ML20101K418
| ML20101K418 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/19/1992 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20101K420 | List: |
| References | |
| NUDOCS 9207020259 | |
| Download: ML20101K418 (20) | |
Text
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UNITED STATES n
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NUCLEAR HEGULATORY COMMISSION o
W ASHINGTON. D C 208/A
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EEQ!LC] A POWER COMPANY
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QSLLIRQRPE 90WER CORPORATION he tM(JCIPAL ELECTRIC A'JTHORITY OF GEORGB
.(ITY OF DALTON. GEORGB DOCKET NO. 5042l EDWIN 1. HATCH _NVC1 EAR PLANT. UNIT 1 NiEt!DMENT TO FA_Oll,lTY OPERATING LICENSE Amendment No.181 L.,
License No. DPR-57 1.
Tne Nuclear Regulatory commission (the Commission) has found that:
a A.
The appilcation for amendment to ti e Edwin 1. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-57 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporatien, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated July 11, 1991, as supplemented February 20, 1952, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of tha Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this ammidment can be cot.'ucted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the connon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements t -
have been satisfied.
9207020259 920619 PDR ADOCK 05000321 P
. 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license an.endiaent, and paragraph 2.C.(2) of f acility %erating License No. flPF-5 is hereby amended to read as follows:
Twh?.1 fL1_.50ecifications 1
!he Technical Specifications contained in Appendix A and B, as revised through Amendment No.122, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 60 days from its date of j
issuance.
FOR_THE NUCLEAR REGULATORY COMMISSION l) }6 fj vid B. Matthews, Director
{
Division of Reactor Projects - 1/11 Project Directorate 11-3 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
June 19, 1992 r
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ATTACHMENT TO LICENSE AMENQ11ENT NO.181 FACILITYJPERATING LICENSE N0. OPR-11 DOCKET NO. 50-321 AllQ TO LICENSE AMENDMENT NO.122.
FACILITY OPERATING LICENSE NO. NPF-5 i
DOCKET NO. 50-366 Replace the following pages of the Appendix "A" Technical Specifications with -
the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paaes Insert Paaes Unit 1 iv iv 1x ix 3.6-10a 3.6-10a 3.6-10b 3.6-10b 3.6-10e 3.6-10c 3.6-10d 3.6-10d 3.6-10e 3.6-10f Unit 2 3/4 7-11 3/4 7-11 3/4 7-12 3/4 7-12 3/4 7 3/4 7-13
-3/4 7-14 3/4 7-14 3/4 7-15 3/4 7-15 3/4 7-16 3/4 7-16 3/4 7-17 3/4 7-17
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M t Mn fect M9 Ent t!MITI M Cc'Ol'10NS 500 05ELMiri ScRVE ltL ANC E E0.'!s t MTt s 3.6.
CRIMARf $15 TEM BOVNDARY 4.6.
PRIMARY SYSTEM $0VNDARY 3 6-1 A.
Reactor Coolant Heetup A.
Reactor _ Coolant Heatep 3.6 1 and Cooldoen and Cooldown B.
Reactor Vessel Temeerature B.
Deactor Vessel Temo-3.6 1 and Pressure erature and Pressure C.
Reatter Vessel Heaa 5tud C.
Peactor vessel Head 3.6 2 Tensioning
$tud Tensioning D.
Idle Recirculation Loop D.
! ale Recirculation 362 Startup Loop Startup E.
Reentulation Pup start E.
Rectreulation Pumo Start 3.6-3 f.
Reactcr Coolant Chemistry F.
Reactor Coolant Chemistry 3.6 4 G.
Reactor Coolant Leakage G.
Reactor Coolant Leekage 3.6-7 H.
Safety and Relief Valves H.
Safety and Relief Valves 3.6 9 Jet Pumps I.
Jet rumps 3.6 9b J.
Recirculation System J.
Recirculation System 3.6-9c K.
Structural Integrity K.
Structural Integrity 3.6-10 L.
Snubbert L.
Sne 5ers 3.6!Caj 3.7.
CONTAINMENT SYSTEMS 4.7.
CONTAINMENT SYSTEMS
- 3. 7-1 A.
Drimary Containment A.
Primary Containment 3.7-1 B.
Stanaby Gas Treatment B.
Standby Gas Treatment 3.7 10 System System C.
Secondary Contatnment C.
Secondary Containtrert 3.7-12 D.
Primary Centatnm:nt 3.7-13 Isolation Valves isolation Vahes 3.B.
RADIDACTIVE MATERIALS 4.8.
RADIDACTIVL MATERIALS 3.8 1 A.
Miscellaneous Radioactive r
A.
Miscellaneous Radto-3.8 1 Materials Sources active Materials Sources 3.9.
AVAILIARY Et[CTRICAL SYSTEMS 4.0 AUXILIARf ELECTRICAL SYSTEMS 3.9-1 A.
Requirements for Reacter A.
Auxiliary Electrical 3.9-1 Startuo Systems Equipment HATCH - UNIT 1 w
Amendmerit No. 181 1e+y
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j t15TOfTA.E1O (Concluoed)
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!Utat 4.6 1 Snubber Visu;.1 Inspection Interval 3.6 W l 3.7-1
~ Primary Containment isolation Valves Which Receive a Primary Containment isolation Signal 3.7-16 3.7-2 Testable Penetrations with Double 0-Ring Seals 3.7-21 3.7-3 Testable renetrations with Testable Bellows 3.7 22 3.7 4 Primary Containment festable isolation Valvet 3.7 23 3.13-1 Fire Jetectors 3.13 2 3.13-2 Fire Hose Stations 3.13-9 3.14.1-1 Radioactive liquid Effluent Monttoring instrumentation 3.14 2 3.14.2-1 Radioactive Gaseous Effluent Monttoring 1
Instrumentation 3.14 7 4.14.1 1 Radioactive Liquid Effluent Monttortng Instrumentation Surveillance Requirements 3.14-4 4.14.2 1 Radioactive Geseous Effluent Monttoring Instrumentation Surveillance Requirements 3.14 11 4.1$.1-1 Radioactive Licuid Effluent sampling and Analysis Program 3.15 2 4.15.2-1 Radioactive Gaseous Waste Sampling and Analysis Program 3.15-10 3.16.1-1 Radiological Environmental Monitoring Program 3.16-4 3.16.1-2 Peporting levels f.r Radioactivity Concentra-tions in Environmental Samrles 3.16 7
'4.16.1-1 Lower Limit of Detectt n 3.16-8 6.2.2-1 Minimum $hift Crew Composition 5-4 6.9.1.7-1 Environmental Radiological Monitortng Program Summary 6-18 6.9.2 1 Special Reporting Requirements 6 19 HATCH - UNIT 1
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W.H E D S UMITING CONDITION f ott Optrat10N 3 6.L. All snutters* shall te Of ELE their failure or failure orrecatrement are those installed cn non safety r y te no adverse ef fect on any safety-related system.the system en which they are installed ADPtitaBillTD Conditions 1, 2. ano 3.
t atT104-i Wtth one or more snubbers inocerable atthin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore th per Specification 4.6.L.4. on the supported comoonent e
system inoperable and follow the appropriate limiting condition of ocerationl statement (s) for that system.
SURVf!LLANCE #f0VIDEMENTS 4.6.L.EachsnubbershalltedemonbatedCPERABLEbytheperformanceofth following augmented inservice inspectten program.
e 1.
.lMrect ien T <re s As used in the Specification, of tre same design and rtanuf acturer," type of snubber
- shall mean snubbers trrespective of capacity.
2.
ytsual Insrect P u snubbers are categorized ts inaccessible or accessible during reactor P ration.
!ach of these categort'es (inaccessible and accessible) may be inspected independently a; cording to t!.e schedule determined by Table 4.6-1.
The visual in',pection interval for each category of 4.6-1 and the first inspect. ten interval determined using this criteria shall be based u; ion the previous inspection Interval as established by the requirements in effect before Amendment 181.
3.
Visual Intrectien a e ntance Criteria c
Visual inspections shall verify that (1) the snubber has no vtstble trdtcations of damage or impatred OPERABILIT'f, (2) attat hments to th foundation or succorting structure are functional, and (3) fasteners e
for the attachment of the snubber to the component and to the snuober anchorage are functional.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptacle for the purpose of establishing the next visual inspection interval, provided that (1) the cause of the rejection is clearly established and remedied for that particular snutber and for other snubbers irrespective of type that may be l
- The appitcable snu.,cers shall be identif ed in plant procedures, 1
i HAICH - UNIT 1 3.6-Ica Amentfr!)ent No.181 l
h.4.6.L.
_ JeEERS SUovEILLANCE CEDW P.(WENTS (C &tinuedt 4.6.L 3.
generically susceptible; and (2) the affected snubber is (Cont.)
functionally tested in the as-found condition and detere.ined 0FtP.ABLE per Specification 4.6.L.5 or 4.6.L.6.
All snubbers found connected to an inocerable common hydraulic fluid reservoir shall te counted as unacceptable and rray be teclassified as acctplable for determining the next inspectica interval provided that criterion (1) and (2) above are ret. A review and evaluation shall be performed and documented to justify continued operation w th an unacceptable snubber.
If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be fre t.
4 LEr,11g,n,11 Te$ts At least once per 18 months during shutdown, a representative s M e I
of 10% of the total of each category (hycraulic or mechanical)ls tested either in place or in a bench test. For each snubber that does not rett the functional test acceptance criteria of Specification 4.6.L.5. or 4.6.L.6., an additional sample of at least 1/2 the site of the inttial lot of that category of snubber shall be functionally tested.
L Functional testir.g shall continue until no additional inoperable snubbers of a particular category are found within a sample or until all safety-related snubbers of that category have been functionally tested.
The representative sample selected for functional testing shall incluoe the various configurations, operating environments and the range of size and capacity of snubbers.
shall be selected rancomly from the total population ofThe representative sample safety-relattd snubbers. At least 25% of the snubbers in the representative sample shall include snubbers from the following three groups:
l 1.
The first snubber away from each reactor vessel nozzle, 2.
Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor, etc.), and 3,
Snutbers within 10 feet of the discharge from a safety-relief valve.
Snubbers identified in plant procedures as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample *. The populations of 4
- Permanent or othU exemptions from functional testing for individual snubbers in those groups may be granted by the Ccmmission only if a justifiable basis l
for exemption is presented and/or snubber life destructive testing was performed to Qualify snubber ccerability for all design conditions at either the completion of their f abrication or at a subsequent date.
HATCH - UNIT 1 3.6-10b Amendment No. 181 1
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$UtVElttaNCE DE0VicEMENTS Meet mues) safety related hydraulic 6hd safety-related enecnanical snubbers may be used jointly or separately as the basis for the esmpling plan, in addition to the regular sample, snubbers placed in the same location as snuD5ers wnich failed the previous functional test snall be retested during the next test period.
Test results of these sr.utzters shall not te incluced in the sampling plan.
If any snubber selected for functional testing either fails to lockup or falls to move (4.e.
frozen in place) the cause will be evaluated and if caused by manufacturer or design deficiency all functionally tested. snubbers of the same design subject to the same defect s This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test criterta.
For the snubber (s) fJund inoperable, an engineering evaluaticn shall be performed on the components which are supported by the snubber (s). The purpose of th$s engineering evaluation shall te to determine if the C0mponents supported by the snubber (s) were adversely affected by the tnoperability of the snubber (s) in order the designed service.to ensure that the supported component remains cap Hydraulic Snubbers functional Test Acrytance Criteri_a g
The hvdraulic sn".,0er functional test shall verify that:
Activati n (restrainin' action) is achieved within the specified a.
s range sf velocity or acceleration in both tension and comp' es s ion, b.
Snubber bleed, or release rate, where required is within the specified range in compression or tension. For snubbers specif!cally required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
6.
Mechantcal Snubbers funcional Test Accent _Ane Criter.ta l The meenanical snuDber functional test shall verify that:
The snubber operates freely over th? stroke in both tension and a.
compression, The force that initiates free movement of the snubber red in b.
either tension or compression is less than the specified max 1tum drag force.
Activation (restraining action) is athieved with the specified c.
range of velocity or acceleration i c h tension and compression.
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HAICH - UNIT 1 3.6 10r low 2ndment NO. 181 l
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SNUPEERS
[UDViltl1NCE Af 0VIDfMNTS ICtetinued)
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SauHer Service Life Meniteries A record of the service life of each snutber, the date at which the designated service life commences and the installation and maintenance recorcs on which the designated service life is based shall be maintained as recutred by Specification 6.10.2.n.
Concurrent with the inservice visual inspection performed during the first refueling outage following issuance of amendment 112 and at least once per 18 months thereafter. the installation and maintenance records for each safety-related snubber shall te reviewed to verify that the indicated service life has not been exceeced or will not be exceeded by more than 10% prior to the next scheduled snubber service life review. If the indicated service life will te rxceeded by more than 10% prior to the next scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life teyond the date of the next scheduled service lifs review. The results of the reevaluation may be used to justify a change to the service life of the snubber. This reevaluation replacement or reconditioning shall be indicated in the records.
HAICH - UNIT 1 L6-10d Amendment No. 181
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lNUEFID VISUAt INSPfCTION INTERVAL YMEER OF UNACCtttaplt syUg:,ta$
Fopulation Column A Column B tulumn L or Category Extend Interval Fereat Interval Reduce Interval (Notes 1 and 21
!Netet 3 and 61
' Notes a and 6)
(Notes 5 and 61 1
0 0
1 20 0
0 2
100 0
1 4
150 o
3 8
200 2
5 13 100 5
12 25 400 8
18 36 500 12 24 48 750 20 40 7A 1000 or greater 29 56 109 TABLE NOTATION A
Note 1:
The next visual inspection interval for a snubber population or category size shall be determined, based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers may be categorized. based upon their accessibility during power operation, as accessible or inaccessible.
These categories may be examined separately or jointly. However, that decision must be made and documented before any inspection and that decision shall be used as the basis upon which to cetermine the next inspection interval for that category.
Note 2:
Interpolation between population or category sites and the number of unacceptable snubbers is permissible.
Use next lower integer for the value of the limit for Columns A P, or C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.
Note 3:
If the number.of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous *.nterval but not greater than 48 months, MATCH - UNIT 1 3.6 10e Amendment No. 181 l-
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Table 4.6-1 (Continued)
.TaPLE NOTaT104 (Cont.)
Note a:
If t>e number of unacceptable snubbers is egual to or less than the numbe* in Column B but great'r than the numoer in Column A, the nest instection interval shall be the same as the previous interval.
Note 5:
If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval. However, if the number 01 u$atteptable snubbers is less '.han the number in Column C but greate" than the number in Column B the next interval st ul be reduced proportionally by interpolation, that is, the breytous i
interval shall be reduced by a factor that is one third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Colurn B to the dif ferer.ce in the nuinbers in Columns B and C.
Note 6:
The provisions of Defi*ition 11., Surveillance frequency, are applicable for all,estection intervals up to and including 48 months.
HATCH tJNIT 1 3.6-10f Amendtaent No. 181
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(( ANT SYSTEMJ 3/4,7,4 $NUBQLPJ LIMITING ( E lll10N FOR OPERATION 3.7.4 All snubbers
- shall be operable.
The onTy snubbers excluded from this requirement are those installed on non-safety related systems and then only if their f ailure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
APPL 13Billif: Conditions 1, 2, and 3.
AC110N:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specifcation 4./ 4.d on the supported component or declare the supported l
system inoperable and follow tne appropriate ACTION statement for that system.
SVRVllllANCE RE0VLR.EMENTS 4.7.4 Each snubber shall be demonstrated OPERABLE by the performance of the following augmented inservice inspection program in additton to the requirements of Specification 4.0.5, a.
Insoection Tvoes As used in this Specification, " type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity, b.
Visual Inspections s
Srubbers are categorized as inaccessible or accessible during reactor operation.
Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.7-1.
The visual inspection interval for each category of snubber shall be determined based upon the criteria provided in Table 4.7-1 and the first inspection interval determined using this criteria shall be based upon the : revious inspection interval as established by the requirements in effect before Amendment 122 c.
Visual InsDection Acceptance Criteria Visual inspections shall verify that (1) the snubber has no visible indications of camage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners
- The applicable snubbers sh'all be identified in plant procedure.s.
HATCH - UNIT 2 3/4 7-il Amendment No. 122 1
axm SURVE!LLMNE RE0VIREMENTS (Continu1O 4.7.4.c. for the attachment of the snubber to the component and to the snubber (Cont.)
anchorage are functional.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that (1) the cause of the rejection is clearly established and refredied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible;-and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Soecifications 4.7.4.e or 4.7.4.f.
All snubbers found connected to an inoperable common hydraulic fluid reservoir.shall be counted as uracceptable and may be reclassified as acceptable for determining the next inspection interval, pronded that criterion (1) and (2) above are met.
A review and evaluation shall_ be performed and documented to justify continued operation with an unacceptable snubber.
If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be
- met, d.
Functional Tests I-At !oast once per 18 months during shutdown, a representative sample of 10% of the total of each category (hydraulic or mechanical)ly sefety-related snubber in use in the plant shall be functional tested either in place or in a bench test.
For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.4.e or 4.7.4.f, an additional sample of at least 1/2 the size of the initial lot of that category of snubber shall be functionally tested.
Functional testing shall continue until no additional inoperable snubbers of a particular category are found within a sample or unti?
all safety-related snubbers of that category have been functionally tested.
The representative sample selected for functional testing shall l
include the various configurations, operating environments and the range of size and capacity of snubbers._ The representative sample shall be selected randomly from the total population of safety-related snubbers.
At least 25% of the snubbers in the rerrnentative sample shall include snubbers from the following three groups:
l 1.
The first snubber away from each reactor vessel nozzle, 2.
Snubbers within 5 feet of heavy equipment (valve, pump, turbine, I
motor, etc.), and HATCH - UNIT-2 3/4 7-12 Amendment No. 122 r
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PLANT SYSTEMS SURVEllLANCE RE0VIREMENTS (Continued) 3.
Snubbers within 10 feet of the discharge from a safety relief valve.
Snubbers identified in plant procedures as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall t.lso be included in the representative sample *.
The populations of safety-related hydraulic and safety-related mechanical snubbers may be used jointly or separately as the basis for the sampling plan.
In addition to the regular sample, snubbers placed in the same location as snubbers which failed the previous functional test shall be retested during the next test period.- Test results of these snubbers shall not be included in the sampling plan.
If any 'ubber selected for functional testing either fails to lockup or fail, to move (i.e., frozen in place) the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the sama design subject to the same defect shall be functionally tested.
This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test criteria.
For the snubber (s) found incperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s).
The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.
e.
Hydraulic Snubbers Functionfl Test Accentance Criteria The hydraulic snubber functional test shall verify that:
1.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and i
l compression.
L
- Permanent or other exemptions from functional testing for individual snubbers in those groups may be granted by the Commission only if a justifiable
-l basis for exemption is presented and/or snubber life destructive testing was peiformed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent drtc.
l HA10! - UNIT 2 3/4 7-13 Amendment No. 122
ptANT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) 2.
Snubber bleed, or release rate, where required, is within the specified range in compression or tension.
For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
f.
Mechanical Snubbers functional Test AcceDtance Criteria The mechanical snuuber functional test shall verify that:
1.
The snubber operates freely over the stroke in both tension and cortpre s sion.
2.
The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force.
3.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression, g.
Snubber Service Life Monitorina A record of the service life of each snubber, the date at which the designated service life commt ices and the installat;on and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.n.
Concurrent with the inservice visual inspection performed during the first refueling outage following issuance of amendment 51 and at least once per 18 months thereafter, the installation and maintenance records for each safety-related snubber shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded by more than 10% prior to the next scheduled snubber service life review.
If the indicated service life will be exceeded by more than 10% prior to the next scheduled snubber service life review, the snubber service life shall be reevalusted or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review.
The results of-the reevaluation may be used to justify a change to the service life of the snubber.
This reevaluation, replacement or reconditioning shall be-indicated in the records.
HATCH - UNIT 2 3/4 7-14 Amendment No. 122
Table 4.7-1 SNVBBER VISUAL IfLSPECTION INTERVAL NUMBER OF UNACCEPTABLE SNVBBERS Population Column A Column B Column C or Category Extend Interval Reneau Interval Reduce Interval (Notes 1 and 2)
(Notes 3 and 6)
(Notes 4 and 6)
(Notes 5 and 6) 1 0
0 1
80 0
0 2
100 0
1 4
150 0
3 8
200 2
5 13 300 5
12 25 400 8
18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 TABLE NOTATION Note 1:
The next visual inspection interval for a snv. der population or category size shall be determined, based upon the previous inspection interval.and the number of unacceptable _ snubbers found during that interval.
Snubbers may be categorized, based upon their accessibility during power operation, as accessible or_ inaccessible.
These categories may be examined separately or jointly.
- However, that decision must be made and documented-before-any inspection and that decision shall be used as the basis upon which to determine the-next inspection interval for that category.
-Note 2:
Interpolation between population or category sizes and the number of unacceptable snubber: is permissible.
Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of unacceptable snubbers as determined by l
interpolation.
l l
HATCH -1) NIT 1-3/4 7-15 Amendment No. 122
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Table 4.7-1 (Continued)
TABLE NOTATION (Cont.)
Note 3:
If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.
Note 4:
If the number of unacceptable snubbers is equal to or less than the nLmber in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
i Note 5:
If the number of unacceptable snubbers is equal to o" greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.
However, if the number of
(
unacceptable snubbers is less than the number in Column C but greater than the number in Column 8, the next interval shall be reduced proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column 8 to the difference in the numbers in Columns B and C.
Note 6:
The provisions of Specification 4.0.2 are applicable for all inspection-intervals up to and including 48 months.
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HATCH UNIT 1 3/4 7-16 Amendment No. 122
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l HATCH - UNIT 2 3/4 7-17 Amendment No. 122 l
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