ML18059A692: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 20: Line 20:


=Text=
=Text=
{{#Wiki_filter:" . consumers Power POWERINli 11/tlCHlliAN'S PROliRE55 Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 February 22, 1994 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 GB Slade General Manager DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -TECHNICAL SPECIFICATIONS CHANGE REQUEST -INSTRUMENTATION AND CONTROL -REVISED PAGES. A complete set of revised pages for our November 15, 1991 Technical Specifications change request, "Instrumentation and Control" are attached.
{{#Wiki_filter:" .
The changes made by the revised pages are the result of suggestions and comments made by NRR reviewers, Doris Liao and Iqbal Ahmed. Answers to questions posed by Mr. Ahmed, during his review, have been attached.
consumers Power                                               GB Slade General Manager
Revised basis pages have also been attached.
          ~-,, POWERINli 11/tlCHlliAN'S PROliRE55 Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 February 22, 1994 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - TECHNICAL SPECIFICATIONS CHANGE REQUEST - INSTRUMENTATION AND CONTROL - REVISED PAGES.
In addition to updating the changes proposed in our November 15, 1991 submittal, four other changes are proposed:
A complete set of revised pages for our November 15, 1991 Technical Specifications change request, "Instrumentation and Control" are attached. The changes made by the revised pages are the result of suggestions and comments made by NRR reviewers, Doris Liao and Iqbal Ahmed. Answers to questions posed by Mr. Ahmed, during his review, have been attached. Revised basis pages have also been attached. In addition to updating the changes proposed in our November 15, 1991 submittal, four other changes are proposed:
: 1) Proposed page 4-6 has been updated to reflect changes proposed for the Palisades Technical Specifications (TS) in response to Generic Letter (GL) 90-06. Parts 4.la, and 4.lb of our November 15, 1991 change request have been replaced by parts 4.1.1.1 through 4.1.1.4 of the February 2, 1994 submittal for GL 90-06. The technical content is nearly identical, and the GL 90-06 TS wording is the result of detailed discussions with the NRC staff (refer to our June 25, 1993 letter on Technical Specifications for Overpressure Protection).
: 1)         Proposed page 4-6 has been updated to reflect changes proposed for the Palisades Technical Specifications (TS) in response to Generic Letter (GL) 90-06. Parts 4.la, and 4.lb of our November 15, 1991 change request have been replaced by parts 4.1.1.1 through 4.1.1.4 of the February 2, 1994 submittal for GL 90-06. The technical content is nearly identical, and the GL 90-06 TS wording is the result of detailed discussions with the NRC staff (refer to our June 25, 1993 letter on Technical Specifications for Overpressure Protection).
: 2) A revised page 3-1, containing a proposed section 3.0.5, and a new page 3-lac have been included in the revised pages. The proposed Specification 3.0.5 and its Basis are taken from NUREG 1432, Standard Technical Specifications, Combustion Engineering Plants. This new specification is necessary to allow testing and repair of equipment taken out of service in accordance with requirements of the proposed action statements, the same reason for which it was added to the new standard technical specifications.
: 2)       A revised page 3-1, containing a proposed section 3.0.5, and a new page 3-lac have been included in the revised pages. The proposed Specification 3.0.5 and its Basis are taken from NUREG 1432, Standard Technical Specifications, Combustion Engineering Plants. This new specification is necessary to allow testing and repair of equipment taken out of service in accordance with requirements of the proposed action statements, the same reason for which it was added to the new standard technical specifications.
9403070242 940222 PDR ADOCK 05000255 P PDR A CMS' e:NCRGY COMPANY
9403070242 940222 PDR ADOCK 05000255 P                             PDR A CMS' e:NCRGY COMPANY
.!.-** ..,. c' 3) 4)
 
.!.-**
      ..,. c' ~
3)
* A revised page 2-2, containing the Reactor Protective System trip settings, and an associated revised Basis page B 2-5, have been included.
* A revised page 2-2, containing the Reactor Protective System trip settings, and an associated revised Basis page B 2-5, have been included.
These pages propose changing the existing Low Steam Generator Level reactor trip setting. This change is to co-ordinate the settings for reactor trip (page 2-2) and for Auxiliary Feedwater (AFW) initiation (page 3-63). Both signals are initiated by the same instrument channels, and both signals have the same minimum setting. The setpoint for both signals are proposed as 25.9%" rather than the current reactor trip setting of "Above the feedwater ring center line." The AFW pump start setpoint is not currently specified in the Technical Specifications.
These pages propose changing the existing Low Steam Generator Level reactor trip setting. This change is to co-ordinate the settings for reactor trip (page 2-2) and for Auxiliary Feedwater (AFW) initiation (page 3-63). Both signals are initiated by the same instrument channels, and both signals have the same minimum setting. The setpoint for both signals are proposed as "~ 25.9%" rather than the current reactor trip setting of "Above the feedwater ring center line." The AFW pump start setpoint is not currently specified in the Technical Specifications. As discussed in the supplied Basis page, the proposed 25.9% indicated level corresponds to the physical position of the feedwater ring center line. This change is proposed because, typically, TS limits are specified in the units indicated on control room monitors.
As discussed in the supplied Basis page, the proposed 25.9% indicated level corresponds to the physical position of the feedwater ring center line. This change is proposed because, typically, TS limits are specified in the units indicated on control room monitors.
: 4)    The explicit requirements for operability and surveillance of the Safety Injection Tank level and pressure instrument channels, items 3 and 4 of Tables 3.17.6 and 4.17.6 of the November-15, 1991 proposed-pages, have been deleted in accordance with the suggestions of GL 93-05, item 7.4.
The explicit requirements for operability and surveillance of the Safety Injection Tank level and pressure instrument channels, items 3 and 4 of Tables 3.17.6 and 4.17.6 of the November-15, 1991 proposed-pages, have been deleted in accordance with the suggestions of GL 93-05, item 7.4. The Description of Changes section of our November 15, 1991 letter describe how the new, re-numbered pages fit into the Technical Specifications.
The Description of Changes section of our November 15, 1991 letter describe how the new, re-numbered pages fit into the Technical Specifications. Attachment 4 contains suggested instructions for page replacement.
Attachment 1 contains the revised proposed Technical Specifications pages.
Attachment 2 contains the Bases for the proposed Technical Specifications.
Attachment 3 contains the answers to questions raised during Mr. Ahmed's review.
Attachment 4 contains suggested instructions for page replacement.
Attachment 4 contains suggested instructions for page replacement.
Attachment 1 contains the revised proposed Technical Specifications pages. Attachment 2 contains the Bases for the proposed Technical Specifications.
Attachment 3 contains the answers to questions raised during Mr. Ahmed's review. Attachment 4 contains suggested instructions for page replacement.
The changes proposed in this letter do not alter the conclusions of the No Significant Hazards Analysis contained in our November 15, 1991 letter on this subject. A copy of this letter has been sent to the State of Michigan.
The changes proposed in this letter do not alter the conclusions of the No Significant Hazards Analysis contained in our November 15, 1991 letter on this subject. A copy of this letter has been sent to the State of Michigan.
For-Gerald B Slade General Manager CC Administrator, Region III, USNRC Resident Inspector, Palisades Attachments}}
For-Gerald B Slade General Manager CC Administrator, Region III, USNRC Resident Inspector, Palisades Attachments}}

Revision as of 17:45, 21 October 2019

Forwards Revised Pages for Util 911115 TS Change Request Re Instrumentation & Control,As Result of Suggestions & Comments Made by NRR Reviewers.Answers to Questions Posed by I Ahmed & Revised Basis Pages Also Encl
ML18059A692
Person / Time
Site: Palisades Entergy icon.png
Issue date: 02/22/1994
From: Slade G
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18059A693 List:
References
RTR-NUREG-1432 GL-90-06, GL-90-6, NUDOCS 9403070242
Download: ML18059A692 (2)
v • d • e


Text

" .

consumers Power GB Slade General Manager

~-,, POWERINli 11/tlCHlliAN'S PROliRE55 Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, Ml 49043 February 22, 1994 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - TECHNICAL SPECIFICATIONS CHANGE REQUEST - INSTRUMENTATION AND CONTROL - REVISED PAGES.

A complete set of revised pages for our November 15, 1991 Technical Specifications change request, "Instrumentation and Control" are attached. The changes made by the revised pages are the result of suggestions and comments made by NRR reviewers, Doris Liao and Iqbal Ahmed. Answers to questions posed by Mr. Ahmed, during his review, have been attached. Revised basis pages have also been attached. In addition to updating the changes proposed in our November 15, 1991 submittal, four other changes are proposed:

1) Proposed page 4-6 has been updated to reflect changes proposed for the Palisades Technical Specifications (TS) in response to Generic Letter (GL) 90-06. Parts 4.la, and 4.lb of our November 15, 1991 change request have been replaced by parts 4.1.1.1 through 4.1.1.4 of the February 2, 1994 submittal for GL 90-06. The technical content is nearly identical, and the GL 90-06 TS wording is the result of detailed discussions with the NRC staff (refer to our June 25, 1993 letter on Technical Specifications for Overpressure Protection).
2) A revised page 3-1, containing a proposed section 3.0.5, and a new page 3-lac have been included in the revised pages. The proposed Specification 3.0.5 and its Basis are taken from NUREG 1432, Standard Technical Specifications, Combustion Engineering Plants. This new specification is necessary to allow testing and repair of equipment taken out of service in accordance with requirements of the proposed action statements, the same reason for which it was added to the new standard technical specifications.

9403070242 940222 PDR ADOCK 05000255 P PDR A CMS' e:NCRGY COMPANY

.!.-**

..,. c' ~

3)

  • A revised page 2-2, containing the Reactor Protective System trip settings, and an associated revised Basis page B 2-5, have been included.

These pages propose changing the existing Low Steam Generator Level reactor trip setting. This change is to co-ordinate the settings for reactor trip (page 2-2) and for Auxiliary Feedwater (AFW) initiation (page 3-63). Both signals are initiated by the same instrument channels, and both signals have the same minimum setting. The setpoint for both signals are proposed as "~ 25.9%" rather than the current reactor trip setting of "Above the feedwater ring center line." The AFW pump start setpoint is not currently specified in the Technical Specifications. As discussed in the supplied Basis page, the proposed 25.9% indicated level corresponds to the physical position of the feedwater ring center line. This change is proposed because, typically, TS limits are specified in the units indicated on control room monitors.

4) The explicit requirements for operability and surveillance of the Safety Injection Tank level and pressure instrument channels, items 3 and 4 of Tables 3.17.6 and 4.17.6 of the November-15, 1991 proposed-pages, have been deleted in accordance with the suggestions of GL 93-05, item 7.4.

The Description of Changes section of our November 15, 1991 letter describe how the new, re-numbered pages fit into the Technical Specifications. Attachment 4 contains suggested instructions for page replacement.

Attachment 1 contains the revised proposed Technical Specifications pages.

Attachment 2 contains the Bases for the proposed Technical Specifications.

Attachment 3 contains the answers to questions raised during Mr. Ahmed's review.

Attachment 4 contains suggested instructions for page replacement.

The changes proposed in this letter do not alter the conclusions of the No Significant Hazards Analysis contained in our November 15, 1991 letter on this subject. A copy of this letter has been sent to the State of Michigan.

For-Gerald B Slade General Manager CC Administrator, Region III, USNRC Resident Inspector, Palisades Attachments

Retrieved from "https://kanterella.com/w/index.php?title=ML18059A692&oldid=1946776"