ML20117K643

Proposed Tech Specs,Revising TS 3/4.4 Re RCS

ML20117K643
Person / Time
Site:	Callaway
Issue date:	09/05/1996
From:	UNION ELECTRIC CO.
To:
Shared Package
ML20117K640	List: ML20117K639 ML20117K643
References
NUDOCS 9609120062
Download: ML20117K643 (5)

Text

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,- REACTOR COOLANT SYSTEM . .

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• 3/4.4.5 SICAM GENERATORS j

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Each steam generator shall be OPERABLE.

3.4.5 ,

APPLICABILITY: MODES 1, 2, 3 and.4.

ACTION: ,

With one or more steam generators inoperable, restoreabove the inoperable 200*F. steam generator (s) to OPERABLE status prior: to increasing T,yg SURVEILLANCE REOUIREMENTS f

4.4.5.0 Each steam generator shall be demo.,strated OPERABLE by performance the following augmented inservice inspection program and the requirements of -

Specification 4.0.5.

Q 4.4.5.1 Steam Generator Samole Selection and Insoection ' Each steam generator shall be oeterminec OPERABLE ouring snutoown Dy selecting andMinspecting at Uf least the minimum number of steam generators specified in Table 4.4-' 4.4-3,

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4.4.5.2 Steam Generator Tube Samole Selection and Insoectjsassi'ficatio , and the generator tube minimum sample size, inspection result TableJ4.4-2 The corresponding action required shall be as spe'cified i d at inservice inspection of steam generator tubes shall be quencies specified in Specification 4.4.5.3 and the inspected tubes AThe shal1 be verified acceptable per the acceptance criteria the of Specifica -

total number of tubes in all steam generators; the tubes selected for the e inspections shall be selected on a random basis except: ' '

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a. Where experience in similar plants with similar water chemistf ythe indicates critical areas to be inspected, then at least 50%

tubes inspected shall be from these critical areas; I

inspection

b. The first sample of tubes selected for each inserv' (subsequent to the preservice inspectioDJ 4-eatisteam generator sha @ - .

L ag% A eev& 0f us.2.a a4 4 4 s. 2. c , previas deadr oc impac6cmr n

.. tG araa repat> ed % deevny a.<c mr ancidered E. . . ' j.T, ff*W '%.Y4Y$? * ]

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9609120062 960905 PDR ADOCK 05000483 P PDR .

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MVIstoyT m REAC10R COOL ANT SYSTEM

• 3 l SURVEILLANCE REQUIREMENTS (Continued)

1) All nonplugged tubes that previously had detectable' wall penetrations (greater than 20%),

2) Tubes in those areas where experience has indicated potential l problems, and

3) A tube inspection (pursuant to Specification 4.4.5.4a.8) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall elected and subjected to a tube inspection.

The tubes selected as second and third samples (if required by c.

Tabl eS4.4- during each 'nservice inspection may be subjected to a t

l parti 41 tu inspection pr vided:

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1) The tubes selected for ".hese samples include the tubes from ,

those areas of the tube) sheet array where tubes with 1 imperfections were pr diously found, and The nspections include those portions of 'he t tubes where  ;

2) l imperfections were previously found.

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The results of each. sample inspection shall be classified into one of the following three categories: t Category Inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but not more than 1% of the 1 total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.

C-3 Here than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.

Note: In all inspections, previously degraded tubes must exhibit significant (greater than 10%) further wall penetrations to be included in the <2bove percentage calculations. l l

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l CALLAWAY - UNIT 1 3/4 4-12

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REVIStoN 1 REACTOR COOLANT SYSTEM

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\ SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.3 Inspection Frecuencies - The above required inservice inspections of l

- steam generator tubes shall be performed at the following frequencies:

a. The first inservice inspection shall be performed after 6 Effective Full Power Months but withi'n 24 calendar months of initial criticality.

Subsequent inservice inspections shall be performed at intervals of

• not less than 12 nor more t'han 24 calendar months after the previous inspection. If two consecu.tive inspections, not including the j preservice inspection, result in all inspection results falling into j

the C-1 category or if two consecutive inspections demonstrate that

' pre.viously observed degradation has not continued and no additional xtended to degradation has occurred, the inspection 1rrva'i ,

J a maximum of once per 40 months; ds1d M '*3 }

l of a steam genera r l b. If the results of the inser ce ins ecti .4-2 t 40-month interv s fall conducted in accordance wit Tabl

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in Category C-3, the inspec on f quency shall nanac be inerrequency

' sed to at least'once per 20 months, increase shall apply until the subsequent ions satisfy the criteria of l

Specification 4.4.5.3a.; the interval may then be extended to a i

maximum of, once per 40 months; and l

c. Additional, unschedul~ service inspections shall be performed on l

each steam generat in ac rdanc th the first sample inspection i

( specified in Tab 4.4-2 during the s1 down subsequent to any of '

the following co tion :

tubes leaks ot including leaks originating

1) Reactor-to-se from tube-to-tube shee n excess of the limits of Specification 3.4.6.2, or

2) A seismic occurrence greater than the Operating Basis E'arthquake, or

3) A loss-of-coolant accident requiring actuation of the Engineered Safety Features, or

4) A main steam line or feedwater line break.

i CALLAWAY - UNIT 1 3/4 4-13 f

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& cf 7 lL l' A/M -3 4 s o REVISJoy 3

- REACTOR C00 TANT SYSTEM .

- SURVEILLANCE RE001REMENTS (Continued)

Preservice Insoection means an inspection of the full length of

9) each tube in each steam generator performed by eddy current  ;

I techniques prior to service to establish a baseline condition >

ing. This inspection shall be performed prior to o "IRAT 'u using the equipment and techniques nitial POWt subsequent inservice ins ections.

expected to be used durin  !

f IA $i!TA2.7~ '

The steam generator sha 1 be determined OPERABLE after completing b.

unding - ions (plu all tubes exceeding the pluggingt co taining hrough-wall cracks) required by L ,e egfAJr limit and all tubes c Ta lej4.4-2ag g y* er rysJr s/ceytys 4.4. Reoor. A

a. 4 thin 15 days following the completion of each inservice: inspection in each steam

'of steam generator tubes, the number of tubes plugge cial Report .

generator shall be reported to the Commission in a 5 pr reratr'd pursuant to Specification 6.9.2; ~

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b. The complete results of the steam generator tube inservice inspection

"!"g shall be submitted to the Commission in a Special Report pursuant to J

3-Specification 6.9.2 within 12 months following

• + s clu - the completion of the inspection. This Special <d VCS \

( Numberandextentoftubes/ Inspected.

detd  !

1) each Location and percent of wall-thickness penetration for '!

2) indication of an imperfection, and .

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3) Identification of tubes pluggedg A J A y

c. Results of steam generator tube inspections, which f all into Category **

C-3, shall be reported in a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days and prior to resumption plant operation.gations conducted to determine cause of the tube degrada corrective measures taken to prevent recurrence.

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3/4 4-15 I CALLAWAY - UNIT 1 M

1 ULNRC-3430 t Attachment Page 7 of 7.

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TABLE 4.4-3 STEAM GENERATOR REPAIRED TUBE INSPECTION 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION [

Sample Size Result Action Required Result Acton Required ,

i A minimum of 20% of C-1 None N .A. NA l repaired tubes (1)(2) l' C-2 Plug defective repaired tubes C-1 None and inspect 100% of the repaired tubes in this S.G. .

C-2 Plug defectrve repaired tubes '

C-3 Perform acten for C-3 result of ,

I first sample i

C-3 Inspect all repaired tubes in this All other S.G.s are None  :

S.G., plug defective tubes and C-1 inspect 20% of the repaired i tubes in each other S.G.

Notification to NRC pursuant to Some S.G.s C-2 Perform action for C-2 result of 150.72 (b)(2) of 10 CFR Part 50 but no additional first sample -

S G are C-3  !

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Additional S.G. is inspect all repaired tubes in l C-3 each S.G. and plug defective i tubes. Nohfication to NRC pursuant to 150.72 (b)(2) of 10 CFR Part 50 (1) Each repair method is considered a separate population for determinahon of scope expansion (2) The inpection of repaired tubes may be performed on tubes from 1 to 4 steam generators based on outage plans.

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