ML18136A465

Updated LER 79-031/03X-1:on 791117,while Reviewing Liquid Waste Release Forms,Discovered That Liquid Waste Monitor Did Not Alarm High & Trip Release Valve During 791117 Isotope Activity Release.Caused by Personnel Error

ML18136A465
Person / Time
Site:	Surry
Issue date:	11/21/1979
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18136A464	List: ML18136A463 ML18136A465 ML18136A466 ML18136A467
References
LER-79-031-03X, LER-79-31-3X, NUDOCS 8002070291
Download: ML18136A465 (2)

Text

{{#Wiki_filter:NP._C_.fORM.36.6 (7-77) . U.S. NUCLEAR REGULATORY COMMISSION e LICENSEE EVENT REPORT -* co NTR O L BLOCK: LI --'----'--~--"'---'---'I 8 1 6 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) I VI A I s I p I s I 1 101 ° I O I -I O I O I O IO, IO I-IO IO 101 41 lj 11 11 1101 I I G) 7 S 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T ITEJ 7 8 ~©I O I 5 I O I O I O I 2 I 8 I O 101 11 11 11 71 11 9 J@ll 11 J 2 J 1 J 1 19 IG) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@ I 1fuile reviewing Liquid Waste Release forms, it was determined that on 11/17 /79, a release was made which contained isotope activity summations greater than l.SE-03 [ilTI uCi/cc (actual summation

1. 60E-03 uCi/cc). The Liquid Haste Radiation Monitor did _[]:II) J :ri()t __ alarm high and trip the release valve as re_qu_ired

_by Technical Specifications l 3.7.E. Since the releases did not exceed the limits allowed by Tech. Spec. 3.11.A.(2) I and 10CFR20 App. B, the health and safety of the public were not affected. This [Q]IJ event is reportable per Tech. Spec. 6.6.2.b.(4). 7 8 9 7 8 SYSTEM CODE [ MJ AJ@ 9 10 CAUSE CAUSE CODE SUBCODE COMPOc!ENT CODE LI@~@ I z I z I z I z I z I z 18 11 l::=J 12 13 SEQUENTIAL REPORT NO. I o I 3 J 11 18 OCCURRENCE CODE q 3j COMP. SUSCODE ~@) 19 REPORT TYPE LB VALVE SUBCODE ~@ 20 REVISION NO. L~ 80 Q LEf1/RO CVENTYEAR REPORT I 7 J 9 J NUMBER 21 22 ACTION FUTURE TAKEN ACTION EFFECT ON PLANT 23 24 26 27 28 SHUTDOWN Q ATTACHMENT METHOD HOURS \.:2. SUBMITTED 29 30 NPRD-4 FORM SUB. 31 PRIME COMP. SUPPL! ER 32 COMPONENT MANUFACTURER u@L:J@ Li@ ~ 1 °1 °1 °1 °1 u@ 33 34 35 36 3 7 40 4 1 LJ LJ@ I z 1 9 I 9 ! 91@ CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 42 43 44 I The Liquid Waste Radiation Monitor, on high activity ( 1. SE-03 (uCi/cc), provides QJJJ a trip** signal to the Liquid Waste Release valve. Since the monitor can be calibrated [III] to one isotope only, the administrative control disallows any releases with activity summations greater than l.SE-03 uCi/cc. Personnel have been instructed to use care [[ill in filling out release forms. 7 8 9 FACILITY '3Q\ STATUS % POW=R OTHER STATUS V METHOD OF 47 80 ITE] ~@ ..__l.._J _O ..... !___,Oj@j Unit 2 Defueled DISCOVERY. DISCOVERY DESCRIPTION LJ@._J _R_e_v_i_e_w_o_f_f_o_r_m_s_. ______ --'-------' 8 9 10 12 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY G:TIJ @) [2_j@-' __ N_A _____ ___ 7 8 9 10 11 7 45 46 80 44 NA LOCATION OF RELEASE @ 44 45 80 PERSONNEL EXPOSURES r::;;., NUMBER TYPE .DESCRIPTION~ LITI , a I o' OJu@.__ __ N_A _____________________ ___. 8 9 11 12 13 PERSONNEL INJURIES © NUMBER DESCRIPTION 41 80 01 0 IO I~ A s 9 11 ... ,2-----------------------------------------~so LOSS OF OR DAMAGE TO FACILITY '4:i\ TYPE DESCRIPTION ~Gv~I __ N_A ____________________________ ____. 7 8 9 10 so ISSU:~BLl~;;CRIPTION@ 0 , NRC USE ONL y " ~I Q_ ct\A',?, 01 11 I OJ l!:Jei,___N_A ____________ 9_sv_:v_-___ ,--__ I I I I II I I I I I I 8 a 10 GS 69 80*;;; o* e ATTACHMENT (PAGE 1 OF 1) SURRY POI.JER STATION, UNIT 1 DOCKET NO: 50-280 REPORT NO: 79-031/03X-l EVENT DATE: 11 /1 7 /79 (UPDATED REPORT) TITLE OF EVENT: Liquid Waste Release 1. DESCRIPTION OF EVENT: -* While reviewing Liquid Haste Release forms, it was determined that on 11/17/79, a release was made which contained isotope activity summations greater than 1. SE-03 uCi/cc. The Liquid Waste Radiation monitor did not alarm high and trip the release valve as required by Technical Specification

3. 7.E. A release rate of 48 gpm was experienced over a period of 60 minutes. 2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS: The Liquid Waste Radiation monitor, on high activity (1. SE-03 uCi/cc), provides a trip signal to the Liquid Waste Release valve. Since the monitor can be calibrated to one

• isotope only, administrative control disallows any releases which contain activity summations greater than 1. SE-03 uCi/cc. The precalculations before release were done twice by two different individuals and both calculations were in error. Since the release did not exceed the lirni ts allowed by Technical Specification 3.11.A. 2 and 10 CFR 20, App. B, the health and safety of the public were not affected.

3. CAUSE: A personnel error caused this event. 4. IMMEDIATE CORRECTIVE ACTION: A check of the waste releases was done for the month of November, to verify compliance with 10 CFR 20, App. B. 5. SUBSEQUENT CORRECTIVE ACTION: Personnel were instructed to use more care in filling out release forms. 6. ACTIONS TAKEN TO PREVENT RECURRENCE:

No further corrective action will be required.

7. GENERIC IMPLICATIONS:

None.}}