ML18094A738
| ML18094A738 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/13/1989 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18094A737 | List: |
| References | |
| NUDOCS 8910060283 | |
| Download: ML18094A738 (14) | |
Text
ATTACHMENT 2 TECHNICAL SPECIFICATION
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REACTOR COOLANT SYSTEM STEAM GENERATORS LIMITING CONDITION FO~ 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 Tavg above 200°F.
SURVEILLANCE REQUIREMENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the require- -
ments of Specification 4.0.5.
4.4.5.1 Steam Generator Samale Selection and Inspection - Each steam generator shall be determine OPERABLE during shutdown &y selecting and inspecting at least the*minimum number of steam generators specified in Table 4.4-1.
4.4.5.2 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 spec1fied in Table 4.4-2.
The inservice inspection of steam generator tubes shall be performed at the frequencies s,pecified 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 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 50% of the tubes inspected shall be from these critical areas.
- b.
The first inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
- 1.
All nonplugged tubes that previously had detectable wall penetrations (>20%),*and SALEM - UNIT 1 3/4 4-7
- e.
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
Tubes in those areas where experience has indicated potential problems.
The results of each sample inspection shall.be classified into one of the following three categories:
Category
- Inspection Results C-1 Less thcrn 5'% of the to ta 1 tubes i nspcc:ted are degr~ded tubes and none of the inspected tube~ ar.:: dc*l'E":ct i Vf;.
C-2 One or more tubes, but not 111ore than *l :~ of the total tubes inspected are defective, or between 5% and 10% of the total tubes i nsper.tf.d are *de9r-aded tube~.
C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
Note:
In all inspections~ previously degraded tubes must exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations.
4.4.5.3 Inspection Frequencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:
- a.
The first inservice inspection shall be performed after 6 Effective 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 consecu-tive inspections following service under AVT conditions, not including the preservice inspection, 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.
SALEM - UN IT 1 3/4 4-8
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
- b.
ervice inspection o a steam generator conducted in
~EF~~
ccordance w 4.4-2 requir"es a third sample inspection WlT'°'
hose results fall in a
-3, the inspection frequency ttJSERT hall be reduced to at least once pe ths.
The reduction C.. ~
- n inspection frequenc~ shall app~y unti~ a :u
- nspectio
- c.
Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions.
- 1.
Primary-to-secoriciai'Y tubes leaks (not iricluding leaks originating from tube-to-tube sheet welds) fo"excess... _of the limits of Specification 3~4.6.2,
- * *~
- 2.
- A seismic occurr!:!ilCS: g;-eat~r t!ia.n tl1c Opc~r".tira(j Basis Earthquake,
- 3.
A loss-of-coolant accident requiring ac~uation of the engineered safeguards, or
- 4.
A main steam line *or feEdwater line brea.k.
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 by fabrication drawings or specifications.
Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
- 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 con ta i ni ng imperfecti ans ~20~~
01 the nominal wall thickness caused by degradation.
- 4.
% Degradation means the percentage of the tube wall thickness affected or removed by degradation.
SALEM - UNIT 1 3/4 4-9
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
- 5.
- 6.
- 7.
Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.
~tlo~oes-n&t;>em+t~
of.....t--he-edd¥-e~M:~Wispec:~t4'6n.;>r~ha-14-be--eeemed-e
~
Pluggin~ Limit means the imperfection depth at or beyond which t e tube sha 11 be removed from service because-rt..,
ma~ec-01rrp~-e pr'io~~
and is equal to 40% of the nominal tube wall thickness.
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.
Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
- 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.
4.4.5.5 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 within 15 days.
- b.
The complete results of the steam generator tube inservice inspection shall be included in the Annual Operating Report for the period in which th.irS inspection was completed.
This report shall include:
t"1e
- 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.
SALEM :. UNIT l 3/4 4-10
_j
- . _)
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\\,.: __ ~
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
- c.
Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the Commission
- shall be reported pursuant to Specification 6.9.l prior to resumption of plant operation.
The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation an9 corrective measures taken to prevent recurrence.
SALEM - UNIT 1 3/4 4-11
'J:tJSE:RTS "to LC.R 88-09 3~ A tube inspection (pursuant to Specification 4.4.5.4.a.8) 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 a partial tube inspection provided:
- 1. The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with.imperfections were previously found.
- 2.
The inspections include those portions of the tubes where imperfections were previously found.
- b.
If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40 month intervals fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months.
The increase in insp&tion frequency shall.apply until the subsequent inspections satisfy the criteria of Specificatf.on 4.4.5.3.a; the interval may then be extended to a maximum of once per
- 40 months.
- 9.
Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to sevice establish a baseline condition of the tubing. This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Co.ntinued)
- b.
4.4.6.5
- a.
- b.
- 9.
Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service establish a baseline condition of the* tubing.
This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
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.
Reports 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.
- AJe./ucM 1 ~ +hit. AAJAJ u11rl op.m.4-11;.Jtij 'Rt
- /J~A-r The completeJresults of the steam generator tube inservice inspection shall be re~tee eR aR aRRual bas.i.s for the period in which the inspection was completed.
This 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 inspe.ctions which fall into Category 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 cause of the tube degradation and corrective measures taken to prevent recurrence.
SALEM - UNIT 2 3/4 4-13
ATTACHMENT 3 TECHNICAL SPECIFICATION CORRECTED PAGES
REACTOR COOLANT S ~
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 Tavg above 200°F.
SURVEILLANCE REQUIREMENTS 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.
4.4.5.1 Steam Generator Sample Selection and Inspection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number. of steam generators specified in Table 4.4-1.
4.4.5.2 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 4.4-2.
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 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 50% of the tubes inspected shall be from these critical areas.
- b.
The first inservice inspection (subsequent to the preservice inspection) 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 potential problems.
- 3.
A tube inspection (pursuant to Specification 4.4.5.4.a.8) 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 for a tube inspection.
SALEM - UNIT 1 3/4 4-7
SURVEILLANCE REQUIREMENTS
- 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 a partial tube inspection provided:
- 1.
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.
- 2.
The inspections include those portions of the tubes where imperfections were previously found.
The results of each sample inspection shall be classified into one of the following three categories:
Category Inspection Results C-1 Less than 5% 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 1% of the total 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 degraded tubes ore more than 1% of the inspected tubes are defective.
Note:
In all inspections, previously degraded tubes must exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations.
4.4.5.3 Inspection Frequencies - The above required i~service inspections of steam generator tubes shall be performed at the following frequencies:
- a.
The first inservice inspection shall be performed after 6 Effective 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 AVT conditions, not including the preservice inspection, result in ~11 inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional has occurred, the inspection interval may be extended to a maximum of once per 40 months.
- b.
If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40 month intervals fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months.
The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 4.A.5.3.a; the interval may then be extended to a maximum of once per 40 months.
SALEM - UN IT 1 3/4 4-8
REACTOR COOLANT s*~
.. SURVEILLANCE REQUIREMENTS (Continued)
- c.
Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions.
- 1.
Primary-to-secondary tubes leaks (not including leaks originating 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 engineered 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 by fabrication drawings or specifications.
Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
- 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.
% 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 is defective.
- 6.
Plugging Limit means the imperfection depth at or beyond which the tube shall be removed from service 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 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 (hot leg side) completely around the LI-bend to the top support of the cold leg.
SALEM - UNIT 1 3/4 4-9
- SURVEILLANCE REQUIREMENTS (Continued)
- 9.
Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service establish a baseline condition of the tubing.
This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
- 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.
4.4.5.5 Reports
- a.
Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15 days.
- b.
The complete results of the steam generator tube inservice inspection shall be in the Annual Operating Report for the period in which the inspection was completed.
This 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 Category 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 to this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
SALEM -
UN IT 1 3/4 4-10
REACTOR COOLANT SYIM SURVEILLANCE REQUIREMENTS (Continued)
- b.
4.4.5.5
- a.
- b.
- 9.
Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service establish a baseline condition of the tubing.
This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
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.
Reports 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.
The complete results of the steam generator tube inservice inspection shall be included in the Annual Operating Report for the period in which the inspection was completed.
This 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 Category C-3 and require prompt notification of the Commission shall be reported pursuant to Specification 6.9.l prior to resumption of plant operation.
The written followup to this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
SALEM - UNIT 2 3/4 4-13