IR 05000335/1981017
| ML17212A696 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 08/13/1981 |
| From: | Hosey C, Wray J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17212A695 | List: |
| References | |
| 50-335-81-17, 50-389-81-13, NUDOCS 8109090375 | |
| Download: ML17212A696 (11) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report Nos. 50-335/81-17 and 50-389/81-13 Licensee:
Florida Power and Light Company 9250 Nest Flagler Street Miami, FL 33101 Facility Name:
St. Lucie 1 and 2 Docket Nos. 50-335 and 50-389 License Nos.
DPR-67 and CPPR-144 Inspection at St. Lucie site near Ft. Pierce Florida Inspector:
J.
R.
r y Approved by:
C.
M. Hose
, A ting Section Chief Technical Inspection Br nch Engineering and Technical Inspection Division rl~ d Date Signed SUMMARY Inspection on July 20-24, 1981 Areas Inspected This routine, unannounced inspection involved 32 inspector-hours onsite in the area of Health Physics Appraisal follow up actions.
Results No violations or deviations were identified in the area inspected.
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.REPORT DETAILS 1.
Persons Contacted Licensee Employees C. Wethy, Plant Manager
"J. Barrow, Operations Superintendent H. Buchanan, Health Physics Supervisor
- H. Mercer, Assistant HP Supervisor
~A. Bailey, QA Operations Supervisor
~N. Roos, Quality Control
- R. McCullers, HP Operations Coordinator
- G. Boissey, Startup
~R. Frechette, Chemistry Supervisor J. Sheets, Supervising Engineer Corporate Licensing J.
Danek, Corporate Health Physicist S. Pearle, Power Resources Speicalist GO
~Attended exit interview The inspection scope and findings were summarized on July 24, 1981 with those persons indicated in paragraph 1 above.
The Operations Superintendent stated that a review of the standing Radiation Work Permit system will be conducted to ensure that proper procedural controls are applied to routine work throughout the plant.
The inspector stated that additional work i-s still necessary in the ALARA and Training programs, especially in the areas of staffing and procedures.
3.
Licensee Action on Previous Inspection Findings (Closed)
Infraction (335/79-20-01)
Invalid testing of engineered safety features filter systems.
The inspector reviewed a test of the Shield Building Ventilation System (HVE-6A and HVE-6B) conducted on August 27, 1979 and concluded that the filters met the requirements of Technical Specifica-tion 4.6.6.l.b.
The inspector also reviewed subsequent filter tests and verified that the surveillance requirements of Technical Specification 4.6 have been met.
(Closed)
Infraction (335/79-20-02)
Improper use of a certified shipping cask.
The inspector reviewed plant procedure HP-40, Shipping and Receipt of Radioactive Material, and verified that the requirement to provide shoring when appropriate has been incorporate (Closed)
Infraction (335/79-20-03)
Improper classification of solid waste shipments.
The inspector reviewed shipping records for 1981.
Proper identification of the radionuclides present appeared to have been properly entered.
The inspector was informed that the licensee's General Office is conducting experiments and will provide the necessary guidance to document Transport Groups I and II isotopes in future shipments.
No Group I or II nuclides have been seen in reactor coolant samples.
The inspector had no further questions.
(Closed) Violation (335/80-06-08)
Failure to have a retraining program.
The inspector reviewed the licensee's response contained in their letter L-80-267 dated August 13, 1980 and verified that a training and retraining program for Health Physics personnel has been developed and implemented pursuant to the requirements of Technical Specification 6.4.1.
The inspec-tor stated that continued work is needed to formalize training procedures and to ensure that each technician receives a
minimum of
hours of retraining each year pursuant to plant requirements.
(Closed)
Unresolved (335/80-06-12)
Comparison of pocket dosimeter and TLD readings.
The inspector reviewed pocket dosimeter and TLD readings for the period in question and concluded that no regulatory dose limit was exceeded.
The inspector also verified that a system to compare pocket dosimeter and TLD readings has been established and is being implemented.
(Closed)
Violation (335/80-06-13)
Failure to follow procedures.
The inspector reviewed the licensee's response contained in their letter L-8 0-267 dated August 13, 1980 and verified from training and plant safety meeting records that the stated actions were taken.
During tours of the facility, the inspector observed worker s properly wearing personnel dosim-etry.
In addition the inspector verified that respirators and respiratory equipment were being properly stored, accounted for, maintained, inspected and tagged as required by plant procedure HP-62.
Plant procedure HP-13B states that Form HP-61 will be used to record sour ce response check results.
The inspector reviewed records indicating that this requirement is being met.
The inspector reviewed Standing Radiation Work Permit 81-13, General Entry into Gas Areas in reactor Auxiliary Building (RAB), used to control routine entries into Noble Gas areas in the RAB and which required personnel to sign in on Form HP 1. 1.
HP Form 37 was used at the job site to control access which appeared to comply with plant procedure HP-1, Radiation Work Permits.
The inspector determined that adequate control was provided.
However, the inspector stated that-more attention should be given to such details when writing and using standing RWPs.
At the exit meeting, the operations superintendent stated that a review of the standing RWP system will be conducted to ensure the proper generation and use of standing RWPs.
The inspector had no further comments or question (Closed) Violation (335/80-06-18)
Contaminated Tool Control.
The inspector reviewed survey records of the clean tool room for,the first six months of 1981 and verified that no contaminated tools had been inadvertently stored in this clean area.
On July 22, 1981, the inspector conducted an inde-pendent contamination and radiation survey of the clean tool room, cold machine shop and scrap metal dumpster and found no indications of contam-inated equipment or material.
The inspector also reviewed training and safety meeting records and determined that the corrective actions listed in FP4L letter L-80-267 dated August 13, 1980, had been taken.
(Closed)
Unresolved (335/80-06-20)
Set points for waste gas= monitor.
The inspector selectively reviewed gaseous release permits for 1981, the waste gas monitor calibration curve, plant procedure C-72, Processing Gaseous Mastes, and discussed the methods for determining alarm setpoints with a cognizant licensee representative.
The inspector concluded that the release limits specified in Environmental Technical Specification 2.4.3.a were not exceeded and that the high alarm setpoint is established and maintained at a
value which will provide automatic termination of the release prior to exceeding the technical specification limit.
Unresolved Items Unresolved items were not identified during this inspection.
Licensee Action on Previous Inspector Follow-up Items (Closed)
(78-19-04) Correlation of new fuel building air effluent monitor with sample results.
The inspector reviewed the calibration of the fuel building exhaust monitor and determined that proper techniques and proce-dures were employeed.
(Closed)
(79-20-04)
Beta/gamma activity on records of analyses of reactor coolant gross activity.
The inspector examined chemistry analysis log sheets and verified that only gross gamma activity is recorded when using isotopic analyses pursuant to plant procedure C-45B.
Beta isotopic analyses are performed and recorded using a different approved chemistry procedure.
(Closed) (80-06-01) Reporting recommendations for health physics supervisor.
The inspector reviewed the plant's most recent organization chart and verified that the health physics supervisor has direct access to the plant manager.
(Closed) (80-06-02) Establishing a formal group with the sole responsibility of ALARA.
The inspector reviewed correspondence from corporate and plant management which established the licensee's ALARA program.
The inspector stated that additional work is necessary to fully implement an adequate program, especially in the areas of staffing, training and interdepartmental involvemen C
(Closed)
(80-06-03)
Focusing the corporate health physics activities on the plants.
The present corporate.health physici st visits the plant regularly.
The inspector discussed this item with the corporate health physicist and licensee representatives and had no further questions.
(Closed)
(80-06-04) Evaluation of the present staffing requirements for the health physics groups As a result of the HP staffing evaluation conducted following the health physics appraisal, the health physics staff has nearly doubled to 26 individuals with two HP operations management positions created as well as professional positions in Emergency Planning, ALARA, Training, and Technical.
The inspector had no further question.
(Closed)
(80-06-09)
Requirements for Health Physics Manual.
A licensee representative stated that ALARA principles are applied routinely to plant activities even though they are not requirements in the health physics manual.
The inspector reviewed documents indicating that many ALARA prin-ciples are being used in preparations for the approaching refueling outage and determined that with the establishment of a formal ALARA program, it appeared ALARA principles will essentially be mandatory.
(Closed)
(80-06-11) Establishment of a formal ALARA program.
The inspector reviewed corporate and plant correspondence whi'ch established a formal ALARA program.
The inspector stated that additional work is necessary to achieve a fully acceptable program, especially in the areas of staffing and proce-dures.
(Closed)
(80-06-14) Training and documentation of training for cleaning of respirators.
The inspector examined personnel and training records and concluded that persons responsible for inspection of respiratory protection equipment have, received proper training.
(Closed)
(80-06-17)
Establishment of a formal training and qualification program for instrument technicians.
The inspector examined personnel and training records and concluded that persons responsible for portable instru-ment calibrations have received proper training.
Radwaste Shipping The inspector reviewed radwaste shipment records for calendar year 1981.
Seven waste shipments were made between January 1 and June 30, 1981.
Less than 25 millicuries of total activity, principally Co-60 contained in spent resins, were shipped to the Barnwell, South Carolina burial site.
On July 23, 1981,
.two boxes and 57 drums containing LSA material was shipped off site for burial.
The inspector reviewed radwaste shipping forms and radiation and contamination surveys and did not identify any violations or deviations.
Licensee representatives indicated that a system for identifi-cation of Transport Group I and II radionuclides is being developed by the licensee's corporate office and will be used with future shipments.
The
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inspector was informed, however, that there has been no indication of Group I and II isotopes in reactor coolant samples and that the plant is confident that amounts of Transport Group I and II radionuclides are not present in their radwaste.
The inspector had no further questions or comments.
7.
Unit 2 Preoperation Inspection On July 20, 1981, the inspector discussed with the plant manager the NRC's preoperational health physics inspection program scheduled to begin on Unit 2 this summer.
The inspector outlined the basis, scope, frequency, general depth and similarity of these inspections to that conducted on Unit 1 during its preoperational phase.
The plant manager stated that he was not at his present position prior to Unit 1 receiving an operating license and looked forward to working compatibly with the NRC health physics inspectors during future inspections of Unit 2.
On July 22, 1981, the inspector accompanied by FP5L corporate licensing representatives and members of the Radiological Assessment Branch of NRR toured" the Unit 2 complex. It was noted that most major equipment in the reactor containment and auxiliary buildings -were installed.
However, a
licensee representative stated that systems will not be ready for start-up testing for quite some time.
The inspector expressed his interest in the scheduling of radwaste system testing and had no further observation I ~