ML17173A894

Forwards LER 79-027/03L-0

ML17173A894
Person / Time
Site:	Dresden
Issue date:	05/30/1979
From:	Stephenson B COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17173A895	List: ML17173A894 ML19269D604
References
BBS-LTR-79-428, NUDOCS 7906050268
Download: ML17173A894 (5)

Text

Commonweillllla Edison Dresden Nuclea.Wwer Station R.R. #1 ,

Morris, Illinois 60450 Telephone 815/942-2920. --~- ____ ,_ __

May 30, 1979 BBS LTR #79-428 James G. Keppler,. Regional Director Directorate of Regulatory Op~rations - Region III U.S. Nuclear Regulatory COIDillission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report f/79-27/03L-0, Docket #050.,...237 is hereby submitted to your office in accordance with Dresden Nuclear Power Technical Specification 6.6.B.2.(b), conditions ieading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.

nson Station* Superi~tendent**.

Dresden Nuclear.Power Station BBS:lcg_

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cc: Director o,f Inspection &'**Enforcement Director of Man~gement Information & PrograIIl Control FileiNRC . , . *.

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j <IJ~I LICENSEE EVENT REPORT J " c.~.d,.TAO'. BLOC<<  ! *I ** I *J0 (PLEASE. PRINT OR TY. . . L REauoREo o~FORMATIONI

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~~~~~~ W© I oI s I o I o I o I 2 I 3 60 61 DOCKET NUMBER I z 101 o I s I o I 2 I z I 9 I© I oI s I 3 I oI z I 9 10 68 69 EVENT DATE 74 75 REPORT OATE 80 jt* [§]2]. I EVENT DESCRIPTION AND PROBABLE CONSEQUENCES @

During startup main turbine trip~ed on high water. level.

"B" yarway reference leg had I

.f drained because of a leak<<)rt **lo:cal pressure indicatio~ isolation val;e . . High Rx 1*;;. rorJ1 LI~~~~~~~~~~~~~~;__~_;_;.~~~~~~~~~~--:-~-=~~:---~

pressure switches PS-263-SSC and D were isolated to is~late. leak.*. Since T. S. Table .

lnTi:l , . . 3 .1.1 requires 2 . :instrument. channels p~r .. trip system,*. an orderly ~ shutdown was. be-.

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[fill . gun inunediately. Minimal safety significance. since both trip systems were still oper-1

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[I)):] I A packing leak wa,s found .on the isolation valve for-PS-263-60B. The l~ak .. was :i.solatedl

. which also isolated 263-ssc* and 55D (high reactor press.ure), and yarway hfgh side. for 263-59B, 58A; 58B~ 72B, and 72D. The packing was adjusted, tested, and the system . I _ ,~:;

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line up was r_eturned_ to normal:* *All instrUrnents returned to the pr_. op~r. range a$ ~he 1

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ATTACHMENT TO LICENSEE EVENr REPORT 79-027/031-0 COMMONWEALTH EDISON COMPANY (CWE)

DRESDEN UNIT (ILDRS2)

DOCKET # 050-237 During startup on Unit *2 .at 1918 on May 2, 1979, the main turbine tripped on high water level. It was discovered that a packing leak existed on the isolation valve for the local pressure indi~atiori, PS-263-60B. The "B" reference leg drained to an abnormally low level through*

the packing leak. This resulted in an: upscale reading on all the yarways on instrument rack 2206. The "B" reference leg _root valve was shut to isolate the leak which isolated the following components: . PS-263-SSC, SSD, LIS-263-58A, 58B, 72B, 72D, and LITS-263-59B. A control systems .

technician locally isolated PI-263-60B (local pressure indica.tion) and PS-263-SSD (reactor .high pressure scram) via their comm9n, .. SeQSing line

• root valve. The "B" reference leg root valve was then opened and the reference leg filled. Since. Tech. *Spec *. Table 3 .1. _l requires two in-**.,,;*

strument channels per trip system, an orderly. reactor shutdqwn was begun immediately. The packing was tightened-and subjected to a hydro of 1000 psi. No leaks were discovered. The isolation valves. for PS-263-SSD and PI-263-60B were opened and the common sensing line root valve was opened, returning the system to normal. This. event was* of minimal safety significance, since one -instrument channel per trip system was still capable of performing its intended function as. designed. This was the first.occurrence of this type on Unit. 2. There was no* ~ffect on public health or safety.

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,, e Commonwealth Edison DEVIATION REPORT DVR NO.

,ST.~L*

D l.!NIT YEAR NO.

2 - 79 - 48 '

PART 1( TITLE OF DEVIATION OCCURRED

. ] 9J8 "B II Yarway level instrumentation r.eading upscale .. 5-2-29 TIME

.DATE SYSTEM AFFECTED 263 PLANT CQNDITIONS .. TESTING Reactor Yessel. P~e$sure*~-

C. Rx pr. @) D OCJ **

• • Startu*p PWR(MWT) '585 psi . LOAD(MWE) 0 YES NO TnC: t-*,.-:11mi>nt-c::-- -* . *'**** ... '. :*: *: MODE DESCRIPTION OF EVENT At 1918 hrs cm 5-2-79 the main turbine tripped on high water level. It was discovered that a packing leak on the local pressure indicator 263-60B isolation valve had caused the. 'B' yarway reference leg to drain. This caused yarway level instruments 263-59B, 263-58B, 263-72B, {ov.er)1;(!

DESCRIPTION OF GAUSE Packing leak on isolation valve to Pl-2_63-60B OTHER APPLICABLE INFORMATION When leak was isolated, level indication came back on scale as the condensing chamber began .

filling the reference leg.

EQUIPMENT IB:::J YES DR NO. WR NO.

W. Pietryga 5-2-79 FAILURE ONO N/A 3218 RESPONSIBLE SUP~RVISOR DATE I

PART 2 OPERATING ENGINEERS COMMENTS Initiated insertion of Control Rods and completed insertion of all control rods within four hours. Redundant ECCS and Rx scram instrumentation would have functioned* a.'s designed.

TYPE OF DEVIATION EVENT OF POTENTIAL TECH SPEC 'NON-REPORTABLE ANNUAL

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• RELATED SAFETY-REPORTABLE OCCURRENCE PUBLIC INTEREST VIOLATION* OCCURRENCE REPORT I NG*.. WR ISSUED D 14 DAY D 10CFR21 YES [X] YES (il D ~ D I

~ 30 DAY NOTIFICATION - NO D .NOD 6.6.B.2.b -'

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,. . REPORTABLE CCCURHENCE ACTION ITEM NQ. PROMPT ON-SITE NOTIFICATION . .. ..

NUMBER .  : - .

B. B. Stephenson 5/11/79 --

~ . 7-9-27-..03L-0 N/A TITLE DATE* - TIME. , '

N/A

-TITLE DATE TIME 24-HOUR NRC NOTIFICATION (Courtesy) PROMPT OFF-SITE NOTIFICATION

~TPH J. Barker. *5/3(79 - F. Palmer 5/11/79 12:20 REGION I I I DATE TIME Tl TLE ... l l ~~cr J. R. Gilliom

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• oTGM'. 5f1Yh9 REGION I I I & DOL CATE TIM_E TITLE .DATE TIME.

RESPONSIBLE COMPANY OFFICER INFORMED OF 10CFR21 ND ONS AND THEIR REPORT TO C TIME

- REVIEW AND ACCEPTANCE BY iTATLON REVIE~* -.y

.:.- -:-----=:--;----_ . AS REQUIRED DATE

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DESCRIPTION OF EVENT and *263-58A to fail high. The leak was isolated which also isolated pressure switch 263-SSD (Rx High Pressure Scram~ ~eactor shutdown commenced at 2103 as required by Technical Specifications.

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