ML17261A111
| ML17261A111 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/12/1979 |
| From: | Saddock H ROCHESTER GAS & ELECTRIC CORP. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| TASK-08-04, TASK-8-4, TASK-RR NUDOCS 7904230168 | |
| Download: ML17261A111 (52) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTFM (RIDS)
ACCESSION NBR '7904230168 DOC- ~ DATE: 79/04/12 NOTARIZED:
NO DOCKET ¹ FACIL:50-244 ROBERT EMMET GINNA NUCLEAR PLANT, UNIT 1, ROCHESTER G
05000244 AUTH BYNAME AUTHOR AFFILIATION SADDOCKiHsG ~
ROCHESTER GAS 8
ELECTRIC CORPo Z IEMANNe D' L ~
RECIP ~ NAME RECIPIENT AFFILIATION OPERATING REACTORS BRANCH 2 VCkWEalm.
SUBJECT:
FORWARDS INFO REQUESTED ON 781208$
RE TOPIC VIII~4g ELECTRICAL PENETRATIONS OF REACTOR CONTAINMENT~
W/19 OVERSIZED DRAWINGS ENCL ~
DISTRIBUTION CODEi A001S COPIES RKCEIVEDSLTR "M'NCL ~
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
~OKVVDUM FOR:
TERA Corp.
FROM:
SUBJECT:
US htKC/TIDC/Distribution Services Branch Special Document Handling Requirements O 1.
Please use the following special distribution list for the attached document.
0 2.
The attached document requires the following special considerations:
Do not send oversize enclosure to the KLC PDR.
Only one oversize enclosure was received please Q Pzopziatazy information - send adfidavit only to the NRC PDR Q Other(:specify) cc.
DSB Piles TIDC/DSB Authorized Signature
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- IfIIIIIIIIIIIIItIIIIIIIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION 41 S9 EAST AVENUE, ROCHESTER, N.Y. 14649 HARRY G. SADDOCK VICK PRKSIOKNT Director of Nuclear Reactor Regulation ATTN: Mr. Dennis L. Ziemann, Chief Operating Reactors Branch No.
2 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 April 12, 1979 TCCCPHONK ARCA COOK TIK S46 2 C~
Crr Pp
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mph lTl H
CO Vl 700
Subject:
Systematic Evaluation Program Topic VIII-4, "Electrical Penetrations of Reactor Containment" R. E. Ginna Nuclear Power Plant, Unit No.
1 Docket No. 50-244
Dear Mr. Ziemann:
Enclosed is the information regarding electrical penetrations of the reactor containment at the R. E. Ginna Station, as requested in your December 8, 1978 letter.
Very truly yours, 7~ A Harry G. Saddock Enclosure 0(
57
4 C.
Sg U
C
Rochester Gas S Electric Corporation R.
E. Ginna Nuclear Power Plant SEP TOPIC VIII-4 ELECTRICAL PENETRATIONS of Reactor Containment, DOCKET NO.
50-244
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Table of Contents Section Title Objective Analysis Testing Conclusion Appendix A - Block Diagrams Appendix B Relay and Fuse Curves Appendix C Electrical Penetration Drawings
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1.0
~Ob'ective The purpose of this submission is to provide the ad-ditional information requested in Mr. Ziemann's letter dated December 8,
- 1978, concerning electrical pene-trations.
It will also be shown that the electrical penetrations presently in service at Ginna are capable of maintaining containment integrity during the worst case short-circuit current conditions.
The worst case conditions are also taken coincident with the failure of the primary overload protection devices.
Failures could result from either loss of control power or a stuck breaker.
2.0
~Anal sis 2.1 There are presently seven different types or configura-tions of electrical penetrations in use at Ginna Station.
These penetrations were manufactured by the Crouse-Hinds Corporation and are identified by configuration types A
through G.
Details of each penetration can be seen on the Crouse-Hinds drawings enclosed as Appendix C of this submission.
In addition to the original seven
- types, a Westinghouse type WX-32714 was installed as part of the in containment T.V. modification.
This penetration was designed for multi-purposed, low voltage power, control and instrumentation applications and conforms to IEEE 317, 1972.
Design details are shown on the Westinghouse penetration drawings included in Appendix C.
2.2 Typical circuits representating each of the seven different electrical configurations were selected.
These circuits are identified by their penetration numbers and are tabulated on Column 2 of Table 1.
Appendix A contains'block diagrams for each typical circuit selected, showing the primary and backup pro-tection devices (breakers or fuses) and all cable information.
All breaker and/or fuse information are also shown on Table 1 Columns 9
6 11.
2.3 Maximum fault currents were calculated for each circuit selected and these values are shown on the respective Block Diagrams.
The worst case current values as seen by each electrical penetration and tabulated on column 7 of Table 1.
A postulated three phase bolted fault is assumed at each penetration.
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2.4 2.5 The manufacturer (Crouse-Hinds) has tested two of the seven electrical penetrations.
The, test shows the maximum short circuit current that the two "power" penetrations configurations A and E can withstand without, mechanical damage.
This data is shown in Table 1, column 4 as "max-current withstand RNS Amps".
The withstand values for the remaining five configurations were derived from manufacturer's calculations using a
ten to one safety factor.
The I t values for each type penetration are shown in 2
Table 1, column 5.
These values were obtained from either manufacture's calculations or from IPCEA P-32-382 Short Circuit Characteristics Of Insulated Cable which-ever was more conservative.
Once the I t values were established, they were used to 2
determine the maximum allowable time that the penetration can withstand the actual fault current.
These time values are then compared against the backup breaker clearing times for each circuit and shown in column 8
of Table 1.
2.6 The trip curves (current versus time) for both the primary and backup clearing devices are enclosed in Appendix B.
The curve numbers are referenced on each block diagram.
The actual clearing times are shown on column 10 and 12 for each circuit.
3.0 The manufacturer has performed Short Circuit Testing on their power penetrations (types A
& E).
The objective of these tests was to investigate the short circuit current capabilities of each penetration type.
The results of this test'ing indicated that the N2 ANG penetration withstood 37.4 KA (rms) for 3 cycles, and the 750 mcm penetration withstood 80 KA for 10 cycles.
No visible damage or gas leakage resulted.
4.0 Conclusion The penetration must retain structural integrity when subject to mechanical stresses caused by the maximum available momentary fault current.
The withstand values are shown in column 4 and the corresponding maximum momentary fault current is shown in column 6.
For those withstand currents determined by analysis, a
safety factor of 3.3 was used.
Thus although the maximum momentary current in penetration AE-5 (3500 A) is above the tabulated withstand current (1400 A), it is well below the current at which mechanical damage is expected to occur (4662 A).
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Characteristic Curves 2.
G22102 Identification 1.
RCP1A-1 Circuit No.
CE-25, 27 AE-6 3.
Case Shawmut A50P FORMIOI AMP-TRAP AE-5 4
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Appendix C
Crouse Hinds Drawings/Numbers 0100350 0100044 0100251 0100252 0100253 0100254 0100259 0100261 0100308 0100314 0100334 0100342 0100411 0100416 0100696 Sheets 1 through 3
Sheet 1 of 1 Sheet 1 of 1 Sheet 1 of 1 Sheet 1 of 1 Sheet 1 of 1 Sheet 1 of 1 Sheet 1 of 1 Sheet 1 of 1 Sheet 1 of 1 Sheet 1 of 1 Sheet 1 of 2
Sheet 1 of 1 Sheet 1 of 1 Sheet 1 of 1 Westinghouse Drawings E 2802 Rev.
C E 2850 Rev.
B