ML17334A337

Tech Specs 3.7.8 & 4.7.8 Re Surveillance Requirements for Snubbers

ML17334A337
Person / Time
Site:	Cook
Issue date:	11/11/1981
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17334A336	List: ML17334A335 ML17334A337
References
NUDOCS 8111170265
Download: ML17334A337 (43)

Text

Attachment No. 1 to AEP:NRC:00504 Revised Technical Specifications-Cook Unit No. 1 Biiii70265 PDR ADQCK Siiiii 0500031S " -. -- *-

PDR

I 4 0 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 Subsecpxent Visual er Ins ection Period Zn ection Period*"

18 months + 25%

0 1 '

12 months i 25%

6 months 254

,3,4 124 days + 25%

5,6,7 62 days + 25~

8 or more 31 days + -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

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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 the components supported by the snubber(s) were adversely affected if 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 HANGER SYSTEN SNUBBER INSTAI LED ACCESSIBLE OR HIGH RADIATION ESPEC I ALLY D IFF ICULT -'O NO. MARK NO ON LOCATION AND EI EVATION I N ACCESS I OLE ZONE RENOVE O

1-GRG-S519 REAcToR Cool ANT ~ ELEv>>68$ <<

I 5 1/2 IN PREssURIzER ENOLosURE 1-GRG-55/7 REAOTCR CooLANT Az 25 ELrv. 610'-5" BETwEEN sTEtt ~

GEN. NO 1 ANO RC PUtIP No I 1-GRC-S5+ REAOTCR cooLA~T Az 41 ELEv 614 10 BELow sTt4 ~

GEN. No>> 1 1-GRG-S555 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 REAOTCR CooLANT Az $ 'lp ELrv. 614i-10 1/8" SELow sTtt.

GEN>> NO ~ It

"-6RG-$ 5o6 REAcToR COCLANT Az $ /2 ELrv. 610'-5" aETwEEN sTtl.

GEti ~ No ~ 4 Atta RC PUNP No YE 1-GRG-S5D RE CTOR Co I T Az 22$

EI f v ~ 614'-10 1/8" art.ow STtt ~

GEI. No. 3 No

Dy G COOK PLANT UNIT 1 TABLE 3.7-4

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SAFETY RELATED HYDRAULIC SNUBBERS4 SYSTB1 SNUBBER INSTALLED ACCESS IBLE OR HIGH RAD I AT ION ESPEC IALLY 0 IFF ICULT SNUBBER HANGER ON LOCATION AND ELEVATION INACCESS IBLE ZONE TO REMVE NO. NARK NO nO 1-GRG"S575 RKhcTCR Coot.ANT Az 208 9

ELKV~ 610I-5" BETWEEN STNe YEs No I~ GENT NO ~ $ AND RG PUNP NO ~

I 10 1-GRG-S582 RKAOTCR GooLANT Az 212 ELKV 617 4 NEAR REACTOR CAVITY I~ALLy ACROSS PRON STII GENT NO ~

1-GRG-S587 REAGTCR CooLANT. Az 260 ELEvo 622'-4 1/4" IN GONTA INVENT 12 1-GRC-S592 REAOTCR CooLANT Az 292 Et.Ev. 68>t-6 >/4 IN PRESSURIZER ENCI.OSURK ~

1-GRG-S594 REAcTCR cooLANT Az 292 Et.Kv 691'-9" N N

PRESSUR I ZER ENCI.OSURE 1-GRG-S596 REAcTQR GooLAN.r Az 285 ELKv 691'-9" PRESSURIZER EN LOSUREe 15 1-GRG-S598 ~

REAcT0R CooLANT Az 292 ELKS 670 5 >/4 IN PREssuRIzER ENCLosURE ~

16 1-GRG-S599 RKAcTCR CooLAN r Az 287 ELEvo 672'-4" IN N

PRESSURIZER ENCLOSURE+

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Do. G COOK PLANT - UNIT 1 TABLE 3.7-4 SAFETY RELATED HYDRAULIC SNUBBERSi.

O O,

SNUBBER NO.

17 HANGER MARK NO 1-GRG-S604 SYSTEM SNUBBER INSTALLED ON LOCATION AND ELEVATION REAOTCR CooLAHT Az 286 ACCESS IBLE OR INACCESS ISLE .

HIGH RAD IAT ION ZONE: ...

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ESPEC IALLY'D IFF ICULT TO REYDVE ELEv ~ 688 10 lN PRESSURIZER ENCLOSURE0 No O 18 1-GRG-S608 REAOTCR cooLAtlT Az 286 ELKS 693'-0" PRESSURIZER ENCLOSUREo BO 1-GRG-S614 REAGT0R cooLANT Az 282 El Ev ~ 681 0 ih PRESSURIZER EHCLOSUREo No

'20 1-FM-S1 FEEouATER Az 31 ELEV 63 fl 9 BEHlNO STH GEN ~ NO ~ 1 21 1-~S2(L) FEEovATER Az 26" ELEv. 633'-6" BEHlNo ST+ ~

O GEN. No, 1 22 1-~S2(u) FEEDMATER Az 26 i ~ -1 ELEv. 636'-0" BEN)No ST(4 GEN No No 23 ~

1-FWS3 FEEou*TER Az 20 ELEVE 629 9 BEN INo STHo GEtl ~ NO ~ 1 1-FH-S4(L) 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

Oo Go COOK PLANT

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- UNIT 1 TABLE 3.7-4 SAFETY RELATEO HYORAULIC SNUBBERSi SNUBBER HANGER SYSTEN SNUBBER INSTALLEO ACCESS IBLE OR 'HIGH RAO IAT ION 'ESPECftLCYMQFF'ICULT--=-,

~NO NARK NO. ON LOCATION PNO ELEVATION INACCESS IBLE " ZONE 70 AEt%VE ~

n O

,O 25 1-AF-S4(U) FEEDWATER Az 154 I ELEVo'640'-8 3/8H BEHlHO

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No STH GERS No 2 26 1-FW-S5 FEEDWATER Az 163 ELEv. 634'-9" BEHiHD STH.

GER ~ No ~ 2 27 1-FW-S6 FEEDWATER Az 15(

ELEVE 629'-9" BEHIHD STHo GEH. No. 2 28 1-FH-S7 FEEowATER Az 204 ELEvo 634 9 BEHIHD STeo N GEH No 3 ~ ~

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29 1-F&S8(L) FEEDWATER Az 200 ELEVE 633'-6" BEHIHD STno GEH ~ No. 3 1-~S8(U) FEEouaTER Az 200 ELEVo 636 W BEH lHO STHo GEH ~ No 1 FL'F-S9 FEEowATER Az 194 El.Ev, 629'-9H BEHlHD STgo GER ~ No ~ 3 1-FW-S10(L) FEEDWATER Az 334o ELEVo 633'-6H BEHIND STHo GEH. No, 4

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Oa Ca COOK PLANT>> UNIT 1

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TABLE 3.7-4 SAFETY RELATEO HYORAULIG SNUBBERS J

SNUBBER NO.

HANGER SYSTEN SNUBBER INSTALLEO ACCESS IBLE OR 'IGH RAO IATION 'SPEG IALLY-0 IFF ICULT NARK NO.. ON LOCATION ANO ELEVATION INACCESSIBLE nO ZONE TO REYQVE 33 1-Al-S10(U) FEEDMATER Az 3344 ELEv 636'-0" BEHIND STN.

GEN. No. 4 No No 1-FW-S11 FEEowATER Az 330 ELEVa 634 9 BEHIND STNa GEN. No. 4 No 35 1-FQ-S12 FEEDMATER Az $ 43 ELEVE 629'-9" BEHINQ STNa GEN. No. 4 No 1-GCS-S634 CHKN&VoL,CONTROL Az 292 ELEve 613'N GONTAINNENT YEs N 37 1&CS-S637 GHEN&vo'I..coNTloL Az 71 I . ELEva 608>-10" IN ANNUIIJsa No Ol 1-GGS-S7$ 7 RG puNp SEAL HATER RC PuNP No. 2 SUPPLY'ETwEEN AND CRANE HALL, INNKDIATELY uNDER ORATING Az 128 ELEva612'-7 1/8H 1-NSS-1 HAIN sTEAN Az 8 ELEV. 639'<<1 1/4N aETNEEN STN GEN ~ No ~ I AND Noa 4 No Alp sTEAN Az 17 ELEV. 635'KTWKEN STNa GENa NO ~ 1 ANO NO ~

41 1-ASS-3 MAIN sTEAN Az 172 ELEVa 639 1 1/4" 3EHINO STNe GKNa NO. 1

Oe Ce COOK PLANT - UNIT 1 TABLE 3 7-4 SAFETY RELATEO HYORAULIC SNUBBERS>>

'LIGH ll SNUBBER HANGER SYSTEH SNUBBER INSTALLEO ACCESS IBLE OR RAD IAT ION ESPEC IALLY OIFF ICULT

~NO NARK NO ON LOCATION ANO ELEVATION I NACCESS I BLE ZONE TO RBSVE O

O 42 HAItt sTEAN Az 165 EI.Eve 635I I BETWEEN STN GCNo No ~ 2 ANO Noo3

~o 43 1-HSS-5 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 1-HSS-7 HA I N STKAH Az 349 ELEvo STNoGKNeNOo1 ANO NOe4 635'LNINO 1-Hss-8 HAIN sTEAH Az 356 ELEv~ 639'>>1 1/4" SETMKEN sTN GENT No 1 ANo No. 4 No 47 1-GGGW"S278 CONPONENT Cool.INC WATER ELEVe 609'N CCW PUNP AREA No 1-GCGW-S309 COHPONCNT Cool.INO WATCR ELKvo 597'-1 5/8" IN PASSACE'NAY NEAR sANPI-INC R00N Aux. BLooi 49 1-GGCH-S837 GONPONKNT Cool. INC WATER EI.EV e 621 '-0U IN CGW PUHP AREA 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

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Di Gi COOK PLANT - UNI'T 1 TABLE 3. -4 SAFETY RELATED HYDRAULIC SNUBBERSi t

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SNUBBER HANGER SYSTEN SNUBBER INSTALLED ACCESS ISLE OR H fGH RAD IATION . ESPECIAL~1FF IGULT NO NARK RO ON LOCATION AND ELEVATION INACCESSIBLE ZONE TO RBSVE no 52 1-GCCW-S840 COHI ONENT COOLING WATER 621'WN N ELEV IN CGW puHp. AREA 5$ 1-GCGW-S841 GOHPONENT COOLING WATER ELEV, 621'-0" IN CGW PUHP AREA No 54 1-GCQ+S842 COHPONENT COOLING WATER ELEv 621'WN IN CGW pUHp AREA No t

1-G CGA-S844 GOHPONENT COOLING WATER ELEve 609'Wu Itt GGW putIp ARE* No 4l 1-GBO-S56> sTHe GEN ~ BLDMDDMN Az 277 ELEV, 608I-6 1/2" IN ANNut.us A c No. No:

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1-GB0-S569 STHo GEN ~ BLDMDDMN Az 278 ELEv ~ 608'& .+2N IN ANNULus No 1<<GBD-S57$ STHo GEtt ~ Bt.oMDoMN .Az- 181 EI.EV. 607'-10 1/2" IN. ANNuLus No I

59 1-GBD-S574 STHe GEN ~ BLDMIADMN Az 181 ELEVE 607 -10 "t/2N IN ANNULUS No 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 SAFETY RELATED HYDRAULIC SNUBBERS~

UNIT 1.

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SNUBBER NO.

HANGER HARK NO ON SYSTEI'I SNUBBER INSTALLED LOCATION AND ELEVATION ACCESSIBLE OR I NACCESS I Bl E; HIGH RADIATION i ZONE ESPECIALLY D IFF IGULT TO REHOVE 62 1-GRH-S47 RESIOUAL Hghl'EHOVAL I

Eggy 581! IN I-M RHR I'UHP Roofs No 1-GRH-S48 RESIDUAL HEAT REHOVAL ELKV~ 580'-6" IN I-M RHR PUHP ROOH No 64 GDG-S13 I AB ENERGY DIESEL ExNAUST ELEv 596'-7 3/8" 65 1-GDG-S14 I-AB EHKRG ~ DIEsEL ExIIAUsT ELEV. 603'-6" 66 1-GS I-S103 SAFETY INJECTION fl.gv, 573! IN I-E RHR 4

I puHp RooH A YKs 67 1-GS I-S128 SAFETY INJEOTION El.gv. 573! IN I-E RHR PUHP ROOH No Yes 1-GSI-S575 SAFETY INJECTION ELEv. 598'-9 3/8" Az 664 IN AN~uLUS 69 . 1-GS I-S657 sAI'KTY INJEOTICN Az 185 ELEv ~ 610'-0" I N ANNuLus No 1-GS I-S707 SAFET'Y INJEcTICN Az 228 ELEVE 608!-4 7/8" BEN INC RC puHp No. 3

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TABLE SAFETY RELATED HYDRAULIC SNUBBERSi c) SNUBBER HANGER SYSTEN SNUBBER INSTALLED ACCESSIBLE OR HIGH RAD IAT ION ESPEG IALLY D IFF IGULT

~NO t%NK NO ON LOCATION AND ELEVATION INACCESS IBLE ZONE TO RENOVE C)

O o =J '71 1-GGTS-S'73(E) GOHTAINHKNT SPRA'Y I ELEv 582I-0H IN I-E N

CONTAINHKNT SPRAY PUIIP ROON

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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 N

DETCGTOR BOX'IPE CHASK c 7g 1-GGTS-S'76(A) CONTAIN>ENT SPRAY E<cvo 5'79 M I Hs I oc LEAK No No DETECTOR BOX' IPE CHASE 75 1-GGTS-S16QA GONTAINNKNT SPRAY (N) ELEvo 582 M INsiPE'LEAK No DKTEOTOR BOX'IPE CHASC 76 1-GGTS-$ 16QA GONTA I NIICNT sPRAY

($ ) ELKv~ 582~M INfiioE LEAK No DETEOTOR BOX'IPE OHASE 1-GGTS-5161 GONTA INHENT SPRAY 77 (E) ELEv. 579'-6H IN I-W No GOHTAINNEHT SPRAY PUIIP ROON 78 1-GCTS-S161 CON TAINNEHT SPRAY (W) ELKV. 5'79'-6H IH I>>M CONTAINIIKNT SPRAY PUHP ROOH

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O,C ~ COOK PLANT UNIT NO 1 ABLE 3.

SAI.ETY RELATED OAAULIC SNUBBERS+

SNUBBER HANGER SYSTEN SNUBBER INSTALLED ACCESSIBLE OR HIGH BAD I AiIN ESPECIALLY DIFF ICULT QI~O ~R~K$~0 -ON OCAT AND E E AT 0 NACCESS BLE Z E -

0 4ENOVE-=

O O

I V9 N/A STEAN GcttERATOR No+ 1 Et.cv, 665' YC C+

80 N/A STCAH GENERATOR No, 1 Et.cv 66!i t ~ Ycs N/A STEAH GENERAToR No ~ 1 Y s Eccv, 665t ~

82 N/A STCAH GENERATOR No, 1 Et.cv. 665t No Y s N/A STEAH GENERATOR Noi' Et.cv 66.'i t Yes N/A STCAH GENERATOR No ~ 2 Et.cvi 665 ~ No

.85 N/A STKAH GCtlCRATOR No ~ 2 Et.cv 665t ~ Y s n/a STCAH GENERATOR Now 2 Et.cv. 665t ~

87 N/A STFAH GENERA'TOR No ~

.Et.cv 665t ~

88 N/A STCAH GEttCRAZOR No ~

pi Et.cv 665t' YEs 89 N%a. STKAH GENERATOR Noy EL,cv, 665t ~ No Ycs

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D.C. COOK PLANT - UNIT NO. Z ABLE 3.7"4 SA ELATED IYORAUL C S UBBERSi SNUBBER HANGER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY D IFF I LT C)

~D khLSh OCA A D A ACCESS BL ZDN REED O 90 N/A STEAH GENERATOR No ~

O I Ea,Ev, 665~4 91 N/A sTEAH GENERAToR.Noi 4 No

)LEVo 6b5~ ~

92 N/A ~

sTEAv GERERAToR No+ 4 ELEvo 665I ~

N/A STEAN GENERATOR No+ 4 N

Ea,EV. 665~.

94 N/A STEAN GERERATOR No+ 4 N

ELEVo 665~.

• 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

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Attachment No. 2 to AEP:NRC:00504 Revised Technical Specifications-Cook Unit No. 2

LANT SYSTEMS I}

C$

3/4. 7 SNUBB RS fi L'ZMI 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 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 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 zmed

'I 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*¹ 0 18 months J 25%

I 12 months + 25~

2 6 months + 25m 3~4 124 days + 25%

5,6,7 62 days g 25%

8 or moze 31 days g 25%

I categorized into two groups: Those. accessible and

~

The snubbers may be

~

I 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

PLANT SYSTEMS SURVEILLANCE RE UIREMENTS t

(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

OSAKA RASCAL .C A A.A. ~Ae W~AA; >

~-

~ 00 TABLE 3.7-9 SAFETY RELATED HYORAULIC SNUBBERS~

SNUBBFR HANGER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR 'IGH RAO IAT ION ESPEC IALLY D IFF IGULT

n. NO MARK MO ON LOCATION ANO ELEVATION INACCESS I BLE ZONE TO REMVE O

0 1 2-GRC-S537 REAcTCR GCQLANT Az 25 I

ELEv ~ 610)-5" Sm GEN ~ No 1 NO NO Ao ft, 2 2-GRC-S538 RLAcTQR CooI.A)IT Az 41 M 0 ELEv ~ 614)-10" RG PU)IP No ~ YES

~

2-GRC-S555 RrAOTCR COCLANT Az 141 NO YES ELrv. 614'-10 1/8"

~

RG Pu))p No 2 I 2-GRC-S562 REAOTOR GooLANT Az 154 ELEy, 610)-5" sTq GEN ~ No. 2 I

2-GRC-S564 REAOTCR CooLANT Az 317 ELEvo 614'-10 1/8N RG Punp NO NO No. 4 2-GRC-S566 REAcTCR cooLANT Az 331 ELEy 610'-5" ST+ GEN No ~ 'NO NO

"

2-GRC-. S573 REACTOR COOLANT AZ 223 ELEv 614'-10 1/8" RC PUNP No+ 0 YES 2>>GRC-5575 REAOTOR CooLANT Az 208'EN.

~ ELEve 610)-5'T)) ~ No. 3 NO 0 2&RC-c582 Ra:AOTCA Cool ANT Az 208 EA Ey, 617)-4-7/8U STg. GEN ~ No ~ YES 10 2-GRC-S592 REAOTCR CCOLANT. Az 282 ELEv. 683'-3 1/8" )N PREssuR)zER ENCLosuRE NO

C COOK LAI1 - UN 7 II ABLE 3.7-9 SAFETY RELATED HYDRAULIC SNUBBERSi SNUBBER HANGER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RAD IATION ESPEC I ALLY D IFF ICUL'.

'

uo ~RK NO+ ON LOCATION AND ELEVATION INACGESS I BLE ZONE TO RENIVE 11 2-GRG-S594 RKAcTCR CCCLANT Az 291 I

ELcv, 683'-3 9/16" IN PRESSURIZER ENCLOSURE N M 2-GRC-5596 REAGTCR CooLANT Az 292 ELcv. 682'-11 1/8" IN PRESSURIZER ENCLOSURE Z~ac-S598 REAOTQR CBCLANT Az 279 ELEVE 6'71I-5 1/4" IN PREssURIzcR ENCLOSURE NO ES 14 2-GRC-S599 REAGTQR cooLANT Az 289 Eggy, 672I-4 1/2" IN PRESSURIZER ENCLOSURE 15 2-GRC-S609 RKAOTCR Goo!.ANT Az 283 ELgyi 689' 5/16" IN PRKSSURIZER ENCLOSURE NO 16 2-GRG-S611 RKAcTCR cooLANT Az 294 ELcv, 681I-8 7/8" IN NO NO PRcssuRIzcR ENCLOsURK 17,

~

fg ~

2-.GRG-S62$

REAcTCR 'cooLANT Az 277 .

ELcv. 682'-9 1/16N IN PRESSURIZER ENCLOSURE 1

18 2WRC-S624 REAGT0R GCCLANT Az 247, ELEVE 615IA ABCVE REI IKI'ANK NO

TABLE 3.7-9 SAFETY RELATEO HYORAULIC SNUBBERS~

C7 SNUBBER SYSTEN SNUBBER INSTALLEO HIGH RAOIATION ESPECIALLY D IFF IGUL Io RO HANGER LOCATION ANO ELEVATION ACCESSIBLE OR I NACCESS I BLE ZONE - RENOVE Io MARK RO ON 19 2-GRC-S 626 REACTOR COOLANT AZ 284 EI.Ev 692~ 3/16 PRESSURIZER ENCLOSURE NO NO 20 2-GRG-S5? 9 REAcTCR GCCLANT Az 283 ELrv. 687'-4 1/16" IN PRESSURIZER ENCLOSURE 2-GRG-S630 REACTOR COOLANT AZ 291 ELEv. 672'-7 11/16" IN

• PRESSURIZER ENCLOSURE 2-GRG-S 632 RrAGTCR CooLANT Az 291 ELEVE 669'-3 11/16" IN PRESSURIZER INCLOSURE NO 2-GRC-S631 REAOTCR CooLANT Az 291 ELEVR 670 'l1 11/16N PRESSURIZER ENCLOSURE 24 2-GRC-S@7 REAcTCR GooLANT Az 260 ELEVE 622'-4 1/4N sT peal Igf .

TANK 0 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

I

!

TABLE 3.7"9 SAFETY RELATED HYDRAULIC SNUBBERSi SIIUBBER HANGER SYSTEN SNUBBER INSTALLED ACCESSIBLE OR HIGH RAD IATION ESPEC IALLY 0 IFF IC

, ~tl0 HA!!K NO ON LOCATION AND ELEVATION INACCESSIBLE ZONE TO RBSVE

/

I 2-FM-S2(u) f'Ecow*TER Az 26 I ELEVe 636/W NEAR STt1 ~ GCN NOe 1 NO 28 2-FM-S3 FccowATER Az 20 ELEVE 629'-9" NEAR STNe GCN ~ No ~ 1 NO NO 29 2-FM-S4(L) FKEowATER Az 155 ELEVe 637'-0N NEAR STHe GEN ~ NO ~ 2 NO

30. 2-FW-S4(U) FKEDwATKR Az 155 ELEV 641'-0" NCAR STH GKN ~ No 2 NO 31 2-FW-S5 FEKDwATER Az 163 ELEVe 634'-9" NCAR STN. GCN ~ No 2 0 32 2-F14-S6 FKEowATER Az 157 ELrv 629'-9" NEAR STN. GENT No 2 0 2-FM-S'7 FKCDwATCR Az 204 ELr.v. 634'.-9" NEAR STNe GEN ~ No ~ 3 NO 2-rW-S&(L) FEEDwATER Az 200 ELrv 633'-6" NcAR STg. GEN, No NO NO 35 2~S&(u) Fccnw*Tca Az 200 ELrv ~ 636/M NEAR STHe GEN ~ NO ~ NO NO ~

~

I

~ ~ v ~

TABLE 3.7-9 SAFETY RELATED HYDRAULIC SNUBBERSi SYSTEN SNUBBER INSTALLED ACCESSIBLE OR I HIGH 'RAD IAT'ION 'ESPEC IALL'Y D lFF lCUL1 SNUBBER No HANGER

~RK~O ON LOCATION AND ELEVATION ~ INACCESS I BLE .-', ZONE...... iTO.'. RENOVE O

0 2-R4-S9 FEED@*TER Az 194 I

ELcv 629'-9" NEAR

.Sm. GKN. No- 3 INO 37 2 FM-S10(L) .FKEDMATER Az 334

.ELKy, 634'-0" NEAR ST~. G N No. 4 I NO 38 2-FWW10(u) .FEEDS*TER Az 334

.El cd 636 7 NEAR STll ~ GENo Noe 4 NO INO 39 2-FM-S11 f KEDHATER Az ELEY ~ 634t 9 330 HEAR sTlli GEN. No. 4 1 ~

NO NO Fo 2-FM-S12 40 FEEDMATER Az 343 El.cvv 629t-9U NEAR sTg GKN. No. 4 tNO 2-GB0-S563(Q sm GKN. BLOMOOMH Az 275 gLcvo 607'-11'H ANHULUS NO

~ I' ~ ~ ~ "

lt ' i

~ III v ~ ~

42 2-G8 0-S563(U) Sm. GEN ~ BLounowN Az 275 El cy, 608t-6U IN ANNUI.Us NO 0 I

43 2MBD-S569(L) sTg. GEN ~ Bl OQDDMN Az 275 vs~ ~

ELKV. 607'-11'-'N ANNULUs NO 44 '-GBD-S569(U ) st, GEN ~ BLowoouN A'z 275 ELcv 608'-6" IN ANNUL.Us llOt 2~BO-S568.

ELKv. 608'-1" IH Py ANNULUs'O GKN ~ BLOMDOMN Az 264 NO'TAN

~ ~ ~

0 C00$ PI.AI<f - IjI TABLE 3.7-9 SAFETY RELATED HYDRAULIC SNUBBERSi ACCESSIBLE OR HIGH RADIATION ESPEGIAI.LY DIFFICULT SNUBBER HANGER SYSTEN SNUBBER INSTALLED INACCESSIBLE ZONE TO RENOVE

~tt ~RK NO>> ON LOCATION AND ELEVATION II6 2-GRH-S6 RESIDUAL HEAT REHOVAL EI.Ev>> 581 A RHR 'Punp Roon 2E NO NO 4p 2-GRH-S7 RESIDUAI. HEAT REHOVAL ELcv. 581'-3" RHR Punp Roon 2E NO 2-GRH-S24 RESIDUAI. HEAT REHOVAL ELcv. 581"-0" RHR Punp Roon 2W NO 2-GRH-S25 RESIDUAL HEAT REHOVAL-EI.Ev 580'-6U RHR Punp Roon 2W NO F

GGCW $ 274 GOHPONCNT COOL ING WATER ELEv. 621'0U CGW Punp ARch NO 2-GCGM-S308 CDHPDNENT GDOL ING WATER ELcv 610'- ., 1/2U CGW Punp AREA, NO NO 2~C~317 COHPONENT COOL ING MATER ELcv, 621I-O'CW Punp AREA NO 2CCW-S320 COHpoNENT CooL INO WATcR gLcv> 61QIAII GCW PUHp ARch 2CCW-S519 COHPDNENT Cool ING WATER A4 'Q2-.

ELcy~ 623I-4N RG Punp ARch.

~

55 .2-GGCW-S52'1 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 HANGER SYSTB1 SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPEC tALLY 0 IFF ICUL)

NO MARK NO ON LOCATION AND ELEVATION INAGCESS ISLE ZONE TO REMVE 57 2-GCQI-S838 GOtIPONKttT COOLING WATrR EI.EV 621'WN CGM Puttp ARKA NO 2-GCCVI-S839 GotIPONENT COOLING MATKR ELEv. 621t-0" CCW PutIP AREA NO 2-GCGltI-SSIIO CotIPONKNT COOL I NG I'IATKR 59'0 ELEv>> 620'Wu CGA Puttp AREA NO 2-GCGM-S843 CotIPONKNT COOLING WATER I

ELKV>> 620I-5U CGQ Puttp AREA NO NO A

61 2-GCm-S306 COMPONENT COOLING MATKR ELEv 596'-2 '3/8" CCW Puttp AREA 62 2-GCS-S634 CNEtt&VGL CGNTRGL Az 299 ELEv. 613'>>1" IN ANNUI.us NO NO 2-GGS-S637 CNEtt&VGL. CoNTRGL Az 72 ELEV. 608'-10" Itj AttNULUs NO 2-GCS-S729 CNEtt&VoL. CGNTRGL Az 234O El Kv ~ 617 IMN Rc PUNP ARKA NO 65 2-YtSS-1 HA Itt sTEAtI Az 8 ELKS 639t-1 I/4'ETWEEN STN. GEN. No 1 *No 4 NO NO 2-VASS-2 HA IN sTEAtI Az 17 ELKS 635 W BETltEEN STN>> GEN>> NO ~ 1 AND 4 NO

'

D O OO":< Lail l - IIII'! I!0 R r

TABI E 3.7-'.I SAFETY RELATED HYORAULIC SNUBBERS a SOBBER. HANGER SYSTEH SNUBBER INSTALLED ACCESSIBLE OR it HIGH RAD IATION ESPEC IALI.Y 0IFF ICUL o NO MARK RO ON LOCATION AND ELEVATION . INACCESS I BLE - ZONE TO REHOVE A ~

o 67 2-HSS-3 HAIN STEAN Az 172 ELCVO 639 1 1/4 BETwEEN STNr GEN ~ NO ~ 2 AtID 3 NO 68 2-HSS-4 HAIN sTEAN Az 165 ELEVE 635 W SKTWEEN STN. GcN. No 2 ANo 3 NO 69 HAIN STctN Az 'l91 ELEVO 635 W BETwEEN STN. GcN. No. 2 AND 'O NO

'0 HA IN STCAN Az 184 ELEV. 639'-1.1/4" BETMEEN STN GcN. No. 2 ANo 3 NO NO 75'-HSS-5 2-HSS-7 7l HAIN STEAN AZ 349

'V ELCV ~ 63$ IW BETWEEN I

C)

STN GEN. No. 1 ANo 4 NO NO 72 HAIN sTcAN Az 356 ELEv 639'-1 1/4" BcTwKEN STN ~ GEN. IN' ANO 4 ~

P 73 2-GS I-S47 SAFETY INJEOTIDN SYsTcN ELcv. 573'-0" NO .YES 74; 2-GS I-S51 SAFETY INJEOTIoN SYsTEN ELcv 573t-0", NO 2-GS I-S575 sAFETY INJEc T I oN sYBTKN Az 65 ELFv; 598'-9 3/8" IN ANNULUB NO

~C., A...-.. i ..lil' i,:l!7 l!O. 2 TABI E 3.7-9 SAFETY RELATED HYDRAULIC SNUBBERSi SNUBBER HANGER SYSTEM SNUBBER INSTALLED ACCESS IBLE OR HIGH RAD IAT !ON ESPEG IALLY DIFFICULT llO HARK RO~ ON LOCATION AtlD ELEVATION INACCESSIBLE . ZONE TO REN)VE Cl 0 2-GS I-S657 2A 76 sAFKTY INJEcTISN sYsTEM Az 185 I

ELEvo 610'-0" IN ANtlULUS NO r+

77 2-GS I-S707 SAFETY IttJgcT I oN SYsTKM Az 221 ELKvo 608 '7 NEAR RG PUMP HOop NO 78 2-GGTS-S61 CONTAINMENT SPRAY EI.Ev. 579 -3" GTS PUMP AREA NO NO 79 2-GGTS-S113(E) GOHTA I NMENZ SPRAY NO Et.gv 582'-0" GTS PuMP AREA

'. 80 2-GCTS-S I 13)M) CONTAINMENT SPRAY Eggy 582IWN CTS PUMP ARgA "A NO 81 ACTS-S114(N) CONTAINMEHT SPRAY ELEV 582 W Itis log LEAK OETKCTOR SOX PIPE CHASE NO 2-GGTS-S114(S) CONTAINMENT SPRAY ELcv. 582'-0" INslog LEAK OETKCTOR SOX I'IPK CHASE NO 83 2-GCTS-S115(N) GONTA I NMKNT SPRAY ELEV 579 A INs I oK LEAlc OETKCTOR SOX PIPE CHASE NP 84 2-GGTS-S115(S) CONTA lttMKNT Sl'RAY ELEv. 579'-6" INSIOK LEAK OETKCTOR SOX PIPE CHASE NO

~ ~ O.C CC4( ILAIII' I'tIIT IIO 2 TABLE 3. I-9 SAFETY RELATER HYBRAULIC SRUBBERS~

StIUBBER HANGER. SYSTEM SNUBBER INSTALLED ACCESS IBI E OR NIGH RAG IATIOtI ESPECIALLY DIFF ICULl NG~ ~t\RK t<0 ~ON LOCATION Al'8 ELEVATION ItIACCESS IBLE ZONE TO RENOVE o

O I

PC 85 ACTS-S116(E) CptlzA IIINCNT SPRAY ELcva 579'-6" Itis loc LCAK Wo DKTCCTOR QOX PIPE CtIASC NO NO Ct 2-GCT-S116(W) COMTA I llNCRT >PRAY ELcv 579'-E" Itts toe LKAK OCTCCTOR Sot PIPE CHASE 87 N/A STEAN GctlcRATOR No 1 ELcv NO YES 665'TKAN 88 N/A GCRERATQR Noi 1 ELcvi 665 NO ES 89 N/A STKAN GENERAT0R No ~ 1 I YES ELcv 665'O 665'TcAN N/A GcllcRATQR No, 1 ELcv 665I YES 91 N/A STCAN GcllCRATOR NO ~ 2 El.cv. 665I ES 92 N/A STEAN GctlcRAToR No ~ 2 ELcv NO ES N/A STCAN Gctt C RA To R No ~ 2 El cvo 665I ES 94 N/A STcAN GctlcRAToR No ~

ELcv ES 665'TKAN N/A GctlcR*ToR Noe EI.KV~ 665' YES

ABLE 3.7-9 SAFE RELA EO H'AAULIC SNUBBERS o SNUBBER IIAHGER SYSTEH SNUBBER IHSTALI.EO ACCESSIBLE OR HIGH RAOIATINI KSPECI ALLY OIFF IQJ n ~lO ~lARI~NO ACCESS BLE Z E TO REHovE A

0 I 96 N/A STEAN GCNCRATOR Ho~ 3 I. ELcvo 665I ~ ES rt 97 N/A STCAM GENERATOR HO ~ 3 ELcv. 665'. ES gB N/A STCAM GCNCRATOR HO ~

ELcvo 665I ~ YES N/A STCAM GCNCRATOR HO% 4 ELcv. 665I ~ YES I

100 101 102

• N/A N/A H/A Snubbers may be added provided that a 665'o STCAM GCNCRATOR ELcvo 665'

~

HO STCAM GENERATOR HO ~

El.cv 665>

STCAH GCNCRATOR HO ~

ELEve

~ . 4 4

revision to Table 3.7-9 is included with. the next License Amendment NO to safety related systems without prior License Amendment to Table 3..7-9 request.

YES ES Modifications to the "High Radiation Zone" column due to changes in high made without prior License Amendment provided that a revision to Table 3.7-9 radiation areas may be the next License Amendment request. is included with

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 during the performance of their assigned radiation protection duties, require>>.'ent 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 possibility of a single fire rapidly involving several areas of the

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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