ML20064N491
| ML20064N491 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/10/1983 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20064N479 | List: |
| References | |
| TAC-49156, TAC-49705, NUDOCS 8302160254 | |
| Download: ML20064N491 (5) | |
Text
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ATTACHENT.1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS Pursuant to 10 CFR 170.12 (c), Georgia Power Company has evaluated the attached proposed amendment to Operating License DPR-57 and has determined that:
a)
The proposed amendment does not require the evaluation of a new Safety Analysis Report or rewrite of the facility license; b)
The proposed amendment does not contain several complex issues, does not involve ACRS
- review, and does not require an environmental impact statement; c)
The proposed amendment does not involve a complex issue or more than one environmental or safety issue; d)
The proposed amendment does involve a single safety issue,
- namely, the changing of reactor coolant leakage limiting conditions for operation and survaillance requirements; e)
The proposed change to Operating LICE.nSe DPR-57 is therefore a Class III amendment.
8302160254 830210 PDR ADOCK 05000321 P
ATTACFNENT 2 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS The proposed change to Technical Specifications (Appendix A to Operating License DPR-57) would be incorporated as follows:
Remove Page Insert Page 3.6-7 3.6-7 3.6-8 3.6-8 3.6-8a t
I l
1
E V
LIMITING CONDITIONS FOR OPERATION SURVElLLANCE REQUJREENTS 6.F.2.c. When the time limits or maximum conductivity or chloride concen-4.6.F.2.c.3. Primary coolant pH shall be tration limits are exceeded, an measured at least once every orderly shutdown shall be ini-8 hours whenever reactor tlated and the react.or shall be coolant conductivity is In the Cold Shutdown condition
> 2.0pmhe/cm at 250C within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- d. Whenever the reactor is not pressurized, a sample of the reactor coolant shall be analyzed at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> for chloride ion content and pH.
G. Reactor Coolant Leakage G. Reactor Coolant Leakage
- l. Unidentified and Total Unidentified sources of reactor Any time irradiated fuel is in coolant system leakage shall be the reactor vessel and reactor checked by the drywell floor coolant temperature is above drain sump systen and recorded 2120F:
at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Identified sources of reactor coolant system leakage shall be reactor coolant system leakage checked by the equipment a.
into the primary containment from unidentified sources shall drain sump systen and recorded not exceed 5 gpm when averaged at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period; The readings provided by the pri-mary containment atmosphere reactor coolant system leakage particulate radioactivity monitor-b.
into the primary containment ing system, the primary contain-from unidentified sources shall ment radiciodine monitoring system, and the primary containment not increase more than 2 gpm when averaged over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> gaseous radioactivity monitoring period; and system shall also be recorded at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
l the total reactor coolant system c.
leakage into the primary contain-ment shall not exceed 25 gpm when averaged over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period; when checked in accordance with 4.6.G.
- 2. Leakage Detection Systems At least one of the leakage a.
measurement instruments associated with each sump shall be operable and two of the other three leakage detection systems identified in Table 3.2-10, note c shall be operable when irradiated fuel is Amendment No.
3.6 7
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIKEMENTS G. Reactor Coolant Leakage
- 2. Leakage Detection Systems (Cont'd)
- a. (Continued) in the reactor vessel and reactor coolant temperature is above 2120F. Further, the primary containment atmosphere particulate radioactivity monitoring system shall be among these three operable systems, or samples shall be obtained and analyzed at least once each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b.
From and after the date that any two of the four systems identified in Table 3.2-10, note c are made or found to be inoperable, but with the primary containment atmosphere particulate radioactivity monitoring system inoperable, reactor power operation may continue for the succeeding 30 days provided the primary containnent atmosphere particulate radioactivity monitoring system reading is checked and recorded at least once each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, c.
From and after the date that any two of the four systems, including the primary containment atmosphere particulate radioactivity monitoring system, identified in Table 3.2-10, note c are made or found to be inoperable, reactor power operation may continue for the succeeding 30 days provided samples of the containment atmosphere are obtained and analyzed at least once each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Amendment No.
3.6-8
LIMITING CONDITIONS FOR OPERATION
-SURVEILLANCE REQUiREW.NTS r
G. Reactor Coolant Leakage
- 3. Shutdown Requirements a.
If the conditions of 3.6.G.l.a-or 3.6.G.1.c cannot be met, reactor coolant systen leakage will be reduced to within the specified limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or an orderly shutdown shall be initiated.
If the condition of 3.6.G.l.b cannot be met, the source of reactor coolant leakage shall be identified or reduced within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or an orderly shutdown shall be initiated. The reactor shall be in the Hot Shutdown condition within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in the Cold Shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
P b.
If the conditions of 3.6.G.2 cannot be met, Specification 3.6.G.3.a shall aoply unless an inoperable system is sooner made operable.
c.
If three of the four leak l
detection systems are made or found to be inoperable, Specification 3.6.G.3.a shall apply.
L l-l l
Amendment No.
3.6-8a
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