ML19220C215
| ML19220C215 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/09/1977 |
| From: | Goller K Office of Nuclear Reactor Regulation |
| To: | METROPOLITAN EDISON CO. |
| Shared Package | |
| ML19220C209 | List: |
| References | |
| NUDOCS 7904300068 | |
| Download: ML19220C215 (12) | |
Text
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NUCLEAR AEGULATORY COMMISslCN i g rg.
i WASWNGTON. O C 20555
- f* 4-Q i e%
,p Dece ee-9, 1977
=...+
TO ALL PWR F ACILIT f LICENSEES Gentlemen:
The NRC staf f hn recently been engaged in a se-ies of discussions with reactor vendors. EFRI, and the Stean Generator Owners Groups concerning steam necerator coerational problems.
Central to inese discussions is an accurate assessnent of operational conditions and exoeriences as well as the programs aimed towaros the resolution of these proolems.
In ceder to ensure that both tne NRC and tne nuclear industry have availaole a ccmprenensive collection of operating data for st'am gener-ators to pertiit informed, timely decisiuns ano actions, CCR is establisning a stean generator information system.
The system will collect 3::r:oriate information from all PWR licensees which Q
will periodically De 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 puDlications.
This information system will enable the NRC and each Licensee to draw f r0m the nreratienal experiences of the entire nuclear industry when making any cecisions concerning steam generators.
This snould resul t in Doth :af ety and economic benefi ts.
Enclosed is a cuestionnaire which we request that you completc for eac'i of your operating PWR units.
We believe t.*at t9e ouestionnaire is self explan3 tory, hcwever, if ouestions arlse cc any clarifica-tions are necessary, clease do not hesitate to contact your NRC Project Manager.
Please include witn your response -oy ciagrans you may have available which illustrite the tube plugginQ and/or the tube degrada tino patterns.
To enable us to maintain the information current, you are further recuested to suunit in the same format inoicated by the question-naire, any changes or additions to your initial suclittal to reflect the future operating experience wi tn your stean generators, i.e.,
the resul ts of future steam generator inspections.
The questionnaire should be co pleted to the extent awl n:able and approprist:: at this time, i.e. regardless of operating experience.
S o, c.:
9 7 g o 4 3 0 0 DM,
The infor?ation 0?ing requested is ouite extensive and will require a diligent ef fort on your :: art and ours to assure accurate and timely completion.
Also, -e realize that carts of tne information may already be available to tne NRC, but not in a convenient format wnich i s readily accessiole.
Therefore, we request that you assist us by returning a single ccmpleted copy of the enclosed cuestionnaire 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 incluoe any comments or suggestions for im;, roving this information systen which you may have.
This recuest i r generic information was approved by GAO under 3 bl a.1k e t clearance number RC071; this clearance expires Septemoer 30, 1978.
Sincerely, k $.4-M Karl R. Goller, Assi stant Director for Operating Reactors Division of Operating Reactors
Enclosure:
Steam Generator Operating Hi story Questionnaire cc w/ enclosure:
See next page a
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O O
EfiCLOSURE 1 STEAM GENEPATCR OPEDATING HISTORf O'JESTIONNAIRE NOTE: All percentages should be reported to four significant figures.
I.
BASIC PLANT IfiFOCNATICri Plant:
Startup Date:
Utility:
Plant Location:
Tharmal P0wer Level:
fluclear Steam Su:: ply System (N555) Supplier:
Narber of Loops:
0 Stea= Generator Smiier, Moeei No. ane Type:
Number of Tubes Per Generator:
Tube Size aad Material.
II. STEAM GENED.ATOR CrEDATING CONDITICNS Normal Coeration Teiperature:
Flew Rate:
Allowable Leakage Rate:
Primary Pressure:
Secondary Pressure:
Accidents Design Base LOCA Max. Delta-P:
Main Steam Line Break (fiSLB) Max. Delta-P:
III.
STEAM GENERATOR SUPPORT PLATE INFORPATICri Material:
Design Tjpe:
Design Code:
h Dimensions:
Flow Rate:
Tube Hole Dimensions:
8O c,7 n 7
Flow Hole Dirrensions :
9 fi 2
IV.
STEM GENEF ATCR BLcw:%'i INFORMAi!CN
~
Frequency of B'cador:
Nomal Blc-dca R3te:
a Blewdown Rate w/:orde ser Leakage:
Chemical Analysis Results Results Parameter Control Limits V.
KATER CHEMISTRY { NECRl'AT ] CN Secondary Water Type of Treatment and Effective Full Power (EFP) Months of Operation:
Typical Cnemistry or impurity Limits:
Feedwater Typical Che-istry or Impurity Limits:
Ccndenser Cooling Water Typical Chemistry er Impurity Limits:
Demineralizers - Type:
Cooling Tcwer (Ocea cycle, closed cycle or none):
'(
i f) 1
()
/ <_. J
3 VI.
TUPSINE STOP '/ALVE TESTING (applicable to Babcock & Wilcox (S&'d) 5.G. only)
Frecuency of Testini Actual:
Manufacturer Rec cTe nd a ti on :
Po,er Level At anich Testing is Conducted Actual:
Manuf acturer Recomendation:
Testing Procedures _(Stroke length, stroke rate, etc.)
Actual:
Manufacturer Recom endation:
VII. STERI GENEUTOR IUEE DEGPiDATION HISTORY (ibe follo.,ing is to be repeated for eacn scheduled ISI)
Inservice ins::ection (ISI) Date:
flumber of ~rP Crys of Operation Since Last Inspection:
O (The following is to be repeated for each steam generator)
Steam Gene nt:r Nu-ber:
Percentage cf Tubes Inspected At This ISI:
Percentage or Tubes Inspected At This 15I That Had Been Inspected At The Previous Scheduled ISI:
Fercentage or Tutes Plugged Prior to This ISI:
Percentage of Tubes Plugged At Th.is ISI:
Fercentage of Tubes Plugged That Did Not Exceed Degradation Limits:
Fercentage of Tubes Plugged As A Result of Exceedance of Cegradation Limits:
Sludge Layer 'hterial Chemical Analysis Results:
Sludge Lancing (date):
Ave. Heignt of Sludge Before Lancing:
Ave. Height of Sludge After Lancing:
Replacement, Retubing or Other Remedial Action Considered: (Sriefly Specify 0? tails)
Q Support Plate Hourglassing:
Support Plate Islanding:
sube Metalurgical Exam Results:
N, C
,)
c, e...
O O
cJ; s
4 Fretting er Vibration ir U-Bend Area (not apolicable to SL 5.G.) AS Of (?)
Percentage of Tubes Plugged Other Pre <entive Measures Wastace/ Cavitation Erosien A5 0F (a)
Hot Lec:
(Re: eat this infor ation for tne cold leg on Cocustion Engineering (C.E. ) and Wes tingneuse (E) 5.G. )
ld le j
Area of Tube Bundle (1) 7 b
c i of Tubes Affected by Wastage / Cavitation Erosion
(
% of Tubes Plugged Oue to I,
Exceedance of Allowable l
Limit (2)
% of Tubes Plu:ged Tnat Did not Exceed Decrvetion Lit.ii t
_L Location Above Tube l
Sheet (3) i I
Max. Wastage /Cavitati:n Erosier.
Rate for Any Single Tuce (Tube Circum. Ave) (Mills /Menth)
Max. Wastage /Cavitatien Eresien in Any Single Unplucged Tube (Tube Circur. Ave) (Mills)
Cracking A5 0F (41 Caustic Stress Corrosion Induced in C.E. and W 5.G.
Ficw Induced Vibration Caused in B&W 5.G.
Ob..
b, Cracking (Co,'t) veceat this information for the cold leg on C.E. and E 5.G.)
P5 Lee:
I)
Area cf Tube Bundle a
b cld l el
% of Tubes Affected By C.ackin; I of Tubes Plugged Due to Crackin;
% of Tubes Plugged That Did Not Exceec Degracation Limit I
location Above rq i
Tube Sheet l
'~
Rate of Leakage Frem Leaking Cracks (gem)
O Denting (Not apolicable to B&W 5.G.) A5 0F (4)
Hot Leg:
(Repeat this information for the cold leg on C.E. anc E 5.G.)
Area of Tube Esndle (1) a b
c d
e
% of Tubes Affected by Denting i
% of Tubes Plugged Due to Exceedance of Alloaable Limit (2)
% of Tubes Plugged That Did Not Exr.eed Degradation Limit Rate of Leakace From Leaking Cents (g;:m) l Max. Denting Rate for Any Single Tuoe (Tube Circum. Ave) (Mills /Montn)
O Max. Dentine in Any Single Unplugged' Tube (Tube Circum. Ave) (flills)
O?t
,I
() U L. t J
9 O
O.
Denting (Con't1 5=:cr:
M31 cer. ting in any single
- , er Tube
- Affec ec Ej Plate Tute in Euadle Are3 Denting in Bundle Levels (Tube A.e) (ftilis) (1)
Area a
b c
d e
a b
c d
e 1
2_
l l
l l
l 3
I I
I I
I I
I 4
I I
I I
I I
I 5
I_
I I
I I
I 7
I I
i i
i I
s I
I l
l l
l I
I I
I I
(,'
9-10 I
I I
I i
I I
i 11 I
12 I
I I
I l
l l
co w:
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C TABLE XEY
!{0TE:
All percentages refer to the per:ent of the tuces within a given area of the tube bundle.
.1 )
Arei of the Tube Sundle No. of Tuces Within the Area a.
Peripnery of Bundle (wi/E0 rows for BiW; wi/10 rews 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) hj-wi/10 rows) d.
Wedge P.egions (C.E. and W only)
(wi/S rc,.s)
~
e.
Interior o' Sundle (remaincar of tubes)
(2)
Allowable Limit fer Wastege/ 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 /Cavi tation Erosion:
Cracking:
O (4)
Spe:ify the date of the inspection for which results have been tabulated.
3 I
UU
(. t._ J
9 9
(i) 8-Vill.
SIGNIFICANT STEAM GENERATOR ABNCREAL CPERATIONAL EVENTS DATE S n'RY finclude event description; unscheduled 15I re:ults, if e
~*rret; and subsequent remedial acticns)
I IX. CONDENSF, !NFCP1.si l.a Condense' i luce Leakage Detectable Detec:icn Mate.-ial Date Rate (gpm)
Limit Method C
X.
RADIATION EXF05URE HISTORY WITH RESPECT TO STEAM GENERATORS Date Exam Desage (Man-Rem)
Repair Desage (Man-Rem) ' Comments l
-c I
d O
$LU
.g.
XI. DEGRACATION FI57CP.Y FCR EACH TYPE OF DEGRACATICN EXPERIENCED FOR TEN REFRESENTATIVE, UNPL'JGGED TU5ES FOR WHICH THE RESULTS OF TWO OR MORE 151'S ARE AVAILACLE If the results f or ten tubes are not available, specify this infor-mation fc-all those tubes for which results are availaole.
(repeat the follcwing information for each tube and degradation type)
Steam Generator No:
Tube Identification:
Type of Cegradaticn:
(specify denting, wastage, cavitation erosicn, caustic stress corrosien cracking, or ' low induced vibratien cracking)
(re; eat tne felic.ing inferr.ation chronologically for each 151 for which reLults 3"e availabit ISI Date:
Cs Amount of Degracation:
(specify amcunt and units)
EFF Months of Operation Since Last ISI for Which Results are Given:
()
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,7 DD Lt-o
HFg o 1 1978 S$4trtoutiqn w/ enclosure
' @g_k e t F i l e L'aR 44 Fi W NRC PDR Local PDR M. Service H. Silver ELD Attorney I&E (3) w/o enclosure:
R. Boyd R. DeYoung D. Vassallo F. 'nilliams H. Smith K. Goller D. Eisennut bcc: NSIC TIC ACRS (16) f\\
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