ML18044A390

Forwards Documents for Clarification of Info Sent to H Levin on 790828 Re Seismic Design.One Oversize Drawing Encl

ML18044A390
Person / Time
Site:	Palisades
Issue date:	12/27/1979
From:	Marusich R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Chen P Office of Nuclear Reactor Regulation
References
TASK-03-06, TASK-3-6, TASK-RR NUDOCS 8001030743
Download: ML18044A390 (11)

Text

• 1 I.,

consumers

!Plower cimmpanv General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 * (517) 788-0550 December 27, 1979 P. Y. Chen Nuclear Regulatory Commission Phillips Building 7920 Norfolk Avenue Bethesda, MD 20014 Attached is the information you requested in late October concerning clarifica-tion of information sent to Howard Levin August 28, 1979 on seismic design at Palisades.

The information is in two parts.

One is a letter from Bechtel pro-

. viding their responses.

The other was generated by Consumers Power Company.

1.

Response B.6-1, Sh 2 (attached) - What are the units and headings above the numbers on this table?

See Bechtel letter.

2.

Response B.6-1, Sh 3 (attached) - What are the units (or, if dimensionless, the definition) of area, Youngs Modulus and.Moment of Inertia (I)?

See Bechtel letter.

3.

Response B.6-3, Sh 1 (attached)

a.

What are the thermal and seismic movements of anchors E-54 and E-60?

Where in the computer output is this noted? What are the wall and pene-tration movements?

See Bechtel letter.

b.

Is Drawing HBD-8-1 and SK-M-1058 the same?

Yes.

4.

Response B.6-2, Sh i and 2 (attached) - Send a more readable copy.

See Bechtel letter.

5.

Response B.6-1, Sh 2 and B.6-2, Sh 3 - Both. sheets summarize the stress analysis of line EB-10 and B.6-1, Sh 2 shows different results for both EB-10 analyses.

Explain the analyses performed. and the differences between the three sets of results for line EB-10.

See Bechtel letter.

6.

Figure B.6-1

a.

Does,the piping analysis consider the s.ummation of the transient load when RV-2236 relieves coupled with the.OBE loads or are the loads consider-ed separately? Has the transient load been considered? *What does the t\\)

(\\C').

Y\\ ",\\

~-'

. 1L ~ _1'l

• v '

(

sooioso 7¥: ~~t.;> '

2.

"A"; "B" through "G" mean? If it means that these are connection points

.for qtl;ier.piping; was this other piping separately analyzed? If so, how was'. the results of the analysis of this other piping input to the analy-

.sis *of the system shown in Figure B.6-1? 'See Bechtel letter.

b.

What is the weight ahd center of gravity.6f RV-2236?

The valve weighs 6 lbs.

Center of gravity* is unknown but a drawing of the valve is attached with. the parts list identifi,ed fOr making a gues.s at the loca-tion of the center of gravity.

c.

Provide the response spectra used in the analysis?

See Below.

d.

Provide the pipe schedule, material, norm~l pressure and temperature.

The pipe schedule and material is ASTM A-312 or A-376 TP-304 seamless ptp.e schedule 10s.

Normal service is 110 psig and 165 F (data from

,Bechtel Drawing M-25.9).

We have received your note to us on December 7, 1979 transmitting to us a letter

• from EG&G which contained request for additional.information.

With regards to these requests, we require either clarification of these requests in order to adequately respond.or will respond to at a slightly later da,te.

The requests are presented followed* by the proposed action:

1.

Section 5.2 (Page 55) of the. report titled "Seismic Review of Palisades Nuclear Power Plant Unit No. 1, Phase,1 Report" by c.*Y. Liaw discusses the analysis methods used in the "original" piping.analysis.

The plot shown in Figure 1 (attached) was enclosed* in this report and described as being "typical" of the response spectra curves originally used.. It is implied that different curves exist* for different el:evations throughout the plant.

It is necessary to know ~hether the plot shoWn in Figure 1 is the correct plot to be used to.* simµlate the* "original" analysis. *Several different plots may be justified depending.on tpe elevations of the subject piping.

A decision on this point is required before any simulation of the original analyses can be completed.

Response

Different response spectra curves were used through the contain--

ment and auX:iliary building.

These curves were transmitted to Howard Levin on August 28, 1979.

CPCo suggests that EG&G take these curves and match them with the computer analysis-input.. If there are any discrepancies let me know and I will obtain a resolution..

2.. The.. isometrics received for the auxiliary feedwa ter system and some as socia-

• ted data are contained in Figures 2 and 3 ~nd Tables 1 and 2.

As can be seen, in several cases this.information is unusable.

Therefore, it is requested

.that drawings and/or isometrics clearly describing the system configuration

3.

J.

~rid support data be supplied. It is further noted that the aux. feedwater computer output received to date is not usable *unles*s the system of units used by the program is-known.

No information concerning the steam line f~eding the *steam driven pump has been receiveq..

Specific* information re-

. qui.red would be as listed in.Items 1 and 3 through 10 on the enclosed form

."Piping System Engineering_ Data" 0Page 8-).

I

Response

The units for the Tables and a readable copy of the isometric are provided in the attached Bechtel memo.

When we sent the information to Howard Levin it was intended that the originals be sent to the analyst in order to avoid requests like the above.

EG&G requests information concerning the steam line going to the steam driveri' pump.

The inf°om.ation 'requested will. be transmitted at a later date.

. 3. Further information regarding the type and co~figuration of supports on the RHR piping is necessary for accurate modeling.~

Response

Exactly what information does EG&G_ require? What portion of the piping are they reviewing? What ~o they.already know -concerning that portion of the piping?

• 4.

More complete information regarding the supports on the component cooling piping is neeQ..ed.

The isometric indicates spring hangers for which no further

. information is given.

Complete data (type, size, configura_tion, etc.).for all suppo~ts wo~ld be desirable.

Response: ' Exactly what information. does EG&G *require? What portion of the piping are they reviewing? What do they alr~~dy know concerning that portion of the piping?

5.

A piping isometric and 'certain support (hanger) drawings were the only data provided for the chemical volume control.* pip_ing system (typical l" -4" field run piping). 'There are several "continuation"* notes on the i.sometric for which no further information is given.

The configuration of the piping and

.- supports on these "continued".lines must be 'known to develop a sufficiently accurate model. *No information was provided concerning the.*.transient loading from R.V. 2236 discharges.

Thus, the inforrlia.tion noted* in Items 1,- 3 through 7, and 9 and 10 of the data list on Page *8 -0,11 be needed ~o complete the

model~ng and analysis of the eve piping.

Respon-se:

All information except that concerning a request for i,:iformatiori noted in Items 1, 3,' 4, 5, 6, 7, 9 and 10 of the data list on Page 8 is provided in the Bech~el letter.* The other information.will be provided* later.

I 6a. On Sheet 1 of Appendix B.6-3, from.Node 250 to Node 285, the line is indicated

• to*be HB-24-16".

However, on Sheet 11 of Appendix B.6-3, the computer print out is 10 '3/4" ""line.' Whieh one is_:*correcy based 'on the as-built?

4.

6b. )Information on Sheet 5 of.Appendix B.6.-3 is not clear.

I Response!, This information will b.e *provided at a later date.

~~~/11_~

RMMaru'sich.

Senior Engineer Nuclear Activities MARU 68-79 j

Bechtel Associates Profession~! Corporation 777 East Eisenhower Parkway Ann Arbor, Michigan Mail Address: P.O. Box 1000, Ann Arbor, Michigan-48106 Mr. R. M. Marusich Nuclear Activities Department Consumers Power Company 1945 w. Parnall Road Jackson, MI

• 49201

Dear Mr. Marusich:

December 11, 1979 Consumers Power Company Palisades Plant Bechter Job 12447-036 RESPONSES TO NRC SEISMIC QUESTIONS File: *0275 w/a 79.-12447/.036-04

j.

~ '

l

.'l*

i.

In response *to your letter of October 30,:<1979, MARU* 55-79, the following information is provided to'¢lari~y.in~ormation pr~viously provided *to the NRC on the ~eismic resistance capability of the Palisades Plant.

1.

The units and headings above the* numbers on the table provided'as Appendix B.6-1, sheet 2~ are as follows (in order from left to right).

a.

b.

c.

d.

e.

f.

g.

h.

i.

j.

k.

1.

Class Outside diameter (in)

Thickness (in)

Inside diameter divided by 12 (in)

Thickness divided by 12 (in)

Weight of steel (lb/ft)

Weight of water (lb/ft)

Weight of insulation (lb/ft)

Total weight (lb/ft) 2 Flow area (in2 )

Metal area (in )

Pressure (psig)

RF f' r: "'t=' D DECl4 797g N.fi..&J., u.t:.P.

I J,.

• Bechtel Associates Profes.sion~I Corporation

. Mr. Marusich December 11, 1979 Page 2.

3.

• 4.

s,.

6.

m.*

.n.

o.*

p.

q.

r *.

s.

t.

Longitudinal pressure stress (psi)

Temperature. ( ° F)

• Material.

Seismic.stress (psi)

Sum~ation of primary ~tresses d~~ to OBE (psi)

All6wable primary stress (psi)

Summation of primary stresses due to SSE (p.si)

Yield stress (psi)

On sheet 3 Of Appehdix B.6-1, the units of ar~a; You2gs 4

Modulus, Moment of Inertia, and weight are ft,.K/ft, ft,

and K/ft, respectively.

(K : 1000 lbs.)

Because the seismic movements.of anchors are ~egligible, no seismic anchor*movem~nt~ were used as inputs in the analyses performed for the Palisades *Plant *.. No thermal anchor novements were use~ in £his sei~mic a~alysis (Appendix B~6-3).

A separate the~mal analysis.would have

been performed which considers the thermal movement of these anchors~

Thermal and seismic ~ovements of walls and penetiations were felt.to be negligible and were not input into seismic and t,herm~.i *analyses for the Palisades Plant.

A more* ieadable co~y of Appendix B.ij~2, she~t l~ is enclosed~ Sheet 2 of Appendix B.6-2 is an in~dvertent duplicate of sheet 1.

The three stress analyses performed. on line }!\\B-10 as sum-

. marized in Appendix B.6...,1, sheet i, :and Appendix B.6-2, sheet 3~ ~re for three diffeient s~6tions.of*line EB-10.

The two."stress analyses *summarized on shee.t.. 2 of,Appendix B.6~1 are for th~ 4". and 6~ di~mete~ sections of* the part 6f line EB-10 showri on sheet 1 of.Appendix B.6~1~

The summary of the stress analysis performed o.n 'the section

.of line* EB-10 from the point where. it emerges from.under-ground to the connections to lin*e EB-14 (see sheet l of Appendix B.6-2) is given* on,,,sheet. 3:*of Appendix B.6-2.*

Due.to the low p~essure of* the boric acid system pi~ing in ~igure B.6-1,* transient loads wo~ld have been considered to be negligible and not used in the piping analysis.

The letter designations in Figure B. 6-1 do represent, connec-tion ~oints.for othei piping which ~as separately analyz~d.

Because this.l~.to.4" diame~er field run pipirig was

• rigidly des;igned,.the~ eftec.ts.,. of.one pipe.on"another adjoining pipe would' 'not' haye.-;t>>~en ~~on~ i'der,ed **. 'sim~i'arly' seismic re.s,ponse spectra :_woiil9 riot,/have' b~e'.n used.in.-..

' ~ * *,

~

\\'

. -~

' " r

Bechtel Associates Professional Corporation Mr. Marus ich December 111 1979 Page analyzing this rigidly de~igned p1p1ng with freq~enties

. over 10* Hz.

Instead, the *analysis would have conserva-tively assumed" *the. maximum seismic acceleration due to an OBE.

DMV/PKS/CASO/lac Enclosure

'* i*

,. ~~r:

_,~. ~. *:

~

Very truly yours, C'. 4, :JI. tZ-r ~.

C. A. St. Onge Project Engineer

• t,'

• *~

• \\

- _t- ~*

~..

.(

j..,

~I

'*\\'

I,

I I.

4.i >

_L

~

.v

. 'F*

I'.

.. \\

,,..._'-7.*

f *

' )'

\\.

\\

/.

..ric \\.

-* y_-* *:

r-.

l Q '-.*

. \\

-~

~,,--.,.

! *~

• ~

,,. -/y***..

+.

5'. (

'*~

g\\,

~J,~..

• on

-~.. c:.oc:y...,...,.uw= *.. *.-..... tl.. -\\.:>.m ~241'."'*J'*-*--~.f.*

_:. ~:***.-

><:".*'!-~-.

. C:<.:.

" i' I

i

. /

.. I

• /

i: -c..

i I

-.. t.,,.

j I '

I l I

\\&) -*.

-~

\\ 'l.

• • ~

~,J

.. '.. ::,.*i'**: *.....

--*~_.,

-~* -K I

~-

(\\

,- I'

,r

• • -~~,-.

,/ c '.:

~ '-'

. *...*. *.~

.. E~(o-2. (~

1')..

• ***--~*

• * * ****..... r-:...**.;;.:

0;:.. ~_:. I:

/LJ~~'I.'\\.

~*... * *.* --~---.. *:_*--~-~ _l.r--.-.* _"'}

• C11tc*.

N~ st3 * *.*

• B E C H T E L. *c 0 M P A N Y PALISADES PLANT CONSUMERS POWER COMPANY AUX. F.W.. PUMP D\\5CH,L.RGE ISOME.TRlC-JOI l"o..

5935 SK-M-370 HY.

A f

• 1 i at. I I I II I

J i

's I

I I I

lllnU JO. -- 099.

• uo. n[!!i!122n. 22)9, 2240 c

25 18 17

~~~L-28 26 19 16 I I 21 2

22 10 I I 8

9 7

24 20 6

5 4

14

. I

8ASI S OF IELCCT 10th FIRC.:':' ______

1~--;:-~~'""':"°i"------f------.:-Ji-------.J-----'-

A T-.

• 1... "'E-.:.

ACCCS$0AllS1 CA, YDlt>Olll~-----1-..lg~~'_:;:.-J::::;:::;::::;::::::=.t:=::.=.:=::=:J:=====-=:.::::l:==:

PIO ca ITCM) NO.

.. ~

/;'* : !&_;

7G FOREICN pat NT NO. :'.'.::::--;r------+-------1f------+------~--_;~

INS111, STO, llHOCNC.._-f"-1.:-;.:'-;::'-:--t-------f-------1-....:.-----I'----~"'

r---------------------------

PRESSURE SAFETY (RELIF.F) VALVE DATA SHEET.

TAe llO.

~ on.

PARRIS *N81N*** 8 CORPORATION

~

~---...........

~ YA&.-

ltlnlt£ff"; r1.;.r- ~9s6""' z..

T\\'PI 11na ORIPIC&

Paasums ""

t*LST OUTUT UP UOC trT

~

~~--

DATE.f*.,,

IMHT llO.iOFL