IR 05000199/1979002
| ML19249D672 | |
| Person / Time | |
|---|---|
| Site: | 05000199 |
| Issue date: | 06/25/1979 |
| From: | Architzel R, Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19249D662 | List: |
| References | |
| 50-199-79-02, 50-199-79-2, NUDOCS 7909250185 | |
| Download: ML19249D672 (8) | |
Text
{{#Wiki_filter:' - - - . .. . U.S. NUCLEAR PEGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-199/79-02 Docket No. 50-199 License No. R-94 Priority: Category: H -- Licensee: Manhattan College Corporation Bronx, New York 10471 Facility Name: Zero Power Reactor Inspection at: Bronx, N2w York Inspection conducted: April 25-26, 1979 Inspector:,[[ h
M R. Architzq)QPReacebr Inspector date signed Approved by: ' '
- I/79
'* p.~C. McCabe, Jr. gChief, Reactor 'date signed A Projects Sectio,n No. 2, RO&NS Branch Inspection Summary: Inspection on April 25-26, 1979 (Report No. 50-199/79-02) Areas Inspected: Routine, unannounced inspection of facility operations including: administration and organization; operations; logs and records; surveillance testing; radiation protection; experiments and tests; and, emergency plans. Licensee action on previous inspection findings was reviewed and a.acility tour was conducted.
The inspection involved 10 inspector-hours on site by one NRC inspector.
Results: Of the seven areas inspected, one item of noncompliance was identified.
(Deficiency - failure to post Emergency Plan, paragraph 8).
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. . " DETAILS 1.
Peregns Contacted Dr. J. Augustus, Assistant Professor (Reactor Operator)
- Brother G. Kane, FSC, Chief Reactor Supervisor
- Dr. B. Koplik, (Reactor Administrator)
Chairman, Mechanical Engineer..ng
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Noncompliances (77-01-02 and 78-01-02): Failure to record data on material irradiations. The licensee responded to this item in letters dated April 7 and 14, 1977, and March la, 1978. No additional examples of failure to record the required data were identified during this inspection.
(Closed) Noncompliances (77-01-01 and 78-01-01): Failure to conduct rod drop time measurements following an extended shutdown. The licensee responded to this item in letters dated April 7 and 14, 1977, and March 13, 1978.
No additioaal examples of failure to perfor.n rod drop tests were identified during this inspection.
(Closed) Noncompliance (78-01-03): Operation with the Gamma Recorder Inoperable. The licensee responded to this item in a letter dated March 13, 1978.
No additicaal examples of operation with the gamma recorder or other required instruments inoperable was identified.
(Closed) Noncompliance (78-01-04): Failure to Log Data During Periods of Operation Greater than One Hour. The licensee responded to this item in a letter dated March 13, 1978. The inspector verified that the format for the committee meetings had been changed to require auditing of operations greater than one hour.
During a record review the inspector did not identify any periods of operation greater than one hour in length.
(Closed) Unresolved Item (78-01-05): Verify Technical Specifications Available, Including Revisions. The licensee has compiled a complete historical license file for operator use, including all license appli-cations, changes and amendments.
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3.
Administration and Organization a.
The licensee's organization remains as described in NRC Inspection Report 78-01 with the exception of the licensing of Dr. J. Augustus as a Reactor Operator.
Dr. Augustus is scheduled to take the SRO examina-tion.
The Chief Reactor Supervisor (CS0) plans to retire soon and states that the present intention is to not renew his license when it expires in 1980. No unacceptable conditions were identified.
b.
The operator requalification program is not required to be presently implemented because there is only one licensed operator in addition to the CSO and this individual plans to be reexamined by the NRC for a SRO license. No unacceptable conditions were identified.
c.
The inspector reviewed minutes of Reactor Operations Committee meetings held the following dates: - Date Number of Attendees 4/25/78
, 10/23/78
4/11/79
Meetings are generally held twice yearly in April and October and include a routine checklist review of facility records and surveillance tests required by the license or Technical Specifications.
No unaccept-able conditions were identified.
4.
Operations, Logs and Records During calendar year 1978, the facility was typically operated during a.
the spring and fall semesters for a period of one hour or less per week in support of laboratory course work.
, b.
The inspector conducted a tour of the facility in company with a licensee representative.
No problems were identified with respect to facility access controls, physical security, cleanliness, control of fire hazards, or storage of licensed material.
The inspector reviewed the following facility logs and records covering c.
the periods indicated: i024
- 50
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-- Reactor Console Checkout Sheet Nos. 434-463, July 1978 - April 1979.
Maintenance Log, March 1978 - April 1979.
-- Reactor Operation Log Book, April 1978 - April 1979.
-- -- Health Physics Record Book, February 1978 - April 1979.
Reactor Operating Committee Minutes, April and October 1978 and -- April 1979.
During the review of the maintenance log the inspector observed drawings and procedures associated with a modification of the demineralizer performed in April, 1979. The change incorporated upward flow through . the resin bed and use of polyester fiber bags between aluminum sheets to hold the resin (previous by glass wool). The licensee stated that completion of this chan e would be reported pursuant to 10 CFR 50.59(b).
o The inspector had no further questions in this area.
5.
Surveillance Testing The licensee's procedures for conducting surveillance tests required a.
by Technical Specifications are contained in the Maintenance Log and are referenced during subsequent tests.
b.
Technical Specification J.4 requires that the moderator be sampled for fission product activity once per semester.
The following moderator sample results were reviewed: Date Activity 4/5/78 No detectable Alpha,4 Beta or Gamma (1000 cc sample less than 10- uC) 10/29/78 No detectable Alpha, Beta or Gamma (1000 ce sample less than 5 x 10 -3 uC) No unacceptable conditions were identified.
Technical Specification J.6 requires a sample check of the c.
lucite hold-down rods be made for evidence of radiation damage once each semester.
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The check consists of removing the lucite rod and using a bench apparatus to measure the modulus of rigidity to ascertain whether significant chcnges in the rods have occurred.
The modulus of rigidity test was conducted on the following dates: April 18, 1979; and, -- -- October 23, 1978.
Test results indicate no degradation of the lucite hold-down rods.
d.
Technical Specification I.4 states, that the time for rod insertion on a scram shall be less than 1.0 second and requires verification of the time every 6 months and whenever the facility has been shutdown for more than 2 months.
Licensee records indicate scram times were determined on the following dates: Date Shim Rod (sec) Reg. Rod (sec) April 18, 1978 0.503 0.474 October 19, 1978 0.51 0.49 February 16, 1979 0.385 0.35 6.
Radiation Protection The inspector's review of personnel radiation exposure records indicated a.
no significant exposure during calendar year 1978 to facility perqonnel.
The following Landauer Radiation Dosimetry Reports were reviewed.
March 1978 - February 1979 Monthly Reports (3 individuals routinely involved in reactor operation) Fall Semestar, 1978 (40 students) Spring Semester, 1978 (5 students) All reported exposures were below the minimum amount measureable.
b.
The inspector reviewed records of calibration (certifications performed by Nuclear Diagnostic Laboratories) for the following portable radiation monitoring instrumentation.
. A 1024.;J2
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. -- G-M Survey Meter Model 2612, Manhattan Identificatiou No. (MID) 17988, performed October 5, 1978.
-- Neutron Survey Meter (Probe Model 2646) MID No. 17989, performed October 5, 1978.
-- Ionization Survey Meter, Model 2586, MID No. 17987, performed October 5, 1978.
No unacceptable conditions were identified.
c.
The inspector reviewed records of sealed source wipe tests, area surveys, contamination surveys, and air samples conducted on April 29 and October 31, 1978. Areas surveyed included the suberitical facility, ZPR room, counting room, lecture room, and graphite pile. All wipes were less than.005 uC (Alpha, Beta and Gerra) detectable.
No unacceptable conditions were identified.
d.
The inspector's review of posting requirements in accordance with 10 CFR 19.11 indicated that all required items were posted or available to facility personnel.
c.
Methods of Releases and IEC 77-14, Separation of Contaminated Water The inspector checked the facility for unmonitored/ unauthorized discharge paths to the environment. No unmonitored/ unauthorized paths ~ were identified. The inspector also discussed the referenced IE ~circular and provided a file copy for the licensee. Discussion of applicable aspects of the circular determined that in addition to the low probability of the ZPR water becoming contaminated, the only connection between the pool and potable water is a manually inserted piece of tygon tube. This connection is only made up when pool water addition is necessary.
No unacceptable conditions were identified.
7.
Tests and Experiments The inspector reviewed the following tests and experiments conducted during the previous year.
a.
Indium fail irtadiations had been conducted on November 14 through 30, 1978. A total of 91 foils were irradiated which are used in determining flux distribution. This determination is one of the stcndard teachning 1024
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experiments listed in Technical Specification E.4.d(1), as are all other experiments conducted during the year.
No unacceptable conditions were identified.
b.
Void coefficient of Reactivity tests (and associated Experimental Proposal approved by NSC at the October,1978 meeting).
Date Measured Coefficient * 3/19/79 3.86 x 10E-6 2/16/79 8 x 10E-6 3/13/79 ' 8.28 x 10E-6 3/15/79 6.47 x 10E-6
- Units = Delta K per cc of void.
No unacceptable conditions were identified.
c.
Gamma Ray Spectrum Experiment. The inspector reviewed the Experi-mental Proposal dated March 2, 1970. The physical arrangement consists of a voided aluminum standpipe with a 3.5" I.D. 10 feet in length standing vertically in the core reflector approximately 8" from the core.
The inspector questioned the licensee concerning the potential worth of the void due to either removal or flooding. The licensee stated that this had not been determined, however, a determination would be made during the next reactor startup. This item (79-02-01) is unresolved.
8.
Emergency Plans Technical Specification E.5 requires posted written emergency and evacuation instructions and specifies that these procedures be reviewed annually by the Reactor Hazards Committee and revised as necessary.
The emergency procedure was reviewed by the Reactor Saf eguards Committee on October 23, 1978.
The inspector identified that the Emergency Procedure was not posted, both inside and outside the ZPR Room, as required on April 25, 1979. This is an item of noncompliance (79-02-02). 9.
Unresolved Item An item about which more information is required to determine acceptability is considered unresolved. Paragraph 7.c contains an unresolved item.
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10.
Exit Interview At the conclusion of the inspecti:n the inspector held a meeting (see Paragraph 1 for attendees) to discuss the inspection scope and findings.
The item of noncompliance and unresolved item were identified.
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