ML20072T363: Difference between revisions

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h          Nebraska Public Power District LOA 8300095
                                                                    * ""$$hhfbeid'** *"
February 25, 1983 Office of Nuclear Reactor Regulation Operating Reactors Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention:    Mr. D. B. Vassallo, Chief
 
==Subject:==
Proposed Change to Technical Specifications -
SORC/SRAB Review Frequency Cooper Nuclear Station NRC Docket No. 50-298, DPR-46
 
==Reference:==
.1) Letter from D. G. Eisenhut to All Licensees dated October 1,  1982,  " Inconsistency Between Requirements of 10CFR50.54(t) and Standard Technical Specifications for Performing, Audits of Emergency Preparedness Programs."
: 2) Letter from D. G. Eisenhut to All Licensees dated October 30,  1982,  " Inconsistency  Between Requirements of 10CFR73.40(d) and Standard Technical Specifications for Performing Audits of Safeguards Contingency Plans (Security Plan)."
 
==Dear Mr. Vassallo:==
 
In accordance with the applicable provisions specified in 10CFR50, OO        Nebraska Public Power District requests that the Technical J
j          Specifications for Cooper Nuclear Station (CNS) be revised as indicated on the enclosed revised pages and as discussed below.
      ;I YO    References 1 and 2 required that the District perform independent review of the subject programs at 12-month intervals.        The present CNS Technical Specifications require that the Safety Review and Audit Board (SRAB) perform an independent review at a 24-month interval, while the CNS Emergency Plan and Security Plan require that the Quality Assurance Department perform an independent review at 12-month intervals. In discussions with the staff, the District was requested to revise the SRAB review requirements of the Technical Specifications so that confusion would not exist between QA and SRAB reviews and regulatory requirements. Thir revision has been performed in accordance with the staff's request and the Standard Technical 8304080056 8'30225' ~'      ' '
PDR ADOCK 05000298 P                  PDR
 
r-Mr. D . B . Vas=1lo Pega 2 February 25, 1983 Specifications for General Electric Boiling Water Reactors (NUREG-0123, Revision 3). Format and editorial changes are also proposed to bring the Administrative Control Section (Section 6.0) of the CNS Technical Specifications into closer conformance with the Standard Technical Specifications. This change will allow for easier revision in the future at the request of the NRC as well as alleviating confusion as to interpretation.
These changes have been reviewed by the necessary safety review committees. As stated in References 1 and 2, because this Technical Specification is clarifying and made at the request of the Commission, the District is not required to remit a license fee for the change.
A marked-up copy of the present Technical Specifications are being sent directly - to our Project Manager to assist him in assessing the editorial changes involved.
Should you have any questions or require additional information, please contact me.
In addition to three signed originals, 37 copies are also submitted for your use.
Sincerely, ay /. Pilant- k . W M^
Division Manager of Licensing & Quality Assurance JMP/jdw:emz25/11 Attachment 4
L}}

Revision as of 13:55, 25 July 2020

Application for Amend to License DPR-46,revising Tech Spec Safety Review & Audit Board (Srab) Review Requirements to Avoid Confusion Between QA & Srab Reviews of Emergency & Security Plans
ML20072T363
Person / Time
Site: Cooper Entergy icon.png
Issue date: 02/25/1983
From: Pilant J
NEBRASKA PUBLIC POWER DISTRICT
To: Vassallo D
Office of Nuclear Reactor Regulation
Shared Package
ML20072T366 List:
References
LQA8300095, TAC-49198, NUDOCS 8304080056
Download: ML20072T363 (2)


Text

.

h Nebraska Public Power District LOA 8300095

  • ""$$hhfbeid'** *"

February 25, 1983 Office of Nuclear Reactor Regulation Operating Reactors Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. D. B. Vassallo, Chief

Subject:

Proposed Change to Technical Specifications -

SORC/SRAB Review Frequency Cooper Nuclear Station NRC Docket No. 50-298, DPR-46

Reference:

.1) Letter from D. G. Eisenhut to All Licensees dated October 1, 1982, " Inconsistency Between Requirements of 10CFR50.54(t) and Standard Technical Specifications for Performing, Audits of Emergency Preparedness Programs."

2) Letter from D. G. Eisenhut to All Licensees dated October 30, 1982, " Inconsistency Between Requirements of 10CFR73.40(d) and Standard Technical Specifications for Performing Audits of Safeguards Contingency Plans (Security Plan)."

Dear Mr. Vassallo:

In accordance with the applicable provisions specified in 10CFR50, OO Nebraska Public Power District requests that the Technical J

j Specifications for Cooper Nuclear Station (CNS) be revised as indicated on the enclosed revised pages and as discussed below.

I YO References 1 and 2 required that the District perform independent review of the subject programs at 12-month intervals. The present CNS Technical Specifications require that the Safety Review and Audit Board (SRAB) perform an independent review at a 24-month interval, while the CNS Emergency Plan and Security Plan require that the Quality Assurance Department perform an independent review at 12-month intervals. In discussions with the staff, the District was requested to revise the SRAB review requirements of the Technical Specifications so that confusion would not exist between QA and SRAB reviews and regulatory requirements. Thir revision has been performed in accordance with the staff's request and the Standard Technical 8304080056 8'30225' ~' ' '

PDR ADOCK 05000298 P PDR

r-Mr. D . B . Vas=1lo Pega 2 February 25, 1983 Specifications for General Electric Boiling Water Reactors (NUREG-0123, Revision 3). Format and editorial changes are also proposed to bring the Administrative Control Section (Section 6.0) of the CNS Technical Specifications into closer conformance with the Standard Technical Specifications. This change will allow for easier revision in the future at the request of the NRC as well as alleviating confusion as to interpretation.

These changes have been reviewed by the necessary safety review committees. As stated in References 1 and 2, because this Technical Specification is clarifying and made at the request of the Commission, the District is not required to remit a license fee for the change.

A marked-up copy of the present Technical Specifications are being sent directly - to our Project Manager to assist him in assessing the editorial changes involved.

Should you have any questions or require additional information, please contact me.

In addition to three signed originals, 37 copies are also submitted for your use.

Sincerely, ay /. Pilant- k . W M^

Division Manager of Licensing & Quality Assurance JMP/jdw:emz25/11 Attachment 4

L