ML18141A013
| ML18141A013 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/14/1983 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM 332, NUDOCS 8306170281 | |
| Download: ML18141A013 (2) | |
Text
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e VIRGINIA ELECTRIC AND POWER COMPANY RXCHMOND, VIRGINIA 23261
- w. L. ST:EWAH:r VICE PRESIDENT NUCLEAR OPERATIONS June 14, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION NUREG-0737: ITEM II.B.3 Serial No. 332 NO/DWL:acm Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 In our letter dated December 27, 1982 (Serial No. 227D),
Vepco committed to complete installation and testing of the Post-Accident Sampling System (PASS) at the Surry Power Station by June 1, 1983.
This commitment date was included in the NRC Order Confirming Licensee Commitments on Post-TMI Related Issues dated March 15, 1983.
Vepco has met this commitment in that the PASS has been completely installed and functionally tested prior to the June 1, 1983 date.
As indicated in our December 27, 1982 letter referenced
- above, final procedures for the PASS will be in place by July 1, 1983.
The performance of the functional test of the PASS was accomplished by a combination of the following methods:
- 1) Demonstration of chemical analysis capability via standard test and calibration samples combined with demonstration of the ability to deliver an actual RCS or containment air sample to the chemical analysis equipment; and
- 2) Actual chemical analysis on RCS and containment air samples with demonstration of accuracy via comparison to standard laboratory chemical/isotopic analysis techniques.
These two methods to functionally test the PASS were necessary to account for the lack of or very low concentrations at normal operating conditions of certain elements to be analysed.
Additionally, consideration of contamination of some peripheral equipment precluded the use of actual RCS samples in some tests.
The following is a brief summary of the PASS functional tests performed:
- Undiluted and diluted grab samples were taken of RCS liquid from one unit.
The dilution ratio was verified.
8306 i°70281--830614 PDR ADOCK 05000280 p
e VIRGINIA ELECTRIC AND PowER CoMPANY To Harold R. Denton Containment air samples were drawn from both units at atmospheric containment conditions.
The ability to draw a containment air grab sample under subatmospheric conditions was demonstrated on one unit.
- The ability to perform required chemical analysis on liquid and stripped gas RCS samples was demonstrated.
A stripped gas grab sample was taken.
The installed PASS is capable of performing its required analytical functions as is.
However, several minor modifications are planned in order to enhance the reliability of the PASS and to aid the PASS operators in using the system.
Also, additional shielding modifications are being engineered and will be installed in order to minimize the exposure to the PASS operators.
Provisions will be implemented by procedure which ensure compliance with the dose requirements of GDC 19 during operation of the PASS.
If there are any questions, please contact us at your convenience.
cc:
Mr. James P. O'Reilly Regional Administrator Region II Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Mr. D. J. Burke NRC Resident Inspector Surry Power Station Very truly yours, j Jl;Jldi;r W. L. Stewart ~