ML20210L594

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Forwards SE Re Licensing of TR NEDC-32410P,Suppl 1, Nuclear Measurement Analysis & Control Power Range Neutron,Monitor Retrofit Plus Option III Stability Trip Function, Submitted by GE on 960524
ML20210L594
Person / Time
Issue date: 08/15/1997
From: Matthews D
NRC (Affiliation Not Assigned)
To: Reigel D
GENERAL ELECTRIC CO.
Shared Package
ML20210L597 List:
References
TAC-M95746, NUDOCS 9708210236
Download: ML20210L594 (3)


Text

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. speeHoot 4,*****

August 15, 1997 Mr. David W. Reigel Project Manager Generic NUMAC PRNM Licensing General Electric Company 175 Curtner Avenue San Jose, California 95125

SUBJECT:

LICENSING TOPICAL REPORT NEDC-32410P, SUPPLEMENT 1, NUCLEAR MEASUREMENT ANALYSIS AND CONTROL POWER RANGE NEUTRON MONITOR (NUMAC-PRNM) RETROFIT PLUS OPTION 111 STABILITY TRIP FUNCTION (TAC NO. M95746)

Dear Mr. Reigel:

The staff has completed its review of Supplement I to the Topical Report NEDC-32410P, " Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC-PRNM) Retrofit Plus Option Ill Stability Trip Function," submitted by General Electric Company (GE) by letter dated May 24, 1996. Additional information concerning this topical report was provided in a letter dated September 30, 1996. This topical report clarifies issues related to the Average Power Range Monitor (APRM) and APRM technical specifications, and proposed technical specifications for the Oscillation Power Range Monitor (OPRM). The staff previously approved Topical Report NEDC-32410P in its safety evaluation transmitted by letter dated September 5, 1995. The staff has reviewed NEDC-32410P, Supplement 1, and concludes that it is acceptable.

The staff safety evaluation approving NEDC-32410P, Supplement 1. is attached.

The conditions for implementing the Supplement I technical specifications amendments are as stated in the staff's September 5,1995 safety evaluation approving NEDC-32410P.

The staff does not intend to repeat its review of the matters found acceptable as described in NEDC-32410P, Supplement 1, when the topical report is referenced in plant specific license amendment applications, except to ensure that the material presented is applict.ble to the specific plant involved. The staff's acceptance applies only to the matters described in the application of MWN NEDC-32410P, and Supplement 1.

In accordance with procedures established in NUREG-0390, the staff requests that GE publish accepted versions of this topical report within three months of receipt of this letter. The accepted versions should include an "A" (designating accepted) following the report identification symbol, and the staff's safety evaluation report.

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David W. Reigle August 15. 1997 Should NRC criteria or regulations change so as to invalidate the conclusions concerning acceptability of the report GE or the applicants referencing the topical report will be expected to revise or resubmit their respective documentation, or submit justification for the continued effective applicability of the topical report without revision of their respective documentation.

This letter is being reissued to correct an error in our previous letter to you dated December 26, 1997, and supercedes that previous letter in its entirety.

If you have any questions concerning the staff's safety evaluation, please contact the NRC project manager, Jim Wilson, at (301) 415-1108.

Sincerely, David B. Matthews, Chief Generic issues and Environmental Projects Branch, Division of Reactor Program Management

Attachment:

as stated cc: see attached list

David W. Reigle -2. August 15, 1997 Should NRC criteria or regulations change so as to invalidate the conclusions concerning acceptability of the report, GE or the applicants referencing the topical report will be expected to revise or resubmit their respective documentation, or submit justification for the continued effective applicability of the topical report without revision of their respective documentation.

This letter is being reissued to correct an (rror in our previous letter to you dated December 26, 1997, and supercedes that previous letter in its entirety.

If you have any questions concerning the staff's safety evaluation, please contact the NRC project manager, Jim Wilson, at (301) 415-1108.

Sincerely, David B. Matthews, Chief Generic issues and Environmental Projects Branch, Division of Reactor Program Management

Attachment:

as stated cc: See next page DISTRIBUTION:

PUBLIC PGEB r/f BBoger JWermiel MCase MWaterman Central DMatthews JMauck JHWilson JRoe BZalcman Document Name: GEREIGLE.LTR _ i/

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