ML19352A974
| ML19352A974 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 05/22/1981 |
| From: | Maine Yankee |
| To: | |
| Shared Package | |
| ML19352A972 | List: |
| References | |
| NUDOCS 8106020459 | |
| Download: ML19352A974 (2) | |
Text
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(J-gaseous waste from the hydrogenated waste gas system shall be provided a minimum average holdup of 60 days except for low radioactivity gaseous waste resulting from purge and fill operations associated with refueling and reactor i
startup.
1 b.
Ibidop time less than that specified in B.3.a above shall i.
be covered in the special effluent report to be included in the semi-annual report required by.Section 5.7.B.(1)(a) of these specifications.
c.
The maximum activity to be contained in one gas decay tank shall not exceed 88,400 curies of Xe-133 equivalent.
4.
During the first indication of primary-to-secondary leakage, concurrent with sufficient fuel defects, a determination of j
the lodine partition factor for the blowdown tank shall be made.
5.
Durinq power operation, the condenser air ejector discnarge shall be continuously monitored for gross radiogas activity.
4 Whenever this monitor is inoperable, grab samples shall be taken from the. air ejector discharge and analyzed for gross t
radiogas activity daily.
l 6.
Gases discharged through the stack shall be continuously i
monitored for gross noble gas and particulate activity.
i Whenever either of these monitors is inoperable, appropriate grab samples shall be taken and analyzed daily.
7.
Purging of the reactor building shall be guverneJ by the following conditions:
j a.
Reactor building purge shall be filtered through the high efficiency particulate air filters and charcoal absorbers whenever the enncentration of iodine and particulate f
isotopes exceeds the uccupational MPC inside the reactor building.
b.
Reactor building purge shall be filtered through the high efficiency particulate air filters and charcoal absorbers whenever irradiated fuel is being handled or any object is being handled over irradiated fuel in the reactor buildino.
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Exception: The requirements of Par 7b above shall not apply from May 22, 1981 j
until either completion of the LPSI check valve installation ordered Apr?) 20, 1981 or completion of operations involving
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irradiated f el handling or handling of any object over irradiated i
fuel during the cycle 5/6 refueling, whichever is earlier. When 1
refueling operations are conducted under this exception, the containment purge valves shall be tripable manually and automatically.
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5 3.17-3
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8196020459 s
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o The quantity and isotopic proportions of radioactive gases released into the reactor coolant system is dependent upon several factors including fuel leakage, burnup and power level.
Changes in power level will affect gaseous generation rates temporarily.
Cases are released from the reactor coolant to the gaseous waste system during degassifier treatment of the letdown and leakage water and also during venting of the system.
This venting may occasionally be performed to degas the system and so 4
control plant chemistry and/or reduce coolant radioactive gas concentrations to en acceptable value for the protection of plant personnel, s
Gaseous waste holdup and decay occurs while it is retained in the reactor coolant system and in the surge drum of the gaseous l
treatment system.
The gaseous waste holdup drums are of sufficient capacity to provide an additional average retention i
4 period of 60 days during normal operating conditions.
The low as practicable gaseous release objectives expressed in this Specification are based on the guidelines contained in the proposed Appendix I of 10 CFR 50. Since these guidelines have not been adopted as yet, the release objectives of this Specification will be reviewed at the time Appendix I becomes a regulation to assure that this Specification is based upon the a
1 guidelines contained therein.
Basis:
The excepticn to Par. 3.17.B.7.b allows installation of additional PC-87 LPSI check valves reducing the probability of event V LOCA to proceed without extending unnecessarily the cycle 5/6 refueling outage.
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Due to the extended time period between reactor shutdown and the present there has been considerable decay of the radioactive fiesion 1
products in the fuel. An analysis of a refueling accident inside 1
containment shows the doses would be appropriately within the guidelines of 10 CFR 100 (specifically in this case on the order of 100 rem thyroid) taking no credit for either filtration or containment isolation.
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