ML18348A887

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Submittal of Completed Steam Generator Operating History Questionnaire
ML18348A887
Person / Time
Site: Palisades Entergy icon.png
Issue date: 06/26/1978
From: Hoffman D
Consumers Power Co
To: Ziemann D
Office of Nuclear Reactor Regulation
References
Download: ML18348A887 (28)
v • d • e


Text

consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201

  • Area Code 517 788-0550 Ju."le 26, 1978
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-,!i" Director, Nuclear Reactor Regulation Att:

Mr Dennis L Ziemann, Chief Operating Reactors Branch No 2

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US Nuclea+ Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - STE.AM GENERATOR OPER~TL~G HISTORY QUESTIONNAIRE CJ r l

(/'J Consumers Power was requested by letters dated December 12, 1977 and c**

C'.)

~~-~-l r*,)

February 10, 1978 to complete a "Steam Generator Operating History Question-naire" for the Palisades Plant.

Completion cf the questionnaire was delayed until results of the most recent steam generator inspection could be compiled and reviewed.

It must be emphasized that the completed questionnaire (attached) does pot supersede previously submitted steam generator inspection reports. All of the information provtded in the questionnaire has been previously sub~itted but was reproduced where applicable.

The effort required to complete the questionnaire was extensive (awroximately 5 man-weeks) and represents an undue burden on Consumers Power in light of current Technical Specification reporting requirements.

David P Hoffman Assistant Nuclear Licensing Administrator CC:

JGKeppler, USNRC I

ENCLOSURE 1 STE.AM GENERATOR OPERATING HISTORY QUESTIONNAIRE NOTE:

All percentages should be reported to four significant figures.

I.

BASIC PLANT INFORMATION Plant:

Palisades Nuclear Plant Startup Date:

December 31, 1971 Ut~lity: Consumers Power Company Plant Location:

Route 1, Box 178, Covert, ~.I 49043 Thei:mal Power Level:

2530 MWt Nuclear Steam Supply System (NSSS) Supplier:

Combustion Engineering, Inc Number of Loops.:

2 Steam Generator Supplier, Model No. and Type:

CE, Unit 1 - S/N CE 66501, Vertical Unit 2 - S/N CE 66502, "U" Tube Number of Tubes Per Generator:

8519 Tube Size and Material: -J/4" 0.D., 0. 048" Wall, Inconel 600 Tubing II.

STEAM GENERATOR OPERATING CONDITIONS Normal Operation 0

Secondary Temperature:

513.8 F Secondary Flow Rate:

5.281 x io6 lb/hr (each loop)

Primary Pressure:

2100 psia Secondary Pressure:

770 psia Accidents Design Base LOCA Max. Delta-P:

1000 psia Main Steam Line Break (MSLB) Max. Delta-P:

2500 psia III.

STEAM GENERATOR SUPPORT PLATE INFORMATION Material:

Carbon Steel, SA-36 Allowable Leak.age Rate:

0.3gpm/24 consecutive hours Design Type:

Full and partial plates with drilled tube and flow holes and flow cut-outs.

Design Code:

1965 edition of the ASME Code,Section III for Class A Vessels.

2 Dimensions:

Flow Rate:

3/4" 5.281 takes Thick Plate, full and partial plates 6

x 10 lb/hr + for full support plate; some recirculation place on secondary side Tube Hole Dimensions:

. 765" Dia.meter Flow Hole Dimensions:

.250" Diameter, 2 per Tube Hole IV.

STEAM GENERATOR BLOWDOWN INFORMATION (Secondary)

Frequency of Blowdown:

Continuous during power operation Normal Blowdoml Rate:

10,000 lb/hr per steam generator Blowdown Rate w/Condenser Leakage:

25,000 lb/hr per steam generator Chemical Analysis Results Assumes no condenser tube leaka e (Typical during Results normal operation) pH 9

Specific Cond.

3. 6.umho/ cm Na+

..:. 2 ppb Silica

<l ppm Suspended Solids <l ppm V.

WATER CHEMISTRY INFORMATION Secondary Water Para.meter Control Limits (F~:in~rmtalt~per)ation a

nis ra ive pH 8.5-9.2 Specific Cond 7. 0 A.Unho I cm Na +

70 ppb Silica 1 ppm Suspended Solids 1 ppm

~JPe of Treatment and Effective Full Power (EFP) Months of Operation:

AVT: Hydrazine for 02, Morpholine for pH, 18 EFP Months (up to January, 1978)

Typical Chemistry or Im.purity Limits:

Normal-Administrative - pH: 8.5-9.2, specific conductivity: 7.0..1\\.Ullho/cm, Na+: 70 ppb, Silica: 1 ppm, Suspended Solids: 1 ppm Feedwater Typical Chemistry or Im.purity Limits:

Normal-Administrative: pH: 8.8-9.2, Cation conductivity: 0.5...umho/cm, 02: 10 ppb, Iron': 10 ppb, Copper: 10 ppb Condenser Cooling Water Typical Chemistry or Im.purity Limits:

Langelier's Limits - +1.0 to +1.5 pH - 7.8 to 8.5

3 Demineralizers - Type:

Powdered resin condensate polishers Cooling Tower (open cycle, closed cycle or none):

closed cycle VI.

TUREINE STOP VALVE TESTING (applicable to Babcock & Wilcox (B&W) S.G. only)

NA - Palisades has CE steam generators Frequency of Testing Actual:

Manufacturer Recommendation:

Power Level At Which Testing Is Conducted Actual:

Manufacturer Recommendation:

Testing Procedures (Stroke length, stroke rate, etc.)

Actual:

Manufacturer Recommendation:

VII.

STEAM GENERA.TOR TUBE DEGRADATION HISTORY The NRC has received previous submittals on all Palisades Steam Generator Inspections to-date; therefore, Part VII will only be completed for the 1978 Steam Generator.Inspection results.

The inspection dates and corresponding CPCo submittals are as follows:

Inspection Date 09/73 06/74 12/74 02/75 01/76 01/78 Primary Submittal Date 21/21/73 7/9/74 1/3/75 3/10/75 3/9/76 3/1/78 Inservice Inspection (ISI) Date:

January, 1978 Reference Submittal Date 1/29/74 8/20/74 1/31/75, 2/6175 3/25/75, 6/24/75 3/22/76 2/27/78, 3/3/78, 4/5/78 Number of EFP Days of Operation Since Last Inspection:

508 EFP days

4 Steam Generator Number:

A Percentage of Tubes Inspected At This ISI:

hot leg 21.7%, cold leg 1.3%

Percentage of Tubes Inspected At This ISI That Had Been Inspected At The Previous Scheduled ISI:

20.9%

Percentage of Tubes Plugged Prior to This ISI:

22.6%

Percentage of Tubes Plugged At This ISI:

.11%

Percentage of Tubes Plugged That Did Not Exceed Degradation Limits:

.03%

Percentage of Tubes Plugged As A Result of Exceedance of Degradation Limits.:

, 08%

Sludge Layer Materi8.l Chemical Analysis Results:

None (Flushing constituents showed sulfide ions)

Sludge Lancing (date):

None Ave. Height of Sludge Before Lancing:

NA Ave. Height of Sludge After Lancing:

NA Replacement. Retubing or Other Remedial Action Considered: (Briefly Specify Details)

Sleeving performed in 1978 (13 sleeves).

Replacement steam generators are on order.

Support Plate Hourglassing:

None known.

Support Plate Islanding:

None known.

Tube Metalurgical Exam Results:

Tube metalurgical exam results have shown intergranular attack but stress corrosion cracking has not been found.

(Prior to 1978 Inspection)

Steam Generator Number:

B Percentage of Tubes Inspected At This ISI:

hot leg 16.9%, cold leg 1.0%.

Percentage of Tubes Inspected At This ISI That Had Been Inspected At The Previous Scheduled ISI:

15.2%

Percentage of Tubes Plugged Prior To This ISI:

20.5%

Percentage of Tubes Plugged At This ISI:

.08%

Percentage of Tubes Plugged That Did Not Exceed Degradation Limits:

.03%

Percentage of Tubes Plugged As A Result of Exceedance ofDegradation Limits:

.05%

Sludge Layer Material Chemical Analysis Results:

None (Flushing constituents Sludge Lancing (date):

None Ave. Height of Sludge Before Lancing:

NA Ave. Height of Sludge After Lansing:

NA showed sulfide ions)

Replacement, Retubing or Other Remedial Action Considered: (Briefly specify Details)

Sleeving performed in 1976 ( 14 sleeves) and 1978 (lo sleeves).

Replacement steam generators are on order.

Support Plate Hourglassing:

None known.

Support Plate Islanding:

None known.

5 Tube Metalurgical Exam Results:

Tube metalurgical exam results have shown intergranular attack but stress corrosion cracking has not been found.

(Prior to 1978 Inspection)

e**

A HOT LEG NA - Palisades has not observed any fretting or vibration.

Fretting or Vibration in U-Bend Area (not applicable to B&W S.G.) AS OF i'.tl Percentage of Tubes Plugged Other Preventive Measures Wastage/Cavitation Erosion AS OF i..!+/-1 January, 1978 AHot Leg: (Repeat this information for the cold leg on Combustion Engineering (C.E.) and Westinghouse (W) S.G.)

Table based solely on 1978 Data......

Area of Tube Bundle (1) a b

c

% of Tubes Affected by Wastage/Cavitation Erosion 12%

% of Tubes Plugged Due to Exceedance of Allowable Limit (2) 0%

% of Tubes Plugged That Did Not Exceed Degradation Limit 0%

Location Above Tube Sheet ( 3)

.1%

Max. Wastage/Cavitation Erosion Rate for Any Single Tube (Tube Circum. Ave)(Mills/Month)

.29 Max. Wastage/Cavitation Erosion in Any Single Unplugged Tube (Tube Circum. Ave) (Mills) 21 Cracking AS OF 1.'.+/-l Caustic Stress Corrosion Induced in C.E. and W S.G.

Flow Induced Vibration Caused in B&W S.G.

d e

25%

.06%

.03%

4.8%

.29 33 6

  • B HOT LEG NA - Palisades has not observed any frett"ing or vibration.

Fretting or Vibration in U-Bend Area (not applicable to B&W S.G.) AS OF 1!+/-...2.

Percentage of Tubes Plugged Other Preventive Measures Wastage/Cavitation Erosion AS OF* l!:.l January, 1978 B Hot Leg: (Repeat this information for the cold leg on Combustion Engineering (C.E.) and Westinghouse(!!) S.G.)

Table based solely on 1978 Data...*..

Area of Tube Bundle (1) a b

c qf of Tubes Affected by

/0 Wastage/Cavitation Erosion 14%

% of Tubes Plugged Due to Exceedance of Allowable Limit (2) 0%

% of Tubes Plugged That Did not Exceed Degradation Limit 0%

Location Above Tube Sheet (3) 0%

Max. Wastage/Cavitation Erosion Rate for Any Single Tube (Tube Circum. Ave)(Mills/Month)

.29 Max.' Wastage/Cavitation Erosion in Any Single Unplugged Tube (Tube Circum. Ave)(Mills) 22 Cracking AS OF (4)

Caustic Stress Corrosion Induced in C.E. and W S.G.

Flow Induced Vibration Caused in B&W S.G.

d e

17%

.05%

.05%

.2%

.29 29 7

8 A COLD LEG NA - Palisades has not observed any fretting or vibration.

Fretting or Vibration in U-Bend Area (not applicable to B&W S.G.) AS OF.£2:1 Percentage of Tubes Plugged Other Preventive Measures Wastage/Cavitation Erosion AS OF l2:l January, 1978 A Cold Leg:

(Repeat this information for the cold leg on Combustion Engineering

( C.E.) and Westinghouse (~) S.G.)

Table based solely on 1978 Data.*..

Area of Tube Bundle ( 1) a b

% of Tubes Affected by Wastage/Cavitation Erosion 0%

% of Tubes Plugged Due to Exceedance of Allowable Limit (2) 0%

% of Tubes Plugged That Did not Exceed Degradation Limit 0%

Location Above Tube Sheet (3) 0%

Max. Wastage/Cavitation Erosion Rate for Any Single Tube (Tube Circum. Ave)(Mills/Month) 0 Max. Wastage/Cavitation Erosion in Any Single Unpltigged Tube (Tube Circum. Ave)(Mills) 0 Cracking AS OF ~

Caustic Stress Corrosion Induced in C.E. and W S.G.

Flow Induced Vibration Caused in B&W S.G.

c d

e 1%

0%

.09%

.1%

.29 23

9 B COLD LEG NA - Palisades has not observed any fretting or vibration Fretting or Vibration in U-Bend Area (not applicable to B&W S.G.) AS OF 1i.l Percentage of Tubes Plugged Other Preventative Measures Wastage/Cavitation Erosion AS OF (4). January, 1978 B Cold Leg: (Repeat this information for the cold leg on Combustion Engineering (C.E.) and Westinghouse(}'.!) S.G.)

Table 'based solely on 1978 Data Area of Tube Bundle (1) a b

c of of Tubes Affected by

a Wastage/Cavitation Erosion 0%

% of Tubes Plugged Due to Exceedance of Allowable

.Limit (2) 0%

% of Tubes Plugged That Did not Exceed Degradation Lim.it 0%

Location Above Tube Sheet (3) 0%

Max. Wastage/Cavitation Erosion Rate for Any Single Tube (Tube Circum. Ave)(Mills/Month) 0 Max. Wastage/Cavitation Erosion in Any Single Unplugged Tube (Tube Circum. Ave) (Mills) 0 Cracking AS OF (4)

Caustic Stress Corrosion Induced in C.E. and W S.G.

Flow Induced Vibration Caused in B&W S.G.

d e

0%

0%

.09%

0%

0

<.9. 6

10

  • Cracking (Continued)

NA - Cracking has not occurred at Palisades.

A&B Hot Legs:(Repeat this information for the cold leg on C.E. and }i S.G.)

(1)

Area of Tube Bu.ri.dle a

b c

d e

% of Tubes Affected by Cracking

% of Tubes Plugged Due to Cracking

% of Tubes Plugged That Did Not Exceed Degradation Limit Location A,bove ( 3)

Tube Sheet Rate of Leakage From Leaking Cracks (gpm)

Denting (Not applicable to B&W S.G.) AS OF~

January~ 1978 A Hot Leg:(Repeat this information for the cold leg on C.E. and W S.G.)

Table based solely on 1978 Data......

Area of Tube Bundle ( 1) a

% of Tubes Affected by Denting 12.4%

% of Tubes Plugged Due to Exceedance of Allowable Limit (2) 0%

% of Tubes Plugged That Did Not Exceed Degradation Limit 0%

Rate of Leakage From Leaking Dents (gpm) 0 Max. Denting Rate for Any Single Tube (Tube Circum.

Ave) (Mills/Month)

.26 Max. Denting in Any Single Unplugged Tube (Tube Circum. Ave) (Mills) 5.8 b

c d

e 24.5%

.04%

0%

0

.29 5.8 NOTE: The maximum dent sizes are based on saturated ECT readings which have been shown to be ~5.8 mills.

The operating period was 20 months.

11 Denting (Continued)

B Hot Leg: (Repeat this information for the cold leg on C.E. and~ S.G.)

Table based solely on 1978 Data Area of Tube Bundle (1) a b

c d

% of Tubes Affected by Denting 11.9%

% of Tubes Plugged Due to Exceedance of Allowable Limits (2) 0%

% of Tubes. Plugged That Did Not Exceed Degradation Lim.it 0%

Rate of Leakage From Leaking Dents (gpm) 0 Max. Denting Rate for Any Single Tube (Tube Circum. Ave) (Mills/Month)

.29 Max. Denting in Any Single Unplugged Tube (Tube Circum. Ave) (Mills) 5.8 Cracking NA - Cracking has not occurred at Palisades.

e 19.8%

0%

0%

0

.29 5.8 NOTE: The maximum dent sizes are based on saturated ECT readings which have been shown to be ~5.8 mills.

The operating period was 20 months.

A&B Cold Legs: (Repeat this information for the cold leg on C.E. and~ S.G.)

Area of Tube Bundle (1) a b

c d

e

% of Tubes Affected by Cracking

% of Tubes Plugged Due to Cracking

% of Tubes Plugged That Did Not Exceed Degradation Limit Location Above (3)

Tube Sheet Rate of Leakage From Leaking Cracks (gpm)

12

  • Denting (Not applicable to B&W S.G.) AS OF ill January, 1978 A Cold Leg: (Repeat 'this information for the cold leg on C.E. and !i_ s.T.)

Table based solely on 1978 Data....

Area of Tube Bundle ( 1)

% of Tubes Affected by Denting

% of Tubes Plugged Due to Exceedance of Allowable Limit (2)

% of Tubes Plugged That Did Not Exceed Degradation Limit Rate of Leakage From Leaking Dents (gpm)

Max. Denting Rate for Any Single Tube (Tube Circum. Ave) (Mills/Month)

Max. Denting in Any Single Unplugged Tube (Tube Circum. Ave) (Mills) a b

c d

.1%

0%

0%

0

.29 5.8 e

1.3%

0%

.04%

0

.29 5,8 NOTE: The maximum dent sizes are based on saturated ECT readings which have been sho~

to be ~5.8 mills. 'fl9 operating period was 20 months.

13 Denting (Continued)

B Cold Leg: (Repeat this information for the cold leg on C.E. and W S.G.)

Table based solely on 1978 Data...*

Area of Tube Bundle (1)

% of Tubes Affected by Denting

% of Tubes Plugged Due to Exceedance of Allowable Limit (2)

% of Tubes Plugged That Did Not Exceed Degradation Limit Rate of Leakage From Leaking Dents (gpm)

Max. Denting Rate for.Any Single Tube (Tube Circum.. Ave) (Mills/Month)

Max. Denting in Any Single Unplugged Tube (Tube Circum.. Ave) (Mills) a b

c 0%

0%

0%

0 No common data points 5.8 d

e

.9%

0%

0%

0

.29 5.8 NOTE: The maximum* dent sizes are based on saturated ECT readings which have been shown to be ~5.8 mills.

The operating period was 20 months.

14

  • Denting (Continued)

A Hot Leg:

Table based solely on 1978 Data *.*.

Support Max. Denting in Any Single

% of Tubes Affected By Plate TUbe in Bundle Area Denting in Bundle Levels (Tube Ave) (Mills) ( 1)

Area a

b c

d e

a b

c d

e 1

.7 1.5

.3

.1 2

1.7 5.8 6.7 12.4 3

5.8 5.8 7,9 11.4 4

5.8 5.8 5.1 11.4 5

5.8 2.5 4.6 7.0 6

2.5 1.5 1.7 4.9 7

5.8 5.8 3,5 4.7 8

,5 0

.1 0

9 5.8 1.5

.2

.4 1 0 5.8 5.8 5,5 9.0 1 1 3.0 5.8 2.9 7.9 1 2 5.8 5.8 3.1 6.2 1 3 5.8 1.1 1.6 0

1 4 5.8 NA

.9 0

\\.

NOTE:

The maximum dent sizes are based on saturated ECT readings which have been shown to be ~5.8 mills.

1 1

1 1

1 Denting (Continued)

B Hot Leg:

Table based solely on 1978 Data....

Support Max. Denting in Any Single

% of Tubes Affected By Plate Tube in Bundle Area Denting in Bundle Levels (Tube Ave) (Mills) (1)

Area a

b c

d e

a b

c d

e 1

1.9 1.3

.8

.5 2

5.8

1. 7 10.0 15.1 3

5.8 5.8 7.1 11.1 4

5.8 5.8 4.3 9.9 5

5.8 3.0 7.2 8.4 6

1.2 3.0 2.3 7.2 7

5.8 5.8 6.o 9.4 8

.8

.2

.3

.1 9

.9 1.2

.2

.3 0

5.8 1.3 4.9 8.0 1

5.8 5.8 3.9 6.1 2

1.5 5.8 4.7 4.9 3

5.8

.9

1. 7

.1 4

2.2 NA

.3 0

NOTE:

The maximum dent sizes-are-based on saturated ECT readings which have been shown to be ~ 5. 8 mills.

15

Denting (Continued)

A Cold Leg:

Table based solely on 1978 Data *.*.

support Max. Denting in Any Single

% of Tubes Affected By Plate Tube in Bundle Area.

Denting in Bundle Levels (Tube Ave) (Miils) (1)

Area

a.

b c

d e

a b

c d

e 1

0 0

0 0

2 5.. 8 5.8

.3 1.2 3

1.3 5.8

.1

.6 4

5.8 5.8

.1

.8 5

0 5.8 0

.2 6

0 1.7 0

.4 7

0 1.1 0

.1 8

0 0

0 0

9 0

1.3 0

.1 1 0 0

1.0 0

.2 1 l

.4 5.8

.1

.5 1 2 0

.9 0

0 1 3 0

0 0

0 4

0 NA 0

0 1

NOTE:

The maximum dent sizes are based on saturated ECT readings which have been shown to be 1:5. 8 mills.

16

  • Denting (Continued)

B Cold Leg: Table based solely on 1978 Data Support Max. Denting in Any Single

% of Tubes Affected By Plate Tube in Bundle Area Denting in Bundle Levels (Tube Ave) (Mills) (1)

Area a

b c

d e

a b

c d

e 1

0

.7 0

.1 2

.5 5.8

.1

,9 3

5.8 5,8 0

.5 4

5.8 5.8 0

,7 5

0 1.5 0

.2 6

0 1.5 0

.3 7

0 5.8 0

.1 8

0 0

0 0

9 0

.6 0

.1 1 0 0

1.4 0

.2 11 0

1.1 0

.2 1 2 0

5,8 0

.2 1 3 0

.5 0

0 4

0 NA 0

0 1

NOTE:

The maximum dent sizes are based on saturated ECT readings which have been shown to be ~5.8 mills.

18 TABLE KEY NOTE:

All percentages refer to the percent of the tubes within a given area of the tube bundle.

(1)

Area of the Tube Bundle

a.

Periphery of Bundle (wi/20 rows for B&W; wi/10 rows for CE and }'!,)

b.

Patch Plate (wi/4 rows)

c.

Missing Tube Lane (B&W only)

(wi/5 rows)

c.

Flow Slot Areas (CE and}'!, only)

(wi/10 rows)

No. of Tubes Within the Area 2036 NA NA The flow slot areas of the various support plates cover the entire tube bundle area; therefore, this area is the same as for a. and e.

No signi-ficant effects have been seen assoc-iated with the flow slots.

See attached diagram of the flow slot areas.

d.

Wedge Regions (CE and E, only)

(wi/8 rows r The wedge attachments for the 14 support plates cover the entire peri-fery of the steam generator; therefore, this area is the same as in a. Perifery of Bundle, above.

See CPCo March 3, 1978 submittal to the NRC.

e.

Interior of Bundle (remainder of tubes)

( 2) 6483 Allowable Limit for Wastage/Cavitation Erosion: (based on % reduction of wall thickness) 64%,

exce~t multiples: 30%.

NOTE:

  • Operating allowances applied to this limit.

Allowable Limit for Denting:

Blockage of.540 11 ECT probe.

  • See Tabie 4.14 of Tech Spec for Operating Allowance.

( 3)

l. Specifies area between the tube sheet and the first support plate NOTE:

.All short radius U-bend tubes were plugged out to Row 11.

2.

Specifies in the following locations: (list the additional locations)

Wastage/Cavitation Erosion:

Throughout steam generator Cracking:

None

( 4)

Specify the date of the inspection for which results have been tabulated; Jam~ary, 1978 19

20 VIII. SIGNIFICANT STEAM GENERATOR ABNORMAL OPERATIONAL EVENTS DATE

SUMMARY

(Include event description; unscheduled ISI results, if performed; and subsequent remedial actions)

No abnormal events occurred in the last cycle.

For previous abnormal events, see Annual Operating Reports.

IX. CONDENSER INFORMATION Conaenser Material For perifery and air removal: SS type 304 (18-8)

Tube Leak.age Date Rate (gpm)

I See Annual Operating Reports I Latest Event Detectable Limit Detection Method Atomic Absorption Spectrophotometer with Graphite Furnace Accessory For all other areas:

90 cu-lONi (Previously Admiralty) 12-27-771

.15 gpm

.05 gpin (After April, 1976)

  • X. RADIATION EXPOSURE HISTORY WITH RESPECT TO STEAM GENERATORS Date Exam Dosage (Man-Rem) 1976 35.8 Mari.-Rem 1978
44. 3 Man-Rem Repair Dosage (Man-Rem)

Comments 227.1 Man-Rem Repair dosage includes all misc. dosage.

180.0 Man-Rem Repair dosage includes all misc. dosage.

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22

  • XI.

DEGRADATION HISTORY FOR EACH TYPE OF DEGRADATION EXPERIENCED FOR TEN REPRESENTATIVE, UNPLUGGED TUBES FOR WHICH TWO OR MORE ISI'S ARE AVAILABLE:

Steam Generator A - Wastage Tube Identification Indication (in % Wall Thickness Reduction)

Quad Line Row Level 09/73 06/74 12/74 02/75 01/76 01/78 l*

26 61 l.i

<20 22 22 D ~ 20 4+

< 20 2

17 90 3

38 38 36 37 31 38 2E 35 35 43 35 38 32 10

.t.20

<.20 4'20 2

37 84 3

45 45 40 38 3-35 2

75 48 4

"20

'20 36 D.

4-35 3

2 101 4

"-20 c.20

'-20 23 3

4 117 3

'-20

..:.20

<20

~20 12 42 42 36 37 41 HL 20

'"'20 3

11 110 3

"'20

""20

"'20

<20 3-

c. 20 12

..:20

<20 420 D

D HL 34 34 30 41 43 3

15 80 3

37 37 33 30 3-35 3

21 94 3

~20 35 420 34

<-20 4

48 31 TS

.... 20

'-20

20.

4 34 30 33 4-27 NOTE:

D designates a de!'lt for which readings are considered unreliable,

., '~-

I,-

23 XI.

(Continued)

Steam Generator A - Denting Tube Identification Inspection Dent Magnitude (Mils - radial '360° Denting)

Quad Line Row Date Steam Generator Level/Mils l'

16 75 01/76 2/.0, 3/.0, 10/.9, 11/.9 01/78 2/.8, 3/.8, 10/.6, 11/.9 2

2 113 01/76 4/.7, 5/1.3, 6/.4, 7/.7, 10/.0, 11/.4, 12/.4 Ol/78 4/i.7, 5/.7, 6/.0, 7/.0, 10/.9, 11/.9, 12/3.0 2

ll 128 Ol/76 3/.8 01/78 3/1.2 2

19 98 01/76 2/.7, 3/.0, 5/.4, 12/1.5 01/78 2/.0, 3/.4, 5/.0, 12/1.2 2

65 26 01/76 2/1.3, 4/.0, 6/.1, 10/.8 01/78 2/1.2, 4/.8, 6/.4, 10/.0 3

, 15 62 01/76 2/.4, 4/.8, 6/.5 01/78 2/.7, 4/1.9, 6/.7 3

20 51 01/76 2/.4, 3/2.2, 5/.4, 7/,7, 10/1.2, 11/. 7 01/78 2/xxx, 3/2.5, 5/.0, 7/.8, 10/1.1, 11/. 7 3

44 85 01/76 2/.5, 5/.9, 7/.4, 11/1.2 01/78 2/.4, 5/.4, 7/.0, 11/.5 3

63 50 01/76 2/1.1, 4/.9, 6/1. 2' 11/1. 9 01/78 2/.4, 4/1.2, 6/.7, 11/2.2 4

47 50 01/76 2/1.l, 4/.0, 11/1.3 01/78 2/.7, 4/.4, 11/.5 NOTE:

xxx signifies a saturated dent magnitude reading.

Saturated dent readings have been shown to be ~5.8 mils.

I e

I

('

~

24

  • XI.

(Continued)

Steam Generator B - Wastage Tube Identification Indications (in % Wall Thickness Reduction)

Quad Line Row Level 08/73 06/74 02/75 01/76 01/78 2

2 115 3

25 26 32

<20 3-30 10 30 36 44 40 11 30

<20 28 2

5 82 3

<. 20

<20

<20 29 3-30 2

6 109 3

"'20 D

420 10 40 38 38 45 43 12

.:;20

"'20

'"20 2

10 75 3

35 35 38 D52 3

R37 3-D30 2

47 32 4

<20 c::20 29 31 4-32 3

9 74 3

'20

<20 38 D

R33 3

13 106 3

"20 420 31 22 3-25 12 25 25 25 31 32 HL 420 28 30 3

40 57 4

D 11 40 40 33 48 53 3

54 87 3

.:;. 20

-<:.20 32 29 3-31 3

74 61 11+2 29 40 38 NOTE: D designates a dent for which readings are considered unreliable.

R designates a rotational ECT reading.

I~ **

~

~

25 11 XI.

(Continued)

Steam Generator B - Denting Tube Identification Inspection Dent Magnitude (Mils - radial 360° Denting)

Quad Line Row Date Steam Generator Level/Mils 1

12 113 01/76 2/.0, 3/.0, 10/.0 01/78 2/.5, 3/1. 5' 10/. 6 2

7 122 01/76 1/.5, 5/.7, 7/.9, 12/1.2, 13/.4 01/78 1/1.3, 5/.0, 7/.0, 12/.8, 13/.0 2

16.

53 01/76 2/.5, 3/1.2, 4/.0, 5/.0, 6/1.7, 7/.0, 11/.5 01/78 2/.4~ 3/1. 3, 4/.3, 5/,9, 6/1.1, 7/.7, 11/.4 2

24 89 01/76 2/Ll, 3/2.7, 5/.0, 7/1.3, 10/.5, 12/.5 01/78 2/1.8, 3/1. 5' 5/.4, 7/,7, 10/.5, 12/.4 2

69 42 01/76 2/.2, 4/1.2, 6/.8, 10/.7 01/78 2/.4, 4/1.9, 6/.5, 10/.2 3

1 74 01/76 2/.4, 3/.4, 4/1.2, 5/.0, 6/.0, 11/.o 01/78 2/.2, 3/. 5' 4/1. 9' 5/.2, 6/.4, 11/.2 3

25 86 01/76 2/.0, 3/1.1, 5/.8, 7/.9, 12/.9 01/78 2/.2, 3/1.1, 5/.5, 7/,5, 12/.0 3

51 14 01/76 2/.5, 3/.5, 5/.4, 7/.5, 9/.8 01/78 2/.5, 3/xxx., 5/.2, 7/.4, 9/.8 3

72 31 01/76 2/.5, 4/.5, 6/.0, 10/.0 01/78 2/.5, 4/1.7, 6/.4, 10/.4 4

20 105 01/76 2/.0, 3/.0 01/78 2/.2, 3/x:.a NOTE:

xxx. signifies a saturated dent magnitude reading.

Saturated dent readings have been shown to be ~5.8 mils.

I.:. \\*

26

\\

XI.

(Continued)

Inspection Dates Versus EFP Months Table Inspection Date EFP Months Between Inspection Dates 09/73 0 EFP - man.

06/74

.2 EFP - man.

12/74" 0 EFP - man.

02/75 5.4 EFP - man.

01/76 16.7 EFP - man.

  • .;'~

UNITED STATES*

NUCLEAR REGULATORY COMMISSION WASHINGTON, D: C. 20555

.. June* 21,.. 1978 All Power Reactor Licensees Gentlemen:

SUBJECT:

REVISIONS TO* INTRUSION* DETECTION SYSTEMS, AND ENTRY.' CONTROL

- HANDBOOKS*AND NUCLEAR SAFEGUARDS TECHNOLOGY HANDBOOK Enclosed is a copy of the Nuclear Safeguards; Techno*logy.Handbook wlifcn *was

  • prepa~ed* tinder- *coritra'ct'f'ortti~ DEfpartrnent
  • af*.-Energy '(OOE). *The purpose of this handbook is ta convey* an understand.ing. of the current SS safeguards technology development program and' its prospective relevance and use to, u*.s *. i.ndustri'aT and* utility organizations,,. as well as to other U*.S *. govern~

ment. agencies and. foternationa1 organi'zations *.

  • Also: enclosed are updates ta, the Entry-Control systems. Handbook" and the

Intrusion Detecti.on Systems Handbook 11

  • that were* sent to\\ you.. earlier.

Enclosures.:

As.stated

\\

\\

cc w/o enclosures:

Serv*i ce List James R *. Mi Tl er*, Assistant Director for Reactor Safeguards

.. Divjsion of Operating. Reactors

.,\\. *: ';

\\

/

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