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| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| page count = 5
| page count = 5
| project =
| stage = Request
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}}


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{{#Wiki_filter:consumers Power KurtM. Haas Plant Safety and Licensing Director l'OWERINli Mlt:HlliAN'S PROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 .December 13, 1994 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT TECHNICAL SPECIFICATIONS CHANGE REQUEST -HIGH THERMAL PERFORMANCE DNB CORRELATION A request for a change to the Palisades Technical Specifications is enclosed.
{{#Wiki_filter:consumers Power                                                   KurtM. Haas Plant Safety and Licensing Director l'OWERINli Mlt:HlliAN'S PROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043
This Technical Specification change request (TSCR) proposes addition of a third DNB correlation to Safety Limit 2.1. This "HTP" DNB correlation is used for the High Thermal Performance fuel loaded during recent Palisades fuel cycles. The following attachments are included:
  .December 13, 1994 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT TECHNICAL SPECIFICATIONS CHANGE REQUEST - HIGH THERMAL PERFORMANCE DNB CORRELATION A request for a change to the Palisades Technical Specifications is enclosed.
: 1) Proposed Technical Specifications pages 2) Existing pages marked to show proposed changes The HTP correlation is being used in the Cycle 12 accident analyses, therefore, we request that the Technical Specifications Amendment approving that change be approved and become effective prior to the end of the upcoming refueling outage which is currently planned to be completed in late July 1995. We will keep the NRR project manager aware of any changes in the planned refueling outage schedule.
This Technical Specification change request (TSCR) proposes addition of a third DNB correlation to Safety Limit 2.1. This "HTP" DNB correlation is used for the High Thermal Performance fuel loaded during recent Palisades fuel cycles.
The following attachments are included:
: 1)         Proposed Technical Specifications pages
: 2)         Existing pages marked to show proposed changes The HTP correlation is being used in the Cycle 12 accident analyses, therefore, we request that the Technical Specifications Amendment approving that change be approved and become effective prior to the end of the upcoming refueling outage which is currently planned to be completed in late July 1995. We will keep the NRR project manager aware of any changes in the planned refueling outage schedule.
Summary of Commitments:
Summary of Commitments:
This letter does not make or alter any commitments to the NRC. I Kurt M. Haas Director, Plant Safety & Licensing CC Administrator, Region III, USNRC Resident Inspector, Palisades State of Michigan Attachments 9412220065 941213 PDR ADOCK 05000255 p PnR *A GMS' ENER6YCOMPANY f\Wl I I It is requested that the Technical Specifications contained in the Facility Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on February 21, 1991, for the Palisades Plant be changed as described below: I. Changes It is proposed that the specifications below be changed to incorporate the HTP critical heat flux correlation.
This letter does not make or alter any commitments to the NRC.
The following changes are proposed:
I Kurt M. Haas Director, Plant Safety & Licensing CC Administrator, Region III, USNRC Resident Inspector, Palisades State of Michigan Attachments 9412220065 941213 PDR p
Safety Limit 2.1: The HTP DNB correlation is added under the Correlation column and its appropriate minimum DNB limit is added under the Safety Limit. That column currently lists XNB and ANFP DNB correlations and their respective limits. The proposed Safety Limit would be: The Minimum DNBR of the reactor core shall be maintained greater than or equal to the DNB correlation safety limit. Correlation XNB ANFP HTP Safetv Limit 1.17 1.154 1.141 The Basis is revised to explain the incorporation of the HTP correlation.
ADOCK 05000255 PnR
                                              *A GMS' ENER6YCOMPANY                                         f\Wl   I I
 
It is requested that the Technical Specifications contained in the Facility Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on February 21, 1991, for the Palisades Plant be changed as described below:
I. Changes It is proposed that the specifications below be changed to incorporate the HTP critical heat flux correlation. The following changes are proposed:
Safety Limit 2.1:
The HTP DNB correlation is added under the Correlation column and its appropriate minimum DNB limit is added under the Safety Limit.
That column currently lists XNB and ANFP DNB correlations and their respective limits. The proposed Safety Limit would be:
The Minimum DNBR of the reactor core shall be maintained greater than or equal to the DNB correlation safety limit.
Correlation       Safetv Limit XNB              1.17 ANFP              1.154 HTP              1.141 The Basis is revised to explain the incorporation of the HTP correlation.
Also references are added that provide further insight into the development and limitations of the correlation.
Also references are added that provide further insight into the development and limitations of the correlation.
II. Discussion The proposed change adds an NRC approved DNB correlation and associated safety limit. The HTP correlation is an extension of the ANFP correlation.
II. Discussion The proposed change adds an NRC approved DNB correlation and associated safety limit. The HTP correlation is an extension of the ANFP correlation. The HTP correlation reflects the results of additional DNB testing of high thermal performance (HTP) fuel. Siemens report EMF-92-153(P)(A) and correspondence from Ashok C. Thadani, Director -
The HTP correlation reflects the results of additional DNB testing of high thermal performance (HTP) fuel. Siemens report EMF-92-153(P)(A) and correspondence from Ashok C. Thadani, Director -Division of Systems Safety Analysis -Office of Nuclear Reactor Regulation, to R.A. Copeland of Siemens Power Corporation, dated December 28, 1993, document the approved methodology and the associated Safety Limit of maintaining a minimum DNBR of 1.141. Both the ANFP and HTP correlations are applicable to HTP fuel that is used at Palisades.
Division of Systems Safety Analysis - Office of Nuclear Reactor Regulation, to R.A. Copeland of Siemens Power Corporation, dated December 28, 1993, document the approved methodology and the associated Safety Limit of maintaining a minimum DNBR of 1.141. Both the ANFP and HTP correlations are applicable to HTP fuel that is used at Palisades. The HTP correlation is restricted to the operating conditions specified in the previously mentioned references, outside of which the ANFP correlation is used.
The HTP correlation is restricted to the operating conditions specified in the previously mentioned references, outside of which the ANFP correlation is used.
 
CONCURRENCES SPECIFICATIONS CHANGE HTP DNBR CORRELATION To the best of my knowledge, the contents of this Technical Specifications change request describing proposed changes which add an DNBR correlation o the Safety Limits are truthful and complete.
TE~ICAL HTP SPECIFICATIONS CHANGE REO~T DNBR CORRELATION CONCURRENCES To the best of my knowledge, the contents of this Technical Specifications change request describing proposed changes which add an addit~onal DNBR correlation o the Safety Limits are truthful and complete.
RJ Ger. g, Reacto and Safety Analysis Engineering Manager DW Operations Manager KM Haas, Plant Safety and Licensing Director III. Analysis of No Significant Hazards Considerations .Consumers Power Company finds the activities associated with this Technical Specifications (TS) change involve no significant hazards and accordingly, a no significant hazards determination per 10 CFR 50.92(c) is justified.
RJ Ger. g, Reacto and Safety Analysis Engineering Manager QJ~                  ~
The following evaluation supports the finding that operation of the facility in accordance with the proposed TS would not: 1. Involve a significant increase in the probability or consequences of an accident previously evaluated.
DW Rogers~
The proposed change to the TS adds the HTP critical heat flux correlation to the Safety Limit -Reactor Core Section 2.1. The HTP correlation is an NRC approved methodology for a Departure from Nucleate Boiling (DNB) Correlation for high thermal performance (HTP) fuel as is used at Palisades.
Operations Manager
The HTP correlation is an extension of the currently approved ANFP correlation.
  /~
There are no associated changes in plant operation.
KM Haas, Plant Safety and Licensing Director
Palisades fuel loaded in cycle 9 and later meet the requirements of the HTP correlation.
 
III. Analysis of No Significant Hazards Considerations
    .Consumers Power Company finds the activities associated with this Technical Specifications (TS) change involve no significant hazards and accordingly, a no significant hazards determination per 10 CFR 50.92(c) is justified. The following evaluation supports the finding that operation of the facility in accordance with the proposed TS would not:
: 1. Involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed change to the TS adds the HTP critical heat flux correlation to the Safety Limit - Reactor Core Section 2.1. The HTP correlation is an NRC approved methodology for a Departure from Nucleate Boiling (DNB) Correlation for high thermal performance (HTP) fuel as is used at Palisades. The HTP correlation is an extension of the currently approved ANFP correlation. There are no associated changes in plant operation. Palisades fuel loaded in cycle 9 and later meet the requirements of the HTP correlation.
Therefore, operation of the facility in accordance with the proposed TS would not result in a significant increase in the probability or consequences of an accident previously evaluated.
Therefore, operation of the facility in accordance with the proposed TS would not result in a significant increase in the probability or consequences of an accident previously evaluated.
: 2. Create the possibility of a new or different kind of accident from any previously evaluated.
: 2. Create the possibility of a new or different kind of accident from any previously evaluated.
The HTP correlation will allow for more accurate DNB predictions within the applicable operating conditions for fuels with the HTP design used at Palisades.
The HTP correlation will allow for more accurate DNB predictions within the applicable operating conditions for fuels with the HTP design used at Palisades. There are no changes in plant operation.
There are no changes in plant operation.
Therefore operation of the facility in accordance with the proposed TS would not create the possibility of a new or different kind of accident from any previously evaluated.
Therefore operation of the facility in accordance with the proposed TS would not create the possibility of a new or different kind of accident from any previously evaluated.
: 3. Involve a significant reduction in a margin of safety. As stated previously, the HTP correlation will allow for more accurate DNB predictions within the applicable operating conditions for fuel with the HTP design. There are no associated changes in plant operation.
: 3. Involve a significant reduction in a margin of safety.
Therefore, operation of the facility in accordance with the proposed TS would not involve a significant reduction in a margin of safety. IV. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specifications change request and has determined that the change involves no significant hazards consideration.
As stated previously, the HTP correlation will allow for more accurate DNB predictions within the applicable operating conditions for fuel with the HTP design. There are no associated changes in plant operation. Therefore, operation of the facility in accordance with the proposed TS would not involve a significant reduction in a margin of safety.
This change has been reviewed by the Nuclear Performance Assessment Department.
IV. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specifications change request and has determined that the change involves no significant hazards consideration. This change has been reviewed by the Nuclear Performance Assessment Department. A copy of this Technical Specifications change request has been sent to the State of Michigan.
A copy of this Technical Specifications change request has been sent to the State of Michigan.
 
CONSUMERS POWER COMPANY To the best of my knowledge, the contents of this Technical Specifications change request, adding an additional DNBR correlation to the Safety Limits, are truthful and complete.
CONSUMERS POWER COMPANY To the best of my knowledge, the contents of this Technical Specifications change request, adding an additional DNBR correlation to the Safety Limits, are truthful and complete.
By  
By ~~~;;....a...___,;d._
..
                    . ......_$_~-"----'==---
Robert A. Fenech, Vice President Nuclear Operations Sworn and subscribed to before me this Jj_ day of 1994. LeAnn Morse, Notary Public Berrien County, Michigan (Acting in Van Buren County, Michigan)
Robert A. Fenech, Vice President Nuclear Operations Sworn and subscribed to before me this Jj_ day of Q~ 1994.
My commission expires February 4, 1997 [SEAL] *' ', ' ' *'}}
LeAnn Morse, Notary Public Berrien County, Michigan (Acting in Van Buren County, Michigan)
My commission expires February 4, 1997
[SEAL]
                                                                        ', ' ' *'}}

Latest revision as of 10:42, 3 February 2020

Application for Amend to License DPR-20,adding Third High Thermal Performance DNB Correlation to Safety Limit 2.1
ML18064A506
Person / Time
Site: Palisades Entergy icon.png
Issue date: 12/13/1994
From: Haas K
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18064A507 List:
References
NUDOCS 9412220065
Download: ML18064A506 (5)
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Text

consumers Power KurtM. Haas Plant Safety and Licensing Director l'OWERINli Mlt:HlliAN'S PROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043

.December 13, 1994 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT TECHNICAL SPECIFICATIONS CHANGE REQUEST - HIGH THERMAL PERFORMANCE DNB CORRELATION A request for a change to the Palisades Technical Specifications is enclosed.

This Technical Specification change request (TSCR) proposes addition of a third DNB correlation to Safety Limit 2.1. This "HTP" DNB correlation is used for the High Thermal Performance fuel loaded during recent Palisades fuel cycles.

The following attachments are included:

1) Proposed Technical Specifications pages
2) Existing pages marked to show proposed changes The HTP correlation is being used in the Cycle 12 accident analyses, therefore, we request that the Technical Specifications Amendment approving that change be approved and become effective prior to the end of the upcoming refueling outage which is currently planned to be completed in late July 1995. We will keep the NRR project manager aware of any changes in the planned refueling outage schedule.

Summary of Commitments:

This letter does not make or alter any commitments to the NRC.

I Kurt M. Haas Director, Plant Safety & Licensing CC Administrator, Region III, USNRC Resident Inspector, Palisades State of Michigan Attachments 9412220065 941213 PDR p

ADOCK 05000255 PnR

  • A GMS' ENER6YCOMPANY f\Wl I I

It is requested that the Technical Specifications contained in the Facility Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on February 21, 1991, for the Palisades Plant be changed as described below:

I. Changes It is proposed that the specifications below be changed to incorporate the HTP critical heat flux correlation. The following changes are proposed:

Safety Limit 2.1:

The HTP DNB correlation is added under the Correlation column and its appropriate minimum DNB limit is added under the Safety Limit.

That column currently lists XNB and ANFP DNB correlations and their respective limits. The proposed Safety Limit would be:

The Minimum DNBR of the reactor core shall be maintained greater than or equal to the DNB correlation safety limit.

Correlation Safetv Limit XNB 1.17 ANFP 1.154 HTP 1.141 The Basis is revised to explain the incorporation of the HTP correlation.

Also references are added that provide further insight into the development and limitations of the correlation.

II. Discussion The proposed change adds an NRC approved DNB correlation and associated safety limit. The HTP correlation is an extension of the ANFP correlation. The HTP correlation reflects the results of additional DNB testing of high thermal performance (HTP) fuel. Siemens report EMF-92-153(P)(A) and correspondence from Ashok C. Thadani, Director -

Division of Systems Safety Analysis - Office of Nuclear Reactor Regulation, to R.A. Copeland of Siemens Power Corporation, dated December 28, 1993, document the approved methodology and the associated Safety Limit of maintaining a minimum DNBR of 1.141. Both the ANFP and HTP correlations are applicable to HTP fuel that is used at Palisades. The HTP correlation is restricted to the operating conditions specified in the previously mentioned references, outside of which the ANFP correlation is used.

TE~ICAL HTP SPECIFICATIONS CHANGE REO~T DNBR CORRELATION CONCURRENCES To the best of my knowledge, the contents of this Technical Specifications change request describing proposed changes which add an addit~onal DNBR correlation o the Safety Limits are truthful and complete.

RJ Ger. g, Reacto and Safety Analysis Engineering Manager QJ~ ~

DW Rogers~

Operations Manager

/~

KM Haas, Plant Safety and Licensing Director

III. Analysis of No Significant Hazards Considerations

.Consumers Power Company finds the activities associated with this Technical Specifications (TS) change involve no significant hazards and accordingly, a no significant hazards determination per 10 CFR 50.92(c) is justified. The following evaluation supports the finding that operation of the facility in accordance with the proposed TS would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed change to the TS adds the HTP critical heat flux correlation to the Safety Limit - Reactor Core Section 2.1. The HTP correlation is an NRC approved methodology for a Departure from Nucleate Boiling (DNB) Correlation for high thermal performance (HTP) fuel as is used at Palisades. The HTP correlation is an extension of the currently approved ANFP correlation. There are no associated changes in plant operation. Palisades fuel loaded in cycle 9 and later meet the requirements of the HTP correlation.

Therefore, operation of the facility in accordance with the proposed TS would not result in a significant increase in the probability or consequences of an accident previously evaluated.

2. Create the possibility of a new or different kind of accident from any previously evaluated.

The HTP correlation will allow for more accurate DNB predictions within the applicable operating conditions for fuels with the HTP design used at Palisades. There are no changes in plant operation.

Therefore operation of the facility in accordance with the proposed TS would not create the possibility of a new or different kind of accident from any previously evaluated.

3. Involve a significant reduction in a margin of safety.

As stated previously, the HTP correlation will allow for more accurate DNB predictions within the applicable operating conditions for fuel with the HTP design. There are no associated changes in plant operation. Therefore, operation of the facility in accordance with the proposed TS would not involve a significant reduction in a margin of safety.

IV. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specifications change request and has determined that the change involves no significant hazards consideration. This change has been reviewed by the Nuclear Performance Assessment Department. A copy of this Technical Specifications change request has been sent to the State of Michigan.

CONSUMERS POWER COMPANY To the best of my knowledge, the contents of this Technical Specifications change request, adding an additional DNBR correlation to the Safety Limits, are truthful and complete.

By ~~~;;....a...___,;d._

. ......_$_~-"----'==---

Robert A. Fenech, Vice President Nuclear Operations Sworn and subscribed to before me this Jj_ day of Q~ 1994.

LeAnn Morse, Notary Public Berrien County, Michigan (Acting in Van Buren County, Michigan)

My commission expires February 4, 1997

[SEAL]

', ' ' *'

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