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{{Adams
#REDIRECT [[05000244/LER-2075-011]]
| number = ML18142B871
| issue date = 06/30/1975
| title = LER 1975-011-00 for R. E. Ginna, Failure to Increase Reactor Coolant Sample Test for Gross Radioactivity Concentration to a Minimum of Once Per Day When Gross Radioactivity Concentration Exceeds 10% of T.S Limit
| author name = White L
| author affiliation = Rochester Gas & Electric Corp
| addressee name = O'Reilly J
| addressee affiliation = NRC/IE, NRC/RGN-I
| docket = 05000244
| license number = DPR-018
| contact person =
| document report number = LER 1975-011-00
| document type = Letter, Licensee Event Report (LER)
| page count = 5
}}
 
=Text=
{{#Wiki_filter:NRC TRIBUTION FOR PART 50 DOCKF'TERIAL (TEMPORARY FORM)CONTROL NO: 74>>FILE INCIDENI'EPORT FILE FROM.Rochester Gas S Elec.Co Rochester, N.Y.14649 L,D White Jr.PBATE OF DOC 6-30"75 DATE R EC'D 7-11-75 LTR TWX RPT.OTHER TO Mr.J.P.O'Reill CLASS UNC LASS PROP INFO.\ORIG 1 si ned INPUT CC OTHER NO CYS REC'D 1 SENT LOCAL PDR DOCKET NO: 50>>244 DESCRIPTION:Ltr trans the following:
ENCLOSURES:
Licensee Event.Report (AO-75-11) on 6-17-75 re failure to increa'se.reactor coolant sample test.for gross radioactivity concentration.ta a.minimum of once pe'r day when gross radioactivity concentration
~exceeds 10%of, the Tech, Spec'limits....
t ,(1 cy encl rec'd)PLANT NAME: R.E~Ginna Plant FOR ACTION/INFORM
.g iD'.'-75)I('l(ibtollil[E@Eg BUTLER (L)W/Copies CLARK (L)W/Copies PARR (L)W/Copies KNI EL (L)Ml/Copies SCHWENCER (L)W/Copies STOLZ (L)W/Copies VASSALLO (L)W/Copies PURPLE (L)Wopies ZIEMANN (L)W/Copies DICKER (E)W/Copies KNIGHTON (E)W/Copies YOUNGBLOOD (E)'/Copies'REGAN (E)W/Copies LEAR (L)Ml/Copies SPELS W/Copies Ml/Copies~INTERNAL DISTRIBUTION TECH REVIEW~R DR~SCHROEDE R OGC, ROOMi P-BOGA~ACCARY GOSSICK/STAFF KNIGHT~CASE PAWLICKI GIAMBUSSO SHAO BOYD"-1'~STE LLO MOOR E.(L)>"-~HOUSTON DEYOUNG (L)"""'~NOVAK SKOVHOLT (L)~ROSS GOLLER (L)(Ltr)~IPPOLITO P.COLLINS/TEDESCO DENISF J, COLLINS RLG OPR LAI NAS~FI I E K REGION (2)BENAROYA~.IfIPC/PE (S)VOLLMER STEELE DENTON~~G R IMES GAMMILL KASTNER BALLARD SPANGLER ENVI RO MULLER DICKER KNIG HTON YOUNGBLOOD REGAN PROJECT LDR HAR LESS LIC ASST R.DIGGS (L)H.GEARIN (L)E.GOULBOURNE (L)P.KREUTZER (E)J.LEE (L)M-RUSHIIROOK (L)S.REED (E).SERVICE (L').SHEPPARD (L)M.SLATER (E)H.SMITH (L)S.TEETS (L)G.WILLIAMS (E)V.WILSON (L)R.INGRAM (L)M DUNCAN A/T IND.BRAITiMAN SALTZMAN MELTZ.PLANS MCDONALD CHAP MiAN DUBF (Ltr)E.COUPE PLTE RSON I.IARTFI E LD (2)~KLECKER EISENHUT'WIGG INTON~F.WILLIAMS EXTERNAL DISTR IBUTION 1 LOCAL POR~Lyons,,N.Y.--
-Rochester, N,Y.~1-TIC (ABERNATHY)
(1)(2)(10)
-NATIONAL LABS~l-NSIC (BUCHANAN) 1-W.PENNINGTON, Rm E-201 GT 1-ASLB 1-CONSULTANTS 1-Newton Anderson NEWMARK/B LUPI E/AG BABI AN~a-ACRS SEI'T TO LIC,",SST Sheppard 7-12-75 SEND OWLY TEN DAY REPORTS 1-P D R-SAN/LA/N Y 1-BROOKHAVEN NAT LAB 1-G.ULR IKSON, ORNL 1-AGMED (RUTH GUSSMAN)Rm 8.127 GT 1-J.D.RUNKLES, Rm E-201 GT
~~~4~/" k~I I H~'g~t~~~1~~~~r~..8 regulatory Do'oker File'/ElS////////I/I/I///>/////////(///////mz ROCHESTER GAS AND.-ORPORATION o.ops'I/g~g@.Ef(fg~@i~42~%El.EPHONE AREA CODE 7IS 546.2700 LEON D, WHITE, JR VICE PRESIDENT June 30, 1975'3~+Kg lug~Q k r pe'r.James P.One'ctor U.S.Nuclear Regulatory Commission Office of Inspection'nd Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Ntk k k'I YOAE"IIAEC*~o 89 EAST AVENUE, ROCHESTER, N.Y.14649
 
==Subject:==
Abnormal Occurrence 75-11, Failure to increase reactor coolant sample test for gross radioactivity concentration to a minimum of once per day when gross radioactivity concentration exceeds 10%of the limit specified in Technical Specification 3.1.4.la.R.E.Ginna Nuclear Power Plant, Unit No.1 Docket No.50-244
 
==Dear Mr.O'Reilly:==
In accordance with Technical Specifications, Article 6.6.2a, the attached report of Abnormal Occurrence 75-11 is hereby submitted.
Two additional copies of this letter and the attachment are enclosed.Very truly yours, L.D.Whi, Jr.Attachment cc: Mr.Donald F.Knuth (40)
I~i~I i t CONTROL BLOCK: '~LIT 2"IcM~LICENSEE EVENT REPORT~~t'-8!eanlatorwt not;kit File 09LEASE ItRIMT ALL REQUIRED 1MFORMATIOM)
LICENSEE NAME Qg NYRE 7 89 CATEGORY[0D1]coNT~MI 7 8 57 58 UCENSE EVENT TYPE TYPE 0 4 1 1 1 1~01 25 26 30 31 32 LICENSE NUMBER 0 0 0 0 0-0 REPORT DATE 0'6 3 0 7 5 EVENT DATE 0 6 1 7 7 5 68 69 74 75 80 G 1 0 0 14 15 REPORT REPORT TYPE SOURCE DOCKET NUMBER T L 0 5 0 0 2 4 4 59 60 61 EVENT DESCRIPTION 4 Jog Durin normal ower escalation after shutdown RCS ross activit increased to 10.6%of 7 8 9 80 I the limit.Fre uenc of ross activit anal sis was not immediatel increased to dail 7 89 80 t00j4 until a steady activity level was established.,Daily degassed analysis showed steady 7 8 9 80 I state except during a subsequent outage.During the following escalation gross analysi 7 8 9 80 Qpg showed decrease until a later stage of escalation when daily gross analysis was started 8 9 PRME Abnormal Occurrence 50-244/75-11/0 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUER MANUFACTURER VKtlATION~Pi Pi~A 9 Pi Pi Pi 9 Pi Pi E 9 9 9 Y 8 9 10 11 12 17 43 44 47 48 7 7 CAUSE DESCRIPTION toas]Not increasing the gross activity analysis frequency was due to observation that stead 7 89-80 Jog state had been reached based on degassed activity analysis.Sampling requirements wer 80 7 89 FACIUTY STATUS tt POWER Qg E~os o 7 8 9 10 12 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE 8 H 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
~t3~OO O E 7 8 9 11 12 13 PERSONNEL INJUFIIES NUMBER DESCRIPTION
~4~oo o 7 8 9 11 12 OFFSITE CONSEQUENCES METHOD OF DISCOVERY DISCOVERY DESCRIPTION H Su t.review of sam le results 44 45 46 OTHER STATUS NA 80 LOCATION OF RELEASE AMOUNT OF ACTIVITY NA NA 44 45 80 NA 80 NA 80 NA 7 8 9 80 Qio]reviewed with'the technicians and added to the sampling schedule and analysis log shee s,.7 8 9 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION
~16 7 89 10 NA 80 80 7 89 NA 80 ADDITIONAL FACTORS Reactor coolant ross activity has averaged 15-20%of the limit for the past three years 7 89 80~19 due to tramp uranium and is proportional to power level.7 89 NAME: Bernard R.Quinn 80 PHDNE,7 1 6-546-2700, ext.29 1-22 1 GPO 88t 667
'a~~.~qr e~II'~}}

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