ML19347E399
| ML19347E399 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/21/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8104270247 | |
| Download: ML19347E399 (3) | |
Text
TENNESSEE VALLEY AUTHORITY CH ATTANOOGA, TENNESSEE 374ot i* /
a to 400 Chostnut Street Tower II (Mb N '\\
O April 21, 1981 1;.Ug J,) d 2,IlbOI" L j 2
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mr Director of Nuclear Reactor Regulation e
s Attention:
Mr. A. Schwencer, Chief Licensing Branch No. 2 SD,N e
Division of Licensing U.S. Nuclear Regulatory Comission Washington, DC 20555
Dear Mr. Schuencer:
In the Matter of the Application of
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Docket No. 50-328 Tennessee Valley' Authority
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TVA has found it necessary to revise the Preoperational/Startup Test Program stated in the Sequoyah Nuclear Plant Final Safety Analysis Report (FSAR). For Sequoyah unit 2, the following changes are being made in addition to those transmitted to you by my letter dated April 15, 1981.
(1) The Initial Turbine Roll vill be conducted during Low Power Physics Testing.
(2) The Reactor Protection Time Response and Operational Test will be conducted during Precritical Testing.
A draft revision to FSAR Table 14.1-1 (page 14.1-52) which changes the test prerequisites for the initial turbine roll is enclosed. This revised page and revisions to FSAR Tables 14.1-2, Preoperational Test Sequence, and 14.1-3, Startup Test Sequence, will be included in the FSAR by Amendment 69.
l If you have any questions, please get in touch with D. L. Lambert at FTS 857-2581.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills,flanager Nuclear Regulation and Safety Sworn Ed subscri ed before me thi.
- Cday of /
1981 L
ML.w NotapPublic j
f My Comission Expires 4/Y 2-0 i
An Equal Opportunity Employer 0
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ENCLOSURE SEQUOYAH NUCLEAR PLANT REVISION TO FSAR TABLE 14.1-1 (PAGE 14.1-52)
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Revised by Amendment 37, October 6, 1975 TABLE 14.1-1 (continued)
LIST OF PREOPERATIONAL TESTS Test Objective Summary of Testing and Title of Test Test Prerequisites Acceptance Criteria j
8%dceg's cd & {dcwn conditiencst h
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l T Initial Turbine Roll
-RCS e t het chut Test objective is to verifNinitialogetaTl*4 wit h-RCS-pumps--a nd-chargl ut, pumps t"rbine retat-len usius steam gen oFWw.
operat iona-l.
Condenser vacuum ararad by " p r heat -
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maintained, steam lines warmed and izer end n eam seuneter lev.1. Will t h 5
A Circulating Water System in opera-bc :sinuained at tso percent levels $Nc"g tion.
and s: car. IntrcJuued to roll the tur1 "' T bi-ne.
During the test, reactor cool-ant temperature, steam generator t
level, pressurizer level, and pressure d
5 will be continuously recorded. The 9
turbine will be placed on the turning rb gear after coastdown.
t
- ynamic Automatic Reactor is critical at zero power, Test objective is to verify automatic D
Steam Dump Control hot
- standby conditions.
Steam operation of T average Steam Dump Dump System is operational. At Control System; to demonstrate con-least one condenser circulating troller setpoint adequacy; and to ob-water pump is in operation, tain final settings for steam pres-sure control of condenser dump valves.
Reactor power is increased to approximately 10 percent by rod
. withdrawal and steam dump to con--
denser.
Setpoint on pressure con-troller will be increased prior to switching to T average control which will rapidly modulate open condenser
- Preoperational test to be completed after core loading.
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VInGINIA ELECTRIC AND Powsm CoxvANY A
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April 20, 1981 q,
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G Mr. Harold R. Denton, Director Serial No. 244 Office of Nuclear Reactor Regulation N0/LEN:smv Attention:
Mr. Steven A. Varga, Chief Docket Nos. 50-280 Operating Reactors Branch No. 1 50-281 Division of Licensing License Nos. DPR-32 U. S. Nuclear Regulatory Commission DPR-37 Washington, D. C.
20555 Gentlemen:
AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR 37 SURRY POWER STATION UNITS NO. 1 AND No. 2 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGE By a letter dated December 28, 1979 (Serial No.1178), Virginia Electric and Power Company requested an amendment in the form of changes to the Technical Specifications, to Operating Licenses DPR-32 and DPR-37 for Surry Power Station Units 1 and 2.
The proposed Technical Specification changes were in response to a NRC letter dated September 25, 1979, concerning requirements for auxiliary feedwater systems at Surry Power Station Units 1 and 2.
In accordance with the NRC recommendations, Specification 3.6-F requires upon instances when the aux-iliary feedwater pumps do not meet operability requirements they be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Subsequent to the September 25, 1979 letter, NUREG 0737 was issued and con-tained the revised requirements to the auxiliary feedwater system.
Included in NUREG 0737 was the requirement to implement the above mentioned Technical Specification by July 1, 1981.
Also, in the %ng-t e rm, the auxiliary feed-water system was to be modified to provide one pump with capability to operate automatically for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> independent of any AC power by January 1,1982.
In order to meet the requirements of the proposed Technical Specifications, a modification is required to existing valves.
A modification to these valves is also required to meet the long-term modification for pump automatic control.
Due to material delivery delay, this modification cannot be complete until Fall of this year.
The proposed Technical Specification changes have not been issued to Vepco to date.
It is requested that issuance be postponed to coincide with the modification required to the auxiliary feedwater system by January 1, 1982.
810.4270/3V
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,VjkOINEA ELECTRIC AMD Pow 2m Courawy to
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Should you have any questions or require additional information, please contact us.
Very truly yours, Manager - Nuclear l
Operations and Maintenance cc:
Mr. James P. O'Reilly, Director Office of Inspection and Enforcanent Region II l
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