ML20244A945

Forwards Change Application 58 to Amend License NPF-1,Tech Spec Section 4.1.3.3,allowing 25% Extension of Surveillance Interval for Rod Drop Time

ML20244A945
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	04/01/1980
From:	Goodwin C PORTLAND GENERAL ELECTRIC CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
Shared Package
ML19309B184	List: ML20235Z795 ML20244A945
References
TAC-13053, NUDOCS 8004030240
Download: ML20244A945 (1)

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-April 1,- 1980L

, Trojan Nuclear-Plant 4 Docket 50-344

. License NPF-1

' License Change Application 58: 1 ly j

L l Director of Nuclear Reactor Regulation.

l ATTN: Mr. A. :' Schwencer, Chief - ,

l Operating Reactors Branch #1. 1 l

Division of Operating' Reactors j U. S. Nuclear' Regulatory:. Commission. '

Lj Washington. D. C. -20555 N j.

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Dear. Sir:

-Attached are three signed' originals and 40 conformed copies of-License Change Application 58 requesting amendment 'of 9perating License NPF-l'. I This License Change Application hast been evaluated to be a Class III' amendment. request and a check for $4',000 ic attached in;accordance with. ,

.j 10 CFR 170.

PGE has transmitted a copy of this request -to the Oregon Department  !

of Energy for~their consultation. j Also attached is one signed copy of-a Certificate of. Service for' License '.

Change Application 58 to the chief executive of the county in which the f acility is located and the Director of the State of Oregon, . Department

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of Energy..

Sincerely, 1

, //

C. Goodwin, Jr.

Assistant Vice President Thermal Plant Operation:and Maintenance-l CC/KM/4sa4A24 Attachment

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c: Director State of Oregon j< . g Department of. Energy '

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~ PORTLAND GENERAL ELECTRIC COMPANY

.CUGENE WATER & ELECTRIC BOARD '

'AND PACIFIC POWER & LIGHT COMPANY ,j TROJAN ~ NUCLEAR PLANT Operating License NPF-1 ' i Dockee 50-344- .1=q License Change Application Sr? ,

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.l-This License Change Application is submitted in'aupport.of. Licensee's.

request to extend the 18 month surveillance interval' required by-

!. Technical Specificat. ion 4.1.3.3 on 'al.c,ne time occurrence ~ to permit

. Plant operation for an additional 2 days. . .

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PORTLAND GENERAL ELECTRIC' COMPANY  !

By _ . dLo- M*

C. Goodwin, Jr. # - .

i Assistant Vice. President , ,

Thenaal . Plant Operationiand Maintenar.ce Jj l

Subscribed and sworn to before 'me this let day of April 1980...

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LLM k Notary Public..off,0regon

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• LCA 58

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REASON FOR CHANGE _

This change to the Technical Specif) cations is proposed to provide an operational flexibility and to utilice the scheduled refueling outage ' for the periodic surveillance requirement of the full-length (shutdren and control) rod drop. times. This Technical Specification Change vill be 1 applicable only to this surveillance interval. and will not affect the l future surveillance' requirements. 7 DESCRIPTION OF CHANGE 1

Section 4.1.3.3 of the Technical Specifications (Page 3/4 1-21) requires  ;

the boa drop time of full-length rods to be demonstrated through measurement ]

prior to reactor criticality at least once' per 18 months. _ Section 4.0.2, l Applicability of Surveillance Requirements (Page 3/4 0-1), allows the {

surveillance interval to be extended beyond the specified time as long as the extension does not exceed 25 percent of the specif'ed surveillance interval.

l l It is requested that this surveillance interval be changed on a single occasion at this time to allow an extension of 2 additional days to complete the scheduled Plant surveillance tast. The increase would be 18 months plus 4.5 months (25 percent) and 2 days. or until midnight April 11,1980.

SAFETY EVALUATION l

1 The time extension proposed in this change for rod drop time surveillance  !

is less than 0.3 percent of the maximus'ellowable time intertal in the Technical Specifications. l The individual full-length rod drop times from j the fully withdrewn position hei.1 been within the Technical Specification .

limit at Trojac. The probability of this change affecting the rod drop 1 time is extremely remote. j l

Based upon the above considerecions, another 2 days, e.g., shutting down l on April 11 vs. fpril 9, is essentially insignificant and would be I inconsequential from a safety viewpoint. Therefore, it can be concluded i that there would be no change in the probcbtlity or consequences of _{

accidents previously considered and no new accidents would be created. j The margin of safety would not be decreased. This change does not '

involve an unreviewed safety question.

EFFECT ON FSAR This change does not require any changes in the existing FSAR. j i

i ENVIRONMENTAL EVALUATION l

l The proposed Technical Specification change has no effect on the environ- l ment, the Final Environmental Report or the F1nal Environmental Statement  !

and does not involve an unreviewed environmental question. I l

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AMENDMENT CLASS ,

- , 1 Lt : The. proposed' change involves a single safety consideration and qualifies f u as 'a Class : III amendment, subject to -a fee of $4000 :as . outlined in :.

10 CFR 170.!

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