ML17339A460

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Forwards Results of Facility Steam Generator Insps & Discusses Insp Criteria & Results.Approval to Return Facility to Power Operation Requested.Util Will Be Ready to Resume Power Operation by 800126.Class III Fee Encl
ML17339A460
Person / Time
Site: Turkey Point NextEra Energy icon.png
Issue date: 01/10/1980
From: Robert E. Uhrig
FLORIDA POWER & LIGHT CO.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
L-80-8, NUDOCS 8001170340
Download: ML17339A460 (64)


Text

REGULATORY INFORMATION. DISTRIBUT'ION'YSTEM (BIDS)

ACCESSION NBR t 80011,70340 DOC, ~ DA'TE! 80/01/1'O'OTARIZED:

NO FACIE:50 250 Tur key Point Ptanti Unj t 3i Florida Power'nd 'Light C

AOYH;NAME

'UTHOR AF'F'llI'ATlON UHAIGgH;K",

Fiiorida Power

& Light Co, RECIP",NAME REC'IPIENT AFFILIATION EiSSNHUTrD<G ~

O.i.vi'sion of Operating Reactor's DOC KE'T ¹ 0Soo025o SUBJECT".

Forwards' esul ts of feei 1 i ty steam generator insps discusses insp criteria

& results.Approva1>> to return feei,lty to power operation requested, Util wilil be r.eady to resume power operat'.fan by 800126 'Class III"fee encl>> ~,

DISTRIBUTION CODE':

A001S COPIES RECEIVED ~ L>>TR ENCL SIZE:

TITf.K: Gerieral Distii.but,iori foj'"after"Issuance o'f Operatjng Lic No(Es:~I+~Kpj 5~ <> d ACiT ION'NTERNAL!

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JV)u~~<<'8 FLORIDA POWER 8 LIGHTCOMPANY January 10, 1980 L-80-8 Office of Nuclear Reactor Regulation Attention:

Hr. Darrell G. Eisenhut, Acting Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D.

C.

20555

Dear Nr. Eisenhut:

Re:

Turkey Point Unit 3 Docket No. 50-250 Steam Generator Ins ections The results of the Turkey Point Unit 3 steam generator inspections conducted during the current refueling outage are attached.

The inspections, which were performed in accordance with Turkey Point Unit 3 operating license DPR-31, showed no new phenomena and veri'fied that the general pattern of denting in Unit 3 is within predictable limits and consistent with previous inspect-ions of the Turkey Point Units.

The general criteria applied for steam generator inspections and preventive plugging are the same as previously applied to Turkey Point Units 3 and 4, with an additional plugging criterion included to provide more conservatism.

The additional plugging criterion leads to the plugging of additional tubes in order to provide for an operating period in excess of 10 months.

This approach provides reasonable assurance of steam generator tube integrity such that safe operation of the unit during normal full power operation or during hypothetical accident conditions is assured for an operating period in excess of 10 effective full power months.

Total steam generator tube plugging at the conclusion of the current outage will be approximately 19.35.

This is conservatively bounded by the 25% tube plugging ECCS analysis which has been previously submitted.

The results of this inspection and the preventive tube plugging program have been reviewed by the Turkey Point Plant Nuclear Safety Committee and the Florida Power 8 Light Company Nuclear Review Board.

They have concluded, based on the inspection results, the implemented plugging pattern, and previously submitted analyses, that the return of Turkey Point Unit 3 to full power operation for at least 10 effective full power months does not involve an unreviewed safety question.

g 4dbd 80011 VO a(CA~0 qS PEOPLE... SERVING PEOPLE

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Office of Nuclear Reactor Regulation Page Two In accordance with condition E4 of operating license DPR-31, Florida Power Light Company requests NRC approval to return Unit 3 to power operation.

Based on our current schedule, we will be ready to resume power operation by January 26, 1980.

We 'have determined that this submittal..involves a Class III fee in accordance with 10 CFR 170.

Accordingly, a check for $4,000 is enclosed.

'Very truly yours, Robert E. Uhrig Vice President Advanced Systems

-8 Technology REU/MAS/RJA/ah Enclosures cc:

Mr. James P. O'Reilly, Region II Harold F. Reis, Esquire

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Turkey Point 3 Steam Generator Inspection Program I.

Introduction An extensive inspection program for the Turkey Point Unit 3 steam generators

.:Ias" conducted in December, 1979.

The'ollowing items were accomplished:

1.

gauging of steam 'generator hot legs and'cold legs - all steam generators 2..

measurerrents of visible flow slots in all steam generators 3.

eddy current inspection of small radius U-bends in, steam generator B

4; Regulatory'uide 1.83 eddy current measurements in the hot'egs and cold legs of all steam generators 5.

preventive plugging Table 1 is a sugary of the approximate number of steam generator tubes inspected in each category and in each steam generator.

Table 1:

Summary of Total Steam Generator Tubes inspected P

8 Hot Lea 8 Cold Lea

~8Hot Le 8 Cold Lea C Hot Lea C Cold L=-'auging 1188 248 1074 176 1134 209 U-Bend. Rows 2-5 R.G.

1.83 143

.67 149 163 149 481 This r port summarizes the inspections conducted, the results of these inspections, and preventiv plugging programs accomplished.

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Page 2'I.

Inspection Programs A.

Gau in Pro ram The tube gauging program in the tubelane area is based on previously defined regions where significant tube deformation has occurred.

These regions are also determined using finite element analysis techniques which yield tube hooo strain contours as a function of plate deformation.

The boundary in t'e peripheral tubelane areas near the three and nine o 'clock wedge locations is modified in the analysis to take into account the greater extent of deformation in this region of the plate determined by previous experience..

Initially, a 12.5% strain boundary was used in the gauging.

program when little plant specific data was available.

After two initial inspections and three reinspections of the Turkey Point Plants; review of specific information indicated the conservatism of the 12.5% boundary.

Consequently, a

15% boundary vias adopted and used in the gauging program during the last inspection.

Mith the addition of the information gained from that inspection (now totaling four reinspections), it is apparent that the 15% boundary is also overly conservative and the 17.5% boundary should be used.

That is, the majority of the tubes inspected do not restrict the.650 inch probe.

In addition, all tubes restricting the

.610 inch or.540 inch probe have all fallen well within the inspection boundary.

This is significant sine the

.610 inch and

.540 inch restricted tubes form the basis for the plugging patterns in the tubelane region.

Since full closure of the flowslots was observed in Turkey Point 3 steam generators during the Dece..ber 1977 inspection, Turkey Point 3 is regarded as beyond full closure by approximately 15.5 EFPtl's..

The tube hoop strain contours estimat d for 15.5 EFP !'s beyond full closure were utilized to determine the 17.5% boundary for the inspection in.the tubelane region.

Additional inspection

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wedge, and patch p1ate regions.

These prog'rams were based on previous tube leakage histories at the Turkey Point and Surry plant sites, as well as previous gauging results at the Surry and Turkey Point sites, as deemed appropriate. 'ue to the current awareness of"the potential for tube deformation on the cold leg side,. inspections of all three steam generator cold legs were performed.

The inspection boundary for the January 1979 inspection (Figure 1) is included for reference.

The gauging inspection boundari'es for the December 1979 inspection are indicated in Figure 2 (typical hot leg) and Figure 3 (typical cold leg).

It -should be noted that the cold legs and cer ain peripheral wedge ar'eas in the hot. legs were inspected. for the first time in January 1979.

The following additional conservatisms were utilized in determining the Turkey Point, 3 inspection boundary:

1.

In the tubelane area it is estimated by analysis that the 17.5Ã strain boundary at 15.5 EFPN beyond full closure'xtends to approximately the Sth row.

The inspection, boundary for this inspection extended to the 10th row.

2. If a restricted tube was found close to the inspection
boundary, the inspection was expanded in that area.

3.

In addition to the specific gauging.inspection program, it should be noted that the central portion of the tube bundles from row 14 upward were tested with 700 mil probes,.providing early.indications on any new deformation which might exist away from the regions usually regarded as acti ve, i.e. the

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tubelane, patch plate,
wedges, and oeriphery.

4.

Tubes restricted in previous inspections, but not adjacent to 'the areas of predominant activity, were retested if not part of the gauging program laid out generally for the thre steam generators'

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B.

Flow'Slot:Measurements Photographs, vere taken in each steam generator through the secondary handholes.

These photographs were then'tilized to measure the openings in the visible flow slots.

Results are discussed in Section III.

Flow slot measurements are utili'zed in the finite element analysis work and are an indicator of the present status of denting in the steam generators.

C.

Other Dentin Related Ins ections

.The,U-'ends of unplugged. tubes in rows 2 thru 5 in steam generator B

were examined v(ith 100 KHZ.

These inspections are performed to confirm the integrity of the small radius U-bends in low number rows.

0.

Re ulatorv Guid 1.83 R.G..

1.83 Inspection Th types and extent of insoections required in this area are speci ied in 'R.G. 1.83.

Typical inspection plans are included (Figures 4 and.5).

During the inspections, expansion of the program in steam generators B and C was accomplished as required by R.G. 1.83.

Results of the inspection are discussed later in this report (as available).

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III.'Ins ecti'on'Results A.

Gau in Pro rams

,Results of the gauging inspections are indicated'n. Figures 6, 7, 8, 9, 10, and 11 and are'summarized in Table 2..

Table 2:

Tube Restriction Summary Number of Tubes Restricting Passag of Gauge SG/

Gauge Diameter Tubelane Hot Leg Cold Leg Periphery and l~'edge Patch Plate Hot Leg Cold Leg Hot Leg

'SGA

.650"

.610"

.540" 31 5

0 0

0 0

433" 1

0.

1 0

35 0

0 SG 8

.650"

.610"

..540" 8

3 0

0 1

0 19 1

0 2

0 1

0 0.

SG C

6 50 II 22

.0 15 0

.610".

5 0

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Summary. comments resulting from the review of this and other data are as 2

0 fol 1 ows:

1.

Tubes in the tubelane region thai restrict the 0.650 inch probe or less lie within the 17..5~ strain boundary.

2.

There were no tubes in the'tubelane region restricting a 0.540" probe (hot leg and cold ')eg).

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Page 6

3'.'n steam generators A, B, and C; restricted'ubes generally developed adjacent to'revious 'activity or clustered together with other new 'activity..

This was particularly true of tubes that restricted the 0.610" and 0.540" probes.

Areas of activity were consistent with past historical data.for this and other plants.

Areas of note were rows 1-15 and 77-92 near the flow slots which finite element analysis predicts should progress much more rapidly than other flow slot areas.

The wedge and tubelane interaction is apoarently causing the finite element analysis to over predict this reaction since the activity in this area is consistent with the remainder of the tubelane flow slots.

In this and in future inspections, this area will be plugged under. the same criteria as the rest of the tubelane area.

4.

Tube restrictions were noted in some of the inspected wedge areas

(.in only the hot legs) of all steam generators and this activity appears consistent w1th previous experience at this and other units.

5.

In this inspecti.on of. the cold leg areas, only one tube restriction was noted. in the tubelane region (SGB).

No activity was noted in the three cold leg wedge areas inspected.

However, slight activi ty was 'noted adjacent to

'he. inspected wedge area in SGB.

The level of activity is consistent with that noted previously in the Turkey Point Unit'4 inspection.

The overall level of activity continues to indicate a very, low growth rate as compared to the hot leg.

6.

During the last 6

EFPl"I of operations, no leakage events occurred.

7.

Review of the gauging results for this six month period shows that 75 tubes were reoorted restricted in the tubelane region; this compares with 214 observed in January, 1979 after 9.5 EFPYi.

The apparent reduction in the number of restrictions reflects the fact that plugging in February, 1979 'was

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performed for a 10 month operating period, but only six months of operation actually ensued.

Therefore, it appears hat the plugging criteria adopted for 10 months operation back in February, 1979 v:ere.conservative.

B.

Flow Slot iIeasurements The results of the flow slot measurements are provided by Fig 12.

C.

Other Dentin Related Ins ections The U-bends of unplugged tubes in rows 2 thru 5 in steam generator 8

were examined at 100 KEIZ.

No indications wire noted in these small radius U-bends.

D.

Re ulator Guide 1.83 Ins ection Results and Evaluati'on

'The regulatory Guide 1.83 'i'nspection results indicate no significant progression of thinning.

A total of only seven tubes were plugged'ased on a 40%=-wall thinning criterion.

The majority of the tubes plugged be-cause of thinning exceeded tne 40% criterion by a very smal amount (within the tolerance of the Eddy Current method),

and the actual thinning of those'ubes may have been less than 40%.

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IV. Plu in Criteria The, progression of strain contours over, the intended operating period is utilized as the basis for preventive plugging of tubes in the tubeland region which are located'n rows beyond 0.540" restri cted tubes.

In earlier inspections the closeness of the strain contour lines prevented identificat',on of the appropriate contour which most reasonably indica ed the extent and progression of tubes with greatest deformation.

Initially, the 15~ strain contour was chosen when limi.ted plant specific data was available and the strain contour lines indicated by finite element analysis fell close together on the plots..

A 'review of the relationsh-p between the most res.ricted'ubers at turkey.Point Units 3 and 4 and the finite elemen; analysis strain contours, indicates that the 17.5Ã strain contour'ore realistically estimates the boundary of these restricted'ubes.

The growth of this contour was evaluated and conservative rate

. of growth for a ten month operating period was'determined;.;that is, three rows should be plugged over most of the tubelane and up to six rows at the outside columns..

Again, it should be pointed out that there have'een numerous cases of tubes restrictinq the 0.540 inch probe for some'ime and not leaking.

In any case the absence of any 0.540 inch restrictions in the tubelane region negates the application 'of this criterion.

The criterion established for plugging tubes in the region of the patch-plate differs from that used for other regions of the bund',e.

All leaks in the patchplate region have occurred at the perimeter of the plate or near to the 'patchplate

boundary, where plug welds connect the patchplate to the main, body of the tube support plate.

All observed data indicate that the phenomenon at the patch plate is local in nature and is not consistent with

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e tne general strained state of the plate, nor can the phenon.enon be

,represented by the finite element model.

Due to these factors, tne region of the patchpl'ate is inspected and a specific set of plugging criteria applied.

'Because of the fact that leakers in this reg'.on have not always res.ricted 0.5-'.0 nch probes, leakers and,tubes that r s r'ct the'.5-':0 inch probe should be treated alike, and the surrounding tubes about both should be plugged.

In addition, tubes that restrict the 0.510 inch probe should be plugged and tubes on either side of the patchpl'ate.boundary (plate perimeter on one side the plug welds on the other three sides) that restrict the 0.650

',nch probe shoul.d be plugg d.

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'inally, due to the'local plate. cracking that is believed to'occur at. the periphery.and near wedge locations, tube leaks may occur here at lower levels of tube restriction-than in the tubelane.

This, the wedge areas should have thei r own inspection program and plugging criteria, The plugging, criteria at hot leg wedge locations cal'ls for tr ating leakers and tubes that restrict the 0.540 inch probe in a similar manner.

In addition, tubes that restrict the 0.610 inch probe and peripheral tubes that restrict the 0.650 inch probe should be plugged.

Cold leg plugging will be based on the degree of activity noted and rates of progression, observed from gauging.

In assessing a

10 month operating period, it was deemed appropriate that more

.preventive plugging be accomplished beyond that dictated. by the above considerations.

It was determined that this basis should rely on plant specific information rather than finite element analysis results.

Since the.

prooosed 10 month cycle is approximately thai for which preventive plugging was performed in February,

1979, an evaluation of tube restriction behavior over the latest period, i.e. the absence of ".540 incn restrictiors in the iubelane, a~"licaiion of the approach adopted in February, 1979 is appropr;a-.e.

The bas.is

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'f the evaluation:(as the comvarison of the,650 inch restricted

-tubes remaining unplugged from the prior inspection and the gauging results on these tubes during this inspection.

The average and conservative estimate of subsequent re-duction was calculated to be approximately 70 mi'is for 10 months.

Thus, if a.650",restricted tube is just slightly above

.610", it is conservativ.

to assume that in 10 months, this tube could reach

.540".

In'pplying these results, engineering judgement was exercised'o choose

.650" restricted tubes most likely to -be close to.610".

In general, tubes restricting a.650" probe located in plugging valleys, those in close proximity to.610" and

.540," restricted tubes, and those in areas of current r

activity were considered for plugging.

The. plugging criteria which supoorts at least ten months of operation are:

l.

All tubes which do not pass the 0.540 inch probe will be plugged.

2.

Additionally, for in excess of ten (10) months operation, three (3) tubes beyond (i.e

, higher row numbers) any tube in columrs 3.

4, 1-92 which di'd not pass the 0.540 inch probe in the tubelane region will be plugged.

All tubes which do not pass.the 0.610 inch probe will be plugged.

The tubes in any column for which plugging under criteria (1)

(2), or (3) above is implemented in the.tubelane region will also

,be plugged in the lower row numbered tubes back to the tubelane if not already plugged.

5.

As a,conservative

measure, tubes completely surrounding any known leaking tubes including the diagonally next tube will 'be plucged i'f not already covered by the foregoing criteria.

Since no leaking tubes were discovered, applicaiion of this criterion is not required.

6.

In any given'olumn which is surrounded by colu...ns containing tubes with -significant tube restrictions or prior plugging, (the. oby

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'reating a "plugging va11ej" in the pattern) engineering judgement will be used to fill the bottom of the valley.

In.he peripheral tubelane areas near the'three'and nine o'lock wedges','tubes'surrounded.

by previously plugged tubes or tubes exhibiting high deformation activity will be plugged based on engineering judgement.

Particular attention was paid to.650 restricted tubes relative to the ten month operation period.

7.

Addition'al preventive plugging will be implemented at the hot leg wedge locations.

This plugging will include all tubes that:

a.

restrict -the 0.540 inch probe b.

restrict the 0.610 inch probe c.

restrict the 0.650 inch probe at the periphery-d.

surround leake'rs a'nd tubes that restrict.the 0.540'inch probe including the diagonally next tube.

8.

Application of the criteria specified in 7. above, will be rrade on the basis of engineering judgement for cold'eg wedge locations.

9.

Additional preventive plugging will be implemented in the patchplate region.

This plugging.wi 11 include all tubes that:

a.

restrict the 0.540 inch probe

. b.

restrict the 0.610 inch probe c.

surround leakers and tubes that restrict the 0.540 inch probe including the diagonally next tube.

d.

lie on either sides of the patchplate boundary (plate perimeter on one side. the plug welds on the other three) and restrict the 0.650 inch probe.

The ten'onth operating period was also evaluated relative to a postulated main ste m line break accident

(.'1SLB).

In doing this tho finite element analysis plots for 18 and 24 EFPH beyond closure (Figures

'3 and 14 >>ere considered.

These are considered to be representati ve of the

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Page 12 anticipated advanced conditions of the'urkey Point Unit 3 'steam generators over the next ten month operating period.

It was assumed that the actual boundary of-,the 17.5/ tube loop strain contour in the most advanced steam generator (B) is. indicated in the tubela'ne region by the previous plugging boundary and the present

.540" restricted tubes.

Using the.finite element analysis results

above, the advancement of the 17.55 tube loop strain contour over the next ten months was estimated to be 1.9.rows.

Using the fact that there are 92 tubes in a'row, the total predicted, tubes in the tubelane region lying within the 17.5Ã strain contour. at the end of the next ten months is:

1.9 rows in ten months x 92 tubes per ro>> = 175 tubes

.Subtracting out the tubes that were preventively plugged in this area in steam generator B this time (14) 'results in a total of 161 '.unplugged tubes within the I7:5/ strain contour at the end of the ten month operating period.

Assuming one intersection involvement per tube and assuming these tubes would leak during a postulated main steam line break, the total rosulting leakage from these tubes would be:

P 161 tubes.

x 0.05 GPN =.8.05 GPll tube This added to the 0.3 GPM leakage assu",:od.to be present at the s"art of a postulated main steam line break (which would increase to approximately 0.7 GPH due to fISLB differential pressures) yield a total 1'eakage less than 10 GPH, which has been determined

.in previous submittals to be an acceptab'ie level of leakage during a postulated ViSLB.

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Page 13'.Re ulator'Guide'1:83 The criteria for.plugging tubes in this area are established in the regulatory guide.

C.

Preventive Plu ging Accom lished The:preventive plugging programs that i;ere implemented are indicated in Figures 15, 16, and 17.

Both gauging and R gulatory Guide 1.83 program I

.plugging are indicated.

Table 3 summarizes this plugging.

TABLE 3 Summary of Tubes Plugged

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'. R,'G; '1.83 SG A

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52 NOTE:

The numbers above are preliminary.

Plugging operations are not completed as of this writing, therefore.,

the final numbers may be slightly.-

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TYPICAL GAUGIHG INSPECTION BOUNDARY -

COLD LEG DECENBER 1979 IHSPECTIOH Test B)ocked-in Region NOZZLE

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ROWS NANWAY 0 GAUGING PLUGGING 8 PREVIOUSLY PLUGGED FIGuRE 15 STEALI IEHERATOR A PREvEHTIvE PLUGGIHG PATTERN

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MANMAY

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