ML18066A738

From kanterella
Jump to navigation Jump to search
Application for Amend to License DPR-20,allowing Use of Both Anfp DNB Correlation & Xnb DNB Correction to Establish New Reactor Protective Sys Setpoints & New Limiting Conditions for Cycle 9 Fuel Operation.Encl Proprietary Rept Withheld
ML18066A738
Person / Time
Site: Palisades Entergy icon.png
Issue date: 08/31/1990
From: Slade G
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18057A433 List:
References
NUDOCS 9009060045
Download: ML18066A738 (4)


Text

consumers

  • Power GB Slade General Manager l'OWERINli MICHlliAN'S l'ROliRESS Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert; Ml 49043 August 31, 1990 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -

DNB CORRELATION - TECHNICAL SPECIFICATIONS CHANGE REQUEST This proposed change to the Technical Specifications is necessary to allow use of- both the ANFP DNB correlation and the XNB DNB correction to establish riew Re~ctor Protective System (RPS) setpoints and new limiting Conditions for Operations (LCO's) for Cycle 9 fuel. Proposed setpoints and LCO's for Cycle 9 will be submitted at a later date as part of another Technical Specification Change Request. Fuel for Cycle 9 will be loaded in late December 1990.

Therefore, Consumers Power Company requests approval of this proposed technical specification change prior to startup from the upcoming refueling outage and that the change be made effective on the date of issuance. contains the proposed changed*pages, Attachment 2 has marked up page changes, and Attachment 3 is the proprietary ANF Report No ANF-89-192(P).

An affidavit justifying withholding that report from public disclosure is included.

~k-r--*

Gerald B Slade General Manager CC Administrator, Region III, USNRC (W/O Attachment 3)

NRC Resident Inspector - Palisades (W/O Attachment 3)

Attachments 9009060045 900831

~I.~ ADOCK 05000255 PDC _}

OC0890-0403-NL02 A CMS' ENERGY COMPANY f1po1

'f 1

1 CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below:

I. Changes A. In Section 2.1 under Specifications, change the sentence to read:

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

B. The Basis of Section 2.1 has been changed to delete reference to the MDNBR as 1.17 and reference is made instead to "the DNB correlation safety limit". Two references and a Table have been added. (See page changes.)

C. In the Basis for Section 3.1, the reference to the minimum DNBR equal to 1.17 is changed to "the minimum DNBR is equal to the DNB correlation safety limit".

II. Discussion

  • The purpose of this change is to allow the use of both the NRC approved generic ANFP DNB correlation and the XNB DNB correlation for Cycle 9 fuel. Reload M is being added to the core for Cycle 9 and is high thermal performance fuel design. The spacer grids and intermediate flow mixers increase subchanpel mixing. Therefore, ANF developed the ANFP DNB correlation using test data representing the thermal performance of the new fuel design. The NRC found the application of the ANFP DNB corre.lation acceptable for use with XCOBRA-IIIC under the limitations delineated in the accociated NRC technical evaluation. ANF has included a copy of the NRC evaluation in the ANF-1224(P)(A) topical report.

Cycle 9 fuel is made up of reloads I, J, K, L, and M. The XNB DNB correlation safety limit will be used for fuel from Reloads I, J, K, and L, while the ANFP DNB correlation safety limit will be used for Reload M. With both correlations, the correlation safety limit will assure, with a 95% probability, that 95% of the fuel rods in the core are protected against experiencing transition heat transfer conditions.

This change allows use of the ANFP DNB correlation with its DNB correlation safety limit for Reload M. It does not effect plant hardware, operating limits or limiting conditions of operation.

OC0890-0403-NL02

2 III. Analysis of No Significant Hazards Consideration Consumers Power Company finds that activities associated with this Change Request include no siginficant hazards; and accordingly, a no significant hazards determination per 10CFR 50.92 (c) is justified. The following evaluation supports the finding that the proposed change would not:

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

This change only allows use of a different DNB correlation and MDNBR. It does not effect plant hardware, plant operation limits nor limiting conditions of operation. Therefore, it does not increase the probability or consequences of an accident previously evaluated.

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

This change does not effect plant operations or hardware.

Therefore it does not create the possibility of a new or different kind of accident from any accident previously evaluated.

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

The existing margin of safety is a 95% probability that 95% of the fuel rods in the core are protected against experiencing transition heat transfer conditions. The DNB correlation safety limits for both the previously used XNB DNB correlation and the ANFP DNB correlation will assure, with a 95%

probability, that 95% of the fuel rods will be protected against experiencing transition heat transfer conditions.

Thus, the mar~in of safety is not reduced.

OC0890-0403-NL02

3 IV. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined that this change does not involve an unreviewed safety question and, therefore, involves no significant hazards consideration. This change has been reviewed by the Nuclear Safety Services Department. A copy of this Technical Specification Change Reques.t has been sent to the State of Michigan official designated to receive such Amendments to the Operating License.

CONSUMERS POWER COMPANY To the best of my knowledge, information and belief, the contents of this Technical Specification Change Request are truthful and complete.

B~ David Sworn and subscribed to before me this 3/th day of !1tt.1~~f 1990 ..

./

[SEAL]

A Avery, Not y Public Jackson County, Michigan My commission expires December 7, 1992 OC0890-0403-NL02