IR 05000193/1985002

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-193/85-02

ML20137M875
Person / Time
Site:	Rhode Island Atomic Energy Commission
Issue date:	11/29/1985
From:	Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Dimeglio A RHODE ISLAND, STATE OF
References
NUDOCS 8512040024
Download: ML20137M875 (2)

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Docket.No: 50-193

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Rhode Island Atomic Energy Commission

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ATTN: .Dr. A. Francis DiMeglio ,

Director '

' Nuclear Science Center South Ferry Road Narragansett, Rhode Island 02882 Gentlemen:

Subject: Inspection Report No.'50-193/85-02 i

This refers to your letter dated September 6,1985, in response to our letter dated August 12, 198 Thank you for _ informing us of the corrective and preventive actions documented 9 in your letter. These actions will be examined during a future inspection of

_your licensed progra ,

, -Your cooperation with us is appreciate

Sincerely, Original signed B78

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' Thomas T.' Martin, Direct ivision of Radiation Safety and Safeguards

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cc:

Professor G..Seidel, Commissioner, RIAEC

'Rev. W. Murtaugh, 0.P., Commissioner, RIAEC John Pascalides, Commissioner, RIAEC Dr. V; C'. Rose, Commissioner Dr. S. J. Pickart, Physics Department Public Document Room (PDR)

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

State of Rhode Island hO DO 0FFICIAL RECORD COPY RL RIAEC 85-02 - 0001. /05/85 OL.1[

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Rhode Island Atomic Energy Commissien 2

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Region I Docket Room (with concurrences)

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RI:0RSS RI:DRSS RI: RSS RI ['RSS of 1/mmb Sh Bellamy Ma in 11/Sd85 11/pb/85 11/ 85 j7g /85 OFFICIAL RECORD COPY RL RIAEC 85-02 - 0002. /05/85 l

O TATE OF RHODE ISI.AND AND PROVIDENCE PLANTATIONS

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RHODE ISLAND ATOMIC ENERGY COMMISSION Nt. clear Science Center South Ferry Road Narragansett, R.I. 02882-1197 September 6, 1985 U. S. Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, PA 19406 Attention: Thomas T. Martin, Director Division of Radiation Safety

& Safeguard Gentlemen:

Please refer to the notice of violation in inspection report 50-193/85-02, dated August 12, 1985. This violation consists of the inability of the Nuclear Science Center to provide the manu- '

facturer's documentation for the efficiency of the absolute filter which are part of the emergency clean up syste These filters were provided by the manufacturer as an integral part of a clean up filter system in 1963 during the construction phase of the facility. This efficiency specification was part of the equipment specification and the manufacturer's documentation ,

was reviewed before installation of the system. In addition, be-fore issuance of an operating license, the USAEC inspected this facility to insure compliance with constructign requirement It is therefore reasonable to assume that the fil'ter efficiency was one of the items checked by USAEC for compliance before issuing an operating license, especially since the clean up system was an addition to the original facility design and was a well documented ammendment to the original construction permit. We cannot, however, document the manufacturer's certification nor the inspection by the USAEC because we cannot locate these records some twenty-two years late The efficiency of this filtering system was reviewed during a previous inspection on September 13, 1971. A copy of the inspection report is attached. As a result of the inspection, we performed a test on October 4, 1971. The test repcrt and results are attached showing an efficiency of 99.986% for the system. It is again rea-sonable to assume that this test was reviewed during the next in-spection. However, the report of the next inspection, September 7, 1972, does not contain the information. A copy of this inspection

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report is attache V rA o i- r fA p -c 7 - .

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Thoma3 T. Martin, Dir ctor -2- S:pterbar 6, 1985

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Following the most recent inspection, June 11-12, 1985, we j\

~ arranged to have the filters tested in place. The test was per-formed by B & B Testing Company of Waltham, Massachusetts on August 13, 1985. Their test of the system showed no penetration of test smoke. Because of the sensitivity of the monitoring instruments, their result is a penetration of 0.01%.

We believe that this penetration test, together with the testing done in 1971, assures that the filters do meet the techni-cal specification The reoccurance of this type of violation will be prevented by a better record retention system which has been in place for several year ' Ve y truly yours,

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A. Francis DiMeglio Director AFD:pb Enclosures (3)

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SEP 7 1972 Rhode Island Atomic Energy Commission Attention: Dr. A L. Quirk, Chairman Docket No. 50-193 Rhode Island Nuclear Science Center Narragansett, Rhode Island 02882 Centlemen:

This refers to the inspection conducted by Mr. K. E. Plumlee and Mr. E. ,

Loibl, of this office on June 26, 27, and 28, 1972, of operations authorized by AEC License No. R-95, and to the discussions of our findings held by Mr. Loibl and Mr. Plumlee with Dr. Quirk and Mr. DiMeglio of your staff at the conclusion of the inspectio Areas examined during this inspection included: (for the period June 1971 to June 1972) reactor operation logs, records of fuel management, sample irrad-intions, personnel exposures to radiation, area health physics surveys, radioact'ive releases to the environment, and audits of operations; and the

! status of operating procedures, emergency procedures and facility security measure ,

Within these areas..the inspection consisted of selective. exam- "

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inations of procedures and representative records, interviews with facility n: personnel, and obcervations by our inspector ~

During this inspection it was found that certain of your activities appeared

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• to be in noncompliance with AEC requirements. The items and references to

', ,the pertinent requirements are listed in the enclosure to this letter. Please

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? - provide us within 20 days, in writing, with your comments concerning these

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items, any steps which have been or will be taken to correct them, any steps that have been or will be taken to prevent reth:rence, and the date all corrective actions or preventive ineasures wert or will be complete . Should to discuss you have ther;. any with yo questions concerning this inspection, we will be pleased

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Sincerely yours,.

m .O es P. O'Reilly Dir ctor Enclosure:

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Description,of Noncompliance Items '

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ENCLOSURE i

i Description of Noncompliance Items Rhode Island Atomic Energy Commission Rhode Island Nuclear Science Center Narragansett, Rhode Island 02882 License No. R-95~

Certain activities under your license appear to be in noncompliance with license requirements as indicated below: Paragraph K.3.d of the Technical Specifications to License No. R-95 states in part, " Corrective action shall be taken to avoid exceeding the pH limit . . . 5.5 to 7.5."

Contrary to the above, all measurements of secondary coolant pH recorded from July 13 to July 23, 1971 were in a range of 7.6 to ~ Paragraph J.1 of the Technical Specifications to License No. R-95 states ,

that the functions of the Reactor Utilization Committee are, in part,

"c. Review at least annually the operating and emergency procedures and the overall radiation safety aspects of the facility," and,

"The Reactor Utilization Committee shall maintain a written record of its findings regarding the above." .

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Contrary to the above,'a review of records indicated that the Reactor Utilization Committee did not review procedures and record its findings within the 12-month interval preceding t; bis inspectio .

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e7o BROAD eTREET NEWARK. NEW JERSEY o7toa SEP 131971 Rhode Island Atomic Energy Commission Docket No. 50-0193 ATTN: Dr. Arthur L. Quirk, Chairman Rhode Island Nuclear Science Center Narragansett, Rhode Island 02882 Gentlemen:

This refers to the inspection conducted by Mr. J. J. Rizzo of our Bethesda, Maryland office on June 22 and 23,1971, of operations authorized under AEC Operating License No. R-95 and to the discussions of our findings held by Mr. Rizzo with Mr. A. F. DiMeglio of your

. staff at the conclusion of the inspectio Areas examined during the , inspection included the following subjects for the period since May 6,1970: reactor operations, facility ( '-

- operating procedures and administrative controls, performance of the Reactor Utilization Comunittee, reactivity and core physics measurements, personnel exposures and radiation surveys, reactor maintenance, and liquid and gaseous releases. Within these areas,

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the inspection consisted of selected examinations of procedures and representative records, interviews with plant personnel and observa-I tions by our inspecto Within the scope of this inspection, no items of noncompliance with

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AEC requirements were identifie As discussed with Mr. DiMeglio, we understand that you plan to test the efficiency of the absolute filters located in the scrubber system within the next three months and that arrangements will be made to have an independent audit performed of your operations on an annual basis. These items will be reviewed during our next inspectio No reply to this' 1stter is necessary; however, should you have any

, questions concerning this inspection,.we vill be pleased to discuss

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j than with yo .

Very truly yours,

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Dpector

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ec: A. F. DiMaglio ,

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EfficiencyTestofEmerg3ncyAbsolute'F11gers ,

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On.10-4-71 the emergency filters were tested with DOP smoke h

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'to determine the efficiency. The smoke ,,.ierato,r was,) positioned to discharge the smoke into the intake to the cleanup'. system on the main floor of jhe reactor room. Thai flow in the cleanup system was reduced by covering the in.take to the system except for a small opening. The cooke was introduced through.this openin The particle detector was calibrated at the upstream side of

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the filters. The baseline reading was set at 70 5 (~100 5

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base'line cou'Id not be achieved because with the gain set to give

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1005 the dark current from the phototube gave a larg.e signal which

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could not be zeroed with the straylight addustment). .With the

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instrument calibrated the air downstream of the filters was (ntroduced into the detector'and the 5 penetration was measure '

The reading on the meter was.less than 0.01 5. With'705 as the

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E= 1 ' E= 1 'O.4 014

., E= .99986 or 99 986 5

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