ML19095A068
| ML19095A068 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/26/1976 |
| From: | Stallings C Virginia Electric & Power Co (VEPCO) |
| To: | Reid R, Rusche B Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19095A068 (6) | |
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VIRGINIA ELECTRIC.A.ND POWER COMP.A.NY RICHMOND, VIRGINIA 23261 November 2.
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.,.'}j' Mr. Benard C. Rusche, Director t7 N0:-V10;*:'!ll9Zt";r,>f1[Rerial No. 344 Office of Nuclear Reactor Regula~.
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1-'fR./EJL:cjw Attn:
Mr. Robert w. Reid, Chief Mail Section
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Operating Reactors Branch ~.,.
Docket Clerk
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50-280 50-281 Division of Operating Reactors r(, 1 U. S. Nuclear Regulatory Commission ~<J..,!~~---
License Nos.
DPR-32 Washington, D. C.
20555 DPR-37
Dear Mr. Rusche:
AMENDMENT TO OPERATING LICENSE DPR-32 AND PPR-37 SUPPLEMENTAL INFORMA~ION TO TECHNICAL SPECIFICATIONS CHANGE NO. 47 SURRY POWER STATION - UNIT NOS. 1 AND 2 In reply to Mr. N. Anderson's verbal request of November 13, 1976, transmitted herewith as Attachment 1 are our responses to questions 2a through 2d that were contained in Mr. R. W. Reid's letter of April 30, 1976.
The questions were originally asked and answered in connection with the Surry 2 Cycle 3 reload core.
The attached responses, as requested by Mr. Anderson, apply to the Surry 1 Cycle 4 reload core.
Should you have any additional questions or coIIUI1ents, we would be most happy to meet with you at your earliest convenience.
Attachment cc:
Mr. Norman C. Moseley Very truly yours,
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C. M. Stallings Vice President-Power Supply and Production Operations 12057
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2.0.a Question Provide a list and briefly describe each physics startup test to be performed for the Cycle 3 reload.
Also.provide the acceptance criterion for each test and discuss how the measured parameter(s) relates to the values used in the accident analysis.
Response
The response to this question for Surry 1 Cycle 4 operation is the same as that given in the letter from Mr. C. M. Stallings to Mr. B. C. Rusche dated May 14, 1976, serial number 017/043073, with the exception that several additional incore flux maps will be taken so that sufficient data will be available to allow the development of the APDM constants that might poten-tially be needed for the surveillance of the heat flux hot channel factor, Fq(Z), as detailed in proposed Change No. 47 to the Technical Specifications Section 3.12.B.2.b (and associated Basis).
2.0.b.
Question Describe in detail the bank worth tests, the maximum deviations from calcu-lated values expected, the criteria used for determining these maximum de-viations, and the procedures to be followed if these deviations are exceeded.
Response
The response to this question for Surry 1 Cycle 4 operation is the same as that given in the letter from Mr. C. M. Stallings to Mr. B. C. Rusche dated May 14, 1976, serial number 017/043073.
e 2.0.c.
Question State your schedule for submitting to 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 accep-tance criterion, the report should discuss the actions that were taken and justify the adequacy of these actions.
Response
The response to this question for Surry 1 Cycle 4 operation is the same as tnat given in the letter from Mr. C. M. Stallings to Mr. B. C.
- Rusche dated May 14, 1976, serial number 017/043073.
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2.0.d.
Question Analyze the effect on the startup power distribution of a postulated inad-vertent loading of a high-enrichment assembly into an incorrect position.
Describe how such a postulated misleading will be detected by the incore detector system.
If the effect is not detectable analyze the effect of the mislead assembly on core performance, power distribution, and MDNBR.
Response
The response to this question for Surry 1 Cycle 4 operation is the same I
as that given in the letter from Mr. C. M. Stallings to Mr. B. C. Rusche dated May 14, 1976, serial number 017/043073.