ML19345F542
| ML19345F542 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 02/13/1981 |
| From: | Randazza J Maine Yankee |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19345F544 | List: |
| References | |
| FMY-81-14, NUDOCS 8102180318 | |
| Download: ML19345F542 (3) | |
Text
I
's Proposed Change #30 2.C.2.1
~
MAME * %kHAllHEE Atom /C PolVER COMPARS *
,ucugr,j,in"gja pM (2c7) 623-3521 e
Feoruary 13, 1981 FMY-81-14 0
United States Nuclear Regulatory Ccmmission wasnington, D. C.
20555 Attention: Office of Nuclear Reactor Regulation
References:
(a) License No. DFR-36 (Docket No. 50-309)
(b) USNRC I & E Inspection Report No. 50-309/79-11
Dear Sir:
Suoject: Mocification to Maine Yankee Tecnnical Specifications Pursuant to Secticn 50.59 of the Commission's Rules and Regulations, Maine Yankee Atomic Power Company nereby proposes the following modifications to Appencix A of the Operating License.
FRCPOSED CHANGE Reference is made to the Technical Specifications containec in Appendix A to Cperating License No. OP-36 issued to the Maine Yankee Atomic Power Company and to Reference (b).
We propose to modify tne current Tecnnical Specification as follows:
A.
Replace page 3.19-1 of Specification 3.19 with the attacneo revised page 3.19-1.
REASON FCR CHANGE Unresolved Item No. 30-9/79-11-01 in Reference (b) reported the following:
"In a review of PORC meeting minutes 79-12 of May 1,1979, the inspector notec & PORC discussion concerning Tecnnical Specification 3.19.b.1 wnich recuires the Safety Injection Tank isolation valve power operators De
'racxeo out'.
Tne licensee states, in this discussion, that these creakers in a 480 volt MCC are not designed to ce racked out.
To meet tne intent of tne Tecnnical Specification, the valve operator pcwer leads nave been cisconnected and tapeo and the breaxers locked open.
The plant is investigating a modification to install cfscannect links and then to propose a change to Technical Specifications to eliminate the conflict."
8102180*>$
9
U. S. Nuclear Regulatory Commisr ion February 13, 1981 Attention: Office of Nuclear Rnactor Regulation Page Two Consequently, Maine Yankee has investigated this problem and has decided to install a disconnect switch in series with the valves' power supply breakers. For administrative control, this disconnect switch will be lockable in the open position and, along with locking the power supply breakers in the open position, will be used in lieu of the existing requirements.
Additionally, Technical Specification 3.19.b.2.b requires that for the reactor coolant system loop isolation valves:
"The breaker thermal overload links shall be physically removed from the breakers." These links were not intended to be used for this purpose. Maine Yankee-intends to install disconnect switches in series with each valve power supply-breaker. For acministrative control the disconnect switches will be lockable in the open position and will be used in lieu of removing the breaker thermal overload -
links.
BASIS FOR CHANGE The proposed change to the Maine Yankee Technical Specifications properly identifies the method which will be used to disable the Safety Injection Tank and reactor coolant system loop isolation valve power operators in the open position when the reactor is critical.
The locking open of these switches in conjunction with locking the breakers open meets the intent of the existing
' Technical Specification with enuipment better suited for the purpose.
The proposed schedule for the installation of these switches is during the 1981 refueling outage.
SAFETY CONSIDERATION The locking open of these switches and breakers will achieve the original intent of Technical Specification 3.19 in lieu of racking out the breakers and removing thermal overload links..Since either scheme will effectively achieve this objective, it is concluded that this proposed Technical Specification change does not present any significant hazards not described in the safety analysis report, and does not involve an unreviewed safety question as i
described in 10 CFR 50.59.
I This change has beEn reviewed by the Main' Yankee Nuclear Safety and Audit
(
Review Committee.
[
FEE DETERMINATION The proposed change requires an' approval that involves a single safety I
issue and is deemed not to involve a significant hazards' consideration. For these reasons, Maine Yankee Atomic Power Company proposed this change as a Class III Amendment.
A payment of $4,000 is enclosed.
I
U. S. Nuclear Regulatory Commission February 13, 1981 Attention: Office of itclear Reactor Regulation Page Three STEDULE OF CHANGE The change described above will be incorporat2d into the Maine Yankee Technical Specifications upon receipt of your approval.
Until the 1981 refueling outage, the operator power 1,. ads will remain disconnented and taped, the thermal overload links physically removed, and the breake:S.ocked open.
During the 1981 refueling outage, the disconnect switenes will be installed and these switches will be used as specified in the proposed lechnical Specification.
1,e trust you will find this information satisfactory; however, should you desire additional information, feel free to contact use.
Very truly yours, MAINE YANKEE ATOMIC PC'nER COMPANY J. B. Randazza Vice President, Operations STATE OF MAINE
)
)ss COUNTY OF KENNEBEC)
Then personally appeared before me, J. B. Randazza who, ~ceing duly sworn, did state that he is a Vice President of Mainc Yankee Atomic Power Company, that he is duly autnorized to execute and file the foregoing request in the name and on the behalf of Maine Yankee Atomic Power Company, and that the statements therein are true to the best of his knowledge and belief.
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