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{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS January 25, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation                           Serial No. 026 Attn: Mr. Steven A. Varga, Chief                               PSE/NAS/lmf/0021N Operating Reactors .Branch No.                       Docket Nos. 50-280 Division of Licensing                                             50-281 U.S. Nuclear Regulatory Commission                             License Nos. DPR-32 Washington, D.C. 20555                                                     DPR-37 Gentlemen:
{{#Wiki_filter:(
SUPPLEMENT 3 TO AN AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR-37 PROPOSED REDUCTION IN BORON CONCENTRATIONS SURRY POWER STATION UNITS l AND 2 In our letter dated September 13, 1983 (Serial No. 521), Vepco requested an amendment to Operating Licenses DPR-32 and DPR-37 to allow operation of Surry Unit Nos. l and 2 at reduced boron concentrations. This letter provides, in Attachment 1, supplemental information in response to an informal request made by the NRC staff via telephone on January 10, 1984.
i I
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS January 25, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Steven A. Varga, Chief Operating Reactors.Branch No.
Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Serial No. 026 PSE/NAS/lmf/0021N Docket Nos.
50-280 50-281 License Nos. DPR-32 DPR-37 SUPPLEMENT 3 TO AN AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR-37 PROPOSED REDUCTION IN BORON CONCENTRATIONS SURRY POWER STATION UNITS l AND 2 In our {{letter dated|date=September 13, 1983|text=letter dated September 13, 1983}} (Serial No. 521), Vepco requested an amendment to Operating Licenses DPR-32 and DPR-37 to allow operation of Surry Unit Nos. l and 2 at reduced boron concentrations.
This letter provides, in Attachment 1, supplemental information in response to an informal request made by the NRC staff via telephone on January 10, 1984.
Should you have any further questions, please contact us at your earliest convenience.
Should you have any further questions, please contact us at your earliest convenience.
Very truly yours, W. L. Stewart Attachment (1) Response to Core Performance Branch questions for the proposed reduction in boron concentrations for Surry Power Station cc: Mr. James P. O'Reilly                       Mr. J. Don Neighbors Regional Administrator                    NRC Project Manager - Surry Region II                                Operating Reactors Branch No.
Very truly yours, W. L. Stewart Attachment (1) Response to Core Performance Branch questions for the proposed reduction in boron concentrations for Surry Power Station cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station 8401300309 840125 PDR ADOCK 05000280 p
Division of Licensing Mr. D. J. Burke                          Mr. Charles Price NRC Resident Inspector                    Department of Health Surry Power Station
PDR Mr. J. Don Neighbors NRC Project Manager - Surry Operating Reactors Branch No.
* 109 Governor Street Richmond, Virginia
Division of Licensing Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia  
( 8401300309 840125 i PDR ADOCK 05000280 I p                      PDR


                - -- ----=- _.....:.--- -
----=- _.....:.--- -
,l
,l e
  *.                                      e Attachment 1 STEAMBREAK ACCIDENT. STATEPOINTS Hypothetical Break     Credible Break With Power     Without Power   With Power Case A           Case B         Case C Core Heat                                     23.7             8. 1           4. 1 Flux,% of 2441 MWT RCS Pressure,                                 959             853             733 psia Loop A Inlet                                 398             276             460 Temp., °F Loop B Inlet                                 469             497             482 Temp., °F Core Boron                                     0.0             0.4             8.2 Concentration, PPM RCS Flow,                                     100               6.4           100 Reactivity,                                     .007             .003           .026
STEAMBREAK ACCIDENT. STATEPOINTS Hypothetical Break Credible Break With Power Without Power With Power Case A Case B Case C Core Heat 23.7
      % delta K/K Time, sec.                                   201             250             395 DNBR                                           1. 93           2.00           5.4}}
: 8. 1
: 4. 1 Flux,% of 2441 MWT RCS Pressure, 959 853 733 psia Loop A Inlet 398 276 460 Temp., °F Loop B Inlet 469 497 482 Temp., °F Core Boron 0.0 0.4 8.2 Concentration, PPM RCS Flow, 100 6.4 100 Reactivity,  
.007  
.003  
.026  
% delta K/K Time, sec.
201 250 395 DNBR
: 1. 93 2.00 5.4}}

Latest revision as of 20:56, 5 January 2025

Forwards Supplemental Info in Response to NRC 840110 Request Re Proposed Amend Concerning Reduction in Boron Concentrations
ML18141A446
Person / Time
Site: Surry  
Issue date: 01/25/1984
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Varga S
Office of Nuclear Reactor Regulation
References
026, 26, NUDOCS 8401300309
Download: ML18141A446 (2)
v • d • e


Text

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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS January 25, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:

Mr. Steven A. Varga, Chief Operating Reactors.Branch No.

Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Gentlemen:

Serial No. 026 PSE/NAS/lmf/0021N Docket Nos.

50-280 50-281 License Nos. DPR-32 DPR-37 SUPPLEMENT 3 TO AN AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR-37 PROPOSED REDUCTION IN BORON CONCENTRATIONS SURRY POWER STATION UNITS l AND 2 In our letter dated September 13, 1983 (Serial No. 521), Vepco requested an amendment to Operating Licenses DPR-32 and DPR-37 to allow operation of Surry Unit Nos. l and 2 at reduced boron concentrations.

This letter provides, in Attachment 1, supplemental information in response to an informal request made by the NRC staff via telephone on January 10, 1984.

Should you have any further questions, please contact us at your earliest convenience.

Very truly yours, W. L. Stewart Attachment (1) Response to Core Performance Branch questions for the proposed reduction in boron concentrations for Surry Power Station cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station 8401300309 840125 PDR ADOCK 05000280 p

PDR Mr. J. Don Neighbors NRC Project Manager - Surry Operating Reactors Branch No.

Division of Licensing Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia

=- _.....:.--- -

,l e

STEAMBREAK ACCIDENT. STATEPOINTS Hypothetical Break Credible Break With Power Without Power With Power Case A Case B Case C Core Heat 23.7

8. 1
4. 1 Flux,% of 2441 MWT RCS Pressure, 959 853 733 psia Loop A Inlet 398 276 460 Temp., °F Loop B Inlet 469 497 482 Temp., °F Core Boron 0.0 0.4 8.2 Concentration, PPM RCS Flow, 100 6.4 100 Reactivity,

.007

.003

.026

% delta K/K Time, sec. 201 250 395 DNBR

1. 93 2.00 5.4
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