ML112520038

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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
ML112520038
Person / Time
Site: Salem  PSEG icon.png
Issue date: 09/19/2011
From: Richard Ennis
Plant Licensing Branch 1
To:
Ennis R, NRR/DORL, 415-1420
Shared Package
ml112520029 List:
References
TAC ME6895, TAC ME6896
Download: ML112520038 (10)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 19, 2011 LICENSEE: PSEG Nuclear LLC FACILITY: Salem Nuclear Generating Station, Unit Nos. 1 and 2 SUB~IECT:

SUMMARY

OF SEPTEMBER 8,2011, 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 (TAC NOS. ME6895 AND ME6896)

On September 8, 2011, a Category 1 public meeting was held via teleconference between the U.S. Nuclear Regulatory Commission (NRC) and representatives of PSEG Nuclear LLC (PSEG or the licensee). The purpose of the meeting was to discuss a proposed license amendment for Salem Nuclear Generating Station, Unit Nos. 1 and 2. The proposed amendment would replace the current Technical Specification limits on primary coolant gross specific activity with limits on primary coolant noble gas activity. A list of conference call participants is provided as .

During the meeting, PSEG provided an overview of the planned license amendment request as detailed on the licensee's slides provided as Enclosure 2. The licensee indicated that the technical basis for the proposed change would be consistent with the approach detailed in Technical Specification Task Force (TSTF) Change Traveler TSTF-490, Revision 1. Since this revision of TSTF-490 has not yet been endorsed by the NRC staff, the licensee originally planned to not reference the TSTF in the application. It was decided that a better approach would be for the licensee to reference TSTF-490, Revision 0, which has been endorsed by the NRC, and to address issues raised by the NRC staff in request for additional information questions for licensee submittals that were based on TSTF-490, Revision O. The licensee anticipates submittal of the license amendment request in October 2011.

Members of the public were not in attendance. Public Meeting Feedback forms were not received.

-2 Please direct any inquiries to me at 301-415-1420 or Rick.Ennis@nrc.gov.

Richard B. Ennis, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311

Enclosures:

As stated cc w/encls: Distribution via Listserv

LIST OF CONFERENCE CALL PARTICIPANTS SEPTEMBER 8, 2011, MEETING WITH PSEG PROPOSED LICENSE AMENDMENT REGARDING REACTOR COOLANT SYSTEM ACTIVITY FOR SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 Name Organization Rick Ennis NRC LaRay Benton NRC Paul Duke PSEG Nuclear LLC Emily Maguire PSEG Nuclear LLC Bill McTigue PSEG Nuclear LLC John Duffy PSEG Nuclear LLC Jeff Heavener PSEG Nuclear LLC Rebecca Novak PSEG Nuclear LLC Elliot Rosenfeld New Jersey Department of Environmental Protection Paul Schwartz New Jersey Department of Environmental Protection Enclosure 1

Overview of Proposed Change

-Reactor Coolant System Specific Activity

  • Replace the current Tech Spec limits on E- 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 Amendment Request (LAR) Submittal Strategy

  • 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 1-131
  • Defines limits for specific activity of primary coolant to be:

- <1.0 ~Ci/gm DOSE EQU IVALENT 1-131

>> Or less than the limit line as shown on Figure 3.4-1 for specific power levels

- <100 I E ~Ci/gm

  • Applicable in Modes 1,2,3,4, and 5
  • Provides Table 4.4-4 for sampling requirement frequencies to determine if the specific activity of the primary coolants is within allowable limits

~ 3

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Proposed Licensing Basis

'T8 1.10 (81 & 82)

  • Minor text changes to explicitly identify the source for the dose conversion factors (DCFs) to be used to calculate Dose Equivalent 1-131
  • 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 Vafues of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1988.
  • T8 1.11 (S1 & S2)
  • Delete E- 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 111.1 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 & 82)
  • 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:5 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 :5601 ~Ci/gm
  • Change applicability requirements to Modes 1, 2, 3, and 4
  • 8R 4.4.8 (81) &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 LeO that is consistent with the whole body radiological consequence analyses which are sensitive to the noble gas activity in the primary coolant.

/Sale

~:;;~~ 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 bounded by the initial assumptions in the safety analyses

&~' 6

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Package: ML112520029 Meeting Notice: ML112351145 Meeting Summary and Enclosure 1: ML112520038 : ML112520047 OFFICE LPL 1-2/PM LA LPL 1-2/BC NAME REnnis ABaxter HChernoff DATE 9/19/11 9/19/11 9/19/11