ML19350A167

AO 50-29/74-2:on 740616,during Routine Refueling Interval Surveillance Testing of Containment Trip Valve Isolation Sys,Setpoints Found Drifting in Excess of Tech Specs Limit. Caused by Switches Set Too Close to Tech Specs Limit

ML19350A167
Person / Time
Site:	Yankee Rowe
Issue date:	06/19/1974
From:	Autio H YANKEE ATOMIC ELECTRIC CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
AO-50-29-74-2, NUDOCS 8102120200
Download: ML19350A167 (2)

Text

.

)

ABNORMAL OCCURRENCE REPORT RESORT NUMBER:

SI' 29/74-2 REPORT DATE:

June 19, 1974 OCCURRENCE DATE: June 16, 197h FACILITY:

Yankee Atomic Electric Company, Rove, Massachusetts IDENTIFICATION OF OCCURRENCE: Containment Isolation Actuation System Setpoint Drift.

CONDITIONS PRIOR TO OCCOM S : Refueling Shutdown, Shutdown Cooling System Operating, Reactor Coolant Temperature at 100 F.

DESCRIPTION c OCCURRENCE During routine refueling interval surveillance testing of the Containment Trip Valve Isolation System, Procedure OP-h610, VC Trip Valve Test and Pressure Switch Calibration, one of the two identical pressure switches, PS-231, used to trip the system operated at 5.3 psig. Also, during the same test, the con-tainment air particulate monitor sample lines isolation system pressure seitch operated at 7 0 psig. This is a violation of Technical Specification Secticn

.D.2.e.8 which lists a maximum setpoint of 5.0 psig.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE PS-231 was set too close to the technical specification. limit and normal

~

-instrumentation drift caused exceeding the limit.

The vapor container air particulate sample lines isolation system pressure switch's out-of-tolerance setpoint was also due to setpoint drift. The magnitude of the out-of-tolerance value (2 psi) is apparently due to the pressura switch having too great a span for its intended use.

ANALYSIS OF OCCURRENCE PS-231 is one of two identical pressure switches (the other oelt,g PS-230) used-to trip the Containmer.t Isolation System. If the containment pressure reaches 55 psig this system autou tically closes 2T trip valves in the vapor container outgoing lines used for the operation of the plant.

r PS-230 operated at <5 psig during the above referenced test, and therefore if containment isolation vere required because of a LOCA the 27 trip valves would have tripped below the ' technical specification limit.

'The vapor container.' air. particulate monitor har its own system for isolating the two one-inch sampling lines. The two sample. lines. terminate in a sealed housing containing the air particulate paper drive mechanisms and detector.

r

.AfD2/2 0900

. - ~....

- -. -... - ~, * -

I The Reactor Containment Pressure Analysis, YAEC FHSR Section h12 shows that during a LOCA v'apor container pressure peaks out at 31.6 psig within 18 seconds. Thic pressure transient greatly exceeds the out-of-tolerance values of 5.3 ' and 7.0 psig.

It can therefore be concluded that vapor con-tainer isolation valves vould have all closed du:ing a LOCA and exposure I

' to personnel and radioactive material release would not have taken place because of the out-of-tolerance setpoints thus resulting in no additional risk to public health and safety.

CORRECTIVE ACTION j

The containment ~ isolation actuation' system pressure svi ch, PS-231, was t

readjusted to operate at h.h psig.

. The containment air particulate sample lines isolation pressure switch was also readjusted to <5.0 psig. In the near future it vill be replaced with a new pressure switch having a narrower span.

FAILURE DATA i

N/A -

1 h, Plant Efuperintendentbm

- f b

a i

e t

i l

I i

i I

I i

I i -

~ h aw..

. w.g. e.

6 a

w

. - - e t-

-c-e L

=_

t

&[.?, l.!$ SON.] f. { l:I$J..$ l...l?.Y Db'- (ha

}N?,

e--

Yv;.w? sf%

J.$

Rowe,Mm ock:.ns 01:57 r a - a. s June 17, 197h

+'

United States Ate.f e Pnergy Co :41[sion~~

Directorate of F.cciletory Operation Region I 631 Park Avenue King of Prunnie, Pennsylvania lph06

Reference:

Licence No. DPR-3 (Do:het No. 50-23)

Dear Sirc:

Purruent to the reporting recuire:. ento,of the Yankee-Eeve Tech-nical Specif.'mtion PecU<en E.2. A, Attn:-

a.m A, ve tre repr ing the follovir. violatica t., be defined a

.-,,:rnal Occurrence 72.-2.

On June 16,197h at ih30 touro th rir. n valor contr.ine-trip valve surr illence tent tvo pr o cure evitches opercted ct prescures above tht allovable act point.

1.

PS-23] one of the two vnwr contniner' nrei.er trip v'lve a

initiating prensure svitches, operated at 5.3 p:!g in;ter.d of the required 5.0 psig.

The vapor container nir prticulate nonitor' pressure crikch 2.

operated at 7 0 psic rather than the required 5 0 psig.

The cet points h!sve be:.n rendju:ted, r

Very truly yours, Mb M

Herbert A. Autio-Pinnt Superintendent HAA/nid

(.r L

j 4,

g, g m l; }

Gb S.

l

_-__.e..

file CYa R:gulatory YANKEE ATOMIC ELECTRIC COMPANY

.~

~

u yop h "

'Sn Rowe,Massochuscits 01367

& - t., h.x

[

E Y4'N KEE L

y N

March 8, 197h S

.s 6...

y _\\.

w p'e/ ~?

,k % ch f

'2, s

y U. S. Atomic Energy Co==ission q

G

i s

g g

Directorate of Licensing gm Washington, D. C. 205h5 Q

T s'

\\

x

Reference:

License No. DPR-3 (Docket 50-29)

In compliance with the reporting requirements of the Yankee-Rove Tech-nical Specifications Attachment A Section E, 2, a, and Section 3 D (l';

(a), ve are reporting an accidental release of gaseous radioactivity.

This incident was described as Abnormal Occurrence Th-1 in the prelim-inary report to Region I Directorate of Regulatory Operations.

The Yankee Rove vaste gas system consists of a lov pressure cover gas system, a high pressure storage system, compressors, pining, valves and instrumentation. Following a routine sampling for inplant purposes on February 27,197h, a leak was discovered at the bonnet joint of the dia-phragm type isolation valve WD-V-63h on the vaste gas surge drum sample line. The leakage was estimated to be approximately one cubic centimeter per second. The leakage was stopped by tightening the bonnet bolting which had re.ixed.

Valve WD-V-634 is not included in the weekly leak check list and had not been leak tested since December 27, 1973. At that time, no leakage was observed.

A conservative release calculation was made by assuming a lec/second leak between December 27, 1973 and February 27, 197h at the highest measured gas activity concentration during the period. The following results were obtained, using a dispersion factor of 1.2h x 10-5 seconds /m3:

Waste Gas Concentration Total Activity Surge Drum At The Site Released in Nuclide Concentration Boundary MPC 63 Days Xe-133 3.7x10-2uM h.6 x 10-13 "M 3 x 10-7 "M 200,000 uCi

-15 Xe-135 5.2 x lo b 1 x 10-7 2800 6.5 r. 10 Kr-85 1.75 x 10-3 "

2.2 x 10-lb 3 x 10-7 9600 1,75 x 1o-14 n 1 x 10-7 C-lh 1.h x 10-3 a

=

7700 a

-7 1.6 x 10-15 H-3 1.3 x lo h 2 x 10 700 1 x 10 h ara 7 2.0 x 1C b

/ 2.* x 10-15 108h t./

/h h 203n~

f W J J l '] ))'T n b

= -.

. _ ~.. ~..

-. ~

?'

2-This releas, is 0.002% of the preposed Technical Specification Limit.

Vai7e WD-V-63h will be added to the weekly Jeak check list.

A preliminary r.trvey of previous gas leak incidentr. revealed only one other inadvertant gas release through a bonnet jo ht.

This release o Strred in 1968 (A0 68-2).

It is felt that a weekly leak test of applicable gas system valves will preclude extended leakage periods. The valve diaphragm.eplacement pro-gram now in effect rhould insure continued reliability f diaphragm valve

' bonnet closures.

Very truly yours, m

l'f

/

U%

Herbert A. Autio Plant Superintendent ljP cc: James P. O'Reilly h

r f

e

AEC ST2I r*JTIC?:_ FO*' PA.T 50 PCCl*IT_

TERTAL (TE:!PORARY 1C3:1)

CONTROL !!O: 2030 FILE: A/g FRC:!:

DATE OF LOC DA'i2 REC'D LTR l'.D:0 RFT CTC.;R Yankee Atomic Electric Company Rowe, Massachasetts Herbert A. Autio 3-5-74 3-12-74 X

TO:

ORIG CC O!iER SElrl AEC P:P. XXX

~

Directorate of Licensing 3 signed 37 CLASS U:: CLASS PROP Ii;FO INPUT 1;0 CYS REC'D DOCi:ET 1:0:

XXX 40 50-29 DESCRIlTIO3:

E!: CLOSURES :

which a leak was discovered in the bonnet

-g gTdWLEDGED

~Ltr reporting abnormal occurrence #74-1 in joint of the diaphragm type isolation valve WD-V-634 on the waste ga,s surge drum sample p0 NOT hEMOVE PLANT UAME: YANKEE-ROWE T03, _ACTIC:: r i:70P".TI C:t 3-12-74 GMC LUTLER(L)

GCETENCE2(L)

IZICIA';;;(L).

REGAN(E)

W/ Copic3 W/ Copies U/I Copics ik U/ Copics CLAI.i'(L)

S'itLZ (L)

DIC10'R(E)

U/ Copies W/ Copfes U/ Copics W/ Copics COLLER(L)

VASSALLO(L) 1*:;IG:ITO::(E)

U/ Copics W/ Copice U/ Copics W/ Copies 131IEL(L)

/SCHO:EL(L)

YOU:GELCDD(E)

W/ Copies U/7 Copies W/ Copics U/ Copics II:TT '_"AL DIS'inTi:UTIC!

MG FILE __

TECU REVI'?

DZ:; ION A/T ID LIC ASST gggy g 7 AEC PDR lENDRIE GRUES OGC, ROQt P-505A SC):20EDER C/c2:ILL DICCS (L)

SALTZ"A:;

MUNTZING/ STAFF MACCARY 1;ASTNER GEARIli (L)

B. HURT CASE 131ICllT BALLARD COULECURI;E (L) p7g33 CIll!BUSSO PAULICKI SPANGLER LEE (L)

MCDONALD LOYD SHA0 MAICRET (L) j MOORE (L)(E R)

STELLO ENVIRO REED (L)

DEYOUNG(L)(I"R)

HOUSTON HULLER SERVICE (L)

INTO J Sl:0VIIOLT (L)

0VAK DICKER SHEPPARD (E)

C. I!ILES P. COLLINF OSS 1311GliTON SMITH (L)

B. KI!!G f M

'DENISE IPPOLITO YOUNGSLCOD

/TEETS (L)

REG OPR EDESCO REG.M; WADE (E) j_ FILE & REGION (3)

LONG PROJECT LDR WILLIAMS (E)

/HORRIS

/LAINAS WILSON (L)

/STEELE

/, EENAROYA IIARLESS

/ VOLLt ?.R A,

EXTEIIAL DIST".T T'. ~ lC:!

/V) /

1 - LOCAL PDR 1-B & H SWINEBROAD 1-P. R. DAVIS [

1 - DTIE(ABER:;?.TliY)

(1)(2X10)-NATIO::AL LA3'S 1-PDR-SAN /LA/::Y 1 - USIC(LUCP.!;;AN) 1-ASLDP(E/W 31d;,Rm 529) 1-GEMLD LELLCECHE 1 - ASLE(YORE /SAYRE/

' U. PE3NINGTO::, Rm E-201 CT EROOKMVE:; 1:AT. LA UOODARD/"li" ST.

1-CONSULTid:T' S 1-AGMED(Ruth Custc j16-CYSACRSv3rklas Neur:ARn/stt:E/AGEAEIAN R1-B-127. CT..

Sent to Lic Asst Teets 3-12-74

'l-GERALD ULRIKSO::.. 0:U;L 1-RD. 1:ULLER..F-30

i E62Ul5wy Docket gjgg rai+o~ w w on m

h {

F" 710-390-0739 cY, EE ATOMIC ELECTRIC COMPANY c

r

$5* -

20 Turnpoke Road Westborough, Massachusetts 01581 h

AN KEE

?

NOV 9 '1973+ ' '

November 2, 1973 RECUtATORY I2 I

'k.K,A

$s V

MAIL SECDON DOCKET CLDtX Q

pw" [

3

' \\

.J.,

5 4

ted States Atomic Energy Commission

- 6_

NOV 91973 i

r Washington, D. C.

2054s u mrd thr Attention: Donald J. Skovholt YY//

• 8 8" Assistant Director of Operating Reactors N

Directorate of Licensing

Dear Sir:

The Technical Specifications for the Maine Yankee, Yankee Rowe and Vermont Yankee plants contain a sub-definition of an Abnormal Occurrence as follows:

" Observed inadequacies in the implementat$on of administrative or procedural controls such that the inadequacy causes or threatens to cause the existance or development of an unsafe condition in connection with the operation of the plant."

Recent contact with the Directorate of Licensing and the Directorate of Regulatory Operations has highlighted the fact that there is a discrepancy between t h intent and the interpretation of this definition.

The Directorate of Regulatory Operations has apparently expanded the scope of applicability of this phrase, beyond that which was originally An e.-

ple of this "extention" is the interpretation that a intended.

surveillance test which had not been performed within the specified time interval, regardless of the result of the previous and subsequent tests, is an Abnormal Occurrence.

It has been our contention, in this instance, that a missed surveillance should be reported in an informational 30 day report but would not assume the stature of an A.O. unless the subsequent test results were out of tolerance.

Your attention is invited to this issue and a ruling as to the applicability of this definition to the instance cited is requested.

Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY ZA L. H. Heider

' >12S fg hg[%3C Assistant Vice President DWE/*4

AEC D?S') 'EUTION FOR PART 50 DOCKET MATE

• tL (TEMPORARY FORM)

CONTROL NO: 6504 FILE:

FROM:

DATE OF DOC DATE REC'D LTR MEMO PST OTIER Ycnkee Atomic Electric Company Rowe, Mass. 01367 8-21-73 8-27-73 X

H. A. Autio TO:

ORIG CC OTIER SENT AEC I-DR x

D. L.

3 signed SENT LOCAL PDR_,

CLASS UNCLASS PROP INFO INPUT NO CIS REC'D DOCKET NO:

XX 4D 50-29 p@CKIPTION:

ENCLOSURES:

Ltr reporting abnormal occurrence No. 73-7 on

~

8-15-73, in which protective system set point m., m.-. m _ d 1.,.. L __ ;

cxc:: ding tSe value specified in tech sy :

w-g^mpp-,m.m

^

PLANT NAME: Yankee FOR ACTICN/INFORMATION 8-27-73 CC BUTLER (L)

SC15?ENCER(L)

ZIDiANN(L)

REGAN(E)

W/ Copies W/ Copies W/ Copies W/ Copies CLARK (L)

STOLZ(L)

DICKER (E)

W/ Copies W/ Copies W/ Copies W/ Copies GOLLER(L)

VASSALLO(L)

KNIGHION(E)

W/ Copies W/ Copies W/ Copies W/ Copies KNIEL(L) 4CHDEL(L)

YOUNGBLOOD(E)

W/ Copies W/7 Copies W/ Copies W/ Copies INTERNAL DISTRIBUTION bREGFILE)

TECH REVIEW DESION A / T I!.3 LIC ASST V EC PDR wfENDRIE GRIMES BRAIIMAN A

~ vDGC, ROOM P-506A JCHROEDER CAMMILL DIGGS (L)

SALTD!AN i

a4iUNTZING/ STAFF MACCARY KASTNER GEARIN (L)

1. CASE

/ NIGHT BALLARD COULBOURNE (L)

PLA';S K

l l

GIAMBUSSO v'PAWLICKI SPANGLER LEE (L)

MCDONALD l

BOYD A HAO MAIGRET (L)

DUBE MOORE (L)(BWR) dTELLO ENVIRO SERVICE (L)

DEYOUNG(L)(PWR)

A0USION MULLER SIEPPARD (E)

INFO

/SKOVHOLT (L) 4 0VAK DICKER SMITH (L)

C. MILES P. COLLINS

/ROSS KNIGHTON

./TEETS (L)

A. King (RO)

/IPPOLITO YOUNGBLOOD WADE (E)

JtEC OPR TEDESCO REGAN WILLIAMS (E)

FILE & REGION (3)

/LONG PROJECT LDR WILSON (L) vMORRIS INAS l

TEELE BENAROYA HARLESS

/TOLIJER EXTERNAL DISTRIBUTION i

S - LOCAL PDR

1. 1 - DTIE(ABERNATHY)

(1)(2)(10FNATIONAL LAB'S 1-PDR-SAN /LA/hY

/1 - NSIC(BUCHANAN) 1-R.S choomrake r,0C,GT,D-323 1-GERALD LELLOUCIE 1 - ASLB(YORE /SAYRE/

1-R. CATLIN, E-256-GT BROOKHAVEN NAT. LAB WOODARD/"H" ST.

1-CONSULTANT' S 1-AGMED(WALTER K0 ESTER l

46 - CYS ACRS 35E2Q35 SENT TO LIC, ASST.

NEWMARK/BLUME/AGBABIAN EM-C-427-GT 8-27-73 TEETS

1. GERALD ULRIFSON...ORNL 1-RD.. MULLER..F-309 GT i

AEC F**TRIBUTION FOR PART 50 DOCKET PJ".RI AL (TEMPORARY FORM)

CONTROL NO: 8128

/

FILE:

FROM:

DATE OF DOC DATE REC'D LTR MDiO RPT OTHER Yc".kee Atomic Electric Co.

W stborough, Mass. 01581 11-2-73 11-9-73 X

L. H. Heider Tot ORIG CC OTHER SENT AEC PDR X

D. J. Skovholt 3 signed SENT LOCAL PDR CLASS UNCLASS PROP IhTO INPUT NO CYS REC'D DOCKET NO:

XXX 40 50-29 DESCRIPTION ENCLOSURES:

Ltr requesti;.g chrification of definition for C3 abCot1Bal occurrence.............

ACKNOVJIzDGED DO NOT REMOVE PLANT NAME: Yankee Rowe FOR ACTION /INFORMATION 11-9-73 BUTLER (L)

SCIMENCER(L) dIEMANN(L)

REGAN(E)

W/ Copies W/ Copies W/1 Copies (info)

W/ Copies CLARK (L)

STOL2(L)

DICKER (E)

W/ Copies W/ Copies W/ Copies W/ Copies GOLLER(L)

VASSALLO(L)

KNIGHION(E)

W/ Copies W/ Copies W/ Copies W/ Copies KNIEL(L) p HEMEL(L)

YOUNGBLOOD(E) l W/ Copies W/ 7 Copies W/ Copies W/ Copies INTERNAL DISTRIBUTION GFILE]

TECH REVIEW DENTON A/T IND LIC ASST l

C PDR witENDRIE GRIMES BRAIIMAN l

v6GC, ROOM P-506A SCHROEDER CAMMILL DIGGS (L)

SALTZMAN

'IZING/ STAFF s41ACCARY KASINER GEARIN (L)

B. HURT CASE KNIGHT BALLARD COULBOURNE (L) p PMNS GIAMBUSSO

./fAWLICKI SPANGLER LEE (L)

MCDONALD BOYD v$HA0 MAIGRET (L)

DUBE MOORE (L)(BWR) v6TELLO

ENVIRO, SERVICE (L)

DEYOUNC(L)(PWR)

AOUSION MULLER SHEPPARD (E)

IhTO 64KOVHOLT (L) d'0VAK DICKER SMITH (L)

C. MILES P. COLLINS 40SS KNIGHTON VTEETS (L) we. KING (RO) s1PPOLITO YOUNGBLOOD WADE (E)

A G OPR wtEDESCO REGAN WILLIAMS (E)

FILE & REGION (3) vt0NG PROJECT LDR WILSON (L)

L410RRIS JAINAS 54TEELE QENAROYA HARLESS VVOLIFER EXTERNAL DISTRIBUTION i# \\

l - LOCAL PDR NONE

\\s G - DTIE(ABERNATHY)

(1)(2)(10)-NATIONAL LAB'S 1-PDR-SAN /LA/NY d - NSIC(BUCHANAN) 1-ASLBP(E/W Bldg,Rm 529) 1-GERALD LELLOUCHE 1 - ASLB(YORE /SAYRE/

1-W. PENNINGTON, Rm E-201 GT BROOKHAVEN NAT. LAB WOODARD/"H" ST.

1-CONSULTANT' S 1-AGMED(Ruth Gussman) d6 - CYS ACRS wn!rier. SENT TO LIC. ASST.

NEWMARK/BLUME/AGBABIAN RM-B-127. GT.

11-9-73 TEETS 1-GERALD ULRIKSON...ORNL l-RD.. MULLER..F-309 G

E q : : -.~.

. m A :' L i-YANKEE ATOMIC ELECTRIC COMPANY

[A

2...

c pp,e, n.N Ln e v

.Yaux?v,a

-u-r %,

W Rowe, Massachusetts 01367

\\Q se av

'6,.,

'b', / p

,ffy iy August 21, 1973 g

c-

/..

y <-

f/hg '4ho

.g 9'

$fp ij$/

4 f

,ky%y,,,.

U. S. Atomic Energy Comission Directorate of Licensing 4

Washington, D. C.

20545

/

g/

.s -

Reference:

License No. DPR-3 (Docket 50-29)

In compliance with the Yankee-Rowe Technical Specifications Attachment A, Section E.4. we are reporting the discovery of a protective system set point exceeding the value specified in Table I.

This incident is reported as Abnonnal Occurrence 73-7.

A preliminary report has been made to the Directorate of Regulatory Operations.

During a monthly nuclear instrumentation suneillance test on August 15, 1973 the trip point on power range channel No. 7 was found to be 109% rather than the specified 108% of rated power. The other five channels providing high flux protection were found with acceptable set points.

'Ihe high ne' tron flux set point protects the core against a DNBR type accident.

The safety of the public was not jeopardized since five other nuclear channels were providing high flux protection. The Technical Specifications require two channels to provide trip protection out of five or six operating channels.

Channel No. 7 will be inspected during the next plant outage.

In addition, the high power trip setpoints on all six channels will be lowered slightly. This change is in a conservative direction and will allow for a slight amount of instrument drift.

The Plant Operations Review Committee reviewed this incident and has approved the aforementioned recomendations.

Very truly yours, W

4p.4%/ 4LW

[O/

P n r

ndent cc:

J. P. O'Reilly, Director

,j Region I, DRO

=

?

AEC DI!

IEUTION FOR PART 50 DOCKET MAT' 'AL (TEMFORARY FORM)

COHTROL NO: 5809 FILE:

FROM:

DATE OF DOC DATE REC'D LTR MEMD RPT OTER Yankee Atomic Electric Company Rowe, Massachusetts 01367 David B. Pike 7-25-73 7-30-73 x

TO:

ORIG CC OTHER SENT AEC PDR r

SENT LOCAL PDR DL 1

CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:

x 1

50-29 ENCLOSURES:

DESCRIPTION:

Ltr reporting Abnormal Occurrence No. 73-6 en 11-6-72, in which the main ce$1 ant filter was found to be plugged....

DO NOT REMOVE

'IACKNOWLEDGED PLANT NAME: Yankee Rowe FOR ACTIO"/INFORMATION 7-30-73 LB BUTLER (L)

SCWENCER(L)

ZIDUSN(L)

REGAN(E)

W/ Copies W/ Copies W/ Copies W/ Copies CLARK (L)

STOLZ(L)

DICKER (E)

W/ Copies W/ Copies W/ Copies W/ Copies GOLLER(L)

VASSALI4(L)

KNIGHION(E)

W/ Copies Copies W/ Copies W/ Copies KNIEL(L)

CHD1EL(L)

YOUNGBLOOD(E)

W/ Copies W/ 7 Copies W/ Copies W/ Copies INTER'IAL DISTRIBUTION

@G FTilt TECH REVIEW DENTON LIC ASST A/T IND

1. EC PDR

'4ENDRIE GRIMES BRORN (E)

BRAI*D'.AN A

'v0GC, ROOM P-506A SCHROEDER CAMMILL DIGGS (L)

SALTZMAN etUNTZING/ STAFF pnACCARY KASINER GEARIN (L)

><ASE

.ANIGHT BALLARD COULBOURNE (L)

PLANS GIAMBUSSO

,#AWLICKI SPANGLER LEE (L)

MCDONALD BOYD ySHAO MAIGRET (L)

DUBE MOORE (L)(WR)

.6TELLO ENVIRO _

SERVICE (L)

DEYOUNG(L)(FWR) 6410USTON_

MULLER SHEPPARD (E)

INTO

• 'fKOVHOLT (L)

=50VAK DICKER SMITH (L)

C. MILES l

P. COLLINS

• 10SS KNIGHTON

>TEETS (L) vs. KING (reg Opr dPPOLITO YOUNGBLOOD WADE (E)

E/W Bldg)(00E)

-REG OPR d'EDESCO REGAN WILLIAMS (E)

• TILE & REGION (3)

• (.ONG PROJECT LDR WILSON (L)

~ HORRIS

• LAINAS

=

I

• $TEELE e4ENAROYA HARLESS

'90 LINER EXTERNAL DISTRIBUTION

/

1 - LOCAL PDR

• 1 - DTIE(ABEPSATHY)

(1)(2)(9)-NATIONAL LAB'S 1-PDR-SAN /LA/NY 64 - NSIC(BUCHA'IAN) 1-R.Schoonrak er,0C, GT, D-323 1-GERALD LELLC1/CHE 1 - ASLB(YORE /SAYRE/

1-R. CATLIN, E-256 CT BROOKHAVEN NAT. LAB WOODARD/"H" ST.

1-CONSULTANT'S 1-AGMED(WALTER K0ESTE

• T6 - CYS ACRS Enami SENT TO LIC ASST.

NEWMARK/BLUME/ACC.DIAN RM-C-427-GT

f. TEETS 7-30-73 1-GERALD ULRIKSON.. 0fNL 1-RD.. MULLER..F-309 C e

s.

-n --

(

fga

~

VANKEE ATOMIC ELECTRIC COMPANY Yd$

~

ROWE, i.'A5SACHURTTS 01367 July 25, 1973

.,.j_c

'5 s I rW

• Y s

Q'

'l lE?j

&.'f.*/)

, 's <

e, ! + Q......

s iJ

• /- A Ob f

.g

\\D jo

~-

V-

\\ )3

~

U. S. Atc=ic Energy Co==issicn

{

S L

l 1

'a~ashington, D. C. 205L5

}

s,.

Attention: Directorate of Licensing b 4

Dear Sirs:

Eeference: License No. DFF-3 (Docket 50-29)

In accordance with the Technical Specifications Sections E.2.a and E.I..b. for the Yankee Ato ic Electric Cc=pany Ecve Plant the exceeding of the chloride specification for the =ain coolant syste= is hereby,re-ported as Abnor=al Occurrence No. 73-6.

During a review of =ain coolant che:istry analyses during the October 1972 to April 1973 shutdown period it was noted that the =ain coolant chloride concentration was 0.1 pp= on Nove=ber 7th and 8th. This exceeded the li=it of <0.1 pp= during shutdown, thereby constituting a variance with the specification of Section 106 of the Final Hazards Su==ary Report.

On Nove=ber 6,1972 at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, the =ain coolant purification syste vas re=oved fro: service for =aintenance. '#et an atte=pt was cade '

to return the system to operation at the end of the day the main coolant filter vas fcund to be plugged. A test was perfor=ed indicating that the integrity of the ion exchange capsule screen had been broken, per=itting carry over of resins to the filter. A replace =ent ion exchanger-filter capsule train eculd not be installed due to unavailability of the yard crane.

The cause of the ion exchanger screen breaP-through is unkncvn.

On Nove=ber 6 a nev cain coolant purification train was installed and valved into operation at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />. The chloride concentration was reduced to <0.1 pp= as of Nove=ber 9; and to <0.05 pp= as of Nove=ter 12.

Very truly yours, ya uwp 3 2<

David 3. Pike Assistant Plant Sup(rintendent DEP/jb 5 SOS-cc: J.-O'Reilly L