ML19341D691
| ML19341D691 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 03/31/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Counsil W CONNECTICUT YANKEE ATOMIC POWER CO. |
| References | |
| TASK-06-02.D, TASK-06-03, TASK-6-2.D, TASK-6-3, TASK-RR LSO5-81-03-079, LSO5-81-3-79, NUDOCS 8104080434 | |
| Download: ML19341D691 (7) | |
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F March 31, 1981 Docket No. 50-213 LS05-81-03-079 fr
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A#40 Mr. W. G. Counsil Vice President
-H Nuclear Engineering and Operations I-N E/SgfA b; Connecticut Yankee Atomic Power Company Post Office Box 270 Y
g Hartford, Connecticut 06101 Cu
Dear Mr. Counsil:
SUBJECT:
SEP TOPICS VI-2.0, MASS AND ENERGY RELEASE FOR POSTULATED PIPE BREAKS INSIDE CONTAINMENT AND VI-3, CONTAINMENT PRESSURE AND HEAT REMOVAL CAPABILITY - (HADDAM NECK PLANT) l We have been informed by our contractor, LLL, that additional infonnation (see enclosure) is needed in order to complete work on SEP Topics VI-2.0 and VI-3.
This information would ensure that our work would reflect the I
current Haddam Neck Plant design. Your timely response (i.e., by April 10, l
1981) would be appreciated.
l Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch f5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page 8104080%by 0
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March 31, 1981
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Docket No. 50-213 l'
L505-81-03-079 Mr. W. G. Counsil, Vice President Nuclear Engineering and Operations Connecticut Yankee Atomic Power Company Post Office Box 270 Hartford, Connecticut 06101
Dear Mr. Counsil:
SUBJECT:
SEP TOPICS VI-2.D, MASS AND ENERGY RELEASE FOR POSTULATED PIPE BREAKS INSIDE CONTAINMENT AND VI-3, CONTAINMENT PRESSURE AND HEAT REMOVAL CAPABILITY - (HADDAM NECK DLANT)
We have been informed by our contractor, LLL, that additional information (see enclosure) is needed in order to complete work on SEP Topics VI-2.0 and VI-3.
This information would ensure that our work would reflect the current Haddam Neck Plant design. Your timely response (i.e., by April 10, 1981) would be appreciated.
Sincerely,
- y Dennis M. Crutchfield, C f
Operating Reactors Bran h #5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page i
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- i Mr. W. G. Counsil HADDAM NECK PLANT DOCKET NO. 50-213
'e cc w/ enclosure:
Day, Berry & Howard U. S. Environmental Protection
.l Counselors at Law Agency One Constitut on Plaza Regica I Office Hartford, Connecticut 06103 ATTN: EIS COORDINATOR JFK Federal Building H
Superintendent Boston, Massachusetts 02203 Haddam Neck Plant RFD #1 Resident Inspector i
Post Office Box 127E Haddam Neck Nuclear Power Station East Hanpton, Connecticut 06424 c/o U. S. NRC East Haddam Post Of fice Mr. Janes R. Himmelwright East Haddam, Connecticut 06423 Northeast Utilities Service Company P. O. Box 270 Hartford, Connecticut 06101 Russell Library 119 Broad Street Middletown, Connecticut 06457 i
Board of Selectmen Town Hall Haddam, Connecticut 06103 Connecticut Energy Agency
-ATTN: Assistant Director Research and Policy Development Department of Planning and l
Energy Policy l
20 Grand Street l
Hartford, Connecticut 06106 Director, Technical Assessment l
Division i
Office of Radiation Prograns (AW-459)
U. S. Environmental Protection Agency Crystal Mall #2 l
Arlington, Virginia 20460 1
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ENCLOSURE il' l
l The NRC Systematic Evaluation Program analyses include performing analyses of reactor containments based on current NRC criteria. These analyses include calculations of the containment pressure and temperature response due to water / steam discharges from a reactor blowdown.
The analyses of the reactor blowdown will be performed using the computer li code RELAP4-Mod 7 and the containment calculations will be performed using l
the computer code CONTEMPT-LT/028.
The following list of questions is intended to define the plant-specific infonnation required to perform an independent analysis of a double-ended guillotine pump suction break, and a steam line break (MSLB).
l BLOWDOWN AND REFLOOD Provide a detailed modeling report and parameter list, including a general description of code utilized as well as actual plant data. Adequate detail is to be provided such that a computer model can be developed from the information submitted.
It is understood that the majority of the submittal will contain information proprietary to Westinghouse. Specific responsu to the following questions are required:
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(1)
Please provide a nodalization diagram for the input deck which identifies the fluid volumes and flowpaths.
If available, a diagram defining the heat conductors, fills, valves, etc., would also be helpful.
(2)
Please define the purpose (kind of analysis) for which the deck is set up, the basic assumptions for the initial and boundary conditions, and the code ve; ston the deck runs on. A copy of a recent document which describes the dec'k (the model) would also l
be helpful.
(3)
Where special modeling techniques are used, and hence the input parameters are not rep.'esentative of the physical description of the plant, please define the best estimate values and describe the reason for these special modeling techniques.
For instance, 1
H if a large flow area was used to eliminate momentum ef fects, so
'l state and define the most representative flow area.
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'l (4)
If the input deck contains any proprietary data which cannot be supplied, please provide an alternate source of nonproprietary data adequate for these analyses.
i (5)
Define the rated core power and reactor coolant pump power.
Also define the safeguards power or the percentage over rated power allowed before an overpower trip would occur.
(6)
If known, please define the primary and secondary conditions for the safeguard power operation, e.g., what is the primary system flow rate and the cold and hot leg tmperatures, and the secondary pressure or temperature and the feed water and steam line mass flow rates.
(7)
Define the maximum inventories which could be available in the system. Are the volumes in the deck defined for cold or hot (considering themal expansion) conditions? Define the normal and maximum operating levels for the pressurizer and steam generators.
(8)
Are the reactor coolant pump definitions in the data. deck accurate and complete? State the pump rated conditions, if not accurately defined in the input data deck.
If two-phase pump performance data are available, please provide. Otherwire, the Semiscale, test data will be used. Please define the friction l
coefficients for a third order polynomial if known. Does the plant design contain an antireverse rotation mechanism?
(9)
A complete and accurate description of the heat conductors should be provf fed with the input data deck. Please verify that l'
the dimensions for the fuel rod heat conductors are adequately representative of the current -Tant fuel for the analyses to be j
performed.
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(10) Please define the valve characteristics including the loss coef-ficients and area versus time charactaristics. Of major impor-I tance is the time required to close, aftsr receipt of signal, for feedwater and steam line isolation valves.
(11) ECCS physical descriptions. Provide a cmplete description of the accumulator, HPIS and LPIS performance characteristics and the assumptions which should be used with single active failure criteria.
(a) Accumulators.
Verify that the model accurately describes the accumulator and line connecting to the primary system, volumes, fics areas, friction losses, and elevations.
Define the aominal and maximum liquid inventory within each accumulator volume and the nominal and maximum expected (tech. spec.) temperature of the water in the accumulator. In addition, the cover gas pressure and injection location in the primary system should be defined.
(b) The HPIS and LPIS flow versus primary system pressure per-
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formance curves as defined at the primary system injection location is required. Again, define ths total number of pumps normally available and the assumptiens used with I
single active failure criteria. Define the source of water for each system, the nominal and maximum (tech. spec.)
temperature, and total inventory available.
j (12) Supplied reactor kinetics information should be defined as best estimate or conservative and is usually assumed to be beginning of life for these analyses. Valves appropriate for both the pump suction break and the steam line break should be provided.- Because the nature of these two transients is somewhat different, separate infomation for each transient may be required. For instance, for the pump suction break, the '
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scram infomation is of secondary importance because the reactor
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shuts down due to the density reactivity feedback.
Specific infomation to be supp?ied shou'Id include the density reactivity, Doppler recctivity, the nominal axial power shape distribution, and the direct rnoderator heating fraction.
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(13) Provide a basic description of the plant safety system operation for nomal conditions versus single active failure criteria, and define the effect on these systems due to the loss of outside power. Specific definition is required to model reactor scram, pump trips, and' secondary isolation of feedwater and steam line, the activation of HPIS, LPIS, and accumulators.
In addition, the activation t'mes for fan coolers and sc iy coolers in the containment will be required. A descriptic. of the signal acti-vating the trip as well as the delay time for initiation of the activity is required.
(14) A description of the trip signal, setpoints, and dela[ times for initiation of each action must be defined.
Please define the
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nomal expected setpoints and delay times and also discuss the reasonable,conservatisms which shculd be assumed for each item.
l CONTAINMENT Provide general it 3 tion relative to the model used in CONTEMPT l
including identifyi.
version of CONTEMPT used, the kind of analysis, general assumptions ust to develop the model, and a description of the purpose for which the model is used. Additional specific information is required as follows:
(1)
Provide a quotable reference for the heat structure data defined I
in the deck.
(2)
De' fine the nomal and maximum expected teaperature pemitted in the containment drywell during normal operations.
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'1 s (3)
Verify that the initiation times, ficw rates, and heat renoval rates in the deck for the sprays and coolers are currently I
valid.
(4 )
Define the maximum tenperatures of any and all ECC water injected _into the core or sprayed into the containment.
(5)
Define the containment spray and fan cooler activation time or activation signal and delay time due to the break and/or loss of U
outside power. Also, define the number of spray and cooler systems normally available and the num5cr to be assumed considering single failure criteria.
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