ML102230416

Rhode Island Atomic Energy Commission Ltr. Enclosing Annual Report Required by Rinsc Technical Specifications (Section 6.8.4)

ML102230416
Person / Time
Site:	Rhode Island Atomic Energy Commission
Issue date:	07/30/2010
From:	Bicehouse H State of RI, Atomic Energy Comm
To:	William Kennedy Office of Nuclear Reactor Regulation
References
Download: ML102230416 (7)

Text

STATE OF RHODE ISLAND AND PROVIDENCE PLANTATIONS RHODE ISLAND ATOMIC ENERGY COMMISSION Rhode Island Nuclear Science Center 16 Reactor Road Narragansett, RI 02882-1165 July 30, 2010 Docket No. 50-193 Mr. William Kennedy, Project Manager Non-Power Reactors, Decommissioning and Environmental Project Directorate Division of Reactor Projects - III/IViV U. S. Nuclear Regulatory Commission (NRC)

Washington, DC 20555

Dear Mr. Kennedy:

This letter and enclosures constitute the annual report required by the RINSC Technical Specifications (Section 6.8.4). Enclosure 1 provides reactor operating statistics. Enclosure 2 provides information pertaining to inadvertent reactor shutdowns or scrams. Enclosure 3 discusses maintenance operations performed during the reporting period. Enclosure 4 describes changes to the facility carried out under the conditions of Section 50.59 of Chapter 10 of the Code of Federal Regulations. Lastly, Enclosure 5 summarizes the radiological controls information. If there are any questions regarding this information, please call me at 401-789-9391.

Sincerely, H. J. Bicehouse Assistant Director for Radiation and Reactor Safety Enclosures (5) cc:

Mr. Jack Donohue, USNRC Region I Dr. John J. Breen, Chairman NRSC Dr. Stephen Mecca, Chairman RIAEC Dr. Anthony Nunez, RIAEC Dr. Peter Gromet, RIAEC Dr. Andrew Kadak, RIAEC Dr. Bahram Nassersharif, RIAEC 4oP.,

ENCLOSURE 1 Technical Specifications Section 6.8.4.a Month Year Reactor Energy Energy Critical Generated Generated (Hours) (MWhrs) (MWdays)

July 2009 21.75 33.10 1.38 August 2009 32.40 46.22 1.93 September 2009 39.53 64.57 2.69 October 2009 84.67 136.17 5.67 November 2009 61.03 96.03 4.00 December 2009 46.32 70.90 2.95 January 2010 47.27 79.00 3.29 February 2010 54.72 90.90 3.79 March 2010 75.93 103.45 4.31 April 2010 79.65 129.10 5.38 May 2010 34.25 48.47 2.02 June 2010 24.77 26.17 1.09 2009-10 Totals 602.29 924.08 38.50 Total Energy Output since Initial Criticality: 62,966.63 MWhrs or 2,623.61 MWdays.

ENCLOSURE 2 EMERGENCY SHUTDOWNS AND SCRAMS The following is a listing of the emergency shutdowns and inadvertent scrams that occurred during the 2009-2010 reporting period. This information is required by Technical Specification 6.8.4.b.

Date Run Logbook Page Description Deliberate/Inadvertent No.

7/14/09 8367 57 6 Scram for tour Deliberate 8/4/09 8372 57 11 Scram for tour Deliberate 9/10/09 8382 57 22 Scram for shutdown to move fuel Deliberate element 12/3/09 8421 57 61 Scram for experiment Deliberate 12/29/09 8428 57 70 Scram for tour Deliberate 1/27/10 8436 57 78 Scram for tour Deliberate 3/16/10 8454 57 96 Scram for tour Deliberate 3/17/10 8455 57 97 Operator error Inadvertent 3/31/10 8463 57 105 Scram when primary pump shut off Deliberate 4/10/10 8467 57 109 Scram for tour Deliberate 4/14/10 8470 57 112 Scram for tour Deliberate 4/20/10 8473 57 115 Scram for tour Deliberate 5/3/10 8481 57 123 Scram by trainee Inadvertent 5/7/10 8484 57 126 Scram for tour Deliberate 5/14/10 8486 57 128 Scram for tour Deliberate 5/18/10 8487 57 129 Scram for tour Deliberate 5/25/10 8489 57 131 Scram caused by blade drop Inadvertent 6/26/10 8500 57 142 Scram for tour Deliberate Table includes planned scrams, ("deliberate"), and unplanned scams, ("inadvertent").

ENCLOSURE 3 Technical Specification 6.8.4.c requires a listing of the major maintenance operations performed in the 2009-2010 reporting period including their impact upon the safe operation of the reactor and the reasons for the corrective maintenance. No major maintenance operations were performed during this reporting period.

ENCLOSURE 4 FACILITY CHANGES - IOCFR50.59 REVIEW Technical Specification 6.8.4.d requires that we provide a listing and description of any 10 CFR 50.59 evaluations conducted during the 2009-2010 reporting period. There was one change requiring a 10 CFR 50.59 evaluation during this reporting period: moving the pneumatic sample transfer system (aka "Rabbit" System) send/receive stations and their control boxes from confinement to Room 305. The change required a penetration of the confinement wall and preservation of the differential pressure between the office area and the confinement. The "Rabbit" System blower continues to be controlled by the reactor operator in the control room.

ENCLOSURE 5 RADIOLOGICAL CONTROLS

1. Environmental Surveys outside the Facility - Technical Specification 6.8.4.e Quarterly OSL 1 badges are deployed outside the reactor building in three separate locations. The general public does not frequent these locations and therefore occupancy factors may be used to approximate annual dose. The allowable external dose rates must be below 50 mrem per year. The quarterly doses in units of mrem are shown in the table below.

LOCATION 3 RD QTR 2009 4 TH QTR 2009 1 sT QTR 2010 2 ND QTR 20102 Northeast Wall 18 Lost 12 16 Demineralizer 73 151 126 115 Door Heat Exchanger 3 14 2 7 Door These areas are in locations where access is limited. Consequently, the general public will not frequent these areas, and appropriate occupancy factors can be used to approximate annual dose. Assuming that the maximum time that a member of the general public would be present in one of these locations is 15 minutes per day, an occupancy factor of 0.01 can be used to obtain the annual dose that would be received by a member of the general public, in any of these areas.

The dose rate in the Northeast Wall area is due to storage of RAM, and is present regardless of reactor operation. The dosimeter placed on this wall was lost during the fourth quarter of 2009. We will assume that the dose measurement was the same as the previous quarter, i.e. 18 mrem. Applying the occupancy factor, the annual dose to an individual in this area would be 0.64 mrem over the course of last year. The annual dose rate at the Demineralizer and Heat Exchanger Doors is dependent on the operations schedule of the reactor. Ignoring the fact that the dose rate is not present 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day, and applying the occupancy factor of 0.01, the annual dose that would be received by an individual at the Demineralizer Door would be 4.65 mrem. Likewise the dose received at the Heat Exchanger Door would be 0.26 mrem. The variations from quarter to quarter and from previous reports were due in part to movements of items within the reactor building during the fiscal year.

2. Annual Exposures Exceeding 500 mrem - Technical Specification 6.8.4.f There were no personnel exposures greater than 500 mrem.

3. Radioactive Effluents - Technical Specification 6.8.4.g A. Individual gaseous effluent concentrations for each reactor operation are recorded on the Monthly Information Sheets (Form NSC-78). The concentration of radioactive materials in the effluent released from the facility exhaust stacks shall not exceed IE+05 times concentrations specified in IOCFR20, Appendix B, Table II, when averaged over time periods permitted by IOCFR20. 3 Gamma spectroscopy of stack gas samples has shown that the principal gaseous effluent is Argon-

41. The maximum concentration for this principal contaminant permitted under that Technical Specification is 1E-8 times I E5 or IE-3 jtCi/cc. Concentrations released during the year were less than 0.02 of that limit.

The total Argon-41 release during the reporting period was 129.36 curies. The calculated effective dose equivalent for this release is 2.7 mrem/year (COMPLY Code).

'Optically Stimulated Luminescence 2 Landauer reads the OSL dosimeters to I mrem.

3 Technical Specifications, Section 3.7.2.

ENCLOSURE 5 RADIOLOGICAL CONTROLS B. Liquid effluent concentrations released to the sewer are documented on the Sewer Disposal Record (Form NSC-52) and/or the Liquid Release Record (Form NSC-17). During the reporting period, one discharge was made to the sewer. On May 11, 2010, 30 gallons of water from the RINSC Retention Tank were discharged to the sewer. The discharge contained 32.968 gCi of Tritium, 0.0633 giCi of Cobalt-60, and 0.025 gICi of Antimony-124. The radioisotope concentrations discharged were Tritium 2.90 E-04 gCi/ml, Cobalt-60 2.92 E-07 pgCi/ml, and Antimony-124 2.24 E-07 pCi/ml. Using the sum of the fractions rule, the discharge was 0.042 (4.2%) of the discharge limit.