ML19030A737

Response to Request, Submit Completed Steam Generator Operating History Questionnaire for Salem No. 1

ML19030A737
Person / Time
Site:	Salem
Issue date:	01/30/1978
From:	Librizzi F Public Service Electric & Gas Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML19030A737 (10)

Text

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PS~G January 30, 1978 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Gentlemen:

STEAM GENERATOR QUESTIONNAIRE SALEM GENERATING STATION UNIT NO.

1 DOCKET NO. 50-272 In response to your request of December 9, 1977, we submit the attached completed questionnaire.

It should be noted that Salem Unit No. 1 is not scheduled to perform its first Inservice Inspection until January 1979, and therefore ~ome of the infor-mation requested is not yet available.

The Energy People Very truly yours,

-~

F. P. Li~

General Manager -

Electric Production II fJl'f I 95-2001 (400M) 9-77

L ENCLOSURE. 1 STEAM GENERATOR OPE~TING HISTORY QUESTIONNAIRE NOTE:

All percentages should be reported to four significant figures.

I. BASIC PLANT INFORMATION Plant: Salem No. 1 Startup Date: 11 December 1976 (initial criticallity)

Utility: Public Service Electric & Gas Company Plant Location:. Hancocks Bridge, New Jersey Therma 1 Power Leve 1 :

3 3 3 8 MWt Nuclear Steam Supply System (NSSS) Supplier: Westinghouse Number of Loops:

Four Steam Generator Supplier, Model No. and Type:

West./Series: 51 Number of Tubes Per Generator: 3388 Tube Size and Material: 0.875"0D,0.050"Wall II.

STEAM GENERATOR OPERATING CONDITIONS Normal Operation Incone1* *

• ~

~**.

Temperature: 547 -

576.35°F Flow Rate: 67,000 GPM Allowable Leakage Rate: l GPM al3=- SG' s, Primary Pressure: 2235 psig Secondary Pressure:. 805 psia (full power)

Accidents Design Base LOCA Max. Delta-P: 1000 psia Main Steam Line Break (MSLB) Max. Delta-P: Unknown III.

STEAM GENERATOR SUPPORT PLATE INFORMATION Materi a 1:

Design Type:

UNKNOWN AT THIS TIME Design Code:

• 500 GPn*any one SG.

Dimensions:

REQUEST HAS BEEN MADE TO WESTINGHOUSE FOR INFORMATION Flow Rate:

Tube Hole Dimensions:

Flow Hole Dimensions:

. :*.. IV.

STEA/'1 GENERATOR SLOWDOWN INFORMATION Frequency of Bl owdown: Continuous Nonnal Slowdown Rate: "20,000 to 25,000 lbs/hr.

Slowdown Rate w/Condenser Leakage: 32;000 lbs/hr. (max.)

C~emical Analysis Results Results Parameter Control Limits Cat. Cond.

1.3 Steady State ~ 2. 0 umhos/cm2 @25

• Transient

~ 7. 0 II II pH @25 OC 8.7 8.5 - 10.0 Free OH 0.10

• • ~ 1. 0 ppm CaC03 OC

• May be increased to 15.0 for the first 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during startup for HOT HUTDOWN

• • May be increase if the sodium level is 0.460 ppm as sodium V.

WATER CHEMISTRY INFORMATION Secondary Water Type of Treatment and Effective *Full Power (EFP) Months of Operation:

AVT : 5.4 Typical Chemistry or Impurity Limits:

In line instrumentation Feedwater Typical Chemistry or Impurity Limits:

Na 1.0 Cat. Cond.

Sp. Cond.

• pH Condenser Cooling WaterN2H4

• oos > 02

°2 Sp. Cona.

ppb 0.2umhos

4. ownhos:*

9.1 0.006 4.0umhos Limits

( 0. 5)

(0.5)

( 3-6)

(8.8-9.2)

(<0.005)

( < 4. O)

Typical Chemistry or Impurity Limits:Brackish Water (Na,Cl,Mg,Ca)

Demineralizers - Type:

N.A.

Cooling Tower (open cycle, closed cycle or none):

N.A

• VI.

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

Frequency of Testing Actual:

Manufacturer Reconmendation:

Power Level At Which Testing Is Conducted Actual:

Manufacturer Recommendation:

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

Actual:

Manufacturer Recommendation:

VII.

STEAM GENERATOR TUBE DEGRADATION HISTORY Not Applicable (The following is to be repeated for each scheduled ISI)

Inservice Inspection (ISI) Date: January, 1979 is the first scheduled ISI Inspection Number of EFP Days of Operation Since Last Inspection:

(The following is to be repeated for each steam generator)

Steam Generator Number:

Percentage of Tubes Inspected At This ISI:

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

Percentage of Tubes Plugged Prior to This ISI:

Percentage of Tubes Plugged At This ISI:

Percentage of Tubes Plugged That Did Not Exceed Degradation Limits:

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

Sludge Layer Material Chemical Analysis Results:

Sludge Lancing (date):

Ave. Height of Sludge Before Lancing:

Ave. Height of Sludge After Lancing:

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

Support Plate Hourglassing:

Support Plate Islanding:

Tube Metalurgical Exam Results:

Fretting or Vibration in LI-Bend Area (not applicable to B&W S.G.) AS OF 1il_

Percentage of Tubes Plugged Other Preventive Measures Wastage/Cavitation Erosion AS OF J..!L Hot.. Leg:

{Repeat this information for the cold leg -on Combustion Engineering (C.E.) and Westinghouse (~J S.G.)

Area of Tube Bundle (1)

I.

?..

b c

% of Tubes Affected by I

Wastage/Cavitation Erosion

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

% of Tubes Plugged That Did not Exceed Degradation Limit Location Above Tube Sheet (3)

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

Max. Wastage/Cavitation Erosion in Any Single Unplu{ged Tube (Tube Circum. Ave)

Mill~-

Cracking AS OF 1il_

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

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

d e

Cracking {Con 1 t)

Fm! Leg:

\\Kepeat this infonnation for the cold l~g on C.E. and !i S.G.J Area of Tube Bundle l

( )

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)

Denting (Not applicable to B&W S.G.) AS OF (4)

Hot Leg:

(Repeat this infonnation for the cold leg on C.E. and!!. S.G.)

Area of Tube Bundle (1) a b

c d

e

% 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 Ci rcum. Ave) (Mi 11 s) *... *1 Denting (Con 't)

Support Plate Levels l

2 3

4 5

6 7

8 9

10 11 12 A

S.

l Max. Dent1 ng in ny ing e Tube in Bundle Area (Tube Ave) (Mills} {l}

a b

c d

e

% of Tubes Aff ecte d B y Denting in Bundle Area a

b c

d e

.. TABLE KEY NOTE:

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

( l)

Area of the Tube Bundle No. of Tubes Within the Area

a. Periphery of Bundle (wi/20rows for B&W; wi/10 rows for C.E. and ~J

b. Patch Plate (wi/4 rows)

c. Missing Tube Lane (B&W only)

(wi /5 rows) *

c.

Flow Slot Areas (C.E. and W only) wi/10 rows)

d.

Wedge Regions (C.E. and~ only)

(wi/8 rows)

e.

Interior of Bundle (remainder of tubes)

(2)

Allowable Limit for Wastage/Cavitation Erosion:

Allowable Limit For Denting:

(3)

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

2. Specifies*in the following locations: (list the additional locations)

Wastage/Cavitation Erosion:

Cracking:

( 4)

Specify the date of the inspection for which results.have been tabulated.

VIII. SIGNIFICANT STEAM GENERATOR ABNORMAL OPERATIONAL EVENTS DATE.

SUMMARY

Primary System has not been opened to date (Include event description; unscheduled 151 results, if perfonned; and subsequent remedial actions)

IX.

CONDENSER INFORMATrON Condenser I Tube Leakage Mate*rial Date Rate (gpm) 90 -

10 Copper Nicke.l.

• -Tube:s are pluggec subs1equent to any detetted.leakage Detectable Limit 2 umhbs Detection Method Cition Conductivity Indication &

Sodium Detectors X.

RADIATION EXPOSURE HISTORY WITH RESPECT TO STEAM GENERATORS Date Exam Dosage (Man-Rem).

Repair Dosage (Man-Rem)

Comments

.None to date i

i Il I I l

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t I

1

f. a '

~

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• .. XI.

DEGRADATION HISTORY FOR EACH TYPE OF DEGRADATION EXPERIENCED FOR TEN REPRESENTATIVE, UNPLUGGED TUBES FOR -WHICH THE RESULTS OF TWO OR MORE ISI 1 S ARE AVAILABLE If the results for ten tubes are not available, specify this infor-mation for all those tubes for which results are available.

(repeat the following infonnation for each tube and degradation type)

Steam Generator No:

Tube Identification:

Type of Degradation:

(specify denting, wastage, cavitation erosion, caustic stress corrosion cracking, or flow induced vibration cracking)

(repeat the following infonnation chronologically for each ISI for which rP~ults are available)

ISI Date:

Amount of Degradation:

(specify amount and units)

EFP Months of Operation Since Last ISi for Which Results are Given:

No ISI's have been performed to date.