ML18348A229

From kanterella
Jump to navigation Jump to search
LER 1977-031-03 Primary Coolant System Leakage
ML18348A229
Person / Time
Site: Palisades Entergy icon.png
Issue date: 06/24/1977
From: Hoffman D
Consumers Power Co
To: James Keppler
NRC/IE, NRC/RGN-III
References
LER 1977-031-03
Download: ML18348A229 (2)


Text

General Offices: ZJ2 West Michigan Avenue, Jackson, Michigan 49201

  • Area Code 517 788-0550 June 24, 1977 f~gufatory Docket F.ile Mr James G Keppler Office of Inspection and Enforcement

.Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 6dl37

  • DOCKEr 50-255 - LICENSE DPR-20 PALISADES PLANT - PCS LEAY..A.GE -

ER-77-031 Attached is a reportable occurrence which involves primary coolant system leakage at the Palisades Pl~nt, David P Hoffman (Signed)

David P Hoffman Assistant Nuclear Licensing Administrator e

\

.e. LICENSEE EVENT REPOR,e Palisades CONTROL BLOCK: ._I__,__..___.__.__..._,J [PLF..ASE PRINT AU. Rf.:12UIRED 11\lFORMATION) 1 6 LICENSE EVENT LICENSE NUMBER TYPE TYPE I olol-lolol'ololol-lolol l411l1l1l1I Io I 3 I 15 25 26 30 31 32 REPORT REPORT TYPE. SOURCE DOCK!;T NUMBER EVENT DATE REPORT DATE 7

@E]coN'T 8

r *I I 57

'f 58 w w 59 60 I ol 51 ol-1ol215151 I69o I 5 I 2 I 6 I 1 I 174I I ol 6l 21411l1J 61 68 75 80 EVENT DESCRIPTION lol2I ._l_F_o_1_1_o_w~i_n~g_p_l_a_n_t_s_t_a_r_t_-_up~,-Pr

__im_ar_y__C_o_o_l_a_n_t__S~y-s_t_e_m__(_P_C_S_)~9-h_e_c_k_s__r_e_v_e_a_l_e_d__w:_n_i_d_e_n_t_i_f_i_e_d____,

7 8 9 80 Iol3ll.__1_e_a_k_a_g_e_o_f__2__t_o_3_g_p_m_.__T_h_e_p_r_o_b_l_em__w_a_s_l_o_c_a_*t_e_d__a_n_d_c_o_r_r_e_c_t_e_d_w_i_t_h_t_h_e_1_2_-_h_o_ur__1_i_m_i_t_ _,I 7 8 9 80 joj4j ._I_a_s_r_e~q~u_i_r_e_d_b~y_T_e_c_h_n_i_c_al___Sp=-e_c_if_i_*_ca_t_i_*o_n_3;__.l__;.5~*-a_._____________________________.I 7 8 9 80 lolsl '------~--------------------------------~--~ER--_.......--0~3=1.._______~_____J 7 8 9 80 fQ.f?J 7 8 9 PRIME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION 7

@El I cl JI 8 9 10 W

11 lv!AILIVIElxJ 12 17 w 43 IFIOl3l5I 44 47 L!!J 48 CAUSE DESCRIPTION

@:@] L Relief Valve RV-2255 between the chemical and volume control tank and the charging J 7 8 9 80 7

~

8 g L pumps was partially unscrewed from its collet.

The RV 'was tightened and the leake.ge l 80

-~ I returned below the 1.0 gpm limit. I

. B 9 80 FACILITY METHOD OF OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION w

Sl .*TUS  % POWER l2J2] l£.J I oI 6 Io NA I Normal Leak Rate Procedure 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVrTY CONTENT 7

rn 8 RELEASED

~

g OF RELEASE

~I 10 11 AMOUNT OF ACTIVITY NA I 44 45 NA LOCATION OF RELEASE 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION IIEl L0 I 0I 0I 7 8 9 11

~

12 13 NA 80 PERS.ONNEL INJURIES NUMBER DESCRIPTION 7

EEJ8 910101~11 12._______N_A----------------~~--------~~~----~----'80 PROBABLE CONSEQUENCES

.[ill] None 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION

[iliJ ~ NA 7 8 g 10 80 PUBLICITY

[TI?J NA 7 8 g 80

- ADDITIONAL FACTORS

-~ NA 7 8 g, 80 7

Gm8 g 80