ML18018B151

LER 76-045-00 for Nine Mile Point Unit 1 Regarding Discovery of Sodium Valve for Liquid Effluents Exceeded the Limit of 1.5 Pmm and LER 77-021-00 Relating to the Stack Sample Pump Being Out of Service for 9 Hours 20 Minutes Due to ...

ML18018B151
Person / Time
Site:	Nine Mile Point
Issue date:	05/18/1977
From:	Schneider R Niagara Mohawk Power Corp
To:	O'Reilly J NRC Region 1
References
Download: ML18018B151 (8)

Text

U.S. NUCLEAR REGULATORY COI ION DOC~T NUMBER NPC FoRM 195 I2-78) N- zzo FILE NUMBER NRC DISTRIBUTION FQR, PART 50 DOCKET MATERIAL. INCIDENT REPORT TO. ~ P FROM: DATE OF DOCUMENT:

Nr. James P; O'Reilly Niagara Mohawk,Power Corp, 05-18-77 Syracuse N. Y. 13202 R. R. Schneider DgP $ $ CP'ED ETTE R ONOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED

+ORIGINAL RfVNC I FIB D Sl (o~EB LASS Q COPY t DESCRIPTION ENCLOSURE I

Licensee'Event Report (RO-50-220/76-4 on 12-XX-76. concerning sodium valve for 'liquid effluents was 1.59 ppm vs a limit of 1.5 ppm.

page

@)@~@gg8 Licensee'Event Report (RO-50-220/77-'2 on 05-07-.77 concerning stack sample pump was ou of service for 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> 20 minutes, du@etc blown fuse....

PLANT NAME..NINE MILE POINT UNIT g 1 2 .pages I ~

Jcm NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J COLLINS F ACTION/INFORMATION BRANCH CHIEF:

W 3 CYS FOR ACTION LIC, ASST,:

H . S I ACRS CYS HQHHNe S NT INTERNAL D IST RIBUTION NRC PDR I&E(2 MIPC SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRIMES BUTLER TEDESCO/MACCARY EISENHUT BAER SHAD VOLLMER/BUNCH KREGER/J COLLINS EXTERNAL DISTRIBUTION CONT. L NUMBER LPDR: 5(Pt.

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771470172 NRC FORM 198 I2.78)

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NMP-0025 NIAGARA MOHAWK POWER CORPORATION NIAGARA '~

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MOHAWK 300 ERIE BOULEVARD. WEST SYRACUSE. N. Y. I3202 e '>

regulate'6 IHag 18, 1977

~. Jamu P. O'ReiLt'.y B~mtoa Unacted S~m Nuet'~ Regulatory ConnLeak on Regin 7 631 Pmk Avenue, King og P~a~, PA. 19406 o<. Q RE: 'Ooek& No. 50-220 Gem A,. O'ReiLI'.y:

ln ae.eoehmee Io&h N~ne NLe Pet Nucleus S~n Tee4u.eaL Speci,peatiom, uIe hereby submit Licensee Event Repo~,

Ueit <1 LER 76-45 and 77-21.

These aepo~ uIece eompL&ed Ln She $ oenat dm~gnated ~ She Licensee Event RepoM lm~~on Booklet 00E-SS-001, dated O~bn 1974, aevkeed 'Oeeembn 8, 1975.

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.R. Sc n Vi.ce Pau&ent-8!eetILie, Paodu~on

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m LICENSEE EVENT'EPORT CONTROL BLOCK: /PLEASE PR)IST ALLREQUIRED Ii9FOR?RATIO&)

LICENSEE EVENT

'04 LICENSE NAME LICENSE NUMBEA TYPE TYPE gg N Y N N P 1 25, 28 4 1 I I I

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7 89 14 15 30 31 32

~01 cow'r 8

CATEGORY 57 58 REPORT REPOAT 0

ODCXET NUMBER 2 2 0.

89 89 2

EVE'NT DATE x x 7 6 74 75 0

REPORT DATE 5 1 8 7 7 80 EVENT DESCRIPTIOiN toom During a review of'hemical discharge records for December 1976, it was found that the 7 8 9

~03 sodium valve for liquid effluents was 1.59 ppm vs a limit of 1.5 ppm. '(ETS 2.3-1 )

7 89 80 Jog Pum out rate exceeded allowable for concentration in the 'make-up demineralizerrwaste .

7 8 9 . 80 until

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.tank. Review of re ords n made Ha 1977.

7 8 9 80

~08 7 8 9 PAME 80 SYSTEI I CAUSE COMPDi 4ENT COMPONENT CDDc CODE COMPONENT CODE SUPPUEA MlUFACTU~m VDLATX)N

~MC A Z Z Z Z Z z x x x ~

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=7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION

~QB The sur veil lance procedure was revised to assure a more timely check on concentration o 7 89 80

~os discharges which have been made. A station modification to provide discharge 7 8 9 80

@10 throttl in ca abi 1 i t will revent recurrence.

7 8 9 METHOD OF 80 FAC(LITY STATUS S. POWER OTHER STATUS 01SCOVEAY OISCOVFAY OcSCRIPTION E ~09 7 NA Routine surveillance 9 10 "

12 13 80 FOAM OF ACT;VITY COATENT RELEASEO OF RELEASE AMOUidT OF ACTIVITY LOCATIONS% OF AcLEASE z . z NA NA 7 8 9 10 11 44 - 45 80 PERSONNEL EXPOSURES

~13 7 8 9 1( 'l2 13 80 PERSONNEI. INJURIES 7 8 9 11 12 ~

80 ggQ)Q coNsEQUENGEs PRDQAQLE NA 7 8 9 80 LOSS OR DAMAGE,TO FACILITY TYPc DESCRIPTION Q~g z 7 89 10 80 PUBLICITY NA 7 8 9 ADDITIONAL FACTORS 7

Jig, 8 9 NA

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LICENSEE EVENT REPORT CONTROL BLOCK: (PLEA8E PAINT ALL REQUIAED NIFQRIVIATIOM) 1 LICEI4SCE LICENSE EVENT I'IAME LICENSE NUMBER TYPE TYPE

[op~] N Y N M P 1 4 1 1 1 1 ~01 7 09 14 15 25 26 30 31 32 REPORT REPORT CATEGORY SOURCE DOCKET NUMBER EVENT DATE REPORT DATE

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TYPE T L 0 5 0 0 2 2 0 5 0 7 7 7 0 5 1 8 7 7 7 8 57 58 59 60 61 68 69 74 75 80 EVENT OESCRIPTION

~02 Stack sample pum was out of service for 9 hours 20 minutes due to blown fuse. Stack 7 8 9 80 toD3] ross radioactivit not monitored as re uired b ETS 2.4.4B. Technician re laced 7 89 80 toad] "'fuse and restored service when erformin weekly sample change. Reported 5/9/77.-

7 8 9 80 s]

,7 89 60 Jog LER 77-21 7 8 9 PRYAE 80 SYSTEM CAIISE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUER MANUFACTURER VIOIATION Iocyj ~Bc 24 U HP X X ~Z Z 9 9 9 N 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION

[oOe] Operator did not recognize low sample flow alarm to initiate promptrestorati'on of servi e.

7 8 9 80 Jog The hi h radiation sensors in the offgas line, main steam line, refueling platform, and 7 8 9 0 reactor building ventilation performed gaseous effluent isolations. These were operaN' Q~

7 89 METHOD OF 80 FACIUTY STATUS POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION 5 ~oo o Routine inspection 7 8 9 10 12 13 44 45 46 FORM OF AMOUNT OF ACTIVITY LOCATION OF RELEASE NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

~00 0 2 NA.

7,8',,<< f'j 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION

[Q4 ~0. 0. 0 NA 7 8 9 11 12 XIXggXIXX:ONSEQUENCES PROBABLE Q~gi NA 89 LOSS OR OAMAGF TO FACILITY 7 89 10 80 PUBLICITY NA 7 89 80 AOOITIONAL FACTORS Jig Release rate prior to incident of iodine and particulates T32>8 days was about 89 7

1 9 6 x 10 3'f limit and nobel gas release <50 pci/sec Unit Shutdown.

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