ML112520047: Difference between revisions
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| number = ML112520047 | | number = ML112520047 | ||
| issue date = 09/19/2011 | | issue date = 09/19/2011 | ||
| title = | | title = 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 | ||
| author name = | | author name = | ||
| author affiliation = PSEG Nuclear, LLC | | author affiliation = PSEG Nuclear, LLC | ||
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=Text= | =Text= | ||
{{#Wiki_filter:LAR S11-02, Deletion of E Bar Definition and Revision to RCS Specific Activity Technical | {{#Wiki_filter: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 | ||
*Reactor Coolant System Specific | |||
Current | Overview of Proposed Change | ||
*Defines limits for specific activity of primary coolant to be: | *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. | |||
>>Or less than the limit line as shown on Figure 3.4-1 for specific power levels | *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. | ||
- 100 / Ci/gm*Applicable in Modes 1, 2, 3, 4, and | The LAR will maintain consistency with industry precedent. | ||
*Provides Table 4.4-4 for sampling requirement frequencies to determine if the specific activity of the primary coolants is within allowable limits Proposed | 2 | ||
*TS 1.10 (S1 & S2)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 | 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) | ||
*TS 1.11 (S1 & S2)Delete -Average Disintegration Energy definition and replace with definition for Dose Equivalent Xe-133*DCFs shall be the air submersion | * Defines limits for specific activity of primary coolant to be: | ||
*TS Figure 3.4-1 (S1 & S2) | - 1.0 Ci/gm DOSE EQUIVALENT I-131 | ||
*LCO 3.4.8 (S1) & LCO 3.4.9 (S2)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/ | >> Or less than the limit line as shown on Figure 3.4-1 for specific power levels | ||
*SR 4.4.8 (S1) & SR 4.4.9 (S2)Revised based on industry precedent Effect | - 100 / Ci/gm | ||
*Limits on specific activity of | * Applicable in Modes 1, 2, 3, 4, and 5 SR 4.4.8 (S1) & SR 4.4.9 (S2) | ||
*This change will implement a | * Provides Table 4.4-4 for sampling requirement frequencies to determine if the specific activity of the primary coolants is within allowable limits 3 | ||
*No significant hazards | Proposed Licensing Basis | ||
*TS 1.10 (S1 & S2) | |||
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. | |||
*TS 1.11 (S1 & S2) | |||
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 | |||
*LCO 3.4.8 (S1) & LCO 3.4.9 (S2) | |||
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 | |||
*SR 4.4.8 (S1) & SR 4.4.9 (S2) | |||
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. | |||
5 | |||
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 | |||
6}} |
Latest revision as of 22:25, 20 March 2020
ML112520047 | |
Person / Time | |
---|---|
Site: | Salem |
Issue date: | 09/19/2011 |
From: | Public Service Enterprise Group |
To: | Division of Operating Reactor Licensing |
Ennis R, NRR/DORL, 415-1420 | |
Shared Package | |
ML112520029 | List: |
References | |
LAR S11-02, TAC ME6895, TAC ME6896 | |
Download: ML112520047 (6) | |
Text
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
- TS 1.10 (S1 & S2)
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.
- TS 1.11 (S1 & S2)
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
- LCO 3.4.8 (S1) & LCO 3.4.9 (S2)
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
- SR 4.4.8 (S1) & SR 4.4.9 (S2)
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.
5
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
6