ML20078S438
| ML20078S438 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/20/1994 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20078S277 | List: |
| References | |
| NUDOCS 9412280303 | |
| Download: ML20078S438 (10) | |
Text
, c.
4 PROPOSED TECHNICAL SPECIFICATION CHANGES 9412280303 941220 PDR ADOCK 05000368 P
pg
REACTOR COOLANT SYSTEM 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 T above 200*F.
avg SURVEILLANCE REQUIREMENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspuction program and the requirements of Specification 4.0.5.
Note: The surveillance requirements of Specification 3.4.5 do not apply to the special steam generator tube inspection to be performed during the 2P95-1 outage scheduled to begin on January 6, 1995. The scope and expansion criteria for this inspection are specified in correspondence to the NRC submitted under separate cover. The scope and criteria shall be approved by the NRC prior to exiting Mode 5.
The results of this inspection shall be reviewed by the Plant Safety Committee prior to resumption of plant operation and reported to the NRC within 30 days of resumption of plant operation.
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.
I The inservice inspection of steam generator tubes shall be performed at the l
frequencies specified in specification 4.4.5.3 and the inspected tubes j
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 those inspections shall be selected on a random basis except:
I 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 sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
ARKANSAS - UNIT 2 3/4 4-6 Amendment No.
1
l i
SURVEILLANCE REQUIREMENTS (Continued) 1.
.All ncnplugged tubes that previously had detectable wall I
penetrations (>20%).
2.
Tubes in those areas where experience has indicated potential problems.
3.
A tube inspection (pursuant to Specification 4.4.5.4.a.9) l-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 s
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:
+
i 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 result of each sample inspection shall be classified into one to the following three categories: '
Category Inspection Results 1
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 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.
1 ARKANSAS - UNIT 2 3/4 4-7 Amendment No.
TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION l
AST 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 l
S Tubes per S.G.
C-2 Plug or sleeve defec-C-1 None N/A N/A tive tubes and inspect additional 2S tubes in Flug or sleeve defec-C-1 None this S.G.
C-2 tive tubes and inspect C-2 Plug or sleeve additional 45 tubes in defective tubes this S.G.
Perform action for C-3 C-3 result of first sample Perform action for C-3 C-3 result of first N/A N/A Sample C-3 Inspect all tubes in All other this S.G.,
plug or S.G.s are None N/A N/A sleeve defective tubes C-1 and inspect 2S tubes in each other S.G.
Some S.G.s Perform action for N/A N/A C-2 but no C-2 result of second additional sample Special Feport S.G.
are to NRC per C-3 Specification 6.9.2 Additional Inspect all tubes in S.G.
is C-3 each S.G.
and plug or sleeve defective tubes.
Special N/A N/A Report to NRC per Spec. 6.9.2.
So 3 N_ % Where N is the number of steam generators in the unit, and n is the number of steam generators inspected n
during an inspection ARKANSAS - UNIT 2 3/4 4-12 Amendment No. M,4-33,444
REACTOR COOLANT SYSTEM BASES Demonstration of the safety valves' lift setting will occur only during shutdown and will be performed in accordance with the 6
provisions of Section XI of the ASME Boiler and Pressure Vessel Code.
3/4.4.4 PRESSURIZER.
A steam bubble in the pressurizer ensures that the RCS is not a hydraulically solid system and is capable of accommodating pressure surges during operation. The steam bubble also protects the pressurizer code safety valves against water relief. The steam bubble functions to relieve RCS pressure during all design transients.
The requirement that 150 KW of pressurizer heaters and their i
associated controls be capable of being supplied electrical power from an emergency bus provides assurance that these heaters can be energized during a loss-of-offsite power condltion to maintain natural circulation at HOT STANDBY.
3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS 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 of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to l
design, manufacturing errors, or inservice conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause 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, j
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 the primary coolant system and the secondary coolant system (primary-to-secondary leakage
)
= 0.5 GPM per steam generator).
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 and by postulated accidents. Operating plants have demonstrated that i
primary-to-secondary leakage of 0.5 GPM per steam generator 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 or repaired.
l 4
ARKANSAS - UNIT 2 B3/4 4-2 Amendment No. 30,
MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS (FORINFORMATION ONLY)
ARKANSAS - UNIT 2 3/4 4-6 Amendment No.
REACTOR COOLANT SYSTEM STEAM GENERATORS i
LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.
APPLICAB7LITY: MODES 1,2, 3 and 4.
ACTION:
With one or more steam generators inoperable, restore the inoperable f
above 200*F.
generator (s) to OPERABLE status prior to increasing Tavg SURVEILLANCE REQUIREMENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice ir.spection program and the requirements of Specification 4.0.5.
Note: The surveillance reauirements of Soecification 3.4.5 do not apolv to the special steam cenerator tube inspection to be performed durino the 2P95-1 outace scheduled to becin on Januarv 6.
1995.
The scope and expansion criteria for this insge,etion are specified in correspondence to the NRC submitted under separate cover. The scope and criteria shall be approved by the NRC orior to exitino Mode 5.
The results of this inspection shall be reviewed by the Plant Safety Committee oriog to resumption of plant operation and reported to the NRC within 30 days of resumption of plant operation.
I 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 sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
ARKANSAS - UNIT 2 3/4 4-6 Amendment No.
~#'
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 1.
All nonplugged tubes that previously had detectable wall
- penetrations. (>20%).
2.
Tubes in those areas where experience has indicated potential problema.
3.
A tube inspection (pursuant to Specification 4.4.5.4.a.89) l 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.
i-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.
J The result of each sample inspection shall be classified into one to the following three categories:
I Category Inspection Results C-1 Less than 5% of the total tubes inspected I
I are degraded tubes and none of the inspected tubes are defective.
j 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 or more than 1% of the inspected tubes are defective.
Note:
In all inspections, previously degraded tubes must i
exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations.
J ARKANSAS - UNIT 2 3/4 4-7 Amendment No.
TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION
-lI AST 3 AMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required A mininmum of C-1 None N/A N/A N/A N/A -
l S Tubes per S.G.
C-2 Plug or sleeve defec-C-1 None N/A N/A tive tubes and inspect additional 2S tubes in Plug or sleeve tiefec-C-1 None this S.G.
C-2 tive tubes and inspect C-2 Plug or sleeve additional 4S tubes in defective tubes this S.G.
Perform action for C-3 C-3 result of first sample Perform action for C-3 C-3 result of first N/A N/A Sample C-3 Inspect all tubes in All other this S.G.,
plug or S.G.s are None N/A N/A sleeve defective tubes C-1 and inspect 25 tubes in each other S.G.
Some S.G.s Perform action for N/A N/A C-2 but no C-2 result of second additional sample Special Report S.G. are to NRC per C-3 Specification 6.9.2 Additional Inspect all tubes in S.G.
is C-3 each S.G. and plug or sleeve defective tubes. Special N/A N/A Report to NRC per Spec. 6.9.2.
S = 3 N % Where N is the number of steam generators in the unit, and n is the number of steam generators inspected n
during an inspection
+*
~ 'S' Stcc-Ccac ctc
. cac ti=c cnc;ptic tc th: C 3 incpcctica rcquir;-.cnt: hcc Sccn g cntcd fc th 2n? incpceticn cf tuic: 29 SE cnd 37 57 fc thc pcricd cf '!c;cric 27, 1992 thccugh May 30, 1903.
ARKANSAS - UNIT 2 3/4 4-12 Amendment No. M,443,443
9 REACTOR COOLANT SYSTEM BASES Demonstration of the safety valves' lift setting will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Vessel Code.
3/4.4.4 PRESSURIZER A steam bubble in the pressurizer ensures that the RCS is not a hydraulically solid system and is capable of accommodating pressure surges during operation. The steam bubble also protects the pressurizer code safety valves'against water relief. The steam bubble functions to relieve RCS pressure during all design transients.
The requirement that 150 KW of pressurizer heaters and their associated contrels be capable of being supplied electrical power from an emergency bus provides assurance that these heaters can be energized during a loss-of-offsite power condition to maintain natural circulation at HOT STANDBY.
3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS 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 of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause 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 the primary coolant system and the seconc34ry coolant system (primary-to-secondary leakage
= 0.5 GPM per steam generator).
Cracks having a primary-to-secondary leakage less than this lixit durina operation will have an adequate margin of safety to withstand the loads imposed during normal opera tion and by postulated accidents. Operating plants have demonstrated that primary-to-secondary leakage of 0.5 GPM per steam generator 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 _or repaired.