ML19326A260
| ML19326A260 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/09/1977 |
| From: | Goller K Office of Nuclear Reactor Regulation |
| To: | TOLEDO EDISON CO. |
| Shared Package | |
| ML19326A259 | List: |
| References | |
| NUDOCS 8002030122 | |
| Download: ML19326A260 (11) | |
Text
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,8 UNITEo ST ATES y
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I WASHING TON. D. C. 20555
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December 9, 1977
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i TO ALL PWR FACILITY LICENSEES Gentlemen:
The NRC staff has recently been engaged in a series of discussions with reactor vendors, EPRI, and the Steam Generator Owners Groups concerning 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.
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 informed, timely decisions and actions, 00R is establishing a steam generator information system.
The system will collect appropriate information from all PWR licensees which g
will periodically be published.
It is prasently anticipated that the initial publication of information will be in the early part of 1978. You will be sent a copy of this and all future publications.
This information system will enable the NRC and each Licensee to draw from the nperational experiences of the entire nuclear industry when making any oecisions concerning steam generators. This should result in both safety and economic benefits.
Enclosed is a questionnaire which we request that you complete for each of your operating PUR units. We believe that the ouestionnaire is self explanatory, however, if questions arise or any clarifica-tions are necessary, please do not hesitate to contact your NRC Projectflanager. Please include with your response doy atacrans you may have available which illustrite the tube plugging and/or the tube degradatinn patterns.
To enable us to maintain the information current, you are further requested to subilit in the same format indicated by the question-naire, any changes or additions to your initial submittal to reflect the future operating experience with your stean generators, i.e., the results of future steam generator inspections.
The questionnaire should be completed to the extent ap,il Rable and appropriate at this time, i.e. regardless of operating experience.
O 8 0 0 2 0 3 0lM-s
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2-O The information being requested is quite extensive and will require
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a diligent ef fort on your part and 'o~urs to assure accurate and timely completion. Also, we realize that parts of the '1 formation may already be available to the NRC, but not in a convenient rormat which is readily accessible. Therefore, we request that you assist us by returning a single completed copy of the enclosed questionnaire to 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 information system which you may have.
This request for generic information was approved by GAO under s bleket clearance number R0071; this clearance expires Septemoer 30, 1978.
Sincerely, k h4 Karl R. Goller, Assistant Director for Operating Reactors Division of Operating Reactors C
Enclosure:
Steam Generator Operating History Questionnaire cc w/ enclosure:
See next page
. ~ ~ - ~ ~
U ENCLOSURE 1 STEAM GENERATOR OPERATING HISTORY QUESTIONNAIRE NOTE: All percentages should be reported to four significant figures.
I.
BASIC PLANT INFORMATION Plant:
Startup Date:
Utility:
Plant Location:
Thermal Power Level:
Nuclear Steam Supply System (NSSS) Supplier:
Number of Loops:
()
Steam Generator Supplier, Model No. and Type:
Number of Tubes Per Generator:
Tube Size and Material:
II. STEAM GENERATOR OPERATING CONDITIONS Normal Operation Temperature:
Flow Rate:
Allowable Leakage Rate:
Primary Pressure:
Secondary Pressure:
Accidents Design Base LOCA Max. Delta-P:
Main Steam Line Break (ftSLB) Max. Delta-P:
III. STEAM GENERATOR SUPPORT PLATE INFORMATION Material:
Design Type:
Design Code:
(b)
Dimensions:
i Flow Rate:
Tube Hole Dimensions:
i Flow Hole Dimensions:
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IV. STEAM GENERATOR BLOWDOWN INFORMATION Frequency of Blowdown:
Normal Blowdown Rate:
Blowdown Rate w/ Condenser Leakage:
Chemical Analysis Results Results Parameter Control Limits V.
WATER CHEMISTRY INFORMATION Q
Secondary Water Type of Treatment and Effective Full Power (EFP) Months of Operation:
Typical Chemistry or Impurity Limits:
Feedwater Typical Chemistry or Impurity Limits:
Condenser Cooling Water Typical Chemistry or Impurity Limits:
Demineralizers - Type:
Cooling Tower (open cycle, closed cycle or none):
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VI. TURB!NE STOP VALVE TESTING (applicable to Babcock & Wilcox (B&W) 5.G. only)
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 GENERATOR TUBE DEGRADATION HISTORY (The following is to be repeated for each scheduled ISI)
Inservice Inspection (ISI) Date:
Number of EFP Days of Operation Since Last Inspection:
O (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 Af ter Lancing:
Replacement, Retubing or Other Remedial Action Considered: (Briefly Specify Details)
J()
Support Plate Hourglassing:
Support Plate Islanding:
Tube Metalurgical Exam Results:
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Frutting or Vibration in U-Bend Area (not applicable to B&W S.G.) AS OF (4)
Percentage of Tubes Plugged Other Preventive Measures Wastace/ Cavitation Erosion AS OF (4)
Hot Leg:
(Repest this informction for the cold leg on Combustion Engineering (C.E.) and llestinghouse (W) S.G.)
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Area of Tube Bundle (1) a b
c d
e
% of Tubes Affected by Wastage / Cavitation Erosion C
% of Tubes Plugged Due to Exceedance of Allowable Limit (2)
% of Tubes Plugged That Did not Exceed Degradation Limit Loration 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 Unplugged Tube (Tube Circum. Ave) (Mills)
Crackin9 AS OF B1 Caustic Stress Corrosion Induced in C.E. and W S.G.
Flow Induced Vibration Caused in B&W S.G.
C
n
. Cracking (Con't) rut teg:
(nepeat this information for the cold leg on C.E. and W S.G.)
III Area of Tube Bundle 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)
O Denting (Not applicable to B&W S.G.) AS OF (4)
Hot Leg:
(Repeat this infomation for the cold leg on C.E. and W 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)
O Max. Denting in Any Single Unplugged Tube (Tube Circum. Ave) (Mills)' -
W
,, o Denting (Con't)
Support Max. Denting in Any Single 7, of Tubes Affected By Plate Tube in Bundle Area Denting in Bundle Levels (TubeAve)(Mills)(1)
Area a
b c
d e
a b
c d
e 1-2 3
4 5
6 7
8 9
O 10 11 12 i
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TABLE KEY NOTE: All percentages refer to the perce'nt of the tubes within a given area of the tube bundle.
(1)
Area of the Tube Bundle No. of Tubes Within the Area a.
Periphery of Bundle (wi/20 rows for B&W; wi/10 rows for C.E. and W) 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) 0 wi/10 rows) d.
Wedge Regions (C.E. and W only)
(wi/8 rows) e.
Interior of Bundle (remainder of tubes)
(2)
Allowable Limit for Wastage / Cavitation Erosion:
Allowable Limit For Denting:
(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:
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(4)
Specify the date of the inspection for which results have been tabulated.
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.8-VIII. SIGNIFICANT STEAM GENERATOR ABNORMAL OPERATIONAL EVENTS DATE
SUMMARY
(Include event description; unscheauled ISI results, if performed; and subsequent remedial actions) i IX. CONDENSER INFORMATION Condenser l Tube Leakage Detectable Detection Material Date Rate (gpm)
Limit Method
(:)
X.
RADIATION EXPOSURE HISTORY WITH RESPECT TO STEAM GENERATORS bate Ex3m nosige (Han-Rem)
Repair Dosage (Man-Rem)I Comments C
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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'$ 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 infomation 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 infomation chronologically for each ISI for which results are available)
ISI Date:
C Amount of Degradation:
(specify amount and units)
EFP Months of Operation Since Last ISI for Which Results are Given:
C
.