ML20114D903
| ML20114D903 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/03/1992 |
| From: | CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20114D898 | List: |
| References | |
| NUDOCS 9209100148 | |
| Download: ML20114D903 (11) | |
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License Humber NPF-3 Scrial Number 2050 Attachment Page 12
. REACTOR COOLANT SYSTEM STE AM ' GENE RATORS i
L!MITING CONDIT!DN FOR OPERATION
- .4.: :..: ne.. ;enerat;c snell ;e 07:=L: mita a w ter level betwe m
- b u..-E
- o. w IN SERT NE W T. S.
3.4. 5' LIM IT IN G COND ITION Fo8.
.m..-.
xa,,.., a RATION, AS ATTACRED
'n'ith one or more steam generators inocerable due to steam a.
- enerator tube imperfections, restore the inoperable generator (s) to OPERABLE status prior to increasing T,yg above 200*F b.
Oth cne or more steam generators inoperable due to the water level reing outside the limits, ce in at least HOT STANDBY althin 6 nours and in COLD SHUTDOWN witnin the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.5.0 Eacn steam generator snall be cemonstrated OPERABLE by perfonnance Of tne fcilowing augmented inservice inspection orogram and the requirements Of 5:e:1fi:stion 4.0.5.
4.4.5.1 Steam Generator Samole-Selection and Insoettien - Eacn steam generator shall be ceternnned OPERAdLE cur 1nc shutdown by wiecting anc insce: tin; at least the minimum numoer of steam generators specified in Table 4 4.1.
4.4.5.2 Steam Generator Tube Samole Select 1:n and Inspection - The steam cenerator tu e mnimum sample size, inspecticn result classification, and lhe corresconoing action required shall be as specified in Table 4.4-2.
Tne inservice inspection of steam generator tubes shall be perfomed at the frecuentfes 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.
- i he tubes selected for each inservice inspection shall include at least 3%
Tof the total number of tubes in all steam generators; the tubes selected for j :these inspections shall be selected on a rancom basis except:
a.
The first sample inspection during each inservice inspection (subsequent to the baseline inspection) of each steam generator snall in:lude:
1.
All tubes or tube sleeves that previously had detectable wall penetrations (> 20%) that have not been plugged or repaired by sleeving in the affected area.
2.
At least 50% of the tubes inspected shall be in tnose areas where experience nas incicat 4 potential problems.
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Docket Number 50-346 License Number NPF-3 Serial Number 2050 At.tachment Page 13 New TS 3.4.5 Limiting Condition for Operation 3.4.5 Each Steam Generator shall be OPERABLE vith a minimum vater level of 18 inches and the maximum specified belov as applicable MODES 1 and 2:
- a. The acceptable operating region of Figure 3.4-5.
H0DE 3:
- b. 50 inches Startup Range with the SFRCS Lov Pressure Trip bypassed and one or both Main Feedvater Pump (s) capable of supplying Feedvater to any Steam Generator,
- c. 96 percent Operate Range with:
- 1. The SFRCS Lov Pressure Trip active.
Or
- 2. The SFRCS Lov Pressure Trip bypassed and both Main Feedvater Pumps incapable of supplying Feedvater to the Steam Generators.
MODE 4:
- d. 625 inches Full Range Level APPLICABILITY:
MODES 1,2,3, and 4, as above.
- ~. _. - - -... -. ~ -
.-.. =. -..
Docket Nuuber 50-346 License Number 14PF-3 Serial Number 2050 Attachment Page 14 Figure 3.4 5 Maximum Allowable Steam Generator Level in H0 DES 1 and 2 t
100 -
(43,96)
T.$
i 1
I 90 -
M 85 80 -
Unacceptable Operating 3
Region 2
Z, 70 -
2 be 3
e$ 60 -
5 Acceptable Ope ra ting 5
Region 3 50 -
- n (0,43) 40 -
1 I
I I
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0 10 20 30.
40 50 60 Main Steam Superheat (oF) i NEW [*igue, 3,4-5 To as insenTso.
AS NEW PAGE 3/4 4-6 m l
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Docket Number 50-346 1.icense Number NPF-3
'"$',m'3*'" 2lc1 p coouy7 sysy 3 FOR INFORMATION ONLY ParJe 15 SURl'EILI.ANCE REOUIREMENTS (Continued) 3.
A tube inspection (pursuant to Specification 4.4.5.4.a.8) shell be performed on each selected tube.
If any selected tube does not petuit 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 I
inspection.
b.
Tubes in the following groups may be excluded from the first random sample if all tubes in a group in both steam generators are inspected. No credit will be taken for these tubes in meeting minimum sample size requirements.
1.
Group A-1: Tubes within one, two or three rows of the open inspection lane.
2.
Group A-2: Tubes having a drilled opening in the 15th support plate.
3.
Group A-3: Tubes included in the rectangle bounded bf rows 62 and 90 and by tubes 58 and 76, excluding tubes included in Group A-1.*
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 less than a full 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:
Cate gry Inspection Kesults 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 FOR INFORMATION ONLY McEvfi"*P"'*d*"""'
Tubes in Group A-3 shall not be excluded after completion of the fifth refueling outage.
3/447 Amendment No. 44,113
. DAVIS-BESS M IT 1_
Docket Number 50-346 License N6mber NPT-3 Serial Ntymber 2050 O's'"' REACTOR' C00MNT SYSTEM FOR INFORMATION ONLY St*RVEILI ANCE REQUIREMENTS (Continued)
Notes:
(1)
In all inspections, previously degraded tubes must exhibit significant (> 107.) further wall penetrations to be included in the above percentage calculations.
'l (2) Where special inspections are performed pursuant to
'l 4.4.5.2.b, defective or degraded tubes found as a result of the inspection shall be included in i
determining the Inspection Results Category for that special inspection but need not be included in 4
determining the Inspection Results Category for the
- j general steam generator inspection.
4.4.5.3 Insoection Frequencies - The above required inservice inspections of steam generator tubes snall be performed at the following frequencies:
j The baseline inspection shall be performed to coincide with the
,l a.
first scheduled refueling outage but no later than April 30, 1980.
i ij j~
Subsequent inservice inspections shall be performed at intervals j
of not less than 12 nor more than 24 calendar -conths af ter the l
previous inspection.
If the results of two consecutive inspec-tions for a given group
- of tubes following service under all I
volatile treatment (AVT) conditions fall 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 for that group may be extended to a maximum of 40 months.
l b.
If the results of the inservice inspection of a steam _ generator 1,
performed in accordance with Table 4.4-2 at 40 month intervals
!l for a given group
- of tubes fall in Category C-3, subsequent inservice inspections shall be performed at intervals -of not less than 10 nor more than 20 calendar months after_the previous inspection. The increase in inspection frequency shall apply l
until a subsequent inspection meets the conditions specified in i
4.4.5.3a and the interval can be extended to 40 months.
I I
Additional, unscheduled inservice inspections shall be l
c.
performed on each steam generator in accordance with the first i
sample inspection specified in Table 4.4-2 during the shutdown subsequent to anf of the following conditions:
1.
Primary-to-secondary tube leaks (not including leaks originating from tube-to tube sheet welds) in excess of the limits of Specification 3.4.6.2.
i
- A group of tubes means:
(a) All tubes inspected pursuant to 4.4.5.2.b, or (b) All tubes in a steam generator less those inspected pursuant to 4.4.5.2.b.
FOR INFORMATION ONLY DAVIS-BESSE, UNIT 1 JM 4-8 Amendment No. 21
Docket Number 50-346
]
License Number NPF 3 Scrial Number 2050
- ""Oy !
FOR INFORMATION ONLY a
.;REACTDR COOLANT SYS; A l50RVEILLANCEREQUIREMENTS._(Continued]
i1 II 2.
A seismic occurrence greater than the vyerating Basis Earthquake.
ll 3.
A loss-of-coolant accident requiring actuation of the jl engineered safeguards.
4 A main steam line or feedwater line break.
)
I d.
The provisions of Specification 4.0.2 are not applicable.
l1.4.4.5.4 Acceptance Criteria a.
As used in this Specification:
1.
Tubino or Tube, means that portion of the tue or tube sleeve which forms the primary system to secondary system boundary.
2.
Imperfection means an exception to the dimensions, finish or l
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.
3.
Degradation means a service-induced cracking. wastage, wear i
or general corrosion occurring on eithe;' inside or outside of a tube.
4.
Dearaded Tube means a tube containing imperfections > 20'a of the nominal wall thickness caused by degradation that has not been repaired by sleeving in the affected area.
5.
Degracation means the percentage of the tube wall thickness affectec or removed by degradation.
6.
Defect ~.eans an imperfection of such severity that
- exceeds tne repair limit. A defective tube is a tube containing a defect that has not been repaired by sleeving in the affected area or a sleeved tu'>e that has a defect in the-sleeve.
7.
Repair limit means the imperfection depth at or beyond which tne tube shall be rf: moved from service by plugging or repaired by sleeving in the affected area because it may become unservice-l able prior to the next inspect'>n and is equal to 40% of the nominal tube wall thickness. The Babcock and Wilcox process described in Topical Report BAW-2120P will be used for sleeving.
8.
Unserviceable describes the condition of a tube if it leaks or l
contains a defect large enough to affect its structural integ-rity in the event of an Operating Basis Earthquake. a loss-of-coolant accident, or a steam line or feedwater line break as-specified in 4.4.3.3.c. above.
ll 9.
Tube Inspection neans an inspection of the steam generator l
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tube from the point of entry completely to the point of exit, i
DAVIS-BESSE. UNIT 1 3/4 4-9 Amendment No. 27,171 FOR INFORMATION ONLY
Docket Number 50-346 License Number NPT-3 Serial Number 20$0 Attachment
~i v6 is FOR INFORMATION ONLY EEACTOR COOLANT SYSTEM 5;UEI,u ANCE REQUIREMENTS (Continveo) 10.
Preservice inspection means an inspection of the fuli lengtn of eacn tute in each steam generator perforreo by eddy current techniques prior to service to establish a baseline condition of the tubing.
This inspection shall be perfor ec prior to initial POWER OPERATION using the ecuipment and techniques expected to be used during subsequent inservice inspections.
i The steam generator shall be determined OPERABLE af ter completing the corresponding actions (plug or repair by sleeving in the affected areas all tubes exceeding the repair limit and all tubes
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c::ntaining through-wall cracks) required by Table 4.4-2.
S.O.3.5 Reports Following eacn inservice inspection of steam generator tutes, 5.
the number of tubes plugged in eacn steam generator shall be reported to the Commission within 15 days.
o.
The complete results of the stean generator tube inservice inspec' ion shall be submitted on an annual basis in a report for the period in whicn this inspection was completed. *nis 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 or sleeved.
c.
Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the Conmission 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.
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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 />.
i i
,4.4.5.7 Wh3n-steam generator tube inspection is performed as per Section 4.4.5.2, an additional but totally separate inspection shall be performed on special interest peripheral tubes in the vicinity of the secured interr.al auxiliary feedwater header. Thir, testing shall only be requirec on the steam generator selected for inspection, and the test snall require inspection only between FOR INFORMATION ONLY DAVIS-BESSE, UNIT 1 3/4 4-10 Amendment No. 3.27.62,171
Docket Number 50-346 License Number NPF-3 Serful Number 2050 E'N""'
FOR INFORMATION ONLY
'SURVEILCANCE REQUIREMENTS (Continued) l 4
the upper tube sheet and the lith tube support plate. The tubes
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selected for inspection shall represent the entire circumference l
of the steam generator and shall total at least 150 peripneral tubes.
4.4.5.8 Visual inspections of the secured internal auxiliary feeowater l
mR heeder, header to shroud attaCnsent welds, and the external header i
N8:
thermal sleeves shall be performed on each steam generator througn
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the auxiliary feedwater injection penetrations.
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These inspections shall be performw durino, the third ano fourth I
refueling outages and at the ten-year 151.
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FOR INFORMATION ONLY l
OAVIS-8E5SE, UNIT 1 3/4 4.104 keenement No. 62
Docket Number 50-346 License Number NPF-3 E,wrial N' umber 2050 anch-nt FOR INFORMATION ONLY Page 23
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Docket Number 50-346 License Humhcr NPF-3 Ser'ial Numbe. 2050 g.gegent OR INFORMATION ONLY
' REACTOR COOLANT SYSTEM BASES
?'4.4.0 PRESSURIZER A steam bubble in the pressurizer ensures that the RCS is not a hydraulically solio system and is capable of accormodating pressure surges during operation.
The steam bubble also protects the pressucizer code safety valves and pilot coerated relief valve against water relief.
Tne low level limit is based on providing enough water volume to prevent a reactor cvolant system low pressure condition that would actuate the Reactor Protection System or the Safety Feature Actuation System. The high level limit is based on providing enough steam volume to prevent a pressurizer high level as a result of any transient.
The pilot operated rel ef valve and steam Dubble function to relieve RCS
- ressure curing all design transients.
Operation of the pilot operated relief
.alve minimizes the uncesirable opening of the spring-loaded pressurizer code safety valves.
3/a.4.5 STEAM GENERATORS ine Surveillance Requirements for inspection of the steam generator tubes ensure tnat tne structural integrity M this portion of the RCS will be maintained.
The progran for inservice inspection of steam generator tubes de based on a mocification of Regulatory Guide 1.83, Revision 1.
Inservice in.. Stion of steam generator tubing is essential in order to maintain surveillance of the conoitions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice concitions tnat lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube cegradation so that corrective measures can be taken. A process equivalent to tne inspection method described in Topical Report BAW-2120P will be used for I
inservice inspection of steam generator tube sleeves. This inspection will l
orovice ensurance of RCS integrity.
Tne 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 It coolant chemistry is not maintained within these chemistry 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 j generator tube leakage between the primary coolant system and the secondary I
coolant system (primary-to-secondary leakage = 1 GPM). Cracks having a l
primary-to-secondary leakage less than this limit during operation will have j an adequate margin of safety to withstand the loads imposed during normal Il FOR INFORMATION ONLY t
DAVIS-BESSE, UNIT 1 B 3/4 4-2 Amenoment No. J35,'171 1
Docket Number 50-346 o
License Number NPF-3 Serial Number 2050 4
4 y
Attachment Pelge 23 i
REACTOR" COOLANT SYSTEM BASES (Continueo) operation anc by postulated accidents.
Operating plants have demonstrated nat primary-to-secondar, leakage of 1 GPM can be detected by monitoring the seconcary coolant.
Leakage in excess of this limit will require plant
'snutcown ano an unscheduled inspection, during which the loaking tubes will
' te located anc plugged or repaired by sleeving in the affected areas.
Wastage-type defects are unlikely with proper chemistry treatment of the
,seconcary coolant. However, even if a defect should develop in service, it will be founc during scheduled inservice steam generator tube examina-itions. As described in Topical Report BAW-2120P, degradation as small as 20% througn wall can be detected in all areas of a tube sleeve exc'ept for the roll expanced areas and the sleeve end, where the limit of detectability 4s 405 througn wall.
Tubes with imperfections exceeding the repair limit of 00', of tne nominal wall thickness will be plugged or repaired by sleeving i
- ne affe:te: areas. Davis-Besse will evaluate, and as appropriate implement,
- etter testing metnods wnich are developed and validated for commercial use so as to enaole detection of degracation as small as 207, througn wall without l
exceotion.
"ntil sucn time as 20*. penetration can be detected in the roll expanced areas anc the sleeve end, inspection results will be compared to those octained during tne baseline sleeved tube inspection.
' Wnenever tne results of any steam generator tubing inservice inspection fall into Category C-3, these results will be promptly reported to the Commission I
pursuant t; Specification 6.9.1 prior to resumption of plant coeration.
Such cases will be consicered by tne Commission on a case-by-case casis and may result in a requirement for analysis, laboratory examinations, tests, accitional sady-current inspection, and revision of the Technical Specifica-tions, if necessary.
'he steam cenerator -
.er level limits _ary conshth the i itial 3s_su Dt_ ion in the M. Under Mode 3, examples of Main Feedwater Pumps that are incapable of supplying feedwater to the steam generators are tripped a
pumps, or a manual valve closed in the discharge flow path, li h
l DAVIS-BESSE, UNIT 1 B 3/4 4-3 Amencment No.171
-.