ML17252B545

LER 79-017-01X2 for Dresden, Units 2 and 3 Re Inadequacies Observed in Implementation of Administrative Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection System or Engineered Safety

ML17252B545
Person / Time
Site:	Dresden
Issue date:	10/23/1980
From:	Scott D Commonwealth Edison Co
To:	James Keppler NRC/RGN-III
References
DJS LTR 80-200 LER 79-017-01X2
Download: ML17252B545 (3)

Text

Commeealth Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 RE.CE!VEC CiSTR!BUTION Telephone 815/942-2920 SERVICES UH!T t9.80 NOV 12 PM 12 28 Of,.fq]J-,e.r

. ) ,_, I\. ,l1 23, 1980 Dis 1:*::. L~ 'Z~i2WF;ViCES JJS. LTR {/80-200:

I I

.james G. Keppler, Regional.Director Directorate of Regulatory Operations - Region III q.I S. Nuclear Regulatory Connnission.

7,99 Roosevelt Road Glen Ellyn, IL 60137 II I

~evised Reportable Occurr~nce Report. #79-017-01X2, Docket #050-237 is 9eing submitted to your off ice in accordance with Dresden Nuclear Power Station '.l;echnicalSpecification 6.6.B.2.(c), observed in-qdequacies in the implementation of administrative procedural con-trols which threaten to cause reduction C?f degree of redundancy provided in reactor protection systems or engineered safety feature

~ystems. This revision corrects errors in Licensee Event Report items 17, 23 and 38.

I f) 111(£~

D~~ ~cott Station Superintendent

Dresden Nuclear Power Station DJS/lg I

I Enclosure i

cc: Director of Inspection & Enforcement i Director of Management Information & Program Control U. S. NRC, Document Mgt. Branch

' File/NRC I

flooJ.

s

. I /1

ATTACHMENT TO LICENSEE EVENT REPORT #79-017-01X2 I COMMONWEALTH EDISON COMPANY (CWE)

I DRESDEN UNIT :'.2 I DOCKET ff 050-237 I

i Measured :\-eakage of volume bounded by*containment isolation valves Ab-2-1601-23, 24, 60, 6+, 62 & 63 was 1660 SCFH. This exceeds the T.S. limits for single containment isolation valve allowable.leakage, total for testable penetrations and isolations valvesand maximum allowable containment leak rate. The leakage was into the secondary containment and the Standby Gas System which resulted in no danger! to public health and safety. Similar events were reported by 50-237/

76-10, SOi-249/76-16 and 50-249/80-07. ' -

I Leakage was initially identified to be from the shaft.seals on A0-2-1601-60.

Subsequen 1t testing indicated leakage 'on the i601-23 and 1601-24 valve shaft seals and~ seat leakage on valve 1601-24. The 1601-24 valve was replaced and shaft sea1ls on valves 1601-23 and 1601;_60 were repaired. No further* action deemed necessary.

U.S. NUCLEAR REGULATORY COMMISSION

• .::;,.

• LICENSEE EVENT REPORT e

~C9NT~OL BLOC~:

. 1 I T I I 6 10 (PLEASE PRINT OR 'TYPE ALL REQUIRED INFORMATION)

~

• 7 8 1*1 9

IL ID IR !Is LICENSEE C9DE 1 2 101° 1° 1- 1°

• 14 15 I 0 1*0 ,,o LICENSE NUMBER I0 1- r0 I 0 25 101 4 1 1 1 1 1 *1 11 101 26 LICENSE TYPE  :.10 57 CAT 58 I I CON'T j' .

~  :~~~~;~©lo 15 10.10 10 12 13 11 101o1312 1111 19 l©I o1 91 o1 31 81 o I@

7 ~ 8 60 I 6~ DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPT~ON AN.D PROBABLE CONSEQUENCES@

(([I] I Measured l~akage of volume bounded by containment isolation valves A0-2-1601-23, 24, 60

" i l

[QI[] I 61, 62 & 6l was 1660 SCFH. This exceeds the T.S. limits for single containment isola-CQJ:IJ I tion valve!allowable leakage, total for testable penetrations and isolation valves and

[Q))J I maximum al+owable containment leak rate. The leakage was into the secondary contain-

((ill I ment and the Standby Gas System which result~d in no. danger to public health and safety.I

[}]I] I Similar events were r~ported by 50-237 /76-10, 50-249/76-16 and 50-249/80-07.

((ill 7 . 8 9 I 80 SYSTEM CAUSE CAUSE COMP. VALVE

coDE CODE SUBCODE COMPONENT CODE SUSCODE SUBCODE

[Iill' I SI DI@ ~@ ~@ Vj AJ Lj Vj El Xj@ ~@) ~@

7 8 9 . 10 11 12 13 18 19 /* 20 SEQUENTIAL OCCUR REN CE REPORT REVISION

~ LEA/RO c"iENT YEAR REPORT NO. CODE TYPE

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~ REPORT 17 j 9 I I . I I 0 I1 I 7I I/ I I0 11 I ~ L...J NUMBER 2,1 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE 1

EFFECT SHUTDOWN ~ ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ' ON PLANT METHOD . HOURS ~ SUBMITTED FORM :;us. SUP.PLIER MANUFACTURER

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33 34 .

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CAUSE DESCRIPJION AND CORRECTIVE ACTIONS 43 44 47 o::::m I Leakage w~s init~ally id'entified to be from the shaft seals on A0-2-1601-60. Subse-o:IIJ quent testing indicated leakage on the 1601~23 and 1601-24 valve shaft seals and seat o:::::I2J leakage o~ valve 1601-24. The 1601-24 valve was replaced and shaft seals on valves DJ}] I 1601-23 and 1601-60 were repaired. No further action deemed necessary.

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STATUS  % POWER OlHER STATUS ~

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RELEASED OF RELEASE AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE @

r2:fil l.!J@) ~@'-I__N..;.../A _ _ _ _ _----' N/A 7 8 9 10 I 11 45 80 PERSONNEL EXPOSURES Q..

NUMBER A TYPE DESCRIPTION~

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@. ao D:TIJ NUMBER ' DESCRIPTION 41 jO jO IO l@).__:---__N_A_______________________________________________J

' 8 9 11 12 so LOSS OF OR DAMAGE TO FACILITY 143\

TYPE DESCRIPTION v:.::J (iE l:J@  : N/A 8 9 ~10::---*----------------------------------------~

1 PUBLICITY (.;;'\ SO ISSUEOQ DESCRl~TION NRC USE ONLY* .,

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