IR 05000199/1986001
| ML20205T308 | |
| Person / Time | |
|---|---|
| Site: | 05000199 |
| Issue date: | 06/09/1986 |
| From: | Elsasser T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20205T300 | List: |
| References | |
| 50-199-86-01, 50-199-86-1, NUDOCS 8606130101 | |
| Download: ML20205T308 (10) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGION I ;
Report N /86-01 Docket N License N R-94 Category H Licensee: Manhattan College Corporation Bronx, New York 10471 Facility Name: Zero Power Reactor Inspection at: Bronx, New York Inspection conducted: May 13-15, 1986 Inspectors: T. Rebelowski, Senior Resident Inspector Millstone Unit 1 & 2 Approved by: & kO, k d 9/SC T. C. Elsasser, Chief, Rehetor Projects Section 3C Date Inspection Summary: Inspection on May 13-15, 1986 (Report No. 50-199/86-01)
Scope: Routine, unannounced inspection (20 hr.) of facility operations. The reac-tor was in an overhaul outage with all fuel elements removed. The open vessel was drained and cleane Results: No violations were identified. The inspector found a need for improving maintenance and surveillance procedures (Detail 9.e).
8606130101 860610 PDR ADOCK 05000199 G PDR
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TABLE OF CONTENTS P. age Plant Status.......................................................... 1 Licensee Action on Previous Inspection Findings....................... 1 Organization.......................................................... 2 Facility Tour......................................................... 2 Facility Operations................................................... 2 NRC Order on Fue1..................................................... 4 Operator Requalification Program...................................... 4 Operating License Renewa1............................................. 5 Maintenance 0utage.................................................... 5 10. Radiation Exposure Reports............................................ 6 11. Emergency Planning.................................................... 7 12. Material Balance Report............................................... 7 13. Shim Rod Anoma1y......................................................
14. Experiments........................................................... 7 15. Use of Low Enrichment Fue1............................................ 7 16. Management Meeting.................................................... 8 1' i 1 1
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DETAILS 1. Plant Status The Zero Power Reactor at Manhattan College started a maintenance outage on April 25, 1986 and was dismantled during this inspection. Completion of maintenance is scheduled prior to May 30, 198 . Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (83-01-02) Operator Requalification. The lic-ensee has responded to concerns about requalification including documen-tation of reactivity changes in start-up log sheets. Also, lecture schedules for the present two candidates include student training 'lec-tures. A review of two examinations noted no topic grade less than 80L Both requalification examinations were acceptable. This item is close LClosed)UnresolvedItem(84-02-01) Standpipe not properly secure On May 24, 1984 the inspector viewed a free floating aluminum standpipe (3.5" x 10' in length) with mounting brackets that were pulled awa Maintainance log review found the following license follow-u Inspection of the tank area found fuel in the pool to be undamage Other items inspected included instrumentation, control and shim rods. No anomalies were identifie Calculations were performed and 13 pounds of weight were added to counteract buoyant forces on the standpip There was no identified damage based on a satisfactory complete console checkou Reactor Coolant samples were taken with no indications of fuel damag The hold-down tie straps for the aluminum tube were replaced using heavier meta The licensee has completed the above actions. The inspector's verifica-tion included review of the maintenance manual and coolant chemistry re-ports, and observation of the additional weights on piping and the new hold-down straps. This item is close (Closed) Inspector Follow Item (64-02-02) Review of Reactor Console Over the past two years, during startups 658'thru 710,
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Checkout Shee the licensee has reviewed all out of tolerance parameters and dc:urented corrective action. In addition, Control Rod Check Para 0raph 6-2 has been modified to specify "25 ma above minimum holding current." This item '
is close . Organization A new Reactor Administrator has been appointed. The organizational positions addressed in Technical Specification E.2., Reactor Management, 6re given below:
Position Reactor Administrator Dr. R. Berlin Chief Reactor Supervisor Dr. Jih Perng Hu Reactor Supervisor Brother G. Kane Radiological Safety Officer Dr. R. Berlin Reactor Operation Committee Chairman Dr. R. Berlin Member Dr. J. Augustus Member Brother G. Kane Member Dr. R. Mayo Member Dr. Jih Perng Hu Member Dr. S. Malsky Dr. Ronald Kane, the former Reactor Administrator, has resigned. Dr. Jih Perng Hu, upon receipt of his senior operator license, was appointed Chief Reactor Supervisor replacing Brother G. Kane, who assumed the position of Reactor Superviso Dr. M. Nikman has resigned from the-Reactor Operation Committe The inspector reviewed the change in Reactor Administrator, who no longer is required to hold the position of Head of the Mechanical Engineering Depart-men This item was reviewed by NAR and found acceptabl Review of dual duties as Reactor Administrator and Radiological Safety Officer, which is not addressed in the Technical Specifications, is under NRR revie . Facility Tocr l
At the conclusion of the entrance management meeting, the inspector toured tha 2ere Pcwor Reactor (ZPR) Laboratory with the Reactor Administrato '
Security was acceptable at the various doors leading to the reactor console anti at the Console itsel ~
i The facility was undergoing a maintenance outage with all fuel elements re-
, moved and stored. Replacement of c1 ping from the reacter coolant pool to the domineralizer was underwa . Facility _Cperation The ZPR reacitor is used for experiments for laboratory courses during the fall and spring semester Training in recognizing reactivity addition and criti-
- call'.y was also provided for senior reactor operators of the Power Authority i of the State of New York (FASNY).
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. 3 a. Logs and Records The inspector reviewed Reactor Operation Log Book No. 4 for the period from June 1984 to April 1985. These logs show dates and times of reactor operation, checkout sheet operation logs, pertinent reactor operational parameters, and the purpose of operation. The irradiation of materials, including the material irradiated and time and power of irradiation, were also logged. The responsible reactor supervisor signed and initialed all leg The inspector exanined the " Reactor Console Checkout Sheets" for checkout numbers 656 through 710. Each set of checkout sheets included eight pages of precedural steps. Each step was documented as verified to be performed satisfactorily. The inspector also reviewed the maintenance log, with findings as noted in the Surveillance Activities section of this repor No unacceptable conditions were identifie b. Surveillance Activities Records in the Maintenance Log and Health Physics Record Book document that the ifcensee has performed the surveillances require (1) Technical Specification (T.S.) 1.4 Insertion Times Once every six months, the licensee is required to verify the maxi-mum time for total insertion of regulating and shim rods to be less than 1.0 seccn Surveillances were performed and results are as follows:
Regulating Rod Shim Red October 2, 1984 0.470 sec 0.460 sec March 29, 1985 0.473 " 0.443 "
Octcber 14 ~1985 0.483 " 0.476 ""
April 22,1986 0.430 " 0.473 All rods met T.S. requirements. The inspector asked the licensee to trend regulating rod insertion time as it appeared to be pro-gressively increasing. The licensee plans to repeat this surveil-lance upon completion of overhaul of the reactor pool tan (2) Technical Soecification The lucite hold-down rods are tc ne checked for radiation damage once a semeste The checks, for modulus of rigidity, were performed with established procedure .
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Tests were performed on October 12, 1984; March 29, 1985; October 14, 1985; November 4, 1985; and May 8, 1986. Rods 55 and 44 ranged from 1.7936E+05 psi to 2.1129E+05 psi, which fell within the estab-lished criteri (3) Technical Specification The reactor moderator is required to be analyzed for fission product activity once per semeste Samples were analyzed on October 8, 1984; April 10, 1985; October 17, 1985; and April 29, 1986. No activity was detecte . NRC Order on Fuel An NRC Order to Show Cause issued 9/27/85 addresses nonpower reactor fue The licensee responded to the order on 11/19/85. Review by the NRC Division of Safeguards found the licensee in compliance with the orde The inspector examined fuel storage and found it acceptable. Additional re-view of the following will be accomplished during subsequent routine inspec-tion, Installation of a new high security lock and establishment of proper key contro Documentation of the licensee's verification of fuel locatio The inspector had no further questions in this are . Operator Requalification Program FSAR - Appendix J - Operator Requalification Program August 17, 198 Letter to R. Kane, Reactor Adninistrator, from C. C. Thomas, Chief, Standardization Special PrCjects Branc Manhattan College response to NRC Inspection Report 50-199/83-01, NRC Inspection Report No. 50-199/84-02, paragraph 1 NRC Inspection Report No. 50-199/84-0 /1/84 Hanhattan College Letter to C. O. Thorias on the Operator Requali-fication Progra The licensee responded to the NRC Division of Licensing on changes to the Operator Requalification Program in reference (f). Commitments were made to document program changes in schedule, lectures, and on-the-job training. The criteria for evaluation of operators includes biannual examinations and ob-servations of reactor startups. Present qualification status follow Brother Kane's SR0 license was renewed on October 19, 198 On November 20, 1984, he passed requalification examination as reactor supervisor.
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. 5 Dr. Hu's RO & SRO Licenses were issued by the NRC on January 6, 1984 and June 12, 1984, respectively. He was appointed as Chief Reactor Supervisor on Sep-tember 1, 1984 and passed requalification Examination on September 13, 198 In addition to the student program, on January 14-15, 1985, five senior reac-tor operator candidates from the Power Authority of the State of New York attended a two-day course of instruction conducted by Brother Kane and Dr. Augustu NRC Region I examined Dr. Hu and qualified him as a Senior Reactor Operator as noted in reference (e). The inspector reviewed the licensee's documenta-tion for Brother Kane, which consists of verification of reactor checkcuts and startups since the May 1984 inspection. No deficiencies were identifie Outstanding item 50-199/83-01-01 is therefore close . Operatina License Renewal On August 26, 1983 the licensee requested that the Operating License for the Manhattan College nuclear facility be renewed. Upon completion of the NRC Division of Licensing's review, Amendment No. 6 to License R-94 was granted for a twenty year renewal. The license restates all changes and amendments made since the original license was issued on August 27, 1962. The inspector verified that no equipment was added or additional experiments made since the last operational inspection in 1984. No unacceptable conditions were iden-tifie . Maintenance Outage The licensee entered a maintenance outage on April 25 in order to clean the reactor tank. A slight aluminum oxide coating had appeared on the tank wall Measurements of tank wall thickness also were schedule Disposal of Pool Water and Demineralizer Resin On April 25, 1986, prior to removal of reactor coolant water and disposal of ion exchange resins, samples were taken to insure that provisions of the Radiation Safety Manual, 1983, Paragraph 6.8, were me Five samples of reactor coolant water and five samples of resin were tested on April 25, 1986. The results indicated no contamination (0.005 mCf/1000 cc and 0.05 uCi/mg.) No Iodine-131 was identified. The reactor coolant was removed from the vessel after removal of the fuel. No de-ficiencies were identifie Removal of Fuel Elements The licensee procedure required a console checkout prior to fuel remova All detection instruments were activated. Fuel elements were raised to the reactor deck and surveyed; no elements exceeded 2.5 mr/hr. The ele- .
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ments were then store The inspector verified that the storage of all reactor fuel elements was satisfactor .
. 6 Nondestructive Examination of Tank Walls Upon cleaning the tank, the licensee obtained ultrasonic thickness meas-urements. Original wall thicknesses were specified to be 0.200"-0.300".
No original thickness measurements were made. Twenty-two selected areas were tested during this outage with a minimum measured thickness of O.2257". These results indicated no significant degradation. The test
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points will remain on the tank for future testing. The inspector had no further question Demineralizer Piping Replacement The inspector witnessed partial assembly of new domineralizer pipin Stainless steel fittings have replaced carbon steel fittings. This new piping was added to minimize the entry of oxides into the demineralize The aluminum reactor cooling tank to stainless steel fittings interface was found satisfactory by Reactor Committee revie Procedure Update The licensee's procedures for maintenance and surveillance are not con-trolled by a single administrative document. They vary in format, con-tent, acceptance criteria, required reviews, etc. Dicussions with the reactor administrator confirmed the need for updating the facility's procedure The licensee stated a review of needed revisions would be conducted in a six-month period and that revisions will be completed within a two year period. This item will be reviewed during a subtiequent inspectio . Exposure Report The inspector reviewed Quarterly Occupational Exposure and Radiation Level Surveys for 1-85 through 3-8 The exposure from the operation of the nuclear facility is a measured value for each individual less the reading from a reference monitor badge. All measured individual readings were less than 100 mr/yr. The reference monitor indicated 130 mr/yr. When measurement crror is considered, the individual exposures are all equivalent to the background exposure, i
Alpha surveys of air samples showed <0.005 uC1/cf. Water sample alpha was measured at <0.005 uCi/ml, Swipes of the laboratory, lecture room, counting room, graphite facility, and ZPR source containers showed <0.005 uCi remov-able contaminant These results are consistent with previous reasurement No unacceptable conditions were identified.
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. 7 1 Emergency Planning Emergency Planning was discussed with the Reactor Administrator. The licensee has verified the emergency telephone numbers for the local hospital and has held fire drill Extraneous material was found during tours, including empty paper cartons in the lower reactor room and parts stored in the upper and lower reactor room in flammable containers. The licensee committed to an extensive cleanup upon conclusion of the outage. The inspector had no further questions on this ite . Material Balance Report The inspector reviewed the Material Balance Report for R-94, SNM827 from 4-1-85 to 9-30-85. It showed all elements and isotopes in the licensee's pos-session in quantities similar to that stated in previous reports. The in-spector had no further questions on this ite *
1 Shim Rod Anomaly The inspector reviewed a rod position anomaly and associated corrective ac-tion On March 5, 1985, immediately after the reactor circuit breaker was closed, the Shim Rod Position Indicator showed 40% rod withdrawa Visual inspection revealed the rod was fully inserte The terminal board associated with the indicator was checke No malfunction was detected. The Shim Rod was withdrawn to 100%. Its upper limit light came on. At that point, Shim Rod position indication was off scale. The position indication was adjusted to provide proper indication. No further incidents of this nature have occurred. The inspector had no further questions on this ite . E_xperiments No changes have occured in the licensee's experiment Discussions with the Reactor Administrator and lecture notes show that stu-dents were advised on Health Physics aspects and ALARA concerns at the start of each semester. The inspector had no further question . Use of Low Enrichment Fuel The NRC has amended its regulations to require licensed non power reactors to use low enriched uranium (LEU) fue The licensee is conducting discussions with the Department of Energy (00E)
and attended one DOE seminar addressing costs of changing to LEU. This will involve the folowin .
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-- Transportation of irradiated fuel to a secure facilit Manufacturing of new fue A new Safety Evaluatio A complete rewrite of all experiment A complete start-up progra Retraining /requalification of reactor operator Submittal of estimates for the above to DOE is scheduled for the fall of 198 Preliminary licensee estimates are $550,000 to $650,00 The inspector noted that licensee is on schedule for submittal of information to 00 . Manaaement Meetina On May 15, 1986, an exit meeting was held with the Reactor Administrator to discuss the scope and findings of this inspection. No proprietary information was identified as being within the inspection coverage.