ML20078M458
| ML20078M458 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/21/1983 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078M461 | List: |
| References | |
| NUDOCS 8310250195 | |
| Download: ML20078M458 (14) | |
Text
_,
/q.m Mcwc UNITED STATES
,!V s ([ g NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D, C. 20555 5
COMMONWEALTH EDIS0N LOMPANY Docket No.
50-237 DRESDEN NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 76 License No.~ DPR-19 1.
The Nuclear Regulatory Comission-(the Comission) has found that:
A.
The application for amenament by Commonwealth Edison Company (the licensee) dated June 13, 1983 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I:
B.
The facility will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Comission:
C.
There is reasonable assurance (i) that the activities authorized i
by this amendment can be-conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public;
}
i
-E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission 's regulations and all applicable requirements have been satisfied.
I 8310250195 831021 PDR ADOCK 05000237 P
pg
.~
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license anencnent and paragraph 3.B of Provisional Operating License No. DPR-19 is-hereby amended to read as follows:
B.
Technical Specifications The Technical Specificatiens contained in Appendix A, as revised through Amendment No. 76, are hereby incor-porated in the license._ The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION.
4
/h/ /W$ A hetY Dennis M. Crute field,,enief Operating Reactors Branch #5 Division of Licensing
Attachment:
1.
Changes to the Technical
. Specifications Date of Issuance:
October 21, 1983 i
ATTACHMEllT TO LICENSE AMENDMENT NO.
PROVISIONAL OPERATING LICENSE N0. DPR 19 D_0CKET N0. 50-237 Replace the following pages of the Appendix A Technical Specifications with the' enclosed pages.
These pages contain the captioned amendment number and a vertical line indicating the change.
Replace Pages 91b 91 d-1 99b t
l k '
5
- m
,w~
,,er-w-
-w,w-yv, e-e n--
evem
..p....-.
neels and DPR-25
)._6 1.lMITING_CONDIl10N FOR OPERATION
. j,6 supyNIM.AMCE_PRQulklcll847 I.
Snubbers (Shock Suppressors)
T.
Snubborn (!! hock Supproomore) l.
During all modes of operation except cold shut-Tlio following surveillance requirementa apply to all down and refuel, all safety related snubbers anfety related enubbers liutad in Tables 3.6.la and limited in Table 3.6.la and 3.6.lb shall be oper-3, (,, g g,,
able except as noted in Specification 3.6.1.2 i
through 3.6.1.4.
1.
Visual Insspectlon 2.
rrom.uJ.eter u.. al
. e ubb.c le d.t.r.nload to A,g jlld6 pent.'el)L Visual lil8peCC Eoin tiltalI b8 per-be inoperable, coutlaued reactor operecloo le permle-alble uuly during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless the forsned Ort ( b-0 asfety related hydraulic and enubber le sooner made operable or replaced. Torue inechl4HICal Gillibberg Colttained ist Talbles 3.6.la sing tiesler enubbere may be Inoperable la either of the folluulus configurations until 1983, to pind 3.6. Ih Ill ACCordatice WIlh Llle belOW Scliedule, f acilitate the luetallettom of the Mark I torue attached piping enodification.
al.
All liydraulic unubbers whose seat material Configusettua As Evesy other enletlag snubber pelt (up to 3 pelre) on the ECCS header, 1884 8 lacell deluOne L rilled by Operal istg exper--
b ience, lab testing or analyniu to be com-or l
couri.orattua si one saf eting soubber f rom each of the patible with the operatieng environment 6e etlag soubber pels. o the accs ggg g g gg g,
.g,, g tion shall includo, but not necessarily be
)
3.
If the requiremente of 3.6.I.I and 3.6.1.2 cannot be IImiLed LO lita1seul iull of Llle laydratilIc 8
met, en orderly shutdova shall be faltleted and the 8
reactor shall be la cold shutdove or refuel condition Illit s! re00rVoir, [ItsId Collllec tInita, alld y
w stata M hours.
g {lthil[10 COI I)CC t k Olt to the pipkalg and allChor l
4.
If a anubber le deteralued to be looperable uhlte the lo verify attubber apurstbj.lity.
I reactor le la the cold ebutduun or refuel mode, the enubber shall be meJa operable or replaced prior to reactor et ertup. This requirement does not epsily to is,
All luechasiical sittildscre chall be v l atia l l y Torue klug fle=Jer saubbare for the period lJentitled j gg3ppe g gd,
Tlg j g jInspec t 5 018 ch4II coupIst la paragraph 3.6.I.2 above, g
gg g g
3.
2.nubbere may be eJJed to safety related systems with-spcC1 Ion Of the alttlIsber alld a t t achmeit t o LO out prior license amenJsent to Tables 3.6.la and/or 3.6.lb psuvided that a revleton to Tables 3.6.la I, g I, g g
g g
g anJ/or 3.6. lb le ti.cluded with the nest Ilcones amend-dannaglo or IImpOEred UporablIILy.
t r.guset.
Bio, al Snubbers Fnund Innperable llaring flex L llaguired Inupectinn Intenval inspection interva}
O 18 n.ontha e 25%
i 12 mont hu 7 25I 2
6 monibn 's 25%
3, 4 124 dayu I 25%
Unit 2 Amendment No. ) 6 %
5, 6, 7 62 daya I 25%
Unit-3AmendmentNo.dr,ph7 all M dayu I25% 91b
O o
O.
t TADI.E 3'.6.la i
Note 1.
These snubbers are being replaced'.
with mechanical snubbera as de-SAFETYREt.AYEDllYDRAUI.10SifUBBER8 N
fei 1$ b ' I's t 1 d
n
{
completion of the Hgrk I Teru DPR-19 attached piping modification.s SHUBBEltS SHUBBERS SilURRER IDCATIDH EL.EVATION AIIHUTil RADIATION AREA DURING '(OR)lAI.
DURING N0ftHAI SHUBBER IN HICll INACCESSIBI.E ACCESSIBl.K!
11 0 i
_DURillo SilGTDOWH OPERATIOff Ut'ERATION
}'
2 Torue Ring Eleader 1501-24" (Note 1) 483
83*
i X
l 3
'Nrua Hing Ileader 1501-24" (Note 1) 4838 74*
1:
X I!
4 Torna Ring Hender 1501-24" (Note ()
483' 38' 3:
),
X l;
5 Torus Hlns licader 1501-24" (Note 1) 4838 29' i(
X I
,j:
7 Torue Rina lloader 1501-24" (Note.1) '
4838 331*
x l
8 Torne Ring Header 1501-24" (Note 1) 433e 322*
e ii, g
l ~,'
9 Torne Ring Ileader 1501-24" (Note 1) 483e 286*
t
- I_
- j 10 Torum Ring llander 1501-24" (Note 1)
(g3e 277 i
.i 1
X a
i.
I
,N
!I 12 Torue Ring Header 1501-24H (Note 1) 433e 218*
h X
l 13 Torise Ring Ileader 1501-24's (Note 1) 433e' 209*
l l !
i I X
l e
' f 15 Torum Ring Ileader 1501-2AH (Note 1) 433e 33 g*
i.
l g
3
}
16 Torue Ring Header 8501-24H (Note 1) 433e 142*
i
.X r,
}i
- lloJlfications to thle table due to changea la blgh ra41stion should be submitted to the NRG as part of the n amendiment resgucet.
ext Ilcansa I
91d-l I
Amendment No. frffM
DPR-19 and Th2 inspectign frequency is beard upon maintaining a DPR-25 When the enuse of rejection of the snubber is constant level of snubber protection. Thus, the re-clearly established and remedied for that snubbes quired inspection interval varies inversely with the and for any other snubbers that may be generically observed snubber failures. The number of inoperable susceptible, and verified by inservice functional enubbers found during a required inspection deter-testing, that snubber may be exempted from being mines the time interval for the next required in-counted as inoperable. Generically susceptible
- opection, inspections performed before that interval snubbers are those which are of a specific make or h::s elapsed may be used as a new pference point to model and have the same design featutes directly detersine the next inspection. llowever, the results related to rejection of the anubber by visual in-of such early inspections performed before the spection or are similarly located or exposed to original require time interval has elapsed (nominst the same environmental conditions such as tempera-time less 25%) may not be used to lengthen the re-ture, radiation, and vibration.
quired inspection interval. Any inspection whose results require a shorter inspection interval will Monitoring of snubber service life shall consist over' ride the previous schedule, of the existing station record systems, including the centit.1 filing system, maintenance files, i
To further increase the assurance of snubber re-safety-related work packages, and snubbes inspection liability, functional tests will be performed once records.
The record retention programs employed at each refueling cycle. A representative sample of the station shall allow station personnel to main-10% of the safety-related snubbers will be func-Lain snubber integrity. The service life foi tionally tested. Observed failures on these samples hydraulic anubbers is 10 years.
The hydraulic will require testing of additional units.
anubbers existing locations do not impose undue safety impiications on the piping and componenta be-Ilydraulic anubbers and mechanical anubbers may each cause they are not exposed to excesses -in environ-be treated as different entities for the above mental conditions.
The service life for mechanical curveillance programs.
anubbers is 40 years, lifetine of the plant. The mechanical anubbers are installed in areas of harnh Ilydraulic snubber testing will include stroking of environmental conditionn because of their dependa-A the snubbers to verify piston movement, lock-up, bility over hydraulic anubbers in these areas.
All und bleed. Funcricnal testing of the mechanical snubber installations have been tigoroughly engineered anubbers will consist of verification that the providing the necessary safety requirements.
Evalua-force that initiates free movement of the snubber Lions of all anubber locations ar.d environmental in either tension or compression is less than the conditions justify the above conservative snubber maximum breakaway friction force. The remaining servic,e lives.
portion of the functional test consisting of veri-fication that the activation (restraining action)
A re-enelyste of the ring heeder deet a beoed upon acceleration t
response spectre derived from the originet auction boeder snelyste is achieved within the specified range of accelera-report demonstrates thec for nornet operation.ptus sele =le, neither tion in both tension and compression will not be
" h* ""d * * " * ""s*t e,* * * '*"*i t e t t oo o r..'".e l o. o r"3 p a i r e or i
- I"'**
d"'*"'"
e.uo6ere to.per.
ne si done. This is due to the lack of competitive enubber from each pelr loopueble out or a poire is coasidered marketable test fixtures available for station use, conservettve. Since the enetysle shows that the plant con operate Therefore, until such time as test fixtures-become esfely fedeflattely with no enubbers on tha ring header the Ilmite-clon on operation end etere o =tth inoperebte enubbere untit svailable, only part (i) of the test will be per-
. nssa is justise, nia ti. treme is adequate to formed; part (ii) will not be done.
.1t = co.piett a or no n u k e co m ett u h.d piplas =adificati a.
Unit 2-Amendment No.M 7' Unit 3 -Amendment Nos.)[,44 0 7 99b a
UNITED STATES
- g
{.h e Y _ n,E l
NUCLEAR REGULATORY COiGMISSION j
WASHINGTON, D. C. 20555
%24 COMMONWEALTH EDISON COMPANY Docket No.
50-249 DRESDEN NUCLEAR POWER STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 License No. DPR-25 i-1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for ancadment by Commonwealth Edison Canpany (the licensee) dated June 13, 1983 complies with tile standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commist. ion 's rules and regulations set forth in 10 CFR Chapter I:
e B.
The facility will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Comi ssion:
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission 's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
r J
[
b m
2.
Accordingly, the license is amended by changes to the Technic 61 Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No. DPR-25 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 67., are hereby incor-porated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION WE$
Dennis M. Crutchfield,,(Cfiief Operating Reactors Brar ch #5 Division of Licensing
Attachment:
1.
Changes to the Technical Specifications Date of Issuance: October 21, 1983 9
b.
ATTACHMENT TO LICENSE AMENDMENT NO.
FACRITY OPERATING LICENSE NO. DPR-25 DOCKET N0. 50-249 Replace the fo] lowing pages of the Appendix A Technical Specifications with the enclosed pages.
These revised pages contain the captioned amendment number and a. vertical line indicating the change.
Replace Pages 91b 91dl 91 e-l 91 e-2 99b 4
t a
w 9
u
"p n
- (.r -
lirn.19 and DPR-25 o
i.f ITi}iiYiiORONIillT0fi 'I t)! OI'ERATION ~
M_nunygil.plian pr.lluglirlial[r I.
Snubbers (Shock Suppressors)
I, finnliborn (Illinelt fluppro o n or o )
1.
During all modes of operation except cold shut-Tiin following curvoillance railuIl cunint o nerly to all down and refuel, all safety related snubbers anfety s elnleil osinbbora l l u l oit in Tables 3.6.in anl limited in Tabic 3.6.la and 3.6.lb shall be oper-3.6.th.
}
able except as noteil in Speci fica tion 3.6.1.2
~!
through 3.6.1.4.
t.
Vianal Innpectlon i
5 2.
From enl siter the tien a enubber le determined to Ag j p,jpppgy,jgggg y[gggg [ j gg g,pe,; g [ pgg glga)I hn per-l be Inoperehle, continued reactor operstlen le permis-alble only during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless the fosincel oil ( 11 0 Safely rcInlesl hyals nulic nnel j
ennbber le sooner made operable or replaced. Torus trinclinIIIctil elltthhcr0 c olit n i nsul in Tablen 'l.6.In l
Rins IIeeder enubbero may be Inoperable la alther of allel 3.6. lb Ill OccDrilallice WIllt I lli? he lieu sclicali In the following configuratione until 1983, to lecilit e's the Instellation of the Mark I torue a
e t.ched piping modification.
a.
All liyilrslulic clittlebers whone ne ra l inn t e r i a l Configuration As Evnuy other enletlog snubber pelt e
litio heell demOllulrnleil by OperalInig CXpef" (up to 3 potre) on the ECCS headere
)
ience, Inh teolling or unnlyn t o lo be coin-or configuration se one a=leting snubber from.ach of abe i nt ih t e wi tle t he operal iiig ciiviii nnient 6 estating enubber pelre on the ECC5 ellall bo Vluually Illapect cel.
Tlil n Intnpec-lion ohnll incluilo, liu l not neee ri te n e l l Y I"i l^
3.
If the requirements of 3.6.I.1 and 3.6.l.2 cannot be g (In i l esl I.0, Innpcel inne 01 lIn* liyilf nill I c met, en orderly shutduvo shall be lottleted and the l
reactor shall be in cold shutdown or refuel condition (IllI 8! I'C80EV0 kI's [IH Id C"nHCt!l "H8 A H'I e
i
=tthi. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
IInl(ogn connection lo the piping nisil niichor 4.
If a enubber is determined to be Inopershf e idille the lo Vol i f y enublier oparnhi iit y.
l reactor le in the cold ebutdown or refuel mode, the enubl.er shell be made operable or replaced prior to reactor startup. This sequirement does not apply to b,
AII piecIlGnICal Gillehbet o nhfil I lic v i ritili l l y Torue Rina lieeJer snubbere for the period ident! fled ilt o pee l esl.
Tliis inopeelinn ohnli convini I
I" Pstoph 3.6.t.2 above.
of, liiiL ilOL licceoaor i I y I*c Ii4iled IO, In-5.
snubb.re may be added to estety related erstems ulth-npcel Ion of thu punbher anil al I achincnt n Io out prior license amendment to Tables 3.6.1 end/or 3.6.lb provided that e revision to Tables 3.6.is t he I Ipilig Otol allChor fut I slilI c al i nn u OI ImpnIrcel opornhIll1y.'
f end/or 3.6.lb le included with the nemt license amend-dainngo or ment request.
lin, of finnblici e l'ound i
luoperable finring fle x t lleepo l t eil luopec t i oni intcaval InnperIinn Inteivnt 0
IH inunthn e 25%
1 I 7 inoni ho 's ' 7 '.1 7
6 niinit h n e 7 '> T 3, 4 174.inyn I / *.1 Unit 2 Amendment No. ) 6 M
.5, 6, 7
61
.l.i y n i ret Unit-3 Amendment No,. AG Jik.6 '1 an il.inyn e rit on
a Note 1.
These enubbero cre being replaced r with mech:nicc1 cnubbsro co,de-Trble 3.6.I.a lineatsd in Srction 3.6.I.2 and a SAFETY RELATED llYDRAULIC SNUBBERSA c
i l
Ha k u
attached piping modification.
j SNUBBERS SNUBBERS SNUBBER IN HIGli INACCESSIB!.E ACCESSIBI.R SHUBBER RADIATION AREA DURING NORMAL DURING NORMAL j;l NO.
LOCATION ELEVATION AZIMUTH DURING SIIUTDOWN OPERATION OPERATION f
f '..
8 2
Torus Ring IIcader 1501-24" (Note 1) 483' 83 X
i o
3 Torus Ring IIcader 1501-24" (Note 1) 483' 74 X
8 4
Torus Ring Ileader 1501-24" (Note 1) 483' 38 X
8 I;i 5
Torus Ring IIeader 1501-24" (Note !)
483' 29 X
8 1;
7 Torus Ring IIcader 1501-24" (Note 1) 483' 331' X
i i I,,
8 Torus Ring Ileader 1501-24" (Note 1) 463' 286 X
8 9
Torus Ring Ileader 1501-24" (Note 1) 483' 286' X
i'.
i l 10 Torus Ring Ileader 1501-24" (Note 1) 483' 227' X
i l
12 Torus Ring Ileader 1501-24" (Note 1) 483' 209' X
13 Torus Ring lieader 1501-24" (Note 1) 483' 209' X
1 l
15 Torus Ring IIcader 1501-24" (Note 1) 483' 151' X
l Isolation Condenser Pipeway Room I
Isolation Condenser Line 1303-12" 558' 180' I
X 1
I 2
1 solation Condenser Line 1303-12" 568' 180' X
X 3
Isolation Condenser Line 1303-14" 580' 195' X
X i*
Drywells I
23 Drywell Cleanup Line 1201-8" 537'6" 84 X
X l
Modifications to this table, due to changes in high radiation, should be submitted to the NRC DPR--2 5 as part of next license amendment request.
I Amendment No.%E'; 67 91d-1
Table 3.6.1.b SnFETY RELATED HECilANICAL SNUBBERS
.l SNUBBER RADIATION AREA DURING NORMAL DURING NORMAL j
NO.
LOCATION ELEVATION AZIMUTH DURING SHUTDOWN OPERATION OPERATION i
l Drywell Recire. Motor 3B-202 524' 328' X
X 2
Drywell Recire. Motor 3B-202 524' 302 X
X 8
3 Drywell Recirc. Motor 3B-202 524
315' X
X I
)
4 Drywell Recire. Motor 3A-202 124' 14 88 X
X I'
i 5
Drywell Recirc. Motor 3A-202 524' 122' X
X l
6 Drywell Recire. Motor 3A-202 574' 1358 X
X 1
'l 7
Drywell Recire. Pump 3B-202 512' 326' X
X 8
Dryweil Recire. Pump 3B-202 512' 304' X
X 9
Drywell Recire. Pusep 3B-202 507' 315 X
X 8
10 Drywell Recire. Pump 3A-202' 512' 124' X
X 1
II Drywell Recire. Pump 3A-202 512' 14 6 X
X 8
i 12 Drywell Recire. Pump 3A-202 507' 135 X
X 8
15 Drywell LPCI Line 1506-16" 513' 256' X
X 4
16 Drywell LPCI Line 1519-16" 513 95' X
X l
21 Drywell Recire. Ileader 201A-22" 533'6" 22' X
X i
(
l' 22 Drywell HPCI 1.ine 2305-10" 550' 121 X
X 8
l-l 25 Drywell Cleanup Line 1201-8" 537'6" 78a X
X l
27 Drywell Cleanup Line 1201-8" 538'6" 60' X
X 29 Drywell Core Spray Line 1404-10" 573' 231' X
X 30 Drywell Core Spray Line 1403-10" 561' 336' X
.X l
i 31 Drywell llPCI Line 2305-10" 563' 14 0' X
X 1,..
i 1
Hodifications to this table, due to changes in high radiation, should be submitted to the NRC as part of next license amendment request.
Med I.
. Amendment No. g,6 7
Table 3.6.1.h (Continuad)
. SAFETY RELATED HECllANICAL SNUMERA e
I SNUBBEli SNUBBERS SNUBBER IN HICH INACCESSIBLE ACCESSIB1.E SNUBBER RADIATION AREA DURING NORMAL DURING NORMAL i
No.
LOCATION ELEVATION AZIMUTH DURING SHUTDOWN OPERATION OPERATION 4
I' 32 Drywell Target Rock Valve 203-3A 542'6" 14' X
X
,L 33 Drywell Target Rock Valve 203-3A 542'2" 31' X
X 34 Drywell Target Rock Valve 203-3A 540' -
19' X
X i
35 Drywell Target Rock Valve 203-3A 540'6" 34' X
X i !
36.
Drywell Recire. Line 3-20'B-22" 532'6" 183 X
X 8
i l ' ) 37 Drywell Feedwater Line 3-3204D-12" 537' 110' X
X 38 Drywell Feedwater Line 3-3204E-12" 538'6" 260' X
X 4
41 Drywell Hain Steam Line 3-3001B-20" 534'9" 28' X
X
, e
);!
42 Drywell Hain Steam Line 3-3001A-20" 534'8" 14' X
X i i
]j 43 Drywell Hein Steam Line 3-3001C-20" 534'8" 332'
.X X
! I fl 44 Drywell Hain Steam Line 3-3001B-20" 542'8" 112' r.
X
[
45 Drywell Hain Steam Line 3-3001B-20" 543'6" 100' X
X 1
46 Drywell Hain Steam Line 3-3001A-20" 543'6"'
75' X
X 47 Drywell Main Steam Line 3-3001A-20" 544'1" 75' X
X I
40 Drywell Hain Steam Line 3-3001D-20" 542'8" 285 X
X 8
i j
49 Drywell Hain Steam Line 3-3001-D-20" 543'6" 285 X
X 8
4 i
j 50 Drywell Hain Steam Line 3-3001C-20" 543'6" 2558 K
X l
(
51 Drywell Hain Steam Line 3-3001C-20",
JS$3'6" 2558 X
X y
i Torus l
)i 16 Torus Ring Ileader 1501-24" 483' 14 28 X
l i :
2 j
DPR-25 91 e-2 1
DPR-1o and,
ilhe inspectign frequency is leancd upon maintaining a DpR-25 in,en 'the cause of rejection of the unubber is
- constant level of snubbar prote'ct. ion.
Thus,.tlin re-clearly established and remedied for that unubber quited inspection interval varies inversely wills the and for any other anubbers that may be generically obsetved snubber failures. The number of inoperable nuneeptible, and verified by inservice functional
'cnubbers found during a required inspection deter-testing, that snubber may be hxempted from being
- mines the time interval for the next required in-
. counted as inoperable. Cencrically susceptible opectlon.
Inspections performed before that interval snubbers are those which are of a specifie make or jhas elapsed may be used as a new 1eference point to model and have the same design features directly
- datermine the next inspection.
Iloweve r, the results related to rejection of the snubber by visual in-
)of such early inspections performed before the npection or are similarly located or exposed to 1 original require time interval has elapsed (nominal the same environmental conditions such as tempera-
,Line less 25%) may not be used to lengthen the re-ture, radiation, and vibration, quired inspection interval.
Any inspection whose
'results require a shorter inspection interval will tionitoring of snubber service life shall consist over' ride the previous schedule, of the existing station record systems, including the central filing system, maintenance filen, iTo further increase the assurance of snubber re-safety-related voik packageg, and snubber inspection iliability, functional testa vill be performed once records. The record retention proRrams employed at each a efueling cycle. A representqtive sample of the station shall allow station personnel to main-
~
itionally tested.
Observed failures on these samples hydraulic anubbers is 10 years.
The hydraulic
- will require testing of additional units.
onubbers existing locations do not impose undue safety implications on the piping and components be-lIlydraulic anubbers and mechanical anubbers may each cause they are not exposed to excesses in environ-ibe treated an different entities for the above mental conditions. The service life for mechanical
- surveillance programs.
anubbers is 40 years, lifetime of the plant.
The 1
mechanical snubbers are installed in areas of harsh lIlydraulicanubbertestingwillincludestrokingof environmental conditions be:ause of their dependa-
{the snubbers to verify piston movement, lock-up, bility over hydraulic anubbers in these areas.
All isnd bleed.
Functional testing of the mechanical snubber installations have been tigoroughly engineered ianubbers will consist of verification that the providing the necessary safety requirements.
Evalua-l force that initiates free movement of the snubber tions of all snubber locations and environmental jin either tension or compression is less than the conditions justify.the above conservrstive snubber jmaximumbreakawayfrictionforce.
The remaining s e r vic,e lives.
! portion of the functional test consisting of veri-A re-enelyste of the ring boeder Joelga bened u a eccelerstloo
' [ 1 c a t 10lt that the activation (restraining action) response spectre derived from the orlginet auct on heeder enelyele
- is achieved'within the specified range of accelera-report demonstrates that for normel operetloa.plus setemic, pelther tion in both tension and comiiression will not be enuttora looperable. The IIntration of a oesteum of 3 paire or I
- done. This is due to the lack of competitive enubber from each pelt looperable out of 6 polte le conaldereJ a
lenarket able test fixtures available for station use.
- ="'*-
8'"** *' =ar'i' 'h="' **** * "'=== *r*
esfely leJellettely with no enubbers on the ring beeJer the limite-
- 1.herefore, unti1 nuch time as test fa,xtures b.ecome t!. on operetloa and etertus witi. Inoperable enubtore until
- lnvailable, only part (i) of t he test will be per-
,1933 le justifled. This time frene la edequate to
- Iormed; part (ii) wi11 not be done.
- * "**' " ' *** " " " * ***"* *******' d ** * ' " '***' ""
! Unit 2-Amendment No. MM IUnit 3 -Amer.dment Nos.f[J6 7
99b