Text

Provides Response to Request for Addl Info,Rev 0,-10CFR50.61 Screening Criterion,Re Summarized Results of Tests Performed on Weld Material from Retired Palisades Steam Generators
	ML18064A518
Person / Time
Site:	Palisades
Issue date:	12/14/1994
From:	Fenech R; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	TAC-M83227, NUDOCS 9412280097
	Download: ML18064A518 (82)
	v • d • e

-*-,

consumers Power*.

POWElllNli MIUllliAN'S PIUlliRESS Site Offices: 27780 Blue Star Memorial Highway, Covert Ml 49043 * (616) 764-8913, Ext 0210 December 14, 1994 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT Robert A Fenech Vice President Nuclear Operations RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION, REVISION 0 - 10CFR50.61 SCREENING CRITERION (RE: TAC NO. M83227)

Consumers Power Company (CPC) letters submitted November 8, 10 and 18 provided information that summarized the results of tests performed on weld material from the retired Palisades steam generato~s. In our November 18,1994 letter, we al~o committed to submit, before March 1, 1995, a site specific surveillance plan for staff approval.

For the integrated portion of this plan that involves use of credible data from other plant~, we have accelerated our schedule to now have an integrated surveillance plan, which addresses the He~t No. W5214 weld material, submitted by the end of January 1995. Credible W5214 weld material data exists for Indian Point 2, Indian Point 3, and HB Robinson 2.

The submittal will address the credibility of W5214 data from these plants for use by Palisades.

Use of credible surveillance data can provide extra operating margin to the PTS screening criteri.a limit due to a reduced Margin Term as defined in Position 2.1 of Regulatory Guide 1.99 Revision 2.

The tests on weld material from our retired steams generators were initiated and performed by CPC to increase the size of, and thus increase the accuracy of, the industry database for weld material fabricated using weld wire from Heat Nos.

W5214 and 348009.

Additionally, since this material is in both the retired Palisades steam generators and the active Palisades reactor vessel, the tests were initiated to determine if material from the retired steam generators is suitable for use in a supplemental surveillance program as a surrogate for reactor vessel material. This test program is ongoing.

An NRC Request for Additional Information (RAI) dated November 30, 1994 requested six items of additional information to enable the staff to complete their review on this subject. It requested that data be submitted within 10 working days and analyses be submitted by January 3, 1994.

The information requested by the

.l ----------------*----

---1-.Jll-

- r--*-

9412280097 941214

~~R ADOCK 0500~5~5 ;

.,i

~~*

~- 1--,--

--*- -+-- -. 0 I

i A CMS' ENERGY COMPANY

.e 2

November 30, 1994 RAI was further clarified during a telephone discussion with the staff on December 6, 1994. As a result of that discussion we are including, as Attachment 7 to this submittal, our preliminary plans for further testing of weld material from*our retired steam generators.

This Revision 0 of our response contains all the data requested and provides some analysis results. Future revisions of this letter will complete our response by January 3, 1995.

lhe following are the six items of information requested and our response to each.

NRC RAI Item No. 1 "Provide the actual time (above 500°F}, temperatures, and cooling method for stress relief of the Palisades reactor vessel ax-ial beltline welds and the Palisades steam generators.

Assess the potential effects.any difference in the heat trea_tment could have on the unirradiated reference temperature of the steam generator and the reactor vessel beltline welds."

CPC Response In order to determine the time at temperature for each component during the interstage and final Post Weld Heat Treatment (PWHT)~ ABB has reviewed the furnace logs and thermocouple strip charts to determine the data requested.

This is shown. in Attachment 1.

Differences in the heat treatment on the unirrad~ated reference temperature of the steam generator and. reactor vessel beltline welds have not been determined to have any effects.

Further work with AEA may better assess whether differences in the heat treatment had any effect on the steam generator material.

NRC RAI Item No. 2 "Compare the Charpy and drop weight data from the steam generators to the CE generic weld data base.. Provide any data that demonstrates the variability o.f the nil ductility transition temperature (NDTT} and.

unirradiated reference temperature in a weld or within a heat of weld wire."

CPC Response The Charpy and drop weight data from the steam generator weld samples have been compared to the CE generic weld data base (CEN-189 data). Available data that demonstrates typical variability of the drop weight nil-ductility transition temperature (NOTT) and the unirradiated reference temperature (RTNor) for a specific heat of weld wire are shown in the ABB Combustion Engineering Nuclear Operations (ABB CENO) response in Attachment 2.

ti 3

Further supporting information is provided in the All Consulting response in Attachment 2A.

In summary, when there are two test results. for a single wire heat, the NOTT and the RTNoT temperatures are found to vary l0°F* to 30°F between results. The differences in the initial RTNoTvalues between the Palisades

steam generator W5214 data and the earlier generic d~ta.base on similar welds may be considered to be within the normal range of variation for these types -0f materials. However, sufficient uncertainty exists relative to the condition of the steam generator W5214 material which prevents it from being considered as being specifically representative of the initial baseline propertiss of the reactor vessel weld seams.

In partic~lar, the measured initial RTNoT for the steam generator weld material was greater than two standard deviations from the genertc -56°F value.. The respo~se to Item No. 3 below will further support the fact the steam generator W5214 material varies significantly from the other W5214 Charpy data base.

Therefore, it is appropriate to contitiue to use the generic mean value of

-56°F for the reactor vessel W5214 welds.

NRC RAI Item No. 3 "Provide.a ri.gorous statistical evaluation bf steam generator Charpy.

data to determine whether the data is statistica77y equivaTent to the surve.i77ance data from (a)' the Indian Po,int-2 survei71arice weld,.(b) the Indian Poin.t-3 survei77ance weld, (c) the Robinson 2 surveillance weld, and (d) a77 three survei77ance welds."

CPC Response A preliminary evaluation is in process. Itwill be submitted by January 3, 1995.

NRC RAI Item No. 4 "P*rovide unaged and aged~Charpy-da'ta from the material therma77y aged in the Palisades reactor vessel. What is its percent copper, nickel and phosphorus?

.. Provide its neutron flux and f7uence, if its irradiation exceeded 1£16 n/cm2 (>JMeV).

Provide the time* and temperature history of the Palisades reactor vessel at *normal operating temperatures with the core critical,. Provide the operating

temperature and the tota.7 time at operating temperature for the welds in the steam generators."

CPC Response The unaged Charpy results for the material in the Palisades* ~urveillance program are listed in Tables 3 through 6 from "Final Report on Palisades Pressure Vessel Irradiation Surveillance Program: Unirradiated Mechanical Properties to Consumers Power", Perrin and Fromm, August 25, 1977. They are

4 included.i~ Attachment No. 4 to this submittal as Tables 4-1 through 4-4.

Aged Charpy results are described in Tables 5-2 through 5-9 from WCAP-1063.7., "Analysis of Capsules T-3.30 and W-290 from the Consumers Power Company Palisades Reactor Vessel Radiation Sur~eillance Program", Kunka and Cheney, September 1984. They are included in this submittal as Tables 4-5 through 4-12 in Attachment No. 4.

Figures 4-1 through 4-4 in Attachment No. 4 represent co~parison plots of the unaged and aged material properties using a *hyperbolic tangent curve fitting routine.

Copper, n i eke l and phosphorus measurements performed, on the Pa 1 i sades surv.eillance weld and plate materials are listed in Tables 4-13 and 4-14*in Attachment No. 4.

The thermal capsule dtd not have dosimetry: installed as part of the capsule, therefore there is no* measured flux or fluence of,the thermally aged material.

However, original design specifications for the thermal capsules calculated that the maximum acc.umul ated dose. would not exceed.

5.. 0 x 1013 (n/cm2 ) over 40 years *at the center of the capsule.

In-house

scoping confirm~ thi~ and shows that, for the time it resided in the v~ssel, the bottom portion rif the thermal capsule (weld material)

recei.ved an approximate accumulated fl uence of 4. O x 1016 (n/cm2 ) or less.. The heat affected zone (HAZ) m~~edal which was abp.ve the center of the capsule had an* approximate fl uence of 2. 0 x 1010 (n/cm2 ) or 1 ess...

The operating ti me and temperatures of t.he reactor ve.sse 1 and steam.

ge~erator welds are shown in Table 4-15 in.Attachment No. 4.

The total

time at operating temperature for the we*lds in the steam generators can

.~

be estimated as the hours criti~al plus a* small percentage of time tb covet hot shutdown conditions.

NRC RAI Item No. 5 "Provide* the approximate number of coils of.weld wire in*-heat W52l4~

Describe (.a) the weld samples that make up the W5214 percent copper data base, (b) the locations within the samples where the percent copper was measured, and (c) the number of copper-coated fi77er.

coils used in the fabrication of the weld.

Provide the measured

percent copper va1ues.from each sample and th.e average value from..

each sample.

Based on this information and data, provide your best-estimate value of the percent copper for the weld heat W5214 ~nd the basis for the value. Provide the best-estimate value of the percent phosphorus for welds fabricated with weld heat W5214."

CPC Response All the requested data is provided in Attachment 5.

Best estimate values will be provided in a subsequent revision.

.. ~'

NRC RAI Item No. 6

. "Perform a statistical evaJuation to determine if the copper values from the steam generator w~1ds are from the same population as the copper values from the other.W5214 welds.

Discuss t'he implications of the results of this analysis on your evall!ation o.f the* amount of copper in the*Palisades reactor vessel beltline.welds that were

.fabPi.cated using heat W5214 weld wire.

CPC Response 5

-Consumers Power Company is eval uat fng the data provided i.n Item No. 5 and*.

will provide a response. to this item when ou.r evaluation 1s* comp-lete.

~ -::

Attachments No.. 1 throug~ No. 6 contain tables, f.igures and explanatory data which support our responses to RAI Items No: l through No. 6 *. Attachment No. 7 provides a preliminary description of our plan to furtherevaluate the weld mate.rial from* o.ur retired steam* gen~rators. As we.committed in our*

- Novembe.r 18th *letter,_ th.at plan. will be.submitted before March 1,: 1995.

There *is no proprietary *infQrmation in this subm'ittal.

. Summary of C6mmitments

*There' are no new commitments in thi_s submittal.

Robert A. Fenech Vice President, Nucl~ar Operations_

CC.Admlni$t,rator, Region.,111, USNRC NRC Resident Inspector - Palisades.

Attachments 1;"j,

ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 RESPONSE TO NRC NOVEMBER 30,1994 REQUEST FOR ADDITIONAL INFORMATION REVISION 0 10CFR50.61 SCREENING CRITERION ITEM NO. 1 This attachment contains a summary sheet and data from three contracts.

Contract 2966 B-2 S.G. (7 Pages)

Contract 2966 B-1 S.G. (10 pages)

Contract 2966 A - R.V. (11 Pages)

ABB -

GENO RESPONSE A general description of the post weld heat treatment (PWHT) requirements for raising and lowering temperature of the components is provided below:

1)

When the weldment is placed in the furnace, the furnace temperature shall not exceed 600°F.

2)

At temperatures above 600°F, the maximum rat.eat which the temperature of the weldment may be raised shall be the lesser of 400°F per hour, or 400 divided by the maximum shell or head plate thickness in inches, but need not be less than 100°F per hour.

3)

During heating, the temperature difference between any two points on the part of the weldment being heated shall not exceed 250°F within any 15 ft. interval of length. During holding time, the maximum temperature difference between any two points shall not exceed 100°F in the portion of the vessel being heated.

4)

The maximum at which the temperature of the weldment is lowered shall be the lesser of 500°F per hour or 500 divided by the maximum shell or

. head thickness in inches, but need-not be less than 100°F per hour. The weldment may be removed from the furnace or local heating may be stopped when the maximum temperature of the weldment has fallen to 600°F. The cooling rate of P-7 materials will be in accordance with special procedures.

The actual time of temperature has been determined for the reactor vessel and each steam generator r

The temperature and duration was determined by reading actual thermocouple output strip charts. The information in the tables includes the heatup and cooldown cycle for each interstage and final PWHT of these components. A summary table has been compiled to identify the cumulative (interstage and final PWH'l) time at temperature for a component.

Post Weld Heat Treatment Times In order to determine the time at temperature for each component during the interstage and final Post Weld Heat Treatment (PWHT), ABB has reviewed the furnace logs and thermocouple strip charts to determine the data in the attached tables.

The time shown on the attached tables is greater than that reported on previous submittals. The reason for this is that the initial data reported was from the furnace inspection logs which report the "hold" time as required by the applicable weld procedure or M&P (Material & Process) Specification. The inspectors were trained to interpret the "hold" time on the furnace charts as that time during which all thermocouples for all component in the furnace were within the specified range (i.e. 1100°F-1150°F for 15 minutes). For this reason a thinner component, such as a steam generator shell, in a heat treat with a thicker reactor vessel shell would reach l l00°F-l 150°F first and would remain within that range longer waiting on the temperature of the thicker part to come within the required range. The revised tables reflect the time at temperature information for each component as determined by individual component thennocouple reading.

PALISADES HEAT TREAT

SUMMARY

SHEET c\\ Vi*_*

- __... _**.**---*--*_2

- _._9

__._6_.* __ 6_**._-._*_* __ *.**_*_B

__._._*_-_**-~-*--**_1_

.. _:_*-*-_**_s

___ *_*_*-*-*-*~--*-G

___._*_-.***-.*~-**_-**_*-_..* -_._*_*--*

>_._- /_._._.. -._-_-_... *.-*.***-**-2_*_>_9_*._**_-**_-_6_-_._6_:._:s

______ *_;~_s_*_*-*--*-**~--.--*~_-*_<_**-*.. *.. *-**

--- * *. *. T_-_--*-_.em_ p~r_ a_tu_ r_-.* _e_;_:

0

_**.* ~* *-.* **_-_.-_* ** *.*-.*_*.** *_-*_.** ** *_*.* *.*.* *** *_*_*_*i;...*_.*_**

__ -_._=._-.--.--.-.*.**=_.**_*_.*.-_.*_*_.. _.-"'""*H*_*_-=

... 0

__.* _+u*_*****

___ *r=_

. _._.--.-_s*

___

__.--*_.*.-**. *_ *.* +._._*_-_*.-. ~~""-""~4;;;;~~

<-* ~*

>++~~~----.;'"-=_,;;,.;;."'-Ii

.*..** : Minu*es... :: JJ:9µ~ >**** *-**_ *-.-*?****Mffiutes*******--.*

600-700 25 52 27 10 700-800 38 25 24 14 800-900 59 8

29 41 900-1000 31 54 33 1000-1100 37 2

25 8

1100-1175 24 35 16 28 1175-1200 37 600-700 14 25 700-800 15 40 800-900 22 20 900-1000 20 35 1000-1100 17 20 1100-1175 16 15 Temperature,°F _

600-700 15 25 700-800 18 55 800-900 29 0

900-1000 26 20 1000-1100 22 10 1100-1175 18 05 F:\\DATA\\RVI\\PALRVI\\2966Bl.SB

CONTRACT 2966 B-2 S.G.

Pg 1of7

- - .****COMPONENT Uppet Sh~UHead >.*.**.*. *. INT. x..*... *.. *.

- - ..

HEATTR.E.Aru;N";.;s9***.>* <<*****.. *

FINAi<* **

- *** *. n.Arn *. 4-.11~61 500-600 25 600-700 20 700-800 30 800-900 45 900-1000 55 1000-1100 2

5 1100-1175 2

25 1175-1200 1

1100-1000 1000-900 1

25 900-800 1

20 800-700 1

40 700-600 600-500 800-900 L/

.'fOTA[,*************************j 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 5 min.

900-1000

- .*.. * : T()TA.E *.*.*.*. *. **.*

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 20 min.

1000-1100

. TOTAL 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 5 min.

1100-1175

TOTAL

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 25 min.

MAXIMUM TEMPERATURE 1150 DEGREES F ARENHEIT

CONTRACT 2966 B-2 S.G.

Pg 2 of 7

.

COMPONENT Upper Shen/cone\\ :.... ** F*JN

.*.* IN.A.:

.... ***................. *.. x:

HEAT TREAT*# U-24<....... *.*

rtLI

'DATE 6-10~67 TEMP~RATmm.*... *** *.... **.*****.**** ***

Ji~~~

.*.. *.. /.* **:.... TIME~.

Minutes 500-600 30 600-700 35 700-800 35 800-900 40 900-1000 35 1000-1100 1

15 1100-1175 35 1175-1200 1100-1000 1

1000-900 1

15 900-800 1

40 800-700 1

50 700-600 2

40 600-500 800-900

. TQT:AL (

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 20 min.

900-1000 50 min.

1000-1100

> TOTAL:***}***..

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 15 min.

1100-1175 35 min.

MAXIMUM TEMPERATURE 1150 DEGREES FARENHEIT

CONTRACT 2966 B-2 S.G.

Pg 3 of 7 COMPONENT Up~er S~ell/Coli~<, ****FIN*****

....... JN

-'**.. :.L*.*

.. :***.*. X

- :..QJ:ti.\\] TR,E.AT lf:.. 0.,63 n:IJ

.. *.*.***..... /

. DATE ** 8-19'-61.

/ *. TEMPF-JiAilli.iE)***.*.. *****.*. *.** )..

1,Hour.: *..

.. -TIME;.:***.*****

Minutes**

500-600 40 600-700 35 700-800 50 800-900 1

900-1000 1

45 1000-1100 2

5 1100-1175 30 1175-1200 1100-1000 50 1000-900 1

20 900-800 1

40 800-700 2

5 700-600 2

30 600-500 3

15 800-900 40 min.

900-1000

{**********

TOTAlJ :****:*.***>**:*.***:*.* 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 5 min.

1000-1100 55 min.

1100-1175 30 min.

MAXIMUM TEMPERATURE 1130 DEGREES FARENHEIT

CONTRACT 2966 B-2 S.G.

Pg 4 of 7 COMPONENT

Upper Shell/Cone?> * *******.

INT~

X d HEAT TREAT# 0~83..<.. : FIN.*

AL.**. )

.<. /.*..*. *:... D.A. TE*** 9~26-67

~~--*.*-:*-*.. :-:. *....,: *.*

- - - \\ Ln6~r- * ***** * ***

> *.>--TIME-.***

Minutes 500-600 55 600-700 40 700-800 35 800-900 40 900-1000 1

10 1000-1100 45 1100-1175 1

5 1175-1200 1100-1000 1

5 1000-900 1

20 900-800 1

35 800-700 2

10 700-600 2

30 600-500 800-900 15 min.

900-1000 TOTAL..

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 30 min.

1000-1100 TOTAL *.*

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 50 min.

1100-1175 TOTAL **..*** **..

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 5 min.

MAXIl\\.1UM TEMPERATURE ---==11:....:.40~--- DEGREES FARENHEIT

CONTRACT 2966 B-2 S.G.

Pg 5 of 7 COMPONENT Upper Shell/Cone...

... *...INt.. *

..* X... *.**.......

HEAT TREAT #

0~92...

FIN.AL DATE 10~ 13-67.

TEMPERATURE

. -*TIME-..

Hour Minutes 500-600 50 600-700 1

10 700-800 55 800-900 30 900-1000 40 1000-1100 55 1100-1175 1

15 1175-1200 1100-1000 55 1000-900 1

20 900-800 1

45 800-700 1

700-600 600-500 800-900 15 min.

900-1000 1000-1100 50 min.

1100-1175 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 15 min.

MAXIMUM TEMPERATURE 1130 DEGREES FARENHEIT

CONTRACT 2966 B-2 S.G.

Pg 6 of 7

Local Heat Treat

/.. *.*.'FEM

.*.. :e

...... E. JM. T.**.*. URE

...*. **.. *... *.**.J.*.x/*.:* \\. )........... r.*JJ9ui".> t

. 'fIME; *.. **... *

M. inu. tes 500-600 25 600-700 45 700-800 1

7 800-900 36 900-1000 45 1000-1100 40 1100-1175 28 1175-1200 1100-1000 33 1000-900 30 900-800 30 800-700 37 700-600 45 600-500 1

800-900 1r******** <.***.]oTAL )* * ** 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 6 min.

900-1000 TOTAL.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 15 min.

1000-1100 TOTAL.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 13 min.

1100-1175 TOTAL 28 min.

MAXThflJM TEMPERATURE 1150 DEGREES FARENHEIT

Local heat treat would apply only to the top 5 feet of the upper shell assembly.

CONTRACT 2966 B-2 S.G.

Pg 7 of 7 H

COE**AM**TP. OT.NERE

.. *.. NA**.TT*.:#GeRn..,.e8r2

a.*>J. Assemb1}1 **.. *.**.F*******IN****.************ALIN**************T

.. *****:*L*****X*

. DATE. 1~41'-68>

TEMPERATURE

.. Hour

'" TIME~

- .Minutes 500-600 3

600-700 7

700-800 4

40 800-900 5

900-1000 5

1000-1100 5

1100-1175 10 10 1175-1200 1100-1000 7

1000-900 15 900-800 12 800-700 5

40 700-600 7

40 600-500 6

800-900 900-1000 1000-1100

>*.,.*.*....... TOTAL<***

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1100-1175 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months 10 min.

MAXrnuM TEMPERATURE 1160 DEGREES F ARENHEIT

CONTRACT 2966 B-1 S.G.

Pg 1of10 coivwoNF:NT uppe~ sfi~n H.

p H

INT~* > X:H

.... HEA,:'f TllE~~ ff N~34 ( * *.. *.***.* *

< FINAL* > > >..

..*.... *.* DATE 12*21.:;66.

.....* **... *TEMPERA$~..*.*. ***.. **.

\\

- - n()~r /.. *****: ** *..** _.- -~-**************..

Minutes 500-600 40 600-700 30 700-800 25 800-900 30 900-1000 40 1000-1100 50 1100-1175 1

1175-1200 1100-1000 45 1000-900 40 900-800 1

800-700 1

700-600 600-500 800-900 TOTAL.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 30 min.

900-1000

- - TOTAL 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 20 min.

1000-1100

- - - - ****.......*.**.. TOTA.i 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 35 min.

1100-1175

>/ ******<**fOTAI.I* >.* > 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months MAXTh1UM TEMPERATURE 1150 DEGREES FARENHEIT

CONTRACT 2966 B-1 S.G.

Pg 2of10

~

COMPONENT Upper Shell/Cone HEAT TREAT # N-54 500-600 600-700 700-800 800-900 900-1000 1000-1100 1100-1175 1175-1200 1100-1000 1000-900 900-800 800-700 700-600; 600-500 800-900 900-1000 1000-1100 1100-1175 MAXIMUM TEMPERATURE

.*INT.***** *x FINAL.

1 1

1 2

1 1

1 2

1 DATE 2~1-67 *

.. **. <. -TIM.J?6.. *. *.** *. *. ** Minutes..

30 50 10 10 50 30 10 20 40 10 10 20 min.

30 min.

50 min.

.*.****** TOTAL.

.1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 10 min.

1140 DEGREES FARENHEIT

CONTRACT 2966 B-1 S.G.

Pg 3 of 10 COMPONENT Upper Shell/Cone..

.INT.

x HEAT TREAT# N-79

FINAL DATE 3-24-67 TEMPERATURE

.*Hour.

-TIME;;:

Minutes 500-600 25 600-700 40 700-800 40 800-900 35 900-1000 40 1000-1100 1

10 1100-1175 1

10 1175-1200 1100-1000 50 1000-900 1

10 900-800 1

10 800-700 1

50 700-600 600-500 800-900 TOTAL 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 45 min.

900-1000 TOTAL 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 50 min.

1000-1100 TOTAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1100-1175 TOTAL*

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 10 min.

MAXIMUM TEMPERATURE 1145 DEGREES FARENHEIT

CONTRACT 2966 B-1 S.G.

Pg 4of10 COMPONENT Um~erShell/Cone.

INT.

X..

HEAT TREAT# N-95 FINAL

.DATE 4-25-67 TEMPERATURE Hour

-TTh1E-Minutes 500-600 20 600-700 30 700-800 1

10 800-900 45 900-1000 1

1000-1100 2

30 1100-1175 1

40 1175-1200 1100-1000 50 1000-900 1

20 900-800 2

800-700 2

30 700-600 45 600-500 800-900 TOTAL' 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 45 min.

/

900-1000 TOTAL.*.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 20 min.

1000-1100 TOTAL... **

3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 20 min.

1100-1175 TOTAL 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 40 min.

MAXTh1UMTEMPERATURE 1150 DEGREES FARENHEIT

CONTRACT 2966 B-1 S.G.

Pg 5 of 10 coMPONENT-dupper slle1i/cri~e IN1'.< ____ x *. d HEAT TREAT /l o~7._.---_

--- --*--*.**-_. FINAL/

DATE 5.;fJ-67 TEMPERA'I'URE _

Hour - -_ -

--- --- -- -_--_--_---TIME;; - -

Mfuutes 500-600 25 600-700 55 700-800 35 800-900 1

15 900-1000 45 1000-1100 1

25 1100-1175 35 1175-1200 1100-1000 40 1000-900 1

900-800 1

15 800-700 1

45 700-600 2

10 600-500 2

35 800-900

\\>-**--*/**.> ~()TAG- ? )***----*_-. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 30 min.

900-1000 45 min.

1000-1100 5 min.

. i""

1100-1175 TOT.AL*-

_35 min.

MAXIMUM TEMPERATURE 1130 DEGREES FARENHEIT

CONTRACT 2966 B-1 S.G.

Pg 6of10

....

coMPoNENT t.Ii;>pei-sii~111c61Ie **

iNTL< x/

. HEAT TREAT # Q,;;i5. **.*.. ***** *.*******..... *.*.. > ~WE >

<PATE 6~12-67.. *

- .. *.* *TEMP:E~~t-

. *.****.**... ***.> > **.lic)ll}. *............. >... ***********' -TiMEc*.**** ***.. ****Minutes*

500-600 45 600-700 35 700-800 55 800-900 1

900-1000 55 1000-1100 1

20 1100-1175 30 1175-1200 1100-1000 1

1000-900 1

55 900-800 2

800-700 55 700-600 600-500 800-900

... TOTAL*.*.<

3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 900-1000 TOTAL***

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 50 min.

1000-1100

T0Tl\\L 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 20 min.

1100-1175

- - - - .<... *.TOTAL{*****.*

30 min.

MAXThflJM TEMPERATURE __

1~1~45~--- DEGREES FARENHEIT

CONTRACT 2966 B-1 S.G..

Pg 7of10 COMPONENT Upper SheH/Cone HEAT TREAT # 0-37

.TEMPERATURE....

500-600 600-700 700-800 800-900 900-1000 1000-1100 1100-1175 1175-1200 1100-1000 1000-900 900-800 800-700 700-600 600-500 800-900 900-1000 1000-1100 1100-1175 INT.*.

X FINAL DATE *7'-2-67 liour

- TIME.-*

Minutes 35 45 55 1

10 35 35 50 1

1 30 1

50 50

(}> f TQ'I\\&13\\. *.*.*<*.** 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months

c*********** /> 'l'o~Ajj >*.. :** /.*.***.*** 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 5 min.

I.

.*.*.T.*. o

.. *.**.rn.**.Ali.***.* >****.**.* 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 35 min.

1**** :... ***.*....* TQTAh*> *.....

50 min.

MAXIMUM TEMPERATURE __ 1=1=50=------ DEGREES FARENHEIT

CONTRACT 2966 B-1 S.G.

Pg 8of10

Local Heat Treat

- ~=#lltfu~sh~111'ili!;~d*F:zi, **x+. *** hA~. s;~s~

. TEMPERATl.JRE * '

.*****: liril1r< ****

</.

- **** ~.TIME~ \\ *

- - - . Minutes 500-600 2

30 600-700 1

50 45 min.

11-------------+------------------ll 11-______

1_0_0-_8_00 __ _1 ____________

37_---11 lhour

~-----8_o_o_-9_o_o ____

5 ___________

5_o_--41 6 hrs 30 min.

ri--------90_0_-l_O_o_o ______________

3_5_-.i1 4 hrs 15 min.

1000-1100 1

50 1-------------+-------------------11 40 min.

1100-1175 35 1-------------+----------------i12hrs 11--______ 1_1_7_5_-1_2_0_0_-+-----------------ii 37 min.

1200-1100 25 min.

11------------+-----------------11 1100-1000 25 35 min.

11---------------+-----------------u 1000-900 25 30 min.

11-------------+-----------------41 900-800 34 45 min.

11-------------+-----------------41 800-700 45 50 min.

11--------------1-----------------11 700-600 45 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 600-500 1

10 800-900 24 min.

7 hrs 15 min.

900-1000 4 hrs 45 min.

1000-1100 TOTAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 15 min.

1 hr 15 min.

1100-1175 TOTAL*

35 min.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1175-1200 TOTAL 37 min.

11-----------_._ __ _,;,, ___ '--...._--------11 MAXIMUM TEMPERATURE ---'1=2'"""'05=----- DEGREES FARENHEIT

~

ocal heat treat applies only to the upper 5 feet of the upper snell.

- These temperature readings represent a single thermocouple at the 12:00 position of the furnace set-up. This T.C. was on the upper shell. This T.C. ran its own course approximately 200-250 degrees higher than the remaining thermocouples. The time inside the table does not include this "maverick" thermocouple.

CONTRACT 2966 B-1 S.G.

Pg 9 of 10

Local Heat Treat COMPONENT Uppet*Shell/Tb~ Head INT. ** * *.. X >

HEAT TREAT #R~22.*.... *

>FINAL*

.... DATE.6-11-68

TEMPERATURE *.

Bour "

...,...,*TIME-Minutes *.

500-600 410/680 Spread 2

600-700 5001715 Spread 2

700-800 620/800 Spread 23 800-900 720/860 Spread 52 900-1000 830/960 Spread 52 1000-1100 4

1100-1175 4

5 1175-1200 1100-1000 22 1000-900 22 900-800 22 800-700 30 700-600 37 600-500 800-900

.(*>:*.. **.

/

.: '. 'f:Q]!\\L)... ** *....

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 14 min.

900-1000 14 min.

1000-1100 22 min.

1100-1175 5 min.

MAXIMUM TEMPERATURE __ 1=1~40~--- DEGREES FARENHEIT

Local heat treat would apply only to the top 5 feet of the upper shell assembly:

- Thermocouple temperature spread shown above was averaged to obtain nominal temperature.

r CONTRACT 2966 B-1 S.G.

Pg 10of10 COMPONENT General Assembly INT.

HEAT TREAT #. R-68 FINAL x

DATE 8-30-68 TEMPERATURE Hour**

-TIME-Minutes 500-600 12 600-700 5

700-800 8

20 800-900 13 40 900-1000 9

20 1000-1100 10 1100-1175 13 1175-1200 1100-1000 3

40 1000-900 4

40 900-800 20 800-700 11 700-600 9

600-500 4

30 800-900

, ***.*. >..*. * *.*.*.*TOTAL********

33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months 40 min.

900-1000

.TOTAL***.*

- - - - 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months 1000-1100 TOTAL 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months 40 min.

1100-1175 TOTAL 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months MAXIMUM TEMPERATURE 1160 DEGREES FARENHEIT

CONTRACT 2966 A - R. V.

Pg 1of11 Hc.oE****AMPT:. OTNERENA**** TT******* #In~-~~~IiC

.. *F**.*.****.*

... *.. *INT.*****.****.**.*~.iu.*.**************~!****** *****************************:****:****:*****.*... ****.:*.**.**.:*.. *.. **,*.*.:..

- .... *.. y H/.****.*.: *.:.*...

HLI

})A.TE! 11~12;.66 500-600 50 600-700 25 700-800 30 800-900 30 900-1000 40 1000-1100 1

10 1100-1175 30 1175-1200 1100-1000 55 1000-900 1

10 900-800 1

20 800-700 700-600 600-500 1r-----*8~0~0-~90~0~-----,L&i:****\\*~

... r=.~=Q1111m1

: 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 50 min.

50 min.

5 min.

1100-1175 I

*~;g~ii\\ :..

1**.< >*: <

!Y:'!*:~*..... >

30 min.

MAXIMUM TEMPERATURE 1125 DEGREES FARENHEIT

CONTRACT 2966 A-R. V.

Pg 2of11 500-600 50 600-700 50 700-800 40 800-900 1

10 900-1000 1

50 1000-1100 3

1100-1175 1

30 1175-1200 1100-1000 1

1000-900 1

30 900-800 1

50 800-700 1

30 700-600 2

20 600-500 2

10 800-900 ~*

900-1000

/****>***)****>l'o~A~ )>***>***********. 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 20 min.

1000-1100 1100-1175 TOTAL **

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 30 min.

MAXIMUM TEMPERATURE 1140 DEGREES F ARENHEIT

CONTRACT 2966 A-R. V.

Pg 3of11 500-600 40 600-700 50 700-800 1

800-900 1

10 900-1000 40 1000-1100 1

10 1100-1175 20 1175-1200 1100-1000 1

1000-900 1

50 900-800 1

30 800-700 700-600 600-500 800-900

TOTAi:/

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 40 min.

900-1000

.*****.**... *.. *.* *... TPTAib i/*

- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 30 min.

1000-1100 10 min.

1100-1175 20 min.

MAXIMUM TEMPERATURE 1125 DEGREES FARENHEIT

CONTRACT 2966 A - R. V.

cofytPoNENT tow~; slte1I*.<> **** : iNt.>

x HEAT. TREAT # N~Sl..

. *. FIN~_

Pg 4of11 DATE 3;;.2s~67 500-600 35 600-700 40 700-800 40 800-900 30 900-1000 50 1000-1100 1

50 1100-1175 20 1175-1200 1100-1000 50 1000-900 1

30 900-800 1

30 800-700 40 700-600 600-500 800-900 900-1000 20 min.

1000-1100 40 min.

1100-1175 MAXIMUM TEMPERATURE 1140 DEGREES F ARENHEIT

CONTRACT 2966 A - R. V.

Pg 5of11 COMPONENT...LOwe~*Sh~Il<.*. *.*.. ***...... *.*.******** lN".r.. x HEAT TREAT # <o~J.2\\*.*** r >-* >* * *.* * ** * > JflNAL***** *-> * ***** ****** >

- .*.

i>A..TE. -5~22-67 ***.

500-600 50 600-700 40 700-800 50 800-900 50 900-1000 40 1000-1100 1

5 1100-1175 2

20 1175-1200 1100-1000 1

20 1000-900 1

30 900-800 2

800-700 1

700-600 1

20 600-500 800-900

... TOTAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 50 min.

900-1000

. TOTA;f,..

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 10 min.

-~

1000-1100

. TOTAL

.*. **. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 25 min.

1100-1175 TOTAL. <

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 20 min.

MAXIMUM TEMPERATURE 1125 DEGREES FARENHEIT

CONTRACT 2966 A-R. V.

Pg 6 of 11 COMPONENT Lower Shell.*.**** *.. ***** <********** IN'J'~ >. X***.

HEAT TREAT#

Q;..29.

FIN~L

- .... DATE. 6:,19'-67.

TEMPERATURE flour

-TIME-Minutes 500-600 40 600-700 25 700-800 35 800-900 40 900-1000 40 1000-1100 1

30 1100-1175 30 1175-1200 1100-1000 50 1000-900 1

30 900-800 1

20 800-700 700-600 600-500 800-900 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 900-1000 10 min.

1000-1100 20 min.

1100-1175 30 min.

MAXIMUM TEMPERATURE 1125 DEGREES F ARENHEIT

CONTRACT 2966 A-R. V.

Pg 7of11 co1VIP0NENT Btltfoni litl.ito~et Shell INTL > *x. <.****** *

.*.. HE~~ TRE.J\\T.#: p~J....*....... *.* *....*. ****.**...*. *..**

F:~AI.t*.***.* *. **.**.*.... ****>*.*/**.*.*..*. *******.*.*.. DAT~.*t0'-27.;67.

, ~~~JlA~t< ************ >

.. /. Hij~t <.< \\

~.T:~i.*.. *... **** 1Vlin11,tes 500-600 40 600-700 30 700-800 30 800-900 30 900-1000 1

1000-1100 40 1100-1175 20 1175-1200 1100-1000 40 1000-900 50 900-800 1

30 800-700 40 700-600 600-500 800-900

- - - - ~g~~********:***~***************** 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 900-1000 50 min.

1000-1100 20 min.

1100-1175 20 min.

MAX'UM TEMPERATURE -~11=20~--- DEGREES FARENHEIT

CONTRACT 2966 A-R. V.

Pg 8of11 coMi>o~NT---*-*v~~e1****.A~~iri61&

- -*-.-.-.. _.-<FJN{_._*.*_-_

INT_._-

- --*.i_.-_.*_T***_*_._.-.. *._-**-:-__ **_>_.x ->> ___ ----

HEAT TREAT# P4o****--*:_

tu;)

> -----DATi >l-S;.;68 ___ -_

500-600 1

10 600-700 50 700-800 620/800 Spread 1

20 800-900 720/860 Spread 1

10 900-1000 830/960 Spread 2

1000-1100 1

40 1100-1175 20 1175-1200 1100-1000 1

1000-900 2

30 900-800 2

50 800-700 1

10 700-600 600-500 800-900 T()J]Al) 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 900-1000

. :.**.*-*-**--.f o'J'.AC>

__ * <> 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 30 min.

1000-1100

/ ***- _____ TOTAL /. -__ *.. -_ 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 40 min.

1100-1175

- - - - .-*.-----*-- -'JJ{)TAL>**-*-* __ *-.*.

20 min.

MAXIMUM TEMPERATURE ---==11=2-=-0 ____ DEGREES FARENHEIT

\\

CONTRACT 2966 A-R. V.

Pg 9of11

. COMPONENT Ve5seLAssembly *.. _.*..

.INT.. X HEATTREAT # P-71

.. FINAL DATE 3~11-68 500-600 1

600-700 1

10 700-800 1

30 800-900 1

30 900-1000 1

20 1000-1100 1

10 1100-1175 20 1175-1200 1100-1000 1

1000-900 2

10 900-800 3

10 800-700 2

700-600 600-500 800-900 900-1000 1000-1100 1100-1175 TOTAih.. ******

20 min.

MAXIMUM TEMPERATURE ---==11=20-=----- DEGREES FARENHEIT

\\

CONTRACT 2966 A - R. V.

Pg 10 of 11 H'. coMPONENTc Ves5eFAs5efubly <u**** *. <INT.. **.***x.*.******.****?.. *........

.* *.*.*.. */.

llEA.T* TREAr u.p~94<*.. **** / * * * ********* <*.*FIN.At.*........ < *.* *. *..... *

.. *****.****.******..

n:A'J:'E** 4-t3:..6s

L TttMPERi\\IrtJRE t.* *

( {H~ri~.. r. )*********

+T~+

..... <. Miinites *.

500-600 50 600-700 50 700-800 50 800-900 40 900-1000 1

20

. 1000-1100 1

5 1100-1175 20 1175-1200 1100-1000 40 1000-900 1

40 900-800 2

30 800-700 700-600 600-500 800-900 900-1000 TOTAL 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 1000-1100 TOTAL**.

1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 45 min.

1100-1175 TOTAL*

20 min.

MAXIMUM TEMPERATURE __ 1=1=20.:._ ___ DEGREES FARENHEIT

l CONTRACT 2966 A - R. V.

Pg 11of11 Minutes***.*

TEMPERATURE 500-600 2

30 600-700 2

30 700-800 2

20 800-900 2

900-1000 1

30 1000-1100 2

20 1100-1175 13 15 1175-1200 1100-1000 2

20 1000-900 2

50 900-800 3

40 800-700 3

50 700-600 5

40 600-500 800-900 900-1000 1000-1100 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 40 min.

1100-1175 MAXIMUM TEMPERATURE 1165 DEGREES FARENHEIT

ATTACHMENT NO. 2 Consumers Power Company Palisades Plant Docket 50-255 RESPONSE TO NRC NOVEMBER 30,1994 REQUEST FOR ADDITIONAL INFORMATION REVISION 0 10CFR50.61 SCREENING CRITERION ITEM NO. 2 ABB CENO RESPONSE 2 Pages

ABB - CENO RESPONSE The Charpy and drop weight data from the steam generator weld samples have been compared to the generic weld data base.

Available data that demonstrate typical variability of the drop weight nil-ductility transition temperature (NDTT) and the unirradiated reference temperature (RT NDT) for a specific heat of weld wire are shown in Table 1. When there are two test results for a single wire heat the NDTT and RTNoT temperatures are found to vary 10

F to 30

F b_etween the results.

The value of RT NDT is determined by the minimum of the NDTT or T cv-60

F, where T cv is the Charpy test temperature at which 50 ft-lbs. absorbed energy and 35 mils lateral expansion are achieved. In some cases the NDTT result controls the RTNoT value and NDTT equals RT NDT* In other cases, T cv-60 is the limiting value for RT NDT and RT NDT will be higher than the NDTT value. In many cases the actual Tcv is not determined.

Charpy impact tests are performed at NDTT+60"F and if the 50 ft-lb and 35 mil criteria are satisfied no further testing is required.

In some cases, the Charpy results at NDTT+60"F could be as much as 90 to 100 ft-lb or the test result could just meet the minimum 50 ft-lb requirement. In such cases, the RTNoT values can be the same or similar because it is controlled by NDTT but the Charpy impact properties for two welds with the same NDTT can be dramatically different. From Table 1, RT NDT varies by 10

F to 30

F when the RT NDT is controlled by NDTT.

In other cases, the Charpy test results at NDTT+60"F may not meet the 50 ft-lb. and 35 mils requirements. When this happens testing is performed at higher temperatures until the criteria are met.

This higher temperature then becomes T cv and T cv-60

F determines the RTNoT* This can be seen in Table 1 for wire heats 13253 and 3P8013 where the RTNoT values are higher than the corresponding NDTT value. The RTNoT varies by 10

F when the Charpy impact properties are limiting.

The Palisades steam generator A, Weld 1-951 Charpy and drop-weight test data produced an RTNoT of -20"F for weld wire heat W5214. This was controlled by drop-weight test results for NDTT. The NDTT could have been -30"F, if specimens 9 and 10 happened to be tested before specimen number 5 which broke at -20"F. The results on W5214 reflect some of the inherent variability in the drop-weight test method. Another factor introducing variability is the comparison of the W5214 test results using single pass weld bead deposits and comparing to earlier data performed on specimens with two pass weld bead deposits. Examination of the Charpy impact data from the W5214 shows the 50 ft-lb Tcv to be approximately 20"F. This is determined from the minimum data points from the full Charpy impact curve in accordance with NB-2331(4). This Tcv would

I I

support an RTNoT value as low as -40°F.

In summary, the data from the SG weld are consistent with the data set from the generic database on similar welds. The measured RTNoT value is within the observed range of variation for these types of weld materials.

However, sufficient uncertainty exists relative to the condition of the SG weld material for it to be considered as being specifically representative of the initial baseline properties of the RV weld seams. The evaluation of RAJ #3 for Charpy energy properties suggests statistically significant differences between the SG weld and other baseline properties from W5214 welds.

Therefore, it is appropriate to continue using the generic mean value of -56°F for the RV W5214 welds.

TABLE 2-1 v ARIABILITY IN NDTT AND RT NOT I

HEAT OF WIRE I FLUX TYPE I

NDTT I

RTNDT I

13253 1092

-40

-70

-50 83650 0091

-10

-40

-40 3P8013 124

-60

-50

-80

-60 88114 0091

-70

-80

-80 89833 0091

-50

-60

-60 90069 0091

-60

-70

-70 33A277 0091

-60

-80

-80 IP3571 1092

-30

-50

1' ATTACHMENT NO. 2A Consumers Power Company Palisades Plant Docket 50-255 RESPONSE TO NRC NOVEMBER 30,1994 REQUEST FOR ADDITIONAL INFORMATION REVISION 0 10CFRS0.61 SCREENING CRITERION ITEM NO. 2 ATI CONSULTING RESPONSE 10 Pages

0~G-S-d4 rKl Ii :~u i, UC.

I VARIABILITY OF DROP-WEIGHT NDT DA.TA FOR HEATS OF C-E FABRICATED WELDS Compiled by T. J. Griesbach, ATI Consulting Here are the resLllts of my initial survey of drop-weight NDT data for multiple measurements on single heats of C-E fabricated welds in support of Item 2:

TABLE 2A-l Heat No.

Flux Typ" DWNDTT(°F)

Sources*

1P3571 Linde 1092

-30, -50 MY, WPS Surv.

13253 Linde 1092

-40, -70 SA2, CKI Surv.

33A277 Linde 0091

-60, -80 FAI, CCl Surv.

90069 Linde 0091

-60, -70 C-E WQ Tests It is observed that the varialion in measured drop-weight data is on the order of 10 to 30°F within a single heat of material.

*TI1is data was gathered from the AT! Consulting RPVDATA database. Printouts containg the data and source reference information arc attached.

DEC 9 '94 13:54 TJG Dcc~mber 9, 1994 Pi=!GE.002

ti rn

()

Ul w

Ul

~

-u D

G'>

rn CSl CS) w TABLE 2A-2 Weld Q_Lficaom* a*d T~t Data for Heat No. 1P3571 Measur~ il.e!.-l1s of Chemistry and Mechanical Properties of Welds WIRE HE

10 : ?3571 WIRE TYPE: B-4 MOD FLUX TYPE: LINDE 1092 SOURCE: MY.SC Ni WIRE:

WIREDIA: 3/16 in.

FLUX LOT: 3958 QVALCODE:

Cu:

1.36 Ni:

0.78' C:

0.14 Mn:

1.38 P: -.l IS S:

0.012 Si:

Mo:

0.55 Cr: --l}C)J Dwi.r::':

-:J dcgF RTNDT:

-30 deg F IUSE:

107 ft-lbs YS: -.26 ksi UTS:

85.2 ksi ELONG. IN 2":

24.2%

RED:-OON r;i AREA:

59.3 %

REFL:l'ICE: :::::R-75-269 TEST DATE:

LAB SAMPLE NO:

RPVDJ1=4 dei..Joped by ATI Consulting

0 rn 0

lD w

Ul Ul ll D

G'J rn TABLE 2A-3 w-eld ~alification and Test Data for Heat No. 1P3571 Measurel Test Results of Chemistry and Mechanical Pro]!erties of Welds

\\\\JRE HEAT NO: IP3571 WIRE TYl"E: B-4 Mld FLUX TYPE: Linde 1092 l'fi WIRE:

WIREDIA: 3/16 in.

FLUX LOT: 3958 Cu:

Ni:

C:

.P:

S:

Si:

Cr!

DWfiiDTT:

-50 deg F RTNDT:

IUSE:

SOURCE: WPS Tei.1 Di.ta QUAL CODE: NIA Mo:

Mo:

ft-Jbs YS:

ksi UTS~

ELONG. IN 2":

REDUCTION IN AREA:

REFERENCE:

TEST DATE:

9/1194 LAB SAMPLE NO:

RPVDJ. TA developed by A Tl Consulting

0 ITl

()

Ul w

c.n m

-u D

G'i ITl TABLE 2A-4 Weld Qualification and Test Data for Heat No. 13253 M~wed Test Resulls of Chemistry and Mechanical Properties of Welds WIRE HEAT NO : 13253 WIRE TYPE: B-4 MOD FLUX TYPE: LINDE 1092 SOURCE: SA2,SC Ni WIRE:

WIRE DIA: 3/16 in.

FLUX.LOT: 3TI4 QUALCODE:

Cu:

0.23.

Ni:

0.71 C:

0.1 Mn:

1.27 P:

0.017 S:

0.01 l Si:

l\\f.o:

0.45 Cr:

0.015 DWNDTT:

-40 deg F RTNDT:

-40 deg F IUSE:

ll l it-lbs VS:

57.7 ksi

- UTS:

78.6 ksi ELONG. IN 2":

20.3 ~'o REDUCTION IN AREA:

60.5 %

REFERENCE:

WCAP-8824 TEST DATE:

LAB SAMPLE NO:

RPVDAT A developfU} by A Tl Consultiog U1 rv CJ U-1

0 rn n

lD w

UI m

-u D

(j) rn TABLE 2A-5 Weld Qualificatio11 aud Test Dabi for Heat No. 13253 Measured Test Results of Chemistry and Meclumical Properties of Welds WIRE HE.AT NO : 13253 WIRE TYPE: B4 MOD FLUX TYPE: LINDE 1092 SOURCE: CKl,SC Ni WIRE:

WIRE DIA: 3/16 in.

FLUX WT: 3791 QUALCODE:

Cu:

0.27 Ni:

0.74 C:

0.26 Mn;.

1.33

~:

0.023 S:

0.014 Si:

Mo:

0.44 Cr:

0.022 DWND'IT:

-70 degF RTNDT:

-70 degF lUSE:

110 ft-lbs VS:

56.ll ks1 UTS:

79 ksi ELONG. IN 2":

23.5 %

REDUCTION lN AREA:

64.3 %

REFERENCE:

WCAP-8047 TEST DATE:

LAB SAMPLE NO:

RPVDATA developed by A TI Consulting en UJ

tJ rn

()

w w

Ul

-,j fSJ fSJ

-J TABLE 2A-6 Weld Qualification and Test Data for Beat No. 33A277 Me~wed Test Results of Chemfa*try and Mechanical Properties of Welds WIRE HEAT NO: 33A277 WIRE TYPE: B-4 FLUXTYPB: LINDE009l SOURCE: FAl,SC Ni WIRE:

WIRE DIA: 3/16 in.

FLUX LOT: 3922 QUALCODE:

Cu:

0.14 Ni:

0.19 C:

0.13 Mn:

1.06 0.016 S:

0.009 Si:

Mo:

0.5 Cr:

0.063 DWNDTT:

-60 deg F IRTNDT:

-60 deg F lUSE:

149 ft-lbs YS:

68.2 ksi UTS:

87.2 ksi EWNG. IN 2":

2Q.6 %

REDUCTION IN AREA; 65.8 %

REFERENCE:

WCAP-8810 l'ESTDATE:

LAB SAMPLE NO:

RPVDATA developed by ATI Consulting c.::.i

-J

0 rn n

lD w

U1 CD

-u D

Gl rn ISl ISl m TABLE 2A-7

=========-

~-======

Weld Qualification and Test Data for Heat No. 33A277 Measured Tesl Resul1s of Chemistry and Mechanical Properties of Welds WIRE HEAT NO: 33A277 WIRE TYPE: B-4 FLUX TYPE: LINDE 0091 SOURCE: CCI,SC Ni WIRE:

WIRE DIA: 3/16 in.

FLUX WT; 3922 QUALCODE:

Cu:

0.24 Ni:

0.18 C:

0.15 Mn:

1.05 P:

0.014 S:

0.013 Si:

Mu:

0.55 Cr:

0.06 DWND1T:

-SO deg F IRTNDT:

-80 deg F IUSE:

160 ft-lbs VS:

72.l ksi UTS:

85.1 ksi ELONG. IN 2":

26Jl %

REDUCTION IN AREA:

71.8%

REFERENCE:

TR-ESS--OOJ TEST DATE:

LAB SAMPLE NO:

RPVDATA developed by ATI Consulting 15

£:::>

1<-i C>

I CD I

CD

_p..

"T]

o

0 rn n

w lfl CD lJ D

Gl rn (SJ (SJ lD TABLE 2A-8 Weld Qualification and Test Data for Heat No. 90069 Measured Test Re~-ults of Chemistry and Mechanical Properlies of Welds WIRE HEAT NO: 90069 WIRE TYPE: LCLP FWX TYPE: LINDE009l SOURCE: CE,WQ Ni WIRE:

WIRE DIA: 3/16 in.

FLUX LOT: 1054 QUAL CODE: G3.19 Cu:

0.05 Ni:

0.03 C:

0.14 Mn:

1.26 0.006 S:

0.006 Si:

0.16 Mo:

0.51 Cr:

0.04 DWNDTT:

-70 deg F IR1'NDT:

-70 deg F IUSE:

l56 ft-lbs YS:

77.2 ksi UTS:

89.9 ksi ELONG. INl":

REDUCTION IN AREA:

70 %

REFERENCE:

C-E 78-12 RSP TEST DATE:

4f2J76 LAB SAMPLE NO: D23726 RPVDATA developed by ATI Consulting 5

~-'

P"l C:>

I I

CD I

CD

.p..

-r]

0 c.:::i CD

0 rn n

lD w

lfl lD TABLE 2A-9 Weld Qualification a*d Test Data for Heat No. 90069 Measured Test Results of Chemilt*try and Mechanical Properties of Welds WIRE HEAT NO: 90069 WIRE TYPE: B-4 FLUXTYPE: LINDE0091 SOURCE: CE,WQ Ni WIRE:

WIRE DIA: 3/16 in.

FLUXLOT: 0842 QUAL CODE: G2.05 Cu:

0.04 Ni:

0.04 C:

0.15 Mo:

1.12 P:

0.007 S:

0.008 Si:

0.19 Mo:

0.49 Cr:

0.02 DWNDTf:

-60 deg F IRTNDT:

-60 deg F IUSE:

162 ft-lbs YS:

70 ksi UTS:

81.8 ksi ELONG. IN 2":

30.5 %

REDUCTION IN AREA:

74.9 %

REFERENCE:

C-E 78-12 RSP TEST DATE:

LABSAMPLENO: 019893 RPVDATA developed by A TI Consulting 3

i

-:~

c:>

I CD I

CD

o

<Jl

=

ATTACHMENT N0.3 Consumers Power Company Pa 1 i sades Pl ant Docket 50-255 RESPONSE TO NRC NOVEMBER 30,1994 REQUEST FOR ADDITIONAL INFORMATION REVISION 0 10CFR50.61 SCREENING CRITERION ITEM NO. 3 RESERVED FOR LATER USE

~.

ATTACHMENT NO. 4 Consumers Power Company Palisades Plant Docket 50-255 RESPONSE TO NRC NOVEMBER 30,1994 REQUEST FOR ADDITIONAL INFORMATION REVISION 0 10CFR50.61 SCREENING CRITERION ITEM NO. 4 15 Tables 4 Figures

TABLE 4-1 TABLE 3.

CHARPY V-NOTCH IMPACT RESULTS FOR BASE METAL PLATE NO. D3803-l, LONGITUDillAL ORIENTATION Impact Lateral Specimen Temperature,

Energy, Expansion, No.

OF ft-lb mils 14E

-150 2.0 2.0 147

-100 3.0 4.5 145

-33 10.0 12.0 l4D

-15 15.5 19.0 l4C

+5 34.0 33.5 143

+21 49.0 45.0 171

+49 77.5 63.0 172

+49 67.0 54.5 173

+49 90.0 67.0 146

+SO 69.0 56.0 141

+72 94.0 75.0 14A

+110 129.5 88.0 142

+150 135.5

'93.5 14B

+225 162.5 85.5 144

+294 143.0 94.0 14J

+360 178.0 78.0 Fracture Appearance, Percent Shear 0

0 l

5 10 15 25 20 25

25.

50 80 100 100 100 100

TABLE 4-2 TABLE 4.

CHARPY V-NOTI:H IMPACT RESULTS FOR BASE METAL PLATE NO. D3803-l, 'IRANSVERSE ORIENTATION Impact Lateral Fracture Specimen Temperature,

Energy, Expansion, Appearance, No.

OF ft-lb mils Percent Shear 23P

-150 2.0 2.5 0

21E

-100 4.0 4.0 o

21B

-33 11.0 13.5 2

23M

-15 12.0 16.o 5

23L

+5 41.5 38.5 10 217

+21 2 7.o 29.0 15 21D

+50 46.0 44.0 20 215

+72 60.0 53.5 30 23T

+90 68.5 58.0 50 23J

+110 94.0 75.0 so*

216.

+150 114.0 79.0 100 23K

+225 107.o 79.0 100 21A

+295 92.0 75.5 100 252

+296 102.0 81.5 100 23U

+360 93.0 78.0 100

TABLE 4-3 TABLE 5. CHARPY V-NO'l'CH Il1PACT RESULTS FOR WELD METAL Impact Lateral Fracture Specimen Temperature,

Energy, Expansion, Appearance, No.

op.

ft-lb mils Percent Shear 36T

-170 4.0 s.o 0

36J

-150 7.0 7.0 0

36P

-135 14.5 14.5 2

367

-100 8.5 11.0 1

36M

-100 31.0 28.0 5

36L

-85 35.0 33.5 10 36E

-75 47.5 41.0 15 36D

-50 41.0 39.0 20 365

-33 56.0 52.0 30:

36C

-5 87.0 75.0 60 363

+20 86.0 77.o 80 366

+so 92.0 79.0 80 361

+72 96.0 85.0 90 36A

+110 117.5 94.0 100 362

+150 112.o 88.5 100 36B

+225 127.5 92e0 100 364

+296 111.0 87.0 100 35K

+360 120.5 91.5 100

TAllLE 4-4 TABLE 6.

CHAR.PY V-NOTCH Il1PACT RESULIS FOR HAZ METAL Impact Lateral Fracture Specimen Temperature>

Energy, Expansicn,

. Appearance>

No.

OF ft-lb mils

Percent, Shear 47Y

-170 s.o 4.0 0

471

-150 s.o 3.0 0

43A

-145 6.0 s.o 0

475

-137 6.0 3.5 2

474

-135 13.0 10.0 1

4-73

-120 15.0 11.0 5

476

-109 20.0 15.0 5

477

-101 25.0 18.5 10 467

-100 64.0 43.0 15 41.A

-75 13.o 13.5 5

465

-34 76.5 56.0 40 463

+20 77.0 45.5 50 466

+so 94.0 71.0 85 461

+72 112.0 76.5 80 46A

+110, 90.0 74.0 100 462

+151 114.0 81.0 100 46C

+225 120.0 86.o 100 464

+296 138.5 87.0 100 472

+360 llS.O 75.0 100

Sample No.

22M 22L 22J 22E 21L 228 22C 21J 21K 220 22K 21M TABLE 4-5 CAPSULE T-330, THERMAL CAPSULE CHARPY V-NOTCH IMPACT DATA FOR THE PALISADES INTERMEDIATE SHELL PLATE D-3803-1 (TRANSVERSE ORIENTATION)

Temperature Impact Energy Lateral Expansion (oF)

(ft-lb)

(mils)

-75 5

6.5

-25 13 18 25 28 20 so 47 42.5 60 48 47.5 77 79 58 100 71 60 150 82 64.5 200 112 78 250 92 74 300 117 80 400 110 78 8092B:lb-091984 Shear

(%)

5 10 26

. 47 45 50 56 78 100 100 100 100

TABLE 4-6 CAPSULE T-330, THERMAL CAPSULE CHARPY V-NOTCH IMPACT DATA FOR THE PALISADES INTERMEDIATE SHELL PLATE D-3803-1 (LONGITUDINAL ORIENTATION)

Sample Temperature Impact Energy Lateral Expansion No.

(oF)

(ft-lb)

(mils) 13M

-so 7

9 13P 0

13 13.S 13C 25 39 32.S 138 35 so 47.2 BE so 65 53 13J 77 112 74.5 13K 150 131 91.5 13Y 200 156 87.0 130 300 158 77.5 13L 350 158 85.5 i3T 400 215 67.S

Specimen 13U was improperly centered on anvil.

8092B:lb-091984 Shear

(%)

2 14

. 20 27 40 66 83 100 100 100 100

I TABLE 4-7 CAPSULE T-330, THERMAL CAPSULE CHARPY V-NOTCH IMPACT DATA FOR THE PALISADES PRESSURE VESSEL WELD METAL Sample Temperature Impact Energy Lateral Expansion No.

(oF)

(ft-lb}

{mils}

33M

-100 12 17 33K

- 75 45 39 343

- 60 22 26 341

- 50 31 32 33L

- 50

.23 26 33P

- 25 32

. 28.5 342 0

82 65.5 33Y 25 93 75.5 344 77 79 88.5 33T 150 120 94.5 33J 300 122 74.5 33U 350 155 79 80928:lb-091984 Shear

(%)

18 30 29 37 42 40 60 84 94 100 100 100

TA:OLE 4-3 CAPSULE T-330, THERMAL CAPSULE CHARPY V-NOTCH IMPACT DATA FOR THE PALISADES PRESSURE VESSEL WELD HEAT-AFFECTED ZONE METAL Sample Temperature Impact Energy Lateral Expansion No.

(oF)

(ft-lb)

(mils) 430

-75 45 39 420

-25 27 27.5 42E

-10 43 41.5 440 0

55 47.5 43E 25 52 47 41E 40 88 57 46E so 130 84 44E 60 115 81 460 77 70 55 45E 150 125

90.s 410 225 110 67 450 300 121 77 8092B:lb-091984 Shear

(%)

3 14 34 44 43 62 88 84 85 100 100 100

co 0

1.£)

N co..

CT -

0 1.£)

s.. pl*

liW1ber 22H 22L 22J 22!

21L 228 22C 21J 2ll 220 221(

21H Teet Te*p

< r)

-75

-25 25 50 60 11 100 150 200 250 100 400 CharpJ Inergy TABLE 4-9*

CAPSULE T-330. THERMAL CAPSULE INSTRUMENTED CllARPY IMPACT TEST RESULTS FOR PALISADES INTERMEDIATE SHELL PLATE 0-3803-1 (TRANSVERSE ORIENTATION)

Nonaaltzed lnerale*

a.arPJ Haxl*WI Prop Yield Tl*e Haxl*ua Id/A Im/A Ip/A Load to Yield Load (ft lb*) :----- (ft-lbe/1n*2)

(kip*)

(uSec)

(kip*)

5.0 40 17 21 2.60 11.0 I05 70 14 1.10.

90 1.55 28.0 22S 119 81 1.10 85 l.75 41.0 171 198 180 2.95 160 l.95 48.0 187 254 111 2.95 85 l.95 79.0 616 107 129 2.85 80 4.00 71.0 572 262 109 2.60 90 l.85 82.0 660 191 467 2.70 80 1.60

.112.0 902 258 644 2.60 85 l.75 92.0 741 226 515 2.25 50 l.50 117.0 942 294 648 2.10 50

).55 110.0 196 249 611 2.20 15 l.45 Tl*e to rrecture Arre et Yield Flow Haxl*ua Load Loed St re**

Streee (uSec)

(ltlpe)

(kip*)

(Ital)

(hi) 85 2.60 195 1.55

.25 108 111 150 l.75

.70 102 Ill 560 1.9S l.95 91 114 605 l.90 1.55 98 115 725 l.85 l.95 94 Ill 655 l.60 1.95 86 101 500 1.00 2.50 89 104 655 86 105 610 14 95 715 69 91 615 11 94

p I 00 C)

LO N

OJ s..,1.

luaber l1H llP llC Ill Ill llJ lllt UY llD llL llT Te*t T-p

< r>

-50 0

25

]5 50 11 150 200

]00

]50 400 Chupy TABLE 4-10 CAPSULE T-330, THERMAL CAPSULE INSTRUMENTED CllARPY IMPACT TEST RESlJLTS FOR PALISADES INTERMEDIATE SHELL PLATE D-3803-1 (LONGITUDINAL ORIENTATION) lloraaltced Energte*

Qarpy Haidaua Prop lleld TIM Haldaua Energy

Id/ A la/ A Ip/ A Load to Yield to.d (ft lb*) ~

(ft-l~~/10*2) ------

(kt pa)

hS.c)

(kip*)

I' 1.0 56 24 l2 1.n 11.0 105 18 66

].1.5 90

].20 19.0

]14 201 Ill l.00 85 4.05 50.0 40]

162 241 2.85 80

].80 65.0 52]

114 209 2.90 90 4.00 112.0 902 no 552 2.80

. 80 4.10 Ill.O 1055 112 72]

2.45 10

].90 156.0 1256

]2]

9))

2.55 90 1.15 151.0 1212 290 982 2.40 100

].55 158.0 1212 294 971

2.10 45

].45 215.0 Ull 215 1446 2.10 60

].50 TIM to Fr*cture Arre at Yield.

Plow Hald*ua Load Load Streaa St re**

(uSec)

(kl pa)

(kip*)

(kat)

(kel) 85

).)5

.10 125 l.10

.n 104 105 485 4.05

.10 99 117 410 1.15 2.15 95 110 740

].95

.90 97 115 815 1.25 1.60 91 114 115 2.10 l.70 81 105 825 85 104 175 80 99 105 68 91 110 69 92

l.

())

0 lD N

O:J CT 0

lD lD

())

~

s-,1*

lluaber llH lU lU 141 llL llP 142 lll 144 llT

))J llU Te*t Teap

< r)

-100

-15

-60

-so

-u 0

25 11 150

)00 no

. I Charpy Inergy TABLE 4-11 CAPSULE T-330, THERMAL CAPSULE INSTRUMENTED CHARPY IMPACT TEST RESULTS FOR PALISAD~S WELD METAL Horaallsed lnerale*

a.upr Ha:alaum Prop Yield Tl*e Ha:alaua U/4 r../A.

Ip/A Load to fleld Load (ft lba) ---- (ft-lb*/tn*2)

(kip*)

(uS.c)

(Upa) 12.0 t1 68 29 l.65 125 l.115 45.0 162 218 144 l.15 90 4.15 22.0 111 ll9 ll l.l) 95 l.n 11.0 250 116 14 1.25 95 l.9S 21.0 IH 104 12 l.25 90 l.10 12.0 258 181 11 l.IS 95 l.IS 12.0 660 290 171 1.10 90 4.10 91.0 149 214 474 2.95 95 1.90 19.0 616 ns 101 2.70 as l.80 120.0

'66 100 666 2.50 15 l.65 122.0

'82 281 699 2.20 15 l.40 155.0 1241 280 961 2.10 65 3.lO TIM *to Fracture Arre*t Yield Flow Had*um Load Load Streaa Stre*a (uS.c)

(klp*)

(klpa)

(kat)

(Ital) 200 l.BO

.10 121 124 500 4.05

.15 110 121 145 l.IS

.u 110 119 425 1.95

.so 101 119 210 1.55

.ss 108 115 445 l.80

.15 105 116 610 l.45.

1.15 102 119 665 l.40 2.2 98 114 125 2.95 2.2 90 l08 110 8l 102 180 1l 9l 115 10 90

r' \\

co 0

'° N

DJ CT -

0

'°

'° Ol s-pl*

Number UD 42D 421 44D 01 411 461 441 460 451 41D 45D Te*t Te*p

( f)

-75

-25

-10 0

25 40 50 60 11 150 225 JOO

\\,! i ',i tt CharpJ lner11 TABLE 4-12 CAPSULE T-330, THERMAL CAPSULE INSTRUMENTED CHARPY IMPACT TEST RESULTS FOR PALISADES WELD HEAT AFFECTED ZONE METAL Mor.allaed !ner,le*

QaarpJ tlad*ua Prop Yield Time "91lf*WI Id/A

!*/A Ip/A Load to lleld Load (ft lb*) ----- (ft-lba/1n*2)

(kip*)

(uSec)

(kip*)

17.0 ll7 114 21 l.55 95 4.05 27.0 217 174 44 l.40 105 4.05 u.o 146 222 125

],;]Q 90 4.15 55.0 441 179 264 l.50 105 4.15 52.0 419 211 201 l.20

90 l.90 88.0 709 147 162 l.15 90 4.10 llO.O 1047 126 721 l.10 95 4.10 115.0 926 282 644 l.15 100 4.00 10.0 564 209 154

].05 85 4.00 125.0 1007 lll 69]

2.80 85

].75 110.0 U6 246 640 2.45 65 l.80 121.0 t14 ll2 662 2.25 75 l.55 Tt.. to fracture Arre*t Yield Flow tlad*ua Load Load St re**

Streaa (uS.c)

(kip*)

(lr.lpa)

(Ital)

(Ital) 275 4.05 117 125 410 4.05

.15 112 123 505 4.15 1.15 110 124 415 4.15

.25 116 127 500 l.80 1.15' 106 118 110 l.75 1.75 105 124 750 2.15 1.40 101 119 665 2.70 1.60 101 118 495 l.85 2.n 101 117 110 92 108 610 80 101 820 14 96

TABLE 4-13 CHEMISTRY FOR WELDS FABRICATED WITH RACO 3 WELD WIRE HEAT NUMBER 3277 WITH Ni200 NICKEL ADDITION Weld Cop er %

Nickel (%

Phosphorus (%

Content Mean Content Mean Content Mean Palisades 0.26 0.25 0.63 1.36 0.011 0.014 surveillance 0.22 1.27 0.011 weld 0.25 1.60 0.013 0.30 1.38 0.014 0.239 1.617 0.016 0.231 1.502 0.017 0.233 1.494 0.017 Palisades 0.25 0.25 0.43 1.09 0.011 0.013 HAZ 0.20 1.28 0.012 weld 0.26 1.19 0.015 0.25 0.95 0.014 0.26 1.25 0.013 0.27 0.98 0.014 0.26 1.27 0.014 0.23 1.09 0.012 0.27 0.90 0.014 0.23 1.18 0.012 0.22 1.28

0. 012*

0.22 1.27 0.012 0.28 1.02 0.014 0.22 1.10 0.012 0.27 1.22 0.015 0.28 0.94 0.015 0.27 1.18 0.015 0.23 0.89 0.012 0.27 0.92 0.014 0.26 1.15 0.011 0.21 1.29 0.013 0.22 1.31 0.012 0.27 1.02 0.014 0.23 1.12 0.012 Best 0.014 Estimate

~--

TABLE 4-14 PALISADES REACTOR VESSEL SURVEILLANCE PLATE CHEMISTRY Material Copper (%)

Nickel (%}

Phosphorus (%)

D-3803-1 0.22 0.49 0.010 0.25 0.48 0.013 0.24 0.53 0.011 0.24 0.53 0.005 0.215 0.52 0.004 0.215 0.523

<0.013 0.215 0.496

<0.013 0.495

<0.013 Best Estimate 0.23 0.51

<0.010

Cycle 1

2 2

2 3

4 5

6 7

8 9

10 11 (1)

(2)

Steam Generator and PCS Data-Cycles 1 thru 11 TABLE 4-15 Typical Typical Typical Typical Dates Hours Critical Power SG Pressure SG Temp 12/30/71-12/20/75 16,087 70 670 498 05/18/76-04/18/77 7,722 100 615 489 04/19/77-11 /06/77 4,351 100 660 497 11/07/77-01/06/78 1,508 100 690 502 04/22/78-09/08/79 10,041 100 680 500 05/28/80-08/29/81 9,015 100 710 505 01 /05/82-08/12/83 10,680 100 685 501 07/24/84-11/30/85 9,040 98 690 502 03/04/86-08/08/88 10,305 100 710 505 11 /29/88-09/15/90 11,596 80 750 511 03/15/91-02/07 /92 7,733 100

n/a

n/a 04/18/92-06/04/93 9,101 100 n/a n/a 11 /08/93-11 /30/94 6,533 100 n/a n/a Cycles 9-11 steam generator data is not applicable due to steam generator replacement after Cycle 8.

T-inlet 523 522 529 535 535 537 536 536 536 537 535 533 533 On 04/19/77, T-ref was increased from 544 degrees to 549 degrees Fahrenheit.

On 11/07/77, 100% power was increased from 2212 MWth to 2530 MWth.

(1)

(2)

FIGURE 4-1 Palisades Huclear Plant Hyperbolic Tangent Curve Fitting ~outine Version 2.0 Printed at 19:40:22 on 12*09-1994 c v

Capsule:

250 200...;.i*~e; D e r

q 15 o.....,.~~

y T

L B

8 100 50 0

Material:

WELD SA302BM Heat No.: 3277 8--- curve #1 curve #2

-300

-200

-100 0

100 200 300 Temperature in Deqreea..

Curve Flu.nee LSE d*LSE USE d*USE Ta 30 d*T a 30 1

O.OOE+OO 2.2 0.0 118.2 o.o

-86.7 o.o 2

1.00E+13 2.2

-o.o 118.6 0.4

-58.4 28.3 Orientation:TL 400 500 600 T a 50 d*T a 50

-47.2 0.0

-21.8 25.4

FIGURE 4-2 Paliaadea HUclear Plant Hyperbolic Tangent Curve Fitting Routine Version 2.0 Printed at 19:4S:14 on 12-09-1994 Capsule:

250 c v *

200 ll

r CJ 150 y

T 100 L

B 8

50 0

Material:

PLATE SA302BM Heat No.:Cl279-3 8

curve #1 1--curv* 12

-300

-200

-100 0

100 200 300 Temperature in Degreea -,

Curve Fluence LSE d-LSE USE d*USE T i 30 d*T a 30 1

O.OOE+OO 2.2 0.0 1S9.1 0.0

-1.a 0.0 2

1.00E+13 2.2 0.0 1S7.3

-1.8 1S.4 17.2 Orientation:LT 400 500 600 T i SO d*T il SO 25.1 0.0 3S.6 10.6

FIGURE 4-3 Palisade* Nuclear Plant Hyperbolic Tangent Curve Fitting Routine Version 2.0 Printed at 19:47:24 on 12*09-1994 Material:

PLATE SA302BM Capsule:

Heat No.:Cl279-3 c v

250

2 0 0--f-+~~e;'+.P+/-+/-

D e

r q 150 y

L B

8 0

-300

-200

-100 Curve Fluenc:e LSE 1

O.OOE+OO 2.2 2

1.00E+13 2.2 8

curve #1

--curve #2 0

100 200 300 Temperature in Deqreea...

d-LSE USE d-USE T i 30 d-T i 30 0.0 102.6 0.0 18.0 0.0 0.0 107.4 4.8 18.9 0.9 Orientation:TL 400 500 600 T a 50 d-T a 50 49.1 0.0 56.5 7.5

FIGURE 4-4 Pali**4** BUclear Plant Hyperbolic Tangent Curve Fitting Routine Version 2.0 Printed 1t 19:S0:04 on 12*09-1994 c v

Capsule:

200 D e r

q 150 y

'f L

B 8

100 50 0

Material: HEAT AFF'D ZONE SA302BM Heat No.:

8 curve #1

--curve #2

-300

-200

-100 0

100 200 300

'temperature* in Degreea

curve Fllmnee LSE d*LSE USE d*USE T a 30 d*T i 30 1

O.OOE+OO 2.2 o.o 119.8 o.o

-89.5 0.0 2

1.00E+13 2.2 0.0 119.4

-0.4

-39.6 50.0 Orientation:TL 400 500 600 T i SO d-T a SO

-46.6 0.0

-8.7 37.8

ATTACHMENT NO. 5 Consumers Power Company Palisades Plant Docket 50-255 RESPONSE TO NRC NOVEMBER 30,1994 REQUEST FOR ADDITIONAL INFORMATION REVISION 0 10CFR50.61 SCREENING CRITERION ITEM NO. 5 7 Pages

ABB - CENO RESPONSE All available purchase orders and receiving records were reviewed for shipments of weld wire W5214.

As shown in the attached table, four shipments of this material were received.

The approximate weight of each shipment is also tabulated. A total of 44,550 lbs of W5214 weld wire was received. Since this material was received in 150 pound spools, there were 297 spools. This data is summarized in Table 5-1.

The W5214 weld samples data base is given in Tables 5-2 and 5-3.

TABLE 5-1 W5214 Supplier Data I

P.O.# I Shipped I Weight I

Coils I

(Calculated) 45-43953 7-23-65 7,200 48 45-43953 3-31-66 10,950 73 45-43953 6-24-66 10,800 72 45-43953 10-24-66 15,600 104 F:\\RVG\\ WP\\RAl-QUES. WP

~.'.2032854232 F-:ao 7-:~~ ?-0~2 DE*: l...l ' 34 13:.20 TABLE 5-2 Italicized Values are the Mean Value for one Weld Chemical Composition of Selected Heat No. W5214 Weld Samples Estimated Identification

%Cu

%Ni

%P Tandem No. of Location Arc CoiJs9

,... 0'12.'it 04463 IP2 !1t1 14 0.20 0.019 x

6-8 Weld not first bead 04494 IP2 1-042 0.76 6-8 Through Thickness 0.77 0.72 0.81 0.96 0.98 0.98 1.01 0.99 0.97 0.96 1.05 1.08 0.81 1.01 1.06 1.03 1.03 1.00 0.81 0.94 04541 1.20 0.021 1

Weld Material Cert.

04577 IP2 0.94 0.02 6-8 Top 1 1/2" of weld 1.07 O.Oll 2 3/16 from ID 1.00 0.02 04673 Millstone 1 1.05 5-7 Not determined chip from weld SeamC 04674 IP2 3-042B 1.121 6-8 Not determined chip from weld

2032854232

~* ---

Identification 04686 MLl 2-072A 04687 IP2 l-042A 04688 PAL S/G 5-943 04690 04691 D4752 04982 HBR2 torus-flange weld IP2 Surveillance Weld IP3 Surveillance Weld

%Cu

% Ni 0.97 0.92 0.99 1.13 0.154 0.99 0.163 0.90 0.152 1.08 0.166 i.oo2 0.159 0.99 0.233 1.oi3.

0.203 1.063 0.203 1.003 0.193 0.223 0.183 0.203 o.2ol 1.oi 0.15 l.02 0.166 1.21 4

0.16 1.12 TABLE 5-2 (continued)

Estimated

%P Tandem No. of Location Arc Coils 9

I 8-10 Weld chip 6-8 Chip from Weld 3-5 Chip from Weld 0.027' 1-2 Test plate l

0.027' WMC for Linde 80 0.0281 1-2 Test plate with Linde 80 l

o.01s1 WMC Linde 80 4 Locations around the flange 0.012 OD surface8 O.Oll 0.014 0.012 0.012 x

9-12 Charpy specimen W-137 Charpy specimen W-12 7 0.0257 Tensile specimen W-67 Tensile specimen W-47 0.0107 Charpy specimen W-177 0.0177 Charpy specimen W-197 0.022 7

Tensile specimen W-5 7

Tensile specimen W-37 6-8 All test specimens were machined from test materials at 1/4t Iocations7 0.019 Heat analysis7 Charpy specimen W-15 7 0.019 x

2

TABLE 5-2 (continued)

Estimated Identification

%Cu

% Ni

%P Tandem No. of Location Arc Coils9 IP3 Nozzle cutout 0.16 1.06 0.017 x

Outside surface, 3/4 thickness, 0.15 1.11 0.018 center of weld8 0.15 1.09 0.018 0.15 1.09 0.018 6-8 HBR2 Surveillance Weld 0.32 0.66 0.021 Heat analysis 7 0.34 Heat analysis 7 0.33 0.63 0.026 Charpy specimen W-1 7 0.35 0.695 Charpy specimen W-207 0.34 0.66 0.024 l

Oyster Creek l 0.0547 Surveillance Weld 0.282 0.021 Charpy specimen 1 E2A 7

0.290 0.056 7

0.023 Charpy specimen 1E2B 7 0.2826 0.0517 0.022 Charpy specimen 1E37 0.285 0.0547 0.022 1-'2 lByme (ABB/CE) to Kneeland (CPCo), "Records Search on Welds 2-112 A/C, 3-112 A/C, E-112 A/C, 9-112, Final Letter Report," P-MECH-92-025, October 12, 1992, Pg. 5-6.

2Yanichko, Williams and Kunka, Evaluation of H.B. Robinson Unit 2 Reactor Vessel Beltline Region Weld Material Chemistry," May 1983, Table 4.

3Iddings, Cadena and Williams, "Reactor Vessei Material Surveillance Program for Indian Point Unit No. 2, Analysis of Capsule V," SWRI Project No. 17-2106 (Revised), March 1990, pg. IV-26.

4Yanichko, Anderson and Kaiser, "Analysis of Capsule Y from the Power Authority of the State of New York Indian Point Unit J Reactor Vessel Radiation Surveillance Program," WCAP-10300, March 1983, pg. 4-3.

5Yanichko, Williams and Kunka, "Evaluation of H.B. Robinson Unit 2 Reactor Vessel Beltline Region Weld Material Chemistry," May 1983, Table 1.

6Chen (GPUN) to Kneeland (CPCo), Novt:mber 4, 1992, pg. 5.

70akridge PR-EDB Version 2 8Evaluation of H.B. Robinson Unit 2 Reactor Vessel Beltline Region Weld Material Chemistry dated 5/83.

9Best Estimate by ABB CE.

f 2032854232 TABLE 5-3 F-365 T-333 P-<J8EV01-l CF:: l J "34 1'3: 18

--., *-*.. -,.~ -'--'-~"-=--*--------

RESULTS OF CHEMICAL TESTING ON PALISADES RETIRED STEAM GENERATOR WELD MATERIAL Mn Cr Cu Mo Ni p

Section through large Weldment 'A' ARl/X l.179 0.0376 0.328 0.508 l.116 0.008 ARl/Y 1.259 0.0349 0.310 0.515 1.006 0.007 ARllZ 1.205 0.0343 0.266 0.509 l.104 0.009 Section rhrough large Weldment 'B' BRl/X 1.270 0.0415 0.198 0.552 1.092 0.013 BRl/Y 1.308 0.0398 0.198 0.545 0.906 0.Qll BRl/Z 1.283 0.0395 0.196 0.547 1.057 0.010 Section through Trepan

'A/SO/A' A/SG/A/3/X 1.142 0.0407 0.365 0.510 1.193 0.006 A/SG/A/3/Y 1.ll8 0.0343 0.292 0.501 1.127 0.009 AJSG/A/3/Z 1.116 0.0334 0.281 0.500 1.066 0.011 Section dlrouah Trcpart

'AJSG/B' AJSG/Bl2/X 1.177 0.0409 0.359 0.515 1.204 0.007 A/SGIB/'2/Y 1.120 0.0397 0.239 0.524 0.960 0.007 AJSGIBf}./Z 1.092 0.0390 0.228 0.516 1.107 0.006 Section lhrOugh Tn:pan

'B/SG/A' B/SG/AJ31X

'l.259 0.0394 0.191 0.535 1.256 0.010 B/SG/A/3/Y 1.226 0.0375 0.192 0.537 1.292 0.011 B/SG/A/3/Z 1.220 0.0378 0.204 0.531 0.998 0.011 Section throush Trepan

'B/SG/B' B/SG/B/3/X 1.269 0.0395 0.165 0.534 1.117 0.009 B/SG/B/3/Y 1.241 0.0393 0.203 0.524 1.088 0.007 B/SGB/3/Z 1.183 0.0388 0.209 0.526 1.292 0.008 Rows beginning with "A" are Heat No. W5214.

Rows beginning with "B" are Heat No. 34B009.

I f /11/ 'i'f Si s

v

of Location coils 0.267 0.0128 0.0021 6

24 mm from ID 0.256 0.0169 0.0021 48 mm from OD 0.267 0.0181 0.0020 24mmfrom0D O.ln 0.0150 0.0026 6

24 mm from ID 0.174 0.0150 0.0026 48 mm from OD 0.177 0.0157 0.0026 24mm from OD 0.241 0.0092 0.0020 6

24 nun from ID 0.277 0.0163 0.0018 48 nun from OD 0.274 0.0176 0.0019 24mmfrom0D 0.251 0.0111 0.0019 6

24mmfromID 0.286 0.0131 0.0020 48 mm from OD 0.278 0.0138 0.0020 24 mm from OD 0.176 0.0140 0.0023 6

24 mm from ID 0.190 0.0149 0.0024 48 mm from OD 0.198 0.0166 0.0024 24mmfrom0D 0.183 - 0.0136 0.0024 6

24 mm from ID 0.190 0.0139 0.0023 48 mm from OD 0.210 0.0129 0.0025 24mmfrom0D

TABLE 5-3 (continued)

Mn Cr Cu Mo Ni p

Section through large Weldment 'A' Al/1/X 1.157 0.0371 0.341 0.502 1.093 0.010 Al/l/Y 1.249 0.0339 0.310 0.507 1.003 0.010 Al/l/Z 1.176 0.0317 0.266 0.487 1.090 0.011 Section through large Weldmcnt 'B' Bl/2/X 1.249 0.0400 0.235 0.546 1.215 0.012 Bl/2/Y 1.304 0.0383 0.189 0.537 l.010 0.012 Bl/2/Z 1.265 0.0389 0.196 0.540 1.098 0.012 Section through Trepan

'A/SG/A' AISQIA/2/X l.137 0.0401 0.367 0.508 1.154 0.011 A/SG/A/2/Y 1.120 0.0328 0.291 0.498 1.156 0.013 A/SG/A/2/Z l.114 0.0333 0.278 0.498

!.OS9 0.012 Section through Trepant

'A/SG/B' A/SGIB/3/X 1.173 0.0407 0.353 0.515 1.203 0.011 A/SG/B/3/Y 1.102 0.0389 0.233 0.523 1.149 0.012 A/SG/B/3/Z 1.lOS 0.0411 0.237 0.519 1.024 0.011 Section through Trepan

'B/SG/A' B/SG/A/2/X 1.292 0.0412 0.195 0.551 1.272 0.017 B/SG/A/2/Y 1.234 0.0379 0.195 0.550 1.331 0.016 B/SG/A/2/Z 1.246 0.0388 0.206 0.544 1.138 0.016 Section through Trepan

'B/SG/B' B/SG/Bf1JX 1.273 0.0397 0.162 0.541 1.126 0.016 B/SG/B/2/Y 1.237 0.0402 0.208 0.536 1.136 0.016 B/SG/312/Z 1.188 0.0391 0.209 0.532 1.307 0.016 Rows betinning with "A" are Heat No. W5214.

Rows beginning with "B" are Heat No. 34B009.

Si s

0.264 0.0146 0.265 0.0174 0.288 0.0181 0.173 0.0159 0.166 0.0182 0.182 o.01n 0.247 0.0115 0.284 0.0178 0.284 0.0182 0.243 0.0110 0.291 0.0158 0.302 0.0141 0.186 0.0181 0.202 0.0170 0.211 0.0165 0.191 0.0177 0.204-0.0165 0.212 0.0156 v

II of Location coils 0.0023 6

24 mm from ID 0.0022 48 mm from OD 0.0022 24 mm from OD 0.0028 6

24 mm from ID 0.0028 48 mm from OD 0.0028 24 mm from OD 0.0021 6

24mmfromID 0.0020 48 mm from OD 0.0021 24mmfromOD 0.0021 6

24mm from ID 0.0024 48 nun from OD 0.0025 24mmfrom0D 0.0031 6

24mmfromID 0.0027 48 mm from OD 0.0027 24mmfromOD 0.0029 6

24mm from ID 0.0027 48 mm from OD 0.0025 24mmfrom0D

ATTACHMENT NO. 6 Consumers Power Company Palisades Plant Docket 50-255 RESPONSE TO NRC NOVEMBER 30,1994 REQUEST FOR ADDITIONAL INFORMATION REVISION 0 10CFR50.61 SCREENING CRITERION ITEM NO. 6 RESERVED FOR LATER USE

ATTACHMENT NO. 7 Consumers Power Company Palisades Plant Docket 50-255 RESPONSE TO NRC NOVEMBER 30,1994 REQUEST FOR ADDITIONAL INFORMATION REVISION 0 10CFR50.61 SCREENING CRITERION PLAN FOR ADDRESSING WELD MATERIAL TEST RESULTS 1 Page

PROPOSED PLAN FOR ADDRESSING WELD MATERIAL TEST RESULTS It is Consumers Power Company's intention to determine (1) if some type of phenomenon may have influenced the initial material properties of the Palisades steam generator. welds and (2) if material properties can be restored sufficiently to allow for its use in the Palisades reactor vessel surveillance program for determining the response of the reactor vessel material to irradiation. The plan will evolve as we proceed, but is expected to follow this general scenario.

1.

Characterize the weld materials investigating the spatial variation in bulk chemistry and material properties. Detailed composition maps of the copper and nickel levels are being prepared using X-ray microprobe. A hardness survey will also be performed. This information is intended to aid in the selection of locations for test specimens.

2.

Perform a pilot heat treatment program for the purpose of determining the optimum heat treatment required to restore or approach the initial material properties. The program will concentrate on recovery of the upper shelf energy and tensile and hardness properties.

3.

Perform heat treatment on a full complement of Charpy, drop weight, tensile and hardness specimens to determine the amount of recovery of the mechanical properties.

4.

Perform microstructural examination of the "aged" and "regenerated" weld materials for the purpose of determining the soluble copper content, and hence, its expected response to irradiation will be representative. This will be established by microstructure examination of a comparison weld or welds, which is also planned.

Potential candidates include the Palisades surveillance weld or surveillance material from H. B. Robinson 2, Indian Point 2 or Indian Point 3.

Completion of this program by March I, 1995 is essential for addressing the future of the supplemental surveillance program, still planned for implementation during the 1995 refueling outage.

v t e Letter Sequence Request
TAC:M83227, (Approved, Closed)
Initiation Request Acceptance... Administration Questions 30 November 1994 Answers 28 December 1994 Results Approval, Approval, Approval Other: ML18059B177, ML18064A576
MONTHYEAR1994-07-12 [Table View]

ML18064A518

Text

SUMMARY

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

~-======

REFERENCE:

REFERENCE:

REFERENCE:

Navigation menu

Search