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I jc0 i UNITED STATES L ;
I NUCLEAR REGULATORY COMMISSION s y
- j j WASHINGTON, D. C. 20555 o !
MAY 2 6 1977
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MEh0RANDUM FOR: W. Pike, Project Manager, Light Water Reactors Branch No. 3, DPM FRCN: G. Lainas, Chief, Containment Systems Branch, DSS
'IIIRU: R. Tedesco, Assistant Director for Plant Systems, DS I i
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR E TOPICAL REPORT NEDE-21078-P (TAC-3619) l NEDE-21078-P l Report Nu:6er:
Report
Title:
Test Results Employed by E for BhR :
Containment and Vertical Vent Loads (' ,
Responsible Branch: LhR-3 l Project Manager: W. Pike i Requested Completion Date: N/S j Incomplete Review Status:
Ey letter dated December 20,1974, (I.F. Stuart to E. G. Case),
E proposed a technical specification limit for the suppression pool temperature. Specifically, the proposed technical specification requires operator actions to limit the bulk pool temperature b61ow 1600F to avoid '
steam quenching vibration during safety / relief valve operation. This limit was established on the basis of experiments perfomed in a foreign countIy. E also submitted a sumary of the test results to support this limit.
E submitted topical report (NEDE-21078-P) to justify this limit. ,
As a result of our evaluation, however, we find that the infomation i provided in the topical report does not totally justify this limit.
Data indic~ ate that excessive steam quenching vibration can occur at a bulk pool temperature significantly below the E proposed temperature limit. We, therefore, cannot conclude on the adequacy of this pool temperature limit for containment designs using a ramshead device '
(this includes Mark I and Mark II types). We have prepared the enclosed request for additonal information, and have dis assed this request l
Contact:
T. Su X27711 8604010030 860114 PDR FOIA FIRESTD85-665 PDR fs
i W. Pike .,
They are aware of the kind of information i
with GE during several telecons. Note that the enclosure contains we need to complete our review. t should be handled accordingly.
proprietary information, therefore,
[-
Gus C. Lainas, Chief for Containment Systems Branch Division of Systems Safety
Enclosure:
As stated cc: S. Hanauer F. Schroeder R. Tedesco J. Glynn C. Long O. Parr D. Vassallo J. Guibert C. Grimes S. Miner R. Cudlin J. Kudrick J. Shapaker R. Boyd (w/o enc 1)
W. Mcdonald (w/o enc 1)
T. Su 3
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Request for Additional Information Topical Report Evaluation Report Number: NEDE 21078-P Report
Title:
Test Results Employed by GE for BWR Containment and i Vertical Vent Loads j Originating Organization: Containment Systems Branch 2 Reviewed By: T. M. Su l The following request for additional infonnation is related to the content in Chapter 4 of NEDE 21078 regarding temperature threshold for high temperature condensation oscillation during safety relief valve (SRV)
I discharge. l
- 1. Figure 4.3-1 (Straight Pipe Condensation Map) shows that the transition !
I' pool temperature from smooth steam condensation (Zone 3) to pulsating condensation (Zone 4) is 1E8*F. Figures 4.3-2 and 4.3-3, however, l show that pulsating condensation occurs when water temperature is above 120*F. To clarify this discrepancy, provide the following additional information:
(a) Provide the data base used to define each condensation zone of {
Figure 4.3-1. Infonnation should include the pressure measurement
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at the pipe discharge, tank walls and tank bottom for various pool temperature and mass flux thru the pipe discharge.
(b) Prov.ide detailed description of the test facility for the test data requested in item (as above and the data provided in Figures 4.3-2 and 4.3-3. Infonnation should include: pipe diameter, distance from pipe discharge to tank bottom, distance from pipe center'line to the wall, location of temperature and pressure sensors.
PROPRIETARY
PROPRIETARY t (c) provide the bases upon which the test results show in figures 4.3-2 and 4.3-3 have been considered in the development of the condensation zones.
- 2. As indicated by the straight pipe test data, severe vibration of the l
test stand was observed when water temperature was elevated to 120*F.
Considering this data, justify your proposed pool temperature limit f l In addition, provide the !
for Mark I and Mark II containments. !'
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following information: .
- l l i 8 - I (a) Ramshead test data performed in the Moss Landing and San Jose l l
- facilities. !
(b) Detailed description of these facilities including instrumentation j
set-up, physical dimensions of the facilities, and the relative dimensions of ramshead discharge to the surrounding structures and I pressure sensors. ~
.l (c) Discuss and justify the applicability of these test data for the ll Mark I and II containments.
- 3. For typical Mark I and II containments, provide figures showing reactor pressure, ramshead mass flux and suppression pool temperature versus time for the following events-(a) Stuck-open SRV during power operation assuming reactor scram at 10 minutes after pool temperature reaches 110*F and all RHR system operable. .
9 PROPRIETARY 9
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- l PROPRIETARY I
1 (b) Same as event (a) above except that only one RHR train available.
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(c) Stuck-open SRV during hot standby condition assuming 120 F pool j temperature initially and only one RHR train available.
(d) Automatic Depressurization System (ADS) activated following a small line break assuming an initial pool temperature of 120*F and only one RHR train available. i ,
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(e) Primary system is isolated and depressurized at a rate of 100*F per hour with an initial pool temperature of 120*F and only one RHR i
train available. !
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- 4. With regard to pool temperature limit, two specific terms, i .e., j
" local" and " bulk" pool temperature, have been quoted in various f ,
1 sections of Chapter 4 of NEDE-21078. For clarification, provide the l following additional information: I
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(a) Provide definition of these two terms and their application to the !
i scaled test facilities data and full scale containment. .
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(b) Section 4.3.2.3 indicates that the local temperature is 10*F I I above bulk temperature. Provide the data base used to support ! !
this value. i e
(c) Based on ? definition civen by (a) above, define the temperature f
scale of , ares 4.3-1 thru 4.3-3 in terms of the suppression pool temperature for an actual containment. '.
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- 5. Sections 4.1.1.3 and 4.3.2.3 describes some operational experience of l I \
SRV events at elevated pool temperature in domestic plants. Provide the. l following additional information:
i (a) Describe in greater detail the scenario of events including: 1
- I name of the plant, time history of reactor pressure and pool o l\
temperature, and operator actions following the incident. ,
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(b) Describe the suppression pool temperature monitoring system and i the relative location of temperature sensors to the SRV discharge.
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MAY 2 61977 I
)OORANDlN ICR: W. Pike, Project Manager, Light Water Reactors Branch No. 3, DIN FRCM: G. Lainas, Chief, Containment Systems Branch, DSS TIRJ: R. Tedesco, Assistant Director for Plant Systems, 1
SUBJECT:
i REQUEST FOR ADDITICNAL INFORMATION FOR E TOPICAL REPORT NEDE-21078-P (TAC-3619) l Report Numbar: NEDE-21078-P l Report Titte: Test Results Bnployed by E for BWR Containment and Vertical Vent Loads Responsible Branch: LWR-3 ,
Project Manager: W. Pike Requested Completion Date: N/S Review Status: Incomplete By letter dated December 20,1974, (I.F. Stuart to E. G. Case),
E proposed a technical specification limit for the suppression pool
- tenperature. Specifically, the proposed technical specification requires operator actions to limit the bulk pool tenperature b610w 1600F to avoid steam quenching vibration during safety / relief valve operation. This limit was established on the basis of experiments performed in a foreign country. E also submitted a summary of the test results to support this limit.
E submitted topical report (NEDE-21078-P) to justify this limit.
As a result of our evaluation, however, we find that the infonnation l' provided in the topical report does not totally justify this limit.
Data indic~ ate that excessive steam quenching vibration can occur at a bulk pool tecperature significantly below the E proposed temperature limit. We, therefore, cannot conclude on the adequacy of this pool temperature limit for containment designs using a ramshead device ,
(this includes Mark I and Mark II types). We have prepared the enclosed request for additonal information, and have discussed this request
Contact:
1 T. Su l X27711 1
s '
W. Pike They are aware of the kind of information with G during several telecons. Note that the enclosure contains we need to conplete our review. t should be handled accordingly.
proprietary information, therefore, p
~
, Gus C. Lainas, Chief for Containment Systems Branch Division of Systems Safety t
T:nclosure: l As stated cc: S. Hanauer '
F. Schroeder R. Tedesco '
J. Glynn '
C. Long O. Parr -
D. Vassallo ,
J. Guibert C. Grimes S. Miner R. Cudlin J. Kudrick J. Shapaker R. Boyd (w/o enc 1)
W. Mcdonald (w/o enc 1)
T. Su
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