ML20091N359

From kanterella
Revision as of 05:40, 25 September 2022 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Suppl to 831230 Application to Amend Licenses NPF-4 & NPF-7, Changing Tech Specs to Revise P-7 Setpoint from Pressure Equivalent to 10% Rated Thermal Power to 10% Full Load Turbine Impulse Chamber Pressure
ML20091N359
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 06/04/1984
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, John Miller
Office of Nuclear Reactor Regulation
Shared Package
ML20091N362 List:
References
753A, NUDOCS 8406120291
Download: ML20091N359 (3)


Text

. ..

VInGINIA ELecTnIc Axn Powun COMPANY H icuxoxn, V HGINIA 20261 w.L.synwaar Vics P.. sin wr wucui. o,.. mon. June 4, 1984 Mr. Harold R. Denton, Director Serial No. 753A Office of Nuclear Reactor Regulation N0/JHL:acm Attn: Mr. James R. Miller, Chief Docket Nos. 50-338 Operating Reactors Branch No. 3 50-339 Division of Licensing License Nos. NPF-4 U. S. Nuclear Regulatory Commission NPF-7 Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY j NORTH ANNA POWER STATION UNIT NOS. 1 AND 2

! REVISION TO PROPOSED TECHNICAL SPECIFICATION CHANGE By our letter dated December 30, 1983 (Serial No. 753), we proposed a Technical Specifications change for North Anna Unit Nos. 1 and 2. The proposed change was to revise the P-7 setpoint from pressure equivalent to 10%

rated thermal power to 10% full load turbine impulse chamber pressure.

The purpose of this letter is to clarify our intent to the revision of the P-7 setpoint and to provide an updated discussion of the proposed Technical Specification change. To further clarify the P-7 setpoint we propose the Technical Specifications to read, " Pressure equivalent to 10% rated turbine .

power." This change will allow the system to be operated as designed and it '

remains consistent with the North Anna Power Station PLS and Setpoint Study. ,

The proposed Technical Specification change for North Anna Unit No. 1 is i provided in Attachment 1. The proposed Technical Specification change for North Anna Unit No. 2 is provided in Attachment 2. An updaced discussion of the proposed Technical Specification changes is provided in Attachment 3.

This clarified request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff.

It has been determined that this clarified request does not involve an l i

unreviewed safety question as defined in 10 CFR 50.59. l The proposed change does not pose a. significant hazards consideration as i described in the Federal Register, dated April 6, 1983, Page 14870, Example '

(1); a purely administrative change to the Technical Specifications: for example, a change to achieve consistency throughout the Technical Specifica-tions. The proposed change will provide consistency with the P-13 interlock.

The P-13 interlock is the input from the turbine impulse pressure channels to the P-7 interlock. The proposed change provides consistency with the North Anna Setpoint Study and PLS document. The proposed change will also' allow the systems to be operated as designed.

\

B406120291 840604 s\g PDR ADOCK 05000338 \

P PDR

r VinoixA Es.acraic Ano Powen COMPANY TO Harold R. Denton Since this letter clarifies our previous submittal and license amendment fees were submitted with the previous submittal, no additional license amendment fees should be required.

Vef truly yours, yi . ~

Ji W. L. Stewart Attachments:

1. Proposed Technical Specification Changes-Unit 1
2. Proposed Technical Specification Changes-Unit 2 3.- Updated Discussion of Proposed Technical Specification Changes cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. M. W. Branch NRC Resident Inspector North Anna Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219 6

9 4

i 4

4 l

y l

a 1

4

\

i o

Y ATTACRIENT 1 V

e i

2'

% . s. - _ . _ _ -. ... _ .