ML20040A039
| ML20040A039 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 11/01/1976 |
| From: | Cox T Office of Nuclear Reactor Regulation |
| To: | Happell J BABCOCK & WILCOX CO. |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201200242 | |
| Download: ML20040A039 (4) | |
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[ 03-3 BSAR-205 Q-2's 220.0 Analysis M 221.42 Since Equations in Hytran assume no heat generation in the (4.4.2.2) fluid, justify your statement that you assume 97.3% of the heat generation occurs within the fuel rod with the remaining 2.7% generated in the coolant.
221.43 You list three references for cladding conductivity. Since (4.4.2.2) they are not all identical, detail the equation you use to calculate conductivity and explain any deviation from the references.
221.44 Justify your statement that failure to include expanded flow (4.4.2.6) areas around bowed assemblies will result in 1.ess than 0.03%
error in the hot bundle flow. Detail these calculations completely and provide the basis and assumptions of your analysis.
221.45 In Section 4.4.2.7 correct your Section reference for a (4.4.2.7) discussion of core pressure drops and hydraulic loads during accident conditions.
.46 Why is there more than a 10% pressure drop difference between eg. 4.4-30)
Greene County and BSAR-205 at the 157" level?
221.47 Provide values of Ke in equation 4.4-7.
Give a reference for (4.4.2.8) the values of K and indicate what experiments they were c
derived from.
221.48 Equation 4.4-26 has a division sign missing. Define the radiation (4.4.2.8) gap conductance (hrad) for equation 4.4-28.
221.49 Amendment notation was omitted in this section.
Provide a schedule (4.4.2.8) for completion of the Oconee 1 fuel exam and the submittal of the data reduction.
221.50 Provide a discussion.of the role of pump monitors in preventing (16.2.3) core DNBR from decreasing below 1.3 if there were a loss of the reactor coolant pump (s).
221.51 Which transient is most limitin; for DNBR? Provide the values (15.1) with respect to time of the assateem. DNBR for all transients which reach a DNBR of less than 1.39.
221.52 Does the 2.5% thermal uncertainty on the peak radial power determination correspond to f "?
If not, indicate where and v
(4.4.2.10) howthis2.5%uncertaintyis3pplied.
8201200242 810403 PDR FOIA MADDEN 80-515 PDR
c.
Acar 1 220-2 221.53 Provide a sample case for TEMP and CHATA.
Include input to (4.4) and output from the codes.
221.54 The.99 flow maldistribution factor for 205-fuel assembly (4.4.2.6) cores must be justified by experimental evidence. Since such evidence will not be available for some time, the 4
staff requires a conservative value for flow maldistribution be applied. The.99 has not been shown to be conservative and the staff requires that the.95 value (used in previous B&W plant applications) be used until a higher number is justified based on vessel model flow test data.
221.55 Provide the data which indicates how fluid from each reactor (4.4.4) coolant inlet pipe (in 4 or 3 pump operation) is distributed to each assembly. For example, will one assembly receive 73%
of its flow from reactor coolant pump 1 and 9% flow from each of the other three reactor coolant pumps.
221.56 In response to Round One Questions, B&W has comitted to provide (4.4)
CHF data on 17 x 17 fuel assemblies. Since BAW-2 has not ben approved for 17 x 17-assemblies, the-data required-for such an approval must be submitted to NRC and approved prior to OL issuance.
221.57 Section 4.4.1 states that flow stability is required during all 4
(Chapter 15) steady-state and operational transient conditions. Examine each j
transient (excluding LOCA or other occurrences for which dig is permitted) for possible flow instabilities. Using HYTRAN, demonstrate the presence or absence of instability.
In particular, l
provide analyses for Steam Line Break and Excessive Heat Removal.
For those transients not analyzed by HYTRAN, provide a stability map such as presented in ANL-76-23 by M. Ishii as justification for not analyzing for stability.
Provide a comparison of HYTRAN to data over HYTRAN's range of application. There should be sufficient data points to insure f
a meaningful analysis.
221.58 In Section 4.4.1 you state that the maximum temperature in a (Chapter 15) fuel pin will not exceed the melting temeprature of that fuel at 112% power during the life of the plant. Provide the maximum fuel centerline temperature for any anticipated transients where the fuel centerline temperature may approach or exceed its limit.
For any transients not analyzed, provide a justification for their exclusion.
Include Steam Line Break in your analyses.
221.59 Provide a description of the method used to mount each of the bolted, magnetic, etc.)ystem sensors (e.g., clamp, drilled &
18 Reactor Diagnostic S
'4.5.9)
SW3 220-3 221.60 Define " active and passive" sensors and note all differences.
(4.4.5.9)
Provide the reasoning behind having only passive sensors on the Reactor Coolant Pumps. Provide the reasoning behind having only one active rather than two active sensors on the CRD mechanisms.
221.61 Provide a connitment to (1) fully define the gap closure (None)
(rod bow) rate for your prototype bundles, (2) determine by experiments the DNB effect that bounds the gap closure from (1), and (3) provide application of separate-effects bundle-bow data to reactor transient analysis.
221.62 The following codes must receive approval from the NRC prior to (4.4) issuance of an operatina license - TACO, HYTRAN, CHATA, TRAP, BAW-10099, BAW-10101 and POWERTRAIN.
221.63 Describe in detail your determination of the hot channel factors (Table 4.4.1) f and f ", including a list and values for all physical parameters u9ed to Obtain the hot channel factors. Give the basis for each input (e.g., reference the fuel specifications or any other docu-
~~
mentation which provides manufacturing tolerance limits consistent with the values used in your derivation). How will you assure that the design values remain valid or that changes, if any, due to as-built deviations from design are procerly accounted for in the hot channel factors?
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