ML18043A572
| ML18043A572 | |
| Person / Time | |
|---|---|
| Site: | Palisades, Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/19/1979 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| TASK-08-04, TASK-8-4, TASK-RR NUDOCS 7903260213 | |
| Download: ML18043A572 (13) | |
Text
Gener<'\\! Offi:-:es: ~12 West Michig~n Avenue. Jac".<.son, Michigan 49'201
- Aro:;a Code 517 786-0550 r.Iarc:h 19, 1919 Lirector, Nuclear Reactor Regulation At.t Mr D :;:, Ziemann, Chief Opere.ting Reactors Branch i~o 2 US :ifaclear Regulatory Commission
~-iashington, DC 20555 DOCI<...t;TS 50-155 AND 50-255. - LICENSES DPR-6
.A~TD DPR PALISADES AND BIG ROCK POINT
?L.UVTS - EUC'I'RIC PEI:JETRATIONS OF P.RACTOR
'.:;0i'.?J:AI~TI'1:81IT, SEP TOFIC VIII-4
~iRC letter dated tecember 8, 1978 requested GonsLlID.ers Power Company to provide infor:naticn pertaining to a typical low-Yoltage containrne!l.t 3_Jenetration circuit, a typical medium-Yoltage penetration circuit and. a typical direct current power penet.rat.ion circuit at Palisades and Big Rock Point.
~he requested ~nfor~ation is proviced in Enclosure (1) for Falisades and in ~nclosure (2) for Big Rock Point.
Consume.rs ?ower Compa~y is concerned that the assumptions inherent in the intro-duction to your ~uest.ions are unnecess2.rily severe.
These assumptions appear t.o oe taken directly from Regulatory Guide l.63 dated July 1978.
Section D of tne
- uid.e states that it will be used in the evaluation of submittals for construc-t.ion permit applications docketed after August 31, 1978.
The original Guide was issued in 1973.
The Palisades ar..d Big Rock ?oint Plants are, of course, con-siderably older than this.
The implicat.io.:::i that a short ci:ccuit condition will develop simultaneously wi-;;h a ;:'aili.rre of tne :;:iri.:r!.ary prctective C.e--rice and at a time when contairi~ent in-tegrity is requir<.::C. see:ns to be ~induly ce>nser7ac;ive in tnat it exceeds the requirements oi' t11e siEgle: fai:'..u.re criteria.
7903260 J./3
2 Consumers Power Company concludes that this implication may be based on a scenario wherein a Loss of Coolant Accident (LOCA) occurs, causing hostile environment in containment, which in turn causes the worst expected fault.
The single failure criteria now requires that the primary protective deYice be assumed to fail.
The conclusion that LOCA conditions necessarily cause worse case faults even in "nonqualified" circuits does not seem to conform to typical design conditions or experience.
A number of containments have been pressurized in the past to design (or close to design) conditions and circuit faulting was not observed.
Secondly, the "nonqualified" circuits within containment usually contain the same general materials and equipment as the qualified circuits.
The difference is usually only the documentation provided.
Consumers Power Company concludes that the simultaneous occurrence of a LOCA, a maximum fault condition and failure of the primary protective device is sufficiently improbable that it need not be considered.
David P Hoffman Assistant Nuclear Licensing Administrator CC JGKeppler, USNR.C BCC SEP Owners Group
Question(l)
A.l.
Typical circuits selected A.2.
Provide trip curves (current versus time) for the primary and secondary protection devices A.3.
Maximwn short circuit current available to the selected pene-tration circuit A.lf.
Conductor size external to the electrical pene-tration B.l.
Manufacturer's electrical pene-tration identifi-cation number Size of conductor(s) in the penetration E{
Rated continuous
~.
current for each g
conductor
~
<D Circuit l Power to primary coolant pump P50A -
4160 VAC Attachment l*
30,318 amps**
(including max off-set - 44,870 amps) 11wo -
750 MCM per phase Viking Industries, Inc Type P-1, Part No 23-0052-0000 1500 MCM 790 full load arnps***
Circuit 2 Power to pressurizer relief isolation valve M0-1042A-48o VAC
- 417 amps**
(offset insignificant)
One -
- 12 AWG per phase Viking Industries, Inc Type P-5, Part No 23-0027-0000
//12 AWG 14 full load amps***
I-'
(l )Q 8
8 uestion numbers refer to the numbers used in NRC letter dated December
, 197.
Circuit 3 Power to bearing oil lift pump P81B-125 VDC
- 2405 amps**
One - #1/0 per pole One -
- 8 shunt field wire Viking Industries, Inc Type P-5, Part No 23-0027-0000
- 1/0 76 full load amps ****
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m Question(l)
B.2.
Rated short circuit overload Duration of rated short circuit over-load B.3.
Description of all electrical tests of these penetrations and results of these tests Circuit 1 Circuit 2 Circuit 3 80,000 amps 1,, 500 amps 15,000 amps 3 cycles 3 cycles 3 cycles See previous submittal dated 12/8/77 to J G Keppler from D A Bixel, Docket 50-255, License DPR-20, Palisades Plant - Response to IE Bulletins 77-05 and 77-05A (l)Question numbers refer to the number used in NRC letter dated December 8, 1978.
- In the case of breakers with more than one trip device (such as magnetic and thermal trip devices), the entire breaker was assumed lost.
- The faults were conservatively assumed to occur at the penetration inside of containment.
- In the purchase specification, the Architect Engineer provided these current valves (on the basis of listed load currents) to the penetration manufacturer speci_fying that the conductors and connectors inside the penetration be sized for these load currents.
- Table 17-23, Standard Handbook for Electrical Engineers 10th Edition, Fink, Donald G and Carroll, John M, McGraw-Hill, Inc, 1969.
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RESPONSE TO DECEMBER 8, 1978 NRC LETTER - BIG ROCK POINT PLANT REQUEST 1 Identify each typical circuit selected.
Response
Case A - Power to the reactor clean-up pump (typical low-voltag~ circuit, 480 V).
Case B - Power to the recirculation pumps (typical medium-voltage circuit, 2400 V).
Case C - Power to the emergency condenser outlet valve (typical direct current circuit).
REQUEST 2 Provide the trip curves.
Response
.case A - See Attachment 1..
Case B - See Attachment 2.
Case C - See.Attachment 3.
REQUEST 3 State the maxim.um short circuit available to the selected penetration circuits.
Response
Case A - 1,541 amps.
Case B - 18,450 amps.
Case C - 635 amps.
REQUEST 4 State the conductor (external to penetration), size for the circuit.
Response
Case A - 3 conductor 12 AWG.
Case B - 3 conductor 4/0 AWG.
Case C - 1 conductor 12 AWG.
Enclosure (2)
RESPONSE TO DECEMBER 8, 1979 NRC LETTER - BIG ROCK POINT PL.Al~, PAGE 2 REQUEST 5 State the manufacturer's electrical penetration identification number, size of conductors in the penetration and rated continuous current for each con-ductor.
Response
Big Rock Point penetrations were manufactured to a design specification pre-pared by the plant Architect Engineer.
No manufacturer's identification number exists.
The identification number in the following table is a Consumers Power Company number.
ID Iiiumber Conductor Size Rated Continuous Current(l)
Case A H-43 le 8 AWG 34 Case B H-87 le 4/0 AWG 176 Case c H-45 le 8 AWG 34 REQUEST 6 State the rated short circuit overload current and duration.
Response
See attachments.
REQUEST 7 Provide a description of all electrical tests*.for these penetrations a:.nd state results of these tests.
Response
The penetrations selected are identical to those used in Dresden 1.
Letter from MS Turbak (Commonwealth Edison) to Edson Case, December 9, 1977, dis-cusses the environmental qualification of these penetrations.
The specification called for an electrical test in which the penetration "units carrying the insulated conductors were meggered with a 500 volt megger and all readings read infinity on the most sensitive scale.
The readings were taken between adjacent conductors and between periphery conductors and the pipe."
(l)From ':L'able 27, Page 14-213, ?ender and Del Mar; "Electrical R..'1.gineers Handbook Fourth Edition,". Wiley & Sons, Inc, 1949.
Enclosure (2)
RESPONSE TO DECEMBER 8, 1979 NRC LETTER - BIG ROCK POINT PLAl.IJT, PAGE 3 Attachments 1-3 show the fault current, the protection device trip curves and current-time correlations. for when the conductor center line, and insulator inside wall become molten.
The correlations were calculated by solving heat transfer equations and assuming the following:
- l. No heat transfer out of insulation (or jacket, if jacketed).
- 2.
Instantaneous fault current applied..
- 3.
No credit taken for the fact that the conductor attached to the penetration is smaller and may melt first thus opening the circuit.
This calculation was performed because the thermal withstand capability has not been tested.
Enclosure ( 2)
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