ML20235C448
| ML20235C448 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Zimmer |
| Issue date: | 03/23/1979 |
| From: | Flynn J CINCINNATI GAS & ELECTRIC CO. |
| To: | Savio R Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML20234A777 | List:
|
| References | |
| FOIA-87-40 NUDOCS 8707090423 | |
| Download: ML20235C448 (44) | |
Text
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Till0 CINCINNATI G AS & ICIECTIU C COM l'AN Y M*-
etuclN N AR OMIO d 5 Pol d' Hi l
d i ou ccy.tR:h 23, 1979 mer ris
""""* wi canas
'Dr. Richard Savio bb U.S. Nuclear Regulatory Commission N!
Advisory Committee on Reactor Safeguards 7 bbl 0lldi tog 1i l
Washington, D.C.
20555 1r
.t-RE:
WM. H.
ZIMMER NUCLEAR POWER STITION -
UNIT 1 - ACRS FULL COMMITTEE MEETING MARCH 9, 1979
Dear Dr. Savio:
1 During the ACRS Full Committee Meeting on March 9, questions were asked by Dr. Okrent and Mr. Ray for which the Applicant did not have answers available in the meeting room.
Attached to this letter are answers to those questions.
Six copies of this letter and its attachments are transmitted herewith.
As we discussed over the phone, because of the form in which the swing curve data is produced by the computer, only one set of swing curves is being transmitted.
Your consideration in this regard is appreciated.
Very truly yours, TIIE CINCINNATI GAS & ELECTRIC COMPANY By
[
f JAME D. FLYNN, Manager Licensing and Environmental Affairs JDF: dew Enclosures
- anmean, a
8707090423 870610 Ik PDR FOIA THOMAS 87-40 PDR
+
ACRS 227th General Meeting March 9, 1979 Stability Question - Page 499 T h e r e s p o n s e,ix) question 222.12 did not include a swing curve for loss of ZPS-1 because that particular case However, this swing curve is was not a " worst" condition.
and indicates that a provided herewith (Case 80 STAB ZIM124)
The effect of the dis-Stuart unit is the "most marginal".
and Miami turbance on other units at Conesville, Beckjord, Fort is also shown.
Of the three stability cases noted in answer to reflects the most marginal question 222.12, Case 80 STAB ZIM123 The swing curve is provided swing condition for the ZPS-1 unit.
(Amos).
and also shows a remote system reference machine
- herewith, The following describes stability studies noted above:
80 STAB ZIM123 Three phase fault at Zimmer on Silver Grove 345 kV Circuit Fault clears at Silver Grove in 3.0 cycles.
circuit.
Pault clears at Zimmer in 10.5 cycles breaker at Zimmer fails.
by means of breaker failure relays clearing all circuit breakers This opens the Zimmer-Stuart,345 kV on Zimmer 345 kV Bus Number 2.
aircuit.
Zimmer and Amos units are stable.
Result:
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80 ' STAB '. ZIM124 Three phase fault at Zimmer on' Silver.' Grove 345 kV-circuit..: Fault. clears'at Silver Grove in 3.0 cycles.
Circuit
~j
- breaker.,at.Zimmer. fails.
Fault clears.at Zimmer in 10.5 cycles by j
'r 1
means.of breaker failure relays which cause the'Zimmer unit to be l
tripped.
4 Result:
Stuart, Conesville, Beckjord, Miami Fort,-
- and Amos units are. stable.
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' Emergency Load Capability Question - Page 500 There are three 345 kV circuits which leave the Zimmer 345 kV Substation.
These are Port' Union, Stuart, and Silver Grove circuits.
The Port Union and Stuart circuits leave Zimmer Substation on the same tower to form a double circuit for about one-half mile.
If both of these lines were lost at one time, the remaining Silver Grove circuit would be required to carry the output of the Zimmer unit.
This unit is rated 840 megawatts, 22 kV, 0.9 power factor which is ab'out
}
j 1562 amps maximum on the 345 kV system.
The normal summer rating of the Zimmer-S lver Grove 345 kV circuit is 2360 amps.
The' emergency summer rating of the Zimmer-Silver Grove 345 kV l.;'
circuit is 2878 amps.
The ratings of wave traps and circuit l-breakers on this line are 3000 amps.
Thus the Silver Grove circuit has sufficient capability to carry the output of the i
Zimmer unit.
!; ),
Spinning Reserve Question f
The CG&E spinning reserve policy is to have 3% of f-the daily system peak load as spinning reserve.
e 4.
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f RESPONSE TO DR. OKRENT'S QUESTIONS ON POST-LOCA MONITORING 9
The Primary ' Containment Atmosphere Radiation Monitor-ing System described in Subsection 7.6.1.8 of the FSAR is designed to monitor the radioactivity level of the primary containment following a loss-of-coolant. accident (LOCA).
The overall system, which has redundant units, monitors for gross gamma radiation, hydrogen and oxygen by means of a small, closed-loop sample line.
f One of the major advantages of locating the monitor outside the t
primary containment is the significantly lower radiation levels i
e which the radiation monitor must be designed for.
The radiation monitor has a range of 0.1 to 10 mr/hr.
Using the assumptions of Regulatory Guide 1.3 for conservative radioisotopic releases and technical specification leak rates, the post-LOCA doses at the Exclusion Area Boundary (EAB) have been conservatively calculated l
to be 20 Rem whcle body 'and 111 Rem thyroid for the initial two-t bour period.
For these same release conditions, the sample line radiation monitor is expected to read a maximum of 1.6 x 104 mr/hr.
1 In order for 10CFR100 dose limits to be reached at the EAB (i.e.,
t 4
l 25 Rem whole body), the detector would have to read 2.0 x 10 mr/hr.
i Using our best estimates of the source for the LOCA condition, we would expect the detector to read 1.0 x 10 mr/hr.
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SUMMARY
STATUS GE MARK lli L
OTHER BWR CONTAI NMENTS 1
I NTRO D UC TI O N A.
Summary of Presenta+ ion B.
Ba ckg rou nd 1.
Des cription of Containment Types 2.
Summary of Test Frograms 3.
S ta+us o f Revi ew Mark til 4.
Status
- Mark i
il 11.
TECHNICAL ISSUES A.
Pool Dynamic Phenomena 1.
Test I n fo rm at i o n 2.
ACRS Concerns (Model D ev elo pmen t) i 3.
Relief Valves l
4.
LOC A Fool Dynamics B.
Other Mark 111 issues 1.
Co ntainment Vacuum Br eakers 2.
Multi node Contai nment Model l
3.
Drywell External Pressure iII.
SUMMARY
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SUMMARY
0F PRES ENT ATI.O N l
RESPOND TO ACRS REQUEST OF APRIL 14, 1975 CONCERNING OUR REV I EW 0F BWR CONT A I NMENTS l
[
k DESCR IBE B AS IS ON WHICH P0OL DYNAMIC LOADS ARE BEING DETERMINED (RV/LOCA)
RECENT ACTIONS TAKEN ON MARK L
l'S AND ll S
J
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Background
1.
Description of Containment Types Mark 1
Mark 11 Mark til 2
Summary of test programs a.
Humboldt-Bodega Bay b.
Mark til small scale large scale c.
Marviken 3.
Summary of Analytical Codes a.
GE (NED0-10320, NED0-20533) b.
NRC (ANC)
( CO N TEMP T) 4.
Status of Revi ew Mark 111 l
a.
meetings (1972-1975) b.
reports and letters I
c.
outstanding items LOC A pool dynami cs relief valve loads conta inment vacuum b r eak er s
.,,,.o i
L mult i no d e co nta i nmen t model drywell external pressure (Clinton) 5 Status of Review Mark i
11 GE Limerick /Susquehanna LaSalle i
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OYSTER CREEK NINE MILE 1
DRESDEN 2&3 QUAD CITIES 1&2 j
MILLSTONE 1 BROWNS F E R R Y 1, 2 & 3 MONTICELLO
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(1972) 5 single valv'e tests 4 multiple valve tests Bro wns Ferry 1
(1973).
i 43 single valve tests 14 mult i p.le valv e t ests German Test I nf o rm at i o n
( 197 2-19 7 5)
In-plant testing
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G E Small~-S cale Tes'ts (1972) l 3-4 inch ve'nts 67 tests L
CE Mark 111 Test P rog ram (1973-)
full scale 1, 2,
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Air tests S er l es 5705, 2
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Third Scale tests S er i es 5801, 3
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4.
LOC A Pool Dynam i cs a,
ch ro no lo gy Mark 111 steam tests (12/73) air tests Grand Gulf ACRS review (5/74) 1/3 scale tests (6/74) initiate ANC effort (1/75) staff letters to Mark 111 (2/75)
GE letters to Mark I
and 11 (2/75) two Mark 11 plants hold construct ion o f. parts o f containment (3/75) staff letters to Mark I
and 11 (4/75) l l
r.
b.
review status a
l (1) loads must.be l
determined with l
appropriate justifica-
{
tion for each plant l
1 (2) testing will probably 1
l[
be required for Mark j
i and 11 (3) not an immediate i
l saf ety concern for operating plants (a)
GE analysis for i
typica1 Mark i
(b)
Humboldt-Bodega i
Bay tests
[
(4) operating plants should respond to our letter l
,j within 60 days l[
(5) plants under construc-j
. l tion should provide a i
schedule for response within 30 days I
1
L c.
actions l
( 1) letters to Mark I
and 11 (a) request for information location and or'ientation of structures magnitude of potential loads justification for loads structural capability (b) back g ro und i n fo rm at i o n al pool dynamics (c) description of phenomena and standard nomenclature (2) letters to Mark 111 (a) s imilar to I
and 11 (b) back gro und on ACRS. co nc er ns (c) request respons e to ACRS con cerns (3) letter to GE (Case to Bray)
(a) extrapolation o f Mark 111 data to Mark I
and 11 useful as interim measure (b) strongly urge Mark i
and 11 testing I
(4) future efforts i
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B.
Other Mark 111 issues 1
Containment Vacuum Breakers (sizing unresolved on all Mark til steel containments) a.
poss ible go vern ing tran s ients break in conta inment followed by spray operation inadvertent spray operation (low initial
- humidity, h igh temperature) b.
staff pos ition demonstrate governing trans i ent,
size vacuum breakers on that basis or size on basis #1, use Tech Specs to ma inta in contai n-1 ment atmosphere RH&T with-in acceptable limits
p.
2.
Multinode Containment Model r
(Wetwell) a.
detai1s of model.to be sub-mitted by GE b.
all applicants have made commitment to open up flow l
area at HCU floor if necessary t
t I
.I
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3.
Drywell External Pressure l
a.
co nc er n sudden steam co ndensat ion at end of blowdown dropping drywell pressure below contai nment pressure b,
condensat ion mechanisms ECCS sp illo v er expulsion of pool water into drywell due to de-pressurization / chugging wall condensation i
c.
test data PSTF water level instrumen-tation indicated swell above weir wall height d,
staff position:
drywell external design pressure based o n bound ing calculati on max imum conta inment P based on 100%
air carryover, saturated at pool T
minimum drywell P
based on saturation pressure at d ry-well temperature results in external design p
of 17-21 psid
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