ML20054J896
| ML20054J896 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/23/1982 |
| From: | Bordine T CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8206300178 | |
| Download: ML20054J896 (15) | |
Text
.
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Company General offices: 1945 West Parnell Road, Jackson, MI 49201 * ($17) 788-0550 June 23, 1982 Dennis M Crutchfield, Chief Operating Reactors Branch No 5 Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - CORRECTIONS TO APRIL 30, 1982 ELECTRICAL EQUIPMENT QUALIFICATION (EEQ) STATUS REPORT Consumers Power Company letter dated April 1, 1982 provided the NRC with additional information in response to the February 24, 1982 NRC letter concerning the environmental qualification of safety-related electrical equipment for the Big Rock Point Plant identified in the TMI Action Plan.
In addition to responding to several NRC/FRC questions, the April 1, 1982 letter also provided copies of test documentation and System Components Evaluation Worksheets (SCEW) for all installed TMI-related equipment. However, Consumers Power Company letter dated April 30, 1982, in addressing electrical equipment aging problem, inadvertently omitted the SCEW sheets and commentary supplemental pages for several equipment components.
The April 30, 1982 submittal also contained typographical errors found in the SCEW sheets. The intent of this correspondence is to correct these administrative mistakes.
The enclosed documents encompass the SCEW sheets which were omitted in the April 30, 1982 submittal. Typographical errors are also noted on the last page of the revision instructions of the enclosure.
In the " Insert Page" h[
oc0682-0008a142 8206300178 820623 PDR ADOCK 05000155 P
i l
D M Crutchfield, Chief 2
Big Rock Point Plant Corrections EEQ Status Report June 23, 1982 Column near the center of the page, and immediately below number 157, the numbers "152a, b and c" should have been "157a, b, and c".
The number "166c" should not have appeared since this page is nonexistant. Should you have any questions regarding this submittal, please so inform us.
W r
Thomas C Bordine Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector-Big Rock Point 2 pages oc0682-0008a142
I CORRECTIONS TO APRIL 30, 1982 ELECTRICAL EQUIPMENT QUALIFICATION STATUS REPORT BIG ROCK POINT PLANT ic0682-0008bl42
Section Remove Page Rev Section Insert Page Rev VI 118 3
VI 118 None VI 118a 3(New)
None VI 120 3(New)
None VI 120a 3(New)
None VI 120b 3(New)
None VI 121 3(New)
None VI 122 3(New)
VI' 126 1
VI 126 3
VI 127 1
VI 127 3
VI 129 VI 129 3
VI 130 VI 130 3
VI 132 VI 132 3
None VI 132a 3(New)
VI 140 1
VI 140 3
None VI 140a 3(New)
VI 1*2 VI 142 3
None VI 142a 3(New) 144 VI 144 3
145 VI 145 4
None VI 145a 3(New)
VI 148 VI 148 3
None VI 148a 3(New)
VI 150 VI 150 3
None VI 150a 3(New)
VI 152 VI 152 3
None VI 152a 3(New)
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VI 157 VI 157 3
None VI 157a 3(New)
None VI 157b 3(New)
None VI 157c 3(New)
VI 162 VI 162 3
VI 163 VI 163 3
None VI 165a 3(New)
None VI 165b 3(New)
None VI 165c 3(New)
None VI 165d 3(New)
None VI 166a 3(New)
None VI 166b 3(New)
None VI 174a 3(New)
None VI 174b 3(New)
None VI 175 3(New)
VI 177 2
VI 177 4
None VI 178 3(New)
VI 181 2
VI 181 4
~
None VI 182 3(New)
VI 185 VI 185 3
None VI 193a 3(New)
None VI 193b 3(New)
VI 212 2
VI 212 3
VI 217 2
VI 217 3
VII None VII Enclosure I 4
Doc 2395A-220A I
l I
^
Owner: Consumers Power Company f,3 Component Sheet No:
Facety: Big Itock Ibint Reh Dochef: 50-155 Date:
DOCUMFHiAilON nf Ff pfNCES l E NymONME NT EQUIPMENT DESCRPTION P.ometer Accident Ouenecanon Accident Oues METHoo HEMS System:
Opereeno Time Section Evaluation Post Incident 30 days 30 days 1
37,9 Plans l D. Nunter Temperesure 8I PT-200-201 l'FI 182 350 Test I1.E 1
Conwonent Pressure Transmitt.
- r Pressure Memdecourer:
les'Al 14.7 60 psig I
Test E
Rosemount ModesNumber Renouve Section 1152GP7A92PB FW l%I 100 100 1
Test II.E Pwchose Order Nwe6er chemicas Sp'*f None FuncitantService:
Containment Pres-4 6
Section sure Transmitter inein 5.2 x 10 5 x 10 1
Tm II.E Acewecy-Spec:
w Dona 8I 40 yrs +
Sheetr 2 1
L *c8888-Accident Electrical Pene-8**'"8'"C' tr g. Room N/A N/A
- =
I N/A Flood Loves Elevoson N/A s"
Above Flood Lovet N
Yes No-s DOCUMENT AilON REFEntNCES NOTES
- 1. Rosemount Report No 117415 Rev B " Qualification Tests.for RosemounJ Pressure Transmitter Model 1152".
wo D
0 0858 0l A
120b SHEET 2 COMPONENT Pre'ssure Transmitter Mfr': Rosemount Model: 1152GP7A92PB Plant ID No:
PT-200, 201 FUNCTION This pressure transmitter is used to provide a continuous indication of con-tainment pressure in the control room as required by the TMI Action Plan, Item II.F.1.
DISCUSSION The test report, Rosemount Report No 117415 Rev B, " Qualification Tests for Rosemount Pressure Transmitter Model 1152" shows that the transmitter is qualified for all accident parameters. The transmitters are located in a normally mild environment with no significant normal radiation.
The transmitters were preaged prior to the environmental tests. The transmitters will also be monitored for aging degradation as part of the Qualification Inspection Program.
Rev 3 3/26/82
EOtMPMENT OUALIFICATION REPOP.T Component Sheet No:
Owner Consumers Power Company NN -...
Fecety: Ilig Itock Ibint.
Date: March 17,1982 Docket: 50-155 ENVInONME NT DOCtJMENTATION nt FERENCES EOurpENT DESCf4PTION MEHOO HEMS p.e,neier Accident ousenceman Accident Owg Section Test 6 Hir ange Contain. [*""'
Ref 1 ment Radiation Aren 30 days 30 days II Evaluation Monitor (Camma)
Plant i D. Nwnbar.
Teenperature RE-8280, 8281 g.Fl 182 357 Section l
Ref 1 Test II.E III Detector (Camma) &
Caggny,mbly
" stay' Section Test p
7 7
Ref 1 II.E III Victoreen, Inc ucensseenber poemove 8'CEI "
877-1 Hu"*my lsi 100 100 Ref 1 Test II.E III i
i Pwchose Orest Munter 1000-5870-Q cheneces 0.45 CPM /Ft f
Spr*r None (See Note 1)
Ref 1 Test II.E III 7%,%,
Camma Radiation
- p.,e8ca 4
200 Mrads Monitor tRed:
7.6 x 10 Section Ref 1 Test (60co) Camma Rays II.E III o
Accuracy-Spec:
age,,
40 yr + Accident 40 yr + Accident
- E I
Loca"oa-Electrical Penetration Room urnergence Elevamon 614'-l 5/F None None N/A N/A N/A Y
f lood Level Elevenon N/A Above Flood tevel-9 Yes No' w
0%
NOTES DOCtJMENT ATION REFERENCES
- 1. Victoreen " Qualification Type Test Data Report for
- 1. Chem Spray Composition 0.28 Molar ll B03 (3000 gpm
[w 3
Class lE Victoreen liigh Range Containment Area Baron) and Na0li to Make a pil of 11.03 0.5 0 20 C Monitor System", 950.301, Signed June 19, 1981; (77 F)
Doc ID I 72-0329-1 771 51-31 (Ref : FC 520) 2.1hese sheets supercede existing pages 121, 122, 123 j
in their entirety since Model Cp-MU was temporary devi e.
0 0658 0l A
122 COMPONENT Detector Mfra Victoreen, Inc.
Model 877-1 Plt. I.D. No. (s) : RE-8280 & RE-8281 FUNCTION Detectors RE-8280 & 81 are used to detec: raaiation emanating from fission and activation products released to the containment as a result of accident conditions. These detectors convert in direct proportion, the radiation levels being monitored into microampere range direct currents for transmittal I
to the control room.
DISCUSSION These detectors are the primary element of a total measurement system.
The aetector is a stackeo plate, three terminal, guaraed ionization chamber, hermeticallly sealed, and operated in the saturated moce. All external surfaces are 316 stainless steel. Basic materials used in construction are stainless steel, aluminum, nickel anc ceramics which have a lifetime much in excess of forty (40) years ano therefore aging is not a constocration for these materials.
Tne detectors are located in the electrical penetration room adjoining the containment.
The containment shell forms a common wall between the vessel and the electrical penetration room. Theretore, the cetectors will only be subject to the environment which is transferrec through the sphere. The highest containment wall temperature at the trip set point is about 150.
~
0 This as a result ot a very small steam line Dreak. Larger breaks result in a faster time of high containment pressure trip and lower wall temperatures.
The normal environment in the room is 400-1000F (seasonal variation).
The electronics are located in the unit control room which is a " mild" environment.
Since the detectors are located outside containment, in the electrical penetration room, chemical spray and submergence need not be aadressed.
CONCLUSION These oetectors are qualified for the environment to which they are subjectea.
Rev 3 3/26/82
EQUIPMENT OUALIFICAT10N REPORT Revision:
Facety: liig Itock Point Date:
Docket: 50-155 ENVIRONME NT DOCUMf NT ATION IW F FRE NCES OUALIFICATION OUTSTANDING EOUer4AENT DESCf4PTION METHOO litMS Poeneter Acc1 dent Ouehacemon Accident Owg syseen.
Opses%
Emergency TW Section Test &
30 days 30 days II.D 1
Evaluation Condenser Plant i D. Nwieer-yp, Section SV 943
/944, l'F) d 235 385 II.E 1
49 Evaluation Solenoid Valve Presswo M'nusecourm A
Section Test &
41.7 80.7 y
Target Rock II.E Evaluation undetNw eer Neseeve 768-021 H*'*"r l%I 100 100 Section Test &
3 II.E Evaluation Purtfisse Onser Nwseer BPC Not Subject 7720-3-256 Fwicsontservece:
to Spray Remote Ventin8 Rossaan of Primary Coolant IRedi 8
Section Test &
7.3 x 10 1.35 x 10 j
Non-Condensible Gas II.E Evaluation Accwecy: Spec:
3,,,,,
40 years +LOCA 40 years +LOCA 1
tm Containment
%,,,,c, Eleveson Not Subject 660' 6" l to Submergence
{
F tood Level g
Elevaton 590' Above Flood Level:
w Yes: X No-a os DOCUMENTATION RFFERENCES NOTES os
- 1. Target Rock Corp. Qualification Test Report vi
- 2375A - 9/26/79 N
- 2. Communication Record 8/7/80 (Telecon)
HRWade, CPCo to Fred W Ferri, Target Rock 0 06'38 01 A
157b COMPONENT
~
Solenoid valves Mf t's Target Rock Model 76B-021 Plaht P.D. Nos.:
SV-4943, 4944, 4945 and 4946 FUNCTION These solenoid valves provide a controlled means of venting primary coolant non-condensible gases to the containment through either, or both, emergency condenser tube bundles. The valves are operated remotely from the control room ano are installeo in two groups, one group for each side of the emergency concenser with each of these groups having two of the valves in series. This oesign provides the redunoancy required for the venting of any primary coolant non-condensible gases.
DISCUSSION Document Reference 1 reports the testing performed by the Target Rock Corporation on a 1" solenoid valve. Document Reference 2 Justifies applying l
the test results from the Target Rock report on the 1" valve to the 3/4" valves installeo at Big Rock Point (BRP). Qualitication of the subject 3/4" valves baseo on 1" valve test results is Justified because the electrical portions of both the installed ano test valves are ioentical.
The test program reported in Document Reference 1 included the following:
1)
Radiation aging of the test valve to 2.2 x 107 rads of gamma exposure.
- 2) Thermal aging of the test valve at 3500F (176.670C) and 55%
relative humidity (RH) for 792 hours0.00917 days <br />0.22 hours <br />0.00131 weeks <br />3.01356e-4 months <br /> or 33 days. During this segment of the testing the valve was cycled once each oay by energizing the solenoid with 120Vac.
3)
Repetitive cycling of the test valve (18,000 cycles) at a rate of 1800 cycles per. hour in a test chamber maintained at 1220F (500C) and 90% RH for ten hours. This cycling was accomplisheo by energizing the solenoid with 120 Vac.
4)
Seismic testing in accorcance with IEEE-344 (1975).
5)
Design Basis Accioent (DBA) testing at peak temperatures ranging from 3650F (196.10C) at one-minute after initiation, falling off to 3120F (155.50C) after three hours.
Rev 3 3/26/82
157c During these temperature transients test chamber press,ure ranged between 79.7 and 80.7 psia. Temperature and pressure conditions were achievea by injecting into the test chamber steam and water chemical sprays. The chemical makeup of this spray is detailed in Document Reference 1.
During this segment of the testing the valve solencio was energized for thirty secono bursts at times 2, 10, 60, 120 and 180 minutes and subsequently ceenergizec. valve operation was verifiea by position switch inaication anc observed flow from the outlet port.
6)
Post DBA testing whose initiation was integrated with the conclusion of the DBA test.
From time three hours until the conclusion of the Post DBA test at time 14 days temperature ano 0
pressure decayed from 312 F and 79.7 psia to 2150F and 25.7 psia. Cycling similar to the cycling performed curing the DBA test was performeo auring the Post DBA test.
- 7) Additional radiation exposure of 12.6 x 106 rads of gamma simulating a postulated accident dose. This was followeo by additional gamma exposure of 1 x 108 rads for a total integrated test dose of 1.35 x 108 rads gamma.
8)
Before, during, and after the environme*ntal testing, functional testing of the valve was performed as cetailed in Document Reference 1.
CONCLUSION Tne parame ters of the test program far exceecea the postulated accident conoitions at BRP in all respects anc tnerefore the 3/4" Target Rock solenoid valves installed at BRP are consicereo qualified for the perioc documentea on the SCEW sheet.
1 Rev 3 3/26/82
EQUIPMENT OUAl.lFICATION REPORT Owner: Consumers Power Company h--
Revision:
Facety: Dig Hock I'oint g.'
Docket: 50-155 ENVIAONMENT DOCUMENT ATION HE FERENCE S ENNN WDM HEMS p emoser Accident a,eenceman Accident Oad system:
Opwoung Tw.e Section High Point Vent 30 days 30 days II.D 1
Test Pint i D. Nwiser Temperature g*Eg Section g
235 340 II.E I
Test e r,, Mod ul e s Con 33 Section 1
41.7 180 psig II.E 1
Test l
Conax Corp.
u %.
peneuve I
ou,,een, pg Section 08}:hi 100 100 II.E 1
Test N;:,N}rchese onsor Muster l
1000-3391-Q Boric Acid and Section Water NA0ll N/pil of 10.5 II.E 1
Test 7
g,.
Environment Seal Section on Solenoid Valves 7.3 x 105 8
2.238 x 10 Rad II.E 1
Test
- "'C
8*
A '"9 Section Teat &
9 D'"'*:
40 yrs + LOCA Sheet 2 l
II.E Evaluation Locaemn Containment
%,,,,c, EW
- o None
> 590 g
w Flood Level Elevaton 590 Above Flood Level:
W Yes.X No:
~
n n
DOCUMENT ATION REFERENCES NOTES
~
~
1.
Conax Corporation Test Report No IPS-409.
[
G on5801A
174b Sheet 2 COMPONENT Conductor Module Mfr: Conax Corporation Model: N-11001-50, 51 Plant ID No: -
FUNCTION These conductor modules are used to provide the environmental seal at the electrical cable opening of the High Point Vent solenoid valves SV-4943, 4944, 4945 & 4946.
These valves are used to vent noncondensible gases from the tubes in the Emergency Condenser.
DISCUSSION The Conax Corporation Test Report No IPS-409 shows that the conductor modules are qualified for all accident parameters. The aging qualification was completed via a test where the test sample was cycled 5 times from 30 F to 150 F,120 times from 350F to 1450F and maintained at 249.80F for 169 hours0.00196 days <br />0.0469 hours <br />2.794312e-4 weeks <br />6.43045e-5 months <br />. The qualified life was obtained from evaluation of this test data. These conductor modules will be included in the Qualification Inspection Program which is being developed to monitor the effects of aging and to provide for the replacement of equipment which has reached the end of its qualified life.
Rev 3 3/26/82
EOUIPNIENT OUALIFICATION REPORT Component Sheet No:
Flevtsion Facety: 1116 Rock Ibint Dochet: 50-1$5 EPMRONMENT DOCUMFNTATION MrEMNCES EN NNM uE nm HEuS Peressieser Accident o m enon Accident Oud system Op*'"ano Section I'"*
fliscellaneous 30 Days 30 Days II D 1
Test Peet I O. Nueer Tenoersewe Section 235 346 II.E 1
Test coveonent Note 1 Pressw e Section uommeswer-A^l 11.7 127.7 II.E 1
Test Rockbestos Modul N N
Seetion l
Firewall III Hwwdny ist 100 100 est II.E l
Pwensee onsor Nweer l
61629-0 Not Subject To Spray resw Electric Control Re8=#on 1 32 x lo' Beta section Cable M
8 5
2.0 x 10 g,,,,
77,g y
7,,t 73x10 Gama ACC"'*cr Spec:
Ao'no Test and ec Mon 10 Years + IDCA Is0 Years + IhCA 1
Evaluation 1
tocoman.
II.E Containment 8*"8'"*
- Not Subject
""~
i To Subinergence
~~
~~
~~
+7 riood tevel 4
Elevenan La8 Above Lovet Yes.
No-DOCUMENTATION MFEMNCES NOTES D
1.
Qualification of Firewall III Class 1E 1.
Electrical Cable 2/C #12 AWG XLPE/NEO Electrical Cables - QR #1806 7/C #12 AWG XLPE/NEO (IRRADIATION CROSS-i. INKED INSUTATION) 0 0858 0f A
's
193b Sheet 2 Com'onent Cable p
2/C 012 AWG, XLPEANEO, Firewall III, 600 V 7/C #12 AWG, XLPE/NEO, Firewall III, 600 V A.
Document Reference 1 demonstrates that the cable with identical insulation is qualitiec (without taking any creoit for the 3acket) for use insiae the containment baseo on 40-year life and LOCA. The test cycle incluced the following:
1.
Thermal aging at 150*C (302*F) for 1,300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> (against the requirement of 850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br /> to simulate a 40-year life); gamma radiation from a Cobalt-60 source for a total dosage of 2 x 108 raos; a LOCA simulation test with chemical spray at a peak temperature of 346*F; 100% relative humidity ano a peak pressure of 113 psig. Total duration of test was 30 cays.
2.
After completion of a LOCA test, further thermal aging at 200*F and l
100% relative humidity for 365 days.
3.
Dielectric test for 5 minutes at 80 V ac/ mil was performed af ter LOCA ano thermal aging tests while immersed in water.
B.
No credit has been taken for the neoprene jacket furnished.
It is concluced that the temperature, radiation, humidity and aging requirements have been exceeaed by a substantial margin ano, therefore, tne cable is qualified for use in this application.
Rev 3 3/26/82
_