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| issue date = 07/01/1981
| issue date = 07/01/1981
| title = Advises of Plans for Cycle 6 Reload Core.Cycle 6 Reload Core Analyzed Per WCAP-9272, Westinghouse Reload Safety Evaluation Methodology. Verification of Reload Core Will Be Performed Through Startup Physics Testing Program
| title = Advises of Plans for Cycle 6 Reload Core.Cycle 6 Reload Core Analyzed Per WCAP-9272, Westinghouse Reload Safety Evaluation Methodology. Verification of Reload Core Will Be Performed Through Startup Physics Testing Program
| author name = THOMAS W N
| author name = Thomas W
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| addressee name = DENTON H R, VARGA S A
| addressee name = Denton H, Varga S
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000280
| docket = 05000280
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=Text=
=Text=
{{#Wiki_filter:r .. ___ .. .....(, e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND~
{{#Wiki_filter:r
VIRGINIA 23261 July 1, 1981 w. N. TJ£OMAS V:tcE PRESlDENT FUEL RESOURCES Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing U.s: Nuclear Regulatory Commission Washington, D;C. 20555  
  . ___   .. .....(,
e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND~ VIRGINIA 23261 July 1, 1981
: w. N. TJ£OMAS V:tcE PRESlDENT FUEL RESOURCES Mr. Harold R. Denton, Director                     Serial No.:  393 Office of Nuclear Reactor Regulation Attn: Mr. Steven A. Varga, Chief                   FR/GLD:  slm Operating Reactors Branch No. 1 Division of Licensing                       Docket No.:  50-280 U.s: Nuclear Regulatory Commission Washington, D;C. 20555                             License No.:  DPR-32


==Dear Mr. Denton:==
==Dear Mr. Denton:==
Serial No.: 393 FR/GLD: slm Docket No.: 50-280 License No.: DPR-32
* RELOAD INFORMATION.FOR.CYCLE 6
* RELOAD INFORMATION.FOR.CYCLE 6 *sURRY NUCLEAR.POWER.STATION UNIT.NO~ 1 Surry Unit No. 1 completed its fifth cycle of operation on September 14, 1980 and went into an extended outage for steam generator replacement, refueling and other modifications.*
                                        *sURRY NUCLEAR.POWER.STATION UNIT.NO~ 1 Surry Unit No. 1 completed its fifth cycle of operation on September 14, 1980 and went into an extended outage for steam generator replacement, refueling and other modifications.* The purpose of this letter is to advise you of our plans for the Cycle 6 reload core.
The purpose of this letter is to advise you of our plans for the Cycle 6 reload core. The Cycle 6 reload core was analyzed in accordance with the methodology documented in Westinghouse Topical Report WCAP-9272 entitled "Westinghouse Reload Safety.Evaluation Methodology." The analysis ducted was consistent with the plant modifications now being made on steam generators and safeguards systems (NPSH concerns).
The Cycle 6 reload core was analyzed in accordance with the methodology documented in Westinghouse Topical Report WCAP-9272 entitled "Westinghouse Reload Safety.Evaluation Methodology." The analysis con-ducted was consistent with the plant modifications now being made on steam generators and safeguards systems (NPSH concerns). The results of this analysis indicated that no key analysis parameters would become more limiting during Cycle 6 operations than the values assumed in the currently applicable safety analysis. Further, the analysis demonstrated that the current Technical Specifications, as approved through Amendment No, 71, are appropriate and require no additional changes.
The results of this analysis indicated that no key analysis parameters would become more limiting during Cycle 6 operations than the values assumed in the currently applicable safety analysis.
A detailed review of the Westinghouse methodology, analysis techniques and results has been conducted by our technical staff. In addition, a review has been performed by both the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control staff. It has been determined that no unreviewed safety questions as defined in 10CFR 50.59 will exist as a result of the Cycle 6 reload core.
Further, the analysis demonstrated that the current Technical Specifications, as approved through Amendment No, 71, are appropriate and require no additional changes. A detailed review of the Westinghouse methodology, analysis techniques and results has been conducted by our technical staff. In addition, a review has been performed by both the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control staff. It has been determined that no unreviewed safety questions as defined in lOCFR 50.59 will exist as a result of the Cycle 6 reload core. Verification of the reload core will be performed through a startup physics testing program. Unless otherwise indicated, this program will be consistent with documentation provided in our topical report* VEP-FRD-36A, "Control Rod Reactivity Worth Determination by the Rod Swap Technique," transmitted by our letter to you dated January 16, 1981 (Serial No. 023). This report is a revision of VEP-FRD-36, an earlier topical report of the same title. 8107070276 810701-, PDR ADOCK 05000280 p PDR l e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton This letter is provided for your information~
Verification of the reload core will be performed through a startup physics testing program. Unless otherwise indicated, this program will be consistent with documentation provided in our topical report*
However~ should you have questions, please contact us at your earliest convenience.
VEP-FRD-36A, "Control Rod Reactivity Worth Determination by the Rod Swap Technique," transmitted by our letter to you dated January 16, 1981 (Serial No. 023). This report is a revision of VEP-FRD-36, an earlier topical report of the same title.
cc: Mr. James P. O'Reilly, Director *Office of Inspection.and Enforcement Region II 2}}
8107070276 810701-,
PDR ADOCK 05000280 p                   PDR
 
e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton                       2 This letter is provided for your information~ However~ should you have questions, please contact us at your earliest convenience.
cc:   Mr. James P. O'Reilly, Director
            *Office of Inspection.and Enforcement Region II}}

Latest revision as of 14:23, 6 November 2019

Advises of Plans for Cycle 6 Reload Core.Cycle 6 Reload Core Analyzed Per WCAP-9272, Westinghouse Reload Safety Evaluation Methodology. Verification of Reload Core Will Be Performed Through Startup Physics Testing Program
ML18139B433
Person / Time
Site: Surry Dominion icon.png
Issue date: 07/01/1981
From: Thomas W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Varga S
Office of Nuclear Reactor Regulation
References
393, NUDOCS 8107070276
Download: ML18139B433 (2)
v • d • e


Text

r

. ___ .. .....(,

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND~ VIRGINIA 23261 July 1, 1981

w. N. TJ£OMAS V:tcE PRESlDENT FUEL RESOURCES Mr. Harold R. Denton, Director Serial No.: 393 Office of Nuclear Reactor Regulation Attn: Mr. Steven A. Varga, Chief FR/GLD: slm Operating Reactors Branch No. 1 Division of Licensing Docket No.: 50-280 U.s: Nuclear Regulatory Commission Washington, D;C. 20555 License No.: DPR-32

Dear Mr. Denton:

  • RELOAD INFORMATION.FOR.CYCLE 6
  • sURRY NUCLEAR.POWER.STATION UNIT.NO~ 1 Surry Unit No. 1 completed its fifth cycle of operation on September 14, 1980 and went into an extended outage for steam generator replacement, refueling and other modifications.* The purpose of this letter is to advise you of our plans for the Cycle 6 reload core.

The Cycle 6 reload core was analyzed in accordance with the methodology documented in Westinghouse Topical Report WCAP-9272 entitled "Westinghouse Reload Safety.Evaluation Methodology." The analysis con-ducted was consistent with the plant modifications now being made on steam generators and safeguards systems (NPSH concerns). The results of this analysis indicated that no key analysis parameters would become more limiting during Cycle 6 operations than the values assumed in the currently applicable safety analysis. Further, the analysis demonstrated that the current Technical Specifications, as approved through Amendment No, 71, are appropriate and require no additional changes.

A detailed review of the Westinghouse methodology, analysis techniques and results has been conducted by our technical staff. In addition, a review has been performed by both the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control staff. It has been determined that no unreviewed safety questions as defined in 10CFR 50.59 will exist as a result of the Cycle 6 reload core.

Verification of the reload core will be performed through a startup physics testing program. Unless otherwise indicated, this program will be consistent with documentation provided in our topical report*

VEP-FRD-36A, "Control Rod Reactivity Worth Determination by the Rod Swap Technique," transmitted by our letter to you dated January 16, 1981 (Serial No. 023). This report is a revision of VEP-FRD-36, an earlier topical report of the same title.

8107070276 810701-,

PDR ADOCK 05000280 p PDR

e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton 2 This letter is provided for your information~ However~ should you have questions, please contact us at your earliest convenience.

cc: Mr. James P. O'Reilly, Director

  • Office of Inspection.and Enforcement Region II
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