Text

Insp Rept 50-057/89-04 on 901108-1212.Major Areas Inspected: Reactor Pool Liner Leak,Facility Operations & 891212 Mgt Meeting.Overall Actions Taken in Response to Reactor Pool Liner Leak Conservative & Safe
	ML19354D924
Person / Time
Site:	University of Buffalo
Issue date:	01/16/1990
From:	Mccabe E; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML19354D920	List: ML19354D919; ML19354D924;
References
	50-057-89-04, 50-57-89-4, NUDOCS 9001250011
	Download: ML19354D924 (24)
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U.S. NUCLEAR REGULATORY COMMISSION

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REGION I

Report No.

50-57/89-04

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Licensee No.

R-77

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Licensee:

State University of New York at Buffalo

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Rotary Road,-South Campus

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Buffalo, New York 14260

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Facility:-

Buffalo Materials Research Center

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Location:

Buffalo, New York

Inspection Conducted:

November 8 through December 12, 1989

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Inspectors:

N. S. Perry, Acting Senior Resident Inspector, Ginna

W. V. Thomas, Radiation Specialist, Region I, DRSS

Approved by:

M O. b M h

i /l6 l90

E. C. McCabe, Chief, Reactor Projects Section 3B

Date

Summary:

Areas Inspected:

Reactive inspection (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) of the reactor pool liner

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leak, routine safety inspection of facility operations (7.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ).

This re-

port also documents.a management meeting between the-licensee and NRC on

December 12, 1989.

Results: Overall, actions taken in response to the reactor pool liner' leak'

were assessed as conservative and safe (section 3).

Facility operations were

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observed to be technically sound (section_4).

The lack of a calibration pro-

gram was referred to the licensee for consideration (section 4.a).

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TABLE OF CONTENTS

PAGE

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Introduction.........................................................

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Persons Contacted....................................................

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3.

Re a c to r Po ol Li n e r Le a k . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -

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Facility Operations.............................................

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4.a Organization, Logs and Records (39745)..........................

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4.b Review and Audit (40745)........................................

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4.c

Procedures...............-.......................................

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5.

.NRC-BMRC Management Meeting..........................................

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6.

Exit Interview (30703)...............................................

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DETAILS

1.

Introduction

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The Buffalo Materials Research Center (BMRC) is located on the south cam-

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pus of.the State University of New York at Buffalo, New York. The reactor

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facility, which opened in 1961, is the only research nuclear reactor in

western New York.

It is owned by the University and is managed by Buffalo

Materials Research, Incorporated.

The research center.contains a high

neutron flux nuclear reactor rated at 2 megawatts thermal, a Van DeGraff-

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accelerator, a large hot cell, and remote handling and testing facilities.

The reactor is used for materials' irradiation studies, short-lived radio-

isotope production for medicine and medical research facilities across the

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country, and for New York University laboratories and industry. The reac-

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tor is also used for neutron activation analysis, reactor materials com-

ponent qualification, and nuclear instrument calibrations.

The reactor is

normally operated weekly from Sunday evening to Friday evening, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a.

day, by three 8-hour shifts.

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2.

Persons Contacted

J. P. Griffin, Health Physics, BMRC

L. G. Henry, General Manager, BMRC

P. M. Orlosky, Operations Manager, BMRC

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D. W. Sullivan, Director, BMRC

The inspector summarized the inspection results with Messrs. Sullivan and

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Orlosky following the inspection on December 11, 1989.

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3.

Reactor Pool Liner Leak

On !!ovember 5,1989, after a two day shutdown, reacter operators prepar-'

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ing for reactor restart discovered that the reactor pool level was lower

than normal by approximately 180 gallons. Normal water loss -over a- week-

end period averages 150-180 gallons due to evaporation and primary recir-

culation pump gland seal leakage.

Initial investigation revealed a steady

drip from a telltale pipe.

The telltale pipe is part of.the suction pip-

ing for a recirculation system which was capped and abandoned in 1978,

after it was determined to be leaking. The abandoned pipe runs from under

the center of the reactor pool to a sump located just outside the contain-

ment structure; water from the sump is pumped into the liquid waste stor-

age system.

Shortly after discovery of the leak, BMRC personnel initiated a study to

determine if all reactor pool water could be accounted for.

The water

flow rate from the abandoned recirculation pipe was measured, along with

the water losses from the primary recirculation pump gland seal and that

due to evaporation; this result was compared to actual water loss as meas-

ured by the decrease in the reactor pool water level. The licensee con-

cluded that, within overall measurement errors, the water lost from the

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reactor pool was accounted for. . BMRC personnel continued to monitor reac-

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tor pool water losses and have noted that leakage from the abandoned pipe

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remained constant at approximately 1.5-2.0 gallons per hour. Addition-

ally, after the primary recirculation pump was restarted on December 5,

1989 for the first time since the reactor was shut down on November 3,

1989, leakage decreased to less than 10 gallons per day.

The licensee

suspects that pump flow disturbed sediments which partially blocked the

leak. The inspector independently performed water balance calculations

for the data obtained on December 4, 1989 and December 8, 1989 and ob-

tained results consistent with those of the licensee, and concluded that

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reactor pool water is accounted for within measurement errors.

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On November 8, 1989, BMRC personnel began searching for the source of the

leak using an underwater microphone and video camera.

Results.from micro-

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phone testing were inconclusive; however, video camera testing identified

a crack in the weld between the abandoned recirculation pipe flange and

the pool liner bottom. This abandoned piping is capped and welded.. Tne

licensee believes the crack has existed for-several years,- and recently

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corroded completely through. The crack is approximately 2-3 inches long.

At the close of the inspection, the licensee was evaluating various short

.and long term corrective actions.

The licensee submitted a letter to NRC

Region I committing to refrain from operating the reactor until tne leak

is fully repaired or, written authorization is received from the NRC.

Radiation levels recorded within the containment building for the weekend

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of November 3-5, 1989 remained at a normal 2.5 mR/hr above the core. .Sub-

sequent measurements from November 4-6, 1989 by the senior health physi .

cist indicated that no radiation-levels above normal background levels

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were found in the facility. The inspector reviewed potential release

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pathways to the environment-and noted that all gaseous releases are fil-

tered through High Efficiency Particulate Activity (HEPA) and charcoal

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filter systems. Reactor leakage water is pumped to one of two 10,000 gal-

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lon hold-up tanks for decay. All' liquid releases are made in batch mode

and are sampled prior to release. When releases are made they are made to-

the sanitary sewer system. Water is not released to the sanitary sewer if

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it exceeds 1% of the Maximum Permissible Concentration (MPC) for non-

restricted use. There have been no releases to the sanitary sewer since

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the leak was discovered. Normally the hold-up tanks are released to the

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sanitary sewer system after sampling and analysis 3-4 times per year, when

approximately 80 percent full of water.

The inspectors concluded that there is good agreement between the amount-

of water collected and the amount of water lost from the pool due to the

leak.

The actions taken by the licensee were assessed as conservative and

safe.

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4.

Facility Operations

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4.a Organization, Logs and Records (39745)

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The inspector verified that the minimum staffing composition for.

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operation as described in technical specifications was met by review-

ing the control room log book.

Additionally, selected portions of

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the control room log book were examined for general content and were-

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found to be adequate in addressing activities and events. .The ab-

normal situation reports for 1989 were reviewed and the inspector-

found entries to be sufficiently' detailed to describe each situation;

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however, no entry was written for the-November 5,.1989 reactor pool'

liner leak.

Licensee personnel stated that this was due to the. fact

that the event was made well-known through other notifications and in-

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various meetings, but the event would be evaluated for entry.

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The reactor maintenance log book was reviewed for 1989. -The inspec-

tor noted that no instrument calibration activities were logged.

When questioned, the licensee stated that-no periodic calibrations

are performed. The~ licensee indicated that initial calibrations were

performed, but subsequent, periodic calibrations were not routinely

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performed.

Licensee personnel agreed to evaluate calibration pro-

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grams for implementation in the near future.

4.b. Review and Audit.(40745)

The inspector reviewed the t'wo most recent Nuclear Safety Committee

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minutes (11-7-89, .11-16-89) and noted that a quorum. existed at each

meeting and the minutes appeared adequate in detail and content.

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Reviews required by 10 CFR 50.59 were examined and the inspector

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found that only in the last year has this process been formally.

accomplished. The three reviews examined (9-12-89, 10-24-89,

12-6-89) had the appropriate reviews and approvals, and documentation

was adequate. .However, the inspector pointed out to the. licensee

that,- in some cases such as replacement of a part with an identical

one,-a 10 CFR 50.59 review is being performed when not.necessary.

The June 14, 1988 annual audit, issued August- 25, 1988, was' reviewed

by the inspector and found to be from an independent source. The

report was comprehensive and all identified weaknesses' were resolved-

by the licensee. The licensee stated that the 1989 annual audit was-

conducted in July, but the report had not been issued.yet. The in-

spector expressed a concern on timeliness of the audit report and the

licensee indicated they would. follow up on this concern by contacting

the auditor.

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4.c. Procedures

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The inspector reviewed procedures to verify that they can accomplish

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their intended purpose, the procedures used are the latest revision,

and that procedures are reviewed and approved as required. The fol-

lowing procedures were reviewed.

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EP #4, Reactor Loss of Coolant Accident,. 5/88 revision.

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OP #5, Routine. Startup Procedure, Startup for Full Power Opera-

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tion, 8/89 revision.

OP #7, Routine Reactor Shutdown, 5/87 revision.

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The following completed procedures were reviewed.

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OP #77, Quarterly Instrument Check, 5/88 revision, performed

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first, second, and third quarters 1989.

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OP #3, Post-Operation Checklist, 5/88 revision, performed

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9-22-89.

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OP #2, Reactor Pre-Operation Checklist, 5/88 revision, performed

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9-24-89.

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In one case the inspector identified.a discrepancy between the proce-

dure revision and the revision indicated in the procedure index.

The

licensee indicated that the index was incorrect and a correction

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would be made.

The inspector could~not verify that the annual review

of the operations procedures was completed by the licensee-as re--

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quired by Technical Specification 6.5.

The licensee' indicated that,

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although the-review was completed, no documentation existed'indicat-

ing that each procedure was reviewed as required,.but.they would

evaluate a means of documenting this review in;the future. The .in-

spector concluded that-better administrative controls' are warranted '*-

to ensure that the procedure index is current and annual procedure

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reviews are documented.

5.

NRC-BMRC Management Meeting

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A meeting was held in the NRC Region I offices on December 12, 1989. 'At'

the meeting, the-BMRC General Manager presented the current status of the.

reactor pool leak and potential corrective actions being evaluated. .A

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video was shown which displayed the location of the weld crack and its

relative size.

Handouts from the meeting are enclosed with this report.

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6.

ExitInterview(30703)

The inspectors met with senior plant management periodically and at the

end of the inspection period to discuss inspection scope and findings.

Based on discussions with licensee representatives, this report does not

contain information subject to 10 CFR 2.790 restrictions.

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Preliminary Report

Reactor Pool Liner Leak

State University of New York at Buffalo

Buffalo Materiale Research Center

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Submitted to I!SNRC-

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December 12, 1989

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Introduction

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On the. afternoon of November b,

1989, the reactor start-up

crew, while' performing

reatine pre- cperational tints,

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served that the reactor pool'Jevel van lower than x rmal by

approximately.180-gallov. .Init3 ci ^ ucestig nien Su tovthe'.

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discovery of a steady d:ip c"

wun

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"'a" pipe

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. which runs from under

cntJ or

t - rom km :.ank tot a

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. . sump in the N-16 hold te

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t"e water

4

m

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drained by gravity to a

. where

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a sump-pump lifts it ut.

atorage

system.

A second "tell-

r from-

the - perimeter of the r.

emains

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dry.

The reactor tank has b

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veing an undnewater

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video system,-and a ising;

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a weld

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at the bottom of the t-

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been

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reviewed by an. expert ir

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and

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he has determined, basc

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probably several years o,

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rw eingles

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a. result of corrosion.

"ago rate

was about 50 gallons per

e 'd con-

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siderably and

on 12/1)

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The amount of water los -

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favorably . with the anot' .

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holding system.

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The' reactor

as not be<

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leak. The University hat

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the reactor until the 3

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Traire -ore po a.iacion has

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been granted by the NRC.

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II.

Previous Leaks

During the mid seventies

curred'

through a section of tt

m system

which was buried in conc A

utible ..for

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repair. Several attempts

.t made to rqcir 'n

cak in the

buried pipe including tue

me of a

m

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f.nflatable

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rubber seals,

infusion

<>f

clastom:rie ;:co m -

the leak-

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from inside the pipe, an, tho inn d a

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a : o_

'toun grout

into the cavity around F o onN 'do oc tha

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Ench.of

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-these methods achieved.1;&lted ou.xesc. . The u

a'.ous grout

however, while not seal b

":e lat

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ta " path of-

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least resistance" from m

.; ta

n't. ; . .

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. .; t sump,'and'

significant quantitie-

/ontaminated water were thus

forced into the groundw

m wth the renctor containment.

During an extended outz

etely dis-

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mantled and the leaks &

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irradiated

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fuel on site was shipped to the DOE for disposal, and the

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remainder was stored in. the reactor Hot Cell.- .#he .other

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more active components of the reactor were stored on site

using improvisational shielding.

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A new primary circulating. loop was

installed,

which-

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penetrates the reactor liner-through two abandoned; beam tube

ports. This piping loop is completely accessible for inspec-

tion or repair.

Six cover plates were welded into place in

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.. the reactor tank to ' seal -off the original liner penetra-

tions. (one 2" drain, one 12" core outlet, and four 4" core

returns) All were located in the lower regions:of:the reac-

tor tank.

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Before the . cover plates were welded in place,. holes were

drilled'in the piping behind them so that the original core

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outlet and return lines could subsequently serve tas "tell-

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tales" .in the event of future leakage.

There are,

thus,

three "tell-taleH systemsg- consisting of the abandoned core

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outlet and return lines as well as an original "tell-tale"

installed at the bottom perimeter of the tank whentthe reac-

tor was constructed.

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Ultrasonic thickness gauging was=used to evaluatetthe over--

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all health of the reactor liner.

Based ' on .these: measure-

ments, it was decided to replace the. horizontal "shisif" sec-

tions of the liner. Dye penetrant evaluations were performed

for the existing and new welds.

The'results were snremark-

able.

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After the welding was completed,. the reactor.: was re-

assembled, however, slow leakage from the tank was observed

and it was. disassembled again.

A crack about 7"

long was

located in the weld between the original = core outlet flange

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and the liner bottom.

. The cover plate weld; was undamaged.

It was theorized that -the original weld from the flange to

the liner was damaged by the-heat-from the cover plate weld

and cracked when weight was applied.~

The damaged. weld was'

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ground out-and re-welded, and.the reactor was re-assembled.

No further leakage was observed.

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III

Location-of the Leak

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Two methods were used to search for and locate the current

leak.

Initially, a sensitive underwater microphone was used in tho'

tank to listen for the leak. This method wast: employed

successfully to locate the leak-in the pool liner at North

Carolina State University.

Two engineers from NCSU came to

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Buffalo and assisted in the search for the leak.

Results of~

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the microphone tests

c.ons w. iw

The 3=

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heard, however, the e: ,; t Ice tion cool.4 n9.

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ninpointed

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due to the reflection or nound in t M e % mt s :ma.

A radiation-resistant winiaturc

Ccr. tater v. ideo camera +was

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then used to search for ihe lec

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crt@ van located-in

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the same location as s L env? .

A bcman the aban-

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doned core outlet flang

W

nr , ttom-

ho location

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of the leak is consir-

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'. cF v:ter in the

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other "tell-tales" and "

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which are

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recovered from the cort

sections

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of the tank, and in pt

' elds, . have

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been. video inspected h1

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located.

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It is therefore, extr

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a the only-

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leak.

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IV

Leak Water Pathway and .

The pathway of the leak

J FigureII. .

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The water seeps through

. joint be-

tween the. flange and t

enters the

"tell-tale" through the <

,during_the

1

previous repairs. It ru:

Mich slo]ies

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downward) and terminate

the reactor

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containment wall over a

The out .

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board and of.the "tell-

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and was open.

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to atmosphere.

Water

h the othDr:

a

groundwater in the sut

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cy into the

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" primary pump pit".-

TL

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$proximatfly

12,000 gallons in volumo

Ty circulat-

, "<

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ing pump and a 1000-ga: m

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From tite

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bottom of the pump pit,

m unt e r M n ti f'tml b3 a sump-pump

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to the 1000 gallon tank.

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en full,ris

pumped under manual cc

.allon main

t

holding tank.

If necest

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t -

"orage tanks

"

are available which pro'

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holding capacity.

.. gallons-of

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A pancake has- been insa :lsd an t: o e a t.b

. end of the

"tell-tale" pipe.

Thio pancaho fu pe ?trab

by a small

diameter nipple which le,'1 to nn isolat a m %ve and then a

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tygon drain directly to 20 p+: m olt-

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ant was also

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installed..

This would 3 hit im

s ix! " * <

Mss raterin

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the event of significan

furi her f.O 1 w

a-

, weld.While

at - the same time it prc ddc.9

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. , a:. t ah

path to the

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sump-pump.

catastrophic failure e

cover piam

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ot considered

credible, however, in

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of dran+ta

lure of'the

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the microphone tests

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h 3=

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heard, however, the e:: et-.

lom clon

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M ru "

"inpointed

due to the reflection M nound in tho

mw

t.

A radiation-resistant finiaiurc

. 2.:u w video camera +was

then used to search fczr Go Irn

n cre.& wn located ~in

the same location as ':m p r ,<

a d ina -u

the'aban-

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doned core outlet-flang

M

mc

ttoa

ho location

.of the leak is consir'='

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vster in-the

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other "tell-tales" anC

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which are

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recovered from the cort

sections

of.the tank, and in pt

elds, have

been video inspected at

.n -located.

It is therefore, extr

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the only-

a

leak.

IV

Leak Water Pathway and L

The pathway of the. lea:.

Figure tI. .

The_ water seeps through

1

joint-be-

tween the flange and t

enters the

"tell-tale" through the .,

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previous repairs. It ru:

-

. during the

nich slopes-

' downward) and terminate:

the reactsor

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containment wall over a

The out-

.

board and of the "tell-~

" i;

.:nd was open

-

to atmosphere.

Water

N the' other

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groundwater in the'sul

x.

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Ly into the

" primary pump pit".

TL 1

m

approximately

12,000 gallons in volumr

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mi

Ty . circulat-

ing pump and a 1000'gai m , ' .d

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ei en

ag.,

From the

bottom of-the pump pit, ' u watorM n 13Pted by a. sump pump

to the 1000 gallon tank.

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sen full,=cis

pumped under manual cc

allon main

holding tank.

If necest

'"t'

orage tanks

are available which pro'

, gallons of'

holding capacity.

A pancake has been insne ued

.t n t ~ wthe

end of the

a

"tell-tale" pipe.

. Thin - pancake .i u pa +trat.

by a small

diameter nipple which lec 'i ta an isolat .m vaive and then a

tygon drain directly to t1m rm rit

a

3

int was also

installed.

This would 3i,i.t me

uxf

'a

'oss ratenin

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the event of significan ' turi Mr - f C > c i

weld while

at the same time it. prc o m u L

, xt n a m.

path to'the

sump-pump.

Catastrophic failure o

cover p2.at.u

rat considered

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credible, however, in

e' , of dr# .- e

1 lure of'the

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-

.

,

weld, the vent and drain valves will'be closed.-

This will

limit the water loss from the pool.

If necessary, the 3"

)

emergency pool fill system can be employed to maintain mini-

num water levels in the. reactor tank.-

g-

V

Radiological Characteristics of the Tank Water

N

x

The reactor tank water typically contains several short-

lived and longer-lived components including the following:

.,

Isotone-

Half life

n

Al-28

2.2 minutes

I

Ar-41-

1.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

e

Na-24

15-hours

I-131

8.0 days

La-140

40.22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months

i

Sb-122

2.7 days

-

Sb-124

60 days-

2

Co-58

71 days

!

Ag-110m

250.4 days

Co-60

5.3 years

t

,

i

'

The presence of CO-60, Co-58, and Ag-110m-is generally con-

'

sidered to be - the " signature" of-pool water during routine-

operations. The presence of. Na-24 is generally interpreted

to mean the pool water.is " fresh".

Table 1 lists the measured activities of the prim ry coolant

on November 6th and December 8th, respectively,;and the cal-

culated activities on November 3rd by decay correcting back-

wards from the November 6th-data.

The calculated

multiples / fractions of the restricted and unrestricted Maxi-

.

mum Permissible concentrations are also included.-

'

~

!

i

t

Table 2 lists the measured activities of the water collected

at the outlet of the "tell-tale" on November 17th and Decem-

i

ber 8th.

The tank water and the

"tell-tale" - water have- been

frequently analyzed.

Results vary as a result of operation

of the demineralizer system and of poor mixing of the-tank

when the primary circulation pump is not operated.

The-

"tell-tale" and the primary analyses are generally in agree -

ment consistent with a prompt transit from the pool to the

endof the pipe.

h

<> d .

ng

&.

E '

5

l

__.

.

'

e

.

-

,. .

,

VI

Environmental Analyses

Samples have also been perjodico ty crawn - from nercby storm-

l

receivers

and a sunp in t N.

E o d.

nr1 of the R is -vault

l

'

(hereafter, the "far su pu)-.

N storm receiv u

.ss beta

results are not disting;.

-u ?

Pron bechgrour

w '. 5 an es-

timated sensitivity of

.R

ciccm s ;ce p

(3 sigma

<

,

r.

confidence).

..

Activity has been meas-

a three

nuclides have been ident

co 60,

plus naturally occurring

t-lived

nuclides in these sampic,

ao Co 58

'

<

detected.

If the Co 60

rate in

i

the same manner, the Co

'

..

~

,,

, . - ,

-r sump"

-

samples in the same_isot

R

a-

c r Wuti m, unow ' that

.

the anticipated level oc

I

mics + e 'on sen-

'

sitivity of the gamma sc.

"

i

Radioactivity was ' detect

..-of

the

!

'

leakage during the seve:

. ides w&e

.

s

detected at this time.

this suhp

approximately two years

as of the

,

'

q

same nuclides.

It is t

currently

a

"-

measured in the "far su .

previcibs '

T

-t

-

'

leaks.

The measured levels os

x ~

vary con-

i

e

. .

<

siderably.

The measurea

~

m when - the

I

sump pump last operate--

, . .c t. d.w w

a.

water the

sample is drawn, and pro:

cc?cipitatien evels.- The

i

'

.

measured values have bee;

'

1'

'"

"

?-

'

The water from the "far

e !

Emp know as

-

.

the twin sump where -it i:

Daily gross

beta assays of the twin

istinguish-

able from background.

VII

Water Balance

.

An obvious and primary c mcw- i n vimbe-

o

s: P the . water

ll

leaking from the tank ir app e lag in.thm tc

tank or is

1

otherwise accounted for.

St o f d ' ~ ing ru

have there-

1

fore, been compared:

'

A.

Loss of water from-

_

n

en measured

1

once each shift

<s

vo Ac.aer; uhen

!. t is measured

daily.

Two methc

, '. m oc w'

a

digital level

i

gauge and measurii <

0.sa o

/eference mark

with a meter stic'

I to be.more

accurate since th

.

'de its-nor-

'

.,

.

. _. . . .. . . -

.. -

-.

.-

-

..

.

,

- -

.,

.

..

'

t

,.

.

f

mal span of operation and ' calibration.

One inch - of

1

pool level is equal to'57 gallons of water.

B.

EvaDoration - The-rate of evapot.ation has been measured

by measuring the - water loss from a large tray filled:

,

with- pool water which- floats on the pool surface.

The

total loss of water is determined by applying the ratio.

-

of the tray surface area to tho' total surface area.

!

These measurements were "not performed - until 11/17/89.

,

,,

-

The results have been generally uniform, however, the

1

r

L

pool has cooled significantly since- the leak began.

-The measured values when extrapolated backwards in

time, thus conservatively underestimate : the amount of

,

I

water lost to-evaporation.

l

c.

Pumn Packina Losses - The primary circulatingIpump uses

-

a water lubricated packing seal.

Water normally drips

past this seal and is collected by the sump pump in thel

~

1

1000 gallon' holding tank.

This drip rate has been

measured . periodically since 11/13/89 by placing a'

beaker under the drip and measuring the water collected

over a timed (nominally five minute) interval.

Prior

to the measured: data, average valuess were used to; es-

'

timate water lost through:the pump packing.

D.

Recovery from "Tell-Tale" - - Periodically, the rate of

!

drip from the "tell-tale" pipe has . been fmeasured.

A

beaker is held under-the, drip for'a timed interval =and

the collected volume ist measured by pouring the water

_

into a graduated cylinder.: . This differential data: is

'

integrated assuming that the leak rate is constant from

the-time of measurement until the next measurement

(every four hours except once a day-on weekends)'.

Figures ,II and III' illustrate. the accountability of

,

water lost versus ~ accounted for.

. Water; loss and

I'

recovery data was balanced for;the period 11/5~to 12/10

'

as follows:

Recovered from "tell-tale"t

977 gallons

Accounted by evaporation:

539 gallons

Accounted by pump packing:

99 gallons-

l

Total lost from pool:

1659 gallons

Balance:

Water lost

1659 gallons

Water accounted for

1615 gallons

i

Difference

44 gallons

Percentage

2.6%

,

7

. -

. - . -

- .

. .

-

..

.

- -

.

-

___ _ - _ _ _ _ _ _ _ _ - _ _

_

._.

_ - _ _ .

- _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ . .

.

. __ _ _

- -

..

.

i.

...

-

L

.;-

.

This is considered well within the overall measurement

accuracy of the data '(estimated to be approximately 5

to 8 %).

VIII options for Repair

A.

Lona Term Renair - Eventually the University intends to

dismantle the reactor to-effect a permanent repair.

l

,

We anticipate storage of the reactor fuel in the Hot

-

Call- using a poisoned compact rack design.

' Ax 50.59

l

review of the use of a compact rack will be performed.

l

If necessary, prior approval of the Commission will.be

requested.

An independent contractor will be retained.

to perform the necessary criticality analyses.-

j

,

Once the reactor is dismantled, tho' condition of ' the

.

-tank will be evaluated using Non-Destructive Evalua-

tion.

The crack will be evaluated by appropriate ex-

parts.

Based on the results of the inspection and/or 'the ad-

' ._

vice of welding experts, permanent repair will be af-

facted.

This may include the replacement of the entire

-

,

lower liner by inserting a new one.

It is expected.to

l

p

take'6 to 12 months to plan the repair and enter into

i

the necessary external contracts.

-

1

B.

Short Term Ootions - The _ University would like to-

j

resume. operation of the reactor _until the final repairs

!

can be performed.

Options identified.thus far for'in-

l

teria operation are:

'

Leave the Crack- AloDR - Under this option, no -effort

j

would be made to repair or_ diminish the rate.of

!

leakage.

It is;strongly suspected that it may continue:

l

to slow as the primary pump is operated.

In any' event,.

'

the water balance .is - favorable.

An inde.pandent con-

~

3

sultant is being retained to perform a radiological

i

pathways analysis based on a hypothetical 1 release to

!

.

the groundwater of the-poo1~ water.

It may be necessary-

=

to require approval of the commission to utilize an al-

ternative means of disposal pursuant to 10 CFR~20.106.-

Seal the Leak with ' an oraanic Gasket

IUnder'this?op-

I

tion,

a radiation-resistant gasket ' would be _ used to --

!

seal off the leak temporarily.

'A " top hat"-would'be-

'

used to provide pressure on the. seal.

Please refer to=

Figures IV and~V.which

are preliminary designs.

The

.

weight of the hat would seal the gasket, to the tank -

bottom.

When the water inside bleeds out,

the- full

weight of pool. hydrostatic pressure would be applied

8

l

1

.

. .

.

- - -

--

..

.

_--

.

a

=

.s

.,

,

'

..

_, ,

.

=;

>

(about 1000 pounds) .

.We expect that' the gasket would

last for several months.

'

In order to' install the top hat, a pipe support between

the center > of . the cover plate and. the bottom . of . the

core outlet-line would have to be. removed.- .(See Figure-

VI)- This strut is tack-welded at1the. botton.and simply

,

cradles the bottom of the pipe.

It is believed 1that-

this strut provides- no significant structural support l

-

and is merely an artifact of the assembly of the. plenum

and its. support legs.

Removing the strut may,_in. fact,

w

decrease the leak by reducing the load on the = center of

'

the plate.

- t

L

A structural review of the strut? is in progress.-

[

Several methods - are under ' consideration for remotely'

.

removing the strut.

.

Access to the strut. is hindered by the reactor beam

tubes numbered one through.four.

We are also consider-

-

ing remotely removing these. beam tubes,

i

Seal with Putty - Radiation-resistant 1puttys have:been

used .to seal similar leaks'

However, vendors _ contacted

-

.

so far cannot point to .a . bonding agent which 'has been

successfully utilized underwater on aluminum....This op -

tion is-not currently considered likely..

Underwater Weldina~ .This.optioneis:also'not considered-

likely.

Underwater and - remote welding. of: aluminum

would be extremely difficult.

Thistoption also poses.

significant potential to make the oleakiworse by inad-

.

.vertently burning through the crack.

>

C.

Surveillance - Whatever option -is selected . forl final

review by the commission, additional : surveillance pro-

cedures are anticipated.

We envision, reasonable limits

on process variables such as the, leak rate.and the

radioactivity concentrations.

We - would - adopt addi-

tional

surveillance procedures such as leak -rate

measurements, visual inspection of - the crackf. monitor-

ing of evaporation and pump packing losses,-etc.

Addi

-

tional environmental monitoring requirements ' are also

l-

expected.

l

The exact procedures - to be followed cannot be deter-

mined until the short term . repair option -is - discussed -

and reviewed by the University, outside consultants-and'

the Commission.

,

9

,

i

. - - - . .

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

,,.,,A...,r-

,.n-

- - -

l----,

, - ,

,

.

_

.

_ .

_

_ _ _

_ _.

_

. -.

-- - -..-.

.

,

"

'

-

-. -.

,

!

>

.!

,..

!

Table 1

!

2.718281

-

.

=t

BUFFALO MATERIALS RESEARCH CENTER

.'

Primary Water Sample Comparisons

.

Calculated

I

.

Nuclide

T 1/2 (d)

Concen.

'Concen.

Concen.

-

.

. .

03-Nov-89 : 06-Nov-8 8

08-Dec-8 9

,

Na-24

0.63

1.3E-03

4;8E-05

0.0E+00

1

Co 58

70.80

1.2E-05

0.0E+00

i

<

Co 60

1923.55

3.4E 06

3.4E-06

2;8E-06

Ag.110m

250.40

2.3E-04

-2.3E-04

3;0E-04

. -

Ag 108m 46386.75~

2.8E-06

- 3.4E-06

}

"

Sb 122

2.70

6.0E-05

2.8E-05'

O.0E+00

Sb 124'

60.20

1.8E-05

7.5E-06

La 140

40.22

8.'7E-06

8.3E-06

1.9E-06

Tc 99m

0.25

4.6E-01

1.2E-04-

-0.0E+00-

! 131

8.04

3.1E-05

2.4E-05

0.0E+00-

,

Total-Con /MPCr

3.4E+00

7.7E-01

~3.9E-01

-

,

.

'

Total Con /MPCr %

343.5

77.3

38.7

Total Con /MPCu

2.0E+02

9.1E+01

1.2E+01

i

Total Con /MPCu %

19866.2

9127.1

~1165.9

MPCr = Maximum Permissible ConcentrationJ(in water)

l;

MPCu '= Maximum Permissible Concentration (in water)

.

i

B

Ii

>

,

r

k

s

.

- - .

-

- .

,,n_.

,. , , , .

, , . , , _

, , . - . _ , . . , . .

.,

.. . . . . . - - .

.

-

.

-

.

, .

,

Table 2

2.718281

BUFFALO MATERIALS RESEARCH CENTER

Old Prl, mary Pipe Discharge comparisons

<

Nuclide

T 1/2 (d)

Concen.

17-Nov-89

08-Dec-89

.

'Na 24

0.63

0.0E+00

Co 58

70.80

2.2E-06

0.0E+00-

.

Co 60

1923.55

2.7E-06

1.0E-05

Ag 110m

250.40

1.3E-04

7.3E-05

Ag 108m

46386.75

1.9E-06

1.8E-06

Sb 122

2.70

0.0E+00

Sb 124

60.20

7.3E-06

8.4E-06

La 140

40.22

2.0E-06

8.2E-07

Tc 99m

0.25

1.2E-06

0.0E+00

,1 131

8.04

1.1E-06

0.0E+00

Total Con /MPCr

2.0E-01

1.2E-01

Total Con /MPCr %

20.0

12.4

I

Total Con /MPCu

9.2E+00

3.7E+00

Total Con /MPCu %

917.5

369.4

MPCr = Maximum Permissible Concentrat ion (in water)

- MPCu = Maximum Permissible Concentration (in water)

l

.

-

.

e

l

.

. . -

..

_

.

. .

- -

.

. - -

,

- . .

FIGURE I

{

.

%

2

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.

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k

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FIGURE II

".

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.

.,ij

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? <y u._;. .. _ =.2 3cy. - ;.3

-

+ 'l

..

WATER LOSS AND

_

.

i

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i

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P

RECOVERY vs. TIME

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1800

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LOSS

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