ML20126H162

Forwards Application for Amends to Licenses DPR-42 & DPR-60, Respectively,Revising Action 21 in Table TS 3.5-2B to Incorporate Statement Allowing 6 H to Trip an Inoperable Channel

ML20126H162
Person / Time
Site:	Prairie Island
Issue date:	12/29/1992
From:	Parker T NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20126H167	List: ML20126H162 ML20126H200 ML20126H211
References
NUDOCS 9301050086
Download: ML20126H162 (2)

Text

.

q Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota $54011927 Telephone (612) 330-5500 December 29, 1992 10 CFR Part 50  ;

Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50 282 License Nos. DPR-42 50 306 DPR 60 Revision to License Amendment Request Dated September 21, 1992 Instrumentation Specification Chances Attached is a revision to the September 21, 1992 License Amendment Request which proposed changes to surveillance test intervals and allowed outage times for the engineered safety features and reactor protection system instrumentation.

The original License Amendment Request proposed changes w!th respect to the shutdown margin requirements specified in Technical Specification Section 3.10.A. Those proposed changes were confusing and did not ci e ly delineate the shutdown margin requirements for plant modes where the reactor is subcritical. The attached revision incorporates a definition for shutdown margin and shutdown margin requirements which are consistent with the Westinghouse Standard Technical Specifications. The attached revision also corrects errors in the proposed Table TS.1-1 related to shutdown margin and updates the table such that the Prairie Island operational modes will be consistent with the Westinghouse Standard Technical Specification operational modes, The Section 3.5 and 4.1 tables have been revised as necessary w support of the change to Standard Technical Specification operational modes.

The original License Amendment Request proposed changing the Temperature for Hot Shutdown from 547'F to 535*F. The adoption of the Standard Technical Specification operational modes eliminates the need for that change and the-evaluation of that change has been eliminated from Exhibit A.

The attached revision also revises Action 21 in Table TS.3.5-2B to incorporate a statement allowing 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to trip an inoperable channel. This statement was inadvertently left out of Action 21 in the original License Amendment Request.

The definition of power operation was erroneously not deleted from Section 1,0 in the original License Amendment Request. That definition is being replaced ,

by the proposed operational mode table. The attached revision deletes the '

definition of power operation from Section 1.0.

9301050086 921229 PDR ADOCK 05000282 I P PDR

\ _

r Northern States Power Company December 29, 1992 Page 2 1

New degraded and undervoltage schemes have been installed at Prairie Island since-the original License Amendment Request was submitted. The attached revision incorporates these new schemes into the Section 3.5 and 4.1 tables and the Section 3.5 Bases.

The control room ventilation system chlorine monitor surveillance requirements are being deleted from Section 4.1 since the monitors are no longer required by the Prairie Island Technical Specifications.

Exhibit A for the original License Amendment Request, which contained the description of the proposed changes, the reasons for requesting the changes and the supporting safety evaluation /significant hazards determination has been revised to incorporate the changes described above. The revised Exhibit A is provided as Attachment 1. The revisions to Exhibit A are denoted by sidebars. The proposed revisions do not change the conclusions of the original significant hazards evaluation.

Attachment 2 contains marked up Technical Specification pages from the original License Amendment Request, with the revisions described above incorporated. Attachment 3 contains revised Technical Specification pages from the original License Amendment Request with the revisions described above incorporated.

Please contact Gene Eckholt (612-388-1121 Ext 4663) if you have any questions l related to this revision of the September 21, 1992 License Amendment Request.

tomas M Perker Director Nuclear Licensing c: Regional Administrator-III, NRC NRR Project Manager, NRC

(- Senior Resident Inspector, NRC State of Minnesota l

Attn: Kris Sanda J E Silberg l Attachments: Affidavit i

p Attachment 1 - Revision to Exhibit A. " Evaluation of Proposed l Changes to the Technical Specifications"

{

l Attachment 2 - Revision to Original Changes Marked Up on' l Existing Technical Specification Pages Attachment 3 - Revision to Original Revised Technical Specification Pages I

l- 1 a