ML20043H735

Provides Clarification to Re Specs for Repair of Leak Testing Canal & Gamma Pit Sections of Reactor Pool Sys. Post-repair Leak Rate Testing Accomplished by Monitoring Water Level in Canal & Gamma Pit

ML20043H735
Person / Time
Site:	05000054, 07000687, 07000377
Issue date:	06/21/1990
From:	Mcgovern J CINTICHEM, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9006260377
Download: ML20043H735 (4)

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CINTICHEM, INC.

' a wholly owned subsidier y of Medi-Physics, Inc.

P.O. BOX 818, TUXEDO. NEW YOFK 10987 (914) 351-2131 June 21, 1990 U. S. Nuclear _ Regulatory Commission Document Control Desk washington, D. C.

20555 r

Gentlemen:

SUBJECT:

Dockets 50 59 and 70-687, Order Modifying License

REFERENCE:

(a) Cintichem letter (JJM/113.90B) dated May 31, 1990 t

Our letter referenced above transmitted,_ among

.other

things, specifications for repair and leak-testing the Canal and Gamma Pit l

sections of the reactor pool system.

This letter is to clarify and'

~

augment this document pursuant to recent discussion with NRC Region I.

On _Page. 9, Section 3.1, it was not clearly stated that repairs to defects in the deep section of the Gamma Pit (16 feet below the normal operating water level) would be completed.

We affirm that all defects-located'below-the normal operating water level in the Canal and Gamma Pit will be repaired.

Post-repair leak rate testing will be-

_ accomplished by monitoring the water level in the Canal and Gamma Pit.

a An ~-. echo sounding. instrument with' a digital -display will be used for monitoring: the water level. changes to a sensitivity. of 0.l".

The 4

-resultant-sensitivity in terms of GPM over-a test duration of-12 hours

will-be 0.0037 GPM in the Canal and 0.0019.GPM-in the-Gamma Pit. ; Leak L

rate testing' will be done in three stages; i.e.,_theolower section.of the-Gamma Pit, the entire Gamma Pit ~ and the Canal.

The duration of.

-the' leak test of each section shall be 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, minimum.

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Section 5,

the leak testing procedure will be modified.

Prior to filling.the Canal and Gamma. Pit with water the concentration of radioactivity in the pool system (Pool, Stall and ' Storage Tank)- shall

be established as a basis for comparison.

The sampling point at S-3 L

will be changed.to B-1, that is the location-in the french-drain q

_ system upstream before any tributaries enter the S-3 drain pipe.

The radioactive concentration in the water system being tested will be

' determined; initially after filling and at'3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> intervals throughout

'the test period.

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l.

Whenever the Canal and Gamma Pit are used for transferring radioactive l

material-after acceptance testing is successfully completed and if the system is not._ absolutely leak tight (leak rate

< 0.3 GPM),

the follcwing monitoring protocol shall be followed:

JJM/129.90B-h bob 9

e U..S.

Nuclear Regulatory Commission Document Control Desk June 21, 1990

-Page-2 J

o The B1 drain line will be monitored for the presence. of. water.

Any water-will be sampled-and analyzed for radioactive concentration regularly at 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> intervals, o Any water found at S-3 will be diverted, retained and tested to assure that it is within MPC limits prior to discharge off-site.

o The Canal and/or Gamma Pit water will be sampled and analyzed-

-for radioactive concentration at 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> intervals, o-If the radioactive concentration in the Canal and/or Gamma Pit water increases to 1/2 MPC, operations in the Canal or Gamma Pit will be discontinued.

o If the radioactive concentration in the Canal and/or' Gamma Pit water increases to MPC the Canal and Gamma Pit will be drained.

We believe that this supplemental information satisfies the requests.

for clarification that arose in our discussion concerning. our repair specifications and acceptance criteria.

Enclosed please find a copy of Construction Technology Laboratories' letter concerning the distinction between-construction codes ACI 349 and.318 regarding the adequacy of the outside canal wall.

Per the standard construction code ACI 318, this wall' is adequate for static and: dynamic loads from seismic activity.

Very truly yours, h@f

-cccL-J. J. McGovern Plant Manager i

.JJMcG/bjc i

Enclosu/e L,

cc: (with enclosure) 1

.Mr. Theodore Michaels, Project Manager 1

Non-power Reactor Project Directorate f

Division of Reactor Projects III, IV, V and Special Projects.

NRR U. S. Nuclear Regulatory Commission Washington, D. C. 20555-Dr. Robert Bores l

U..S.

Nuclear Regulatory Commission l

Region I 475 Allendale Road King of Prussia, PA 19406 l

L JJM/129.90B

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S. Nuclear Regulatory Commission Document Control Desk June 21,.1990 Page 3 (without enclosures)

Mr.. Ray Jackson-U. S. Nuclear Regulatory Commission Washington, D.

C. 20555

. r.

Dr.

F. Bradley New York State Department of Labor Radiological Health Unit One Main Street, Room 813 Brooklyn, NY 11201 Dr.

F. Caporuscio New York State Environmental Protection Agency Region II - 2 AWM-RAD 4

26 Federal Plaza New York, NY 10278 Ms. Annette Dorozynski, Supervisor Town of Tuxedo P. O. Box-725 Tuxedo, NY 10987 t

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L I

JJM/129.90B l

l

v Construction Technology Laboratories, Inc.

6420 CMd Orchard Road, Skokie, FinoW 60077-1030 Phone; 700 9%-7500 -

Tetex: 9102401669 CTL.SKO Fax: 70696fr6541 April 20, 1990 Mr. James McGovern Cintichem, Inc.

Long Meadow Road Tuxedo, NY 10987 Roonirs to the Gamma Pit and Canal

Dear Mr. McGovern:

Under separate cover, CTL draft repair specifications (dated April 20, 1990)~were cent to you yesterday by express courier.

Included in the transmittal were specifications for steel struts to support the outside Canal wall. According to CTL calculations, these strut repairs are required to satisfy the provisions of ACI 349 for Nuclear Safety Related Concrete Structures.

However, they are not required to satisfy the provisions of ACI 318, Building Code Requirements for Reinforced concrete.

If the reactor is decommissioned, it would seem likely that the NRC would allow the use of ACI 318 and thus would not require this portion of the repairs.

We are still awaiting your comments regarding our draft evaluation report dated April 4,-1990. -As calculations have been completed, we have added a caution to the report indicating that Hold-up Tank walls are overstressed by exterior soil pressures.

Hence, if left unre) aired,

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the south wall should be braced or personnel access to the tank s1ould be restricted.

Both the specifications and report can be finalized at'your request.

If-zouhaveanyquestions,pleasecall, Very truly yours,

~

s Peter R. Kolf Evaluation Engineer Structural Evaluation Section q-L PRX/bc Copy to--

H. C. Kosel J. P. O'Connor a

C. A. Olson 260212 x

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