ML20072L351

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Pump & Valve Operability Summary
ML20072L351
Person / Time
Site: Byron, 05000000
Issue date: 06/10/1983
From: Kamenic M, Snider J
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20072L320 List:
References
CAE-05-01, CAE-5-1, NUDOCS 8307130325
Download: ML20072L351 (40)
v • d • e


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PVORT Draft SER Generic Item 3 r

Aging considerations have been incorporated into the qualification

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program for Class lE electrical equipment and i nstrumentation in plant harsh environment areas.

Qualification testing complies with the

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. sequential testing requirements of IEEE-323-1974.

The description of this program has been supplied to the NRC.

Evidence showing compliance with the sequential test requirements has been provided during the EQ audit.

, A separate program for the environnental qualification of mechanical equipment has not been required by Byron.

However, Commonwealth Edison has' developed a program to insure that aging of mechanical components will not adversely affect the availability of safety related mechanical equipment._ This program incorporates maintenance and surveillance and is further discussed in SQRT Generic Item #6.

s i

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.3120b.

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PV0RT Draft SER Generic Item 4 At this time, over 90% of the system pre-operational test procedures have been writter: and approved for testing at Byron.

All active pumps are included in the pre-operational test program and the Preservice Testing Program Plan for Pumps.

Parameters measured include inlet pressure, differential pressure, flowrate, vibration, lubrication level, and bearing temperature where appropriate.

Pump performance is evaluated against test acceptance criteria developed from system Design Criteria and FSAR Safety Limits.

The pre-operational tests and the Preservice Testing Program will demonstrate that the active pumps will function as installed and perform their required safety function within the overall system design.

Virtually all active valves are stroked to demonstrate their operability during system pre-operational testing and in the Preservice Testing Program Plan for Valves.

Tests on valves include seat leakage tests, full stroke tests, check valve exercise tests, relief valve setpoint checks, fail safe tests, position indication checks, and part stroke tests.

In addition, valves are timed where required, to verify movement to their safe position within prescribed time limits.

Beyond system pre-operational testing and preservice testing of pumps and valves, inservice testing of pumps and valves as required by ASME Section XI is performed on a periodic basis to demonstrate the continued operability of active pumps and valves.

A complete description of the Preservice/ Inservice Testing Program Plan for Pumps and Valves is included in the November 4, 1982 letter from T.R. Tramm to H.R. Denton.

3120b

i PVORT Draft SER Generic Item 5 i

Commonwealth Edison record keeping systems are maintained in accordance with 10CFR50 Appendix B.

A filing system has been established to enable station personnel to retrieve qualification documentation when needed.

For Non-NSSS equipment, engineering documentation (seismic qualification reports, etc.) is transferred from Sargent & Lundy files to the station.

The qualification documentation is organized by Sargent & Lundy procurement specification number and is filed accordingly by the central files office of the station.

Documentation is retrievable by the S&L procurement specification number and the equipment piece number.

The subject documentation is currently being transferred to the station.

With regard to NSSS equipment, qualification documentation is maintained in a central file location by Westinghouse in Pittsburgh.

This documentation is retrievable by valve location number for valves, and SPIN and project number for pumps and all other mechanical equipment.

Complete qualification documentation for NSSS Class lE equipment is retrievable by reference to WCAF-8587 and WCAP-8687.

4 i

l i-3120b E

0 PVORT Draft SER Generic Item 6 4

Pump and Valve Operability Assurance Program As described-in Section 3.9.3.2 of the Byron /Braidwood FSAR, an operability assurance program has been established to assure active pumps and valves will perform their intended safety function during the life of the plant under postulated plant conditions.

Active mechanical equipment is that Seismic Category I equipment which must perform a mechanical motion during the course of shutting down the plant or mitigating the consequences of an accident.

Active pumps and valves are listed in Tables 3.9-15 and 3.9-16 of the FSAR, respectively.

P Testing, analysis, a combination of testing and analysis, or previous operating history are acceptable design methods for assuring operability

)

of components for all expected combinations of loadings.

Vendor in-shop tests or analyses, pre-operational tests, hot functional tests, static deflection tests, and periodic inservice surveillance form the basis for this program.

In the case of vendor in-shop tests or analyses, acceptance criteria for operability are provided in the component procurement specification.

.The procurement specification specifies seismic qualificatien criteria, pipe reactica end loads (including i-weight, thermal and seismic loads), environmental ~ conditions, design

-transients, system operation requirements, special test requirements, and other considerations which are important in the overall design of the components.

Stress limits are listed in FSAR Table 3.9-10 for active valves and Table 3.9-8 for active pumps.

The note for these tables reaos "The stress limits specified for active pumps (and valves) are more restrictive than ASME III limits to provide assurance that operability will not be impaired for any? operating condition."

Verification that the vender has complied with all design requirements set forth in the component procurement specification assures operability of the component for its intended safety function.

Conformance to current seismic qualification and environmental qualification parameters

-is verified by independent programs.

The philosophy employed by CECO reflects that of Paragraph-1.a.(10) of Standard Review Plan 3.10, Revision 2.

This paragraph states that if dynamic testing of a pump or valve assembly proves to be impractical,

-static testing of the assembly is acceptable provided nozzle loads and dynamic amplification effects are addressed and'the component-is operated

during and after the applied loads.

For:large size and high' pressure valves it is often impractical, if not. impossible, to perform dynamic, full flow testing.

Test facilities do not have adequate capacities for j

-the.large. high pressure valves.

For those valves for which dynamic full flow testing is possible,.the additional benefits. gained over static testing do not justify the cost.

Byron /Braidwood Station personnel will develop and. implement-

{

preoperational and hot functional test procedures prior to plant

~

~

t operation. -Inservice-Surveillance conforming-to ASME Code, Section XI-T

. requirements will=be conducted periodically to assess operational L

readiness of-pumps and: valves during their service life.

,3120b

=

-~

0 PVORT Draft SER Generic Item 6

'All vendors supplying active components maintain an approved Quality Assurance Program commensurate with the requirements set forth in 10CFR50, Appendix B.

The vendor's Quality Assurance Program provides for effective implementation of procedures, instructions, or reviews to ensure that all testing and analyses are-accomplished in compliance with the specification and applicable codes and standards, Pump Operability Active pumps are qualified for operability by first being subjected to vendor in-shop tests as required by the component procurement specification.

The in-shop mechanical tests include hydrostatic tests of pressure retaining parts and pump performance tests.

Hydrostatic test procedures and reports conform to ASME Code Section III requirements.

Performance tests are completed in accordance with Hydraulic Institute Standards.

Generally, the pumps are run at design flow and head, shutoff head, 120%

of design flow, and two intermediate points to verify performance characteristics.

NPSH requirements are determined by test for each pump from 0 to 120% of design flow.

Verification that running clearances are adequate and that vibration and noise levels are within acceptable limits is recorded during performance tests.

All Class lE equipment associated with active pumps meet the qualification requirements of IEEE 323-1974.

Valve Operability Active valves are qualified for operability by first being subjected to vendor in-shop tests as required by the component procurement specification and then in many~ cases through static deflection tests..

The in-shop mechanical ~ tests include shell hydrostatic or pneumatic tests to ASME Code Section III requirements, backseat and main. seat leakage tests,; disc hydrostatic tests, and functional tests to verify that the valve will open'and close within the specified time limits when subjected to the design differential pressure.

Wnere functional tests to verify opening and closing capabilities are not practical, analysis is used to assure operability.

Where required, impact testing is performed in accordance with ASME Code Section III.

The static. deflection test that is performed involves applying a load or loads equivalent to the resultant of the three-dimensional SSE. accelerations to the center of=

gravity of the_ assembly extended structure.

While in the deflection position, the valves are cycled to show'that any internal rubbing or

-bending will not occur to-the point that the1 valve is not able to respond upon demand and open or close within:the specified time.

As before, '

during:in-shop mechanical tests, the maximum differential pressure to y

which the' valve is designed-is applied.

3120b Sir

N PV0RT Draft SER Generic Item 6 Valve Operability (Continued)

In developing the methodology for performing static deflection tests, the need to apply nozzle loads was evaluated and determined not to be necessary.

The basis for excluding nozzle loads is that the valve body is designed to requirements which are more conservative than requirements for attached piping.

This would result in yielding of the pipe rather than the valve.

Also assurance that deformation due to nozzle loads will not occur is gained by specifying maximum nozzle loads to the piping designer.

The static deflection testing performed under the operability assurance program is in many ways more severe than the dynamic testing addressed by SRP 3.10.

Since the static load is applied at or above the extended structure center of gravity, the resulting loads, moments, and deflections are greater than if the loading was distributed.

This static testing causes deflections and any associated internal rubbing to be continuous as opposed to intermittent deflections that would result from dynamic testing.

At no point is there any relaxation that would aid operability.

For valves designed to be rigid, dynamit amplification effects do not affect the loads applied to the valve during the static deflection test or the qualification acceleration level.

In those ceses where valves are not rigid, dynamic amplification effects are taken.into account in calculating the loads to be used in the static deflection test and the qualification acceleration level for the valve.

A further discussion of loads and accelerations used in the static deflection. tests is provided in FSAR Section 3.9.3.2.

Active valves are seismically qualified by tests or analyses per the requirements of IEEE 344-1975.

All Class lE equipment associated with active valves meets the sequential testing requirement of IEEE 323-1974.

For motor operated valves, analyses are performed to verify compatability of. operator torque output versus valve torque requirements.

In summary,.in-shop mechanical, cold hydro and hot functional tests assure that pumps and valves will operate under normal conditions The static deflection tests and combination of test and analysis assure that active pumps and valves will operate under all intended service conditions.

5 3120b

e SARGENT&LUNDY 005EiM l

INTER-OFFICE MEMORANDUM

'i-N[

From.

T.

R.

Eisenbart - 24, x2172 Date December 27, 1982 I'

Project No. 4391/2 3 46834t_

j' Dept JDiv. E l e c t ri c a lf_Eroic c.t_EDSinc e r i n g Spec. No.

F/L-2819 l

File No.

4391/25C 4

Page No.

1 of 1 I

t j

Client Commonwealth. Edison Co-Sin.

ByIon/Braidwood Unit 1 & 2 1

l Suyect _._ Oua.lificittion_Dnc.umentati_ OIL _for Station Batteries i

i i

To:

K.

Ad,lon - 30 1

\\

l Attached find the Qualification Documentation submitted by Gould Incorporated for the 125VDC Station Batteries supplied for Byron /

Braidwood.

(Spec. F/L-2819) i A

i

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I f

TRE:sh j

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f e

4

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s

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wr

+, -

-v-ws-

% ww mw-

-- n, r,v, w m w r,o v e~.<,- e m wm ---> n, a w ro ww,,

,~+~w eo,~e~~ ~ w n n me,-,.w m m,wae sw w e m >w a m,, m,- ~ m -- e m. e,-,w -~w-,-.~-----wows-,wws

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5-

?

Oould inc.. ladustrie4 Battery Division M*A Cabot Boulevard West. Langhotee. Pa 241 e

Teiar.non, f 215, 757 0555

{

h'h

]

lElectrorucs & Elecinc.

CADLt.GOULNATBAT L ANGHORNE, PA,f._ -_ _~ -"-

I Prwsuc1:.

- Twx;coulo t AHtt sto w 20se coutoLA40Sto w-2m December 14, 1982 i

f f

t Sargent and Lundy Engineers 55 East Monroe Street Chicago, IL 60603 T. C 3. d e p.eh Attn:

say Re: Byron /Braidwood Sargent and Lundy Spec. No. Y-2819 Commonwealth Edison P.O. No. 194757, 758 GNB Batteries Inc./Could S.O. KE 5145, 5147, 5149, 5186 Subj et.t : Environmental Qualification Report (EQR)

Lead Acid Storage Batteries IEEE 344/323/535 C;te&<7 l

Dear Mr. p. -

Enclosed please find one (1) copy of our EQR and one (1) copy of Wyle k

Laboratories' Test Report, Volumes I and II to support the qualification of our NCX Batteries for the Byron /Braidwood Stations. Additianal copies will be made available upon notice of approval.

Ver truly yours, llovard Rubin Product Manager Utility Batteries and Chargers 4

IIR:dh t.

I cc:

Mr. J. Murray - BBEL 10#5413 I

i l

i-i 4

4

+-k~---

e.-,p p

9,y

-,.,,4-ym, a-ryc,,,

,,,,-m

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SJRGENT Q LUNDY 3

25 1962

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' ; n,pa im inau m.f[~O

~

9 JNTER OFFICE MEMORANDUM -

,g. j l

- - -- 1 j _____.

[';

From G.

K.

Roy X2713 Date January 20, 1983

(_)

Project No.

4391,2/4683.4-00 Dept./Div.

Mechanical / Component Oualification Spec. No.

F/L-2819 File No.

COD-005567 1 Of 1 Page No.

Client CECO Stn.

Byron /Braidwood Unit 1&2 Subject Review of Seismic 4.eport for Storage Battery & Battery Racks (l&2DC01EA,EB; 1&2DC02EA,EB)

..his file has been microfilmed &

To:

J.

S.

Paniaguas

- 30 r;turnSd 10 the Project Eng'r;cc.

CC:

W.

C. Cleff

- 22 K.

L. Adlon

- 30 T.

Eisenbart

- 24 COD File

- 30 h

y

~

..a w A.. e. nu..,wap-.a..T. i %; Rf46.l;4 .~,.,,_..,,wm n.- 7 r

: ::m 3.

-Input Motion ' :a'J , e.- (;.~.., Single-Axis ,. ~ m Multi-Axist. _- -

pm

, a ; ta=o r w n=n m. s ,~ ~- m-ge ng-m -. .- w.n aw D Other: Comments: -. ~ -

..,,,. - c ; = }2
;.%,',.,.

4. Test Method ~ ' -EN UI $ N-p.r"L:. a Sine dwell (single frequency),: ~

  • 1r "a)~ Frequency range i

b) ~ Dwells at: ~ -~~ ~ ~ (Hz) c) Number of tests in each orientation: Upset / Service Emergency Service Level C Level B Faul.te..d....S_.ervic_e Level D s ~

W ;M'F-niur-

- ~ - h-d) Duration:~~ - .r -..4.._ e) Input acceleration in each direction: Upset / Service Level B H ~ m"U'hk w I ' .V i Emergency ervice Level C ,,.A gcA: Faulted Service Level D H' ~ fsM2 Y g f) How is cross coupling and modal participatioh accounted for7 ~ -...,. n i u, n,..., n N m), -...-i.Defid_:.1*. -.. ""Ef M:' v v he+EM9_o_ W 7 ~ 4.A, Ig - ..l,g;:,.,gyggng y -sg - =g + ~ ~ _. g b Mali - C, o 0 Sine beat (single frequency): n. ~ "< a) w ar,. p.% m g p.. - m --Frequency range:.. -,. - -, _ s....._.w .r. "~~r*=~ ~- ~ uo b)'. Number of tests'"in"each 'rientationt WWMC' o 0 >. c m icru M E s37H w;+ p;'-* ~~' u -- -.,,Emersainf a~r~v~ic=e;.I4 vel C O G s oc - Upset / Service Level B Faulted'. Service Level D 1 =. d FOR OFFICE USE.ONLY - NOT TO BE $M ~M D-2.4' SENT OUTSIDE OF SARGENT &.LUNDY;

Pap T T 4 af ' 9

-... -. ~..... hk* M4, % 'd Me. h. '.O'. .e m a. we.. d5 y h h7 K. - A" M - ~s m... e, u e, m s., m m .,7,, I,, i'.* ' ' .: ' 1Q Att....a. g38f/ j 2 h6h,. 8-(M CQD 00556/ REv.: op FILE NO.: PROJECT NO.: c) Number of beats: , Number of cycles per beat: j d) Beats at: (Hz) e) Input acceleration in each direction: Upset / Service Level B.2.. - .H V 2 4 .~.

6. Emergency Service Level C

,, Hp,'d. , y%.lb-2 Service Idtvel.D - V 4 y F n-t O O P ulted c :s a.a.%n. . W + - a - - m u t a }k-e, .;,-) y._ ew mea newswesms:s m. z m g)._9,,,. is cross ~ coupling and'uodaUparticipation'accodrite'd for? v ~ ...x... @ Random motion (multi frequency): ~~~~~~ ~ ~ i a) Frequency range: I MZ) 40NOO552 .2-- .:--te.m r -- b) Number of tests in each orientation: -it,f3l f.5 Upset / Service Level B g Emergency' rvice' Level C f Faulted

  1. ..S_er,vice3 Level D c) Duration:

M 8de. S. 21 c2 ca r.11:NNU$20 4 d) Does Test Response Spectra (TRS) envelop Utha g t.g g Required Response Spectra (RRS)?.9a.e q w u o ... r .m g.m Yes - Provide RRS and TRS as attacbeent s No - Explain: 5-E ^' ~.~m-n.. - ~ ~ - 5. Dynamic G.aracteristics S-k b 1du - -~.. @"Naturalfrequencies: ( Q [ ~ H['E35.[* k H[Fr g. g g y 55.)g,)f3 2 Estural frequencies not determined. .

  • w m-u

..-m. .. _ _. _ __. m._ __ u_. ~.....,.m. sa.w%.e .4 m -. _.. so .- --- m g,_ . ~.a .6. Additional Loads =..m, -.. w..1u%w +w %a r.... + w ~- - w w. - ~ ~ - .c n g g, eAre.ss.ormal operating loads con. side. rod. t d...,.5iagagc=;a.i.ws_ _., _ e =~ PE z... n o> s._s,,,a 4 5v .v....c .. m 4 Not applicable. E. O!! Ci~.H&.2f!IcPW#E. e to g. n ,.c c::ne:n w ..Yes N': im1 %IOM5:14LhEEh.T y t u 3 m. Aw aw, s o No - explain: - - - " ' " " ^:" - 2,3 ' ~~.=,t.?t.h t.. X..: w_ r o= l

b. ss 7-

.m.. 'i.M. i. "..<. _. / A V.. &., 4.... U.. ' " ' ^ " * ~ ~ ~~ Tr.O. ~ - ..OFF I CE.USE.ONt.Y,. . NOT;.TO ; BE - ggg . W -CQD-2.4 FOR SENT ' OUTS I DE - OF "S ARGENT -t.;UNOY- 'Tage ~ 5. og 9-s - M % :

3. q_m

.d. U $. E', $5 d((U..

  • w-

.g I g\\ N5 I D gm.- i ~ " ,,gv--y 1 +mnm* $ l PROJECT NO.: M'}lj2-h83J4 - St> FILE NO.: CQD-005667 REV. : pp ^ 7. Monitoring a) Is the component functionally monitored? Q7es O No O Not applicable ~ b) Is component's operability verified? Oves O No O Not applicable 8. Does the test meet the requirements of IEEE 344 1911? QYes O No-explain: G. QUALIFICATION BY ANALYSIS 1. 'fype of Analysis @ Static Analysis @ Simplified Dynamic Analysis O Modal Analysis 0 Time History Analysis N.J O Other: 2. Analytical Model O Finite Element Other: 3. Method of Analysis O Computer-Aiaea Caiculation 2 a) Programs used: Y

  • Y b) Have the programs been validated?

.n .S 8 Oyes No @ Hand Calculation e; 2& FOR OFFICE USE ONLY - NOT TO BE WGEMMM wpu O -- P88e 6 Of 9 SENT OUTSIDE OF SARGENT f, LUNDY .m ,.3 PROJECT NO.: @G/ 6$3fg-00 FILE NO.: CQD- 005567 RE'J. : SD 7 u 4. Operating Loads Are the operating loads considered in the analysis? Not applicable 9 Yes O No - explain: 5 Static / Simplified Dynamic Analysis a) Acceleration coefficients: Upset / Service Level B H f.? f ,H /* 7I 2 ,V 3U Emergene ervice Level C H

1. @

,H 2.@

6. @

,V Faulted Service Level D 1 2 b) Are dynamic loads applied in the horizontal and vertical directions simultaneously? @Yes O No-explain: (O ' ) 6. Hodal Analysis a) Identify Response Spectra used; b) Damping factor used: c) Number of significant modes considered: d) Natural period / frequency of each: e) Method of combining modal responses: Nc Absolute Sum 3h Square root of sum of the squares (SRSS) 1 nm l Ae O in compliance with NRC Regulatory Cuide 1.92, Rev. . Date l g, 4g other: Ib E :: ea i b)' FOR OFFICE USE ONLY - NOT TO BE SARGENT&LUNDY HAs-coo-2.4 SENT OUTSIDE OF SARGENT & LUNDY Page 7 of 9 P FILE NO.: CQD- 009567 REV.: Op PROJECT NO.: gy/j fg g.pp O 7. Time History Analysis 8. Results

p,.-

4.? a) Stress evaluation at critical locations: LOAD DYNAMIC TOTAL ALLOWABLE LOCATION COMBINATION STRESS STRESS STRES,S PSt 951 M M '$ V De4M M 23943 A37&D ts~ ~ case) cors) O M9nMs D L t n- [2.132 AO vFO / I O f- "Y A; b~ 8ie N T. xo Ea FOR OFFICE USE ONLY - NOT TO BE W G M & M OY FM -CQD-2.4 O SENT OUTSIDE OF SARGENT & LUNDY Page 8 of 9 t. rs f$/j @3 FILE NO.: CQD- 005567 REV.: Cp PROJECT NO.: i O Deflection evaluatinn at critical locations (Active Components only): b) s CALCULATED ALLOWABLE LOCATION DEFLECTION DEFLECTION +.. i-H. COMMENTS i m- ,nana m raa a w! s a a k es acs was a m'aj N W. 8 M 2 7 O 4 c; 0 b8 3'3 e i E s e a FOR OFFICE USE ONLY - NOT TO BE WM MM CQNd O SENT OUTSIDE OF SARGENT L LUNDY p.g, 9 og 9 P. r --w-----g,...----. ,,,-nn-...,,, ,,~,,,,,~w--...m..,,-~,,-a-- ..+--,-,,,w-r-- - _ = . ~ _.-- .. _= Legend }** 1'

  • IRS Page No. III-434 O Byron /Braidwood RRS Report No. 44681-2

( FULL SCALE SHOCK SPECTRUM (g Peek) Byron /Braidwood Station Commonwealth Edison Co DAMPING E 100 - se e a .my f-1 I al I T ITy v g i e 4 n. u7 M S I I I r I I E E I T I I I I g ' l l e f + t. l. l I i i 11 4 eae it. 1I LE RAE E E A All ilj l t s r i I e 3 I e I I ' ]Il til! 54.t t 89 eN' WWW W YF d WEA 981' t #48 4

  • e i

] e ? e a j, I u urv s r-uv e. 8 't 4 t y - - : = 6 .m um 9. ~' 2 ~ ~, k _._ _L 2 4 is 9 l

~

a m m F y f 1 'lC I E i m. m r. I \\- lc,, t n 1 .n, . _. ia f n i 6 a i i ti Ite e 1 i ! : =U +Li.iI ii4! t il e i R i ia4s seie a. i i i _y I, f ~4 i m i i + 1 \\ t-I l'i I .,1 I I a i .I i i I e e = N I . i i r n 8 I I ~ a i t 5. f '. - ' u I I 1 g .g s: s ~~ 4 e - [; h ^ f f i r, m,..' O ' ~ E_3 :L.___ I I I E E I >h I' I I .I I 1 l I I I E I e u y E I a i r a v 1. I i t a w i x av r I ! ~ I I' L i

  • I'

.11 i 5

  • II r t r

'I i u u a u yi n 1, [ d ' Ii I' li I-3 I I I+ 'l-1 $ 1 IlE I 1 rIi 4.[, r g lCC s a . e e a e o ie a a . e e r e e se - e ... r e e ie i -.,. _. _.. _.. Frequency 04rl..=-==rcW3c4se emir'7.r- - . 1000 1 n 10 m m. ~- - ,ee< myr-m_.,.. .-.w..,.. -, _ .--,m.. d . _~ Fig. 8.1 mm Lacanoes ps). (, g . _.n._7_~_ i gag gg r --.. -.-. _ w = = - I Comparison of TRS vs RRS Vertical OBE

r-O~* NN-

~ G-- Front-to-Back/ Vertical 21 Damp / -ing ?- 9 ~ ' .s q q g 1U ...,r p g*~ee wnmmw -. -.-- .,, ug s. ,3 s + s, - rw ~ $A

    • Li

. -, I.w<, mm m$wa sm'a 1e:.w - ,a, e .... w .= .= Lege.nd TRS Fage No. III-4'29 Report No. 44681-2 O Byron /Braidwood RRS FULL SCALE SHCCK SPECTRUM (g Peak 3 Byron /Braidwood Station Commonwealth Edison Co. DAMPtNG 100,. r s ] e l 6 1 F e y; ;3_ O s - - ~, 9 I 5 7 ' I I I i i. 3 i e ] EI A E t 7, E .A E I< 5 I8 I !!I i 1 l I 3 'II. 3, E I I 3 I 10

  • e S

I y . 1 ,I s.E 1 I I, a 4 k 4 S 3 i 4 O \\- v f 3, G_^ ~ r ~ ~ .1 I I I I I " i f*. !1 I M8445 l o, I i'li 1 I I T E,I I T i i w in i n, r .y 4 i,,.,,, ..f.... .. i.,. e y ,I I I F I Y y I 1 L, ,I ,I = t! e g e. 4 _MD MM EIE EE!!!NHEE!! IE E EEW seem .m r

=ss====

_=

=

i

===- i,

== .--_____==: s

==.

==.

===_ 4 -W 37 I -ma..

i.-

1. i ,, e. ,,,,,m,, r I, ,,, i, n e ..m.,., ,.o ,n. s a + s + e s ie .a. ,s.s.......A.ew a .... r.... 1 ~ ' " n -- - -- rtu.._ 1000 10... Frequency 0izh . ;._Ea _,_ ~-- .n _2 ( SPECNEN LOCATION NO. Fig. 8.2 1 ~<_ b .n AXIS TEST RUN NO. - Comparison of TRS vs RRS Horizontal OBE . Cry =q=r ; Front-to-Back/ Vertical 2% Damping ~ + - - - " - - - - - P ~%r s 4 Y me e A w + 1. 6 ~ .- N ?e.l k f

  • 4 5

A e4he a.. -. - -.- n. -~- .-..--.-~..-----,--a n 1

Legend Page No. III-458 Report No. 44681-2

  • TRS FULL SCALE SHOCK SPECTRUM Ig PeakJ 0 Byron /Braidwood RRS i

Byron /Braidwood Station 1.00 10 C 100 Q im Commonwealth Edison Co. DAMPING d

100, i

? i i e e 4 a -3 =a e i i I - f 1 I I l - l 1 t i 1 3 I I I 3 10 '; 6 I I s 4 7 e e a L' + C. e j 1 S 8 T q 3-k _ f ..r a 1 - ^ i o- .. t i i i i1 i I i 1 I. -1 I' V! i i 1 i g / 2 1 I" S i 3; 8 =. s a. e EE-l i 1 1 it I { l _{) 9 g g, g g <i i. ,s a s <s s o e e.e a a e s s s e ene s s s s e u..e 7 1 10 100 1000 Frsquency (Hz) SPECIMEN ~/ LOCATION NO. S Fig. 8.3 b TEST RUN NO. I AXIS Comparison of TRS vs RRS Vertical OBE Side-to-Side / Vertical 2% Damping .? e ng. ,s---- --,--g ,r,,- - - - - -m ,y---.ye- -,e,w

  • - ~ -

I Legend Page No. III-453 TRS Report No. 44681-2 I.. FULL SCALE SHOCK SPECTRUM Ig PeaW G Byron /Braidwood RRS s Byron /Braidwood Station 1.00 10 0 100k 10CCD Commonwealth Edison Cc. h DAMPING 10Q.. 8 ? I O -a._- x f e- __-A--- 6 ~ 4 .__.my_..-_--_., a b 9 r I a 1 i t 1 I e I i i t J 10,, i-9 w. J e t 8 y 1, 4 a r m- -c - -; e w 3 ; t ' 8 me I / _l _'] i Ii i I. ,I, I !, ,t 1. s 1 v_ i 1 * e ~ v v," 4 lj e n<. 1: r ~ e p_.__.-g- -~~ ~m i 38 I i 'l. I i t. ..'t = I ! I N 1I ( 1

  • l' Ii l

g k t l i a a ... r.... a a ..., en a a e s ie 1 10 ..a'100 _ 100C %g ~"~ SPECIMEN LOCATION NO. Fig. 8.4 AXIS TEST NN NO. l Comparison TRS vs RRS Horizontal OBE Side-to-Side / Vertical 2% Damping P. l . m r -w7 7,,.. 3 -e yv-r T-r*1-* -7.-- -+y-be --tr'+h-. --N^v 7w. W y+1mr-+1 -^--+----r-

7_ _ _. . - ~. t I 1.* Legend Page No. III-444 . g 1 Report No. 44681-2 G Byron /Braidwood RRS FULL SCALE SHOCK SPECTRUM (g peak 3 b,, Byron /Braidwood Station !4 1.00 10 0 100 2 1CCCC commonwealth Edison Co. DAMPING y i 100,, e \\ e l ~ I t + 3 1 7. l-i l i i-r' i, 10,. + i i . i e i e t } 4 g ^ l* l' 1 - iF C - a r f' If F i i / j A, L i 1 's J'_L f l 2 1 l p a m; 1 a e = 1:a ( I. e U f.".5 l

  • O

)*\\ = e ,i i a a

  • e e r. e i.

1 10 -100 j, Frequency DizJ '~1000 ~ SPECMEN LOCATION NO. 1/CA Fig 8.5 AXIS FI/t/ TEST RUN NO. Comparison of TRS vs PRS Vertical DBE (SSE) Front-to Back/ Vertical 2% Damping 'O ~ - +- ,.m_ .,,, - - + - ~. - -a.--..-yww-9ygw-,g. y-9-y- ---F

    • 1'

.t w ttp 'M'+'T-+1*~ =-~'""*vP-44-T'p*=-- wer.- -=+=-*w'"'-* ww W-- Nw+-f " ' - - - - " ^ - - - - -- ^-

~ Legend + TRS Page No. III-439 G Byron /Braidwood R'S Repcrt No. 44601-2 f FULL SCALE SHOCK SPECTRUM (g peak! Byron /Braidwood Station Commonwealth Edison Co 1.00 10 0 100(2 100CD DAMPING M 100. e +9+ 577 i 4 i 1 4 y T 3 f

    • 4%

- w-1 \\' .r g e 4 3 -i -y I T.--f ' : ' s D , p. , g.gg w -+ww-m>< - a4 I i - I =1 i I I I I ^ = ' ' l [ l l I j J' T i I I il i I E f I E E I II T I I b ' "h 1 I j' l I J] .,t i 1 I l f I ) I [ f a

  • 6 e i i 6

6 o 6 .66 6, .I. t 3i l i 8 ' I I i1 i t

  • l p

10 " 0 %m I f 1 I S A ] d E 14 ] e e i e g 4 m. 4 ) / 3 =.--.e n g* y'. s I. 2 1 J FM L T [ I I I I I I I. ~T /. wl'. 1 .,+..I I] j it'g. i.. i .ite.. is. ..i si i.. ici n i. i .9,i+li 7-efi i .i (- i t. r 6. vi si. . i i 1 ,9 s 3.- 9 7 g d ma E I I I: l I Sg 0 t as 4 m - e 9, . M.' _.e usi h sunu.m.==.e_ unum mes

======= = = -

- ' - - - + = ^h ?*, 3, ','-2l3. ".-22=== t 'mg-m _ s @'=="'""'*""" m M I I 1. I E........... I I w u. w w g i: i ! :. 9 I 1. '. i. I I. I.i

1 IIE E*I a

i a a. r I a e i I 4 I3 l l : I TI !4 r 6 . t!eial6. i 1. t ] l 4. gl. 6lIilI I 1 IIE I11 8 3 e li ii I68 i i - i i 1 a. + ~e 's.%q.,e =. c i a a + e e r e e se a, _.. . r.s a a.- e e a e e re .,i 1o y._. q) 1000 _._u _... a.: t .__2. h y (Hal.- - n-., =n:= n. m -- a SPECNEN LOCATX3N.NO.? t~.. Fig.-8.6 E\\ wgg-r Comparison of TRS vs RRS Horizonta1 DBE (SSE) 2-A~~~""*CpTC.,.. - a p f ront-toBack/ Vertical-2% - Damping - ,.. s:m.m.+ e

w. 2 5.52 2.E f,*::i.'
  • +.

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P Q M hy @y G, a, ud h i Aif-e x- ~ r h~_y r w,., - m' 3 3 ,,. m. m _ L . 'sws<nm mt-

j Ltgend + Page No. III-4G 7g Report No. 44681-2, G Byron /Braidwood RRS FULL SCALE SHOCK SPECTRUM (g peak) Byron /Braidwood Station m nwea t son Co. 1.00 10 0 100 $ 1CCCC DAMPING lMl 10d' t 6 s s g q'; ,i i i o. ,, 1, . "? 10.e

I 7

s ^_ r 1. Cs. s b ~ E

== t w ,,~ q . l 2 'fE i- 'A ' 4 6f g. I 6 / I' 8T-li i; .iXi f. t l.. ^j Y g. ,, j, 1 e. / ' ~ 's' 1 - + g,'l 2 6 7 s n s 1, eu 2 E *, s

  • eI:

/ + = c-e \\ s s n , i -i. .o, 4 .n .i, ,.i. a a + + e easu a s. 1 ja _... t. a..._., .....~ ' 1 G3 ".. 1000 g

i. _,

SPECMEN LOCATICN NC. M ~ Fig. 8.7 (.' AXIS M TEST RJN NO. O i 7} Comparison of TRS vs RRS Vertiac1 DBE (SSE) Side-toSide/ Vertical 2% Damping E O 6 9 < d e 5g.4w e W PN'eW- - * ~ ' ' ' ' ., qp

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Page No. III-463 G Bycon/Braidwood RRS I Report No. 44681-2 FULL SCALE SHOCK SPECTRUM (g peaki Byron /Braidwood Station i Commonwealth Edison Co. I 1.00 10 0 100 2 1CCCC DAMPING M 4 100** I e i ? 4 s } e f i I I I 6 I. F i i I f I e [ 4 i 4 4 5 4 5 i i t I a 4 4 .. I v 1 I 10 ,a 9 4 \\$ 4 3 t ) s ~ C-J m-j- x i e 1 2 --u r i 'c, r-i. i S a / I I.I *! 1,, 1 Ii/_ f. .ii.. i r. o. . is o ,1 .i, ,I. e e 2 7 g: 1 l.i, o s,. k[5 90 t a l i 1 i i i

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o i. + i i i i. ,i i a a

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4 1 10 100 Frequency 042) 1CCO SPEOMEN . LOCATION NO. NM Fig 8.8 ~ AXIS M b) TEST RUN NO. D l \\.s Comparison of TRS vs RRS Horizontal DBE(SSE) Side-to-Side / Vertical 2% Damping 1, ~

. -,e. Jo--- SARGENT& LUNDY ENG::NEERS rouxocosees 55 E AST MO N ROE STRECT f CHICAGO, ILLINOIS 60603 ( (ala) ase.aooo January 31, 1983 Project Nos. 4391/2-00 4683/4-00 Commonwealth Edison Company Byron /Braidwood Stations - Unit 1 E.2 Storage Batteries S&L Contract F/L 2819 ~ CECO P.O. Nos. 194757/194758 Gould S.O. KE 5145, 5147, 5149, 5186_ x Mr. Howard D. Rubin, Product Manager Utility Batteries and Chargers Gould Inc. Industrial Battery Division 2050 Cabot Boulevard West ' Langhorne, PA 19047

References:

1) Gould Rerort on Environmental ] Qualifiy5ttion of C 9t:A lE ) Load-Acid St.orage Eatteries Application Engineering File No. 068399 November 19, 1982. 2) Wyle Test Report No..:4681-2 (2 Volumes), October 27, 19817

Dear Mr. Rubin:

Your transmittal of December 14, 1982, submitted the,. referenced reports for whichtwo offer the fol-lowing comments:~-^ e 1) Random selection of cells is required for the type t'e&@t per IEEE 535-1979 Section 8, P8. Howerer, no attempt, as made to randomly select the NCX 1680 tbst cells, Te s t specimens to be inspected and evaluated at (utility) customer installation to argbre suitability for qualification purposes" (Reference 1, Section 1, Part 2.1, PCT /4).~ Please ' A justify. J o, ,r JO t s a 4's A. ' d'- v yy Y' -+- Nn b b ,.m ..~s .g -~

  • " * ' * * = '

..N 9,

WH.G6LElkN & LUJFJL@T/ r ENGINEERO ,3 (HICAG3 Mr. H. D. Rubin January 31, 1983 Gould Inc. Industrial Battery Division Page 2 2) No discussion was made on the accuracy of the test data even though this was a requirement of the test plan .(Reference 1 Section 1, Part 9 (4E), PCT /ll). Please justify. 3) Please provide the 10 year ambient time-temperature profile for the battery room, (which was air-conditioned) where the NCX 1680 test cells were aged. k) s The battery load for NCX 1680 test cell was not clearly defined. This information is required for comparison with anticipated load for NCX 1200. Please provide the same. 5) NCX 1200 cells (Dwg. #107006D Rev. F) were purchased but type NCX 1680 cell (Dwg. #10628SD Rev. K) were tested. The report states that both types are identical based on a comparison of their respective assembly drawings.

However, this alone is insufficient to demonstrate similarity as required by IEEE 535-1979.

For example, alloy composition I l 1s not delineated on the drawings. Please demonstrate similarity within the guidelines of IEEE 535-1979. l 6) Seismic Test Series No. 4 test, for the NCX 1680 cells ,s ( ) failed. After the test, cell spacer material was changed from Urethane to Polyethelyne foam type Dow Chemical (Ethe Foam No. 220) on 3/12/82, ECO #0017. This spacer material was used on failed seismic test No. 5 and successful seismic test No. 6 for the NCX 1680 naturally aged cells. 'a) Has this material been changed out on delivered NCX 1200 cells to Byron /Braidwood? b) What effect does temperature and radiation aging have on this material? c) Will these aging mechanisms affect the seismic test results? .7). IEEE 450-1975 was used for capacity test as indicated in l. Reference 1 (Section 7, Addendum, PCT /72). 'IEEE 450-1980 was used as a reference in the test plan. Why wasn't the capacity test indicated in 450-1980 used during Wyle's l test? Note capacity test requirements are different in these ~ revisions. 7 ( ) .~

CARGENT Q LUNDY CNOlNLCRD CMl?A20 ' Mr. H. D. Rubin January 31, 1983 Gould Inc. Industrial Battery Division Page 3 8) IEEE 535-1979, section 8.3.1.4, says " Cells are qualified when there is no abrupt changes of more than five percent of the current or voltage of the discharge during seirnic test and when the post seismic discharge capacity is 80% or more of the cells rated discharge capacity. The first part of thite qualification criteria was not addressed in qualifying the naturally aged NCX 1680 cells. 9) It was not specifically identified in the reports (Reference 1& 2) to what environmental and operating conditions including temperature and load durations that the purchased NCX 1200 were being qualified. This is important because anything that affected electroyte temperature affects its life. Also, an average ambient temperature is not sufficient for qualification because cell life is exponentially related to electrolyte temperature (IEEE 535-1979, Section 6 (7), Note, P7). Please provide information on the same.

10) The reports do not adequately deal with cell interface and connections in accordance with IEEE 535-1979 Section 5 (4),

P6. Please provide information on the same. O i ) The aforementioned reports cannot be accepted until all of the '~' noted comments are resolved. The documents must be revised as noted or acceptable justification provided. Enclosed is a stamped Status 4 copy of the cover sheets for each of the documents. If you have any questions, please don't hesitate to call me at (312) 269-3794. Yours very t uly, ,) ~ l R. J. Zakaras RJZ:lmd Engineering Analyst In duplicate Component Qualification Copics: Division J. T. Westermeier D. L. Leone /W. C. Cleff T. Eisenbart K. L. Adlon J. S. Paniaguas AEM/APD/ RDR/RJZ CQD File 005572 e -}}

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