IR 05000193/1978005
| ML19308A225 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 11/15/1978 |
| From: | Greenman E, Mccabe E, Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19308A224 | List: |
| References | |
| 50-193-78-05, 50-193-78-5, NUDOCS 7901040138 | |
| Download: ML19308A225 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-193/78-05 Docket No.
50-193 License No.
R-95 Priority
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Category F
Licensee:
Rhode Island Atomic Enerav Comission South Ferry Road Narragansett, Rhode Island Facility Name:
RIAEC - Nuclear Science Center Inspection at: Narragansett, Rhode Island Inspection conducted: October 25-26, 1978 Inspectors:,
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7A-T. F. Stetka# Reactop Inspector date signed Yb-U JN
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E. G. Greenga g ReacttJ Inspector
' date signed date signed Approved by:
A G d Otl+d i l /4 l7F E. C. McCabe, Jr., Lnier, deactor Projects date signed Section No. 2, RO&NS Branch Inspection Summary:
Inspection on October 25-26, 1978 (Report No. 50-193/78-05)
Areas Insoected:
Routine, unannounced inspection of procedures, surveillance, experiments, IE Circular followup, review of Annual Report, and turnover of project inspector responsibility.
Facility tours were conducted.
The inspection involved 16 inspector-hours onsite by two NRC regional based inspectors.
Resul ts : No items of noncompliance were identified.
7901040['N^
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Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted
- A. DiMeglio, Director of Operations M. Doyle, Assistant Director of Operations
- A. Quirk, Chairman, RI Atomic Energy Commission The inspector also contacted other licensee personnel including operation's staff personnel.
- denotes those present at the exit interview.
2.
Review of Annual Report The Annual Report for the period July 1, 1976 to June 30, 1977, for the RIAEC Research Reactor was reviewed.
This review verified that the required information has been reported.
No inadequacies were identified.
3.
Facility Tour The inspectors toured various areas of the facility including the control room; equipment rooms; reactor room operating floor; process areas; and, exterior areas to determine the general state of clean-liness, housekeeping and adherence to fire protection guidelines.
Minimum licensed operator complement requirements were verified.
Nuclear instrumentation operability requirements, flow limits and power level parameters were also confirmed.
No unacceptable conditions were identified.
4.
Facility Procedure Review a.
The inspectors reviewed the licensee's administrative guidance that is contained in a procedure entitled " General Considerations" dated March 1, 1978.
This review verified that responsibilities of operators and senior operators were established via procedures and that procedure changes, approvals and level of subsequent
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review were covered.
No inadequacies were identifie.
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b.
The inspectors reviewed the following procedures for technical adequacy and conformance with Technical Specification require-ments:
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Reactor and Control System Checkout;
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Routine Startup; and,
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Shutdown (Section 9.1, Normal Shutdown).
The inspectors " walked through" the Routine Startup and Normal Shutdown procedures and verified step-by-step that the pro-cedures accomplished their intended purpose and were the latest revision.
No inadequacies were identified.
5.
Limiting Conditions of Operations (LCO) Review The following operating conditions were observed during the plant tour and record reviews:
Parameter TS Limit Observed Value Primary Coolant Flow
> 1200 gpm 1680 gpm
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Reactor Thermal Power 2 MW l.9 MW Pool Water Level
> 23 ft. above
> 23 ft. above Core Core Primary Coolant Inlet 5 ll50F 920F Temperature Primary Coolant Outlet 5,1250F 96 F Temperature Pool Surface Radiation
< 10 MR/HR 4.5 MR/HR Level Fuel Elements in Maximum of 35
Core Containment Building
> 0.5" H 0 0.5" H O
2 Differential Pressure No items of noncompliance were identifie *
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6.
Surveillance Review The following surveillance procedures were reviewed to verify that the procedures were adequate to accomplish their intended function and meet Technical Specification requirements:
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Appendix D of " Procedure for Determining Rod Drop and Magnet Release Time" and data recorded on March 23, Juna 28, and September 5,1978 for Control Rod Scram Times and Withdrawal Rates, and Regulating Blade Withdrawal Rate;
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Standby Power System Check List and data for the Confinement Building Retest performed durirg the period of February 23 to October 19, 1978;
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Pre-Startup Check Sheet - Monthly Addendum and data recorded for the period January 3,1978 through October 4,1978;
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Water Analysis Data for Secondary System and data recorded for secondary water pH for the period January 6, 1978 through October 23, 1978; and,
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Water Analysis Data for Primary System and data recorded for primary water pH and conductivity for the period January 4.
1978 through October 20, 1978.
During this review the inspectors noted that the Resistivity Bridge that is used to measure the primary water conductivity has been out of service since March 15, 1978 and that the primary water con-ductivity was being determined by other analytic methods.
The inspectors discussed the availability of the Resistivity Bridge with licensee representatives who stated that the bridge would be repaired or replaced.
This item will be examined in subsequent
'nspections.
7.
Experiments The inspectors selected sampie irradiations being conducted to confirm that experiments were approved by the Reactor Utilization Committee, that they did not constitute an unreviewed safety question and that reactivity effects were considered and within limits.
The bulk of experimental activity involves usage of the pneumatic rabbit.
Exper-imental shielding for facilities, hoods, and posting was also examine '
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The licensee's documentation for experiments Nos. 24, 36, 45, 49 and 58 were reviewed in detail.
Negligible reactivity effects were ob-served.
Health Physics review of experiments is provided when applicable. No unacceptable conditions were identified.
8.
IE Circulars Which Require No Response Inspection was performed for the following IE Circular to verify whether: the Circular was received by licensee management, review for applicability was performed, corrective action (if any) was initiated and/or evaluated and that supporting documentation was available.
Findings were as follows:
IE Circular 77-14 " Separation of Contaminated Water Systems from Non Contaminated Plant System."
One potential pathway with the potable water system was identified.
Inspection confirmed that the licensee had installed a check valve to minimize potential for contamination of domestic water.
Dis-cussion with a cognizant licensee representative indicated that valve checks would be incorporated into monthly check lists.
This item will be reviewed for this during a subsequent inspection.
9.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on October 26, 1978.
The inspector summarized the scope and findings cf the inspection as they are detailed in this report.