ML20037A458
| ML20037A458 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/01/1976 |
| From: | BABCOCK & WILCOX CO. |
| To: | |
| Shared Package | |
| ML20037A457 | List: |
| References | |
| NUDOCS 8001310528 | |
| Download: ML20037A458 (10) | |
Text
ENCL 05URClJ STANDARD TECHNICAL SPECIFICATIONS REACTOR COOLA*.tT SYSTEM STEAM GENERATORS
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i LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE with a water level between
(
) and ( ) inches.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more steam generators inoperable due to steam a.
generator tube imperfections, restore the inoperable generator (s) to OPERABLE status prior to increasing T,yg above 200*F.
b.
With one or mors steam generators inoperable due to the water level being outside the limits, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />,
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SURVEILLANCE REQUIREMENTSW *~
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4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements.
of Specification 4.0.5.
i 4.4.5.1.. Steam Generator Sample Selection and Inspection - Each steam generator shall be determined OPERABLE during shutdown by selecting and 4
inspecting at least the minimum number of steam generators specified in Table 4.4-1.
Steam Generator Tube Samole Selection and Insoection - The steam 4.4.5.2 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 inspection shall include at least 3%
of the total number of tubes in all steam generators; the tubes selected for these in:pections shall be selected on a random basis except:
l Where experience in similar plants with similar water chemistry f
a.
indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.
t S&W-STS 3/4 4-6 June 1,1976 x
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REACTOR COOLANT SYSTE
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'y SURVEILLANCEREQUIREMENTS3 Cont'inued)i 4
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The first sampla inspesii6n.duSing each inservice inspection
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b.
(subsequenttothepreserviceinspection)dfeachsteam
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s generator shall.. include:
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All nonplugged.. tubes thnt previously had' detectable wall 3
y 1.
penetrations (>IX),and Tobes in those areas where experience has indicated poten-s~
2.
. ttal problems?
The second and thi.-d sar.p,le inspection during each inservice 1
inspection as requirgd.by Table 4.4-2 may be less than a full c.
tube inspection' by concentrating the inspection on those areas of the tube sheet arra/ and on those portions of the tubes wheref tubes witiqiiverfect,ipns were previously found, y
The tube inspection'shs)1, be' conducted according to 4.4.5.4.a.8.
d.
If the tube doe!i rot p'ermitspMege of the eddy current in-.
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spection probe the entire, length of the' tube.this.shall be rec 9eded and an adjacent tubehshall b'e selected. '. Tubes which.-
do no't permit the passage of the eddy current probe will be-considered as degraded tubes when classifying inspection results.
The results of each : ample inspection shall be classified into one of U
the following three categories:
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Inspection Results
(-
y_tig,ori t
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? '< ~ Less than 5% of the total tubes inspected C-1
.t are degraded tubes and none of the inspected
, tubes are defective.
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One er more tubes, but cot more than 15 of C-2 the total tubes inspected are dnfective, or between 5% and 10% of the total tubes I'
H inspected are degraded tubes.
f Here than 10% of the total tubes inspected C4 are degraded tubes or more then 15 of the tnspected tur,es are defective.
i In all impections, previously degraded tubes must Note:
exMbit sisntficant.4105). further wall penetrations to-be inchded in the above percentage calculations.
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i REACTOR COOLANT SYSTEM URVEILLANCE REQUIREMENTS (Continued)
S Inspection Frequencies - The above required inservice inspections
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of steam senerator tubes shall be perforned at the followl.ng frequenci 4,4,5,3 e
The first inservice inspection shall be performed after 6 a.
Effective Full Power Months but within 24 calendar mo initial criticality.
pertonned at intervals of not less than 12 nor more than 24-If two consecu-calendar months after the previous inspection.
tive inspections following service under AVT co results falling into the C-1 category or if two consecutive i
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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 onct per 40 months.
conductedtin accordance with Table 4.4-2 at 4 b.
fall in Category C-3, the insepetion frequency shall be in-The increase in creased to at least once per 20 months.
meets the conditions specified in 4.4.S.3.a an t
j can be extended to a 40 month period.
Additional, unscheduled inservice inspections shall be perfonned
-on each steam generator in accordance with the first sample c.
inspection specified in Table 4.4-2 during the shutdown subsequen to any cf the following conditions.
Primary-to-secondary tubes leaks (not including laaks criginating from tube-to tube sheet welds) in excess of 1.
, the limits of Specification 3.4.6.2, A seismic occurrence greater than the Operating Basis 2.
Earthquake, A loss-of-coolant accident requiring actuation of the 3.
engineered safeguards, or l
A main steam line or feedwater line break.
4.
k June 1,1976 3/4 4-8 I'i 1
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1 I! REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acceptance Criteria As used in this Specification:
a.
Imperfection _means an exception to the dimensions, finish 1.
or contour of a tube from that required by fabrication Eddy-current testing indications drawings or specifications.
Below 20% of the nominal tube wall thickness, if detectable, may b'e considered as imperfections.
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2.
Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
- 3. 1 Degraded Tube means a tube containing imperfections >20%
of the nominal wall thickness caused by degradation.
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- 4. t % Degradation means the percentage of the tube wall thickness affected or removed by degradation.
5.
Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect l
is defective.
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 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 structural 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.
8.
Tube Inspection means an inspection of the steam generator tube from the point of entry comfletely to the point of 1
l er.i t.
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3/4 4-9 June 1, 1976 i+
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1' URVEILLANCE REQUIREMENTS (Continued)
S 9.
Preservice Inspection is a 100% tube inspection performed on each tube in every steam generator by eddy current or alternative techniques prior to service to establish a base line condition of the tubing. This inspection should be performed preferably after the field hydrostatic -
test and prior to initial plant start up.
Such inspections should be conducted under conditions and with equipment and techniques equivalent to those expected to be employed during subsequent inservice inspections.
The steam generator shall be detemined OPERABLE after completing 3
b.
the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by a
Table 4.4-2 B
4.4.5.5 Reports ing each inservice inspection of steam generator tubes, the b
Foll msnber of tubes plugged in each steam generator shall be reported a.
to the Commission within 15 days.
The complete results of the steam generator tube inservice b.
inspection shall be included in the Annual Operating Report for the period in which this inspection was conpleted. This report 4 -
shall include:
i 1.
Number and extent of tubes inspected.
l Location and percent of wall-thickness penetration for 2.
each indication of an imperfection.
l Identification of tubes plugged.
3.
Results of steam generator tube inspections which fall into Category C-3 and require prompt notificction of the Commission c.
shall be reported pursuant to Specification 6.9.1 prior to The written followup of this resumption of plant operation.
i report shall provide a description of investigations conducted l
to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
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June 1, 1976 3/4 4-10 I
B&W-STS
t gREACTORCOOLANTSYSTEM SURVEILLANCE REQUIREMENTS (Contir.ued) 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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TABLE 4.4-1 1
1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION 1
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Yes No Preservice inspection Two Three Four Two Three Four No. of Steem Generators per Unit I
w All One Two
.Two 5
First inservice Inspection I
t 2
3 One One One One Second & Subsequent inservice Inspections Table Notation;
- 1. The laservice inspection eney be limited to one steem generator on a rotating' schedule enc h
(where N is the number of steem generators in the plent) if the results of the first or previous ins i
ditions in all steem generators are performing in a like menner. Note that under some circumstances, the operat ng con Under such circum-one or more steem generefors may be found to be more severe than those in other steem generators.
stances the semple sequence shell be modified to inspect the most severe conditions.
- 2. The other steem generator not inspected during the first inservice Inspection shall be inspected.
inspections should follow the instructions described in 1 ebove.
- 3. Each of the other two steem generators not inspected during the first inservice inspections shel g
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ibed in 1 aoove.
- s second and third Inspections. The fourth and subsequent inspections shall follow the instruct ons escr i
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l I REACTOP COOLANT SYSTEM _
l BASES 3/4.4.4 PRESSURIZER _
A steam bubble in the pressurizer ensures that the RCS is not a ydraulically solid system and is capable of accomodating pressureThe h
urges during operation.
code safety valves and power operated relief valves against water relief.
s The low level limit is based on providing enough water volume to prevent a pressurizer low level or a reactor coolant system low pressure condition that would actuate the Reactor Protection System or the t
Engineered Safety Feature Actuation Systen as a result of.a to prevent a pressurizer high level as a result of any transient.
The power operated relief valves and steam bubble function to Operation of the relieve RCS pressure during all design transients.
power operated relief valves minimizes the undesirable opening of the h,
spring-loaded pressurizer code safety valves.
3/4.4.5 STEAM GENERATORS 5
The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the b
4 will be maintained. tubes is based on a modification of Regulatory Guide 1.
Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event t l
there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that le a means of characterizing the nature and cause of any tube degradation corrosion.
I 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 If the to result in negligible corrosion of the steam generator tubes.
secondary coolant chemistry is not maintained within The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the primary coolant
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system and the secondary coolant system (primary-to-secondary 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
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i June 1, 1976 B 3/4 4-2
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BASES imposed during normal operation and by postulated accidents. Operating l
plants have demonstrated that primary-to-secondary leakage of 1 GFM 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.
Wastage-type defects are unlikely with proper chemistry the 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 of the tube nomin' l wall a
i thickness. Steam generator tube inspections 5T~ 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 steam 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 operation. Such cases will be considered by.the Commission on a C-case-by-case basis and may result in a requirement for analysis, labora-tory examinations, tests, additional edd-current inspection, and re-vision of the Technical Specifications, if necessary.
The steam generator water level limits are consistent with the initial assumptions in the FSAR.
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i B&W-STS B 3/4 4-3 June 1, 1976 1
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