ML20031G761

Amend 74 to License DPR-46,improving Operability & Surveillance Requirements for Hydraulic Snubbers & Adding Similar Requirements for Mechanical Snubbers

ML20031G761
Person / Time
Site:	Cooper
Issue date:	10/07/1981
From:	Ippolito T Office of Nuclear Reactor Regulation
To:
Shared Package
ML20031G762	List: ML20031G761 ML20031G763
References
TAC-08817, TAC-10427, TAC-8817, NUDOCS 8110230632
Download: ML20031G761 (18)

Text

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UNITED STATES y

g NUCLEAR REGULATORY COMMISSION g

E WASHINGTON, D. C. 20555 t

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NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. DPR-46 1.

The Nuclear Regulatory Cbmmission (the Commission) has found that:

A.

The application for amendment by Nebraska Public Power District dated July 15, 1981 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.

The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Commission;

~

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common-t defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

~

2.

Accordingly, the license is amended by changes to the Technical Spec-l ifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility Operating License No. DPR-46 'is l

hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 74, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

8110230632 811007 DR ADOCK 05000298 PDR L

2 3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATdRY COMMISSION A

Thomas.'Ippolito, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

~ Changas to ths Technical Specifications

. Dated:

Octob~er 7,1981 W

e e

4 4

ATTACHMENT'TO ' LICENSE AMENDMENT'NO. 74 MCILITYOPERATINGLICENSENO.DPR-46 DOCKET NO. 50-298 Revise Appendix A as follows:

Remove Insert 137a 137a 137b 137b 137c 137c 137d 137d 137e 137e 137f 1379 137h 1371 137j 137k 1371 153a 153a 153b 229 229 4

4

LIMITIN'; CO:;DITION FDR OPERATION SURVEILLANCE REOUIREMENT 3.6.H Shock Suppressors (Snubbe rs) 4.6.H Shock Suppressors (Snubbers) 1.

During all modes of operation The following surveillance require-except Cold Shutdown and Refuel,

' ments apply to all snubbers listed all safety related snubbers shall in Tables 3.6.1, 3.6.2, and 3.6.3.

be operable except as noted in 3.6.H.2 througn 3.6.H.5 below.

1.

All snubbers shall be visually inspected in accordance with 2.

The snubbers listed in Tables the following schedule:

I 3.6.1, 3.6.2, and 3.6.3 are re-quired to protect the primary Number of Snubbers Next Required coolant system or other safety' Found Inoperable Ins pection related systems or components.

During Inspection Interval All others are therefore exempt or During Inspection f rom these specifications.

Inte rval 3.

With one or more snubbers in-0 18 months + 25%

operable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> re-1 12 months [ 25%

place or restore the inoper-2 6 months f;25%

able snubber (s) to OPERABLE 3, 4 124 days f;25%

s tatus and pe rf o rm an engi-5, 6, 7 62 days j;25%

neering evaluation per 8 or more 31 days j;25%

1 Fjecification 4.6.H.4 on the supported component or The required inspection interval declare the supported system or shall not be lengthened more subsystem inoperable and follow than one step at a time.

the appropriate ACTION state-ment for that system.

Snubbers may be categorized in groups, " accessible" or "inac-4.

If a snubber is determined to be cessible" based on their acces-inoperable while the reactor is sibility for inspection during in the shutdown or refuel mode, reactor operation and by type, the snubber shall be made oper-hydraulic or mechanical.

These able or replaced prior to reactor four groups may be inspected

startup, independently according to the above schedule.

5.

Snubbers may be added to, removed, or substituted for, by analysis, 2.

Visual Inspection Acceptance f rom safety related systems with-Criteria out prior License Amendment to Tab les 3.6.1, 3.6.2, and 3.6.3, Visual inspections shall verify provided that a revision to these (1) that there are no visible tables is included with a subse-indications of damage or impair-quent License Amendment reques t.

ed OPERABILITY, (2) attachments to the foundation or supporting Amendment No. 74

-U@n-

_LL1121::G CO;JDITIO.3 FOR OPEKATIu.

SURVEILudiCE REOU1!Ild:iT 4. 6. 11 Snock Suppressors (Snubbe rs)

(cont'd) structure are secure.

Snubbers 7

wnien appear incperaole as a result of visual inspections may De cetermined OPERABLE for tne purpose of establisning the next visual inspection interval, providing that (1) the csuse of tne rejection is clearly estao-11sned ana remeated for that particular snuober and for otner snubbers tnat may oe generically susceptible; or (2) the af fected snuboer is functionally tested in tne as found condition and determined OPERABLE per Specifi-cations 4.6.11.6 or 4.6.d.7 as applicaole.

ilowever, wnen tne fluid port of a nydraulic snuober is found to be uncevered, the snuboer shall se determined in-operable and cannot be determined OPERABLE via functional testing f or the purpose of establishing

,the next visual inspection inter-val.

All snuboers connectea to an-inoperable comaan hydraulic fluid rese rvoir snall oe counted as inoperable snubbers.

3.

At least once per 18 months cur-ing snutdown, a representative sample, 10% of tne-total of

(

eacn type of snubber in use in l

Ine plant, shall oe functionally l

tested either in place or in a

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benen test.

For eacn snubber tnat does not meet the func-

)

J tional test acceptance criteria of Specification 4.6.11.5 or 4. 6. 11. 0, an additional 10% of tnat type of snubber shall be function-ally tested.

4.

The representative sample select-ed for functional testing shall include various configuration, opera ting environments and the range of size and capacity of snubbers.

Tabler. 3.6. L. 3.6. 2, and 3.6.3 may be used jointly or separately as the basis for tne sampling plan.

Amendment No. 74

-RMEA-

1.I'lITI2G l'0!!DI 10.; r -

JP E t'ATIOd SUlWEILIA.;Cs Ru)CI.sD!a:!T 4.6.H Snock Suporessors (S uuboe rs )

s

- (Cont'C) in aadition to tne regular sam-ple, snubbers wnich failed tne previous functional test shall be retested curing tne next test s

period.

If a spare snubber has x

been installed in place of a f ailed snubber, then born the c

f ailed snubber (if it is repaired

'7-s ~

and installen in anotner position)I

~ '

(, -

and tne spare snubber shall oe s-s retested.

Test results of snese snubbers may not be included for tne resampling.

Permanent or otner exemptions from functional testing for inalvidual snuboers, in hign raalation cones or that are t

difficult to remove may be

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'J granteu by the Commission caly

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if a justifiable oasis for exemption is presented and/or

~1 snubber life oestructive test-ing was performed to qualify 1

,c y

sd

-snubber operability for all 4

s design conditions at eitner rne completion of their fab-

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rication or at a subsequent 3s s

date.

s If at-y snubber selected for

. functional testing eitner fails 4.

to lockup or falls to move, i.e.,

9 '- -cf rozen in place, the cause will s

'.s_

'be evaluated and if caused by i

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manuf acturer or design deficiency c

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all snubbers of the same oesign g'g A

and~ subj ect to tne same defect r.

s s

').

shall~be tested or inspected to determine if tne defect is pre-sent.

Tnis testing requirement s

snall oe ind'ependent of tne re-quirements stated above for snubbers not meeting tne func-

-tional test acceptance criteria.

N.

,o 2

For the snubber (s) found inoper-vs aole, an engineering evaluation g;

s

",s sr.all be performed to determine

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Ine need ' for furtner action or s

testing on af fected components.

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.a +

Amendment No 474 x

\\., ' 1 "K _s I-

_t37c_

s a1

1 LfMXTitlG CuilDITf 0.1 Fat. OP EK4.T80ll I_

.J ALLA:;CE REQUIxGEitT

4. b.11 Snock Suppressors (Snubbers)

(cont't) 5.

liyiraulic Snubbers Functional Test Acceptance Criteria Ine hydraulic snubber functional test snall verify tnat:

1.

Activation (res training act-ion) is acnieveo within the specified range of velocity or acceleration in born tension and compression.

2.

Snubber bleed, or release rate, vnere requirea, is within the specified range in compression or tension.

6.

Mechanical Snabbers Fun _ctional Test Acceptance Criteria The mechanical snubber func-i tional test snall verify tnat:

1.

Tne force that initiates free movement of tne snub-ber rod in either tension or compression is less tnan tne specified maximum crag Corce.

2.

Activation (res. training act-ion) is achieved within the specified range of velocity or acceleration in born tension and compression.

3.

Snubber release rate, unere required, is within the specified range in com-pression or tension.

7.

Snubber Service Life !!onitoring A record of the service life of eacn snubber, the date at unien the designated service life commences and the installation and maintenance records on wnien tne designated service life is based shall oe main-tained as required oy Specif1-cation 6.6.2.J.

Amendment No. 74 g

-137d-

LD11TIMG C0dD1'iX03 PJr. OPE /ATK0i1

-J AVE *LIAJCC REOUInC:..

• . o. !! Snock Suppressors (Snuocers)

(cont'd)

Concurrent vitn tne first in-service visual inspection and at least once per 13 months thereafter, tne installation and maintenance records of eacn snuboet listea in Tables 3.6.1, 3.6.2, ana 3.6.3 shall be reviewed to verify that the indicated service life has not been exceecea or will not be exceeaed prior to the next scneduled snubbe.r service life review.

If tne indicated ser-vice life will be exceedea prior to the next scheauled snubber service life review, tue snubbar service life snall be reevaluatea or the snubber snall be replaced or recondi-tionea so as to extend its service life oeyond the date of Inu next seneauled service life review.

This reevaluation, replacement or reconattioning

.shall be indicatea in the records.

Amendment No. 74

- -137e.

Taole 3.6.1 SAFETY RdLATED INDRAUL.2 S110CK SUPPRESS 011S (S:iUBBERS)

Snubber :lo.

Location Cleva tion BS-S-1 Torus Area 870' BS-S-2 Torus Area 889' BS-S-3 Torus Area 890' BS-S-ll3A Torus Area 890' BS-S-113B Torus Area U91' BS-S-l l6 A Torus Area 889' BS-5-116B Torus Area a89' BS-S-125A Torus Area 892' BS-S-125B Torus Area 891' CS-S-1 S.E. Quad 918' CS-S-2 S.E. Quad 929' CS-S-3 S.E. Quad 946' CS-S-o S.E. Quad 913' CS-S-7 b.E. Quad 929' CS-VE-7 S.E. Quad 694' CS-S-10 Rx Blds, 931' 946' CS-5-il Rx Bldg,.931' 940' CU-S-89 S.E. Torus Area 893' 672' ilP-S-4 S.W. Quad

~

d69' dP-S-11 S.W. Quad JP-S-15 S.W. Quad 874' HP-S-ISA HPCI Rm 865' IIP S-22A HPCI Rm 365' MS-S-1 S.W. Quaa 864' MS-S-2 S.W. Quad d68' MS-S-3 S.W. Quad 880' MS-S-4 S.W. Quad 873' MS-S-7A S.W. Quad 874' MS-S-7B S.W. Quad 874' MS-5-8 Torus Area 865' MS--S-10 Torus Area 899'

.MS-S-11 Torus Area 897' MS-S-11A Torus Area d97' MS-S-12 Torus Arua 888' MS-S-12A Torus Area d89' MS-S-13 "B" RHR Hx Rm 904' MS-S-13A "B" RilR Hx Rm 905' MS-S-13B "B" KilR 11x Rm 911' MS-S-14 "B" RilR Hx Rr 923' MS-5-15 "B" Rilk Hx Rs 934' MS-S-ISA "B" RHR Ex Rm 934' MS-S-16 Torus Area 885' MS-5-16A Torus Area 881' MS S-16B Torus Area 881' Amendment No. 74 9

Tao le 3.,. i SAFETY RELATED HYDRAULIC S;10CE SUPPRESSORS (SJUBBERS) (Cont'c)

Snubber No.

Location Elevatiun MS-5-17 "A" RIIR lix Rm 904' 215 - S - 1 8 "A" RilR Ex Km 905'

!!S-S-19 "A" kilR lix Rm 923' 3

tis-S-20 "A" RRR Ex Rm 934' MS-S-20A "A" Rak Hx R:s 934' M.9-S-23 Torus Area 898' MS-S-24 Torus area 898' MS-S-25 N.E. Quad 877' MS-S-26 N.E. Quan d79' Ms-S-75 "A" R!!R ilx Rm 932' ris-S-7 b "B" RdR Ex Ra 932' d5-S-lllA "A" ki!R ilx Rm 923' RCC-S-3 Rx Blog, 931' 945' RCC-S-4 Rx Bidg 931' 943' RCC-S-20 dx Blog, 931' 953' RCC-S-21 Rx Bldg. 931' 953' RCC-S-22 Rx Bldg, 931' 953' RF-S-1 N.E. Quad 898' RF-S-1A N.E. Quad 896' RF-S-2 N.E. Iorus Area 896' RF-S-3 liPCI Pa 870' RF-S-4 S.U. Torus Area 894' RF-S-5 S.U. Torus Area 897' RF-S-6 S.U. Torus Area 891' RF-S-45C H.d. Quad 882' RF-S-45D N.E. Quad 882' RF-S-46A N.E. Quad 882' RF-S-51A U. E. To rus 897' RF-S-51B N.E. Torus 897' Ril-S-20 Rx Blda, 903' 912' all-S-21 Rx Bldg, 903' 911' RH-S-22 Torus Area 695' RH-S-23 Torus Area 892' Rd-S-24 Torus Area 897' Ril-S-25 H. RHR Ex Rm 927' Kil-S-25A Rx Bldg, 903' 922' Ril-S-26 N. RRR Hx Rm 929' Ril-S-27A "A" Rdk lix Rm 933' 4

RH-S-29 kx Bldg, 903' 904' l

RH-S-30A Torus area 898' Rii-S-30B Torus Area 898' Rti-S-32 Torus Area 894' Rll-S-333 Torus 892' Amendment No. 74

-1378-

Table 3.6.1 SAFI"_Y RELATID liYDRAULIC Sl!UCK SUPPRESSORS (S LUBBERS) (Cant'd)

Snuboer No.

Location 21evation Ril-S-34 Rx Blds, 903' 919' R.1-S-35 S. RHR fix Em 912' RH-S-36 S. R11R 11x Rm 914' Ril-S-37 S. Rilk.04 Rm 91b' Ril-S-38 S. IUIR ilx fun 930' Kii-S-39 S. Rrut aIx R:n 927' Ril-S-40 S. R:ik Hx Rm 915' Rii-S-41 S.W. Quad 873' Ril-S-42 S.W. Quaa 074' Ril-S-43 Torus Area 897' Ril-S-44 S.W. Quad d84' Ril-S-45 S.W. Quad 884' Rll-S-48 li.W. Quaa 884' Rti-S-49 N.W. Quad d85' RIl-S-51 N. RHR lix Rm 914' Rd-S-52 N. R11R Hx Rn 915' RII-S-54 N.W. Quad 873' Ell-S-55 N.W. Quad 874' RH-S-56 N. Ritt lix Ra 927' RH-S-57

3. RIIR dx Rm 927' R11-S-59 Torus Area 696' Ril-S-65 S.W. Quad 887' RH-S-6o Rx Bldg, 903' 907' R11-S-76A Torus area 898' RH-S-70B Torus Area 89d' Itil-S-7 7 Torus Area 690' RH-S-78A Torus Area 897' Ril-S-78B Torus Area 897' R11-4-80 N.W. Quad 889' Ril-S-96A

'tx Bldg, 903' 920' I

kM-S-f,8

1.J. Quad 891' Rt.'-S-lu 3 A S.U. Quad 876' RH-S-107A N.W. Quad 876' SW-R-23A Intake Str.

904' SW-H-23D Intake S tr.

904' SW-H-23E Istake Str.

904' SW-if-23ti Intake Str.

904' e

f Amendment No. 74 m

Table 3.6.2 ACCESSIBLE SAFETY RELATED MECHANICAL SHOC): SLTPRESSORS (SNUBBERS)

Snubber _No.

Location Elevation liS-S-9A Torus Area 894' MS-S-9B Torus Area 894' RH-S-58 "A" RHR Hx Rm 921' RF-S-51C N.E. Torus Area 899' SW-H-23B Intake Str.

904' SW-H-23C Intake Str.

904' SW-H-23F Intake Str.

904' SW-H-23G Intake Str.

904' Amendment Not 74

-1371-

Taole 3.6.3 INACCESSIBLE SAFETY RELATG MECilANICAL SHOCK SUPPRESSORS (SNUBBER 5; Snuboer No.

Locatiott Elevation CS-S-4 Dryvell 947' CS-S-5 Drywell 951' CS-S-8 Drywell 947' CS-S-9 Drywell 951' CU-S-3 A Drywell 925' CU-S-3B Drywell 925' tis-s-21 Drywell 920' riS-s-22 Drywell 919' HS-S-63 Drywell 921'

!!S-S-149A Steam Tunnel, Rx Bldg 918' RF-S-8~

Drywell 924' RF-S-9 Drywell 924' RF-S-10 Drywell 928' RF-S-11 Drywell 924' ks-S-12 Drywell 924' RF-S-13 Drywell 928' RF-S-14 Drywell 925' RF-S-15 Drywell 922' RF-S-16 Drywell 923' RF-S-17 Drywell 927' 924' RF-S-13 Drywell 924' RF-S-19 Drywell RH-S-3 Rr. Under Snielu Plug 972' nti-S-4 Rx Cavity 972' Ril-S-5 Drywell 921' RH-S-6 Drywell 920' Ril-S-7 Dryvell 921' R11-S-SA Drywell 918' kil-S-8 B Drywell 918' Rd-S-9 Drywell 915' Ril-S-10 Dryvell 911' Ril-S-ll Drywell 916' R11-S-13 Drywell 922' RH,S-14 Drywell 921' Ril-S-15 Drywell 922' Rd-S-16 Drywell 917' RH-S-17 Dryvell 917' RH-S-18 Drywell 916' R11-S-19 Drywell 916' RH-S-6 7 Dryvell 917' Ril-S-68 Drywell 917' RH-S-69A Drywell 915' R11-S-69B Drywell 915' Ril-S-70 Drywell 916' Ame'ndment No. 74

_ftna_

Table 3.6.3 IJACCESSIBLE SAFETY RELATU) MCC:lA'11 CAL SHOCK SUPPK2SSORS (SUUBBERS)

(Cont'd)

Snu'cber No.

Location Elevation kii-S-71 Drywell 914' Ril-S-72 Drywell 914' R'l-S-7 2 A Drywell 914' Ril-S-73 Drywell 91b' SS-A2 Drywell 923' SS-A3 Drywell 922' SS-02 Drywell 924' SS-B3 Drywell 922' SS-C2 Drywell 924' SS-C3 Drywell 922' SS-D2 Drywell 923' SS-D3 Drywell 923' SS-7Al Drywell 914' SS-7A2 Drywell 914' SS-7B1 Drywell 914' SS-7B2 Drywell 914' SS-8Al Drywell 917' SS-8A2 Drywell 917' Dryvell 891' SS-1A 898' SS-2A Drywell SS-3Al Drywell 904' SS-3A2 Drywell 904' SS-4A Drywell 909' SS-5A Drywell d98' S S-1B Drywell 891' SS-2B Drywell d98'

,SS-3B1 Drywell 904' SS-3B2 Drywell 904'

~SS-4B Drywell 909' SS-5B Drywell 898' VR-S-1 Drywell 902' VR-S-2 Drywell 919' VR-S-3 Drywell 899' VR-S-4 Drywell 918' VR-S-5A Drywell 903' VR-S-5B Dryvell 903' VR-S-6 Drywell 905' VR-S-7A Drywell 893' VR-S-7B Drywell 893' 4

VR-S-8 Drywell 899' Amendment No. 74

.e

Taole 3.6.3 INACCESSIBLE SAFETY RELATE'.) MECHANICAL SHOCK SUPPRESSURS (S::UBBERS)

(Cont'd)

Snub

• er No.

Location Eleva tion o

VR-H-61D Drywell d97' V3-H-62C Drywell 899' VR-H 63B Drywell 897,'

VR-H-63C Drywell 898' VR-55-9-Y Drywell 919' VR-55-9-Z Drywell 919' VR-55-23-X Drywell 906' VR-55-23-Y Drywell 907' VR-55-26-Z Drywell 906' VR-So-12-Y Drywell 913' VR-50-26-Y Drywell 916' VR-56-24-X Drywell 907' VR-56-24-Z Drywell 910' VR-57-12-Y Drywell 922' VR-58-12-Y Drywell 924' VR-59-7-X Drywell 920' VR-59-7-2 Drywell 920' VR-6 0-7-X Drywell 920' VR-60-7 ~

Drysell 920'

^

VR-61-8 '.s Drywell 919' VR-61-8-Y Drywell 919' VR-61-8-2 Drywell 919' 915' VR-61-17-X Drywell 915' VR-61-17-Z Drywell VR-62-8-X Drywell 922' VR-62-8-Y Drywell 915' VR-62-8-2 Drywell 915' VR-62-17-X Drywell 915' VR-62-17-Z Drywell 915' VR-S-14 Drywell 896' VR-S-32 Drywell 897' VR-3-43 Drywell 894' VR-S-51 Drywell 896' VR-S-87A Drywell 894' VR-S-87B

,Drywell 894' VR-S-88 Drywell 894' VR-H-62B Drywell 899' VR-H-64D Drywell 899' Amendment No. 74

-RJ2R-

BASES:

l-3.6.H and 4.6.H Snubbers Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe trans-iant, while allowing normal thermal motion during startup and chutdown.

The consequence of an inoperable snubber is an increase in the probability of structural damage to piping as a result of a esismic or other event initiating dynamic loads.

It is therefore required that all snubbers required to protect the primary coolant system or any other safety system or component be operable during reactor operation.

Breause the snubber protection is required only during relatively low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacement.

Since plant startup should not cocmence with knowingly defective safety related equipment, Specification 3.6.H.4 prohibits startup with inoperable snubbers.

All safety related snubbers are visually inspected for overall integrity and operability.

The inspection frequency is based upon maintaining a constant level of snubber protection.

Thus the required inspection interval varies inversely with the observed snubber failures.

The number of inoperable snubbers found during a required inspection determines the time interval for the next required inspection.

Ins p,ections performed before that interval has elapsed may be used as a new ref erence 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 require a shorter inspection interval will override the previous schedule.

When the cause of the rejection of a snubber is clearly established and re=edied for that snubber and for any other snubbers that may be generically susceptible, and/or verified by functional testing, that snubber may be exempted from being counted as inoperable.

Gznerically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions, such as temperature, radiation and vibration.

l l

l Amendment No. 74 l

-153a-I -

~

BASES (cont'd)

Whet a snubber is found inoperable, an engineering evaluation is per-formed, in addition to the detensination of the snubber mode of failure, in order to determine if any safety related component or system has been adversely af fected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant ef fect or degradation on the supported com-ponent or system.

In cases where the cause of failure has been identified, additional snubbers, having a high probability for the same type of failure or that are being used in the same application that caused the failure, shall be tested.

This requitement increases the probability of locating inoper-able snubbers without testing 100% of the snubbers.

Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.

To further increase the assurance of snubber reliability, functional 5

tests should be performed once each refueling cycle.

Ten percent of each type of snubber represents an adequate sample for such tests.

Observed failures on these samples should require testing of additional units.

Snubbers in high radiation areas or those especially dif ficult

.to remove need not be selected for functional tests provided operability was previously verified.

The service lide of a snubber is evaluated via manuf acturer input and consideration of the snubber service conditions.

The requirement to monitor the snubber service life is included to ensure that the snubbers

~

~

periodically undergo a performance evaluation in view of their age and operating conditions.

These records will provide statistical bases for future consideration of snubber service life.

Amendment No. 74

-153b-

' 6.6.2.G (cont'd) usage evaluation per the pSME Boiler and Pressure Vessel Code Section III was perf ormed for the conditions defined in tne design specification. Tne locations to be monitored shall be:

a.

The feedvater no=zles b.

The shell at or near the waterline c.

Tne flange studs 2.

Monitoring, Recording, Evaluating, and Reporting a.

Operational transients that occur during plant operations will, at least annually, be. reviewed and compared to the transient conditions defined in the component stress report for the locations listed in 1 above, and used as a basis for the existing fatigue anal's...

b.

The number of transients unien are comparable to or more severe rnan tne transient evaluated in the stress report Code fatigue usage calculations will be recorded in an operating icg oook.

For tnose transients unich are more severe, available data, sucn as the metal and fluid temperatures, pressures, flow rates, and other conditions will be recorded in the log book.

c.

The number of transient events that exceed the design specification quantity and the number of transient events with a severity greater than that included in the existing Code fatigue usage calculations shall be added.. Uhen this sum exceeds the predicated number of 2

design condition events by twenty-five, a fatigue usage evaluation of sucn events will be performed for the af fected portion of tne RCPB.

H.

Recorcs of incividual plant staf f members showing qualifications,

training and retraining.

I.

Recorcs for Environmental Qualification wnich are covered under tne pro-visions of paragrapn 6.8.

J.

Records of tne service lives of all nydraulic and mechanical snubbers, listed on Tables 3. 6.1, 3. 6. 2, 3. 6. 3 including the date at which the ser-vice life ccamences and associated installation and maintenance records.

6.6.3 Records and logs relating to the following items shall be kept for two ye a rs.

A.

The test results, in units of microcuries, for leak tes,ts of sources performed pursuant to Specification 3.8. A.

B.

Records of annual pnysical inventories verifying accountability of tne sources on record.

1.

See paragrapn U-415.2, ASME Section III,1965 Edition.

2.

The Code rules permit exclusion of twenty-five (25) stress cycles from secondary stress and fatigue usage evaluation.

(See paragraphs U-412(t)(3) and N-417.10(f) of tne Summer 1968 Addenda to ASME Section III,1968 Edition.)

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Amendment No. 74

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