ML20073R547
| ML20073R547 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/29/1983 |
| From: | Crouse R TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| 936, TAC-42508, NUDOCS 8305040305 | |
| Download: ML20073R547 (28) | |
Text
TOLEDO EDISON RcHAno P. CnouSE Docket No. 50-346 O~
i41m es saat License No. NPF-3 Serial No. 936 April 29, 1983 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz Operating Reactor Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Stolz:
This letter is in response to your letter dated March 25, 1983 (Log No. 1256) concerning Saftey-Related Electrical Equipment for the Davis-Besse Nuclear Power Station Unit No. 1.
A review of all existing Justification for Continued Operation (JCO) statements has been performed and JCOs exist for all equipment which may not be qualified.
All JCOs are reaffirued. The previous response submitted on March 10, 1983 has been reviewed and there are no changes or proprietary informations Regarding items in Technical Evaluation Report (TER) Category IV, only TER item 46 is in this category. These components are felt to be qualified and all applicable documentation associated with these components is enclosed l as Attachment I. Item 84 is incorrectly labeled in as Category IV, it is in reality Category IIIB.
l Very truly yours, i
RPC:LCS:TKR bt e/3 Attachment cc:
DB-1 NRC Resident Inspector r
l THE TOLEDO EOISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652 8305040305 830429 PDR ADOCK 05000346 P PDR
. = - _
TABLE 3 - TER CATECORY IV I I I I l 1 I I l Analysis / l 1 l Discussion l l TER l SCW l l Modification lJustificationlRequested l l Number l Numbe r l Replacement l Test i I I I I I I l I I I l 1 1 l l
-- l l Note 1 l --
l l 46 l 218H-019 l N l l l 1
l l l 218H-020 l N l l l l
I l 218H-021 l N l l
I 1
l l l 219H-022 l N l l 1 1 I l l l I l Note 1: This item is felt to be qualified. All qualification references applicable to this ites are atta,ched.
l f
l Paoo 1 of 1 1
. , . . . _ . . , . _ _ . - _ . ~ . . . . _ . _ _ . . . _ , . . . . _ _ _ , , . . . _ . . _ , _ . . , . . _ . . _ _ . . _ _ _ _ _.___. .. .. . . - . . _ _ . . _
N E N TR P go
. . h FRC Pr$ct No. C5257 00Enkhn Raerrch C:nt:r FRC Assignm:nt No.13 lc AD n.f The r, akt nlasirvir 2mh cnd Rue Sirstis Phde . Pa 19103(215)448 10 0 FRC Task Nc.. 6 EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPME EQUIPMENT ITEM NO. 46 RTD LOC ATED IN THE CONTAINMENT, ELEV. S'0" ROSEMOUNT MODEL 177HW2 1 HOUR REQUIRED OPERATING TIME:
TER CHECKSHEET NO. 46 LICENSEE REFERENCE (S): 3789, 60 FUNCTION (PLANT ID): SENSES TEMPERATURE (TERC3B4)
SERVICE: R.C. LOOP 2 HOT LEC NARROW RANCE TEMP. FOR RPS CHANNEL 3 LICENSEE SUBMITTAL: SCEW(S ): 218H-022 FUNCTION (PLANT ID): SENSES TEMPERATURE (TERC3B2)
SERVICE: R.C. LOOP 1 HOT LEC NARROW RANGE TEMP. FOR RPS CHANNEL 1 SCEW(S): 218H-021, 021 A, B LICENSEE SUBMITTAL:
FUNCTION (PLANT ID): SENSES TEMPERATURE (TERC3A4)
SERVICE: R.C. LOOP 2 HOT LEC NARROW RANCE TEMP. FOR RPS CHANNEL 2 LICENSEE SUBMITTAL: SCEW(S ): 218H-02 0, 020A, B FUNCTION (PLANT ID): SENSES TEMPERATURE (TERC3A2)
SERVICE: R.C. LOOP 2 HOT LEG NARROW RANCE TEMP. FOR RPS CHANNEL 4 218H-019, Ol9A, B .
LICENSEE SUBMITTAL: -SCEW(S):
-d i
1 l-
[
ONLY:
DESIGNATION FOR DEFICIENCY IDENTIFIED BY THE NRC SER - CIRCLED ITD4 (S)
(See Section 3 of this TER for I49end)
I, WH, RPN, EXN, SEN, QI, RPS, None, l
R, T, h RT, P, H, h 5, (R), M, Not stated, Not applicable LISTING OF APPLICABLE CHECKSHEETS:
Checksheet Pace No.
Contents la Equipment Item lb Summary of Licensee Responses to the NRC SER 2
Equipment Environmental Qualification Sumary Forms 3a, W Licensee Response to NRC SER 4=, 4L, 4, 40, L. ,f-System Consideration Review G. , '., L , 50, 56 *n Sf, Equipment Environmental Qualification Review gu u 9 E, &
Installed TMI Lessons Learned Implementation Equipment Summary Maintenance anc Replacement Schedule Summary % N, b
~
,y FRC Assignm:nt foND[.13 FRC 4 o - .#Twore.akhainv=2:s1 0 031215)448 1000 Tcsk No.
' ' $nh aU Race Snws. Phde . Ps O. Ys a EQUIPMENT ENVIRONMENTAL QUALIFICATION R
<p HE NRC SER - ONLY CHECKED ITD45 ARE APPLI SIMMARY OF LICENSEE RESPONSES TO T (has/h;; c.;;) provided a response to the SER concerns.
1 Tne Licensee is I specifically stated that the equipment l DBE The Licensee (has/has not) qualified and/or will function when exposed to the applicab e environmental service conditions.
1 The Licensee has presented information which shows there are no outstanding qualification deficiencies.
proposed a cor rective action for this equip =ent (has/has not)
_ The Licenseeitem whose qualification has not been fully established, (has/has not) been provided by the Justification for interim operation s item.
Licensee for this equipment Licensee:
._ Corrective action specified by the J
Equipment replacement with qualified equipment
_ Equipment modification ce level J _ Equipment relocation above submergen diation source
_ Relocate or shield equipment from ra(testing / analysis)
_ Verify qualification by additionalrelocation to a mild environment
_ Equipment in progress )
Qualification testing of equipment
_ Other ( item The Licensee has provided other information ionfor forthis equipment interia that can be construed as a basis for justificat g operation.
5 provided a schedule for the proposed (nas/has(Schedule not) for accomplishing the corrective .)
_ The Licensee corrective action.
l action _
the equipment item does not require qualification The Licensee states that and/or should be exempted from environmental qualification.
l O Y BASED ON REVIEW DESIGNATION (See OF RESULTANT Section 3 of this TER NRC QUALIFICATION EVALU for legend) l - CIRCLED ITEM ONLY:
II.c Qualified Life Deficiency q
I.a Qualified III.a Exempt I.b Modification III.b Not in Scope lLj Established Available II.a Qualification Not h Documentation Not II.b Not Qualified
'LJ
NRC Convact rum nr.- 'W
- s. FRCPr jectNo.C5257 2
' FRC Assignm:nt N3.13
'. $I_FA'o :nkhn Rese on or The r.:nst arch tamw Cent:r FRC Task ND. Co *~
2mh cnd Rue Sze<
Criteria Regarding Submergence Satisfied Cra teria Regarding Radiation Satisfied _
l Criteria Regarding Test Sequence SatisfiedFailures or Severe Anomalies i Criteria Regarding Test L, (If Any) Satisfied _
Criteria Regarding Functional Testing SatisfiedSatisfied Criteria Regarding I 4strument Accuracy Satisfied _
Test Duration Margin (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> + Function Time)(NUREG-0588, Cat. I) _
' Criteria Regarding Margins Satisfied
- b. DESIGNATION:
_X = CATEGORY NRC QUALIFICATION CATEGORY I.a Equipenent Qualified I,b Equipment Qualification Pending Modification _
II.a Equipreent Qualification Not Established 11.0 Equipment Not QualifiedEqu'ipment Satisfies All Requirements
- II.c or Replacement Schedule Justified III.a Equipment Not Exeispt From Qualificationin the Scope of the Qualification y III,0, Equipment IV Documentation Not Made Available n
l I M
NR@ LccniffciNs.NFKarFrm Pcga ps FRC ProjIct No. C5237 5I 3
lbhkr:nklin Rssearch Ccnter FRC Assignm:nt No.13 i . D. 4.on s4 The Feenklin inudun FRC Task No. CDf ,
.ahcad Rue Seems Phele Pa 19ttu1215)448 Iftra EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW O NOTES:
c re rw e to ue, nnh wVaifa t
- l. fle b f[ow e w.=>
re vi eu> :
Izjefcor A w wers Iw e n u_ n Euo.r,m me d l h eet b o m t,0.mt m s a, x , ts . i , 3 /e (7,f .
- A s3 as ceb % e,J as oul,C,<mL G<
The docu med J ceIc d 4m J,/: 4.
t m o,,e h ,r,m ss m j ,
, , - , ek .
I 6
9
~
4 W
W
FRC Prtlect(7Jo.~C5757 Ohr nkhn Rzw:rch Ccnt:r FRC Assignment No.13 3o A o-or Th Finakimla.inus2 Sof
' *' b .nd R.c. se is. Phd. . Pa 17103(215; W m FRC Taok No.
EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW OF EQUIPMENT ITEM NO. fjls, LICENSEE RESPONSE TO NRC SER OiO:,Ti:"."," ," 5::.: .-"""" ""'-"- '- - """"- ' ~ ~~'--- --
l lE E .
E 5
5 LJ p
Ls, r,
tJ .
r, L:
im o
0 0
0 e--.- -,
n tE: e70-023 eds'() nuclear
' ' COPY: a. v. soran s RECORD OF CONVERSATION O meeting Other H Telephone 2- '"--v"-" DATE July 30, 1980 g , F. Levandoski FROM:
sabcock 6 Wilcox PHONE NO.: (804) 384-3111 COMPANY:
1NI-1 Environmental Qualification of Class IE Electrical Equipment
SUBJECT:
Summary of Conversation: .
Mr. Levandoski stated that the standard test time for the tests, whose results Kre provided in his letter to L. McBee dated
- February 11, 1980, subject: Environmental Qualification Sub-committee, is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
JET /cek im 1
I l
l e
k o
4
g u . .) p 6 .
- - - - ...).
(. .
,j n\
l .~s: 2'T. 3 2.'.i
- i R05tMOUNT INC .*0s* orrect ser 31u3 r e'wwtaPous */suwt Die 3:43s # 7tt tti'; sa !st:
r Twz. sic $4 Jtt) 1ttg r ;; 9:3 e
6
-[
( -
INVEST! GAT 1tA 3
RADlATION REQ'1RD:ENT J CDEL 177A' .
r C- Resercunt Report 87t,14 ,
l l[ h.* C* . : r; L :.:.C' r r c.c: .. :
. n .; .
L .. ...,.... BABC0CK & \','ll.00X 5 I'I '
DOCUMENT NUMDER
[
.- J a. .. ?. 620-0017-182122
. s. .. : .: .
OM9 00
- 57 - -
E cf'f/W4M4 .*-J V 4 i tn s : .- .
f I
Prr,.:rc.?
b.s I.'eIter 2 rett 16 kgest 1974 fI r I
I
., _.y. - _ . , , _ _ ,. . . - - . - . _ _ - _ _ , _ _ _ _ _ .
- JNVESTIGATION
{[.
L RADIt. TION REQUIF.EMDJT NQDEL 177 W L RMT lieport $7414 .
r L
SU N Y .
Specification requirer >ents for the 177tN senser arc 5 that the unit rust rats. This require-ent g be capable of surviving a total radiatien doseage of 3.0 x 10 r was evaluated and test results show the design ccn withstand this anount of ex;osure without any neticeable effects. In addition, a unit was exposed to 3.8 x 108 rads.
" This unit also yielded successful results.
BACKGR5)RD 8
Prior to this test, the ' radiation exposure requirerent of 3.0 x 10 rads for r There had been sorne question if th2177W model had not been envirenmentally tested.
this leel of exposure was too hig5, consequently it was decided to subject two sensors to radiation, one at the specificbtien level of 3.0 x 108 rads and the other it aPerfoman slightly higher level of 3.8 x 10 rads.
( , Greater after radiatien which would shw any dar.:ging effects caused by the radiation exposure.
damage or deterioration caused by the longer exposure would be indicated by L
F 4 a larger shift in the results for the sensor having the longer exposure time. [
IWESTIGATIO1 '
177HW sensors subjected to a radiatien testing were S/ti 3370 at a Evaluatiers 12 vel of 3The x 10 tEr ads and S/N 3371 at the maximum level of 3.8 x 105 rads.
ptf or to and after the radiation exposure were - calibrations at P.o. 212*f and 600*F, l{ - IR Check at 603'F and roon temperature - and time response in water at 175'T f1 win <.
at 3 fps. The actuci radiation exposure was conducted at Iso edix, Inc., parsi:pany, j New Jersey and the testing procedure follo'. tad was as outlined in a memo fron Isor'edix a The memo is an attacht ent to this report. After completion of the radiation These testing, the two units were returried to Resemount for final calibratien and testing. >
calibration and testing results togetner with the previous dstr. are given in Table I.
All virtations or shifts were considered insige.i-
)I The shifts are shwn in Table II.
ficant and were within the follwing limits:
.032 ohms $
ho R .004 ches 212
.o2-lI % j' Alpha 1 ppm j
lP Time Response 0.6 sec.
4 The IR readings with 100 VDC applied were all found to be greater than ,
f 100 megs when measured at room temperature and greater than 10 megs when l{,.
., measured at 600*F. In addition the sensors were thoroughly inspected for visible indications of damage or deterioration and nothing was found.
Tgese test results show the 177W design can withstand the radiation requireme of 3.8 x 10 reds. A
.{o' -
5 TCLE I
{
,~(' Calibration, IR a .d Time Respo.se Data j t
211brztfon 1 5/N 3370 $/n 3371 Tests Sefore Exposure Element (1 Element (2 Element fl Elen:nt (2 r
Ro 99.784n 100.470a 100.155a 100.165a 138.992n 139.947a 139.518a 139.5Ma f 212 L
500 219.612n 221.052a 220.439a 220.5453 ALPriA .003929a/c/*C .003929a/n/*C .003930n/n/*C .003933n/c/*C Ngs 40 Ngs 350 Pass 255 Fags Ik00 Time ,.
7.2 sec 6.9 sec 8.3 sec 8.0 see
{ Response (Aver 3) 8 Exposure 3 X 105 rads 3.8 X 10 rads i
Calibration &
Tests After Exposure Elerent #1 Elerent #2 Elerent 81 Element f2 Ro 99.7E3a 100.470a 100.153n 100.168a 138.994n 139.948a 139.522n 139.560a
[
212 P 600 219.6233 221.112n 220.444a 220.547a
.003929n/;/*C .c/a/'C .003933.9/c/*C
( ALPHA 003930 /a/*C 20 Hegs 350 Heg: 300 Hegs IR 10 Hegs 600 '
!I IR g 700 Megs 700 Megs 200,000 Megs 300,000 Megs
" 'E "8' 6.6 sec 6.7 sec 8.5 sec 8.1 sec r3
,E -
E '
o .
lt
_ y ., ... . ..;.,,. \ ?. W
{.. TA3LL II Calibratien. IR and Tine Response Shifts S/R 3370 - 5/N 3371 Element il Elenent (2 Eter.ent #1 Elerent (2
,03) .000 .032 +.032
{ a R,
+.032
+.032 4.031 +.004 a212 4.011 +.C24 +.035 +.032 6633
" + 1 ppm C + 1 ppm 0 6 ALPHA Time Respense .6 see
.2 sec +.2 sec f.1 sec Variation NOTE: Both units used Never Seer'NS-165 as a "thereal grease in the silver bushing
[
to themowell I.D. interface.
[
r0 I l
[
l I
i I
_w rti geport 61114 . _
P u, .
F .- ,
g ISOMEDIX w
P July 19, 1974 L
e w Mr. Don Mattachuck Rosemount, Inc.
12001 W. 78th Street Eden Prairie, Minnesota 95435 P
Dear Mr. Mattachuck:
w P The following will summarize the radiation sequence pertinent to the w
testing of two sensors with connection heads submitted by Rosemount and received by us at Isomedix on June 7, 1974. The irradiation was performed following the sequence in Instructions as outlined in your l) "Special Instructions".
Irradiation was begun on June 7, 1974 using cobalt-60, at a dose rate of lx10 6 rad per hour. A total dose of 300 Mrads was administered Units were to one unit, and 380 Mrad to the other, as marked on each unit.
rotated and turned during exposure to achieve a more uniform dose distribution.
The overdose f actor to edges of the units was 1 15.
w Irradiation was performed in air at ambient temperature (70'F) and a
- slight negative pressure (1/4" water). The maximum temperature of the as confirmed by readings h
sample during irradiation did not exceed 100*F, in an oil solution in the vacinity of the test samples.
Dosimetry was performed using a victoreen Model 555 Integrating Dose Rate Motor and Probe. The unit was calibrated on January 15, 1974 by the Victoreen Instrument Company, using Cobalt-60 and Ces.um-137 sources f whose calibrations are traceable to the U.S. National Bureau of 5 Standards. A copy of the calibration certificate is available.
Confirming dosimetry utilizing a Red Perspex system was also completed.
?
Irradiation was completed on July 19, 1974 and units returned to you b under separate cover.
F k very Twly yoors. ,
Georie 'i. Di. et z ** ' v ,c'
..,,;...., t, t - .: _. ...,
t, san e p
- i. r.n .c .: : hs :.. . :, . . . . .
'.,........s......-w - .
E e .- ' w e
.'l" 1.-
E . . . i....
sc.v..... ....... .. *
-- _ . - - . . _ _ ._ .- . ..x.
. p 6 -
o C
a T.3',M Ws l
Rostk'Out(T IKO.12*,31 *EST fait, stAtti / EDEN PAAlait. u NNttoT A 3593 s t Twa st0 st&3tc3 TELIK P 4tt3 O
O 28 August 1975 o
b o
I o
Lailey Heter Co.
P . f) . Son 400 Wirkliffe, OH 44002 Attention: Mr. Lee Perossa p . Mail Station 3KL 6
hVestigation Radiation Requirecent Model 177HW Subse:t: t ip b Referen:e: Rose =ount Report 87414 Gentlemen:
Attached please find the referenced report which outlines 377R.i radiation capabilities. If you have any further questions, please contact me.
Very truly yours,
(
I
% e. w w -
Steven R. M:hattin
.r Applications Engineer
}
SRM: gel
Attachment:
Rosemount Report 87414 l
I .
l t
.c I - - . - . . . . . _ _ _ _ _ , ,
I
..,, ,, g p [9:' A ?- . i ;
g, .,g . ;,g.,;, .
gy,g .,,.g , y M,,W ),i
',THC'. BABCOCK & WILCOX COMrANY -
. p0WER GEllERAT10ft GROUP I
()
F.J. Levandoski, Product Manager from
. L. McBee, Protection Equipment Uni.t '7/7,,b ees ses.5 Cust. ,
File No.
'I' B&W Owners Group Su b,J . Oate Envircrrnental Qualification Subecmittee March 19,1950 g............................................
Reference:
Your note of 3/14/80 requesting test dates be included on matrix.
The attached Rev 01.of Owners Group Environmental Qualification matrix is the response :o your request. One additional item was added in the matrix for the documentation for the NI Preamplifier - a re;: ort addendum
~
was added (55-0087-00). .
~
LM/whm p ., .
-( .
cc: w/ attach.
PCi Burstein .h e -
3.gP . E.r. oownng, sanager 3 N
el8 i -
i 1.
l l .
1
.
- 00-2/80 177 H&W Ntith5 GROUP 03 3/C0 PAG g* -
[NVIR0tdlIN 'luAliFICATION
. K\f."JfM IL'CE 14tillHtNT ACCilk tilVIR0flME NT [QUIPHENT 00AllflCAT10N 00CtlM[NTATION REHApi(5 .
(nmLR IPMENT FUNCil0N AND IIDOE L NO SP[CIFICATION REQtjllttitNT 1%JA 4X10 I with 4.51 shift 81W 58-0081-00 See figure 1 , ~
Dalley 05-3-17 21104 iniciit c Il04 Roentgen no eUect (Har. 12,1973) input to (3-4-9) Reactor N55-9/1070 Press. Sil P$lG Press. 59 PSIG (5-6) toolant Reactor Bf3X4IX-AX o Protection I3*b9I P; Temp. 2060 f (7) Fl u.e p Autoclave P/T vs Tlee I"I D5I# NNI 1048 Han loaccuracy 112%
-) -(B) P/T vs Tise Plot attached a ta
, n curacy 20115.(4, Seismic Vibration 3 Ants 3G *teached at -
(349) l'ressurizer Indication Bailey 12-15llz below 12ltz (5-6) I cvel and DY3040-AX Displacement Limited to (1 li .insmitter Control .375 D.A.
gg Man inaccuracy 21 .
gygg li mpe ry - seeL ,
g4y ,.
(3 4-9) Eleam Generatoi- Indication Dalley -
(5 6) evel Start-up and DY84B1X-A (7) in.1 Operate Control .
(n) . .
(11)
(14)
CT" Tank tevel Indication Bailey CS-3-17/N55-9/ Not Required
"(3'-4'-9[ Design Range Only (5-6) and BY8X31X-A 1070 (3-4-9)
(7) Control ~
(H) Ntli 1048 .
(11) L5-6)<(7)-(8) *
(14) , Lil)-(14) .
2.21106 Roentgen Certificate of See Figure 2 Hotorola C5-3-17/N55-9/ 2X104Roentgen
([-4U) Heactor Input to (Westinghouse) 1070 Press. 58 PSIG Press. 59 PSIG Conformance Copies of Test Coulant Reactor Pro- Report for P/T Reports Supplit .]
tection System 56111 Temp. 2850F Temp. 20bor riessure 58-0093-00 utu LOCA. Radiatfor P/T vs Tim.e See Attached Autoclave P/T vs Time Vibration. Design Ham Inaccuracy a101 Plots Attached, lies. (Sept.1969)
- Rda9e n4ccurac tg61Selsnic m @lNott war,i}A k$a' e
fis m.o e cry - Jcc?,
S
E,
. v 171 B W OWNERS CROUP .
- '00-2/80 ENVIRONHfNIAl. QUALIFICATION
- 01-3/80
- PACE 2 MANUFACTURF. EQUiFsENT ACCsDEN Q vlkOleHt C. T UTPHENT QUALIFICATION
__.Orl L Dntt rterWT F1fMCTION AND PW)Drl. NO SPFC1FirATION a rt)tilit t urNT 0ATA 90CiHTMTAT10N RfHApr3 ,
(3-4-9) meactor input to Hutorola CS-3-17/NSS- 2XIO Rocutsen 2.25106 Roentgen Certifteste of See Fig. 2 Coul.ent Ingineer 56115 911070 Press 53 l'SIG Press 59 FSIC Conformance Copias of Pere.mure Safety Protec- (3-4-9) F/T vs time see attached Temp. 2860F 58-0093-00 test reports alun System man. Inacc'y i 10% Autoclave F/T vs time For r/T supplicJ to 8614 (SFAS) plote attached man in- ($ cpl.]969) IMCA acc'y 8.62. Selenic (VI- R.eItation bration) 3C sinusoidal Vlier.s t ion I-50 112 3 Ants man. IL"elnn B. ente Inacc'y .25g See Fic. 34I38 (5-6) unactor Coolant input to SFAS Fontan to NNIl048 2 104 Roentgent 58-0079-00 -
cops,,og g,,g (7) Freeniere and inJicatlos EllCN Press. 58 PSIC (Dec.22.1971) ,,p,,,g , ,,ppgg,g (8) Temp. 28 ff 4.6X104 BsJ; press 90 to n!.W (II) Steam / alt sus fr. ace,y 1101 PSIA Temp '3180F 3th'A (14) Selsele (Vibration) 1 - 2 5112 pil 100t man inace'y 52; E2*l l d t l *
- 3C (Vertfral & ilorizontal) Vibration 3C; 3 Aute Vibr.stion man. .inacc y 1 51 3,gg p,,ig,s.,,,
I to 50111 (5-6) Halu Stese InJlcation Tomboro NN11048 (7) Fremente and Control E!ICH P s 90 IA Trop. 3180F (11) R . II . 100%
gg49 H.e s . Inacc'y 52
- Vll. rat ion 3G 3 Ants a 3.01; I to 50117 (3-4-9) Neattor input to Roscuount CS-3-17/ MSS Not requircJ 3.8110 8 paJ Cert!ficate of The 177tN has been (5-0) s'oulant Reactor lro- 177CY 9/1070 Design Range Requiremente Temp. 325 F Conformance (177CT) quellffed for (7) Tempes .s t ure tection Sye- (3-4-9) (11) NNil048 only Press. 4.0 FSIC *** "" ** I"I*""
kil 1001 58-0372-00 (177119)
(8) lietector tem Rumemoient (5-6) (7) (8) (Jan.19*1978) by stellarity to (II) 1771M (14) 177 CY - Vibration tlin 104AFP and is (14) (5-6) (7) by An.nlysis ti.e replacement (8) (14) 17 7 IN 3 3112 , bl-ma l a i 8 no t int a l.e 17 7CT 3G ZrA (5-6) Beaetur input to Ru mewun t NNI-1048 F X 10 R mJ 5 x'106 Red 58-0261-00 (2/11/711 Sc.- Figure 4 (7) s*oul .en t kcactor ll52t:I' *sA92 & Temp. 286* F 70 rslG 316*F 58.It?20-00 (9/19/15)
(n) recu nee routettton 011-1001108-00 Press. Sil PSIC 5.eturnacJ Steam / Chemical (14) I s .en .wil t t e r S y s t ras 10t12 Itti .-la mical spray speey; mas inace'y 51 ,
us e .am/.e le ; m.se Inace'y 102 Se l !.. t c Sc i e.se le 1 - 1511/ ; 3G ZPA 1 ' 4 11 / .3 D.A.
u t.s s t .e 1. . . Snare'y 52 14-lutiliz 3C,ZrA H.e s i n.e. c ' y i II
o '
j
- . 4 a i l
177 88W OlNIERS GROUP 00-2/80 EIIVIR0reif tliAL ()UALIFICATI0ll 01 3/80 NANUFACTURE Elllat rMEfff ACCll4NT s'NVIRONMENT EQUlrritna QUALIFILATIEM FIROCTIOsl g n Hopft 100 SPECIFICATIOtt DATA DOCUNFWTATION RFNARES tNNFR. _EflWirD8Ettf RFQttillitJillT _ _
(3-4-9) NI Fre- Impest to nelley rf NI/ prs-CS-2-15 Accllent Re.tvirceent Deslam Range 50-1017404-01 .elmole .
(%-6) empliller Reacter pro- No. 662)l40Al Deelgen llange Design It.enge Only (1) Rnd 2.4X10 For T&ll (6/N/70 (Vibrattee)
(7) tection system Itad. 2.0x10% (2) Temp 400 to 1608 Se16 ele 58-0087-v{u untow F sig (I) Temp.40-150 (1) II.imidity 942 (2/5/10) .lasteJ by (II) llueldity 0-902 Bil at 1400r 50-0038 00 :h her Table (14) Coint . Tested IC (10-19-70) to 2 0.375 NI/RPS-10lg 7 to 40 lit . opy of Red lli.E!1II) 1 Asle Leys t avalI.
(3-4 9) Sneerce Range Inpu t. to Reec- West ingliouse Nt/ItrS CS-2-18 (1) Red. 30-60 CPS /NV (1) R.ed. 49.4 CPS /MV 58-0%?s-00
(%-6) HI Inetector tar Protection WI.-23682 Hl/pr5 1018 (2) Frees. 150 PSIC (2) Press. 150 PSIC (11/17/70)
(7) System (14 only) (1) Tear. 2128F (3) Temp. 212*F (R) (4) 902 Ril (4) 1001 Ril .
(ll) No accident requirement Selbete (Vibration)
(14) Design Range only , IC Vertical 6 Itortrontal (I-4-9) Intermediate Input to Beac- Westinghouse (1) Rail 4-8E10-38s A/HV (1) Rad 6.6sl0*I4 A/MV 58-0529-00 Ranr.s Detectoi to Protection W1.-23615 (?) Press.150 PSIC (2) Press. 150 PSIC (6-24-70) ,
System (1) Temp. 212*F (1) Temp. 2120F (4) 97!! Rif (4) 1001 RH No acclJent tearstrement Selsmic (Vibration) ,
tseutgn Rasiga Oilly IC Vertical & Igor! ental (3-4-9) rouer Range Impest to Rese. Westinghause (1) Rail 1.2-2.1XIO*I3 A/NV (1)*RaJ 1.62xt0*Il A/NV 58-00d9-01(6/22/70)
(b6) Detector f or Protect io-i WI.-23636 (2) Frerns. 150 PSIC (2) Press. 150 rSic connector Test Red (7) System (1) 1emp. 212*F (1) Temp. 282 F C.aen.a 2GN/Itr (n) (4) 902 mil (4) slumlJity 2002 Bil Nruttnn Flus 10 6 ,y (II) No accl.lcut requirement aAt 750 volta Tear. 200 F (14) Design Range uenly Scismic (Vibretton) l*s ss. IBD PSI IC vertic.sl & Blorleontal E4ffil.R ( ett 11 Is.4-9) strance 1.2.3 154) *I111 (7) I lor tile (ts) p a b .ue sa n Ill) !.f ttell 104) s s s es
. w a -
w a 3
~
(21sd) ajnsssJd ceals
. . a a a -
a I
(- -
E=
I l
I I
I l
a -
= -
I -
l Ee ~1 1
==
= .- I g
=
w k N_4 I J I
- I ._
S
~~ ~
E
=
,~ %~ ^ , , 1 2
M
- 5 w I / p
- E mEl - {g -
. ~
> w-
-= a
= w os
. m . wa a m
-w - m .
Ub O -
es;
- m M
=
i -- ~
t
/
./
/ k' . -
n
/ / .
- u
/ -
N
['i
' ,R;S:-wg i
, _ =
( - m u -
WW h, e; e s l ,! .- -
- t. m n
~
- ; z m
- I =
W-
-~
> - o
/ I w 3 C C
>= .
a e.
i Il .
~=
-o I I
. *j S lI i
i -
1 1
I '
s I _
i lI 1
i . _
l I I.
i!
=
=
t FN . -
a a
o .
a .
g en ew -
(j)asnr;ae:21
- ,. , , ec ,- , , , ,w4 -. c-----,----.---,,---,----.--,-----,--e, - -- - - _ _ _ _ _ _ - - - - - - - - - - - - -
/,<
e a (21sd) aJnssaJJ . .
a a a a, a f , ,
e- = W n ~ W e C w, 'j - .-
.a=- gI * -
i, O D =
w >- .i E a== q i heJ A E % =
- 8
-= w g *"
43 A %
WM % M 2
- EL w -
e M p. . I 2 anC g
E I m t
w w
- o
') . m Lsa
' - c
- a. I
~ C N x M g
.SD - m. m
.. . . w
.= M E
a
5
. D J
'" 4 O $ _ e 3:: I A
-=
C w
c / W e Z W W
- ,/ r
- = Da* .' i t=) "C C M C =d N W ,
8 # '~ "
w C Q DE v
/ "
C c w
.# 9 l
- e >=
aug e. C b.=
/ *
.EE M O i / ,
w EE:
c l M Q
>=
. D.= \
n W =C a
O \ ~, . . . .
(.3 g,,j , C C
u
.%g H h. M
) ~ ~ m w w
/ ' s ,
.5 E c= m E5
" N es. m6 1 \ - a, EC C '> .
2: c- n
) . / "E 6D .#
/ C LD
- - 2, -
4@
=
i
(
f "C M M [ # O k*.
e=.
y
.c.
l i .- , tg I **i - l =C =
g c / l i. me I o ;;lE
\ g C
.o
. . - ~
4 a
c = auC '
5 m -
t;;
, ll w
f N !
=
C g
E
= -
d b e
m >
M i* .
- l. a g 8 C C l O h
~
f C l 1 y g
l .
=
W ,
E m
-- ( w
- O a - C U w2
- O 3pm s.-
== se: W ,
- D & M auC Uw l ce -
WM "
dea auC >= g
. =
W D C C C C C a 6n C st) C sn
- gy get . c's N N .-- .C=* *
, , , (3.) aJnicJ at::a1 ,
~.- a a a a a q, - a, c)
, a. -
. o.
e,
- a ,.
i .
- a M andulfindin0) c 1c3 aJnssaJd O
,,,,----.c - . . , , - , , .,n-, -..m. - - - . - , - , - - - - --e-~--,--w- --,.---n- ,
O
/
3 -
a, 300 -300 P =
v .: = . .
co rio in
.u uc n
e a a. '
g - -
d -
l g .
. . . .i o o ' '
. ~ - - -
y ;
4
. , tz
. ,2 = 5 y - -
(- ;
.rU - ,
, .imc. *
.. {,
I .
1
-244* F, 20 pelg -
y'; g a 221:ris L:Inu3 30 &llN. .
=
- *j200 p
- * <-- 30-Illti. DROP *l .,
- o m
h.
m l
b d g -
9 z - -
e -
HOTE; . - -
150 -
,e 9s f. CURVE NOT TO SCALE ,
.' em 2.00RIC ACID SPRAY APPt. LED FOR , COOLDOWN _ E 3 "
PERIOD 24110013. SPRtY 00FFERED TO - .
.e
- 9 -
a, pH OF D.23 1010.0 FOR FIRST g -
100 - .- 2 HOURS. AnD B.5 TO 9.25 FOR .-
r--AtJC:ENT g HENAINING Tig8E .
'M .
/ A m -
~y 7 .
. --g .
60-ulN. DROP *
- + -
+ *l5-SEC rt;g I p 30 1 1 I I I 7 O I 2 3 4 0 -
. 23 24 25 36 - 4 0 g
- w TIME (HHS) os
! Figure 4. Specified Temperature / Pressure Profile 'Of Steam / Chemical-Spray. Exposure i .ilGURE3A.
. i
( <
li . .: .
I.-
i
., l; - - - ,
I . ,
l
- CALCULATION /PROSLEM COVER SHEET Calculation / Problem No: 1040-001 n42 f Chemical Spray Analysis of Safety-Related Cor.ponents Tltle:
Cilent: Toledo Edison project Davis Besse Unit No. 1 Equipment Qua1212 cat 2on
- Job No. 1040-001-671 Design input /Reforences:
Refer to Table of Contents on Page 2 of 8. .
Assumptions:
Refer to Table of Contents 'on Page 2 of 8.
M;thod:
' Refer to Table of Contents on Page 2 of 8.
R: marks:
f 1 The purpose of this calculation is to analyze the effectsthe ofDavis-Besse a Boric Acid Spray on certain safety-related components installed at Nuclear Power Station, Unit No. 1.
APPROVED DATE REV. NO. REVISION PERFORNED BY OfECKED l l '***"*'
d)2Nfdd c ,.. .. N fSki d i9-tM '
1 pp. 1-7 g [fy/ /- [ - [f, 2 lpg.7 g [ j l f > 7 -4 A ,
y .
I I I i
"" Sheet 1 of I a g. :**P* _ , _
TABLE OF COMTENTS l
TITLE PAGE N'*:rsr r SECTION Pu rpose 3 1.0 Scope 3 2.0 References 3 30 Method of Ana1ysis 4 4.0 Basic Data & Assumptions 4 5.0 5.1 Basic Data
- 5. 2 Assumptions Sunnary Results 6 6.0 Body of Calculation 7 7.0 7.1 Rosemount 177}M-2RTD 7.2 Bailey Transmitters 7.3 Materials Analysis O WI" 1142/ ~l$f 1A 7/.
i %0W shht KY /-A 22 Joe w 1990-do1-411 *E 2 C^'C
- Olds @DUChar m .o < - <f r.
o,P t
=v ., un c coo un
- t. -
4 10 PURPOSE 1
To analyze the effects of a Boric Acid Spray (3000 ppn Boric Acid, pH = 5) on Rosenount 177HW-2 Resistance Tt.nperature I Detectors (RTD's) and Bailey Meter BY transmitters. This calculation is in support of Davis-Besse, Unit No. 1,79-01B j Ouslification Data Worksheets.
20 SCOPE This calculation applies to all Rosenount 177-HW-2 RTD's and all Bailey BYBB41X-A, BY3B40X, and BY3X41X-A transmitters installed at the Davi s-Besse Nuclear Power Station, Unit No.
- 1. his analysis will cover the effects that the Davis-Besse chemical spray will have on these components under the conditions of a postulated Loss of Coolant Accident (LOCA).
3.0 RE FERENCES
- 1. Letter from Rosemount to EDS Nuclear, Dated 12 /31/81, containing a drawing of the 177HW R"D (79-OlB Response Pe f e re nc e V-3 4 A ) .
- 3. Telephone conversation of 7/9/E1, between Dan Dutoit (Rosenount) and J. Abbate (EDS), regarding the Rosenount l
177-HN-2 RTD. (79-OlB Response Ref erence ROC 34E) l
- 5. Telechone conversation of 6/30/81, batween Bob Rand (Bailey Meter) and Bill Bellando (EDS), regarding Bailey BY transmitters (79-01B Response Ref erence ROC-SA) .
6 R&W Report No. 58-0881-00 (Bailey Transmitters) (79-01B Reference J-1).
- 7. " Corrosion Resistant Materials Handbook" by Ibert Mellan. Published by Noyes Data Corporation, 1966.
- 8. Davis-Besse Nuclear Power Station, Unit 1 FEAR.
O Tf , 9/toffl M* ']}/*)/ft -
i i FA 7hlrt X7 l-842
' Jos e ge 4ei..s *11 _
'"" 3
" or edS$nUCbcT /8*O - 88 ' - M I arv sv natt cwecato catt
s s e 4.0 METHOD OF ANALYSIS The exposed materials were identified by examining test reports, drawings, and parts lists of the units involved.
Knowing the exposed materials, their resistance to Boric Acid (ph=5) was detemined by a document search of published materials in the field of corrosion resistance.
5.0 BASIC DATA AND ASSUMPTIONS 5.1 Basic Data High-high containment vessel pressure, togather with either high containment vessel pressure or low reactor coolant pressure (conditions present during 1,0C A's) , will cause the safety features actuating system to open the containnent spray isolation valves and start two containment spray pumps. The pumps take suction intially from the horated water storage tank. The contai nment spray' systen shares the borated water storage tank supply with high and low pressure injection systens.
Af ter the water in the borated water storage tank reaches I
a low level, the spray punn suction is transferred tn t'e containment vessel emergency sump. The sump water is then recirculated for use by tha containment spray, hi gh I
l pressure injection, and low pressure injections systems.
I Baskets of Tri.modium Phosphate (Na3PO4) are available in the sump so that when sump flooding occurs, neutralization will result. The spray pH upon recirculation is then 7.0 or greate'r (FSAR 6.2.2 2.2).
o X 2 pen, Mr- sM/F
/ saw t/1/>< KT H 82
' Jose,0 /0 4) .0ds= 6*)/ _
'" M J
'I' 6 MkOI avo-su -,v t OF r
- 1. , ,, ,, ,,,,,,, ou 1
l
. e 5.0 BASIC DATA AND ASSUMPTIONS 5.1 Basic Data (Con't)
The chemical properties of the borated water storage tank (BWST) supply are 1800 ppm Boron at a pH value of This supply can last a approximately 5.0 ( FS AR 6.2. 3.1) .
maximum of approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> when minimum safeguards are operating (one containment spriy pump):
BWST Maximum Capacity 550,000 Gal.
(FS AR Table 9-14 )
Containment Spray Punp Capacity 1300 Gal./ Min.
(TSAR Table 6-6)
- B'MT Max imum Capaci tv BUST Maximum Depletion Time Containment Spray Pump Capacity (One Conteinment Spray Pump)
- 55n,000 Ga1.
1300 Ga1./ Min.
= 423 Minutes
= 7 Hours 3 Minutes During normal plant operations, the borated water storage tank At contains a mininum capacity of 360,000 gallonn (TSAR 6 3.2.6).
this capacity, the tanks's depletion time (with minimum safegaards operating) will be 4.6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s:
= 360,000 Gal BWST Depletion Time (One Containment Spray Pump) 1300 Gal./ Min
= 276 Minutes
= 4 Hours 36 Minutes f
l l
l i
I g> **"Bif'- 1/jefp o CT =pf,q}) /
f WM VW2L '
M7 l-243
' ~ " Joe no /gj 40/-t'1/ -
" * 'f j
MS O WDUCD8p caLeno gew-sur-JYL n,
y my my oats cwsenso eats l
l ._ e . -o _ _ _ , , . _ _ _ . . _ _
6 *
.% 0 BASIC DATA AND ASStMPTIONS 5.1 Basic Data (con't)
There is only a remota chance that merely a single containment spray pump will be in operation following a Ioss of Coolant Accident. This occurrence would only result fron deliberate operator action or multiple failures of redundant safety systems. The Safety Features Actuation System is designed so that both trains o' the high pressure injection, low pressure injection, and containment spray systen will operate following a Inss of Coolant Accident. With these norna) safeguards operating, the borated water storage tank supply (BWST) will last only 40 minutes. (15.4.6.4) 5.2 Assunptions
- 1. The " wash-off" and dilution effects that the prinarf coolant (which flashes to steam) would have on the chemical spray is not considered. This assumption makes the analysis more ,
conservative.
~
- 2. The analysis of each naterial in made assuning that the material is not painted. This assumption is conservative as some conponents are painted and would provide additinnal corrosion resistance. Only identified corrosion resistance enverings are accounted for.
- 3. For the purpose of this calculation, all 0-Rings and Gaskets are considered as exposed materials. In mnst cases, these meterials are under large compressive forces that limit their chemical spray exposure to little or none at all. Thi s assumption further adds conservatism to the calculation.
6.0 SLMMARY RESLTLTS The Rosemount 177Htf-2 RTD's and Bailey BY8841X-A, BY3M40X, and BY3X41X-A units are qualified by analysis for chemical spray exposure at Davis-Besse Unit 1. The exposed materials are all rated gnoi or above for corrosion resistance to Boric Acid (ph=5).
O Tfi 'Y.Y!) 5,~ WJ 9h2/1/
) M /}1/11 $Y-l'AN Joe No fagt .op/ -O/ paat /
i/
C * " or eids$fMJClO8r #
'8"/8 ~ 0'/ ~ # '# 1 Y nev sy amis cemento caTE
6 -
4 0 7.0 BODY OF CALCULATION 7.1 Rosemount 177-HW-2 FTD These units are ermpletely sealed, therefore, oniv its external casings and seals are exposed. In addition, these units are covered with a chemical resistant paint.
The exposed materials are as follows:
COMPONEh7 MATERIAL Header Stainless Steel Flexitallic Gasket 304 Stainless Steel Housing Aluminum Alloy 214 Materials a,nd Parts Ref erences: References 1, 2, 3, 4, 7.2 Bailey BY 'Dfpe Transmitters These units are completely sealed, and therefore, only the external casings and seals are exposed. In addition, these units are covered with a chemical resistant paint.
The exposed materials are as follows:
CO!!PONT.NT MATERIAL Amplifier Housing Aluminum Gaskets SBR (Styrene Butadiene Rubber)
Materials and Parts references: Ref 5 ,6 y k& '}/)a/2) %f 9//?N) i MM ih/su k7 /~ B-8 2.
" * * /*W ~***"
,,, u 9
2 by #119 % K1 3 2742 "** o' y pts eds()nUCISBP /* *8 -d * ' - * '/1 arv ev ute c acaso
j
' 7. 3 MATERIALS ANALYSIS
= e, S
MATERIAL CORROSION RESISTANCE W B03(ph=5) REF Up to concentrated boiling, 7 Stainless Steel fully resistant Corrosion so slight as to be 7 Aluminum negligible Good Resistance 7 SBR l
l l
olW 'Utoni W 9h!A) l 'Mu i/@i A'1 J t-82 JOS NO /gttt=00f 4 4 / '"Gl y
M I OF DAM /d W-d8/- W L [
mEV SV DAM CMECRED 1
l
- .- . -. . _