ML18101A225

Proposed Tech Specs Re Snubber Visual Insp Schedule

ML18101A225
Person / Time
Site:	Salem
Issue date:	09/09/1994
From:	Public Service Enterprise Group
To:
Shared Package
ML18101A224	List: ML18101A222 ML18101A225
References
NUDOCS 9409210116
Download: ML18101A225 (11)

Text

PLANT SYSTEMS

• 3/4.7.9 SNLBBERS LIM IT ING CONDIT ION FOR OPERATION 3.7.9 All snubbers shall be OPERABL.f.

APPLICABILITY: MOC£S 1, 2, 3 and 4. (MOC£S 5 and 6 for snubbers located on systems required OPERABLE in those MOC£S).

ACTION:

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 OPERABL.f status and perform an engineering evaluation per Specification 4.7.9c on the supported cofTl)onent or declare the supported system inoperable and foll CM appropriate ACT ION statement for that system.

SURVEILLANCE REQUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the foll<Ming augmented inservice inspection program and the requirements of Specification 4.0.5.

'/

SALEM - UNIT 1 3/4 7-28 Amendment No. 93 r--**

9409210116 940909 PDR ADOCK 05000272 P PDR

NEW PAGE 3/4 7-32 e TABLE 4.7-3 SNUBBER VISUAL INSPECTION INTERVAL Number of Unacceptable Snubbers Column A3 Column B4 Column C5 Population 1

• 2 Extend Repeat Reduce

/Category Interval Interval Interval 1 0 0 1 80 0 0 2 100 0 1 4 150 0 3 8 Notes: 1. The next visual inspection interval for the population of a snubber category shall be determined based upon the most recent 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. This decision shall be made and documented before any inspection and used as the basis upon which to determine the next inspection interval for that category.

2. Interpolation between population or category sizes and the number of unacceptable snubbers is permissible. Where the limit for unacceptable snubbers in Columns A, B, or C is determined by interpolation and includes a fractional value, the limit may be reduced to the next lower integer.

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.

4. If the number of unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the current interval.

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 current interval. However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation, that is:

U - B Ii Io Io

• i/3

• C - B where: Ii next inspection interval Io previous inspection interval u number of unacceptable snubbers found during the previous inspection interval B number in Column B c number in Column c

6. The provisions of Specification 4. 0. 2 are applicable for all inspection intervals up to and including 48 months.

SALEM-UNIT 1 3/4 7-32

PLANT SYSTEMS BASES

~7.9 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on I nonsafety related systems and then only if their failure or failure of the system on which they were installed, would have no adverse effect on any safety related system.

A list of individual snubbers required to be operable per the technical specifications with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.7l(c) of 10 CFR Part 50. The accessibility of each snubber shall be determined and approved by the Station Operations Review Co111nittee. The determination shall be based on the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g.,

temperature, atmosphere, location, etc.) and the reco111nendations of Regulatory Guide 8.8 and 8.10. The addition or deletion of any snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.

The visual inspection frequency is constant inspection is determined When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers are.those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection or are similarly located or exposed to the same environmental conditions, such as temperature, radiation, and.vibration.

J

-

When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in.

order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.

• SALEM - UNIT 1 B 3/4 7-6 Amendment No. 93

e e Pil~'<T SYSTEMS

~

~ (Ccntinued)

~---7

\__, To provide assurance of snubber functiaial re.liability, a representative scmple of the installed S1'1LJl:lberS will be functicntlly tested durirq plant 1.ns-ev-.f.- sh1ItdcJWrlS at 18-mc:rrt:h intel:vals. Cl:&llved failures of these sanple sra.J1::Cers

, I _ /. shall require f'unctiaial tE6tin; Of additia'lal. units.

\1.e,[oe>vt"-e-C- .

+e.ic.k .fvt?w1 Permanent or ether E!lCl!ll¢ions frail the surveillance pzc:gzam far

.in:lividual Sl'lll::lbers may be granted by the Qmnissiat if a justifiable basis f:i.~ far exmpticri is pt&Ented an:i, if ~li.cable, srd::lt>c' lite destructive 1 1- b testin;i was perfamad to qualify the S1'1J1Dma far the 8R>].icable design

!3 -S/tf cxn:litiais at either the ccmpletian of their fabricaticn or at a slbse:µ!rlt.

date. SnJbbers SO exenpta:i shall be listed in the list Of imi.viduaJ. snubbe.rs

.in:licatin; the extent of the exenpticns.

Hydraulic snJt:bars an:1 mechanical Sl'lll::lbers my md1 be treated as a different entity far the above SUIVeillance pzc:gzam.

'!he service life of a snubber is evaluated via Dlln1facb.Jre:r irpJt ard infcmnatiai thrc:uJh ccnli.deratic:n of the snJl:Eler l9CVi.ca a:n:litia'& ard associ.ata:l inst:allaticn an:l maintenan:B :cec:m:ds (newly .installed ~, seal replacad, sprin; replaceci, in high radiaticn arm, in hi9b ta*ccab.1r9 a.raa, etc... ). 'Iha ~ to m:mitcr the !ftl1:Dlr' sarvica lite is incll.md to ensure that the *Sl'lll::lbers periodically urdergo a parfcmDlll'1C9 eval.uatial :...n view of their age and c.peratin;i a:n:liticns. 1hels9 mwz:da will prcvida stat.ist.ical bu* far tubire cxmsidamticn of srJJ!:lbar sm:vica lite. 'Iha ~ tor the maintenanc9 of niccmJs and the srU:i:m:' SEVim lit* raviar are not intermd to affe:t plant q:>eratic:n.

SAIDI - UNl'l' 1 B 3/4 7-7 Aml!rdn& rt *-- 1.3 9

'.

P lANT SYSTEMS 3/4.7.9 SNLBBERS LIMITING CONDITION FOR OPERATION 3.7.9 All snubbers shall be OPERABLE.

APPLICABILITY: MOIES 1, 2, 3 and 4. (MOIES 5 and 6 for snubbers located on systems required OPERABLE in those MOIES).

ACT ION:

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 Specification 4.7.9c on the supported C0111JOnent or ~eclare the supported system inoperable and follaw appropriate ACTION statement for that system.

SURVEILLANCE REQUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

a. Visual Inspection An -i n;-~vi ce- ~.iJJal i ns~Vo~- of ~11 s.rfubbers sha be- pe~f or~ in -

acco. dance wiyr. the foll~~g schedu}i for each pe7A us s in this Re.pi ctce- sy.eeifi cation, type o~snubber sha _,f' mean snub r of the s design

~and man~urer, i;:.respective at capacity *

. i-,rifh No. Ipoperabl e S.nlJbbers of "J-n5et1..f j_ EacJt/T e er ;is ecti on P ri ad Subseguent/Inspecti on

<onths + ;2:£ 12 months/.:+7'25%

6 monY1s + 25%

3y4 124 day*s + '!5i 5, 6, 7 62/a~ys ! 25i

~8 or more ll: days !:. 25 Snubj)ers are categorized a~ccessible/.access,ible dUr~

ope.ratiori. Eaph group (a;cessible and inaccessib,le) may be inspecte*

reactor independently/; n accordance with th( ab ove sche'CiUl e.

/ / / / 7 i nspect-teln i nte/VSha 11 novle 1eng/ed mor2 n prp~ons of )'pecifica_pi/n4.0.2 ar;e not applicable.

SALEM - UNIT 2 3/4 7-23 Amendment No. 68

NEW PAGE 3/4 7-27 e TABLE 4.7-3 SNUBBER VISUAL INSPECTION INTERVAL Number of Unacceptable Snubbers Column A3 Column B4 Column C5 Population 1* 2 Extend Repeat Reduce

/Category Interval Interval Interval 1 0 0 1 80 0 0 2 100 0 1 4 150 0 3 8 Notes: 1. The next visual inspection interval for the population of a snubber category shall be determined based upon the most recent 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. This decision shall be made and documented before any inspection and used as the basis upon which to determine the next inspection interval for that category.

2. Interpolation between population or category sizes and the number of unacceptable snubbers is permissible. Where the limit for unaccept~ble snubbers in Columns A, B, or C is determined by interpolation and includes a fractional value, the limit may be reduced to the next lower integer.

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.

4. If the number of unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the current interval.

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 current interval. However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation, that is:

U - B I1 Io Io

• i/3

• C - B where: Ii next inspection interval Io previous inspection interval u number of unacceptable snubbers found during the previous inspection interval B number in Column B c number in Column C

6. The provisions of Specification 4. 0. 2 are applicable for all inspection intervals up to and including 48 months.

SALEM-UNIT 2 3/4 7-27

..

/'}..'t PAGES 3/4 7thru 3/4 7-30 l ARE CELETED

/ 2. 'i(

SA LEM - UN IT 2 3/4 7~ thru 3/4 7-30 Amendment No. 68

PAGE INTENTIONALLY

.* " ~BA~SE~S~~.9i--~~--~~~~--11.----~--~--~~

3/4.7.9 SNUBBERS All snubbers are required OPERABLE to ensure that th* structural integrity of the reactor coo 1ant system and a 11 other safe.ty re 1ated system~.

is maintained during and following a seismic or other event initiating dynam._

loads. Snubbers excluded from this inspection program are those. installed on nonsafety related systems and then only if their failure or failure of the system on which they were installed, would have no adverse effect on any safety-related system.

A list of individual snubbers required to be operable per the technical specifications with detailed information of snubber location an~ size and of system affected shall be available at the plant in accordance with Section 50.7l(c) of 10 CFR Part 50. The accessibility of each snubber shall be determined and approved by the Station Operations Review Committee. The determination shall be based on the existing radiation levels and the expect~d time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g.,

temperature, atmosphere, location, etc.) and the recommendations of Regulatofy Guide 8.8 and 8.10. The addition or deletion of any snubber shall be made in accordance with Section 50.59 c~ 10 CFR Part 50.

based upon maintaining constant inspection is determifi~cl When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection or are similarly located or exposed to the same environmental conditions, such as temperature, radiation, and vibration.

When a snubber 1s found inoperable, an engineering evaluation is performed, in addition to the d1termi*nation of the snubber mode of failure, order to determine if any safety-related component or system has been adversely 1ffect1d by the 1noperabil1ty of the snubber. The engineering evaluation shall determine whether or not th~ snubber lllOde of failure has imparted a significant effect or degradation on the supported component or system.

SALEM - UNIT 2 B 3/4 7-6 Amendment No. 68

~

3/4.7 PIAN!'

e SYSTfH?

~

SWM&'l Ccmt;jrnffil

~ ~provide assurance of snul:X>er functiooal reliability, a. tept sa1t:ative

( ~le cf the installed srrubbers will be functiaially tested durin;J plant sluitdoWnS at 18-m:::nth intervals. Ci:lSetved failures of these sanple Sl'IJtbers shall recpire functiaial test.in; of additiaml. units.

1nStf' .f Pemanent or other exEl!Pticrm fran the sm:veillance pi:c*qzam for

()..el o'-'1- feJ iniivi.dual snJt:i>ers my be granted by the Qmnjsaial if a justifiable basis far exeu::ptiat is pz s uted am, if CSR>licable, srall:i:Jer life destructive

.+-e.o<:+ -~(11 testinq was performed to qualify the Sl'IJl::b!rs far the ~icable design ocniltiaw at either the oc:q>letiat of their fabri.catim or at a subsEqJent f"~ date. Sr1Jl::b!rs so exaipted shall be listed in the list of irdividual. Sl'1.ll:t>e.rs *

() >/q '?-~ b imicatin; the extent of the exenpticrm.

Hydraulic srutiJers am mechanical Sl'IJl:t>ers nay eadl be treata:l as a different entity far the above surveillarx:e pztgiam. I 1

'lhe service life of a srall:lber is evaluated via llllmlfact:m:er .irpJt am infomatiat thraJgh OCllSideraticm of the sn.Jtlber service ocniltiaw ard.

associated installatiat am maintenance recmds (newly inltal.l.ai sn.JtDr, seal replaced, sprirq repl.aca:t, in high tadiaticn area, in b.igb t011ei:at:ure area, etc *** ) * 'lhe recpirement to llalitor the snJl::lbex' serrlca life is .in:luded to ensure that the srlJl:i>ers periodically urdatgo a perfCDllllUD9 evaluatiat in view of their age am cpratinJ cxn:iltiais. 'lbesa LEIOOlds will provide statistical bases far future oc:nsideratiat of Sl'Ull::i:>er service life. 'Iha racpirements for the maintenance of reands am the sr"llti:>er service life review are not inten:led to affect plant q>eraticm *

.*

.*

SAUM - UNIT 2 B 3/4 7-7 Amerdwent No. 117

INSERT 1

• All snubbers shall be categorized into two groups: those accessible and those inaccessible during reactor operation. The visual inspection interval for each category of snubbers shall be determined based upon the criteria provided in Table 4.7-3.

INSERT 2 The inspections are performed for each category of snubbers. The snubbers are categorized by accessibility (i.e., accessible or inaccessible during reactor operation) . The next visual inspection for each category may be twice, the same, or reduced by as much as two-thirds of the previous inspection interval. This interval depends on the number of unacceptable snubbers found in proportion to the total number of snubbers in each category from the most recent inspection. Intervals may be increased up to 48 months if few unacceptable snubbers are found in these inspections. The visual inspection interval will not exceed 48 months. However, as for all surveillance activities, unless otherwise noted, allowable tolerances of 25% are applicable for snubbers. Table 4. 7-3 establishes three limits for determining the next visual inspection interval corresponding to the population of each category of snubbers. For a category that differs from the representative sizes provided, the values for the next inspection interval may be found by interpolation from the limits provided in Columns A, *B, and C. Where the limit for unacceptable snubbers in Columns A, B, or C is determined by interpolation and includes a fractional value, the limit may be reduced to the next lower integer. The first inspection interval determined using Table 4.7-3 shall be based upon the previous inspection interval as established by the requirements in effect before amendment ( ).