ML20129C271

From kanterella
Revision as of 16:37, 21 August 2022 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Forwards Safety Evaluation Re SPDS Design,Per NRC .Implementation Does Not Involve Unreviewed Safety Question & Does Not Require Change to Tech Specs. Implementation Will Be Completed by Apr 1986
ML20129C271
Person / Time
Site: Maine Yankee
Issue date: 05/31/1985
From: Whittier G
Maine Yankee
To: John Miller
Office of Nuclear Reactor Regulation
Shared Package
ML20129C276 List:
References
RTR-NUREG-0737, RTR-NUREG-737 5835L-SEN, 8535L-SEN, GDW-85-160, GL-82-33, MN-85-106, NUDOCS 8506050453
Download: ML20129C271 (2)


Text

, __-

m-

,n*

O MAME HARHEE ATOM 10 POWER 00MPARUe auaugraja?n"e%s (k (207) 623-3521 9

May 31, 1985 MN-85-106 GDW-85-160 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. James R. Miller, Cnief Operating Reactors Branch No. 3 Division of Licensing

References:

(a) License No. [PR-36 (Docket No. 50-309)

(b) USNRC Letter to MYAPCo dated December 17, 1985, Supplement 1 to NUREG-0737 (Generic Letter No. 82-33)

(c) USNRC Letter to MYAPCo dated June 14, 1984 - Order Confirming Licensee Commitments on Emergency Response Capability (d) USNRC Letter to MYAPCo dated March 6, 1985

Subject:

Maine Yankee Safety Parameter Display System - Safety Evaluation Gentlemen:

In accordance with References (b) and (d), enclosed is a safety evaluation of the Maine Yankee Atomic Power Company Safety Parameter Display System (SPDS).

Maine Yankee has reviewed the SPDS design in accordance with Section 50.59 of the Commission's Rules and Regulations. Implementation of the SPDS does not involve an unreviewed safety question, and does not require change to our technical specifications.

Maine Yankee plans to install the SPDS hardware during the upcoming refueling outage, and complete implementation by April of 1986. The Maine

. Yankee Plant Operations Review Committee (PORC) has reviewed the plant hardware changes associated with the SPDS. The PORC has determined that the hardware changes do not involve an unreviewed safety question (P01C-84-20).

The PORC will review the software changes associated with the SPDS prior to implementation. Inplementation cannot proceed unless the PORC verifles that no unreviewed safety question is involved.

8506050453 850531 PDR ADOCK 05000309 Aoo3 gg F PDR f

5835L-SEN

, - - .y-1 s.

J MAINE YANKEE ATOMIC POWER COMPANY g

' United States Nuclear Regulatory Commission Page Two

' Attention: - Mr. James R. Miller, Chief

M-85-106 We trust this information is' satisfactory. Should you have any questions,

~ please contact us.

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

Enclosure:

(29 pages) cc: Dr. Thomas E. Marley Mr. Cornelius F. Holden 5835L-SEN J