ML19207A826

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Tech Specs for RCS Re Changes in Surveillance Requirements for Steam Generator Tube Insp
ML19207A826
Person / Time
Site: Davis Besse 
Issue date: 08/17/1979
From:
TOLEDO EDISON CO.
To:
Shared Package
ML19207A822 List:
References
NUDOCS 7908220434
Download: ML19207A826 (5)
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Text

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REACTOR COOLANT SYSTEM T.L STEAM GENERATORS k,

LIMITING CON 0! TION FOR OPERATION 7

t 3.4.5 Each steam generator shall be O'PERABLE with a water level between i,,

18.and 343 inches.

APPLICABILITY: H0 DES 1, 2, 3 and 4.

A_ CTION:

a.

With one or more steam generators inoperable due to steam generator tube imperfections, restore the inoperable generator (s) to OPERABLE status prior to increasing T,yg.above 200*F.

b.

With one or more steam generators inoperable due to the unter level being outside the limits, be in at least HOT STANOBY l

within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

i SURVEILLANCE REOUIREMENTS l

t 4.4.5.0 Each steam generator shall be demonstrated OPERACLE by perforrance of the following augmented inservice inspection program and the requirements of Specification 4.0.S.

4.4.5.1.

Steam Generator Samole Selection and Inspectica - Each steam generator shall be determined OPERABLE during shutdown bf selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.

4.4.5.2 Steam Generator Tube Sample Selection and Inspection - The steam generator tube minimum sample size, inspection result classification. -

and the corresponding action required shall be as specffled la Table 4.4-2.

The inservice inspection of steam generator tubes shall be perfomed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4.

The tubes selected for each inservice inspection shall include at least 37, '

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

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U,V!S-EEssE, UNIT 1 3/4 4-6 t

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1 REAciOR C00ULNT SYSTEM

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SURVEILLANCEREQUIREMENTS(Continued)

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a.

The first sample inspection during each inservice inspection (subsequent to the baseline inspection) of each steam generator shall include:

1. 'All.nonplugged tubes that previously had detectable wall penetrations (>20%), and

~ 2.

At least 50% of the tubes inspected shall be in those areas where experience has indicated patential probless.

V.v.t. 4. 4. O A tube inspection (pursuant to Specification W.;..."'

shall be perfomed on each selected tube. If any

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selected tube does not pemit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a,ube inspection.

h, Tubes in the following groups any be excluddfrca the first random sa:ple if all tubes in a group in both sttas isntrators are inspected. No credit will be taken for these tubes in meeting minimum sample size requirements.

(1) Group A-1: Tubes within one, two or three rows of the.

I open inspection lane.

(2) Group A 2: Tubes having a drilled cpening in the Ifth support plate.

C.

The tubes selected as the second and third seglas (if required by iable 4.4-2) during each inservice inspctica cay be subjected to less than a full tube inspection provihd:

1.

The tubes selected for these sagles include the tubes I

from those areas of the tube sheet array where t@.s edth i

imperfections were previously found.

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2.

The inspections include those portions of the tubes where imperfections were previously found.

i DAVIS-BESSE UNIT 1 3/4 4-7 t

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_ REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

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The. results of each sample inspection shall be classified into one of i

the following three categories:

Category l

InsDection Results

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C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected l,

' tubes are defective.

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One or more tubes, but not more than 15 of the total tubes inspected are defective, or between 5% and 10% of the total tubes t

inspected are degraded tubes.

2 C-3 More than 10% of the total tubes inspected are degraded tubes or rore than 4 of the inspected tubes are defective.

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e NOTES: (1) In all inspections, previously degnded tubes wat exhibit significant (>10%) further wall penetratims to be included in, the above p.ercentage calculations, j

(2) Were special inspections are perforzed pbsuant to p

4/gg,g MCJ, defective or degreded tubes fataf as c result of the inspection shall be included in deterair.ing the Inspection Results Category for that special inspection q but need not be included in determining the Inspect.ics Results Category for the general straa generator inspection.

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4 4.5.3 steam generator tubes shall be performed at t o

The baseline inspection shall be perforu d fe essere4/ ***Yd a.

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Subsequent inservice in:;ections shall be h

calendar cienths af ter the previous inspectica. perform t

I If the resu.lts of evo consecutive inspections for a giken group

  • of tubes following servfee or if two consecutive inspecticas de=onstrate t degradation has not continued and no additional degradation has occurred, the inspection interval for that group may be extended, _10b).
  1. CI to a maximurs of 40 months.

MIS-EESSE. UNIT 1 3/4 4M 7*-

REACTOR COOLANT SYSTEM SURVEILLANCEREQUIREMENTS(Continued) 4.V-1 i

b.

If the results of the inservice inspectio f a steam generator Performed in accordance.with Table at 40 month intervals for i

a given group

  • of tubs: fall in Category C.3, subsequent inservice l-inspections shall be performed at intervals of not less than 10 nor more than 20 calendar months after the previous inspection.

The increase in inspection frequency shall apply until a subsequent inspection mee6s the conditions specified in 4.'" 4.. and the in,

terval can be extended to 40 months.

% f,t.Js Additional, unscheduled inservice inspections shall be perfomed

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on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions:

1.

Primary-to-secondary tubes leaks (not including leaks originating from tube-td tube sheet welds) in excess of the limits of Specification 3.4.6.2.

2.

A seismic occurrence greater than the Operating Basis Earthquake.

3.

A loss-of-coolant accident requiring actuation of the engineered safeguards.

4.

A main steam line or feedwater line break, i

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  1. A group of tubes means: (a) All tubes inspected purs:::nt to MLI : ;,et

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(b) All tubes in a steam gen: rater less thosa inspected pursuant to M* Ir 2 i-

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RTEA&4 G1NERATOR )UBE IM5PfCTION "w

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M 1ST SAMPLE INMC' TION

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f 2ND SAA4PLE SPASPECTION 2RO $A44PLE 8N5PEC50N Saenple Size Result

' Action 88 w red u suas Action Required Fes9tt Action staquired e

Z A minimum of C-1 None tJ/A N/A N/A N/A s

ST per j

8' C-2 5%g catective tubas C-1 None MrA N/A Y

and inspecs additional

% desma suhs -

~ C-8 None 25 tubes in this S. G.

Ca2.

arid inspect additional C-2 PM det:ctive tub:s 45 subes in this S. G.

Festorm action for C-3 C-3 resula of first M

sarmple 4=

Perforrn action for C-3 C-3 sesult of first N/A N/A sample m

C -3 inspect ass tubes in All other this S. G., plug de-S. G.s are None N/A N/A tectbwe tubes and C-1 Inspect 25 subes in S " S G 8 Perform action for N/A N/A eads other S. G.

C-2 bu;t no C-2 result of second additional Prornpt notification S. G. are to NRC pursuant C-3 so spedtkath Ashtitionas snspect all sulms en E83 S. G. is C-3 cach S. G. and plug alclective tula Pronipt notif 6 cation N/A N/A to NRC pursuant au specilication 6.9.1 L') S - 3 % Where N is the nurmber of steam generators in the ur..t. and n is the nuanber of stea.n generators inspected during an inspecalon n

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(2)

For tubes inspected pursuant to 4. ! " ' " -31 No action is required for C-1 resul'ts. For C-2 results in one or both steman gergeratorti plug defective tubes. For C-3 resulta Jn one p

plus defective tubra and provide proopt twtification of flRC c

or both stemas generators, p

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