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TAC:ME6895, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Open) TAC:ME6896, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Open) |
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MONTHYEARML1123511452011-08-24024 August 2011 Forthcoming Meeting with PSEG Nuclear LLC (PSEG) to Discuss Proposed License Amendment Regarding Reactor Coolant System Activity for Salem Nuclear Generating Station, Unit Nos. 1 and 2 Project stage: Meeting ML1125200472011-09-19019 September 2011 Summary of Meeting with PSEG Nuclear LLC to Discuss Proposed License Amendment Regarding Reactor Coolant System Activity for Salem Nuclear Generating Station, Unit Nos. 1 and 2 Project stage: Meeting ML1125200382011-09-19019 September 2011 Summary of, Meeting with PSEG Nuclear LLC to Discuss Proposed License Amendment Regarding Reactor Coolant System Activity for Salem Nuclear Generating Station, Unit Nos. 1 and 2 Project stage: Meeting 2011-08-24
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LAR S11-02, Deletion of E Bar Definition and Revision to RCS Specific Activity Technical Specification Salem Units 1 and 2 Pre-Application Meeting September 8, 2011 Enclosure 2
Overview of Proposed Change
- Reactor Coolant System Specific Activity Replace the current Tech Spec limits on - Average Disintegration Energy with limits on noble gas activity.
The noble gas activity would be based on DOSE EQUIVALENT XE-133 and would take into account the noble gas activity in the primary coolant.
- License Li Amendment A d t Request R t (LAR) Submittal S b itt l Strategy St t The technical basis for the proposed change will be plant specific and consistent with the approach provided in TSTF 490, Rev. 1 However, PSEG does not plan to reference the TSTF in the LAR.
The LAR will maintain consistency with industry precedent.
2
Current Licensing Basis TS Definitions 1.10 Dose Equivalent I-131 1.11 - Average Disintegration Energy Reactor Coolant System Specific Activity LCO 3.4.8 (S1) & LCO 3.4.9 (S2)
- Defines limits for specific activity of primary coolant to be:
- 1.0 Ci/gm DOSE EQUIVALENT I-131
>> Or less than the limit line as shown on Figure 3.4-1 for specific power levels
- 100 / Ci/gm
- Provides Table 4.4-4 for sampling requirement frequencies to determine if the specific activity of the primary coolants is within allowable limits 3
Proposed Licensing Basis
Minor text changes to explicitly identify the source for the dose conversion factors (DCFs) to be used to calculate Dose Equivalent I-131
- DCFs shall be the Thyroid Committed Dose Equivalent (CDE) inhalation dose conversion factors from Table 2.1 of Federal Guidance Report No. 11 (FGR-11), Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, 1988.
Delete - Average Disintegration Energy definition and replace with definition for Dose Equivalent Xe-133
- DCFs shall be the air submersion Effective dose conversion factors from Table III.1 of Federal Guidance Report No. 12, (FGR-12) External Exposure to Radionuclides in Air, Water, and Soil, EPA, 1993.
- TS Figure 3.4-1 (S1 & S2)
Delete figure
Revise text to remove reference to Figure 3.4-1, and to replace it with a DEI primary coolant specific activity level of 60 Ci/gm Replace 100/E Bar specific activity limit for primary coolant nuclides other than iodine with a dose equivalent Xe-133 specific activity limit of 601 Ci/gm Change applicability requirements to Modes 1, 2, 3, and 4
Revised based on industry precedent 4
Effect on Safety
- Limits on specific activity of the reactor coolant ensure that the offsite and control room doses are appropriately limited during analyzed transients and accidents.
- This change will implement a LCO that is consistent with the whole body radiological consequence analyses which are sensitive to the noble gas activity in the primary coolant.
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Conclusion
- No significant hazards consideration No physical or plant operational changes Proposed change ensures consistency with assumptions in the safety analyses Proposed change will ensure the monitored values are b d d bby th bounded the iinitial iti l assumptions ti iin th the safety f t analyses l
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