ML18139C066
| ML18139C066 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/06/1982 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18139C065 | List: |
| References | |
| NUDOCS 8210200048 | |
| Download: ML18139C066 (2) | |
Text
TS 3.11-3
--1\\-1.-
Above are met.
- 10.
The requirements of Specification 3.0.1 are not applicable.
B.
Gaseous Wastes la.
The controlled release rates of gaseous wastes, excluding halogen and airborne particulates originating from station operation shall be limited as follows:
l: Qi (MPC) i
~ 2.0 X 105 3
m sec where Qi is the controlled release rate (curies per second) of any radioisotope i and (MPC) i' in unit of microcuries per cubic centi-meter is defined in column 1, Table II of Appendix B to 10 CFR 20.
- b.
With the release rate of gaseous wastes exceeding the above limit, without delay restore the release rate to within the limit.
- c.
The provisions of specification 6.6.2.a are not applicable.
- 2.
The release rates of activity shall not exceed 16 percent of those specified in paragraph B.la above when averaged over any calendar quarter or 10 percent of those specified in paragraph B.la above when averaged over any 12 consecutive months.
3a.
The release rate limit of all radioiodines and radioactive materials in particulate form with half-lives greater than eight da_ys released from the site to the environs as part of the gaseous wastes shall be such that 3 X 105 Q ~ 1 where Q = the measured release rate of the radioiodines and radioactive materials in particulate form with half-lives greater than eight day~ (Ci/sec).
- b.
The average release rate per site of all radioiodines and radioactive materials in particulate fQrm with half-lives greater than eight days during any calendar quarter shall be such that 13 [3 X 105 Q] ~l I
- r r I
fuel in the containment.
- 11.
The requirements*of Specification 3.0.1 are not applicable.
Basis TS 3.11-5 The releases of radioactive materials will be kept as low as practicable as required by 10 CFR 50 and will not exceed the concentration limits specified in 10 CFR 20.
At the same time, the licensee is permitted the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases in excess of four percent of the concentration limits specified in 10 CFR 20.
However, all releases must be kept within the concentration limits specified in 10 CFR 20.
It is ex-pected that using this operational flexibility under unusual operating conditions, the licensee shall exert every effort to keep levels of radioactive materials released from the plant as low as practicable and that annual releases will not exceed a small fraction of the annual average concentration limits-specified in 10 CFR 20.
The limiting conditions for operation contained in specification A-3 above, which relates to the total number of curies which may be released in liquid effluents in any year, is based on the expected performance of the Surry Power Station assuming both units are operating with 0.25 percent leaking fuel and each unit is experiencing a 20 gallon per day primary to secondary system leak rate.
The formulas and limits prescribed in specifications 3.11.B.1 and B.2 take atmospheric dilution into account and assures that at the point of maximum ground concentration at the site boundary, the requirements of 10 CFR 20 will not be exceeded.
The limit is based on the highest annual average value of X/Q which will occur at the