ML19345G126

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Ao:On 730907,as Found Trip Setting of One Reactor High Pressure Trip Sensors Measured Above Tech Specs Limit.Cause Not Stated.Pressure Sensor Recalibr
ML19345G126
Person / Time
Site: Humboldt Bay
Issue date: 09/19/1973
From: Searls F
PACIFIC GAS & ELECTRIC CO.
To:
US ATOMIC ENERGY COMMISSION (AEC)
References
7135, NUDOCS 8103020665
Download: ML19345G126 (2)


Text

{{#Wiki_filter:, file Gy. 9 I R'eMtory_ PACIFIC GAS AND ELECTR,IC C O M PANY hOW3 l 77 BEALE STREET. SAN F R A N CISCO, C ALIFO R NI A 94106.(415) 781-4211 U,"S.Y[.."' S.Id c ".I[ September 19, 1973 .~?!!;.YEO .'I.'ses"s..ev JOHN C. MOR RISS E Y t ff 's-7::.*.*."::. E. h.h '.c .me..nu.amea.m rp. 7/ft".'."O.".*.Ta' .,oa.-...ooe-p (4. (, \\

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, p- .e.a r 10 'k u, EJ. - 20n".0;*. ,y. g he S,.,z ['- y,{'3*.'{f,3? At' ic Energy Commission ( h,-{ r. r..,n. t.f r....- g ' gg,p Washingtod, D. C. 20545 Q 1_. ..m.... / nGM,.H5 Attention: Director '~~ hdiMS Directorate of Licensing 4 ')3 (jf Re: Docket No. 50-133 License No. DPR-7 Gentlemen: Humboldt Bay Power Plant Unit No. 3 was shut down on August 31, 1973 for the annual refueling and maintenance outage. The unit is scheduled to be returned to service on September 28, 1973. One of the many operational tests performed during each regularly scheduled reNeling outage in accordance with Table IX-1 of the Technical Specifications is a functional test of all safety system trip sensors and circuits. This test is performed in several parts during the first two or three weeks of each re-fueling outage under the supervision of the Instrument Foreman. Following the completion of the test, the Instrument Foreman re-views and signs the completed test results. The data is then reviewed by a plant engineer who is also a member of the Plant On-site Review Committee and finally by the entire Plant On-site Review Committee to assure that all tests have been satisfactorily completed prior to reactor startup. This test was begun on Septem-ber 4, 1973 and is still in progress. lOn September 7, 1973, the "as found" trip setting of one of the four reactor high pressure l trip sensors was measured to be 1215 psig. The Technical Specifica-tions limit is 1200 + 10 psig during periods when the reactor is in the " power operation" mode. (Refer to Table VI-1.) There is no requirement for reactor high pressure protection during refueling operation. (Refer to Table VI-2.) The three other reactor prec.ru e trip sensors had settings in the range of 1200 to 1205 psig o.e e,,16 have initiated a reactor trip at the proper point if a ret h s r;ressure condition had e octirred during the previous opert!ing y tiod. i P00R ORIGINAL ?L

t ( U. S. Atomic Energy Commission September 19, 1973 Attn.: Directer. Directorate of Licensing Page 2 Each of the sensors is a Type 73 movement in a Foxboro Rotax Model N/41 pressure controller. This is the first time since plant startup in 1963 that one of these devices nas been found above i limits. The pressure sensor has been set and recalibrated to 1200 psig. Section IX.H.2.a of the Technical Specifications revised March 2, 1973 requires an abnormal occurrence report to the Director - of the Regulatory Operations Office within 24 hours by telephone and telegraph followed by a written report within 10 days to the Director of Licensing in the event of a safety system setting less conservative than the limiting setting established in the Technical Specifications. Because the existing practice has been to review operational tests performed during refueling outages after the tests have been completed (but prior to startup), the out-of-limit condition was not immediately reported to plar.t management. To avoid future problems with this reporting requirement all personnel performing operational tests have been instructed to report immediately any safety system setting that is found to be out of specifications even if the test is still in progress and the unit is shut down. The condition was reported to i the Region V Office of Regulatory Operations by phone on September 17, 1973 and this report is submitted in compliance with Section IX.H.2.a. Very truly yours, 7.Sc.- CC: U. S. Atomic Energy Commission Directorate of Regulatory Operations Region V P. O. Box 1515 Berkeley, California 94701 I \\ l l +- ev + -yv+r---+-p+ yg-n r.y-y -yg-9-y-% ,-w w- -r-- y,, +rgi--q-rn-g-y ,-+g-; 9-et

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