ML20153H696

From kanterella
Jump to navigation Jump to search
Forwards Revised Page 2 to on Open Items & Items for Verification Re Emergency Feedwater Sys
ML20153H696
Person / Time
Site: Maine Yankee
Issue date: 02/25/1986
From: Whittier G
Maine Yankee
To: Thadani A
Office of Nuclear Reactor Regulation
References
6995L-GDW, GDW-86-42, MN-86-25, NUDOCS 8603030256
Download: ML20153H696 (2)


Text

. . p.

MAIRE HARHEE AToml0POWERCOMPARUe ,vaug,afu',,?n", o",'",'s h (207) 623-3521 e

February 25, 1986 MN-86-25 GOW-86-42 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Ashok C. Thadani, Director PWR Project Directorate #8 Division of Licensing

References:

(a) License No. OPR-36 (Docket No. 50-309)

(b) MYAPCo Letter to USNRC dated December 12,1985 (MN-85-174)

Subject:

Emergency Feedwater System Evaluation Open Items Gentlemen:

Reference (b) provided Maine Yankee's response to several open items and items for verification related to the Maine Yankee emergency feedwater system.

We wish to withdraw page two of our response and replace it with the attached revised page.

We apologize for any inconvenience this change may cause you.

Very truly yours, MAItE YANKEE ATOMIC POWER COWANY hhAV G. D. Whittier, Manager Nuclear Engineering & Licensing GDW/bjp

Attachment:

(1 Page) cc: Dr. Thomas E. Murley Mr. Cornelius F. Holden Mr. Pat Sears o\

o sN 0603030256 860225 PDR ADOCK 05000309PDR p

6995L-GDW

r MAINE YANKEE ATOMIC POWER COMPANY l

'J ATTACHENT The addition of another_ indicator on the-main control board is not justified and could have an overall adverse impact on safety in that unnecessary displays on the main control board are contrary to good human factors practices.

I:i summary, the design of the existing level indicators and alarms is appropriate. Changes to the existing design are not necessary, and could diminish safety.

NRC Open Item #3:

Safety grade automatic start circuit for motor driven pumps do not have approved Technical Spccifications. As stated in the "SER", ICSB is pursuing this matter - GL-1.

Maine Yankee Resoonse:

Maine Yankee has submitted a proposed change to our Technical Specifications covering the emergency feedwater system in a letter dated January 14,1985 (MN-85-10, Proposed Changa #110). It is our understanding from informal communications with the Staff that the matter of the auto-initiation logic testing has been resolved.

NRC Item For Verification #1:

Recommendation of GL The Licensee should provide verification that the valve internals had been removcd from the valve and the AFW supply lina.

Maine Yankee Response:

The internals to the valve in the AFW supply line have been removed. This action was documented by our letter dated June 12,1985 (Annual Report of Facility Changes and Relief and Safety Valve Failures and Challenges, MN-85-ll6).

PC Item for Verification #2:

Long Term Recommendation 4 - The Licensee should provide information regarding operator diversion time in the event a break occurs in the AFW header.

Maine Yankee Response:

In the highly unlikely event of a rupture of the EFW manifold during hot standby,'we estimate that the operators would have approximately 35 minutes to divert flow from the EFW manifold and through the 1st point heaters to prevent steam generator dry-out. This is sufficient time for the operators to perform the necessary manual actions required to divert EFW flow through the alternate path. )

l:

6995L-GOW.