B13061, Provides Listed Info Re Util Cable Vault Water in-leakage, Including Substantial Safety Hazards Evaluation CY-87-02,per 880908 Request.W/Eight Oversize Drawings

Provides Listed Info Re Util Cable Vault Water in-leakage, Including Substantial Safety Hazards Evaluation CY-87-02,per 880908 Request.W/Eight Oversize Drawings

ML20206B057
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	11/09/1988
From:	Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20206B059	List: B13061, Provides Listed Info Re Util Cable Vault Water in-leakage, Including Substantial Safety Hazards Evaluation CY-87-02,per 880908 Request.W/Eight Oversize Drawings ML20259B128 ML20259B133 ML20259B139 ML20259B146 ML20259B151 ML20259B157 ML20259B163 ML20259B172
References
B13061, NUDOCS 8811150326
Download: ML20206B057 (27)

Text

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O e NORTHEAST UTILITIES a.ner.i Orr,c.. . s.ioen sir..i. seri.n. Connect.cui

. . .c h TFORD. CONNECTICUT 06141-0270 k k I J 7.[2.![M,7, l,2C (203) 665-5000 November 9, 1988 Docket No. 50-213 B13061 Re: Cable Vault U.S. Nuclear halatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

Haddam Neck Plant Cable Vault In-leakaae In response to a September 8, 1988 NRC Staff request, Connecticut Yankee Atomic Power Company (CYAPCO) hereby provides lhe Staff with the following information pertaining to cable vault water in-leakage.

Evaluations and Reoorts o A copy of the Substantial Safety Hazards Evaluation (SSH), CY-87-02 o Copies of Plant Incident Reports (PIRs)86-225 and 84-43 The Supplement to LER 87-007 will be transmitted to the NRC by December 31, 1988 and consists of information described above.

Corrective Actions CYAPCO has installed observation wells at various site locations to determine the affect that the changing water table level has on the cable vault in-leakage. CYAPC0 has also performed non-destructive testing on the slab reinforcing and concrete. Test results have shown that there has been no adverse affect on the slab structural integrity. All internal conduits have been sealed with silicone foam to prevent water leakage through the conduits. At present, CYAPC0 is investigating the advantages of installing permanent sump pumps with emergency power.

Duct Banks A copy of duct bank drawings 16103-33006, sheets 1 and 2; 16103-34021, sheets 1 and 2; 16103 35037, sheet 3; 16103-50086, sheets 3 and 4; and 16103-50000, sheet 5 is attached. Design of the duct banks entering the cable vault do not include "low point" drains, gj

'l 8811150326 001109 (,

PDR ADOCK 05000213 PNU TO P g igS g5

l U.S. Nuclear Regulatory Comission B13061/Page 2 November 9, 1988 We trust you find this information satisfactory to resolve your concerns with cable vault in-leakage. If you have further questions, please contact our licensing representative directly.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY E. J'.

dtY y

W Senior)fP6cfka Vice President cc: W. T. Russell, Region I Administrator A. B. Wang, NRC Project Manager, Haddam Neck Plant J. T. Shediosky, Senior Resident Inspector, Haddam Neck Plant M. L. Padovan, Analysis of Operating Events Division, NRR

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i Docket No. 50-213 i j' p UE i

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Attachment ,

j Haddam Neck Plant

Cable Vault In Leakage 1

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November 1988

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• l.4 NOR1HEAST UTILITIE5 1 )

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N TO: P. M. Austin, Manager, Reliability Engineering D. O. Nordquist, Director, Quality Services P. Callaghan, Manager, Nuclear Safety Engineering W. D Romber Vice President, Nuclear Operations G# NMn _, Unit Superintendent 4.c P,6 e' , Chairman, Nuclear Review Board

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Nuclear Records FROM: 3. L. M a,'ewski ~

(Ext. 3924)

"eneration Facilities Licensing / Berlin

SUBJECT:

Completed SSH Evaluation SSH Evaluation No. dY-O -C1 has been completed. It has been determined that this item /d$ loc an SSH. In accordance with step 10.6 of NEO 2.01, a copy of the completed evaluation is attached for your 4

information/ records.

Original: GTL SSH Tile (J1JO olt0 mgy Ig3 BP91

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Figura 7.1

-"? .' ' SSH Evaluatien Wa. @'- 67-02.

NORTHEAST UTILITIES SSM EVALUATION FORM STEP 1.0 ORIGINATOR (NEO Group Employee) -

Identification of Potential SSH REFER 70 SECTIONS 4.0 AND 6.1 0F THIS PROCEDURE FOR GUIDANCE PRIOR TO INITIATION OF THIS FORM.

1.1 Describe the suspected noncompliance or defect (a'.tnh appropriate documentation). ATTACH 6p 1.2 Initiate a Corrective Action Request (CAR) if ductmined to be necessary in acec dance with Reference 3.3 of tbta procedure, and forward the L.R to the Manager, Quality A m rance.

CAR Initiated: Yes O No[ '

1.3 Forward SSH Evaluation _ Form to immediate sLpervisor.

EH.Reucmptl__ 4-23-8 0 Originator cr.grN c. Date STEP 2.0 Immediate Supervisor I 2.1 Determine that the noncompliance or defect meets the conditions of Section 6.1. If it does not, re+ urn to originator with explanation. File a copy in the appropriate originator's plant or department SSH file.

2.2 If it is determined that the SSH Evaluatiot should be continued, or if the originator has forwarded the SSH Evaluation Form a second ti:ne for further consideration, attach the information needed to support a written report (see 10CFR21.21(b)(3),

Reference 3.1 Attachment 8. A) and that needed to perform a technical review.

2.3 Obtain the proper SSH Evaluation Number and forvard SSH Evalua-tion Form w!th required i.nformation to the Manager, Generation Facilities Licensing.

Date Received from Originator j 87 Suggested Processing Time - ten working days This iS

[is)(isnot)hSSH .

'/ .M -S 7 momediate Superviso di.3.)c i Date Originator

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NEO 2.01 Rev. 1 Date: 03/15/85 Page 7.1 1 of 6

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'..$TEP 3.0 MANAGER, GENERATION FACILITIES LICENSING (er d' signee) -

Technical Revif'> Assi g ey 3.k Los in SSH Evaluation.

3.2 Designate technical evaluation responsibility to the appropriate NUSCO Engineering Supervisor (s) or Managers (s) and forward the .

SSH Evaluation Form with attached documentation

• the first indicated evaluator.

Designated NUSCO Engineering Supervisor W.8r.' ems . ld.13cdr e . 7. 3/ol.u/c/[ l

> <s e r Date Received " l./I r/g7 Suggested Procet' .ng Time - three working days Manager, Generation M"C Date Facilities Licensing STEP 4~.0 hTSCO ENGINEERING SUPERVISOR (S) OR MANAGER (S), OR 'slRECTOR, hT SYSTEM SECURITT (or designee) - Technical Eva'uation

t. 1 Evaluate the deviation and make an SSH determination.

4.2 Forward written evaluation and determination with SSH Evalu-ation Forn and attached documentation to Manager, Generation Facilities Licensing.

Late Received Y O M E*.lo)S7-W P _I "

• WnMa.

jg gh Suggested Processing Time - five vor ins days This / J .- ekSSH ,((/ ) S g. g yg&, J gv4.A in SSH cm pal ~A- ll 1.pyg n ,_s'.s.

NUSCO Engineer (ng m

Date AJ 4

}g Supervisor (f)/ Manager (s) kN STEP 5.0 MANAGER, GENERATION FACILITIES LICENSING (or designee) -

Nuclear Operations Review Assignment 5.1 Forward SSH Evaluation Form and attached documentation and evaluations to Vice President, Nuclear Operations, for opera-tional review.

Date Received _6, ,$7 S ggested Processing Time - three working days .

$$N h k/1.h%UDate $!ll 17 Manager, Genera non Facilities Licensing a cyels.tA ~ d p:ndh CQn:hkil Q* whv t o CFR. St.*1 2 5 us:~, w rey <Js chECD M W en 4%Emy[ am 4/n./r?, .7ftw wai U . NEO 2.01 Rev. 1  !

&dsa% ( 1, f. ,iut cqvshl/. dn.,tv.,g a vslodw Lt%(M r ?.c-)) Date: 03/ S/85 W > $- ' fh: 4 'rv -tA c N A t. v. 44e ,6 s e; ki/mb./ ) Pas 7.1 - 2 of 6 p,VLu. 'r/ir s 7

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Figur2 7.1

' STEP 6.0 VICE PRESIDENT, NUCLEAR OPERATIONS (or dvsignie) -

Nuclear Operations Review and Determination 6.1 heview SSH Evaluation and documentation and make an SSH determination.

6.2 If the determination is positive, forward SSH Evaluatiten Form with the determination and attached doet.n atat4"a to the Senior Vice President, Nuclear Engineering and Operat'uns7for it tal decision.

6.3 If the determination is negative, forward SSH Evaluation Form with the determination and attached documentation ) the Manager, Generation Facilities Licensing.

Date Received 7// fb7 Suggested Processing Time - three working days

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This - an SSH (is) { ny )

p /) Ay 7 n-O Vice Preside #, Date Nuclear Operations STEP 7.0 MANAGER, GENERATION FACILITIES LICENSING (or design -

l NRB/SNRB REVIEW ASSIGNMENT 7.1 The Vice President, Nuclear Operations, has made a negative SSH determination. Forward SSH Evaluation Form and attached '

documentation to the appropriate NRB/SNRB Chairperson for NRB/SNRB review.

Date Received 9/ 7 Suggested Processing Time - three working days l l

• 2L9a k.. an anager, Generoti6n eh Date' ~

q Facilities Licer. sing 1

STEP 8.0 I

LT*I.EAft PJ.VIEV BOARD / SITE NUCLEAR REVIEW BOARD - NRB/SKRB (In the Eent of a negative deterrination by the Vice P, resident, Nuclear j Operations) 8.1 Revie. 1.f:r;.W on and make an SSH determination.

l 8.2 If the Board's determination is positive, forward 3S1] Evaluation

' Form, with the determination and information to the Senior. Vice

! President,. Nuclear Engineering and Operations, for final j . determination.

8.3 If the determination is negative, forward SSH 't t :ation Form with attached determination and information ts ut Manager, Generatios. Facilities Lietnsing, for final dir.g:.,.ition.

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NEO 2.01 Rev. 1 Date: 03/15/85 Page ?.1 - 3 of 6 I

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' .. . ' .'57E P 8 . 0 C=tinued Date Received /-/V- 77 The (Y NRB/SNRB has determined this im sn SSH.

% s hot]

As soon as possible, or no later than the Suggested Processing Time next scheduled NRB/SNRB , as dettrained by the Chairperson.

b_O f V .#? W B/3NRB Chairperson Date Id-t-87 STEP 9.0 SENIOR 91CE P, RESIDE)rf, NUCLEAR ENGINEERING AND ^DERATIONS (or desig_ nee) - Final. Decision 9.1 Date and time received from:

Vicb.dident, Nuclear Operations, or Nuclear Review Board /

1. N* Site Nuclear Review Boa-d

) ~

NOTE: 10CFR21 reporting time requirements begin at the time the Responsible Officer personally is made aware of a positive SSH determination by his/her staff.

9.2 Review the positive SSH determination of the Vice President, Nuclear, Operations or the appropriate NRB/SNRB and make final de t e rmina tion. -

9.3 Forward to Manager, Gen mation Facilities Licensing, for any necessary reporting ar

• ion and final disposition.

9.4 In the event the Senior Vice President, Nuclear Engineering and Operations, disagrees with the positive SSH determination, the written basis for his determination shall be attached to the l

SSH Evaluation package which will then be forwarded to Manager, i Generation Facilities Licensing, for final disposition.

Processing time limits - Return to Manager, Generation Facilities Licensing, in time to permit a 48-hour verbal report to the NRC, if necessary (if final determination is positive). ,

I (agree and determine this is) (disagree and determine this is not) an SSH.

C M 5 Vice President, Date Fu <' r Engineering and Gy=.ations i

NEO 2.01

• Rev. I pate: 03/15/85 Page 7.1 4 of 6

.- l -

Figure 7.1 STEP 10.0 MANAGER. GENERATION FACILITIES LICENSING (er d'ain'ee) -

Reporting and Disposition j[f 10.1 No report of an SSH is necessary if the defect or noncompliance has been already report,ed by another reporting mechanism, and the information required in 10CFR21.21(b)(3) was provided to the NRC.

10.2 If the defect or nencompliance has not been previously reported, notify the NRC Office of Inspection and Enforcement within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the Senior Vice President, Nuclear Engineering and operations br.ving received a positive SSH determination by the Vice President, Nuclear Operar ons, or the Nuclear Review Board / Site Nuclear Review Bo ud, and ,

10.3 Submit a written report to the NRC Office of Inspection and Enforcement within five (5) days of informing the Senior Vice

. President, Nuclear Engineering and Operations, of making a ositive SCH determination, in conformance wifh 10CFR21.01(b)(3),

i 10.4 enior Vice President, Nuclear Engineering and Operations, does ot review the SSH Evaluation if the determination of the Vice

President, Nuclear Operations and the Nuclear Review Board / Site i Nuclear Review Board is negative.

10.5 A negative SSH determination has been made, but the deviation cou1J be of concern to other licensees because of its potential generic nature.

Yes a No a If yes, take appropriate action as necessary, per Section 6.3.

Time and Date Received _ ljlf' f t '$9 Processing Time Limits - See 10.2 and 10.3 above.

Time and Date 10.2 Completed / /t Manager, Generation Tacilities Licensing Time and Date 10.3 Completed bl/k Date 10.6 Distribute copies of the completed SSH Evaluation .nd NRC notification letter (if any) to the parties listed below as directed in Section 6.7.

o Manager, Reliability Engineering -

o Manager, NUSCO Quality Assurance '

o Manager, Nuclear Safety Engineering I

NEO 2.01 Rev. 1 Date: 03/15/85 Page 7.1 - 5 of 6

~ ~

.lWP 10.0 continued Vico Prcsident, Nuclear Operatir:s e

o Applicable Unit Superintendent o Applicable technical reviewer (s) o q Chairman of applicable Nuclear Review Board / Site Nuclear Review Board o Manager, Generation Facilities Licensing (Original for SSH File).

o Vendor Supplying Basic Component If Positive SSH Evaluation (NRC Notification Letter only)

Date distributed Signed i

e NEO 2.01 Rev. 1 Date: 03/15/85

- Page 7.1 - 6 of 6

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IDENTIFICATION OF POTENTIAL SSH 4-23-87 In accordance with NEO 2.01, Step 6.2.1 equires that the suspected noncompliance or defect be described.

CABLE VAULT WATER IN-LEAKAGE BACKGROUND The Cable Vault penetration ares distributes the control, power and instrumentation cabling into the reactor containment building for all the reactor coolant system and other , prima ry support systems. Ground water leakage into the Cable Vault has been a concern for several years. The extent of the leakage has primarily been through cracks in the Cable Vault floor.and walls.

PIR 86-225 (attached) is the most recently reported event.

Efforts to seal the cracks have proven unsuccessful in completely ,

eliminating the leakage. l

~ '

EVENT A recent event (PIR attached) describes a new inleakage condition being experienced in the Cable Vault. It reported that the conduit bank which conducts the electrical cabling from the Service . building to the Cable Vault has started to leak ground water. The conduit banks are located between 6-8 feet above the Cable Vault floor elevation.

POTENTIAL SSH In accordance with step 4.1.3 of NEO 2.01, this concern is i considered to be a "Major Deficiency", in that if a seismic event were to occur while the water table is at its present height, ,

1 the increased water leakage into the Cable Vault may be of sufficient quantity to cover the penetration terminations and i "result in a loss of safety function necessary to mitigate the i consequences of the accident". Personnel actions are currently i

. required to prevent the normal water intrusion levels from affecting the penetrations. It is unclear as to whether personnel ,

actions would be sufficient to keep the increased water inleakage  ;

at safe levels during the seismic event.

f,';s7p g p N.h87 R.M.Rogocidaki'/ Engineer 1

l SSH EVALUATION NO. 87-02 l CONNECTICUT YANKEE CABLE VAULT WATER IN-LEAKAGE .

STEP

4.0 TECHNICAL EVALUATION

THIS IS A SSH There are five safety related electrical penetrations (4C, 14 C , 13 C ,

20C, and 26C) with terminal block terminations located within approximately eight and eighteen inches from the cable vault floor. These consist of safety related instrumentation circuits ,

associated with the RCS System. These terminal, blocks are not qualified for wet environment (water submersion). Flooding of the terminal blocks could cause erroneous instrument readings, loss of safety related functions and short circuits.

1 Prepared By: . 5 -/2 -r7 ,,

J. Chiloyan Date

. Generation Electrical Engineering Approved By: Mb W. H.

h Beck'er, Supervisor 6-12-8 7 Date Generation Electrical Engineering i

SE:35 l

I .

CIVIL STRUCTURAL TECHNICAL EVALUATI6N CONNECTICUT YANKEE SSH EVALUATION NO. CY-87-02 CABLE VAULT WATER IN-LEAKAGE SSN-87-02 identifies the concern that "if a seismic event were to occur while the water table is at its present height, the increased water in-leakage into the cable vault may be of sufficient quantity to' cover the penetration terminations." This event could "result in a loss of safety function necessary to mitigate the consequences of an accident." The intent of this technical evaluation is to address that concern as outlined in NE&O 2.01, Section 5.7.1.

GCE has evaluated the potential for increased water in-leakage into the' cable vault due to an SSE. This evaldation has concluded that the potential for water in-leakage into the cable vault to increase during or following an earthquake less than or equal to the safe shutdown earthquake is minimal. This conclusion is based upons i o NUSCO Calculation 86-207-229-GC which reviews the potential _

stress development in the cable vault structure due to an SSE. This review referenced the URS/J. A. Blume Seismic r Reevaluation of Major Structures of the Connecticut Yankee  !

Atomic Power Plant Report (December 1982) which details the free-field acceleration design response spectra for i

structures at the CY site. This report has determined that the SSE free field base horizontal acceleration is .17g.

Similarly, the SSE free field base vertical acceleration is 1

.113g. Utilizing these inputs, this calculation has

determined that the maximum stresses which could potentially be developed in the cable vault structure as a result of an SSE will remain well within normal allowables. Therefore, '

there is a minimal possibility of existing cracks to i significantly change size.

o NUSCO calculation 83-106-130-GC which has determined that the  !

cable vault structure, as outlined on NUSCO drawings 16103-50086 sheets 3 and 4, can withstand a 30 foot MSL flood elevation without structural failure. This 30-foot MSL flood l load envelopes the SSE loading condition on the cable vault ,

structure. t o NUSCO drawings 16103-50086 sheets 3 and 4, 16103-33006  ;

sheets 1 and 2, 16103-34021 sheets 1 and'2, 16103-350,37 sheet j 3, and 16103-50000 sheet 5 which detail the structural

. outline and location of the cable vault structure and the conduit duct-banks entering the cable vault structure. These

drawings identify the details necessary in limiting water 4 in-leakage following natural occurrences which cause sudden 1

limited horizontal and vertical loading on the structure such as an SSE. These details include positive and negative concrete reinforcement, water seals, adequate reinforcement i 4

splicing, and adequate lateral stability for the walls.

1

s Civ~il Structurcl T chnical Evoluction Pago 2

.' CY Cablo V ult Water In-Leckago SSH Evaluation No. CY-87-02 Based on these inputs, the potential for increased water in-leakage related to an SSE has been examined. There is no potential for significantly increased water in-leakage following an SSE and, therefore, there is no SSH.

The concern does exist that water removal from the cable vault, following an SSE event, may be restricted due to the potential loss of offsite power. Emergency electrical power to service the existing pumps in the cable vault following a seismic event is presently not available. GCE has concluded that the existing water removal capability following an SSE event is potentially deficient and should be addressed.

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' Civil Structt:rcl Technical Evolucticn P g3 3

, CY Cablo V ult Cat:r IC-Lerkag3 SSH Evclustion No. CY-87-02 5 24 ! ? 7 G. A. Flannery, Enginee Date Generation Civil-Strue ral Engineering f ... E 0 $ Yl Walter J.geriggsf/Aupervisor / 'Da t e Generation Civil-Structural Engineering ff T oDel t N. Smayt, Manager

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(f2o fpq Date Generation Civil and Fossil Engineering

&f fJk T. Leonard Johpon, Director

.(f2O/& T Date Generation Engineering and Design CS-D17-43 4

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Technical Evaluation: SSH 87-02 l

References:

1. Generation Civil-Structural Enginaering Technical l Evaluation. SSH Evaluation No. CY-87-02, 5/20/87

2. Generation Electrical Engineering Technical Evaluation, SSH Evaluation No. CY-87-02, 5/12/87 Discussion

• There is water in-leakage into the containment cable vault. The cable vault contains safety related cables required for design basis accident mitigation. The SSH was initiated based on the potential for increased  ;

in-leakage following a safe shutdown earthquake (SSE). It also identifies i that personnel actions are required r,ven without an SSE to prevent buildup i

of the water. Reference 1 evaluates the potential for increased in-leakage -

following an SSE. This evaluatico concluded that there is no potential for significantly increased in-leakage fn11owing an SSE. Reference 2 identified the lowest elevation above the cable vault floor where safety related cables are located. In addition, it identified that the cables would not be expected to function following submergence under water. [

The cables are credited for design basis accident mitigation. If they were f to be submerged and their function lost, the consequences of the design basis accidents would he more severe. In addition, if enough cables are affected, then safe shutdown capability may be lost. Following a design basis accident such as an SSE, there would be many cctions that personnel would have to take to mitigate and recover from the event. The pre-existing in-leakage, if not pumped out in time, could cause a loss nf sa.*t shutdown capability.

Conclusion I c Based on the fact that the pre-existing in-leakage would cause a Inss of l

safe shutdown capability, if not pumped out, it is concludad that this is r an SSH.

e LL D. J. Parker ~

c/dn Date '

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Transient Lalysis Section [

%W N. 5. Kai, Supervisor del 97 Date i

l Transient Analysis Section

/ b$o d/ f/ k *? -

(J/ A. Blaisdell, Manager Date 7afety Analysis Branch

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Connecticut Yankee SSH Evaluation No. 87-02 Cable Vault Water In-Leakage Based upon tha following, I have determined that this is not a SSH:

o following a t'SE, the increase in in-leakage into the cable vault is minimal.

o Without operator action, water level rise in the cable vault is 1/8" per hour. The lowest terminal blocks are 8" above the cable vault floor. To reach this penetration would require no-operator attention for 3 days.

o A portable electric generator / sump pump is available for pumping in the event of loss of power.

o Assuming operator action is required within 3 days, this mitigation is no more than operator action expected in other events except that the operator has significantly more time in which to perform the action. -

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Wayne D. Romberg g Date Vice President - Nvelear Operations t

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C1t-54-4M Cable Vault Tritiuw g.-

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The high water table that we esperienced in April resulted in h water serping up thrauth the cable vault flonr. Once the river .g

• 2 s ' '& '.g,~.  ; receded, the water table level decrease followed several eays ,,

' 4-l' later. The cable vault in-leakage diminished to aero, as well.

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by early May. . M ' 3,',j'.{

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Concern was raised on the tritium concentratian of the water ,

h,*'*b, J t m *. .i . leaking into the emble vault. The attached tahles and graph ..

.' ,1, E *3 depict the shange from a nornet groundw. iter tritium cancentra- i]4 4p

[f,9t**4/, .~. t tion (f rom the high 10-5 range to the low 10-6 uC/el range) to '

values in the high 10-4 to low 10-3 uC/mi range. The containeent , " (.,;;

, hg h + J, ' + sussp exhibited a similar change in tritlue concentration. ,d u ,. ,

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Investigation  ;,'l !. :)s,'.L

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Inventeries of tanks were checked for unaccounted for losses. ,  ; Q.W' ,

None were noted. Tanka and suw e ware che:ted dur!.eu transfer T T*

Q . .y- j,Q ,. periods, and water voluw s were all accounte'sle. The test tank s - ,'.Y I' h discharte line was checked, and found to be intact up to the F  %.q',*; *,i. point of discharge in the PAR service water line.

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The stets generrtor b!cvdev.a 11:*.e ves faund ta have a ==jor ,

• y Y. This was l 3, a- breach under the druming room floor on Ptey 19.19A6 3

ruled out as the source of tritium as secondary syntem trit tires

$ k'.1 run in the order of 10-5 uc/ml.

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trations startint around April 12,19%. f.'ere ren.aina no ex.

planation on the laree increste and sut,.quent decrease in the .}

f,{h, , l , r, if'/.' s ,-

tritium toncentration in be .h the cable vault and the sat susp 1.aboratory instru cnt at inn and prm edure s were checked

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3 out acceptable. .e

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The floading that occurtM in estly June 1944 resulted in a high . . . , , - f, ,

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water table and inleakapc into the cable vault. but no increase ,

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been. Di ar bs t r.e (**rmit= bove been made riot in account for all .'V'

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• 7) j ' ' act ivity digebergrj f rr e Lt e Latile sa61t t > tl.e yard sewer systee. g , > 4,. .

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