ML20205T711

Application for Amend to License NPF-11,changing Tech Spec Table 3.3.6-2 Re Control Rod Withdrawal Block Instrumentation Setpoints by Decreasing Rod Block Monitor Trip Setpoints & Allowable Values by 2%.Fee Paid

ML20205T711
Person / Time
Site:	LaSalle
Issue date:	06/10/1986
From:	Allen C COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20205T715	List: ML20205T711 ML20205T718
References
1756K, NUDOCS 8606160174
Download: ML20205T711 (2)

Text

. .

7 Commonwealth Edison y* ) 72 West Adams Street, Chicfgo, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690-0767 June 10, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 I

Subject:

LaSalle County Station Unit 1 Supplemental Information to Proposed Amendment Technical Specification for Facility Operating License NPF-ll - Reload Licensing Package for Cycle 2 NRC Docket No. 50-373 Reference (a): E. D. Adensam letter to D. L. Farrar dated May 9, 1986 transmitting Amendment 40.

Dear Mr. Denton:

Pursuant to 10 CPR 50.90, Commonwealth Edison (CECO) proposes to amend Appendix A, Technical Specification, to Facility Operating License NPF-11. These changes are being submitted for your staff's review and prompt attention, since approval of this amendment could affect Unit 1 startup date as discussed with Dr. Bournia of your staff on June 5, 1986.

LaSa11e's recently approved Unit 1, Cycle 2 Reload Licensing submittal (NPF-11, Amendment 40) selected the Rod Withdrawal Error (RWE) analysis performed with a Rod Block Monitor (RBM) rod block setpoint of 107%. After receipt of the amendment to the license, it was discovered that the amendment failed to reflect the RBM setpoint changes on Technical Specification Table 3.3.6-2, Control Rod Withdrawal Block Instrumentation Setpoints. To conform with the approved submittal, the RBM trip setpoints and allowable values on Table 3.3.6-2 must be decreased by 2% for both dual and single loop operation (see Attachment A).

Amendment No. 40 to NPF-ll also included two typographical errors which should be corrected (see Attachment A). First, the Thermal Hydraulic Stability specification on Index page VI does not exist and is being deleted.

The stability requirements are incorporated into Technical Specification 3.4.1.1-1 (Recirculation Loops). Second, the page number for Figure 3.4.1.1-1 (Core Thermal Power versus Total Core Flow graph for stability monitoring) is 8606160174 860610 PDR P

ADOCK 05000373 PDR g 9 Q $l50 k OO l

'h

3 June 10, 1986 H. R. Denton l

being changed to 3/4 4-lb to properly position the Figure in the Technical Specifications. This typo was identified with CM Allen letter to Dr. A.

Bournia dated May 12, 1986.

l The attached change has received both On-Site and off-Site review and approval. We have reviewed this amendment request and find that no j significant hazards consi wation exists. Our review is documented in l

Attachment C.

Commonwealth Edison is notifying the State of Illinois of our request for this amendment by transmitting a copy of this letter and attachments to the designated State Official. In accordance with 10 CFR j

l'10.12(c), enclosed is a check for $150.00.

Please direct any questions you may have concerning this matter to this office.

! One signed original and fifteen (15) copies of this transmittal and its attachments are provided for your use.

Very truly yours, C. M. Allen Nuclear Licensing Administrator 1m f

Attachments A: Technical Specification Change to NPF-ll B: Evaluation of No Significant Hazards Consideration cc: Region III Inspector - LSCS Dr. A. Bournia - NRR M. C. Parker - State of Ill 1756K

!