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{{#Wiki_filter:Attachment No. | {{#Wiki_filter:Attachment No.1 to AEP:NRC:00504 Revised Technical Specifications-Cook Unit No.1 Biiii70265 Siiiii PDR ADQCK 0500031S"-.--*-PDR 4 0 I n' 0 PLANT SYSTEMS 3/4.7.8 SNUBBERS LIMITING CONDITZON FOR OPERATION 3.7.8 All snubbers listed in Table 3.7-4 shall be OPERABLE APPLZCABZLITY: | ||
MODES 1, 2, 3 and 4.(MODES 5 and 6 for snubbers located on systems recpxired OPERABLE in those MODES).ACTION: With one or more snubbers inoperable, within 72 hours replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.8.C on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.SURVEILLANCE RE UZREMENTS 4.7.8 Each snubber shall be demonstrated OPERABLE by perfonnance of the following augmented inservice inspection program and the recpxirements of Specification 4.0.5.a.Visual Zns ections The first inservice visual inspection of snubbezs shall be performed after four months but within 10 months of commencing POWER OPERATION and shall include all snubbers listed in Table 3.7-4.Zf less than two (2)snubbers are found inoperable during the first insezvice visua1 inspection shall be performed 12 months 25%from the date of the first inspection. | |||
Otherwise, subsecpxent | Otherwise, subsecpxent visual inspections shall be performed in accordance with the following schedule: No.Inoperable Snubbers er Ins ection Period Subsecpxent Visual Zn ection Period*" 0 1',3,4 5,6,7 8 or more 18 months 12 months 6 months 124 days 62 days 31 days+25%i 25%-254+25%+25~+-25m The snubbers may be categorized.into two groups: Those accessible and those inaccessible during reactor operation. | ||
No.Inoperable | Each group may be inspected independently in accordance with the above schedule.<<The inspection interval shall not be lengthened more than one step at a time.SThe provisions of Specification 4.0.2 are not applicable. | ||
. | D C Cook Unit 1 3/4 7-28 l | ||
~I'~I I~~~~~~~~II&II~0~~~~I~I~~~~~~~~~~~~~~~~~I~~~~~~~~~-~~0~~~~~~~~~~~~I III e 0~~~II~~0 II~~'.~~~~~~0~~~'.~~~I~~~I~~0~~I~~~~~~~0 II~~~~II~I~~II~0~~~~~I~~~~~~~~0~~~0 I~~0 I~~~~~~~~~~~~~0 II~~0~0~~ | |||
<< | PLANT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) | ||
In addition to the regular sample, snubbers which fai1ed the previous functional test shall be retested during the.next test period.If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position)and the spare snubber shall be retested.Test results of these snubbers may not be included for the re-sampling. | |||
~I'~ | If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design efficiency all snubbers of the same 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.acceptance criteria.For the snubber(s) found inoperable, 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.d.H draulic Snubbers Functional Test Acce tance Criteria The hydraulic snubber functional test shal1 verify that: l.-Activation (restraining action)is achieved within the specified range of velocity or acceleration in both tension and compression. | |||
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.e~Snubber Septi ce 1'+0 Mo<i+<r~~N A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.Concurrent. | |||
with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber listed in Table 3.7-4 and shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.If the indicated service life will be exceeded 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 beyond the date of the next scheduled service life review.This reevaluation, replacement or reconditioning shall be indicated in the records.D C Cook-Unit 1 3/4 7-30 la D G COOi(PLANI-UNIT 1 TABLE SAFETY RELATED HYDRAULIC SNUBBERS~SNUBBER NO.O I HANGER MARK NO 1-GRG-S519 1-GRG-55/7 SYSTEN SNUBBER INSTAI LED ON LOCATION AND EI EVATION REAcToR Cool ANT~ELEv>>68$<<5 1/2 IN PREssURIzER ENOLosURE REAOTCR CooLANT Az 25 ELrv.610'-5" BETwEEN sTEtt~GEN.NO 1 ANO RC PUtIP No I ACCESSIBLE OR HIGH RADIATION I N ACCESS I OLE ZONE ESPEC I ALLY D IFF ICULT-'O RENOVE 1-GRC-S5+1-GRG-S555 REAOTCR cooLA~T Az 41 ELEv 614 10 BELow sTt4~GEN.No>>1 REAcTCR Cool ANT Az 141 ELrv>>614'-2" BELow sTN>>GEN.No 2 No 1-GRG-S562 REAcTCR CCOLANT Az 154 ELEv.610'-5" aETwEEN sTtt>>GEII.No.2 ANO RC puttp No>>2 1-GRG-S564 | |||
"-6RG-$5o6 1-GRG-S5D REAOTCR CooLANT Az$'lp ELrv.614i-10 1/8" SELow sTtt.GEN>>NO~It REAcToR COCLANT Az$/2 ELrv.610'-5" aETwEEN sTtl.GEti~No~4 Atta RC PUNP No RE CTOR Co I T Az 22$EI f v~614'-10 1/8" art.ow STtt~GEI.No.3 YE No | |||
~\TABLE 3.7-4 Dy G COOK PLANT UNIT 1 SAFETY RELATED HYDRAULIC SNUBBERS4 SNUBBER HANGER NO.NARK NO n O 9 1-GRG"S575 I~10 1-GRG-S582 1-GRG-S587 SYSTB1 SNUBBER INSTALLED ON LOCATION AND ELEVATION RKhcTCR Coot.ANT Az 208 ELKV~610I-5" BETWEEN STNe GENT NO~$AND RG PUNP NO~I RKAOTCR GooLANT Az 212 ELKV 617 4 NEAR REACTOR CAVITY I~ALLy ACROSS PRON STII GENT NO~REAGTCR CooLANT.Az 260 ELEvo 622'-4 1/4" IN GONTA INVENT ACCESS IBLE OR HIGH RAD I AT ION INACCESS IBLE ZONE YEs ESPEC IALLY 0 IFF ICULT TO REMVE No 12 15 16 1-GRC-S592 1-GRG-S594 1-GRG-S596 1-GRG-S598 1-GRG-S599 REAOTCR CooLANT Az 292 Et.Ev.68>t-6>/4 IN PRESSURIZER ENCI.OSURK | |||
~REAcTCR cooLANT Az 292 Et.Kv 691'-9" PRESSUR I ZER ENCI.OSURE REAcTQR GooLAN.r Az 285 ELKv 691'-9" PRESSURIZER EN LOSUREe~REAcT0R CooLANT Az 292 ELKS 670 5>/4 IN PREssuRIzER ENCLosURE~RKAcTCR CooLAN r Az 287 ELEvo 672'-4" IN PRESSURIZER ENCLOSURE+ | |||
2. | N N N~~ | ||
e~ | ~~TABLE 3.7-4 Do.G COOK PLANT-UNIT 1 SAFETY RELATED HYDRAULIC SNUBBERSi. | ||
SNUBBER NO.O O, 17 18'20 21 22 HANGER MARK NO 1-GRG-S604 1-GRG-S608 1-GRG-S614 1-FM-S1 1-~S2(L)1-~S2(u)SYSTEM SNUBBER INSTALLED ON LOCATION AND ELEVATION REAOTCR CooLAHT Az 286 ELEv~688 10 lN PRESSURIZER ENCLOSURE0 REAOTCR cooLAtlT Az 286 ELKS 693'-0" PRESSURIZER ENCLOSUREo REAGT0R cooLANT Az 282 El Ev~681 0 ih PRESSURIZER EHCLOSUREo FEEouATER Az 31 ELEV 63 fl 9 BEHlNO STH GEN~NO~1 FEEovATER Az 26" ELEv.633'-6" BEHlNo ST+~GEN.No, 1 FEEDMATER Az 26 ELEv.636'-0" BEN)No ST(4 GEN No i~-1 No O BO No O No ACCESS IBLE OR HIGH RAD IAT ION~ESPEC IALLY'D IFF ICULT INACCESS ISLE.ZONE:...TO REYDVE 23~1-FWS3 1-FH-S4(L) | |||
FEEou*TER Az 20 ELEVE 629 9 BEN INo STHo GEtl~NO~1 F EEOMA TER AZ 154 ELEVe 636'A 3/8U BEHINo Sm~GEN~No.2 No 0 C Cook-Unit 1 3/4 7-34 SNUBBER~NO HANGER NARK NO.Oo Go COOK PLANT-UNIT 1<<TABLE 3.7-4 SAFETY RELATEO SYSTEN SNUBBER INSTALLEO ON LOCATION PNO ELEVATION HYORAULIC SNUBBERSi ACCESS IBLE OR'HIGH RAO IAT ION'ESPECftLCYMQFF'ICULT--=-, INACCESS IBLE" ZONE 70 AEt%VE~n O ,O I 25 1-AF-S4(U) | |||
1-GRG-S555 | FEEDWATER Az 154 ELEVo'640'-8 3/8H BEHlHO STH GERS No 2~<<.N o 26 1-FW-S5 FEEDWATER Az 163 ELEv.634'-9" BEHiHD STH.GER~No~2 27 28 29 1-FW-S6 1-FH-S7 1-F&S8(L)FEEDWATER Az 15(ELEVE 629'-9" BEHIHD GEH.No.2 FEEowATER Az 204 ELEvo 634 9 BEHIHD GEH No 3 FEEDWATER Az 200 ELEVE 633'-6" BEHIHD GEH~No.3 STHo STeo STno I<<'N~~~~1-~S8(U)1 FL'F-S9 1-FW-S10(L) | ||
"-6RG-$ | FEEouaTER Az 200 ELEVo 636 W BEH lHO STHo GEH~No FEEowATER Az 194 El.Ev, 629'-9H BEHlHD STgo GER~No~3 FEEDWATER Az 334o ELEVo 633'-6H BEHIND STHo GEH.No, 4~'<<'4<<' | ||
~\ | ~g~~TABLE 3.7-4 Oa Ca COOK PLANT>>UNIT 1 SAFETY RELATEO HYORAULIG SNUBBERS SNUBBER HANGER NO.NARK NO..n O 33 1-Al-S10(U) | ||
~ | J SYSTEN SNUBBER INSTALLEO ON LOCATION ANO ELEVATION FEEDMATER Az 3344 ELEv 636'-0" BEHIND STN.GEN.No.4 No No ACCESS IBLE OR'IGH RAO IATION'SPEG IALLY-0 IFF ICULT INACCESSIBLE ZONE TO REYQVE 35 1-FW-S11 1-FQ-S12 FEEowATER Az 330 ELEVa 634 9 BEHIND STNa GEN.No.4 FEEDMATER Az$43 ELEVE 629'-9" BEHINQ STNa GEN.No.4 No No 37 I.Ol 1-GCS-S634 1&CS-S637 1-GGS-S7$7 1-NSS-1 CHKN&VoL,CONTROL Az 292 ELEve 613'N GONTAINNENT GHEN&vo'I..coNTloL Az 71 ELEva 608>-10" IN ANNUIIJsa RG puNp SEAL HATER SUPPLY'ETwEEN RC PuNP No.2 AND CRANE HALL, INNKDIATELY uNDER ORATING Az 128 ELEva612'-7 1/8H HAIN sTEAN Az 8 ELEV.639'<<1 1/4N aETNEEN STN GEN~No~I AND Noa 4 Alp sTEAN Az 17 ELEV.635'KTWKEN STNa GENa NO~1 ANO NO~YEs No N No 41 1-ASS-3 MAIN sTEAN Az 172 ELEVa 639 1 1/4" 3EHINO STNe GKNa NO.1 TABLE 3 7-4 Oe Ce COOK PLANT-UNIT 1 SAFETY RELATEO HYORAULIC SNUBBERS>>O O I~o SNUBBER~NO 42 43 HANGER NARK NO 1-HSS-5 1-HSS-7 1-Hss-8 SYSTEH SNUBBER INSTALLEO ON LOCATION ANO ELEVATION HAItt sTEAN Az 165 EI.Eve 635I BETWEEN STN GCNo No~2 ANO Noo3 HAIN sTKAN Az 191 ELEvo 635I BKTMEKN STNeGENoNoo2 AND Noo3 HAIN STEAN Az 184 ELEvo 639'-1 1/4" SETMKEN STHe GEN~No.2 ANo No.3 HA I N STKAH Az 349 ELEvo 635'LNINO STNoGKNeNOo1 ANO NOe4 HAIN sTEAH Az 356 ELEv~639'>>1 1/4" SETMKEN sTN GENT No 1 ANo No.4 ll ACCESS IBLE OR'LIGH RAD IAT ION ESPEC IALLY OIFF ICULT I NACCESS I BLE ZONE TO RBSVE No 47 49 1-GGGW"S278 1-GCGW-S309 1-GGCH-S837 CONPONENT Cool.INC WATER ELEVe 609'N CCW PUNP AREA COHPONCNT Cool.INO WATCR ELKvo 597'-1 5/8" IN PASSACE'NAY NEAR sANPI-INC R00N Aux.BLooi GONPONKNT Cool.INC WATER EI.EV e 621'-0U IN CGW PUHP AREA No 1-GCCW-S838 | ||
~ | |||
~~ | |||
FEEou*TER | |||
FEEDWATER | |||
FEEDWATER | |||
FEEouaTER | |||
~g~~ | |||
'COHPONENT | 'COHPONENT | ||
' | 'Cool Itlo WATKR ELEV~621'-0" IN GGW PUNP AREA 51 1"GCGW-S839 COHPONENT GOOLINC WATKR ELKvo 62'1IMU IN GGW PUHP AREA | ||
' | 'TABLE 3.-4 Di Gi COOK PLANT-UNI'T 1 SNUBBER HANGER NO NARK RO n o 52 1-GCCW-S840 5$1-GCGW-S841 SAFETY RELATED HYDRAULIC SNUBBERSi t~~ACCESS ISLE OR H INACCESSIBLE SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVATION COHI ONENT COOLING WATER ELEV 621'WN IN CGW puHp.AREA GOHPONENT COOLING WATER ELEV, 621'-0" IN CGW PUHP AREA No N fGH RAD IATION.ESPECIAL~1FF IGULT ZONE TO RBSVE 4l i I 54 59 1-GCQ+S842 1-G CGA-S844 1-GBO-S56> | ||
1-GB0-S569 1<<GBD-S57$ | 1-GB0-S569 1<<GBD-S57$ | ||
1-GBD-S574 COHPONENT | 1-GBD-S574 COHPONENT COOLING WATER ELEv 621'WN IN CGW pUHp AREA t GOHPONENT COOLING WATER ELEve 609'Wu Itt GGW putIp ARE*sTHe GEN~BLDMDDMN Az 277 ELEV, 608I-6 1/2" IN ANNut.us STHo GEN~BLDMDDMN Az 278 ELEv~608'&.+2N IN ANNULus STHo GEtt~Bt.oMDoMN.Az-181 EI.EV.607'-10 1/2" IN.ANNuLus STHe GEN~BLDMIADMN Az 181 ELEVE 607-10"t/2N IN ANNULUS A c No No No.No No No: No I No 60 1"GRH-S7A. | ||
.Az- | RESIDUAL HEAT REHOVAL ELEVo 581 I-8 1/2")N I-E RHR puHp Roofs N~~~61 1-GRH-S7B RESIDUAL HEAT REHOVAL ELEv, 581'-4" IN I-E RHR PUHP ROON A No No j~'ABLE 3.7-4 Do Go GOOK PLANT-UNIT 1.SAFETY RELATED HYDRAULIC SNUBBERS~SNUBBER n NO.O 62 I 64 65 66 4 I 67 HANGER HARK NO 1-GRH-S47 1-GRH-S48-1-GDG-S13 1-GDG-S14 1-GS I-S103 1-GS I-S128 1-GSI-S575 SYSTEI'I SNUBBER INSTALLED ON LOCATION AND ELEVATION RESIOUAL Hghl'EHOVAL Eggy 581!IN I-M RHR I'UHP Roofs RESIDUAL HEAT REHOVAL ELKV~580'-6" IN I-M RHR PUHP ROOH I AB ENERGY DIESEL ExNAUST ELEv 596'-7 3/8" I-AB EHKRG~DIEsEL ExIIAUsT ELEV.603'-6" SAFETY INJECTION fl.gv, 573!IN I-E RHR puHp RooH SAFETY INJEOTION El.gv.573!IN I-E RHR PUHP ROOH SAFETY INJECTION ELEv.598'-9 3/8" Az 664 IN AN~uLUS ACCESSIBLE OR HIGH RADIATION I NACCESS I Bl E;i ZONE No No A No ESPECIALLY D IFF IGULT TO REHOVE YKs Yes 69.1-GS I-S657 1-GS I-S707 sAI'KTY INJEOTICN Az 185 ELEv~610'-0" I N ANNuLus SAFET'Y INJEcTICN Az 228 ELEVE 608!-4 7/8" BEN INC RC puHp No.3 No | ||
.~t~~j TABLE ON Go COOK PLANT-UNIT 1~*J-~SAFETY RELATED HYDRAULIC SNUBBERSi c)SNUBBER~NO C)O o=J'71 I HANGER t%NK NO 1-GGTS-S'73(E) | |||
SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVATION GOHTAINHKNT SPRA'Y ELEv 582I-0H IN I-E CONTAINHKNT SPRAY PUIIP ROON ACCESSIBLE OR INACCESS IBLE HIGH RAD IAT ION ESPEG IALLY D IFF IGULT ZONE TO RENOVE N~72~1 GGTS-S7$(W)CoNTA INDENT BPRAY ELEv.582'-0" IN I-E CONTAINIIENT SPRAY PUHP ROON'1-GGTs-s76(B) | |||
.~t~~ | CONTAINMENT SPRAY ELEV.579-6"'INBIDE LEAK DETCGTOR BOX'IPE CHASK N c 7g 1-GGTS-S'76(A) | ||
CONTAIN>ENT SPRAY E<cvo 5'79 M I Hs I oc LEAK DETECTOR BOX'IPE CHASE No No 75 76 1-GGTS-S16QA GONTAINNKNT SPRAY (N)ELEvo 582 M INsiPE'LEAK DKTEOTOR BOX'IPE CHASC 1-GGTS-$16QA GONTA I NIICNT sPRAY ($)ELKv~582~M INfiioE LEAK DETEOTOR BOX'IPE OHASE No No 77 1-GGTS-5161 GONTA INHENT SPRAY (E)ELEv.579'-6H IN I-W GOHTAINNEHT SPRAY PUIIP ROON No 78 1-GCTS-S161 CON TAINNEHT SPRAY (W)ELKV.5'79'-6H IH I>>M CONTAINIIKNT SPRAY PUHP ROOH~~ | |||
CONTAINMENT | O,C~COOK PLANT-UNIT NO 1 ABLE 3.SAI.ETY RELATED OAAULIC SNUBBERS+O O I C+SNUBBER QI~O V9 80 HANGER~R~K$~0 N/A N/A N/A STEAN GcttERATOR No+1 Et.cv, 665'STCAH GENERATOR Et.cv 66!i t~No, 1 STEAH GENERAToR No~1 Eccv, 665t~SYSTEN SNUBBER INSTALLED-ON OCAT AND E E AT 0 ACCESSIBLE OR NACCESS BLE HIGH BAD I Ai IN Z E ESPECIALLY DIFF ICULT 0 4ENOVE-=--YC Ycs Y s 82 N/A N/A STCAH GENERATOR Et.cv.665t STEAH GENERATOR Et.cv 66.'i t No, 1 Noi'No Y s Yes.85 N/A N/A STCAH GENERATOR No~2 Et.cvi 665~STKAH GCtlCRATOR No~2 Et.cv 665t~No Y s n/a STCAH GENERATOR Et.cv.665t~Now 2 87 N/A STFAH GENERA'TOR No~.Et.cv 665t~88 89 N/A pi N%a.STCAH GEttCRAZOR No~Et.cv 665t'STKAH GENERATOR Noy EL,cv, 665t~No YEs Ycs | ||
CONTAIN>ENT | ~~D.C.COOK PLANT-UNIT NO.Z ABLE 3.7"4 SA ELATED IYORAUL C S UBBERSi C)O O I SNUBBER~D 90 91 92 HANGER khLSh N/A N/A N/A SYSTEM SNUBBER INSTALLED OCA A D A STEAH GENERATOR No~Ea,Ev, 665~4 sTEAH GENERAToR.Noi 4)LEVo 6b5~~~sTEAv GERERAToR No+4 ELEvo 665I~ACCESSIBLE OR ACCESS BL HIGH RADIATION ZDN No ESPECIALLY D IFF I LT REED 94 N/A N/A STEAN Ea,EV.STEAN ELEVo GENERATOR No+4 665~.GERERATOR No+4 665~.N N*Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-.4.provided that a revision to Table 3.7-4.is included with the next License Amendment request.Modifications to the"High Radiation Zone" column due to changes in high radiation areas may be made without prior License Amendment provided that a revision to Table 3.7-4 is included with the next License Amendment request. | ||
O,C~ | ADMINISTRATIVE CONTROLS c.Records of facility radiation and contamination surveys.d.Records of radiation exposure for all individuals entering radiation control areas.e.Records of gaseous and liquid radioactive material released to the environs.f.Records of transient or operational cycles for those facility components identified in Table 5.9>>1.g.Records of training and qualification for current members of the plant staff.h.Records of in-service inspections performed pursuant to these Technical Specifications. | ||
i.Records of Quality Assurance activities required by the QA Manual.j.Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.k.Records of meetings of the PNSRC and the NSDRC.1.Records for Environmental Qualification which are covered under the provisions of paragraph 6.13.m.Records of the service lives of hydraulic snubbers listed on Table 3.7-4 including the date at which service life commences and associated installation and maintenance records.6,11 SAuIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with-the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.D C Cook-Unit 1 3/4 6-20 | |||
- | ~~~'~~II~~.~.~~I~~~~~~~~e~~e~~t~~~~~~e~~~~I~~~~~~~~~~~~e~e~I~II~~-~e~t~~~II e~~e~~~-e e II~II~~-I~~~~I~I II~~~~e~~~~e~e e-~~~~II~~~~e I~e e I~~~I e~~~~~~~~~~~~~I~~~~~~~-~~~~ | ||
~~D.C. | -0~0 0 0 0~~~~~~~0 It~~~0~~~~0 0 0~~~~II~0~~~~~~~~I~~0~0~~~~~~~0 II 0 0~~~~~~0~~~0~~~~II It 0~~II~~~~~~0 I~II 0~II~~~0~0~~0~~0~~~0 0~0~~~0 I~~~0~II 0~~~~~~0 I 00 II~~~~0~0~~II~~~I 00 II~~~~0 0~~II 00 I 0~~~~~0~~I~~0~~~~~I~0 II 0 0~0~~~~0~0~0 I~0 0 I 0~~~~0 | ||
ADMINISTRATIVE | ~I~~~~~~~~~~~~~~~Il~r~~~~~~~'~~~~r~~~~~~~~~~~~~l~r~~~~~l r~~~~~II~r~l 0~~~~~~~~r-~r~~r~r~~~l ill I~~~~II r~~r r~~~~r~~~r~r r~~~~I~~~~~I~~~~~~~~~~~~~~~~l 0~~~r~~~~~~l | ||
f. | |||
i. | |||
~~~'~~II~~.~.~~I~~~~~~~~e~~e~~t~~~~~~e~~~~I~~~~~~~~~~~~e~e~I~II~~-~e~t~~~ | |||
-0~ | |||
~I~~~~~~~~~~~~~~~Il~r~~~~~~~'~~~~r~~~~~~~~~~~~~l~r~~~~~ | |||
Attachment No. | Attachment No.2 to AEP:NRC:00504 Revised Technical Specifications-Cook Unit No.2 LANT SYSTEMS I}C$3/4.L'ZMI 7 SNUBB RS fi ING CONDITION FOR OPERATION 3(7..1 All snubbers listed in Table 3.7-9 shall be OPERABLE I APPLICABILITY: | ||
MODES 1, 2, 3 and 4.(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).ACTION: l 4.7.7.1 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.l a.Visual Ins ections The first insezvice visual inspection of snubbers shall be perfo'I zmed after four months but wxthxn 10 months of commencing POWER OPERATION and shall include all snubbers listed in Table 3.7-9.Zf less than two (2)snubbers are found inoperable during the first insezvice visual inspection, the second inservice visual inspection Shall be performed 12 months+25%from the date of the first inspection. | |||
Otherwise, subsequent | Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule: 'o.Inoperable Snubbers Subsequent Visual er Ins ection Period Zns ection Period*¹l With one or more snubbers inoperable, within 72 hours replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.7.1c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.)~(SURVEZLLANCE RE UIREMENTS 0 I 2 3~4 5,6,7 8 or moze 18 months 12 months 6 months 124 days 62 days 31 days J 25%+25~+25m+25%g 25%g 25%I~~I The snubbers may be categorized into two groups: Those.accessible and those inaccessible during reactor operation. | ||
'o.Inoperable | Each group may be inspected independently in accordance with the above schedule.I I I i"The inspection interval shall be lengthened more than one step at a time."The provisions of Specification 4.0.2 are not applicable. | ||
DC Cook-Unit 2 3/4 7-20 PLANT SYSTEMS SURVEILLANCE RE UXREMENTS (Continued) b.Visual 1ns ection Acce tance Criteria Visual inspections shall verify (1)that there are no visible indications of damage or impaired OPERABIL'ZTY, (2)attachments to the foundation or supporting structure are secure, and, (3)in those locations where snubber movement.can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.Snubbers which appear inoperable as a result of.visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1)the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2)the.affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7,7.1.d as applicable. | |||
However, when the fluid port of a hydraulic snubber is found to'be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.c, Functional Tests At least once per 18 months during shutdown, a representative sample QQ@of the total of each type of snubber in use"in the plant shall be functiodally tested either in place or in a bench'test. | |||
For each snubber that does not meet the, functional test acceptance criteria of Specification 4.7.7.l.d an additional 10%of that type of snubber shall be functionally tested).The representative sample selected for functional testing shall include.the various configurations, operating environments and the range of size and capacity of snubbers.At leash 25%of the snubbers in the representative sample shall include snubbers from the following three categories: | |||
1.The first snubber.away from each reactor vessel nozzle 2, Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor, etc.)3.Snubbers within 10 feet of the cEscharge from a safety relief valve Snubbers identified in Table 3.7-9 as"Especially Difficult to Remove"'r in"High Radiation Zones During Shutdown" shaU.also be included in the representative sample.**Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to~alify snubber operability for all design conditions at either the completion of their.fabrication or at a subsequent date, D C Cook-Unit. | |||
2 3/4 7-21 t PLANT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued) | |||
However, | In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position)and the spare snubber shall be retested.Test results of these snubbers may not be included for the re<<sampling, If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in.place, the cause will be evaluated and Xf caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested.This testing requirement shall be independent of the zecpxirements stated above for snubbers not meeting the functional test acceptance criteria, For the snubber(s) found inoperable, 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.d, H draulic Snubbezs Functional Test Acce tance Criteria The hydraulic snubber functional test shall verify that@l.Activation (zestzaining action}is achieved within the specified range of velocity or acceleration in both tension and compression. | |||
c,Functional | 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.e.Snubber Service Life Monitorin A record of the service life of each snubber, the date at which the designated service life commences and the.installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber listed in Table 3.7-9 shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review;If the indicated service life will be exceeded 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 beyond the date of the next scheduled service life review.This reevaluation, replacement or zeconcb'.tioning shall be indicated in the records.D C Cook-Unit 2 3/4 7-22 | ||
~00 OSAKA RASCAL.C A A.A.~Ae W~AA;>TABLE 3.7-9~-SAFETY RELATED HYORAULIC SNUBBERS~SNUBBFR n.NO O 1 0 I Ao ft, 2 M~HANGER MARK MO SYSTEM SNUBBER INSTALLED ON LOCATION ANO ELEVATION 2-GRC-S537 REAcTCR GCQLANT Az 25 ELEv~610)-5" Sm GEN~No 1 2-GRC-S538 RLAcTQR CooI.A)IT Az 41 ELEv~614)-10" RG PU)IP No~ACCESSIBLE OR INACCESS I BLE'IGH RAO IAT ION ZONE NO YES ESPEC IALLY D IFF IGULT TO REMVE NO 0 I I 2-GRC-S555 2-GRC-S562 2-GRC-S564 2-GRC-S566 RrAOTCR COCLANT Az 141 ELrv.614'-10 1/8" RG Pu))p No 2 REAOTOR GooLANT Az 154 ELEy, 610)-5" sTq GEN~No.2 REAOTCR CooLANT Az 317 ELEvo 614'-10 1/8N RG Punp No.4 REAcTCR cooLANT Az 331 ELEy 610'-5" ST+GEN No~YES NO'NO~NO NO NO" 2-GRC-.S573 2>>GRC-5575 REACTOR COOLANT AZ ELEv 614'-10 1/8" REAOTOR CooLANT Az~ELEve 610)-5'T)) | |||
~223 RC PUNP No+0 208'EN.No.3 YES NO 0 10 2&RC-c582 2-GRC-S592 Ra:AOTCA Cool ANT Az 208 EA Ey, 617)-4-7/8U STg.GEN~No~REAOTCR CCOLANT.Az 282 ELEv.683'-3 1/8")N PREssuR)zER ENCLosuRE YES NO C COOK LAI1-UN 7 II ABLE 3.7-9 SAFETY RELATED HYDRAULIC SNUBBERSi SNUBBER uo 11 I M 14 15 16 HANGER~RK NO+2-GRG-S594 2-GRC-5596 Z~ac-S598 2-GRC-S599 2-GRC-S609 2-GRG-S611 SYSTEM SNUBBER INSTALLED ON LOCATION AND ELEVATION RKAcTCR CCCLANT Az 291 ELcv, 683'-3 9/16" IN PRESSURIZER ENCLOSURE REAGTCR CooLANT Az 292 ELcv.682'-11 1/8" IN PRESSURIZER ENCLOSURE REAOTQR CBCLANT Az 279 ELEVE 6'71I-5 1/4" IN PREssURIzcR ENCLOSURE REAGTQR cooLANT Az 289 Eggy, 672I-4 1/2" IN PRESSURIZER ENCLOSURE RKAOTCR Goo!.ANT Az 283 ELgyi 689'5/16" IN PRKSSURIZER ENCLOSURE RKAcTCR cooLANT Az 294 ELcv, 681I-8 7/8" IN PRcssuRIzcR ENCLOsURK ACCESSIBLE OR HIGH RAD IATION INACGESS I BLE'ZONE N NO NO ESPEC I ALLY D IFF ICUL'.TO RENIVE ES NO NO 18 2WRC-S624 17, 2-.GRG-S62$ | |||
1. | REAcTCR'cooLANT Az 277.ELcv.682'-9 1/16N IN PRESSURIZER ENCLOSURE 1 REAGT0R GCCLANT Az 247, ELEVE 615IA ABCVE REI IKI'ANK~~fg NO TABLE 3.7-9 SAFETY RELATEO HYORAULIC SNUBBERS~SNUBBER RO 20 24 C7 Io Io 19 HANGER MARK RO 2-GRC-S 626 2-GRG-S5?9 2-GRG-S630 2-GRG-S 632 2-GRC-S631 2-GRC-S@7 SYSTEN SNUBBER INSTALLEO ON LOCATION ANO ELEVATION REACTOR COOLANT AZ 284 EI.Ev 692~3/16 PRESSURIZER ENCLOSURE REAcTCR GCCLANT Az 283 ELrv.687'-4 1/16" IN PRESSURIZER ENCLOSURE REACTOR COOLANT AZ 291 ELEv.672'-7 11/16" IN*PRESSURIZER ENCLOSURE RrAGTCR CooLANT Az 291 ELEVE 669'-3 11/16" IN PRESSURIZER INCLOSURE REAOTCR CooLANT Az 291 ELEVR 670'l1 11/16N PRESSURIZER ENCLOSURE REAcTCR GooLANT Az 260 ELEVE 622'-4 1/4N sT peal Igf.TANK NO NO NO 0 ACCESSIBLE OR HIGH RAOIATION ESPECIALLY D IFF IGUL I NACCESS I BLE ZONE-RENOVE 25, 2-R4-S1 FEEowATER Az 31 ELEv.634-9N NEAR STIIY GEN~No+1 NO NO 26 2-FW-S2(L) | ||
.FEEouATER Az 264 ELEve 633'-6N NEAR STIIY GEN NO 1 NO TABLE 3.7"9 I!SAFETY RELATED HYDRAULIC SNUBBERSi SIIUBBER ,~tl0/I I HANGER HA!!K NO 2-FM-S2(u) | |||
SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVATION f'Ecow*TER Az 26 ELEVe 636/W NEAR STt1~GCN NOe 1 ACCESSIBLE OR INACCESSIBLE HIGH RAD IAT ION ESPEC IALLY 0 IFF IC ZONE TO RBSVE NO 28 29 30.31 32 35 2-FM-S3 2-FM-S4(L) 2-FW-S4(U) 2-FW-S5 2-F14-S6 2-FM-S'7 2-rW-S&(L) 2~S&(u)FccowATER Az 20 ELEVE 629'-9" NEAR STNe GCN~No~1 FKEowATER Az 155 ELEVe 637'-0N NEAR STHe GEN~NO~2 FKEDwATKR Az 155 ELEV 641'-0" NCAR STH GKN~No 2 FEKDwATER Az 163 ELEVe 634'-9" NCAR STN.GCN~No 2 FKEowATER Az 157 ELrv 629'-9" NEAR STN.GENT No 2 FKCDwATCR Az 204 ELr.v.634'.-9" NEAR STNe GEN~No~3 FEEDwATER Az 200 ELrv 633'-6" NcAR STg.GEN, No Fccnw*Tca Az 200 ELrv~636/M NEAR STHe GEN~NO~NO NO 0 NO NO NO NO NO 0 NO NO~ | |||
~I v~~~HANGER~RK~O SNUBBER No O 0 I 37 2-R4-S9 2 FM-S10(L)2-FWW10(u) 38 39 2-FM-S11 Fo 40 2-FM-S12 2-GB0-S563(Q 2-G8 0-S563(U)42 43 2MB D-S569(L)44'-GBD-S569(U | |||
2. | |||
e. | |||
~ | |||
~ | |||
REAcTCR' | |||
.FEEouATER | |||
~ | |||
)2~BO-S568. | )2~BO-S568. | ||
TABLE 3.7-9 SAFETY RELATED HYDRAULIC SNUBBERSi ACCESSIBLE OR I HIGH'RAD IAT'ION'ESPEC IALL'Y D lFF lCUL1~INACCESS I BLE.-', ZONE...... | |||
iTO.'. | iTO.'.RENOVE SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVATION FEED@*TER Az 194 ELcv 629'-9" NEAR.Sm.GKN.No-3 INO.FKEDMATER Az 334.ELKy, 634'-0" NEAR ST~.G N No.4 I NO.FEEDS*TER Az 334.El cd 636 7 NEAR STll~GENo Noe 4 NO INO f KEDHATER Az 330 ELEY~634t 9 HEAR sTlli GEN.No.4 NO NO 1~FEEDMATER Az 343 El.cvv 629t-9U NEAR sTg GKN.No.4 tNO sm GKN.BLOMOOMH Az 275 gLcvo 607'-11'H ANHULUS NO lt i~"~'II I v~~~I'~~Sm.GEN~BLounowN Az 275 El cy, 608t-6U IN ANNUI.Us I sTg.GEN~Bl OQDDMN Az 275 ELKV.607'-11'-'N ANNULUs NO 0 vs~~NO st, GEN~BLowoouN A'z 275 ELcv 608'-6" IN ANNUL.Us t llO NO'TAN GKN~BLOMDOMN Az 264 ELKv.608'-1" IH ANNULUs'O Py | ||
~~~ | ~~~0 C00$PI.AI<f-IjI TABLE 3.7-9 SAFETY RELATED HYDRAUL IC SNUBBERSi SNUBBER~tt HANGER~RK NO>>SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVATION ACCESSIBLE OR HIGH RADIATION ESPEGIAI.LY DIFFICULT INACCESSIBLE ZONE TO RENOVE II6 2-GRH-S6 RESIDUAL HEAT REHOVAL EI.Ev>>581 A RHR'Punp Roon 2E NO NO 4p 2-GRH-S7 2-GRH-S24 2-GRH-S25 RESIDUAI.HEAT REHOVAL ELcv.581'-3" RHR Punp Roon 2E RESIDUAI.HEAT REHOVAL ELcv.581"-0" RHR Punp Roon 2W RESIDUAL HEAT REHOVAL-EI.Ev 580'-6U RHR Punp Roon 2W NO NO NO F GGCW$274 GOHPONCNT COOL ING WATER ELEv.621'0U CGW Punp ARch 2-GCGM-S308 CDHPDNENT GDOL ING WATER ELcv 610'-., 1/2U CGW Punp AREA, 2~C~317 COHPONENT COOL ING MATER ELcv, 621I-O'CW Punp AREA 2CCW-S320 COHpoNENT CooL INO WATcR gLcv>61QIAII GCW PUHp ARch NO NO NO NO~55 2CCW-S519.2-GGCW-S52'1 COHPDNENT Cool ING WATER A4'Q2-.ELcy~623I-4N RG Punp ARch.ConpoNENT GooI.INO WATER Az 132.ELEV, 624~-9U RG Punp AREA NO 2-GCCW-S5~0 COHpoNENT CooLING WATER Az 308 ELcv>>619'-3N RG Punp AREA NO D C COM PLAili-UNI NO.TABLE 3" 9 SAFETY RELATED HYDRAULIC SNUBBERS~SNUBBER NO 57 59'0 I A 61 62 65 HANGER MARK NO 2-GCQI-S838 2-GCCVI-S839 2-GCGltI-SSIIO 2-GCGM-S843 2-GCm-S306 2-GCS-S634 2-GGS-S637 2-GCS-S729 2-YtSS-1 2-VASS-2 SYSTB1 SNUBBER INSTALLED ON LOCATION AND ELEVATION GOtIPONKttT COOLING WATrR EI.EV 621'WN CGM Puttp ARKA GotIPONENT COOLING MATKR ELEv.621t-0" CCW PutIP AREA CotIPONKNT COOL I NG I'IATKR ELEv>>620'Wu CGA Puttp AREA CotIPONKNT COOLING WATER ELKV>>620I-5U CGQ Puttp AREA COMPONENT COOLING MATKR ELEv 596'-2'3/8" CCW Puttp AREA CNEtt&VGL CGNTRGL Az 299 ELEv.613'>>1" IN ANNUI.us CNEtt&VGL. | ||
CoNTRGL Az 72 ELEV.608'-10" Itj AttNULUs CNEtt&VoL. | |||
CGNTRGL Az 234O El Kv~617 IMN Rc PUNP ARKA HA Itt sTEAtI Az 8 ELKS 639t-1 I/4'ETWEEN STN.GEN.No 1*No 4 HA IN sTEAtI Az 17 ELKS 635 W BETltEEN STN>>GEN>>NO~1 AND 4 ACCESSIBLE OR HIGH RADIATION INAGCESS ISLE ZONE NO NO NO NO NO NO NO ESPEC tALLY 0 IFF ICUL)TO REMVE NO NO NO NO NO r'D O OO":<Lail l-IIII'!I!0 R TABI E 3.7-'.I SAFETY RELATED HYORAULIC SNUBBERS a SOBBER.o NO A~o 67 68 HANGER MARK RO 2-HSS-3 2-HSS-4 SYSTEH SNUBBER INSTALLED ON LOCATION AND ELEVATION HAIN STEAN Az 172 ELCVO 639 1 1/4 BETwEEN STNr GEN~NO~2 AtID 3 HAIN sTEAN Az 165 ELEVE 635 W SKTWEEN STN.GcN.No 2 ANo 3 ACCESSIBLE OR it HIGH RAD IAT ION ESPEC IALI.Y 0IFF ICUL.INACCESS I BLE-ZONE TO REHOVE NO NO 69'0 7l'V I C)72 73 74;75'-HSS-5 2-HSS-7 2-GS I-S47 2-GS I-S51 2-GS I-S575 HAIN STctN Az'l91 ELEVO 635 W BETwEEN STN.GcN.No.2 AND HA IN STCAN Az 184 ELEV.639'-1.1/4" BETMEEN STN GcN.No.2 ANo 3 HAIN STEAN AZ 349 ELCV~63$IW BETWEEN STN GEN.No.1 ANo 4 HAIN sTcAN Az 356 ELEv 639'-1 1/4" BcTwKEN STN~GEN.IN'ANO 4 SAFETY INJEOTIDN SYsTcN ELcv.573'-0" SAFETY INJEOTIoN SYsTEN ELcv 573t-0", sAFETY IN JEc T I oN sYBTKN Az 65 ELFv;598'-9 3/8" IN ANNULUB'O NO NO NO NO NO NO NO NO~P.YES | |||
.2-GGCW-S52'1 COHPDNENT | ~C., A...-..i..lil'i,:l!7 l!O.2 TABI E 3.7-9 SAFETY RELATED HYDRAULIC SNUBBERSi SNUBBER HANGER llO HARK RO~SYSTEM SNUBBER INSTALLED ON LOCATION AtlD ELEVATION ACCESS IBLE OR HIGH RAD IAT!ON ESPEG IALLY DIFFICULT INACCESSIBLE | ||
.ZONE TO REN)VE Cl 0 2A I r+77 78 2-GS I-S707 2-GGTS-S61 76 2-GS I-S657 sAFKTY INJEcTISN sYsTEM Az 185 ELEvo 610'-0" IN ANtlULUS CONTAINMENT SPRAY EI.Ev.579-3" GTS PUMP AREA SAFETY Itt JgcT I oN SYsTKM Az 221 ELKvo 608'7 NEAR RG PUMP HOop NO NO NO NO 79'.80 81 2-GGTS-S113(E) 2-GCTS-S I 13)M)ACTS-S114(N) 2-GGTS-S114(S) | |||
GOHTA I NMENZ SPRAY Et.gv 582'-0" GTS PuMP AREA CONTAINMENT SPRAY Eggy 582IWN CTS PUMP ARgA CONTAINMEHT SPRAY ELEV 582 W Itis log LEAK OETKCTOR SOX PIPE CHASE CONTAINMENT SPRAY ELcv.582'-0" INslog LEAK OETKCTOR SOX I'IPK CHASE"A NO NO NO NO 83 2-GCTS-S115(N) 84 2-GGTS-S115(S) | |||
GONTA I NMKNT SPRAY ELEV 579 A INs I oK LEAlc OETKCTOR SOX PIPE CHASE CONTA lttMKNT Sl'RAY ELEv.579'-6" INSIOK LEAK OETKCTOR SOX PIPE CHASE NP NO | |||
~C.,A...-..i..lil'i,:l! | ~~O.C CC4(ILAIII'I'tIIT IIO 2 TABLE 3.I-9 SAFETY RELATER HYBRAULIC SRUBBERS~StIUBBER NG~HANGER.~t\RK t<0 SYSTEM SNUBBER INSTALLED~ON LOCATION Al'8 ELEVATION ACCESS IBI E OR ItIACCESS IBLE NIGH RAG IATIOtI-ESPECIALLY DIFF ICULl ZONE TO RENOVE o O PC Wo Ct 85 I ACTS-S116(E) | ||
. | CptlzA IIINCNT SPRAY ELcva 579'-6" Itis loc LCAK DKTCCTOR QOX PIPE CtIASC NO NO 2-GCT-S116(W) | ||
COMTA I llNCRT>PRAY ELcv 579'-E" Itts toe LKAK OCTCCTOR Sot PIPE CHASE 87 88 N/A N/A STEAN GctlcRATOR No 1 ELcv 665'TKAN GCRERATQR Noi 1 ELcvi 665 NO NO YES ES 89 I 91 92 N/A N/A N/A N/A STKAN GENERAT0R No~1 ELcv 665'TcAN GcllcRATQR No, 1 ELcv 665I STCAN GcllCRATOR NO~2 El.cv.665I STEAN GctlcRAToR No~2 ELcv 665'O NO YES YES ES ES N/A STCAN El cvo Gctt C RA To R No~2 665I ES 94 N/A N/A STcAN GctlcRAToR No~ELcv 665'TKAN GctlcR*ToR Noe EI.KV~665'ES YES ABLE 3.7-9 SAFE RELA EO H'AAULIC SNUBBERS o SNUBBER n~lO A 0 96 I.rt 97 gB IIAH GER~lARI~NO N/A N/A N/A N/A SYSTEH SNUBBER IHSTALI.EO STEAN GCNCRATOR Ho~3 ELcvo 665I~STCAM GENERATOR HO~3 ELcv.665'.STCAM GCNCRATOR HO~ELcvo 665I~STCAM GCNCRATOR HO%4 ELcv.665I~ACCESSIBLE OR ACCESS BLE HIGH RAOIATINI KSPECI ALLY OIFF IQJ Z E TO REHovE I ES ES YES YES 100 I 101 102 N/A N/A H/A STCAM GCNCRATOR HO~.4 ELcvo 665'STCAM GENERATOR HO~El.cv 665>~STCAH GCNCRATOR HO~4 ELEve 665'o NO YES ES*Snubbers may be added to safety related systems without prior License Amendment to Table 3..7-9 provided that a revision to Table 3.7-9 is included with.the next License Amendment request.Modifications to the"High Radiation Zone" column due to changes in high radiation areas may be made without prior License Amendment provided that a revision to Table 3.7-9 is included with the next License Amendment request. | |||
ADMINISTRATIVE CONTROLS e.Records of gaseous and liquid radioactive material released to the environs.f.Records of transient or operational cycles for those facility components identified in Table 5.7-1, g.Records of reactor tests and experiments. | |||
~~O. | h.Records of training and qualification for current members of the plant staff.I Records of in-service inspections performed pursuant to these Technical Specifications. | ||
j.Records of Quality Assurance activities required by the QA Manual.k.Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.1.Records of meetihgs of the PNSRC and the NSDRC.m.Records for Environmental Qualification which are covered under the provisions of paragraph 6.13.n.Records of the service lires of hydraulic snubbers listed on Table 3.7-9 including the date at which service life commences and associated installation and maintenance records.6 ll RADIATION PROTECTION PROGRAM Procedures for'personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.1 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the"control device" or"alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded D.C.Cook-Unit 2 6-20 ADMINISTRATIVE CONTROLS 6.12 HIGH RADZATXON AREA 6.12.1 (Continued) and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit*.Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following: | |||
~ | a.A radiation monitoring device which continuously indicates the radiation dose rate in the area.b.A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset inte-grated dose is received.Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowl-~edgeable of them.c.An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit.6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mxem/hr.Zn addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative.control of the Shift Supervisor on duty and/or the Plant Health Physicist. | ||
6.13 ENVIRONMENTAL UALXFICATION 6.13.1 By no later than June 30, 1982 all safety-related electrical ep'pmert in the faciliiy shall be qual'ied in accordance wit:..ah=provisions of: Division of Operating Reactors"Guidelines for Evalu ating Environmental Qualification of Class 1E Electrical Equipment in Operating Reactors" (DOR Guidelines); | |||
or, NUREG-0588"Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," December 1979.Copies of these documents are attached to Order for Modification of License No.DPR-58 dated October 24, 1980.6.13.2 By no later than December 1, 1980, complete and auditible records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NURE&-0588. | |||
ADMINISTRATIVE | Thereafter, such records should be updated and maintained as current as equipment is replaced, further tested, or otherwise further qualified. | ||
f. | *Health Physics.personnel shall be exempt from.the RWP issuance require>>.'ent during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high'radiation areas;"'.C.COOK-UNIT 2 6-21 | ||
h. | |||
j. | |||
a. | |||
. | |||
6. | |||
or,NUREG-0588 " | |||
Thereafter, | |||
* | |||
C.COOK- | |||
ZANT SYSTEMS ASES 3/4.7.6 EsF vENTILATIoN sYsTEM The OPERABILITY of the ESF ventilation system ensures that radio-active materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environment. | |||
The operation of this system and the resultant effect on offsite dosage cal-culations was assumed in the accident analyses.3/4 7 7 HYDRAULIC 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 nonsafety-related systems and then only if their failure of failure of the system on which they are installed, would have no adverse effect on any safety-related system.The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbezs found during an inspection. | |||
3/ | Inspections performed before that interval has elapsed may be used as a new reference.point to determine the next inspection. | ||
Inspections performed | However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%)may not be used to lengthen the required inspection interval.Any inspection whose results required a shorter inspection interval will override the previous schedule.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 generical'y susceptible, and verified by insezvice 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 aze similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration. | ||
However, | 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 adversly 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.D.C.COOK-UNIT 2 B 3/4 7-5 LANT SYSTEMS ASES To provide assuranc<: | ||
of snubber functional reliability< | |||
a representative sample of the installed sr>><t hers will be functionally tested during plant shutdowns at 18 month int<<rvals, Observed failures of these sample snubbezs shall require functional t<-<: ting of additional units.The service life of a snubber is evaluated via manufactured input and information through consid<.r<xtion of the snubber service conditions and associated installation an<I maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high tempezature area, etc...).The zequir<ment to monitor the snubber service life is included to ensure that the snubbezs periodically undergo a performance evaluation in view of their age and operating conditions. | |||
Generically susceptible | These records will provide statistical b'<<;us foz future consideration of snubbex service life.The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation. | ||
3/4.7.8 SEALED"SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emltters, is based on 10 CFR 70.39(c)limits for plutonium. | |||
This limitation will ensure that leakage from byproduct, source, and special nuclear material.sources will not exceed allowable intake values.3/4-7~9 PIRE SUPPRESSION SYSTEMS The OPERABILITY of the fixe suppression systems ensures that adequate fire suppression capability is available to confine and extinquish fires occuring in any portion of the facility where safety related equipment is located.The fire suppr<~::sion system consists of the wator syst~~, spray and/or sprimiers, COHalon and fire hose stations.The collec-tive capability of the fir<<<:uppression systems is adequate to minimize potential damage to safety x<.lated equipment and is a major element in the facility fire protection pzogram.In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to sezvx.ce.D C.COOK UNIT 2 B 3/4 7-6 PLANT SYSTEMS In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.The requirement for a twenty-four hour report to the Commission provides for prompt evalua-tion of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.3/4.7~10 PENETRATION PIRE BARRIERS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to~adjacent portions of the facility.This design feature minimizes the f possibility of a single fire rapidly involving several areas of the t facility prior to detection and extinguishment. | |||
The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections. | |||
During periods of time when the barriers are not functional, a con-tinuous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier is restored'o functional status.D.C.COOK-UNIT 2 B 3/4 7-7}} | |||
3/4.7. | |||
Revision as of 06:46, 6 July 2018
ML17334A337 | |
Person / Time | |
---|---|
Site: | Cook |
Issue date: | 11/11/1981 |
From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
To: | |
Shared Package | |
ML17334A336 | List: |
References | |
NUDOCS 8111170265 | |
Download: ML17334A337 (43) | |
Text
Attachment No.1 to AEP:NRC:00504 Revised Technical Specifications-Cook Unit No.1 Biiii70265 Siiiii PDR ADQCK 0500031S"-.--*-PDR 4 0 I n' 0 PLANT SYSTEMS 3/4.7.8 SNUBBERS LIMITING CONDITZON FOR OPERATION 3.7.8 All snubbers listed in Table 3.7-4 shall be OPERABLE APPLZCABZLITY:
MODES 1, 2, 3 and 4.(MODES 5 and 6 for snubbers located on systems recpxired OPERABLE in those MODES).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 OPERABLE status and perform an engineering evaluation per Specification 4.7.8.C on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.SURVEILLANCE RE UZREMENTS 4.7.8 Each snubber shall be demonstrated OPERABLE by perfonnance of the following augmented inservice inspection program and the recpxirements of Specification 4.0.5.a.Visual Zns ections The first inservice visual inspection of snubbezs shall be performed after four months but within 10 months of commencing POWER OPERATION and shall include all snubbers listed in Table 3.7-4.Zf less than two (2)snubbers are found inoperable during the first insezvice visua1 inspection shall be performed 12 months 25%from the date of the first inspection.
Otherwise, subsecpxent visual inspections shall be performed in accordance with the following schedule: No.Inoperable Snubbers er Ins ection Period Subsecpxent Visual Zn ection Period*" 0 1',3,4 5,6,7 8 or more 18 months 12 months 6 months 124 days 62 days 31 days+25%i 25%-254+25%+25~+-25m The snubbers may be categorized.into two groups: Those accessible and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.<<The inspection interval shall not be lengthened more than one step at a time.SThe provisions of Specification 4.0.2 are not applicable.
D C Cook Unit 1 3/4 7-28 l
~I'~I I~~~~~~~~II&II~0~~~~I~I~~~~~~~~~~~~~~~~~I~~~~~~~~~-~~0~~~~~~~~~~~~I III e 0~~~II~~0 II~~'.~~~~~~0~~~'.~~~I~~~I~~0~~I~~~~~~~0 II~~~~II~I~~II~0~~~~~I~~~~~~~~0~~~0 I~~0 I~~~~~~~~~~~~~0 II~~0~0~~
PLANT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued)
In addition to the regular sample, snubbers which fai1ed the previous functional test shall be retested during the.next test period.If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position)and the spare snubber shall be retested.Test results of these snubbers may not be included for the re-sampling.
If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design efficiency all snubbers of the same 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.acceptance criteria.For the snubber(s) found inoperable, 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.d.H draulic Snubbers Functional Test Acce tance Criteria The hydraulic snubber functional test shal1 verify that: l.-Activation (restraining action)is achieved within the specified range of velocity or acceleration in both tension and compression.
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.e~Snubber Septi ce 1'+0 Mo<i+<r~~N A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.Concurrent.
with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber listed in Table 3.7-4 and shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.If the indicated service life will be exceeded 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 beyond the date of the next scheduled service life review.This reevaluation, replacement or reconditioning shall be indicated in the records.D C Cook-Unit 1 3/4 7-30 la D G COOi(PLANI-UNIT 1 TABLE SAFETY RELATED HYDRAULIC SNUBBERS~SNUBBER NO.O I HANGER MARK NO 1-GRG-S519 1-GRG-55/7 SYSTEN SNUBBER INSTAI LED ON LOCATION AND EI EVATION REAcToR Cool ANT~ELEv>>68$<<5 1/2 IN PREssURIzER ENOLosURE REAOTCR CooLANT Az 25 ELrv.610'-5" BETwEEN sTEtt~GEN.NO 1 ANO RC PUtIP No I ACCESSIBLE OR HIGH RADIATION I N ACCESS I OLE ZONE ESPEC I ALLY D IFF ICULT-'O RENOVE 1-GRC-S5+1-GRG-S555 REAOTCR cooLA~T Az 41 ELEv 614 10 BELow sTt4~GEN.No>>1 REAcTCR Cool ANT Az 141 ELrv>>614'-2" BELow sTN>>GEN.No 2 No 1-GRG-S562 REAcTCR CCOLANT Az 154 ELEv.610'-5" aETwEEN sTtt>>GEII.No.2 ANO RC puttp No>>2 1-GRG-S564
"-6RG-$5o6 1-GRG-S5D REAOTCR CooLANT Az$'lp ELrv.614i-10 1/8" SELow sTtt.GEN>>NO~It REAcToR COCLANT Az$/2 ELrv.610'-5" aETwEEN sTtl.GEti~No~4 Atta RC PUNP No RE CTOR Co I T Az 22$EI f v~614'-10 1/8" art.ow STtt~GEI.No.3 YE No
~\TABLE 3.7-4 Dy G COOK PLANT UNIT 1 SAFETY RELATED HYDRAULIC SNUBBERS4 SNUBBER HANGER NO.NARK NO n O 9 1-GRG"S575 I~10 1-GRG-S582 1-GRG-S587 SYSTB1 SNUBBER INSTALLED ON LOCATION AND ELEVATION RKhcTCR Coot.ANT Az 208 ELKV~610I-5" BETWEEN STNe GENT NO~$AND RG PUNP NO~I RKAOTCR GooLANT Az 212 ELKV 617 4 NEAR REACTOR CAVITY I~ALLy ACROSS PRON STII GENT NO~REAGTCR CooLANT.Az 260 ELEvo 622'-4 1/4" IN GONTA INVENT ACCESS IBLE OR HIGH RAD I AT ION INACCESS IBLE ZONE YEs ESPEC IALLY 0 IFF ICULT TO REMVE No 12 15 16 1-GRC-S592 1-GRG-S594 1-GRG-S596 1-GRG-S598 1-GRG-S599 REAOTCR CooLANT Az 292 Et.Ev.68>t-6>/4 IN PRESSURIZER ENCI.OSURK
~REAcTCR cooLANT Az 292 Et.Kv 691'-9" PRESSUR I ZER ENCI.OSURE REAcTQR GooLAN.r Az 285 ELKv 691'-9" PRESSURIZER EN LOSUREe~REAcT0R CooLANT Az 292 ELKS 670 5>/4 IN PREssuRIzER ENCLosURE~RKAcTCR CooLAN r Az 287 ELEvo 672'-4" IN PRESSURIZER ENCLOSURE+
N N N~~
~~TABLE 3.7-4 Do.G COOK PLANT-UNIT 1 SAFETY RELATED HYDRAULIC SNUBBERSi.
SNUBBER NO.O O, 17 18'20 21 22 HANGER MARK NO 1-GRG-S604 1-GRG-S608 1-GRG-S614 1-FM-S1 1-~S2(L)1-~S2(u)SYSTEM SNUBBER INSTALLED ON LOCATION AND ELEVATION REAOTCR CooLAHT Az 286 ELEv~688 10 lN PRESSURIZER ENCLOSURE0 REAOTCR cooLAtlT Az 286 ELKS 693'-0" PRESSURIZER ENCLOSUREo REAGT0R cooLANT Az 282 El Ev~681 0 ih PRESSURIZER EHCLOSUREo FEEouATER Az 31 ELEV 63 fl 9 BEHlNO STH GEN~NO~1 FEEovATER Az 26" ELEv.633'-6" BEHlNo ST+~GEN.No, 1 FEEDMATER Az 26 ELEv.636'-0" BEN)No ST(4 GEN No i~-1 No O BO No O No ACCESS IBLE OR HIGH RAD IAT ION~ESPEC IALLY'D IFF ICULT INACCESS ISLE.ZONE:...TO REYDVE 23~1-FWS3 1-FH-S4(L)
FEEou*TER Az 20 ELEVE 629 9 BEN INo STHo GEtl~NO~1 F EEOMA TER AZ 154 ELEVe 636'A 3/8U BEHINo Sm~GEN~No.2 No 0 C Cook-Unit 1 3/4 7-34 SNUBBER~NO HANGER NARK NO.Oo Go COOK PLANT-UNIT 1<<TABLE 3.7-4 SAFETY RELATEO SYSTEN SNUBBER INSTALLEO ON LOCATION PNO ELEVATION HYORAULIC SNUBBERSi ACCESS IBLE OR'HIGH RAO IAT ION'ESPECftLCYMQFF'ICULT--=-, INACCESS IBLE" ZONE 70 AEt%VE~n O ,O I 25 1-AF-S4(U)
FEEDWATER Az 154 ELEVo'640'-8 3/8H BEHlHO STH GERS No 2~<<.N o 26 1-FW-S5 FEEDWATER Az 163 ELEv.634'-9" BEHiHD STH.GER~No~2 27 28 29 1-FW-S6 1-FH-S7 1-F&S8(L)FEEDWATER Az 15(ELEVE 629'-9" BEHIHD GEH.No.2 FEEowATER Az 204 ELEvo 634 9 BEHIHD GEH No 3 FEEDWATER Az 200 ELEVE 633'-6" BEHIHD GEH~No.3 STHo STeo STno I<<'N~~~~1-~S8(U)1 FL'F-S9 1-FW-S10(L)
FEEouaTER Az 200 ELEVo 636 W BEH lHO STHo GEH~No FEEowATER Az 194 El.Ev, 629'-9H BEHlHD STgo GER~No~3 FEEDWATER Az 334o ELEVo 633'-6H BEHIND STHo GEH.No, 4~'<<'4<<'
~g~~TABLE 3.7-4 Oa Ca COOK PLANT>>UNIT 1 SAFETY RELATEO HYORAULIG SNUBBERS SNUBBER HANGER NO.NARK NO..n O 33 1-Al-S10(U)
J SYSTEN SNUBBER INSTALLEO ON LOCATION ANO ELEVATION FEEDMATER Az 3344 ELEv 636'-0" BEHIND STN.GEN.No.4 No No ACCESS IBLE OR'IGH RAO IATION'SPEG IALLY-0 IFF ICULT INACCESSIBLE ZONE TO REYQVE 35 1-FW-S11 1-FQ-S12 FEEowATER Az 330 ELEVa 634 9 BEHIND STNa GEN.No.4 FEEDMATER Az$43 ELEVE 629'-9" BEHINQ STNa GEN.No.4 No No 37 I.Ol 1-GCS-S634 1&CS-S637 1-GGS-S7$7 1-NSS-1 CHKN&VoL,CONTROL Az 292 ELEve 613'N GONTAINNENT GHEN&vo'I..coNTloL Az 71 ELEva 608>-10" IN ANNUIIJsa RG puNp SEAL HATER SUPPLY'ETwEEN RC PuNP No.2 AND CRANE HALL, INNKDIATELY uNDER ORATING Az 128 ELEva612'-7 1/8H HAIN sTEAN Az 8 ELEV.639'<<1 1/4N aETNEEN STN GEN~No~I AND Noa 4 Alp sTEAN Az 17 ELEV.635'KTWKEN STNa GENa NO~1 ANO NO~YEs No N No 41 1-ASS-3 MAIN sTEAN Az 172 ELEVa 639 1 1/4" 3EHINO STNe GKNa NO.1 TABLE 3 7-4 Oe Ce COOK PLANT-UNIT 1 SAFETY RELATEO HYORAULIC SNUBBERS>>O O I~o SNUBBER~NO 42 43 HANGER NARK NO 1-HSS-5 1-HSS-7 1-Hss-8 SYSTEH SNUBBER INSTALLEO ON LOCATION ANO ELEVATION HAItt sTEAN Az 165 EI.Eve 635I BETWEEN STN GCNo No~2 ANO Noo3 HAIN sTKAN Az 191 ELEvo 635I BKTMEKN STNeGENoNoo2 AND Noo3 HAIN STEAN Az 184 ELEvo 639'-1 1/4" SETMKEN STHe GEN~No.2 ANo No.3 HA I N STKAH Az 349 ELEvo 635'LNINO STNoGKNeNOo1 ANO NOe4 HAIN sTEAH Az 356 ELEv~639'>>1 1/4" SETMKEN sTN GENT No 1 ANo No.4 ll ACCESS IBLE OR'LIGH RAD IAT ION ESPEC IALLY OIFF ICULT I NACCESS I BLE ZONE TO RBSVE No 47 49 1-GGGW"S278 1-GCGW-S309 1-GGCH-S837 CONPONENT Cool.INC WATER ELEVe 609'N CCW PUNP AREA COHPONCNT Cool.INO WATCR ELKvo 597'-1 5/8" IN PASSACE'NAY NEAR sANPI-INC R00N Aux.BLooi GONPONKNT Cool.INC WATER EI.EV e 621'-0U IN CGW PUHP AREA No 1-GCCW-S838
'COHPONENT
'Cool Itlo WATKR ELEV~621'-0" IN GGW PUNP AREA 51 1"GCGW-S839 COHPONENT GOOLINC WATKR ELKvo 62'1IMU IN GGW PUHP AREA
'TABLE 3.-4 Di Gi COOK PLANT-UNI'T 1 SNUBBER HANGER NO NARK RO n o 52 1-GCCW-S840 5$1-GCGW-S841 SAFETY RELATED HYDRAULIC SNUBBERSi t~~ACCESS ISLE OR H INACCESSIBLE SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVATION COHI ONENT COOLING WATER ELEV 621'WN IN CGW puHp.AREA GOHPONENT COOLING WATER ELEV, 621'-0" IN CGW PUHP AREA No N fGH RAD IATION.ESPECIAL~1FF IGULT ZONE TO RBSVE 4l i I 54 59 1-GCQ+S842 1-G CGA-S844 1-GBO-S56>
1-GB0-S569 1<<GBD-S57$
1-GBD-S574 COHPONENT COOLING WATER ELEv 621'WN IN CGW pUHp AREA t GOHPONENT COOLING WATER ELEve 609'Wu Itt GGW putIp ARE*sTHe GEN~BLDMDDMN Az 277 ELEV, 608I-6 1/2" IN ANNut.us STHo GEN~BLDMDDMN Az 278 ELEv~608'&.+2N IN ANNULus STHo GEtt~Bt.oMDoMN.Az-181 EI.EV.607'-10 1/2" IN.ANNuLus STHe GEN~BLDMIADMN Az 181 ELEVE 607-10"t/2N IN ANNULUS A c No No No.No No No: No I No 60 1"GRH-S7A.
RESIDUAL HEAT REHOVAL ELEVo 581 I-8 1/2")N I-E RHR puHp Roofs N~~~61 1-GRH-S7B RESIDUAL HEAT REHOVAL ELEv, 581'-4" IN I-E RHR PUHP ROON A No No j~'ABLE 3.7-4 Do Go GOOK PLANT-UNIT 1.SAFETY RELATED HYDRAULIC SNUBBERS~SNUBBER n NO.O 62 I 64 65 66 4 I 67 HANGER HARK NO 1-GRH-S47 1-GRH-S48-1-GDG-S13 1-GDG-S14 1-GS I-S103 1-GS I-S128 1-GSI-S575 SYSTEI'I SNUBBER INSTALLED ON LOCATION AND ELEVATION RESIOUAL Hghl'EHOVAL Eggy 581!IN I-M RHR I'UHP Roofs RESIDUAL HEAT REHOVAL ELKV~580'-6" IN I-M RHR PUHP ROOH I AB ENERGY DIESEL ExNAUST ELEv 596'-7 3/8" I-AB EHKRG~DIEsEL ExIIAUsT ELEV.603'-6" SAFETY INJECTION fl.gv, 573!IN I-E RHR puHp RooH SAFETY INJEOTION El.gv.573!IN I-E RHR PUHP ROOH SAFETY INJECTION ELEv.598'-9 3/8" Az 664 IN AN~uLUS ACCESSIBLE OR HIGH RADIATION I NACCESS I Bl E;i ZONE No No A No ESPECIALLY D IFF IGULT TO REHOVE YKs Yes 69.1-GS I-S657 1-GS I-S707 sAI'KTY INJEOTICN Az 185 ELEv~610'-0" I N ANNuLus SAFET'Y INJEcTICN Az 228 ELEVE 608!-4 7/8" BEN INC RC puHp No.3 No
.~t~~j TABLE ON Go COOK PLANT-UNIT 1~*J-~SAFETY RELATED HYDRAULIC SNUBBERSi c)SNUBBER~NO C)O o=J'71 I HANGER t%NK NO 1-GGTS-S'73(E)
SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVATION GOHTAINHKNT SPRA'Y ELEv 582I-0H IN I-E CONTAINHKNT SPRAY PUIIP ROON ACCESSIBLE OR INACCESS IBLE HIGH RAD IAT ION ESPEG IALLY D IFF IGULT ZONE TO RENOVE N~72~1 GGTS-S7$(W)CoNTA INDENT BPRAY ELEv.582'-0" IN I-E CONTAINIIENT SPRAY PUHP ROON'1-GGTs-s76(B)
CONTAINMENT SPRAY ELEV.579-6"'INBIDE LEAK DETCGTOR BOX'IPE CHASK N c 7g 1-GGTS-S'76(A)
CONTAIN>ENT SPRAY E<cvo 5'79 M I Hs I oc LEAK DETECTOR BOX'IPE CHASE No No 75 76 1-GGTS-S16QA GONTAINNKNT SPRAY (N)ELEvo 582 M INsiPE'LEAK DKTEOTOR BOX'IPE CHASC 1-GGTS-$16QA GONTA I NIICNT sPRAY ($)ELKv~582~M INfiioE LEAK DETEOTOR BOX'IPE OHASE No No 77 1-GGTS-5161 GONTA INHENT SPRAY (E)ELEv.579'-6H IN I-W GOHTAINNEHT SPRAY PUIIP ROON No 78 1-GCTS-S161 CON TAINNEHT SPRAY (W)ELKV.5'79'-6H IH I>>M CONTAINIIKNT SPRAY PUHP ROOH~~
O,C~COOK PLANT-UNIT NO 1 ABLE 3.SAI.ETY RELATED OAAULIC SNUBBERS+O O I C+SNUBBER QI~O V9 80 HANGER~R~K$~0 N/A N/A N/A STEAN GcttERATOR No+1 Et.cv, 665'STCAH GENERATOR Et.cv 66!i t~No, 1 STEAH GENERAToR No~1 Eccv, 665t~SYSTEN SNUBBER INSTALLED-ON OCAT AND E E AT 0 ACCESSIBLE OR NACCESS BLE HIGH BAD I Ai IN Z E ESPECIALLY DIFF ICULT 0 4ENOVE-=--YC Ycs Y s 82 N/A N/A STCAH GENERATOR Et.cv.665t STEAH GENERATOR Et.cv 66.'i t No, 1 Noi'No Y s Yes.85 N/A N/A STCAH GENERATOR No~2 Et.cvi 665~STKAH GCtlCRATOR No~2 Et.cv 665t~No Y s n/a STCAH GENERATOR Et.cv.665t~Now 2 87 N/A STFAH GENERA'TOR No~.Et.cv 665t~88 89 N/A pi N%a.STCAH GEttCRAZOR No~Et.cv 665t'STKAH GENERATOR Noy EL,cv, 665t~No YEs Ycs
~~D.C.COOK PLANT-UNIT NO.Z ABLE 3.7"4 SA ELATED IYORAUL C S UBBERSi C)O O I SNUBBER~D 90 91 92 HANGER khLSh N/A N/A N/A SYSTEM SNUBBER INSTALLED OCA A D A STEAH GENERATOR No~Ea,Ev, 665~4 sTEAH GENERAToR.Noi 4)LEVo 6b5~~~sTEAv GERERAToR No+4 ELEvo 665I~ACCESSIBLE OR ACCESS BL HIGH RADIATION ZDN No ESPECIALLY D IFF I LT REED 94 N/A N/A STEAN Ea,EV.STEAN ELEVo GENERATOR No+4 665~.GERERATOR No+4 665~.N N*Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-.4.provided that a revision to Table 3.7-4.is included with the next License Amendment request.Modifications to the"High Radiation Zone" column due to changes in high radiation areas may be made without prior License Amendment provided that a revision to Table 3.7-4 is included with the next License Amendment request.
ADMINISTRATIVE CONTROLS c.Records of facility radiation and contamination surveys.d.Records of radiation exposure for all individuals entering radiation control areas.e.Records of gaseous and liquid radioactive material released to the environs.f.Records of transient or operational cycles for those facility components identified in Table 5.9>>1.g.Records of training and qualification for current members of the plant staff.h.Records of in-service inspections performed pursuant to these Technical Specifications.
i.Records of Quality Assurance activities required by the QA Manual.j.Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.k.Records of meetings of the PNSRC and the NSDRC.1.Records for Environmental Qualification which are covered under the provisions of paragraph 6.13.m.Records of the service lives of hydraulic snubbers listed on Table 3.7-4 including the date at which service life commences and associated installation and maintenance records.6,11 SAuIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with-the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.D C Cook-Unit 1 3/4 6-20
~~~'~~II~~.~.~~I~~~~~~~~e~~e~~t~~~~~~e~~~~I~~~~~~~~~~~~e~e~I~II~~-~e~t~~~II e~~e~~~-e e II~II~~-I~~~~I~I II~~~~e~~~~e~e e-~~~~II~~~~e I~e e I~~~I e~~~~~~~~~~~~~I~~~~~~~-~~~~
-0~0 0 0 0~~~~~~~0 It~~~0~~~~0 0 0~~~~II~0~~~~~~~~I~~0~0~~~~~~~0 II 0 0~~~~~~0~~~0~~~~II It 0~~II~~~~~~0 I~II 0~II~~~0~0~~0~~0~~~0 0~0~~~0 I~~~0~II 0~~~~~~0 I 00 II~~~~0~0~~II~~~I 00 II~~~~0 0~~II 00 I 0~~~~~0~~I~~0~~~~~I~0 II 0 0~0~~~~0~0~0 I~0 0 I 0~~~~0
~I~~~~~~~~~~~~~~~Il~r~~~~~~~'~~~~r~~~~~~~~~~~~~l~r~~~~~l r~~~~~II~r~l 0~~~~~~~~r-~r~~r~r~~~l ill I~~~~II r~~r r~~~~r~~~r~r r~~~~I~~~~~I~~~~~~~~~~~~~~~~l 0~~~r~~~~~~l
Attachment No.2 to AEP:NRC:00504 Revised Technical Specifications-Cook Unit No.2 LANT SYSTEMS I}C$3/4.L'ZMI 7 SNUBB RS fi ING CONDITION FOR OPERATION 3(7..1 All snubbers listed in Table 3.7-9 shall be OPERABLE I APPLICABILITY:
MODES 1, 2, 3 and 4.(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).ACTION: l 4.7.7.1 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.l a.Visual Ins ections The first insezvice visual inspection of snubbers shall be perfo'I zmed after four months but wxthxn 10 months of commencing POWER OPERATION and shall include all snubbers listed in Table 3.7-9.Zf less than two (2)snubbers are found inoperable during the first insezvice visual inspection, the second inservice visual inspection Shall be performed 12 months+25%from the date of the first inspection.
Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule: 'o.Inoperable Snubbers Subsequent Visual er Ins ection Period Zns ection Period*¹l 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 4.7.7.1c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.)~(SURVEZLLANCE RE UIREMENTS 0 I 2 3~4 5,6,7 8 or moze 18 months 12 months 6 months 124 days 62 days 31 days J 25%+25~+25m+25%g 25%g 25%I~~I The snubbers may be categorized into two groups: Those.accessible and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.I I I i"The inspection interval shall be lengthened more than one step at a time."The provisions of Specification 4.0.2 are not applicable.
DC Cook-Unit 2 3/4 7-20 PLANT SYSTEMS SURVEILLANCE RE UXREMENTS (Continued) b.Visual 1ns ection Acce tance Criteria Visual inspections shall verify (1)that there are no visible indications of damage or impaired OPERABIL'ZTY, (2)attachments to the foundation or supporting structure are secure, and, (3)in those locations where snubber movement.can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.Snubbers which appear inoperable as a result of.visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1)the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2)the.affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7,7.1.d as applicable.
However, when the fluid port of a hydraulic snubber is found to'be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.c, Functional Tests At least once per 18 months during shutdown, a representative sample QQ@of the total of each type of snubber in use"in the plant shall be functiodally tested either in place or in a bench'test.
For each snubber that does not meet the, functional test acceptance criteria of Specification 4.7.7.l.d an additional 10%of that type of snubber shall be functionally tested).The representative sample selected for functional testing shall include.the various configurations, operating environments and the range of size and capacity of snubbers.At leash 25%of the snubbers in the representative sample shall include snubbers from the following three categories:
1.The first snubber.away from each reactor vessel nozzle 2, Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor, etc.)3.Snubbers within 10 feet of the cEscharge from a safety relief valve Snubbers identified in Table 3.7-9 as"Especially Difficult to Remove"'r in"High Radiation Zones During Shutdown" shaU.also be included in the representative sample.**Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to~alify snubber operability for all design conditions at either the completion of their.fabrication or at a subsequent date, D C Cook-Unit.
2 3/4 7-21 t PLANT SYSTEMS SURVEILLANCE RE UIREMENTS (Continued)
In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position)and the spare snubber shall be retested.Test results of these snubbers may not be included for the re<<sampling, If any snubber selected for functional testing either fails to lockup or fails to move, i.e., frozen in.place, the cause will be evaluated and Xf caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested.This testing requirement shall be independent of the zecpxirements stated above for snubbers not meeting the functional test acceptance criteria, For the snubber(s) found inoperable, 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.d, H draulic Snubbezs Functional Test Acce tance Criteria The hydraulic snubber functional test shall verify that@l.Activation (zestzaining action}is achieved within the specified range of velocity or acceleration in both tension and compression.
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.e.Snubber Service Life Monitorin A record of the service life of each snubber, the date at which the designated service life commences and the.installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber listed in Table 3.7-9 shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review;If the indicated service life will be exceeded 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 beyond the date of the next scheduled service life review.This reevaluation, replacement or zeconcb'.tioning shall be indicated in the records.D C Cook-Unit 2 3/4 7-22
~00 OSAKA RASCAL.C A A.A.~Ae W~AA;>TABLE 3.7-9~-SAFETY RELATED HYORAULIC SNUBBERS~SNUBBFR n.NO O 1 0 I Ao ft, 2 M~HANGER MARK MO SYSTEM SNUBBER INSTALLED ON LOCATION ANO ELEVATION 2-GRC-S537 REAcTCR GCQLANT Az 25 ELEv~610)-5" Sm GEN~No 1 2-GRC-S538 RLAcTQR CooI.A)IT Az 41 ELEv~614)-10" RG PU)IP No~ACCESSIBLE OR INACCESS I BLE'IGH RAO IAT ION ZONE NO YES ESPEC IALLY D IFF IGULT TO REMVE NO 0 I I 2-GRC-S555 2-GRC-S562 2-GRC-S564 2-GRC-S566 RrAOTCR COCLANT Az 141 ELrv.614'-10 1/8" RG Pu))p No 2 REAOTOR GooLANT Az 154 ELEy, 610)-5" sTq GEN~No.2 REAOTCR CooLANT Az 317 ELEvo 614'-10 1/8N RG Punp No.4 REAcTCR cooLANT Az 331 ELEy 610'-5" ST+GEN No~YES NO'NO~NO NO NO" 2-GRC-.S573 2>>GRC-5575 REACTOR COOLANT AZ ELEv 614'-10 1/8" REAOTOR CooLANT Az~ELEve 610)-5'T))
~223 RC PUNP No+0 208'EN.No.3 YES NO 0 10 2&RC-c582 2-GRC-S592 Ra:AOTCA Cool ANT Az 208 EA Ey, 617)-4-7/8U STg.GEN~No~REAOTCR CCOLANT.Az 282 ELEv.683'-3 1/8")N PREssuR)zER ENCLosuRE YES NO C COOK LAI1-UN 7 II ABLE 3.7-9 SAFETY RELATED HYDRAULIC SNUBBERSi SNUBBER uo 11 I M 14 15 16 HANGER~RK NO+2-GRG-S594 2-GRC-5596 Z~ac-S598 2-GRC-S599 2-GRC-S609 2-GRG-S611 SYSTEM SNUBBER INSTALLED ON LOCATION AND ELEVATION RKAcTCR CCCLANT Az 291 ELcv, 683'-3 9/16" IN PRESSURIZER ENCLOSURE REAGTCR CooLANT Az 292 ELcv.682'-11 1/8" IN PRESSURIZER ENCLOSURE REAOTQR CBCLANT Az 279 ELEVE 6'71I-5 1/4" IN PREssURIzcR ENCLOSURE REAGTQR cooLANT Az 289 Eggy, 672I-4 1/2" IN PRESSURIZER ENCLOSURE RKAOTCR Goo!.ANT Az 283 ELgyi 689'5/16" IN PRKSSURIZER ENCLOSURE RKAcTCR cooLANT Az 294 ELcv, 681I-8 7/8" IN PRcssuRIzcR ENCLOsURK ACCESSIBLE OR HIGH RAD IATION INACGESS I BLE'ZONE N NO NO ESPEC I ALLY D IFF ICUL'.TO RENIVE ES NO NO 18 2WRC-S624 17, 2-.GRG-S62$
REAcTCR'cooLANT Az 277.ELcv.682'-9 1/16N IN PRESSURIZER ENCLOSURE 1 REAGT0R GCCLANT Az 247, ELEVE 615IA ABCVE REI IKI'ANK~~fg NO TABLE 3.7-9 SAFETY RELATEO HYORAULIC SNUBBERS~SNUBBER RO 20 24 C7 Io Io 19 HANGER MARK RO 2-GRC-S 626 2-GRG-S5?9 2-GRG-S630 2-GRG-S 632 2-GRC-S631 2-GRC-S@7 SYSTEN SNUBBER INSTALLEO ON LOCATION ANO ELEVATION REACTOR COOLANT AZ 284 EI.Ev 692~3/16 PRESSURIZER ENCLOSURE REAcTCR GCCLANT Az 283 ELrv.687'-4 1/16" IN PRESSURIZER ENCLOSURE REACTOR COOLANT AZ 291 ELEv.672'-7 11/16" IN*PRESSURIZER ENCLOSURE RrAGTCR CooLANT Az 291 ELEVE 669'-3 11/16" IN PRESSURIZER INCLOSURE REAOTCR CooLANT Az 291 ELEVR 670'l1 11/16N PRESSURIZER ENCLOSURE REAcTCR GooLANT Az 260 ELEVE 622'-4 1/4N sT peal Igf.TANK NO NO NO 0 ACCESSIBLE OR HIGH RAOIATION ESPECIALLY D IFF IGUL I NACCESS I BLE ZONE-RENOVE 25, 2-R4-S1 FEEowATER Az 31 ELEv.634-9N NEAR STIIY GEN~No+1 NO NO 26 2-FW-S2(L)
.FEEouATER Az 264 ELEve 633'-6N NEAR STIIY GEN NO 1 NO TABLE 3.7"9 I!SAFETY RELATED HYDRAULIC SNUBBERSi SIIUBBER ,~tl0/I I HANGER HA!!K NO 2-FM-S2(u)
SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVATION f'Ecow*TER Az 26 ELEVe 636/W NEAR STt1~GCN NOe 1 ACCESSIBLE OR INACCESSIBLE HIGH RAD IAT ION ESPEC IALLY 0 IFF IC ZONE TO RBSVE NO 28 29 30.31 32 35 2-FM-S3 2-FM-S4(L) 2-FW-S4(U) 2-FW-S5 2-F14-S6 2-FM-S'7 2-rW-S&(L) 2~S&(u)FccowATER Az 20 ELEVE 629'-9" NEAR STNe GCN~No~1 FKEowATER Az 155 ELEVe 637'-0N NEAR STHe GEN~NO~2 FKEDwATKR Az 155 ELEV 641'-0" NCAR STH GKN~No 2 FEKDwATER Az 163 ELEVe 634'-9" NCAR STN.GCN~No 2 FKEowATER Az 157 ELrv 629'-9" NEAR STN.GENT No 2 FKCDwATCR Az 204 ELr.v.634'.-9" NEAR STNe GEN~No~3 FEEDwATER Az 200 ELrv 633'-6" NcAR STg.GEN, No Fccnw*Tca Az 200 ELrv~636/M NEAR STHe GEN~NO~NO NO 0 NO NO NO NO NO 0 NO NO~
~I v~~~HANGER~RK~O SNUBBER No O 0 I 37 2-R4-S9 2 FM-S10(L)2-FWW10(u) 38 39 2-FM-S11 Fo 40 2-FM-S12 2-GB0-S563(Q 2-G8 0-S563(U)42 43 2MB D-S569(L)44'-GBD-S569(U
)2~BO-S568.
TABLE 3.7-9 SAFETY RELATED HYDRAULIC SNUBBERSi ACCESSIBLE OR I HIGH'RAD IAT'ION'ESPEC IALL'Y D lFF lCUL1~INACCESS I BLE.-', ZONE......
iTO.'.RENOVE SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVATION FEED@*TER Az 194 ELcv 629'-9" NEAR.Sm.GKN.No-3 INO.FKEDMATER Az 334.ELKy, 634'-0" NEAR ST~.G N No.4 I NO.FEEDS*TER Az 334.El cd 636 7 NEAR STll~GENo Noe 4 NO INO f KEDHATER Az 330 ELEY~634t 9 HEAR sTlli GEN.No.4 NO NO 1~FEEDMATER Az 343 El.cvv 629t-9U NEAR sTg GKN.No.4 tNO sm GKN.BLOMOOMH Az 275 gLcvo 607'-11'H ANHULUS NO lt i~"~'II I v~~~I'~~Sm.GEN~BLounowN Az 275 El cy, 608t-6U IN ANNUI.Us I sTg.GEN~Bl OQDDMN Az 275 ELKV.607'-11'-'N ANNULUs NO 0 vs~~NO st, GEN~BLowoouN A'z 275 ELcv 608'-6" IN ANNUL.Us t llO NO'TAN GKN~BLOMDOMN Az 264 ELKv.608'-1" IH ANNULUs'O Py
~~~0 C00$PI.AI<f-IjI TABLE 3.7-9 SAFETY RELATED HYDRAUL IC SNUBBERSi SNUBBER~tt HANGER~RK NO>>SYSTEN SNUBBER INSTALLED ON LOCATION AND ELEVATION ACCESSIBLE OR HIGH RADIATION ESPEGIAI.LY DIFFICULT INACCESSIBLE ZONE TO RENOVE II6 2-GRH-S6 RESIDUAL HEAT REHOVAL EI.Ev>>581 A RHR'Punp Roon 2E NO NO 4p 2-GRH-S7 2-GRH-S24 2-GRH-S25 RESIDUAI.HEAT REHOVAL ELcv.581'-3" RHR Punp Roon 2E RESIDUAI.HEAT REHOVAL ELcv.581"-0" RHR Punp Roon 2W RESIDUAL HEAT REHOVAL-EI.Ev 580'-6U RHR Punp Roon 2W NO NO NO F GGCW$274 GOHPONCNT COOL ING WATER ELEv.621'0U CGW Punp ARch 2-GCGM-S308 CDHPDNENT GDOL ING WATER ELcv 610'-., 1/2U CGW Punp AREA, 2~C~317 COHPONENT COOL ING MATER ELcv, 621I-O'CW Punp AREA 2CCW-S320 COHpoNENT CooL INO WATcR gLcv>61QIAII GCW PUHp ARch NO NO NO NO~55 2CCW-S519.2-GGCW-S52'1 COHPDNENT Cool ING WATER A4'Q2-.ELcy~623I-4N RG Punp ARch.ConpoNENT GooI.INO WATER Az 132.ELEV, 624~-9U RG Punp AREA NO 2-GCCW-S5~0 COHpoNENT CooLING WATER Az 308 ELcv>>619'-3N RG Punp AREA NO D C COM PLAili-UNI NO.TABLE 3" 9 SAFETY RELATED HYDRAULIC SNUBBERS~SNUBBER NO 57 59'0 I A 61 62 65 HANGER MARK NO 2-GCQI-S838 2-GCCVI-S839 2-GCGltI-SSIIO 2-GCGM-S843 2-GCm-S306 2-GCS-S634 2-GGS-S637 2-GCS-S729 2-YtSS-1 2-VASS-2 SYSTB1 SNUBBER INSTALLED ON LOCATION AND ELEVATION GOtIPONKttT COOLING WATrR EI.EV 621'WN CGM Puttp ARKA GotIPONENT COOLING MATKR ELEv.621t-0" CCW PutIP AREA CotIPONKNT COOL I NG I'IATKR ELEv>>620'Wu CGA Puttp AREA CotIPONKNT COOLING WATER ELKV>>620I-5U CGQ Puttp AREA COMPONENT COOLING MATKR ELEv 596'-2'3/8" CCW Puttp AREA CNEtt&VGL CGNTRGL Az 299 ELEv.613'>>1" IN ANNUI.us CNEtt&VGL.
CoNTRGL Az 72 ELEV.608'-10" Itj AttNULUs CNEtt&VoL.
CGNTRGL Az 234O El Kv~617 IMN Rc PUNP ARKA HA Itt sTEAtI Az 8 ELKS 639t-1 I/4'ETWEEN STN.GEN.No 1*No 4 HA IN sTEAtI Az 17 ELKS 635 W BETltEEN STN>>GEN>>NO~1 AND 4 ACCESSIBLE OR HIGH RADIATION INAGCESS ISLE ZONE NO NO NO NO NO NO NO ESPEC tALLY 0 IFF ICUL)TO REMVE NO NO NO NO NO r'D O OO":<Lail l-IIII'!I!0 R TABI E 3.7-'.I SAFETY RELATED HYORAULIC SNUBBERS a SOBBER.o NO A~o 67 68 HANGER MARK RO 2-HSS-3 2-HSS-4 SYSTEH SNUBBER INSTALLED ON LOCATION AND ELEVATION HAIN STEAN Az 172 ELCVO 639 1 1/4 BETwEEN STNr GEN~NO~2 AtID 3 HAIN sTEAN Az 165 ELEVE 635 W SKTWEEN STN.GcN.No 2 ANo 3 ACCESSIBLE OR it HIGH RAD IAT ION ESPEC IALI.Y 0IFF ICUL.INACCESS I BLE-ZONE TO REHOVE NO NO 69'0 7l'V I C)72 73 74;75'-HSS-5 2-HSS-7 2-GS I-S47 2-GS I-S51 2-GS I-S575 HAIN STctN Az'l91 ELEVO 635 W BETwEEN STN.GcN.No.2 AND HA IN STCAN Az 184 ELEV.639'-1.1/4" BETMEEN STN GcN.No.2 ANo 3 HAIN STEAN AZ 349 ELCV~63$IW BETWEEN STN GEN.No.1 ANo 4 HAIN sTcAN Az 356 ELEv 639'-1 1/4" BcTwKEN STN~GEN.IN'ANO 4 SAFETY INJEOTIDN SYsTcN ELcv.573'-0" SAFETY INJEOTIoN SYsTEN ELcv 573t-0", sAFETY IN JEc T I oN sYBTKN Az 65 ELFv;598'-9 3/8" IN ANNULUB'O NO NO NO NO NO NO NO NO~P.YES
~C., A...-..i..lil'i,:l!7 l!O.2 TABI E 3.7-9 SAFETY RELATED HYDRAULIC SNUBBERSi SNUBBER HANGER llO HARK RO~SYSTEM SNUBBER INSTALLED ON LOCATION AtlD ELEVATION ACCESS IBLE OR HIGH RAD IAT!ON ESPEG IALLY DIFFICULT INACCESSIBLE
.ZONE TO REN)VE Cl 0 2A I r+77 78 2-GS I-S707 2-GGTS-S61 76 2-GS I-S657 sAFKTY INJEcTISN sYsTEM Az 185 ELEvo 610'-0" IN ANtlULUS CONTAINMENT SPRAY EI.Ev.579-3" GTS PUMP AREA SAFETY Itt JgcT I oN SYsTKM Az 221 ELKvo 608'7 NEAR RG PUMP HOop NO NO NO NO 79'.80 81 2-GGTS-S113(E) 2-GCTS-S I 13)M)ACTS-S114(N) 2-GGTS-S114(S)
GOHTA I NMENZ SPRAY Et.gv 582'-0" GTS PuMP AREA CONTAINMENT SPRAY Eggy 582IWN CTS PUMP ARgA CONTAINMEHT SPRAY ELEV 582 W Itis log LEAK OETKCTOR SOX PIPE CHASE CONTAINMENT SPRAY ELcv.582'-0" INslog LEAK OETKCTOR SOX I'IPK CHASE"A NO NO NO NO 83 2-GCTS-S115(N) 84 2-GGTS-S115(S)
GONTA I NMKNT SPRAY ELEV 579 A INs I oK LEAlc OETKCTOR SOX PIPE CHASE CONTA lttMKNT Sl'RAY ELEv.579'-6" INSIOK LEAK OETKCTOR SOX PIPE CHASE NP NO
~~O.C CC4(ILAIII'I'tIIT IIO 2 TABLE 3.I-9 SAFETY RELATER HYBRAULIC SRUBBERS~StIUBBER NG~HANGER.~t\RK t<0 SYSTEM SNUBBER INSTALLED~ON LOCATION Al'8 ELEVATION ACCESS IBI E OR ItIACCESS IBLE NIGH RAG IATIOtI-ESPECIALLY DIFF ICULl ZONE TO RENOVE o O PC Wo Ct 85 I ACTS-S116(E)
CptlzA IIINCNT SPRAY ELcva 579'-6" Itis loc LCAK DKTCCTOR QOX PIPE CtIASC NO NO 2-GCT-S116(W)
COMTA I llNCRT>PRAY ELcv 579'-E" Itts toe LKAK OCTCCTOR Sot PIPE CHASE 87 88 N/A N/A STEAN GctlcRATOR No 1 ELcv 665'TKAN GCRERATQR Noi 1 ELcvi 665 NO NO YES ES 89 I 91 92 N/A N/A N/A N/A STKAN GENERAT0R No~1 ELcv 665'TcAN GcllcRATQR No, 1 ELcv 665I STCAN GcllCRATOR NO~2 El.cv.665I STEAN GctlcRAToR No~2 ELcv 665'O NO YES YES ES ES N/A STCAN El cvo Gctt C RA To R No~2 665I ES 94 N/A N/A STcAN GctlcRAToR No~ELcv 665'TKAN GctlcR*ToR Noe EI.KV~665'ES YES ABLE 3.7-9 SAFE RELA EO H'AAULIC SNUBBERS o SNUBBER n~lO A 0 96 I.rt 97 gB IIAH GER~lARI~NO N/A N/A N/A N/A SYSTEH SNUBBER IHSTALI.EO STEAN GCNCRATOR Ho~3 ELcvo 665I~STCAM GENERATOR HO~3 ELcv.665'.STCAM GCNCRATOR HO~ELcvo 665I~STCAM GCNCRATOR HO%4 ELcv.665I~ACCESSIBLE OR ACCESS BLE HIGH RAOIATINI KSPECI ALLY OIFF IQJ Z E TO REHovE I ES ES YES YES 100 I 101 102 N/A N/A H/A STCAM GCNCRATOR HO~.4 ELcvo 665'STCAM GENERATOR HO~El.cv 665>~STCAH GCNCRATOR HO~4 ELEve 665'o NO YES ES*Snubbers may be added to safety related systems without prior License Amendment to Table 3..7-9 provided that a revision to Table 3.7-9 is included with.the next License Amendment request.Modifications to the"High Radiation Zone" column due to changes in high radiation areas may be made without prior License Amendment provided that a revision to Table 3.7-9 is included with the next License Amendment request.
ADMINISTRATIVE CONTROLS e.Records of gaseous and liquid radioactive material released to the environs.f.Records of transient or operational cycles for those facility components identified in Table 5.7-1, g.Records of reactor tests and experiments.
h.Records of training and qualification for current members of the plant staff.I Records of in-service inspections performed pursuant to these Technical Specifications.
j.Records of Quality Assurance activities required by the QA Manual.k.Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.1.Records of meetihgs of the PNSRC and the NSDRC.m.Records for Environmental Qualification which are covered under the provisions of paragraph 6.13.n.Records of the service lires of hydraulic snubbers listed on Table 3.7-9 including the date at which service life commences and associated installation and maintenance records.6 ll RADIATION PROTECTION PROGRAM Procedures for'personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.1 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the"control device" or"alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded D.C.Cook-Unit 2 6-20 ADMINISTRATIVE CONTROLS 6.12 HIGH RADZATXON AREA 6.12.1 (Continued) and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit*.Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.A radiation monitoring device which continuously indicates the radiation dose rate in the area.b.A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset inte-grated dose is received.Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowl-~edgeable of them.c.An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit.6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mxem/hr.Zn addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative.control of the Shift Supervisor on duty and/or the Plant Health Physicist.
6.13 ENVIRONMENTAL UALXFICATION 6.13.1 By no later than June 30, 1982 all safety-related electrical ep'pmert in the faciliiy shall be qual'ied in accordance wit:..ah=provisions of: Division of Operating Reactors"Guidelines for Evalu ating Environmental Qualification of Class 1E Electrical Equipment in Operating Reactors" (DOR Guidelines);
or, NUREG-0588"Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," December 1979.Copies of these documents are attached to Order for Modification of License No.DPR-58 dated October 24, 1980.6.13.2 By no later than December 1, 1980, complete and auditible records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NURE&-0588.
Thereafter, such records should be updated and maintained as current as equipment is replaced, further tested, or otherwise further qualified.
- Health Physics.personnel shall be exempt from.the RWP issuance require>>.'ent during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high'radiation areas;"'.C.COOK-UNIT 2 6-21
ZANT SYSTEMS ASES 3/4.7.6 EsF vENTILATIoN sYsTEM The OPERABILITY of the ESF ventilation system ensures that radio-active materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environment.
The operation of this system and the resultant effect on offsite dosage cal-culations was assumed in the accident analyses.3/4 7 7 HYDRAULIC 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 nonsafety-related systems and then only if their failure of failure of the system on which they are installed, would have no adverse effect on any safety-related system.The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbezs found during an inspection.
Inspections performed before that interval has elapsed may be used as a new reference.point to determine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%)may not be used to lengthen the required inspection interval.Any inspection whose results required a shorter inspection interval will override the previous schedule.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 generical'y susceptible, and verified by insezvice 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 aze similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.
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 adversly 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.D.C.COOK-UNIT 2 B 3/4 7-5 LANT SYSTEMS ASES To provide assuranc<:
of snubber functional reliability<
a representative sample of the installed sr>><t hers will be functionally tested during plant shutdowns at 18 month int<<rvals, Observed failures of these sample snubbezs shall require functional t<-<: ting of additional units.The service life of a snubber is evaluated via manufactured input and information through consid<.r<xtion of the snubber service conditions and associated installation an<I maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high tempezature area, etc...).The zequir<ment to monitor the snubber service life is included to ensure that the snubbezs periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statistical b'<<;us foz future consideration of snubbex service life.The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.
3/4.7.8 SEALED"SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emltters, is based on 10 CFR 70.39(c)limits for plutonium.
This limitation will ensure that leakage from byproduct, source, and special nuclear material.sources will not exceed allowable intake values.3/4-7~9 PIRE SUPPRESSION SYSTEMS The OPERABILITY of the fixe suppression systems ensures that adequate fire suppression capability is available to confine and extinquish fires occuring in any portion of the facility where safety related equipment is located.The fire suppr<~::sion system consists of the wator syst~~, spray and/or sprimiers, COHalon and fire hose stations.The collec-tive capability of the fir<<<:uppression systems is adequate to minimize potential damage to safety x<.lated equipment and is a major element in the facility fire protection pzogram.In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to sezvx.ce.D C.COOK UNIT 2 B 3/4 7-6 PLANT SYSTEMS In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.The requirement for a twenty-four hour report to the Commission provides for prompt evalua-tion of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.3/4.7~10 PENETRATION PIRE BARRIERS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to~adjacent portions of the facility.This design feature minimizes the f possibility of a single fire rapidly involving several areas of the t facility prior to detection and extinguishment.
The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.
During periods of time when the barriers are not functional, a con-tinuous fire watch is required to be maintained in the vicinity of the affected barrier until the barrier is restored'o functional status.D.C.COOK-UNIT 2 B 3/4 7-7