ML18141A125
| ML18141A125 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/23/1983 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18141A124 | List: |
| References | |
| NUDOCS 8309290267 | |
| Download: ML18141A125 (5) | |
Text
TS 3.10-4
- 12.
A spent fuel cask or heavy loads exceeding 110 percent of the weight of a fuel assembly (not including fuel handling tool) shall not be moved over spent fuel, and only one spent fuel assembly will be handled at one time over the reactor or the spent fuel pit.
- 13.
A spent fuel cask shall not be moved into the Fuel Building unless the Cask Impact Pads are in place on the bottom of the spent fuel pool.
- 14.
Two trains of the control and relay room emergency ventilation system shall be operable.
With one train inoperable for any reason, demonstrate the other train is operable by performing the test in Specification 4.20.A.1.
With both trains inoperable comply with Specification 3.10.B.
- 15.
Containment purge shall be filtered through the high efficiency particulate air filters and charcoal absorbers.
B.
If any one of the specified limiting conditions for refueling is not met, refueling of the reactor shall cease, work shall be initiated to correct the conditions so that the specified limit is met, and no operations which increase the reactivity of the core shall be made.
C.
Af~er initial fuel loading and after each core refueling operation and prior to reactor operation at greater than 75% of rated power, the movable incore detector system shall be utilized to verify-proper power distribution.
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8309290267 830923 PDR ADOCK 05000280 P
PDR '
I D.
The requirements of 3.0.1 are not applicable.
- Pending NRC approval
TS 4.9-2
- E.
The dose rate due to noble gases in gaseous effluents shall be determined continuously to be within the limits of Specification 3.11.B.1 in accordance with the methods and procedures of the ODCM.
The dose rate due to Iodine-131, Tritium, and all radionuclides in particulate form with half life greater than 8 days, in gaseous effluents shall be determined to be within the limits of Specification 3.11.B.1 in accordance with the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.9-2.
F.
The concentration of hydrogen or oxygen in the waste gas holdup system shall be determined to be within the limits of Specification 3.11.B.5 by continuously monitoring the waste gases in the waste gas holdup system with the hydrogen or oxygen monitors required operable by Table 3.7-S(b) of Specification 3.7.E.
G.
The quantity of radioactive material contained in each gas storage tank shall be determined to be within the limits of Specification 3,11.B.6 at least once per month when the specific activity of the primary reactor coolant is s 2200 µCi/gm dose equivalent Xe-133.
Under the conditions which result in a specific activity> 2200 µCi/gm dose equivalent Xe-133, the Waste Gas Decay Tanks shall be sampled once per day.
H.
The radiological environmental monitoring samples shall be collected pursuant to Table 4. 9-3 from the specific locations given in the table and figure(s) in the ODCM and shall be analyzed pursuant to the requirements of Table 4.9-3, the detection capabilities required by Table 4.9-5.
Jame*
Cl-I River Site Boundary
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. Plgure 5.1-1 Map Deflftlna Unre1tricted Areas for.Radioactive Gaseous and Liquid Effluents
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A Ga1eou1 Release
- 1, Proceu Vent-131 ft.
c, 2: Vent-Vent Stacks-considered ground level release Liquid leave, 1ite Security Fence-Area outside is unrestricted for gaseous effluents
~and Maximum*tndividual Occupancy within site boundary:
- 1) Canal Bank Fishing* 160 hr/yr Liquid Maxi111U111 Individual Occupan::::
within site boundary:
- 1) Boat Fishing Discharge Canal*
800 hr/yr I I
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tn..,
\\mile IJQ i:::
>1 Scale t'I)
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ATTACHMENT 2
e SAFETY EVALUATION These proposed changes supplement the Radiological Efflqent Technical Specifications (RETS) submittal.
Added by this proposed change is a
Specification concerning filtering during containment purge.
This Specification is in the currently approved Surry Technical Specifications, but was inadvertently removed from the Technical Specifications in the RETS submittal.
Surveillance requirements of the Waste Gas Decay Tanks are added to Specification 4.9.G.
These requirements are a part of Justification No. 15 of the RETS submittal but were mistakenly left out of Specification 4. 9.G.
Figure 5.1-1 is revised for clarity and a scale is added.
These proposed changes are administrative in nature.
These proposed changes do not pose a significant hazards consideration or any danger to the safe operations of the plant and/or public safety.
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