ML19317G761

Forwards Questionnaires Re Steam Generator Operating History.Changes or Additions to Initial Submittal That Reflect Future Operating Experiences Should Be Submitted.Addressed to All PWR Licensees

ML19317G761
Person / Time
Site:	Indian Point, Arkansas Nuclear, Rancho Seco
Issue date:	12/09/1977
From:	Goller K Office of Nuclear Reactor Regulation
To:	ARKANSAS POWER & LIGHT CO., CONSOLIDATED EDISON CO. OF NEW YORK, INC., SACRAMENTO MUNICIPAL UTILITY DISTRICT
Shared Package
ML19317G744	List: ML19317G743 ML19317G761
References
GL-77-6, NUDOCS 8004010589
Download: ML19317G761 (12)

Text

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION y

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December 9, 1977 E

TO ALL PWR FACILITY LICENSEES b

Gentlemen:

E' The NRC staff has recently been engaged in a series of discussions with I

reactor vendors, EPRI, and the Steam Generator Owners Groups concerning i

steam generator operational problems. Central to these discussions is an accurate assessment of operational conditions and experiences as well as the programs aimed towards the resolution of these problems.

.. q.2 In order to ensure that both the NRC and the nuclear industry have available a comprehensive collection. of operating data for steam gener-ators to permit infomed, timely decisions and actions, D0R is establishing a steam generator information system.

The system

~ ~ ~ ~ ~ -

will collect appropriate information from all PWR licensees which will periodically be published.

It is presently anticipated that

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the initial publication of infomation will be in the early part of 1978.

You will be sent a copy of this and all future publications.

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This information system will enable the NRC and each Licensee to draw from the operational experiences-of the entire nuclear industry

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when making any cecisions concerning steam generators. This should 2

result in both safety and economic benefits.

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Enclosed is a questionnaire which we request that you complete for

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each of your operating PUR units. We believe that the questionnaire 55i is self explanatory, however, if questions arise or any clarifica-tions are necessary, please do not hesitate to contact your NRC fl Project lianager. Please include with your response any diagrams you may ',ove available which illustrate the tube plugging and/or

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the tube degradation patterns.

To enable us to maintain the information current, you are further requested to suboit in the same format indicated by the question-nair -

any changes or additions to your initial submittal to reflect p $5+

i the..ture operating experience with your steam generators, i.e., the results of future steam generator inspections. The questionnaire E ~~

should be completed to the extent applicable and appropriate at

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this time, i.e. regardless of operating experience.

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The information being requested is quite extensive and will require'

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a diligent effort on your part and ours to assure accurate and timely

[=E completion.

Also, we realize that parts of the infomation may already

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be available to the NRC, but not in a convenient format which is readily accessible. Therefore,'we request that you assist us by-

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returning a single completed copy of the. enclosed questionnaire to EP-the Director of Nuclear Reactor Regulation, U. S. Nuclear Regulatory Commission, Washington, D. C.

20555, within 60 days of receipt of this letter. Please include any comments or suggestions for improving this

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fnformation system which you may have.

.m This request for generic information was approved by GA0 under a blanket

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clearance number R0071; this clearance expires Septembe,r 30, 1978.

Sincerely, kh

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"22E Karl R. Goller, Assistant Director

.for Operating Reactors

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Division of Operating Reactors

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Enclosure:

Steam Generator

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Operating History

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Questionnaire cc w/ enclosure:

See next page

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ENCLOSURE

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STEAM GENERATOR OPERATING HISTORY QUESTIONNAIRE

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NOTE: All percentages should be reported to four significant. figures.

I.

BASIC PLANT INFORMATION

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Plant:

Startup Date:

1

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Utility:

s =5:s Plant Location:

hfNf Thermal Power Leyel:

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Nuclear Steam Supply System (NSSS) Supplier:

Number of Loops:

Steam Generator Supplier, Model No. and Type:

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Number of Tubes Per Generator:

Tube Size and Material:

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II. STEAM GENERATOR OPERATING CONDITIONS

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Nomal Operation

......:.xx n.

Temperature:

Flow Rate:

Allowable Leakage Rate:

Primary Pressure:

Secondary Pressure:

Accidents Design Base LOCA Max. Delta-P:

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

III. STEAM GENERATOR SUPPORT PLATE INFORMATION j

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Material:

i Design Type:

Design Code:

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Dimensions:

i Flow Rate:

Tube Hole Dimensions:

Flow Hole Dimensions:

- - = =

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L.

> (2 2-IV.

STEAM GENERATOR BLOWDOWN INFORMATION

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Frequency of Blowdown: '

Normal Blowdown Rate Blowdown Rate w/ Condenser Leakage:

.

Chemical Analysis Results

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Results rarameter Control Limits

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V.

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

E Typical Chemistry or Impurity Limits:

Z. 9 Feedwater_

Typical Chemistry or Impurity Limits:

te Condenser Cooling Water Typical Chemistry or Impurity Limits:

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E Demineralizers - Type:

Cooling Tower (open cycle,closedcycleornone):

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3-VI. TURBINESTOPVALVETESTING(applicabletoBabcock&Wilcox(B&W)5.G.only)

==t Frequency of Testing Actual:

Manufacturer Recomendation:

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Power Level At Which Testing Is Conducted e:..

Actual:

Manufacturer Recomendation:

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

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Actual:

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Manufacturer Recommendation:

VII. STEAM GENERATOR IUBE DEGRADATION HISTORY (The following is to be repeated for each scheduled ISI) l Inservice Inspection (ISI) Date:

7:

Number of EFP Days of Operation Since Last Inspection:

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

Steam Generator Number:

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Percentage of Tubes Inspected At This ISI:

Percentage of Tubes Inspected At This ISI That Had Been Inspected At

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The Previous Scheduled ISI:

Percentage of Tubes Plugged Prior to This ISI:

Percentage of Tubes Plugged At This ISI:

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Percentage of Tubes Plugged That Did Not Exceed Degradation Limits:

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Percentage of Tubes P'.ugged As A Result of Exceedance.of Degradation i~~~~~

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Limits:

t..:.._. _

Sludge Layer Material Chemical Analysis Results:

Sludge Lancing (date):

Ave. Height of Sludge Before Lancing:

Ave. Height of Sludge After Lancing:

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=:4 Replacement, Retubing or Other Remedial Action Considered: (Briefly Z:

SpecifyDetails)

Support Plate Hourglassing:

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Support Plate Islanding:

g.;

Tube Metalurgical Exam Results:

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Fretting or Vibration in U-Bend Area (not applicable to B&W S.G.) AS OF 141 Percentage of Tubes Plugged Other Preventive Measures

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Wastage /CavitationErosionASOFJ41

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Hoteleg:

(Repeat this information for the cold leg on Combustion Engir. sering (C.E.) and Westinghouse (W) S.G.)

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Area of Tube Bundle (1) a b

c d

e

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% of Tubes Affected by

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Wastage / Cavitation Erosion

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% of Tubes Plugged Due to

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Exceedance of Allowable

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Limit (2)

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% of Tubes Plugged That

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,Elll Limit g,}.

Location Above Tube Max. Wastage / Cavitation Erosion mu.;;~.l:

Rate for Any Single Tube

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(Tube Circum. Ave) (Mills / Month)

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Max. Wastage / Cavitation Erosion in Any Single Unplugged Tube e:: =

(Tube Circum. Ave) (Mills)-

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$.5 ff

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Crackin9ASOF,(_41 4

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

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

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Wt Leg:

taepeat this information for the cold leg on C.E. and E S.G.)

II)

Area of Tube Bundle a

b c

d e

% 'of Tubes Affected By Cracking

% of Tubes Plugged Due to Cracking

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% of Tubes Plugged That Did Not Exceed Degradation Limit p==E:

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Location Above (3)

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Tube Sheet

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Rate of Leakage From.

Leaking Cracks (gpm)

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Denting (Not applicable '.o B&W S.G.) AS OF (4) y===.:

Hot Leg:

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

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Area of Tube Bundle (1) a b

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II.)

% of Tubes Affected by Denting

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% of Tubes Plugged Due to

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Limit (2)

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% of Tubes Plugged That Did Not Exceed Degradation L_~~~

Limit Rate of' Leakage From Leaking Dents (gpm) g;;;

Max. Denting Rate for Any iE Single Tube (Tube Circum. Ave) (Mills / Month) ggg;=

Max. Denting in Any Single Unplugged Tube (Tube i

Circum. Ave) (Mills)* '

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Denting (Con't) 5 Support Max. Denting in Any Single

% of Tubes Affected By 2

Plate Tube in Bundle Area Denting in Bundle Levels (TubeAve)(Mills)(1)

Area

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NOTE: All percentages refer to the perce~nt of.the tubes within a given

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area of the~ tube bundle.

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(1)

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

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a.

Periphery of Bundle (wi/20 rows for B&W; w

wi/10 rows for C.E. and W)

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b.

Patch Plate (wi/4 rows) c.

MissingTubeLane(B&Wonly)

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(wi/5 rows)

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Flow Slot Areas (C.E. and W only)

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wi/10 rows) d.

Wedge Regions (C.E. and W only)

(wi/8 rows) e.

Interior of Bundle (remainderoftubes) i=9.gg.g (2)

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Allowable Limit for Wastage / Cavitation Erosion:

Allowable Limit For Denting:

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(3) 1.

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:

F (4)

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

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i= m VIII. SIGNIFICANT STEAM GENERATOR ABN0EMAL OPERATIONAL EVENTS ji===_

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SUMMARY

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(Include event description; unscheduled ISI results, if

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performed; and subsequent remedial actions)

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IX. CONDENSER INFORMATION ls;.

Condenser Tube Leakage Detectable Detection

== E Material Date Rate (gpm)

Limit Method

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X.

RADIATION EXPOSURE HISTORY WITH RESPECT TO STEAM GENERATORS e

Date ExamDosage(Man-Rem)

Repair Dosage (Man-Rem)

Comments

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k XI. DEGRADATION HISTORY FOR EACH TYPE OF DEGRADATION EXPERIENCED FOR TEN REPRESENTATIVE, UNPLUGGED TUBES FOR WHICH THE RESULTS OF TWO OR MORE E"

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ISI'S ARE AVAILABLE

.:. I If the results for ten tubes are not available, specify this infor-O[.-

mation for all those tubes for which results are available.

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

Steam Generator No:

EM= =s Tube Identification:

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Type of Degradation:

(specify denting, wastage, cavitation erosion, F

caustic stress corrosion cracking, or flow s

induced vibration cracking)

==== g (repeat the following information chronologically for each IS'I for which re',ults are available)

II ISI Date:

tenount of Degradation:

(specify amount and units) 3 EFP Months of Operation Since Last ISI for Which Results are Given:

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UNITED STATES I

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NUCLEA8. RESULATORY COesset00404 WWMTON, O. C.

M POSTAe8 ANO PSSS PAIS i;;.2.u;2 i

voetso states avcasse OPPICI AL Sullmang essw6ateay consenessioes PEN ALTY POR PAIVATE t#SE. 4309

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Sacras.:ntoLitunicipal. Utility District 3.

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General Counsel:

6231 S Street 1

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Post Office Box 15830

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Sacrcnento, California - 95813

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- Business and flunicipal Departnent

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'Sacramsnto City-County. Library 828 I' Street

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- Sacrament'o, California 95814

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