ML19095A807

Submit Abnormal Occurrence Report No. AO-S1-75-15

ML19095A807
Person / Time
Site:	Surry
Issue date:	08/18/1975
From:	Stallings C Virginia Electric & Power Co (VEPCO)
To:	Moseley N NRC/RGN-II
References
Serial No. 647 LER 1975-015
Download: ML19095A807 (5)

Text

VIRGINIA ELECTRIC .A.ND POWER COMP.A.NY RIOHMOND,VIROINIA 23261 August 18, 1975*

.file Cy.

Mr. Norman C. Moseley~ Director Serial No. 647 Office of Inspection and Enforcement POM.f/JTB:nkw*

United States Nuclear Regulatory Commission Region II - Suite 818 Docket No. 50-280 230 Peachtree Street, Northwest License No. DPR-32 Atlanta, Georgia 30303

Dear Mr. Moseley:

Pursuant to Surry Power Station Technical Specification_6~6.B.l, the Virginia Electric and Power Company.hereby submits forty (40). copies of Abnormal Occurrence Report No. AO-Sl-75~15.

The substance of this report has been reviewed by the Station Nuclear Safety and Operating Committee and will be placed on*. the agenda for the next meeting of the System Nuclear Safety and Operating Committee.

Very truly yours,

--!~ )f);) /r::** / :' ' ?lJ:

C( , ( (I ( ~ \:,/ft{({, I v I

C. M. Stallings

• Vice President-Power Supply and Production Operations Enclosures 40 copies of AO-Sl-75~15 cc: Mr. K. R. Goller Mr. Bryce P. Schofield, Director Bureau of Industrial Hygiene 8878 L

LICENSEE EVENT REPORT

~ AO-Sl-75-15 co NTRO L f:1LO CK : *_,___._~___._l___._I___.l.____JI

._l [PLE9'J PRINT ALL REGUIRED INFORMATION]

1 6 LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE

~ I VI A I s Ip 1* s I 1 I I o I o 1-1 o I o! o I o I o 1-1 o I o I 14 I 1 I 1 I 1 I 0 1 I31O I 132I 7 8 9 14 15 25 26 30 REPORT REPORT CATEGORY TYPE. SOURCE DOCKET NUMBER EVENT DATE REPORT DATE

~coNT Ip I ol L!J LJJ I o I s I o 1-1 oI 21 8 ! o I jol8!0l317ISI I I I 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESG:RIPTION

@:§ l During normal operation a *1eaking fitting on "B" Overhead Gas Compressor resulted in I 7 8 9 80 lo!sj I the unplanned release of radioactive material from the site. Appropriate operational I 7 89~---------------------------------------------"so

~  !;-I_p_r_o_c_e_d_u_r_e_s_w_e_r_e_f_o_l_l_o_w_e_d_t_o_i_s_o_l_a_t_e_t_h_e_r_e_l_e_a_s_e_.__T_h_e_l_e_a_k_1._*n_g_f_1._*t_t_1._*n_g_h_a_s_b_e_e_n_r_e_-_~I 7 8 9 80

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7 8 9 PRIME 80 SYSTEM CAUSE COMPONENT COMPONENT SUPPLIER MANUFACTURER w

CODE CODE COMPONENT CODE VIOLATION 7

@El I MJ Bl 8.9 10 11 Ip I I I p I 12 E) X IX I 17 w 43 I z I9 I9 I9 I 44 47 L!J 48 CAUSE DESCRIPTION

~ I A loose fitting on "B" Overhead Gas Compressor allowed airborne radioactive material j rn ~I 7

7 8 9 8 9

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7 IT19J8 9 80 FACILITY METHOD OF STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION EE]

7 8 w

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45 46 Ventilation Vent Monitor Alarm 80 FORM OF ACTIVITY CONTENT rn RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE LMJ lliJ I 28.5 Ci Total Auxiliary Bldg. Vent to Atmosphere 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION /

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[IeJ 7 8 9 1°1 °1°111 12 13 80 PERS"ONNEL INJURIES NUMBER DESCRIPTION EE]

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N/ A 1~2-----------------------------------------'so OFFSITE CONSEQUENCES

.[ilij N/ A 7 8 9 80 LOSS OR DAMAGE TO FACILITY OESCAIPTiON w

TYPE

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7 8 9 N/A 80 I

ADDITIONAL FACTORS

~ I See Attached 7 8 9 80 IT@

7 8 9 80 NAME: _ _ _ E_._M_._si_ve_e_n_e_y_,_,_Tr_._ _ _ _ _ _ _ _ _ _ _ PHONE:_ ( 804) 35 7-3184 GPO 6B1

• 667

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SUPP,MENTATRY INFORMATION ON THE RELEASE OF AIRBORNE RADIOACTIVE MATERIAL DUE TO OVERHEAD GAS COMPRESSOR LEAK ABNORMAL OCCURRENCE AO-Sl-75-15 At approximately 1750 on August 3, 1975, an alarm was received on the ventilation vent gaseous and particulate radiation monitors (RI-VG-103,104).

Approved operational procedures were carried out in an effort to terminate the release from the site and locate the source of radioactivity.

The source of radioactivity was located the following morning. A leaking fitting on the suction unloader to "B" overhead gas compressor was emitting airborne radioactive material t6 the gas stripper room. The exhaust from this room goes into the ventilation vent system and then off site. An inspection of the ventilation vent radiation monitor chart indicated that airborne parti-culate and gaseous activity were released from the site for fourteen hours as a result of the leak.

All radionuclides in the ventilation vent system during the leak were identified. However, the concentrations of only the particulate activities and iodine- 131 were actually measured. The concentrations of the gases present were determined using the radiation monitor charts and the calibration data in the manufacturers instruction book, For conservatism, it was assumed that all of the Xenon present was Xe- 133

• This yields a higher activity* concentration than that if a mixture of Xe- 1 33 and Xe-1 35 is assumed.

The activities present in the ventilation vent as a result of the leak were as follows:

Radionuclide Concentration (µCi) cc xel33 2 X 10- 5 xel35 Included as part of Xel33 I 131 4.9 X 10- 11

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Radionuclide Concentration cl:. c~)

1133 11.6 X 10-12 Cs 137 2.3 X 10-10 Co60 3.8 X 10-11 Rb88 1.9 X 10- 9 The release rates in Ci/sec for each of the above radionuclides were as follows:

Radionuclide Qi(Ci/sec) xel33 56.6 X 10- 5 J

xel35 Included as part of Xe 1 3 3 1131 138.8 X 10-11 1133 328.5 X 10-12 csl37 65.1 X 10-10 co60 107.6 X 10-11 Rb88 53.8 X 10-9 Technical Specification 3.11 requires that the controlled release rate of airborne particulate and gaseous activity be governed by the following relationship:

L___Qi_ < 2.0 x 10 5 m3 MPCi sec, Qi is the release rate of any radionuclide i and MPCi is the maximum permissible concentration of any radionuclide i from Appendix B, Table II of 10CFR20. MPCi must be reduced by a factor of 700 for any halogen or particulate activity with a half life of greater than eight days. _Q_!_ for each radionuclide

t-fPCi released as follows:

(

Radionuclide M__ (m3 )

MPCi sec e

Xel33 18.9 X 10 2 Xel35 Included as part of Xe 133 131 . 2 1 99.1 X 10 10 2 133 1 5.76 X Cs137 2 88 X 10 Co60 25 X 10 2 Rb88 1. 79

= 2.3678x 10 4 m3 sec This represents 11.8% of the value specified in Technical Specification 3.11.B.1.

Several employees were exposed to higher than normal levels of airborne particulate activity in the auxiliary building during this occurrence, The radionuclides present in_ the auxiliary building and the highest measure con-centrations were as follows:

Radionuclide Concentration (µCi) cc 1131 5.49 X 10-10 csl34 3.87 X 10-10 csl37 1. 28 X 10- 9 1.24 X 10- 8 No employee was exposed to concentrations of airborne particulate activity in excess of the levels specified in Appendix B, Table I to 10CFR20. No abnormal pocket dosimeter readings were recorded; therefore, whole body exposure to employees due to the presence of airborne gaseous activity is minimal.

It is concluded that this release was insignificant and did not affect the health or safety of the general public or station employees.