ML17192A579

Forwards LER 80-006/03L-0

ML17192A579
Person / Time
Site:	Dresden
Issue date:	03/13/1980
From:	Stephenson B COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17192A580	List: ML17192A579 ML19305B358
References
80-213, NUDOCS 8003190549
Download: ML17192A579 (2)

Text

Commonwea1t9C1ison Dresden* Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 March 13, 1980 BBS LTR /180--213 James G. Keppler, Regional Dir.ector Directorate of Regulatory Operations .. Region III U.S. Huclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report /180-06/031-0, Docket 11050-249, is being submitted to your office in accordance with Dresden Nuclear Power Station Technical Specification 6.6.B.2. (d), ,abno.rmal de-gradation of systems othei:: than those specified in item B.1.e .

. above designed .to contain radioactive material resulting from the fission proce'ss.

• 1. ~~

B. ~t~~~,~

Station Superintendent Dresden Nuclear Power Station BBS:lcg Eric lo sure cc: Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC

~~-

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• LICENSEE EVENT REPORT

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.  !-1_....___,__....1...._....__....---!.6 1 l0 (PLEASE PRINT OR TYPE ALL,OUIRED INFORMATION) rrD I IL ID IR Is I 3 8 9 I

LICENSEE CODE .

101 0 I 0 14 15 I -I 0 I0I 0I 0 I 0 LICENSE NUMBER I-I0I 0 101 4 I 1 I 1 I 1 I 1 101 25 26 LICENSE TYPE 30 I

57 CAT 58 10

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~©I 60 61 o Is Io Io Io 12 I4 19 DOCKET NUMBER 68 101 69 o I 2 I 1 I s I s I o74I© I75o I 3 I 1 I 3 I s EVENT DATE . REPORT DATE Io 80 ICV

=-EVENT DESCRIPTION Af'o'.'D PROBABLE CONSEQUENCES@ .

2m I During Unit 3 refueling outage, a LLRT was performed on "A" feedwater inbOardcheck

~ I valve 3-220-58A. The measured leakage was 1,104.51 SCFH, which exceeded the limit

~ I for a single isolation valve (29.38 SCFH, Tech. Spec. 4.7.A). This was of minimal

~ LI_s_a_f_e_t_y_s_i_gn_i_*f_i_c_a_n_c_e_s_i_n_c_e_l_e_a_k_a_g_e_m_e_a_s_u_r_e_d_t_h_r_o_u_g_h_t_h_e_o_u_t_b_o_a_r_d_f_e_e'--d_w_a_t_e_r_c_h_e_c_k_v_a_*_lv___e-.J

IBJ LI _w_a_s_b_e_l_o_w_T_e_c_h_._s_p_e_c_._1_i_m_i_t_s_*_a_n_d__t_h_e_f_e_e_d..,w_a_t_e_r_1_*i_*n_e_i_s_c_a_p_a_b_l_e_o_f_b_e_i_ng_i_s_o_l_a_t_e_d__,..b_Y_~

IT2J LI _a_m_o_t_o_r_o_p_e_r_a_t_e_d_v_a_l_v_e_u_p_s_t_r_e_a_m_o_f_t_h_e--.;.c_h_e_c_k_v"""a_l_v_e_s_._s_.i_*mi_*l_a_r_e_v_e"'""n_t_:__ s_o_-..,..2_3_9_1_7_8_-_o_3_._-..J

£ITJ8 9 80 SYSTEM CAUSE CAUSE './ COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE is IA I@ L!J@ ~@) /VIA/LIV/E/X/@ ~@ L~@

' 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION

~-.. LEA/RO

~ REPORT NUMBER LVENTYEAR I 8 21 I 022I I 23 I

24 REPORT NO.

I 0 I0 I 6 I 26 I /I 27 I0 28 CODE I3 I 29 w

TYPE 30 I I 31 NO.

LQJ 32 ACTION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

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33 34

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35 W

36 Io 101 o Io I 37 40 L.!U@

41 L!J@

42 LU I c 16 16 IS I@

43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

~I Excessive leakage through feedwater check valve 3-220-58A was due to worn seat/disc assembly pins, which prevent proper alignment of the disc to the seat. The seat/disc

~ assembly was replaced and the valve retested. Leakage was reduced to 0.520 SCFH,

Im *I well below Tech. Spec. limits.* The replacement assembly pins. and bushings are made*

~ I from a hardened alloy. No further corrective action deemed necessary. I*

8 9 80 FACILITY METHOD OF Im STATUS l..!!J@

% POWER I 0 I 0 lI....._

OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION 8 9 I 0 10 12 11

_;,.N""-'/A 44 W@l Local Leak Rate Test 45 46 80 ACTIVITY

>;-r;"'lRELEASED OF RELEASE CONTENT AMOUNT OF ACTIVITY e

~

LOCATION OF RELEASE @

~ W@ UJI N/A ' NLA I 8 9 10 11 44 45 80 PERSONNEL EXPOSURES ~

NUMBER (:;":;\TYPE DESCRIPTION rITJ.jO /0 )0 J\3'UJ@)L--.:.N~/A::__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _---'

8 9 11 12 13 80 PERSONNEL INJURIES * ~

• NUMBER DESCRIPTION 41 3:0 8 I0 9

I 0 I 0 11l@L-.. . 12

_ ___:N;;.:..,.:.;.A..,...,- - - - - - - - - - - - - - - - - - - - - - - . . . . ; . . . . , . . . - - - - - '

80 LOSS OF OR DAMAGE TO FACILITY t4:;\

~ TYPE DESCRIPTION ~

~ W@ N/A e 9 10 80 PUBLICITY ~ NRC USE ONLY ISSUE Dr,;:;\ DESCRIPTION~ .,

~~~~-~N~/~A...;....,..._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~ 1111111111111!

8 9 10, 68 69 80* c; T

• A *. Ciesla X-462 0