ML19347C981

From kanterella
Jump to navigation Jump to search

Application for Amend to Licenses NPF-5 & DPR-57,submitted as Proposed Changes to Tech Specs Re BWR Scram Sys Design
ML19347C981
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 02/26/1981
From: Widner W
GEORGIA POWER CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML19347C983 List:
References
TAC-42218, TAC-42219, TAC-43684, TAC-43685, NUDOCS 8103100425
Download: ML19347C981 (3)


Text

c-

4; m.n ;

no n,,

Uc ' C

  • r e W: < ' s

,, o 33 3 -

r,

,.n m e o L

W. A. Widner February 26, 1981 Georgia Power u.l,e a: l ?," " " ~#

  1. 2+"+nv' U. S. Nuclear Regulatory Commission Office of tbclear Reactor Regulation s

Washington, D. C.

20555

/

g NRC 00CKETS 50-321, 50-366 y(

O

,a OPERATING LICENSES DPR-57, NPF-5 (01 W.A EDWIN I. HATCH NUCLEAR PLANT UNITS 1,)/,

BWR SCRAM SYSTEM DESIGN 8

g Gentlemen:

(b y

In accordance with the provisions of 10 CFR 50.90, as required by 10 CFR 50.59(c)(1), Georgia Power Company hereby proposes amendments to Operating Licenses NPF-5 and DPR-57.

The proposed amendment would be to incorporate revised Technical Specifications in response to your July 7, 1980, letter.

The proposed Technical Specifications will strengthen the provisions for assuring continued operability of the control rod drive system during reactor operation by providing surveillance requirements on the scram discharge volume vent and drain valves.

In addition, the pressure relie f valves are added to the existing tables of containment isolation valves and included in the normal surveillance requirements.

The proposed changes in no way alter system design or operation, and thus do not create the possibility of a new accident or malfunction of equipment, nor does it increase the probability of previously analyzed accidents or malfunctions.

Margins of safety are increased by the addition of periodic surveillance on these valves which become containment isolation valves during the time period following a scram and before the scram is reset.

The Plant Review Board and the Safety Review Board have revi2wed the proposed changes to the Technical Specifications and the basis, stated above, for the proposed changes, and have concluded that they do not involve an unreviewed safety question.

Accordingly, we therefore request your review and approval of the proposed changes to the Technical Specifications as shown in the attachments.

Very truly yours, 22'dM Me c03/

W A. Widner 0,0 f RDB/mb

')

Attachments Sworn to and subscribed before me this 26th day of February,1981.

hD0n

~

/

f40ta y Pubbc. Georgia, Sta;c at Large My Commission Expires Sept. 20,1983 xc:

R. F. Rogers, III

-810 310 0f.f6

[

M. Manry

~

ATTACHMENT 1 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 PROPOSED-CHANGES TO TECHNICAL SPECIFICATIONS

- Pursuant to 10 CFR 170.12 (c),

Georgia Power Company has evaluated the attached proposed amendment to Operating Licenses zDPR-57 and NPF-5 and has determined that:

a).

of' a new Safety Analysis Report or rewrite of the The proposed amendment does not require the evaluation facility license; b)

.The proposed amendment does not contain several complex' issues, does not involve ACRS review, and does not require an environmental impact statement; c).

The. proposed amendment-does not involve a

complex

- issue, an environmental issue or more than one safety issue;-

.. d )

. issue,lnamely, the addition ~of scram discharge volume The proposed _ amendment does involve a single - safety vent ~ valves, drain valves,-and pressure relie f valves to the existing tables of' containment isolationLvalves.

e)

- The -- proposed change is therefore a Class III amendment

for one unit and a Class I. amendment for the other

. unit.

j.

t

..L.

a n

m..

m.sL

m. m.

m-.2...

.i 2

m J

ATTACHMENT 2 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I.

HATCH NUCLEAR PLANT UNIT 2 PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS The proposed change to Technical Specifications (Appendix A to Operating License NPF-5) would be incorporated as follows:

Remave Page Insert Page 3/4 6-23 3/4 6-23 3/4 6-32 3/4 6-32 A