ML19345A512
| ML19345A512 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/30/1976 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19345A511 | List: |
| References | |
| NUDOCS 8011240092 | |
| Download: ML19345A512 (11) | |
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IN EX
_IMITING* CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 5ECTION 3/4.4.6 CHEMISTRY............................................
3/4 4-12 3/4.4.7 SPECIFIC ACTIVITY....................................
3/4 4-15 3/4.4.8 PRESSURE / TEMPERATURE LIMITS Mair. Coolant System..................................
3/4 4-19 Pressurizer..........................................
3/4 4-25 3/4.4.9 STRUCTURAL INTEGRITY.................................
3/4 4-26 3/4.4.10 STEAM GENERATORS.....................................
3/4 4-32 3/4. 5 EMERGENCY CORE COOLING SYSTEM (ECCS) 3/4. 5.1 ACCUMULATOR..........................................
3/4 6 3/4.5.2 ECCS SUBSYSTEMS......................................
3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS......................................
3/4 5-9 3/4.5.4 SAFETY INJECTION TANK................................
3/4 5-11 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity................................
3/4 6-1 Containment Leakage..................................
3/4 6-2 Co nta i nme n t Ai r Loc k................................. 3/46-4 Internal Pressure....................................
3/4 6-5 Air Temperature......................................
3/4 6-6 Containment Vessel Structural Integrity..............
3/4 6-7 Continuous Leak Monitoring System.................... 3/4 6-8 3/4.6.2 CONTAINMENT ISOLATION VALVES.........................
3/4 6-9 (ANKEE R0WE V
8 01124 0 09R
MAINCOOLANTSYS['
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BASES For normal opening and reclosing, the structural integrity of the Main Coolant System is unchanged. Therefore, satisfactory performance of a system leak test at 2200 psig following each opening and. subsequent reclosing is acceptable demonstration of the system's structural integrity. These leak tests will be conducted within the pressure-temperature limitations for Inservice Leak and Hydrostatic Testing of Figure 3.4-4 and 3.4-5.
3.4.4.10 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the MCS will be maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection cf steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is i
evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.
In-service inspection of steam generator tubing also provides a means of characterizing the nature and cuase of any tube degradation so that corrective measures can be taken.
The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes.
If the secondary coolant chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking. The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between primary coolant system and the secondary coolant system (primary-to-secondary leakage = 1 gallon per minute total leakage).
Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation. Operating plants have demonstrated that primary-to-secondary leakage of 1 gallon per minute total leakage can readily be detected by radiation monitors of steam generator blowdown.
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged.
Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant.
However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations.
Plugging will be required for all tubes with imperfections exceeding the plugging limit of 40 percent of the tube nominal wall thickness.
Steam l
generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20 percent of the original tube wall thickness.
Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be promptly reported to the Comission pursuant to Sepcification 6.9.4 prior to resumption of plant operation.
Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
YANKEE R0WE B3/4 4-12
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C MAIN COOLANT SYSTEM STEAM GENERATORS LIMITING CONDITIONS FOR OPERATION 3.4.10 Each steam generator in a non-isolated reactor coolant loop shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more steam generators in non-isolated main coolant loops a.
inoperable, restore the inoperable generator (s) to OPERABLE status prior to increasing T,yg above 200*F.
SURVEILLANCE REQUIREMENTS 4.4.10.1 Steam Generator Sample Selection and Inspection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting two steam generators as specified in Table 4.4-4.
4.4.10.2 Steam Generator Tube Sample Selection and Inspection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-5.
The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.10.3 and the inspected tubes shall be verified acceptable per the accep-tance criteria of Specification 4.4.10.4.
The tubes selected for each inservice inspection shall include at least 3 percent of the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
Where experience in similar plants with similar water chemistry a.
indicates critical areas to be inspected, then at least 50 percent of the tubes inspected shall be from these critical areas.
b.
The second inservice inspection (subsequent to the first inspection) of each steam generator shall include:
1.
All nonplugged tubes that previously had detectable wall penetrations >20 percent, and 2.
Tubes in those areas where experience has indicated potential problems.
Subsequent inservice inspections should concentrate (by c.
selecting at least 50 percent of the tubes to be inspected) on those areas of the tube sheet array and on those portions of the tubes where tubes with imperfections were previously found.
YANKEE R0WE 3/4 4-32 t
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MAIN. COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
The results of each sample inspection shall be classified into one of the following three categories:
Ca tegory_
Inspection Results C-1 Less than 5 percent 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 3 tubes inspected are defective, or between 5 and 10 percent of the total tubes inspected are degraded tubes.
C-3 More than 10 percent of the total tubes inspected are degraded tubes or more than.
3 tubes are defective.
NOTE:
In all inspections, previously degraded tubes must exhibit significant (>10 percent) further wall penetrations to be included in the above percentage calculations.
4.4.10.3 Inspection Frequencies - The above required inservice inspections of steam generator tubes shall be perfonned at the following frequencies:
a.
Inservice inspections shall be performed at intervals or not less than 12 nor more than 24 calendar months subject to the following:
If two consecutive inspections result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.
b.
If the inservice inspection of a steam generator conducted in accordance with Table 4.4-5 requires a third 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 subsequer.t inspection demonstrates that a third sample inspection is not required.
c.
Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-5 during the shutdown subsequent to the following condition.
1.
Primary-to-secondary tubes leaks (not inc!uding leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.5.2.
YANKEE R0WE 3/4 4-33
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MAIN. COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.10.4 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 percent of the nominal tube wall thickness, if detectable, may be considered as imperfection.
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 percent of the nominal wall thickness caused by degradation.
4.
% Degradation means the percentage of the bbe wall thick-ness affected or removed by degradation.
5.
Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective. Any tube which does not permit the passage of the eddy-current inspection probe shall be deemed a defective tube.
6.
Plugging Limit means the imperfection depth at or beyond which the tube shall be removed from service because it may become unserviceable prior to the next inspection and is equal to 40 percent of the nominal tube wall thickness.
7.
Unserviceable describes the condition of a tube if it leaks.
8.
Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) past the top (fifth) support.
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-wal'I'; racks) required by Table 4.4-5.
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4.4.10.5 Reports a.
Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Comission in a Special Report pursuant to Specification 6.9.6 within 15 days.
b.
The complete result of the steam generator tube inservice inspection shall be included in the Annual Operating Report, pursuant to Specification 6.9.2, for the period in which this inspection was completed. - This report shall include:
YANKEE R0WE 3/4 4-34
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MAIN. COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 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 Category C-3 and require prompt notification of the Consnission shall be reported pursuant to Specification 6.9.4 prior to resumption of plant operation. The written follow-up of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
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l YANKEE R0WE 3/4 4-35
c TABLE 4.4-4 7
MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED g'
DURING INSERVICE INSPECTION p
m
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- oe Preservice Inspection No m
No. of Steam Generators per Unit Four 4
i!P Inservice Inspection Two I
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'i TABLE 4.4-5
- lE STEAM GENERATOR TUBE INSPECTION 2
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_ J.f 1st SAMPLE INSPECTION 2nd SAMPLE INSPECTION 3rd SAMPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required A minimum of C-1 None N/A N/A N/A N/A P
S Tubes per S. G.
C-2 Plug defective tubes C-1 None N/A N/A and inspect additional Plug defective tubes C-1 None S tubes in this S. G.
C-2 and inspect additional C-2 Plug defective tubes S tubes in this S. G.
Perform action for g
C-3 C-3 result of first 1
a sample Perform action for k
C-3 C-3 result of first N/A N/A sample C-3 Inspect 2S additional tubes in this S.G.,
C-1 tione ti/A N/A and plug defective tubes C-2 Plug defective tubes O
and inspect additional N/A N/A Prcmpt notification S tubes in this S. G.
to NRC pursuant to specification 6.9.4 C-3 laspect all tubes in this S. G. and plug defective tubes.
N/A N/A Prompt notification to NRC pursuant to Specification 6.9.4 S = 6%
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ADMINISTRATIVE CONTROLS (5) A description of major ~ safety-related corrective main-tenance performed during the outage or power reduction, including the system and component involved and identi-fication of the critical path activity dictating the length of the outage or power reduction; and (6) A report of any single release of radioactivity or radiation exposure spe^ifically associated with the outage which accounts for more than 10% of the allowable annual values.
A tabulation on an annual basis of the number of station, c.
utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions. *** e.g.,
reactor operations and surveillance, inservice inspection, waste processing, and refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposure totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the whole body dose received from external sources shall be assigned to specific major work functions.
d.
Indications of failed fuel resulting from irradiated fuel examinations, including eddy current tests, ultrasonic tests, or visual examinations completed during the report period.
Complete results of steam generator inservice inspections e.
Specification 4.4.10.5.b 6.9.3 Monthly Operating Report. Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Office of Inspection and Enforcement, U.S. Nuclear Regulatory Comission, Washington, D.C. 20555, with a copy to the appropriate Regional Office, to arrive no later than the tenth of each month following the calendar month covered by the report.
rep 0RTABLE OCCURRENCES 5.9.4 REPORTABLE OCCURRENCES, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC.
Supplemental eports may be required to fully described final resolution of occurrence.
r In case of corrected or supplemental reports, a licensee event report hall be completed and reference shall be made to the original report s
date.
- This tabulation supplements the requirements of 520.407 of 10-CFR Part 20.
(ANKEE R0WE 6-16
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e ADMINISTRATIVE CONTROLS (d) Total dissolved gas radioactivity (in curies) and average concentration released to the unrestricted area.
(e) Total volume (in liters) of liquid waste released.
(f) Total volume (in liters) of dilution water used prior to release from the restricted area.
(g) Total gross radioactivity (in curies) by nuclide released based on representative isotopic analyses performed.
(h) Percent of Technical Specification limit for total radioactivity.
(3) Solid Wastes (a) The total amount of solid waste shipped (in cubic feet).
(b) The total estimated radioactivity (in curies) involved.
(c) Disposition including date and destination.
6.9.6 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicab' 2 reference specification:
a.
Inservice Inspection Program Reviews, Specification 4.4.9.1.
b.
ECCS Actuation, Specifications 3.5.2 and 3.5.3.
Inoperable Meteorological Monitoring Instrumentation, Specifi-c.
cation 3.3.3.3.
d.
Sealed Source leakage in excess of limits, Specification 4.7.6.3.
e.
Radioactive Solid Waste Disposal, Specification 3.7.9.1.
f.
Steam Generator Inservice Inspection Results, Specification 4.4.10.5 YANKEE R0WE 6-22