ML19224B817

From kanterella
Jump to navigation Jump to search
Submits Update to 790424 Response to IE Bulletin 79-06A, Revision 1 Re Tripping of Pressurizer Water Level Bistables & Resetting of Containment Isolation
ML19224B817
Person / Time
Site: Crane, Trojan  Constellation icon.png
Issue date: 05/04/1979
From: Goodwin C
PORTLAND GENERAL ELECTRIC CO.
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML19224B816 List:
References
NUDOCS 7906270005
Download: ML19224B817 (2)


Text

W1111.... u.ndulad, Brtchl, bur i us, n..ider, Withers, Frew1 ;,

.csson, Christensen, Caidos, Sullivan, Loy, Quinn, Kieblock, Perry, NOB, H. T, Trojan Operating Committee, Shift Supervisors, R. C. Farley (Bechtel) - A!!.N:

L. Damon,

R. Kelly (W), L. Weislogel (PP&L), D. Axtell (EWEB), R. Nyland (SPA), ::. Axelrac, Inspector, C. Tram:el_1 P. Higgins (Edison Electric Institute), NRC Resident (JRC. DOR), Reading File, TNP:COV REL F: NRC Region V ISE Chrono

,, J'

/,

_w,=,

Portland Genem! Electric Ccmpany ll~ D [d Crv,es Gxemn.Jc Asss: art Vce Prescent Iby 4, 19 79 Trojan Nuclear Plant Docket 50-344 License NPF-1 Mr. R. H. Engelken, Director U.S. Nuclear' Regulatory Co==ission Region V Suite 202, Walnut Creek Plaza 1990 N. California 31vd.

Walnut Creek, California 94596

Dear Sir:

The following information updates our response of April 24, 1979 to your IE Bullerin 79-06A, Revision 1:

Bulletin Item 3, Revision 1:

Upon reviewing all Plant codes, it was determined that tripping of the pressurizer water level" bistables in Mode 1 was not an unreviewed safety question.

It was also determined that ope _'ation in Modes 2 and 3 with the pressuricer water level bistables in the tripped position had

~

not been cdequately analyzed and reviewed.

On April 25, 1979, while in Mode 1 the pressuriter water level bistables were therefore placed in the tripped positicn.

When the Plant entered Modes 2 and 3 on April 27, 1979, the pressurizer water level bistables were returned to the nor=al position.

Bulletin Item 4:

To clarify our original response, Contain=ent isolation is auto =atically initiated by a safety injection signal.

Operator action is required to reset Contain:ent isolation after the safety injection signal is reset.

Bulletin Ite= 13. Eevision 1:

The Plant is currently in a taintenance and inspection outage; we will be identifying

} } k O b, <,

design changes and preposing Technical Specification changes based on our reviews by May 18, 1979.

O 7906270CO f s ___ m

^

PofJcnd General Elechic Ccmpany Mr. R. H. Engelken May 4, 1979 Page two The. procedure revisions identified in our April 24 letter that were to be conplete by May 1 have been acco=plished (Bulletin Ite=s 1, 2 3,8,9 and 12).

Sincerely,

/?

b C. Good in, Jr.

Assistant Vice President Ther=al Plant Operation and Maintenance CG/ CAT /4kk7E14 c:

Mr. Lynn Frank, Director State of Oregon Department of Energy Office of Manage =ent Infor=atica and Progra: Ccatrol o

o 254 00D

-