ML19326C149
| ML19326C149 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/21/1977 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8004210650 | |
| Download: ML19326C149 (5) | |
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We have conncnced review of your December l~,1976 reload analysis q ;'y r for ANO-1 and have detemined that the additional information described in the attachment is required. Based on our preliminary
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Horace Jewell, Esquire House, Holms & Jewell 1550 Tower Building Little Rock, Arkansas 72201 Phillip K. Lyon, Esquire House, Holms & Jewell 1550 Tower Building Little Rock,- Arkansas 72201 Hr. Donald Rueter Manager, Licensing Arkansas Power & Light Company Post Office Box 551 Little. Rock, Arkansas 72201 Arkansas Polytechnic College Russellville, Arkansas 72801 m
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ARKANSAS POWER & LIGHT COMPANY ARKANSAS NUCLEAR ONE - UNIT NO. 1 (ANO-1)
DOCKET N0. 50-313 REQUEST FOR ADDITIONAL INFORMATION A.
PHYSICS STARTUP TESTS 1.
Provide a list of Physics Startup Tests and briefly describe each test to be performed for the cycle 2 reload. Also provide the acceptance criterion for each test and discuss how the measured parameter (s) relates to the values in the accident analysis.
2.
Describe in detail the bank reactivity worth tests, the maximum deviations from calculated values expected, the criteria used for establishing the maximum permissible deviations, and the procedures to be followed if these deviations are exceeded.
3.
State your schedule for submitting to the NRC a brief summary report of physics startup tests. This report should include both measured and predicted values.
If the difference between the measured and predicted value exceed the acceptante criterion, the report should discuss the actions that were taken and justify the adequacy of these actions.
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BAW --1433, RELOAD REPORT 1.
Discuss the implied conservatisms for the larger densified fuel c.ack, i.e.,141.12 inches (page 6-2).
2.
Provide the DNBR sensitivity study for flux / flow setpoint inclusive of the minimum acceptable DNBR of 1.3 (pages 6-3 and 6-4).
List the DNBR at which the analyses were conducted.
3.
For the cold water accident, the report quoted an initial power of 60% of rated for 2 pump operation (page 7-3) as compared with the maximum permissible power level with 2 pump operation of 52.6% of rated power level (page 8-6).
Provide the analysis of accident initiation from the maximum allowable setpoint of 52.6% thermal power level.
4.
Provide the analysis which incorporates the effect of fuel 1
rod bow on power peaking and core parameters (page 8-1).
C.
TECHNICf,L SPECIFICATIONS
'1.
Provide the analysis which was used to establish figure 2.1.3 and discuss this analysis in detail.
Your discussion should include:
a.
The reasons for identical three and four pump operational curves for core protection safety limits on reactor coolant pressure and temperature; and t
s
. b.
The means of incorporation of the fuel rod bow DNBR penalty (figure 2.1.3).
Specifically, was this penalty imposed on all modes of operation (i.e., 2, 3, and 4 pump operational modes)? Discuss how the TEMP and CHATAH codes are.used in the analysis.
2.
Provide revised Technical _ Specifications for core vent valve test requirements as follows: The test requirements on the vent valves (page 73a) must include a test for that moment when the vent valves start to open. The vent valves must start to open at a differential pressure of*1 15 psi and 0
must be fully open at 1 30 psid.
If force equivalents are 0
to be specified, a detailed analysis and documentation is
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required.
3.
Discuss why the curves for core protection safety limit (figure 2.1.3) must be duplicated in figure 2.1-1.
If this duplication is not required, we recommend that the figures
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be incorporated into a single figure.
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