ML20091N907

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Proposed Tech Spec 4.7.5-1 Re Snubber Visual Insp Interval
ML20091N907
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 01/28/1992
From:
DETROIT EDISON CO.
To:
Shared Package
ML20091N899 List:
References
NUDOCS 9201310148
Download: ML20091N907 (22)
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Text

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ENCLOSURE 2 Pit 0 POSED TECIINICAL SPECIFICATIONS MARK-UP 9201310148 920128 PDR ADOCK 05000341 i' P PDR

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INDEX LIST OF TABLES (Continued) {

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---TABLE 3.3.7.9-I DELETED...................................... .. 3/4 3-68 3.3.7.11-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSIRUMENTATION ................................ 3/4 3-72 4.3.7.11-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . . . . 3/4 3-74 3.3.7.12-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION ................................ 3/4 3-77 4.3.7.12-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLAdCE REQUIREMENTS . . . . . . 3/4 3-81 3.3.9-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION ................................ 3/4 3-87 3.3.9-2 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SETPOINTS ...................... 3/4 3-88 4.3.9.1-1 FEE 0 WATER / MAIN TURBlNE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . . . . 3/4 3-89 3.3.11-1 APPENDIX R ALTERNATIVE SHUTDOWN INSTRUMENTATION. .3/4 3-91 4.3.11.1-1 APPENDIX R ALTERNATIVF. SHUTDOWN INSTRUMENTATION SURVEILLANCE REQUIREMENTS....... 3/4 3-92 (

3.4.3.2-1 REACTOR COOLANT SYSTEM PRES $URE ISOLATION VALVES ......................................... 3/4 4-12 3.4.3.2-2 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAKAGE PRESSURE MONITORS .............................. 3/4 4-12 3.4.4-1 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS ........ 3/4 4-15 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM ............................... 3/4 4-18 4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM--

WITHDRAWAL SCHEDULE . .............. ........... 3/4 4-22 4.6.1.1-1 PRIMARY CONTAINMENT ISOLATION VALVES / FLANGES LOCATED IN LOCKED HIGH RADIATION AREAS . ....... 3/4 6-lb 3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES . . . . . . . . . . 3/4 6-22 3.6.5.2-1 SECONDAR' CONTAINMENT VENTILATION SYSTEM AUTOM'.TI: . ISOLAT ION D AMPERS . . . . . . . . . . . . . . . . . . . . 3/4 6-5 3 a

L 3.7.3-1 SURVEY to*NTS FOR SHORE BARRIER ................. T/4 7-12 l HM-l svent , n W R L. p.u, P(% DO U !N MT2. VAL 3/47-3 /4 7- 3 2 l

3.7.7.5-1 DELEIED..................................

3.7.7.6-1 DELETED. ......... .... ............... ..... 3/4 7 (

l 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHE;ulE .. . . . . . 3/4 8-8 xxiv Amendment No. 49, 59,02 FERMI - UNIT 2

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1 PLANI SYSTEMS '

3/4.7.5 $NUBBERS ({..

LIMITING CONDIT]DN FOR OPERATION i

3.7.5 Alla hydraulic and mechanical snubbers shall be OPERABLE.

APPllCABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. OPERATIONAL CONDITIONS 4 aTid'L for snubbers located on systems required OPERABLE in those OPERATIONAL CONDITIONS.

AC110N:

With one or more snubbers inoperable on any system, 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 4.7.59. on the attached component or declare the

> attached system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE REQUIREMENTS 4.7,5 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program in addition to the requirements of Specification 4.0.5.

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a. Inspection Types -

As used in this specification, type of snubber shall mean snubbers '

of the same design and manufacturer, irrespective of capacity.

R ept ru c. w rw m.r ts

b. Visual Inspections eu u tt y r P m ..

' A bbers are categoriz d as ir. accessible or accessible dJrAng reachweration. Each of these groups (inaccessji le'and acces-sible) may4tQnspected independently accordi M the schedule below. The firstM vice visual insp f each type of snubber shall be-perfo fler 4 mpat but within 10 months of commencing POWER OPERATION a t 1 include all hydraulic and mechanical snubbers. I ubb(ers 4-each type on any system are found OPERABLE during e first*ffinservice Tdyl inspection, the second inservic tsuas inspection of that systettr's 1 be performed at the fi fueling outage. Otherwise, subsequent al inspec-tion a given system shall be performed in accordance witirtu (

,.f<rTTowing schedule:

  • As described in the bases.

FERMI - UNIT 2 3/4 7-16

f INSERT A

b. Visual Inspections Snubbers are categorized ar inaccessible or accessible during reactor operation. Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.7.5-1. The visual inspection interval for each category o." snubber shall be determined based upon the criteria provided in Table 4.7.5-1. The first inspection interval determined using this criteria shall he based upon the previous inspection interval as established by the requirements in effect before Amendment (+).

(+) NRC will include the number of the license amendaent that implements this change.

-! PLANT SYSTEMS

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SURVEILLANCE REQUIREMENTS (Continuedi ._

D o, Af Inoperable Snubbers of Each Type Subsequent Visuar on Any Syn m er Inspection Period In_syc. tac (briod*#

0 -16 months 12%

1 12 months 12%

2 ,- 6 months 1 2 %

r s Visual Inspection Acceptance Criteria Visual. inspections shall verify that: (1) there are no visible ru um nt.

indications of damage or impaired OPERA 531LITY an;f (2) attachments to the foundation or supporting structure are Ae W e, and (3TTasteners for attachment of the snubber to the ccmponent and to the snubber b ** i anchorage are-'trm+,- Snubbers which appear inoperable ALa_telul.t_ -

oT visuaFinspe'ctionsTy be detarained-OPERABtUor theJ.urp_c,se_of establishing the next visual ;nspection interval, p-ovlded that:

(1) the cause of the rejection is clearly established and remedico for that particular snubber and f or other snubbers 4 net;'ecth^ ef-

-t-ype en %at Egte that may be generically susceptible; and (2) the affetted snubber is functiorally tested in the asefound condition and f

determined OPERABLE per Specifications 4.7.5f. For those snubbers common to more than one system, the OPERtsBillTY of suen snubbers shall L i(< ADb .

QQ(,, be relatedsystems.p considered in assessing OPERMML)T the-surwi.11 T cm tace schedulo-4cr eac Pret - W o "- DE Cu mirm n M uuAe cc.rpgatt Apo

d. Transient Event Inspection hnY Gn Rec.tnsuricn impmu An inspection shall be performed of all hydraulic anti mechanical snubbers attached to sections of systems that have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> f or accessible areas and 6 months for' inaccessible areas following such an event. In addition to satisfying the visual in3pection acceptance criteria, freedom-of-motion of mechanical snubbers shall De verified using at least one of the following:

(1) manually induced snubber movement; or (2) evaluation of in place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel.

'--%e-.insgction interval for each type of snubber on a given system shal_Lnot-be lengthe'ned'more--thaQone step at a time unless a._ge.asMe pT55Teii has been t+nr1Tsfe~c~ tion interval may be identified 1ergthenedand one jcorrected; 1ii'that.-patrDps-thereatter tp the -ftr5TTi~me and t if no inoperable snubbers- tTf Tiia. Lt type are found on that system. ~ ~ - . ,

"The prov464ons--of-4pecifiut4en-4v04-are-not-app 44 cable,- '

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( 3/4 7-17 FERMI - UNIT 2 l

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r 1 INSERT B A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber, if continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.

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/%D_D10M 4,J&L l

]ABL2 4.7 & 1 EfLUJ[lffly_JSUAt illSPECl[01LJNTERyg 3

NUMBER OF UNACCEPTABLE SNUBBERS Population Column A Column B Column C or Category Extend Interval Repeat Interval Reduce Interval 11{q1m_LJnd 2) (Not_es 3 and 6) (Notel 4 and_Q) (Notes 5 attd_ql 1 0 0 1 80 0 0 2

^

100- 0 1 4 150 0 3 8 200 2 5 13 300 5 12 25 400 8 - 18 36 500- 12 -24 48

! 750 20 40 78 1000 or greater 29 56 109 l

Note 1: The_ next visual _ inspection interval for _a snubber population or category _shall be determined based upon the previous inspection

interval and the number of unacceptable _ snubbers found during that
. interval. Snubbers-may be categorized . based upon their-l' accessibility during power operation,-'as accessibl_e or l inaccessible. These categories may be exami_ned separately or -

l_- Jointly. However, the licensee must make and document that-d_ecision before any inspection and shall use that: decision as the basis upon which to determine the next inspection interval for that category. -

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i TABlf A 7,5-1 NOTES (Continued)

Note 2: Interpalation between population or category sizes and the number of unacceptable snubbers is permissible. Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of unacc.ptable snubbers as determined by interpolation.

Note 3: If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.

Note A: If the number of unacceptable snubbers is equal to or less than l the number in Column B but greater than the number in Column A, .

the ne<t inspectinn interval shall be the same as the previous interval.

Note 5: If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be

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two-thirds of the previous interval. However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation; that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.

Note 6: The provisions of Specification 4.0.2 are applicable for ell inspection intervals up to and including 48 months.

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PLhNT SYSTEMS '

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BASES

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e REACTOR CORE ISOLATION COOLING SYSTEM (Continued)

Wita the RCIC system inoperable, adequate core cooling is assured by the OPERABILITY of the HPCI system and justifies the specified 14-day out of service pe ri od . .--

The surveillance requirements provide adequate assurance that RCIC will be OPERABLE when required. Although all active components are testable and full flow can be demonstrated by recirculation during reactor operation, a complete. functional test requires reactor shutdown. The pump _ discharge piping is: maintained full to prevent water. hammer damage and to start cooling at the -

earliest possib moment. .

3/4.7.5 SNUBBERS All snubbers are, required OPERABLE to ensure that the structural integrity of the.r'eactor coolant system and all other safety-related systems is maintained during and.tollowing 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 or failure of the. system on which they

-are_ installed, would have no adverse effect on any safety-related system.

. Snubbers are classified and grouped by design and manufacturer but not by

' h- 'sizei for example, mechanical snubbers utilizing-the same design features of. the 2-kip,10-kip, and 1004ip capacity manuf actured by Company "A" are of the same type. The same. design mechanical snubbers manufactured by Company "B" for the purpcscs of this. Technical Specification would be a different type, as would hydraulic snubbers. frca either manufacturer.

A list of individual. snubbers with detailed information of snubber location '

.and. size and of system affected shall-be.available at the plant in accordance -

with-Section 50.71(c)_of 10 CFR Part 50. -The accessibility of each snubber sN11 be determined and_ approved by the-Onsite Review Organization. - The -

determination _shall be based upon the existing radiation levels and the expected '

time to perform a visual inspection _in each snubber location as well as other

. factors associated with accessibility during. plant operations (e.g., temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10._ The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59:of 10 CFR Part 50.

The visual inspection frequency is based.upon maintaining a consta jntaV of. Snub tion to each safety-related_ system. Therefore Equired =

inspection interva inversely with the observ er failures on a_ T given system and is determine umpf.ra operable snubbers-found

=during an inspection of each s i n establish the inspection f requency for each-t nucber on a safety-rel ha-it was assumed that the. y of snubber failures and-initiating events is t with t.ime n that the failure of any_ snubber on that system could cause the-sy -

Rcancs u/ pern*uc f( ou wGAT pnGE.

FERMI - UNIT 2 B 3/4 7-2 e-

a INSERT C l The visual inspectJan fregunney is based upon maintaining a constant level of I snubber protection to each safety-related system. Therefore, the required inspection interval varies based upon the number of unacceptable snubbers found during the previous inspection in proportion to the slees of the various I snubber populations or categories and the previous inspection interval as specified in NRC Generic Letter 90-09, " Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions". In order to establish the '

inspection frequency for each type of snubber on safety-related systems it was assumed that the frequency of snubber failures and initiating events is constant with time and that the failure of any snubber on any system could cause the system to be unprotected and, therefore, result in failure during an assumed initiating event. Inspections performed before the 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 require a shorter inspection interval will override the previous schedule.

INSERT D The acceptance criteria used in both the visual inspections and the functional testing determines the OPERABILITY of the snubber (s). When a snubber is determined to be inoperable, an Engineering Evaluat!on is required. This 3 provides for an evaluation of the snubber mode of failure to determine if the i snubber mode of failure has adversely affected the safety-related component o:

system to which it was attached. This evaluation will further verify that the system is still capable of meeting its design function.

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.P.Lt.NT SYSTEMS BASES RrnrwE I mr.n T" c' SNUBBERS (Continued) cm potwgs/pnct

t. 2

,taQn rotected and to result in f ailure during an assumed init.14tinfeirent, inspection 144rmed before the interval has elapsgLmay-te'used as a new refer-ence point to determine ttinex.t.J s ectiQn.-4foFever, the results of such early inspections perf ormed before the or' n W equired time interval has elapsed

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(nominal time less1,5%)-may~~n'ot be used to lengtheTthT require inspection ntetval s interval, AnydliiIpection whose results require a shorter inspection vi+1 override the previous schedule. - rg pm e t, q p xut"b"ce mtuce) Pnc C v

- Me ac-ceptance critor44-are--to-beM6ed-4n-the-visua inspecMon te

---determiaS493ABILLThaf-the-snubber 4, -for-example r -if-a-f4uid-port-of-a-hydraulic-snubber is--found-to-be-uncovered,-the-,,nubber-shall-be-deciared.

-inoperabh and-+ha34--not-be-determined 4PERABLE-via-functional-testing,-

To provide assurance of snubbei functional reliability one of three functional testing methods is used with the stated ccceptance criteria:

1. Functionally test 10% of a type of snubber with an additional -1 M 6 1 tested for each functional testing failure, or
2. Functionally test a sample size and determine sample acceptance or

'. rejection using Figure 4.7.5-1, or

(

3. Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation.

Figure 4.7.5-1 was developed using "Wald's Sequential Probability Ratic Plan" as described in " Quality Control and Industrial Statistics" by Acheson J. Duncan.

Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructise testing was performed to qualify the snubbers for the applicable design conditions at either Snubbers the so exempted completion of their fabrication or at a subsequent date.

shall be listed in the list of individual snubbers indicating the extent of the exemptions.

The service lifa of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and asso-ciated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature ar.ra, etc.) The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evalua'.ior in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.

FERMI - UNIT ? 8 3/4 7-3 i

m. . ..... . . . _ _ _ . . . .~ .__ _ . . _ _ _._._

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k ENCLOSUllE 3 4 i

TECIINICAL SPECIFICEION CilANCE PAGES t

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list OF TABLES (Contintied) _

TABLE PAGl l

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3.3.7.9-1 DELETED.......................................... 3/4 3-68 l l

3I3.7.12-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION......... 3/4 3-77 4.3.7.12-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS........................ 3/4 3-81 3.3.9-1 FEEDWATER/ MAIN TURBINE-TRIP SYSTEM ACTUATION INSTRUMENTATION.................................. 3/4 3-87 3.3.9-2 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SETP0lNTS........................ 3/4 3 4.3.9.1-1 FEEDWATER/ MAIN TUR8INE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS........ 3/4 3 89 3.3.11-1 APPENDIX R ALTERNATIVE SHUT 00WN INSTRUMENTATION,. 3/4 3-91 4.3.11.1-1 APPENDIX R ALTERNATIVE SHUiDOWN INSTRUMENTATION SURVEILLANCE REQUIREMENTS........ 3/4 3-92 3.4.3.2-l REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES........-................................... 3/4 4-12 3.4.3.2-2 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAKAGE PRESSURE M0NITORS................................ -3/4 4-12 3.4.4 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS.......... 3/4 4-15 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.........,....................... 3/4 4-18 4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM--

WITHDRAWAL SCHEDULE.............................. 3/4 4-22 4.6.1.1-1 PRIMARY CONTAINMENT ISOLATION VALVES / FLANGES LOCATED-IN LOCKED HIGH RADIATION AREAS........... 3/4 6-lb' 3.6.3-1 PRIMARY CONIAINMENT ISOLATION VALVES............. 3/4 6 22 3.6.5.2-1 SECONDARY CONTAINMENT VENTIl.ATION SYSTEM AUTOMATIC ISOLATION DAMPERS...................... 3/4 6-53 4.7.2.1-1 CONTROL ROOM EMERGENCY FILTRATION SYSTEM DUCT-LEAK TESTING SURVElllANCE REQUIREMEN1S........... 3/4 7-10b 3.7.3-1 SURVEY POINTS FOR SHORE BARRIER.................. 3/4 7-12 4.7.5-1 SNUBBER VISUAL INSPECTION INTERVAL............... 3/4 7-20a- l 3.7.7.5-1 DELETED.......................................... 3/4 7-32 3.7.7.6-1 DELETED.......................................... 3/4 7/-37 l

l 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE................... 3/4 8-8 1

!- FERMI - UNIT 2 xxiv Amendment No. f9,E9,E/,//,//,

, 4-LANT SYSTfM

_ SHXLILLy[CE_RE0VIRQ1,ENTS (Continimd) ____ _ _

- c.- At_least_once per.18 months by:

1- Performing a system functional test which included simulated automatic actuation and restart and verifying that each '

automatic _ valve in the flow path actuates to its correct p osition. Actual injection of coolant into the reactor vessel may be excleded. ,

2. Verifying-that the system will develop a flow of greater  !

-than or equal to 600 gpm-in the test finw path with a system- l

-head corresponding to reactor vessel operating pressure including injection line losses when steam is being supplied to the turbine at a pressure of 150 + 50, -0 psig.*

3. Verifying _ that the suction for the RCIC system is automatically transferred from the condensate storage tank ..

to the suppression puol on a condensate storage tank water '

level-low signal,  !

s r

-I The provisions of Specificat-ion 4.0.4 are not-applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam-pressure is adequate to perform the-tests, FERMI - UNIT 2 3/4 7-15

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RLANT SYSTEMS-3/.1,15 SNVBBERS-llMITING_ CONDITION FOR OPERATION ,

3.7.5 All' hydraulic and mechanical snubbers shall be OPERABLE.

AEEllCELillIX: OPERA 110NAL CONDITIONS 1, 2, and 3. OPERATIONAL CONDITIONS 4  ;

and 5 for-snubbers located on systems required OPEP,ABLE in those OPERATIONAL

-CONDITIONS. 4 bCTION: ,

With one or more snubbers inoperable on any system, 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 OPERAB E status and perform an engineering evaluation per Specification 4.7.59 on the attached component or

  • oeclare the attached system inaerable and follow the appropriate ACTION statement for-that system.

SURVElLtANCE Rf0VIREMENTS,__ , ,

4.7.5- Each snubber shall be demonstrated OPERABLE by perfurmance of the following augmented inservice inspection program in addition to the requirements of Specification 4.0.5,

a. Inspecticn Typn As used in this spe.ification, type of snubber shall mean snubbers of the-same design and manufacturer, irrespective of capacity, b_ yligal Insoectiont 5,1ubbers are categorized as inaccessible or accessible 'duri'.g reactor operation _ Each of these categories-(inaccessible and

, accessible) may be inspected independently- according_ to the schedule determined by Table 4.7.5-1. The visual inspection ~

interval for each category of snubber shall be determined based upon the criteria provided in Table 4.7.5-1. The first inspection interval-determined using this criteria shall be based upon the-previous inspection . interval' as established by the requirements in I 6 =effect before Amendment .

i I's A described in the bases.

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! FERMI UNIT 2 3/4 7-16 Amendment No.

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P1 ANT SYSTEliS

)JLEVELLANCE REQUIREMENTS (Continued) _i

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c. Vjis a l Insag_c.11on Act n tance Criteria Visual inspections shall -verify that: (1) there are no visible indications of damage or impaired OPERABILITY and (2) attachments to the foundation or supporting structure are functional, and-(3) l

, fasteners for attachment of the snubber to the component and to the snubber anchorage are functional. Snubbers which appear 5 inoperable as a result of visual inspections shall be classified I as unacceptable and mby be reclassified acceptable for the purpot,e l of establishing the next visual inspection interval, irovided that: (3) the cause of the rejection is clearly esta311shed and remedied for that particular snubber and-for other snubbers that j may be ge terically susceptible; and (2) the affected snubber is functicnally tested in the as found condition and determined OPERABLE per Specification 4.7.5f. For those snubbers common to -

more-thari one system,-the OPERABILITY of such snubbers shall be considered in assessing the OPERABILITY of each of the related '

systems. A review and evaluation shall be performed and I documented to justify continued operation with an unacceptable I snubber. If continued operation cannot be justified, the snubber I shall be declared inoperable and the ACTION requirements shall be met. l

d. Inrtsical Event insegg_Qgn An inspection shall be performed of all hydraulic anJ mechanical-snubbers-attached to sections of systems that have experienced '

unexpected, potentially damaging transients as-determined from-a-review of operational data and a-visual inspection of the systems within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for accessible areas and 6 months for inaccessible- .

areas following s'uch an event. In addition to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified using .at least one of the following: (1) manually. induced snubber movement;-or (2) evaluation of in-place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel.

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/ FERMI - UNIT 2 3/4 7-17 Amendment No, E _ _.

o . >

ELANT-s1SHMS.

SURKl t t ANC.E_RpJUJ REME NTS ( Con t i nyi _ __ _

e;

.f3mLlo.nal Tutt 09 ring the first refueling shutdown and at least once per 18 months thereafter during shutdown, a representative sample of snubbers shall be tested using one of the following sample plans.

The sample 31an shall be selected prior to the test perioJ and cannot be clanged during the test period. The NRC Regional Administrator shall be notified in writing of the sample plan selected prior to the test period or the sample plan used in the prior test-period shall be implemented:

1) At least 10% of the total of each type of snubber shall be functionally tested either in-place or in a bench test. For each snubber of a type that does not meet the functional test acceptance criteria of Specification 4.7.5f., t.n additional 5% of that type of snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally tes+ed; or
2) A representative sample of _each tyoe of snubber shall be i functionally tested in accordance with Figure 4.7.5-1. "C" is the total number of snubbers of a type found not meeting .

the acceptance requirements of Specification 4.7.5f. - The cumulative number of snubbers of a type tested is denoted by "N".. At the end of each day's testing, the new values of ,

"N" and "C" (previous day's total- plus current day's increments) shall be_ plotted on Figure 4.7.5-1. If at any time the point plotted falls in the " Reject" region all .

snubbers of that type shall- be functionally tested.. If at any time the point plotted falls-in the " Accept" region, testing of snubbers of that type may be terminated. When the point plotted lies in the;" Continue Testing" region, additional snubhers of that type shall be tested until-the points falls in the " Accept" region or the " Reject" region, or all the snubbers of that type have been tested. Testing-equipment Nilure during- functional testing may invalidate that day' .esting and allow that day's testing to resume anew at a :ater time, providing all snubbers tested with the failed equipment during the day of equipment failure are-retested; or--

3) . An initial representative sample of 55 snubbers shall be fun.tionally tested, for each snubber type which does not mee+ the functionalitest acceptance criteria, another sample

.of at least one-half the size of the initial sample shall be tested until the total number tested.is equal to the initial

' sample size multiplied by the factor,1 + C/2, where "C" is the number of snubbers found which do not meet the j functional test acceptance criteria. The results from this f sample plan shall be l

l L FERMI - UNIT 2 3/4 7-18 l

L

l LABL E 4.7.5-1 SJNMf3LYll!)Al INSPECTICN 1MILRVAL l

I NUMBER Of_llNECEPTAHLLSNUBBERS ._

Population Column A Column D Column C I or Category Extend intarval Repeat Interval Reduce Interval I lug 1_e_s e 1 and_?)_ (Notes 3_a_dn 6) (Notes 4 and_5) .INMes 5 and_jj l

1 0 0 1 l

80 0 0 2 I

, l 100 0 1 4 l

1 150 0 3 8 200 2 5 13 300 5 12 25 l

l I

400 8 18 36 I 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 I

l t l I

I l

Note 1: The next visual inspection interval for a snubber ropulation or I category shall be determined based upon the previous inspection I interval and the number of unacceptatG snubbers found during that I interval. Snubbers may be categorted, based upon their I accessibility during power operation, as accessible or I inaccessible. These categories may be examined separately or I jointly. liowever, the licensee must make and document that I decision before any inspection and shall use that decision as the I basis upon which to determine the next inspection interval for I that category. f FERMI - llNIT 2 3/4 7-20a Amendment No.

,=..,; ,

TABL E 4.7.5-1 t(Q1[S (Continued)

' Note 2: . Interpolation between population or category sizes and the number of unacceptal,le snubbers is penaissible. Use next lower integer for the value of the limit for Columns A, B, or C if that integer l Includes a fractional value of unacceptable snubbers as determined

-by. interpolation. l Note 3:- . If the. number of unacceptable snubbers is equal to or less than  !

the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months. l Note 4: If the number of unacceptable snubbers is equal to or less than the number in Column.B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.

Note 5: If the number of unacceptable snuSbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval. However, if the number of unacceptable snubbers is less than the number in Column C but greater than the' number in Column B, the next interval shall be j reduced proportionally by interpolation; that is, the previous '

interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.

Nate 6: The provisions of Spectfication 4.0.2 are applicable for all inspection intervals up to and including 48 months.

l l

l r-L FERMI - UNIT 2 3/4 7-20b Amendment No.

o

,e .,

l 4

PLAN 1 SY_SIGS bgIs , ,,,,,_

RLAC.10MORLlS0J AJ10L(_0Alll{LSMIE (Continued) 4 With the RCIC system inoperable, adequate core cooling is assured ta the

( .RABill1Y of_the HpCl system and justifies the specified 14 day out of orvice period.

The surveillance requirements provide adequate assurance that RCIC will be OPCRADtE when required. Although all active components are testable and full flow can be demonstrated by recirculation during reactor operation, a ,

complete-functional test requires reactor shutdcwn. The pump dischargo piping '

is maintained full to prevent water hammer damage and to start . cooling at the earliest possible moment. ,

.3/4.7.5 SNUBBERS All snabbers are required OPERABLE to ensure that the structural ,

integrity of the reactor coolant system and all other safety related systems is maintained during and followit.g a seismic or other event initiating dynamic loads. Snubbert excluded from this inspection program are those installed on nonsafety related systems and then wly if their failure or failure of the sniem on which they are installed, would have ro adverse effect on any i si.fety related system. -i Snubbers are classified and groused by design and manufacturer but not by size. For example, mechanical snutoerr utilizing the same design features

" the bkip,10 ktp, and 100 kip capacit/ manufactured by Company "A" are of same type. The same design mechanical snubt, ors manufactured by Company "B" for the purposes of this Technical Specification would be a different type, as would hydraulic snubbers from either .ganufacturer.

A list of individual snubbers with detailed infonation of snubber location and size and of system af fected shall be available at the plant in accordance with Section 50.7)(c) of 10 CFR Part 50. The accessibility of each  :

snubber shall be determined and approved by the Onsite Review Organization.  !

1he determination shall be based upon the existing radiation levels-and the expected time to perform a visual inspection in each snubber location as well ,

as other factors-associated with accessibility during plant _ operations (e.g., l temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 0.8 and 8.10. The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CTR Part 50.

The visual inspection frequency is based upon maintaining a constant level of snubber protection to each safety-related system. 1herefore, the required inspection interval varies based upon the number of unacceptable snubbers:found during the previous inspection in proportion to the sizes of -

the various snubber popu14tions or categories and the previous inspection I interval as specified in-NRC Generic Letter 90 09, " Alternative Requirements c for Snubber Visual- Inspection Intervals an) Corrective Actions", in order to l

establish the inspection frequency for each type of snubber on safety-related FERMI - UNIT 2 B 3/4 7-2 Amendment No. [

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~. __ _. _ _ ____.__._m_ _ . _ _ _ _ _ _ - . _

. p ..

l MLLSlilfl$

FAKS EMIDS (Continued) systems it was assumed that the frequcncy of snubber failures and initiating '

events is constant with time and that the failure of any snubber on any syrtem I could cause the system to become unprotected and, thcrofore, rctult in failure during an assumed initiating event. Inspections performed before the 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 i not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule. ,

The acceptance criteria used in both the visual inspections and the functional testing determines *he OPERABit.11Y of the snubber (s). When a I' snubber is determined to be inverable, an Engineering Evaluation is required. '

ihis provides for an evaluation of the snubber mode of failure to determine if the snubber mode of failure has adversely affected the safety related component or system to which it was attached. This evaluation will further verify that the system is still capable of neeting its design functhn.

To provide assurance of snubber functional reliability one of three functional testing methods is used with the stated acceptance criteria:

1. functionally test 10% of a type of snubber with an additional 5% l tested for each functional testing failure, or
2. functionally test a sample site and determine sample acceptance or rejection using figure 4.7.5-1, or
3. functionally test a representative sample size and determine samp'e acceptuce or rejection using too stated equation, figure 4.7.5-1 was developed using "Wald's Sequential Probability Ratio Plan" as described in " Quality Control and Industrial Statistics" by Acheson J. Duncan.

Permanent or other exemptions frcm the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis- i for exemption is presented and, if aoplicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the-completion of their fabrication or at a subsequent date. Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.

FERMI UNIT 2 B 3/4 7-3 Amendment No.

.s M M L S LS M Wa BAMS 1he service life of a snubber is established via nanufacturer input and L information through consideration of the snubber service conditions and as'.ociated installation and n.aintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area,

etc.). The requirement to monitor the snubber service life is included to f ensure that the snubbers periodically undergo a performance evaluation in view I of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.

3LL1JL.3LALULEQUELILHIMitMllM _

- lhe limitations on removable contamination for sources requiring leak 2 testing, including alpha emitters, is based on 10 CIR 70.39(e) limits for i; plutonium. This limitation will ensure that leakage from byproduct, source, 7 and special nuclear material sourcss will not exceed allowable intake valucs.

!' Scaled sources are classified into three groups according to their use, with surveillance requirements commensuaate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Scaled sources which are continuously enclosed within a shleided mechanism, i.e., sealed sources within radiation monitoring devices, are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

o 3AL7 D[l[l[D l 34LLLJH1010  !

FERMI - Uilli 2 8 3/4 7-4 Amendment flo. 62 '

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