4 4-3 I
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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) b.
The first inservice inspection (subsequent to the preservice in-spection) of each steam generator shall include:
1.
All nonplugged tubes that previously had detectable wall penetrations (>20%), and 2.
Tubes in those areas where experience has indicated poten-tial problems.
c.
The second and third inservice inspections may be less than a
' full tube inspection by concentrating (selecting at least 50% of the tubes to be inspected) the inspection on those areas of the tube sheet array and on those portions of the tubes where t'Jbes with imperfections were previously found.
d.
Tubes in specific limited areas which are distinguished by unique operating conditions and/or physical construction may be excluded from random samples if all such tubes in the specific area of a steam generator are inspected with the inspection result classi-fication and the correspoiiding action required as specified in Table 4.4-6.
Nc credit will be taken for these tubes in meeting i
minimum sample size requirements.
Degraded or defective tubes found in these areas will not be considered in detennining the inspection results category as long as the mode of degradation is unique to that area and not random in nature.
The results of each sample inspection shall be classified into one of the following *.hree categories:
Category Inspection Results C-1 Less than 5% of the total tubes inspected are de-graded tubes and none of the inspected tubes are defective.
C-2 One or more tubes, but not more than 17. of the to-tal 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 de-graded tubes or more than 1% of the inspected e
tubes are defective.
Note:
In all inspections, previously degraded tubes must ex-hibit significant (>10%) further wall penetrations to be included in the above percentage calculations.
CRYSTAL RIVER - UNIT 3 3/4 4-7 Amendment No. 3 3
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.3 Inspection Frequencies - The above-required inservice inspections of steam generator tubes shall be performed at the following frequencies:
The first inservice inspection shall be performed after 6 Effec-a.
tive Full Power Months, but within 24 calendar months of initial criticality. Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.
If two consecutive inspections following service under all volatile treatment (AVT) conditions, not including the preservice inspection, result in all inspection results falling into the C-1 category, or if two consecutive in-spections demonstrate that previously ooserved degradation has not continued and no additional degradation has occurred, the in-spection interval may be extended to a maximum of once per 40 months.
L.
If the inservice inspection of a steam generator, conducted in accordance with Table 4.4-2 and/or Table 4.4-6 requires a third l
sample inspection whose results fall in Category C-3, the inspection frequency shall be reduced to at least once per 20 months.
The reduction in inspection frequency shall apply until a subsequent inspection demonstrates that a third sample inspection is not required.
Additional unscheduled inservice inspections shall be performed c.
on each steam generator in accordance with the first sample in-spection specified in Table 4.4-2 and/or Table 4.4-6 during the
[
shutdown subsequent to any of the following conditions:
1.
Primary-to-secondary tube leaks (not including leaks origin-ating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2, 2.
A seismic occurrence greater than the Operating Basis Earthquake, 3.
A loss-of-coolant accident requiring actuation of the engi-neered safeguards, or 4.
A main steam line or feedwater line break.
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 oy fabrication drawings CRYSTAL RIVER - UNIT 3 3/4 4-8 Amendment No. 3 3
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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) i or specifications.
Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
1 2.
Degradation means a service-induced cracking, wastage, wear, or general corrosion occurring on either inside or outside of a tube.
3.
Degraded Tube means a tube containing imperfections >20% of the nominal wall thickness caused by degradation.
4.
P. Degradation means the percentage of the tube wall thick-ness affected or removed by degradation.
S.
Defect means an imperfection of such severity that it ex-ceeds the plugging limit. A tube containing a defect is de-fective. Any tube which does not permit the passage of the eddy-current inspection probe shall be deemed a defective tube.
1 6.
Plugging Limit means tne imperfection depth at or beyond which tne tube shall be removud from service because it may become unserviceable prior to the next inspection and is equal to 40% of the nominal tube wall thickness.
7.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structJral integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.
3.
Tube Inspection neans an inspection of the steam generator tube from tne point of entry completely to the point of exit.
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2 (and Table 4.4-6, if the provisions of Specifica-tion 4.4.5.2.d are utilized).
4.4.5.5 Reports j
a.
Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15 days.
CRYSTAL RIVER - UNIT 3 3/4 4-9 Amendment No. 3 3 5
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 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.
Number and extent of tubes inspected.
2.
Location and percent of wall-thickness penetration for each indication of an imperfection.
3.
Identification of tubes plugged.
c.
Results of steam generator tube inspections which fall into Cate-gory C-3 and require prompt notification of the Commission shall be reported pursuant to Specification 6.9.1 prior to resumption of plant operation.
The written followup of this report shall provide a description of investigations conducted to determine i
cause of the tube degradation and corrective measures taken to l
prevent recurrence.
4.4.5.6 The steam generator shall be demonstrated OPERABLE by verifying steam generator level to be within limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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CRYSTAL RIVER - UNIT 3 3/4 4-10 Amendment No. 3 3 l
9s TABLE 4.4-6 C
SPECIFIC LIMITED AREA INSPECTION 5s
- c E
IST SAMPLE INSPECTION OF A 2ND SAMPLE INSPECTION OF A il
" SPECIFIC LIMITED AREA"
" SPECIFIC LIMITED AREA" w
Sample Size Result Action Required Result Action Required 100% of Area in both S.G.'s C-1 None N/A N/A C-2 Plug defective tubes N/A N/A C-3 Plug defective tubes N/A N/A p
E?
100% of Area in one S.G.
C-1 None N/A N/A C-2 Plug defective tubes and C-1 None inspect 100% of corres-ponding area in other S.G.
C-2 Plug defective tubes 8
C-3 Plug defective tubes 5.
M C-3 Plug defective tubes and C-1 None 5
inspect 100% of corres-ponding area in other S.G.
C-2 Plug defective tubes 2
C-3 Plug defective tubes os c.a
REACTOR COOLANT SYSTEM BASES J
imposed during normal operation and by postulated accidents.
Operating plants have demonstrated that primary-to-secondary leakage of 1 GPM can be detected by monitoring the secondary coolant. Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged.
Operational experience has shown that tube defects can be the result of unique operating conditions and/or physical arrangements in specific limited areas of the steam generators (for example, tubes adjacent to tne open inspection lane or tubes whose 15th tube support plate hole is not broached but drilled). A full inspection of all of the tubes ir such spe-cific limited areas will provide complete assurance that degraded or defec-tive tubes in these areas are detected. Because no credit is taken for these distinctive tubes in the constitution of the first sample or its re-sults, the requirements for the first sample are unchanged.
This require-ment is essentially equivalent to and meets the intent of the requirements set forth in Regulatory Guide 1.83, " Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes", Rev.1, July 1975, and does not re-duce the margin of safety provided by those requirements.
Wastage-type defects are unlikely with proper enemistry treatment of the secondary coolant. However, even if a defect should develop in ser-vice, it wil! oe found during scheduled inservice steam generator tube ex-aminations. Plugging will be rtauired for all tubes with imperfections ex-ceeding the plugging limit of 40% of the tube nominal wall thickness.
Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.
Whenever the results of any stcam generator tubing inservice inspec-tion fall into Category C-3, these results will be promptly reported to the Commission pursuant to Specification 6.9.1 prior to resumption of plant op-eration. Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory exami-nations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
The steam generator water level limits are consistent with the initial conditions assumptions in the FSAR.
Amendment No. 3 3 CRYSTAL RIVER - UNIT 3 B 3/4 4-3
REACTOR COOLANT SYSTEM BASES 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to detect and monitor leakage from the Reactor Coolant Pressure Bounda ry. These detection systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Sy:tems", May 1973.
3/4.4.6.2 OPERATIONAL LEAKAGE PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.
Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.
Industry experience has shown that, while a limited amount of leakage is expected from the RCS, the UNIDENTIFIED LEAKAGE portion of this can be reduced to a threshold value of less than 1 GPM. This threshold value is sufficiently low to ensure early detection of additional leakage.
The total steam generator tube leakage limit of 1 GPM for all steam generators ensures that the dosage contribution from tube leakage will be limited to a small fraction of Part 100 limits'in the event of either a steam generator tube rupture or steam line break.
The 1 GPM limit is consistent with the assumptions used in the analysis of these accidents.
The 10 GPM IDENTIFIED LEAKAGE limitation provides allowance for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage cetection systems.
The CONTROLLED LEAKAGE limit cf 10 GPM restricts operation with a total RCS leakage from all RC pump seals in excess of 10 GPM.
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