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{{#Wiki_filter:UNITED'STATES OF AMERICA NUCLEAR REGULATORY COMMISSXON BEFORE THE ATOMIC SAFETY AND LICENSING BOARD'Xn the Matter of))FLORIDA POWER 6 LIGHT COMPANY ,))(Turkey Point Nuclear.Generating
{{#Wiki_filter:UNITED 'STATES OF AMERICA NUCLEAR REGULATORY COMMISSXON BEFORE THE ATOMIC SAFETY AND LICENSING BOARD
)Units 3 and 4))Docket Nos.50-250-SP 50-251-SP (Proposed Amendments to Facility Operating License to Permit Steam Generator Repairs)STATEMENT OF MATERIAL FACTS AS TO WHXCH THERE'S NO GENUINE ISSUE TO BE HEARD (CONTENTIONS 3 and 6)Contention 3 1., Section 5.,2.2.,4 of the Steam Generator Repair Report (SGRR)contains an analysis of the liquid releases which may be expected to result from the operations associ-ated with the steam generator repair.2.The data presented i;n Tables 5.2-4 and 5.2-5 of the SGRR are representative of concentrations which can be expected in reactor coolant and laundry waste water, respectively.
'Xn the Matter of                       )     Docket Nos. 50-250-SP
3.The values in Table 5.2-6 of the SGRR, which gives the estimated releases wi;th the discharged liquid waste, are reasonable.
                                        )                       50-251-SP FLORIDA POWER     6 LIGHT COMPANY     ,)
4.In the event that processed primary reactor coolant and laundry waste water are to be discharged, the discharge will be into the canal system.
                                        )     (Proposed Amendments        to (Turkey Point Nuclear. Generating     )     Facility Operating        License Units 3 and 4)                         )     to Permit Steam Generator Repairs)
4i 1 5.A conservative estimate of the maximum individual dose from all liquid'eleases during the repair (including primary reactor coolant and laundry waste water)has.been calculated:
STATEMENT OF MATERIAL FACTS AS TO WHXCH       THERE'S NO GENUINE     ISSUE TO BE HEARD (CONTENTIONS 3 and 6)
using the methods outlined, in NRC Regulatory
Contention   3 1.,   Section 5.,2.2.,4 of the Steam Generator Repair Report (SGRR) contains an analysis of the liquid releases which may be expected to result from the operations associ-ated with the steam generator repair.
'Guide 1.109:.6.The dose, from these releases meets the require-.ments of Section.II, Paragraphs A and, D'f Appendix.I to 10 CFR Part 50.7:..The liquid releases'rom the steam generator repair (including primary reactor coolant and laundry waste water)are as low as reasonably achievable within the meaning of 10 CFR Parts 20'nd 50.Contention 6 8.The period July 1979 to June 1980 fairly represents releases which may be expected from the operating unit, during the repair of, the other.9.The total liquid releases to be expected from one operating unit and the repair of the other unit can be estimated by adding the actual liquid releases of radio-isotopes from one operating unit during the period-from July 1, 1979-June 30, 1980, and the estimated liquid releases from the repair of.one unit shown in Table 5.2-6 of the SGRR.10.A conservative estimate of the maximum indi-vidual dose from the combined liquid releases has been calculated.
: 2. The data presented i;n Tables 5.2-4 and 5.2-5 of the SGRR   are representative   of concentrations which         can be expected   in reactor coolant   and laundry waste water, respectively.
41 0 11.The dose from these combined liquid releases meets the requirements of Section II, Paragraph A, and Section II, Paragraph D of Appendix I to 10 CFR Part 50.12.The.total gaseous releases to be expected.from one operating unit and'he repair of.the other unit can also be estimated by adding the actual gaseous re-leases of radioisotopes:
: 3. The values in Table 5.2-6 of the SGRR, which gives the estimated releases wi;th the discharged liquid waste, are reasonable.
from one operating unit during the period from July 1,.1979-June 30, 1980, and the estimated'aseous releases from the repair of one unit as shown in Table 5.2-2 of the SGRR.13.A conservative estimate of the maximum indi-vidual dose from the combined gaseous releases has been calculated.
: 4. In the event that processed primary reactor coolant and laundry waste water are to be discharged, the discharge   will be into   the canal system.
14.The maximum individual doses from the combined gaseous releases all meet the requirements of Section II, Paragraphs B, C,.and D of Appendix I,to 10 CFR Part 50.15.The cumulative offsite liquid and gaseous radiation releases as a result of all activity at Turkey Point, during tne proposed repairs, do comply with 10 CFR Parts 20 and 50.Respect f ully submitted, STEEL HECTOR 6 DAVIS Co-Counsel for Licensee, Florida Power 6 Light Company 1400 Sout ast First National Bank Bu'ing Miami, F rida 33131 (.305)57 2863 Date: April 8, 1981 By: Norma A.Coll i!0}}
 
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: 5. A conservative estimate of the maximum individual dose from all liquid'eleases during the repair (including primary reactor coolant and laundry waste water) has. been calculated: using the methods outlined, in NRC Regulatory
'Guide 1.109:.
: 6. The dose, from these   releases meets the require-
.ments of Section. II, Paragraphs   A and, D'f Appendix. I to 10 CFR Part 50.
7:.. The liquid releases'rom the     steam generator repair (including primary reactor coolant         and laundry waste water) are as low as         reasonably achievable within the meaning of     10 CFR Parts 20'nd 50.
Contention   6
: 8. The period July 1979 to June 1980 fairly represents releases which may be expected from the operating unit, during the repair of,the other.
: 9. The total liquid releases to be expected from one operating unit and the repair of the other unit can be estimated by adding the actual liquid releases of radio-isotopes from one operating unit during the period- from July 1,   1979 June 30, 1980, and       the estimated liquid releases from the repair of. one unit shown in Table 5.2-6 of the SGRR.
: 10. A conservative estimate of the maximum indi-vidual dose from the combined liquid releases           has been calculated.
 
41 0
: 11. The dose from these   combined   liquid releases meets the requirements     of Section II, Paragraph A, and Section II, Paragraph D of Appendix I to 10 CFR Part 50.
: 12. The. total gaseous releases to be expected.
from one operating unit and'he repair of .the other unit can also be estimated by adding the actual gaseous re-leases of radioisotopes: from one operating       unit during the period from July 1,. 1979 June 30, 1980, and the estimated'aseous releases from the repair of one unit as shown in Table 5.2-2 of the SGRR.
: 13. A conservative estimate of the maximum indi-vidual dose from the combined gaseous releases has been calculated.
: 14. The maximum individual   doses from the combined gaseous   releases   all meet the requirements     of Section II, Paragraphs   B, C,. and D of Appendix I,to   10 CFR Part 50.
: 15. The cumulative offsite liquid and gaseous radiation releases as a     result of all activity at Turkey Point, during tne proposed repairs,       do comply   with 10 CFR Parts   20 and 50.
Respect fully submitted, STEEL HECTOR 6 DAVIS Co-Counsel   for Licensee, Florida Power   6 Light Company 1400 Sout ast First National Bank Bu'ing Miami, F rida 33131
(.305) 57 2863 By:
Norma  A. Coll Date:   April 8, 1981
 
i! 0}}

Latest revision as of 09:55, 22 October 2019

Statement of Matl Facts as to Which There Is No Genuine Issue to Be Heard,In Support of Summary Disposition of Contentions 3 & 6 Re Cumulative Offsite Dose & Discharge of Laundry Waste & Coolant Water
ML17340B026
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 04/08/1981
From: Coll N
FLORIDA POWER & LIGHT CO., STEEL, HECTOR & DAVIS
To:
Atomic Safety and Licensing Board Panel
Shared Package
ML17340B023 List:
References
ISSUANCES-SP, NUDOCS 8104220630
Download: ML17340B026 (6)
v • d • e


Text

UNITED 'STATES OF AMERICA NUCLEAR REGULATORY COMMISSXON BEFORE THE ATOMIC SAFETY AND LICENSING BOARD

'Xn the Matter of ) Docket Nos. 50-250-SP

) 50-251-SP FLORIDA POWER 6 LIGHT COMPANY ,)

) (Proposed Amendments to (Turkey Point Nuclear. Generating ) Facility Operating License Units 3 and 4) ) to Permit Steam Generator Repairs)

STATEMENT OF MATERIAL FACTS AS TO WHXCH THERE'S NO GENUINE ISSUE TO BE HEARD (CONTENTIONS 3 and 6)

Contention 3 1., Section 5.,2.2.,4 of the Steam Generator Repair Report (SGRR) contains an analysis of the liquid releases which may be expected to result from the operations associ-ated with the steam generator repair.

2. The data presented i;n Tables 5.2-4 and 5.2-5 of the SGRR are representative of concentrations which can be expected in reactor coolant and laundry waste water, respectively.
3. The values in Table 5.2-6 of the SGRR, which gives the estimated releases wi;th the discharged liquid waste, are reasonable.
4. In the event that processed primary reactor coolant and laundry waste water are to be discharged, the discharge will be into the canal system.

4i 1

5. A conservative estimate of the maximum individual dose from all liquid'eleases during the repair (including primary reactor coolant and laundry waste water) has. been calculated: using the methods outlined, in NRC Regulatory

'Guide 1.109:.

6. The dose, from these releases meets the require-

.ments of Section. II, Paragraphs A and, D'f Appendix. I to 10 CFR Part 50.

7:.. The liquid releases'rom the steam generator repair (including primary reactor coolant and laundry waste water) are as low as reasonably achievable within the meaning of 10 CFR Parts 20'nd 50.

Contention 6

8. The period July 1979 to June 1980 fairly represents releases which may be expected from the operating unit, during the repair of,the other.
9. The total liquid releases to be expected from one operating unit and the repair of the other unit can be estimated by adding the actual liquid releases of radio-isotopes from one operating unit during the period- from July 1, 1979 June 30, 1980, and the estimated liquid releases from the repair of. one unit shown in Table 5.2-6 of the SGRR.
10. A conservative estimate of the maximum indi-vidual dose from the combined liquid releases has been calculated.

41 0

11. The dose from these combined liquid releases meets the requirements of Section II, Paragraph A, and Section II, Paragraph D of Appendix I to 10 CFR Part 50.
12. The. total gaseous releases to be expected.

from one operating unit and'he repair of .the other unit can also be estimated by adding the actual gaseous re-leases of radioisotopes: from one operating unit during the period from July 1,. 1979 June 30, 1980, and the estimated'aseous releases from the repair of one unit as shown in Table 5.2-2 of the SGRR.

13. A conservative estimate of the maximum indi-vidual dose from the combined gaseous releases has been calculated.
14. The maximum individual doses from the combined gaseous releases all meet the requirements of Section II, Paragraphs B, C,. and D of Appendix I,to 10 CFR Part 50.
15. The cumulative offsite liquid and gaseous radiation releases as a result of all activity at Turkey Point, during tne proposed repairs, do comply with 10 CFR Parts 20 and 50.

Respect fully submitted, STEEL HECTOR 6 DAVIS Co-Counsel for Licensee, Florida Power 6 Light Company 1400 Sout ast First National Bank Bu'ing Miami, F rida 33131

(.305) 57 2863 By:

Norma A. Coll Date: April 8, 1981

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