ML20064G189
| ML20064G189 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 03/07/1994 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20064F570 | List: |
| References | |
| NUDOCS 9403160060 | |
| Download: ML20064G189 (9) | |
Text
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ATTACHMENT 2 PROPOSED CHANGES TO APPENDIX A TECHNICAL SPECIFICATIONS FOR FACILITYOPERATING LICENSES NPF-37, NPF-66, NPF-72, and NPF-77 AFFECTED PAGE INDEX Byron Revised Page:
3/4 6-2 Braidwood Revised Page:
3/4 6-2 9403160060 940307 PDR ADOCK 05000454 P
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CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE i
LIM!'!NO CON 0! TION FOR OPERATION 3,6.1.2 Containment leakage rates shall be limited to:
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l a
An overall integrated leakage rate of:
1)
Less than or equal to L,, 0.10% by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, 44.4 psig, or
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2)
Less than or equal to L 0.07% by weight of the containment t
air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Unit 1 (0.07% by weight of the contain-ment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Unit 2) at P, 22.2 psig, t
b.
A combined leakage rate of less than 0.60 L, for all penetrations and valves subject to Type B and C tests, when pressurized to P,.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With either the measured overall integrated containment leakage rate exceeding 0.75 L, or 0.75 L, as applicable, or the measured combined leakage rate for g
all penetrations and valves subject to Types B and C tests exceeding 0.60 L,,
restore the overall integrated leakage rate to less than 0.75 L, or less than 0.75 L, as applicable, and the combined leakage rate for all penetrations g
subject to Type B and C tests to less than 0.60 L, prior to increasing the Reactor Coolant System temperature above 200*F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR Part 50:v+4e9-the-methods-and-prov4s4cor of ^%I N45 4=4971 a.
-Thece-Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 1 10 unth-4*terve4+-due4eg-shutdowa. at a pressure not less than P,, 44.4 psig, or P. 22.2 psig; 6 %
t tech-10 year nrvice-pee 4ed: -The-thi-ed-tes t-o f-e ac h-set-s ha 44-be conduc ted-du ri ng-the-shu t down-fo r-t he-40-yea r-pla n t-ins e rvice-4astectioH l
BYRON - UNITS 1 & 2 3/4 6-2
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
1)
Less than or equal to L,, 0.10% by weight of the containment 1
air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,, 44.4 psig, or 2)
Less than or equal to L. 0.07% by weight of the containment t
air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Unit 1, (0.07% by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Unit 2) at P, 22.2 psig.
i b.
A combined leakage rate of less than 0.60 L, for all penetrations and valves subject to Type B and C tests, when pressurized to P,.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
i With either the measured overall integrated containment leakage rate exceeding 0.75 L, or 0.75 L, as applicable, or the measured combined leakage rate for g
all penetrations and valves subject to Types B and C tests exceeding 0.60 L,,
restore the overall integrated leakage rate to less than 0.75 L, or less than 0.75 L, as applicable, and the combined leakage rate for all penetrations g
subject to Type B and C tests to less than 0.60 L, prior to increasing the Reactor Coolant System temperature above 200'F.
SURVEILLANCE REQUIREMENTS j
4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR Part 50: us4m; the-::thed: cr.d provisions-of-ANGI-
-M45+1976-4hree-Type A tests (Overall Integrated Containment Leakage Rate) a.
shall be conducted at-40-t-10-month-4ntere h-duv4ng-shutdown at a pressure not less than P,, 44.4 psig, or P 22.2 psig; dtteng-t
-each-10 yeae-service-period. The third-test-of each set-shah-be-
-c o nd uc ted -d u r i ng-t he-s hu tdown--fo r-the-107cer plant-hservice-
-inspectiont BRAIDWOOD - UNITS 1 & 2 3/4 6-2
ATTACHMENT 3 EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evaluated the proposed amendment and determined that it involves no significant hazards consideration. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazards if operation of the facility in accordance with the proposed amendment would not:
(1)
Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2)
Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3)
Involve a significant reduction in a margin of safety.
The proposed amendment would modify the Byron and Braidwood Station Technical Specification Surveillance Requirement 4.6.1.2 to delete the specific reference to ANSI N45.4-1972 (" Leakage Rate Testing of Containment Structures for Nuclear Reactors"). Also, Surveillance Requirement 4.6.1.2.a would be amended by removing the schedule requirement for a Type A (overall integrated containment leakage rate) testing to be performed specifically at 40110 month intervals. The schedule for Type A testing would conform to the requirement of Appendix J of 10 CFR 50.
A.
The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
Soecification 4 A1 f The editorial change to delete the reference to ANSI N45.4-1972 will not increase the probability or consequences of any accident previously evaluated.
Testing will continue to be performed in accordance with ANSI N45.4-1972 as it is referenced in Appendix J of 10 CFR 50.
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Page 2 Spgjhcation 4.6.1.2.a The proposed changes will allow flexibility in the scheduling for Type A tests in i
the 10-year service period while still meeting the requirements in 10 CFR 50 Appendix J. The additional flexibility is needed for plants using 18-month fuel cycles to allow refueling outages and testing intervals to coincide. By conforming to 10 CFR 50 Appendix J, the test frequency, test methodology and acceptance criteria remain the same. Therefore, there is no significant increase in the probability or the consequences of an accident previously evaluated.
B.
The proposed changes do not create the possibility of a new or different type of accident from any accident previously evaluated.
Spmification 4.612 The editorial change to delete the reference to ANSI N45.4-1972 will not affect the design or operation of any system, structure or component in the plant.
There are no changes to parameters governing plant operation and no new or different type of equipment will be installed. No new accident scenarios are created by the proposed change because the test performance will continue to meet the requirements of Appendix J of 10 CFR 50, which references ANSI N45.4-1972.
Soecification 4.6.1.2.a The proposed changes do not affect the design or operation of any system, structure or component in the plant. There are no changes to parameters governing plant operation and no new or different type of equipment will be installed. No new accident scenarios are created by the proposed change because the test frequency continues to rneet the requirements of Appendix J of 10 CFR 50. There is no affect to the containment structure, the penetrations, or the facility. The proposed change to the test schedule only provides flexibility in meeting the same requirement for three tests in a 10-year period. The testing method and bases have not changed. Operation of the units with this more flexible test schedule will not result in an accident previously not analyzed in the Updated Final Safety Analysis Report (UFSAR).
Page 3 The proposed changes do not impact the design bases of the containment and do not modify the response of the conta'inment during a design basis accident.
Therefore, the changes do not create the possibility of a new or different type of accident from any accident prev ously evaluated.
C.
The proposed changes do not involve a significant reduction in a margin of safety.
Soecification 4.6.1.2 The editorial change to delete the reference to ANSI N45.4-1972 will not decrease the margin of safety. Testing will continue to conform to the requirements of Appendix J of 10 CFR 50, whicn references ANSI N45.4 t 972.
The initial conditions and methodologies used in the accident analyses remain unchanged. Therefore, the rest Its of the accident analyses are not impacted.
Specification 4.6.1.2.a The proposed changes do not impact the margin of safety for any Technical Specifications. The initial conditions and methodologies used in the accident analyses remain unchanged, therefore, the results of the accident analyses are not impacted. The proposed changes to the schedule only provide flexibility in meeting the same requirement for three tests in a 10-year period. These proposed changes do not affect or change any limiting conditions for operation (LCO), or any other surveillance requirements in the Technical Specifications.
The testing method, acceptance coteria, and bases for the suiveillance requirement are not changed. The Technical Specifications continue to require testing that is consistent with the requirements of Appendix J of 10 CFR 50.
Therefore, the changes do not involve a significant reduction in a marain of safety.
- i Summary Based on the above evaluation, Commonwealth Edison has concluded that these changed do not involve any significant hazards considerations.
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ATTACHMENT 4 ENVIRONMENTAL ASSESSMENT Commonwealth Edison has evaluated the proposed amendment against the criteria for and identification of licensing anc regulatory actions requiring environmental assessment in accordance with 10 CFR 51.21. It has been determined that the proposed change meets the criteria for a categorical exclusion as provided for under 10 CFR 51.22(c)(9). This determination is based on the fact that this charge is being proposed as an amendment to a license issued pursuant to 10 CFR 50, it involves changes to a surveillance requirement and the amendment meets the following specific criteria:
(i) the amendment involves no significant hazards consideration.
As demonstrated in Attachment 3, this proposed amendment does not involve any significant hazards considerations.
(ii) there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite.
As documented in Attachment 1 there will be no change in types or increases in the amounts of any effluents released offsite.
C (iii) there is no significant increase in individual or cumulative occupational radiation exposure.
This proposed change will not result in changes in the operation or configuration of the facility. There will be no change in the level of controls or methodology used for processing of radioactive Pffluents or handling of solid radioactive waste nor will the proposal result in any change in the normal radiation levels within i
the plant. Therefore, there will be no increase in individual or cumulative occupational radiation exposure resulting from this change.
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4 ATTACHMENT S 1
BYRON's PERIODIC TYPE A TEST SCHEDULE 1
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ATTACHMENT 5 BYRON's PERIODIC TYPE A TEST SCHEDULE l
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