LR-N06-0195, 2005 Summary of Revised Regulatory Commitments Salem Nuclear Generating Stations Units 1 & 2: Difference between revisions

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=Text=
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{{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 APR 2 8 2O01               PSEG LR-N06-0195                 Nuclear LLC U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Attn: Document Control Desk 2005  
{{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 APR 2 8 2O01 PSEG LR-N06-0195 Nuclear LLC U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Attn: Document Control Desk 2005  


==SUMMARY==
==SUMMARY==
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In accordance with the Nuclear Energy Institute (NEI) process for managing Nuclear Regulatory Commission (NRC) commitments and associated NRC notifications, PSEG Nuclear LLC (PSEG) submits this correspondence to discuss a commitment that was changed and not reported by other means during 2005.
In accordance with the Nuclear Energy Institute (NEI) process for managing Nuclear Regulatory Commission (NRC) commitments and associated NRC notifications, PSEG Nuclear LLC (PSEG) submits this correspondence to discuss a commitment that was changed and not reported by other means during 2005.
Salem Unit I and 2 Technical Specifications (TS) Amendments 232 and 213, respectively.
Salem Unit I and 2 Technical Specifications (TS) Amendments 232 and 213, respectively.
Salem Unit 1 and 2 TS Amendments 232 and 213, respectively, approved the deletion of TS 314.1.3.2.2. The NRC's Safety Evaluation (SE) to these amendments included the following statement: "Although more than one shutdown or control bank may be withdrawn from the fully inserted position at a time, a shutdown margin of at least 5% AK (KS         4 no greater than 0.95) will continue to be maintained by procedures during full-length control rod testing to prevent inadvertent criticality in the shutdown condition.,
Salem Unit 1 and 2 TS Amendments 232 and 213, respectively, approved the deletion of TS 314.1.3.2.2. The NRC's Safety Evaluation (SE) to these amendments included the following statement: "Although more than one shutdown or control bank may be withdrawn from the fully inserted position at a time, a shutdown margin of at least 5% AK (KS 4 no greater than 0.95) will continue to be maintained by procedures during full-length control rod testing to prevent inadvertent criticality in the shutdown condition.,
While this amendment resulted in being able to perform control rod testing on multiple banks, maintaining the lKf at or below 0.95 requires the Reactor Coolant System to be borated to conservatively high levels (around 2700 ppm),
While this amendment resulted in being able to perform control rod testing on multiple banks, maintaining the lKf at or below 0.95 requires the Reactor Coolant System to be borated to conservatively high levels (around 2700 ppm),
well over the typical refueling boron concentration (approximately 2100 ppm).
well over the typical refueling boron concentration (approximately 2100 ppm).
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AJ1 95-2168 REV. 7199
AJ1 95-2168 REV. 7199


                                                                            -MPR I   2006 Document Control Desk LR-N06-01 95                                 2 An evaluation for maintaining a higher Kff was performed. This evaluation demonstrated that it is acceptable to lower the Keff during refueling evolutions.
-MPR I 2006 Document Control Desk LR-N06-01 95 2
As a result, a revised commitment has been implemented using the provisions of 10CFR50.59.
An evaluation for maintaining a higher Kff was performed. This evaluation demonstrated that it is acceptable to lower the Keff during refueling evolutions.
As a result, a revised commitment has been implemented using the provisions of 1 OCFR50.59.
The revised commitment states "Although more than one shutdown or control bank may be withdrawn from the fully inserted position at a time, the maximum allowable core Kff will be limited to no greater than 0.98 (assuming that all shutdown and control rod banks are fully withdrawn), during full length control rod testing, to preclude inadvertent criticality during the performance of the specific evolution in the shutdown condition."
The revised commitment states "Although more than one shutdown or control bank may be withdrawn from the fully inserted position at a time, the maximum allowable core Kff will be limited to no greater than 0.98 (assuming that all shutdown and control rod banks are fully withdrawn), during full length control rod testing, to preclude inadvertent criticality during the performance of the specific evolution in the shutdown condition."
Should there be any questions please contact Howard Berrick at 856-339-1862.
Should there be any questions please contact Howard Berrick at 856-339-1862.
Sincerely, omas P. Joy e Site Vice President - Salem Mr. S. Collins Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 U. S. Nuclear Regulatory Commission ATTN: Mr. S. Bailey, Licensing Project Manager - Salem Mail Stop 08B1 Washington DC 20555-001 USNRC Senior Resident Inspector - Salem (X24)
Sincerely, omas P. Joy e Site Vice President - Salem Mr. S. Collins Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 U. S. Nuclear Regulatory Commission ATTN: Mr. S. Bailey, Licensing Project Manager - Salem Mail Stop 08B1 Washington DC 20555-001 USNRC Senior Resident Inspector - Salem (X24)
Mr. K Tosch, Manager, IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625}}
Mr. K Tosch, Manager, IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625}}

Latest revision as of 09:06, 15 January 2025

2005 Summary of Revised Regulatory Commitments Salem Nuclear Generating Stations Units 1 & 2
ML061290585
Person / Time
Site: Salem  PSEG icon.png
Issue date: 04/28/2006
From: Joyce T
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N06-0195
Download: ML061290585 (2)


Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 APR 2 8 2O01 PSEG LR-N06-0195 Nuclear LLC U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Attn: Document Control Desk 2005

SUMMARY

OF REVISED REGULATORY COMMITMENTS SALEM NUCLEAR GENERATING STATIONS SALEM UNIT NOS. I AND 2 DOCKET NOS. 50-272 AND 60-311 Gentlemen:

In accordance with the Nuclear Energy Institute (NEI) process for managing Nuclear Regulatory Commission (NRC) commitments and associated NRC notifications, PSEG Nuclear LLC (PSEG) submits this correspondence to discuss a commitment that was changed and not reported by other means during 2005.

Salem Unit I and 2 Technical Specifications (TS) Amendments 232 and 213, respectively.

Salem Unit 1 and 2 TS Amendments 232 and 213, respectively, approved the deletion of TS 314.1.3.2.2. The NRC's Safety Evaluation (SE) to these amendments included the following statement: "Although more than one shutdown or control bank may be withdrawn from the fully inserted position at a time, a shutdown margin of at least 5% AK (KS 4 no greater than 0.95) will continue to be maintained by procedures during full-length control rod testing to prevent inadvertent criticality in the shutdown condition.,

While this amendment resulted in being able to perform control rod testing on multiple banks, maintaining the lKf at or below 0.95 requires the Reactor Coolant System to be borated to conservatively high levels (around 2700 ppm),

well over the typical refueling boron concentration (approximately 2100 ppm).

The high boron concentration can result in excessive primary water processing to dilute back down to the critical boron concentration.

AJ1 95-2168 REV. 7199

-MPR I 2006 Document Control Desk LR-N06-01 95 2

An evaluation for maintaining a higher Kff was performed. This evaluation demonstrated that it is acceptable to lower the Keff during refueling evolutions.

As a result, a revised commitment has been implemented using the provisions of 1 OCFR50.59.

The revised commitment states "Although more than one shutdown or control bank may be withdrawn from the fully inserted position at a time, the maximum allowable core Kff will be limited to no greater than 0.98 (assuming that all shutdown and control rod banks are fully withdrawn), during full length control rod testing, to preclude inadvertent criticality during the performance of the specific evolution in the shutdown condition."

Should there be any questions please contact Howard Berrick at 856-339-1862.

Sincerely, omas P. Joy e Site Vice President - Salem Mr. S. Collins Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 U. S. Nuclear Regulatory Commission ATTN: Mr. S. Bailey, Licensing Project Manager - Salem Mail Stop 08B1 Washington DC 20555-001 USNRC Senior Resident Inspector - Salem (X24)

Mr. K Tosch, Manager, IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625