IR 05000272/1979017
| ML18081A438 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/17/1979 |
| From: | Clemons P, Crocker H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18081A434 | List: |
| References | |
| 50-272-79-17, NUDOCS 7910290374 | |
| Download: ML18081A438 (9) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Report No. 79-17 *
Docket No. 50-272 License No. DPR-70 Region I Priority: --
Licensee:
Public Service Electric and Gas Company Category:
C Attention: Mr. F. W. Schneider, Vice President - Productiorr 80 Park Place Newark, New Jersey Facility Name:
Salem Nuclear Generating Station, Unit 1 Inspection at: Hancocks Bridge, New Jersey Inspection conducted:
May 22-25, 1979 Inspector:
0?~,~
R. E. Clemons, Radiation Specialist Approved by:.::4?,~~
H:W~cer,Acting Ch'ief, Radiation Support s*ection FF & MS Branch Inspection Sunmary:
Inspection on May 22-25, 1979 (Report N /79~17)
Areas Inspected: Routine, unannounced inspection by a regional based inspector of the radiation protection program as it relates to the refueling outage including: Bulletin 78-08, procedures, training, posting, labeling, exposure control, respiratory protection9 surveys, and annual report. Shortly after arrival, areas where work was being conducted were examined to review radiation control proce-dures and practices. The inspection involved 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br /> on site by one regional based NRC inspecto Results:
Of the 9 areas inspected, no items of noncompliance were identified in ~6 areas. Three apparent items of noncompliance were identified in 3 areas (Infraction - failure to follow procedures, Paragraph 3; Infraction - failure to label a container; Paragraph 4; Deficiency - failure to post, Paragraph 5).
.7s1029o37Y
DETAILS Persons Contacted Principal Licensee Representatives Mr. C. Fantacci, Technician - Nuclear
- Mr. W. Grau, Quality Assurance Staff Assistant
- Mr. J. Gueller, Senior Performance Supervisor Mr. P. Landers, Nuclear Training Staff Assistant
- Mr. M. Metcalf, Quality Assurance Engineer - Resident Group
- Mr. H. Midura, Manager
- Mr. L. Miller, Performance Engineer Mr. E. Nielsen, Rad Services
- Mr. R. Silverio, Assistant to Manager
- Mr. J. Stillman, Station Quality Assurance Engineer Mr. R. Ziegler, Senior Staff Engineer The inspector also interviewed several other licensee and con-tractor personnel during the course of the inspectio *Denotes those present at the exit intervie IE Bulletin No. 78-08 IE Bulletin No. 78-08 was sent to all utilities in the region on June 12, 197 The subject of the bulletin was 11Radiation Levels From Fuel Element Transfer Tubes.
The licensee responded* to the bulletin on August 7, 1978 informing the Director of the action taken, and the licensee also stated that a detailed radiation survey would be performed during the first refuelin The inspector reviewed survey data of the Transfer Tubes as Fuel Elements were transferred during. the period April 29, 197 The survey revealed a minor streaming problem at a pipe sleeve imbedded in one of the shield wall The licensee 1s survey in-dicated a dose rate of 150 mR/hr at the pipe sleeve immediately adjacent to the floor of elevation 100 as an element was being transferre The inspector noted that the area was conspicuously posted in accordance with 10 CFR 20.20.
Procedures The licensee has developed procedures in accord with the technical specification requirements. Technical Specification 6.11 states, 11Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
The inspector visited the training trailers to determine if
- appropriate employees had received the training as required by Administrative Procedure No. 24'.,
11Radiological Safety Program 11 which requires certain individuals be retrained in the Radiation Workers Training Course RP-1, at a time inter-val of one yea The inspector inquired as to what individuals were required to take this course and he was told that individuals having blue or black TLD dosimeters with unes-corted access to controlled areas, were required to take the Radiation Workers Training Cours The inspector was provided a list of personnel who had been issued dosimeters and the list was current as of May 9, 1979. Using this list the inspector selected the names of approximately twenty licensee personnel on May 24, 1979 and asked the Nuclear Training Staff Assistant to confirm that these individuals had received the required training within the stated time interva Two employees had not been retrained in the Radiation Workers Training Course within the one year time interva One em-ployee was trained last in *December 1977 and the second em-ployee was last trained in April 197 Both of these employees have current blue or black TLD dosimeters which indicate that they are required to have the retraining within the time interval of one yea *
. This was the first outage experienced by Salem I, and a sig-nificant operation involved was the eddy current test i the Steam Generators No. 12 and 14 where dose rates were up to 18 R/h The license has Procedure PD 15. 1. 012, 11 Past Operation De-briefing, 11 developed pursuant to Technical Specification 6.11 which states 11 **** to keep exposure to radiation as low as practical, it** is necessary to learn from the experience of work performe To insure documentation of such experience, whether good or bad, a critique shall be held after the
.* completion of those tasks deemed radiologically significan The debriefing should be conducted immediately after the event and should be conducted by a Technical Foreman-Rad Protection.
On May 25, 1979, the inspector asked a licensee representative if a post operation debriefing had been conducted on the work performed on the steam generator The Licensee representative said that a critique had not been conducte He stated that the report was in the process of being written, and the de-briefing would be conducted once the report was complete The inspector asked a licensee representative when was the work on the steam generator completed, and he was told that work was completed on/or about April 25, 197 Technical Specification 6.11 requires procedures be adhered to for all operations involving personnel radiation exposur Procedure PD 15.1.012 requires that debriefing should be conducted immediately after an operation is complete The inspector noted that failure to follow procedures re-presents noncompliance with license conditi-0n. (79-17-01)
Container The license has an Instrument Calibrator located in the Instrument Repair and Calibration Roo This Calibrator contains eight Cesium-137 sources, totaling approximately 170 Curie As the inspector toured this area on May 24, 1979, he noted that the Instrument Calibrator was labeled with a radiation symbol but nothing els He asked a license representative what was in the calibrator and he was informed that the Instrument Calibrator contained eight Cesium-137 sources.. The licensee did not know the activity of the sources at the time, but the inspector ob-served that a data sheet on a wall near the calibrator indicated that one source mai have 170 curie The inspector informed the licensee representative that containers containing license quan-tities of radioactive material must be properly labele On May 25, 1979, the inspector was informed that the calibrator contained approximately 170 curies of*Cesium-13 CFR 20. 203 ( f)
11Containers 11 states 11 **** each container of l i-censed material shall bear a durable, clearly visible label
tfJ
identifying the radioactive contents.
A label required pursuant to the above should bear the radiation caution symbol and the words 11Caution, Radioactive Material 11 or 11Danger, Radioactive Material.
It shall also provide sufficient information to permit individuals handling or using the containers, or working in the vicinity thereof, to take precautions to avoid or minimize exposure The inspector stated that failure to label the Instrument Calibrator properly represents noncompliance with the regulations. (79-17-02) Posting As the inspector toured the facilities on May 23, 1979, he noted that a bulletin board was located on a wall at the entrance to the Control Access Are He looked on the board to determine if the posting required by 10 CFR 19. 11 was availabl CFR 19. 11, 11 Posting of Notices to Workers, 11 requires in paragraph (a) that current copies of regulations, licenses, license conditions, or documents incorporated into a license by reference, shall be posted by the license Paragraph (b) permits the licensee to post a notice which describes the document and state where it may be examined, if it is not practicable to post the documen Paragraph (d) states, 11Documents... shall appear in a sufficient numb~r of places to permit individuals engaged in licensed activities to observe them on the way to or from any particular licensee activity location to which the document applies...
Contrary to the requirement, the appropriate documents, or notices describing the documents stating where the documents may be examined, were not posted in the Control Access Area, an area through which licensee employees had to pass going to and from licensee activities to which the doucments applie Employees could enter the Control Access Area without going through other areas that may have been poste The inspector noted that failu~e to post the required documents, or notices, represents noncompliance with the regulation (79-17-03)
- Exposure Control The inspector reviewed TLD data for the second quarter of 1979 for all persons involved in the refueling outag The inspector noted that three individuals exceeded 1250 mR during the perio The licensee had all of the Form 4 information as required by 10 CFR 20. 102 as reviewed by the inspector.. The maximum exposure received was 1750 millirem by one individua A diver from the Walker Diving Crew entered the Fuel Transfer Pool on May 2, 1979 and May 3, 197 The same diver also entered the Reactor Cavity on May 2, 197 The diver entered these areas because of problems experienced in transferring the fuel bundle According to a li~ense representative the diver received a total dose of 15 mR when he entered the Fuel Transfer Pool on May 2, 1979; 8 mR on May 3, 1979 during his stay in the Trans fer Pao The diver received 11 mR during his stay in the Reactor Cavit According to the licensee representative the diver spent ap~
proximately one hour on each entry into the two area The inspector asked to see the extremity dosimetry data on those persons entering the Steam Generators to perform various opera-tion The licensee provided extremity dosimeters for about eight people who entered the Generator The TLD data indicated that no regulatory limits were exceeded by anyone involved with the Steam Generator operation No items of noncompliance were identifie.
Respiratory Protection On April 2, 1979, the licensee notified the Director of Region I, by letter, that the implementation and enforcement of the Respiratory Protection Program in compliance with 10 CFR 20.103 at Salem I, would become effective in 30 days from the date of the lette During this inspection the inspector reviewed the licensee's respirator program in accord with the requirements of Regulatory Guide 8.15, 11Acceptable Programs for Respiratory Protectio The inspector determined that the licensee's respirator program did not meet the requirements of Regulatory Guide 8.15.C.4 in the following instances: Written procedures to ensure proper selection, superv1s1on, and training of personnel using such protective equipmen ~--------
.*
7 Written procedures to ensure the adequate individual fitting of respirators, as well as such procedures to ensure the testing of respiratory protective equipment for ope.rability immediately prior to each us Written procedures for maintenance to ensure full effective-ness of respiratory protective equipment, including procedures for cleaning and disinfection, decontamination, inspection, repair, and storag Written operational and administrative procedures for control, issuance, proper use, and return of respiratory protective equipment, including provisions for planned limitations on duration of respirator use for any individual as necessitated by operational condition As a minimum, the following additional technical items are to be observed:
(1) Respirable air of approved quality and quantity is to be provided and oxygen deficiency is to be avoided This fact was brought to the attention of a senior member of the staff at Salem I who informed the inspector that in spite of the commitment made in the letter of April 2, 1979, the respirator program had not been implemente The program will be in compliance with 10 CFR 20. 103(c) prior to implementatio The inspector verified that selected individuals were being whole body counted by the licensee through a contracto According to the information given the inspector individuals are whole body counted when they enter the site, and again just prior to their leaving the sit The inspector reviewed data which indicated that individuals working in the Steam Generator had been counted upon entry to the site, and again prior to leaving, with two exception The two individuals were counted upon entry to the site, but they were not counted prior to leaving the site. The inspector asked a licensee representative what the requirement was for whole body counting individuals prior to their leaving the site and he was informed that *there was no requiremen No items of noncompliance were identifie *
8 Surveys 10 CFR 20.201 11Surveys 11 As used in the regulations in this part, 11 survey 11 means an evaluation of the radiation hazards incident to the production, use, release, disposal, or presence of radioactive materials or other sources of radiation under a specific set of condition When appropriate, such evaluation includes a physical survey of the location of materials and equipment, and measurements of levels of radiation or concentrations of radioactive material presen Each licensee shall make or cause to be made such surveys as may be necessary for him to comply with the regulations in this par The inspector reviewed survey data from i nsi.de Steam Generators No. 12 and 14 to assure compliance with the requirements of 10 CFR 20. 20 According to the information given the inspector surveys were made inside Steam Generator No. 12 on April 12, 1979, and inside Steam Generator No. 14 on April 14, 197 The results of the surveys are as follow:
Location Manway General Area Tube Sheet Location Manway General Area Tube Sheet Steam Generator No. 12 Primary Coolant Inlet Primar7 Coolant Outlet Gamma (R/hr)~Beta (Rad/hr)
Gamma (R hr)-Beta (Rad/hr)
15
10
20 Steam Generator No. 14
12
8
18 Primary Coolant Inlet Primar7 Coolant Outlet Gamma (R/hr)-Beta (Rad/hr)
Gamma (R hr)-Beta (Rad/hr)
12
7
18
10
10
20
- -~)
.~ Procedure PD-15.4.012, 11Containment Air Sampling Schedule, 11 developed pursuant to Technical Specification 6.11, requires air samplihg under certain condition With the reactor shutdown and the reactor coolant system open, and the continuous air monitor functional, particulate and iodine samples are required to be taken daily on three elevation The inspector reviewed air sample data for the period April 11-22, 1979 to determine if the licensee fulfilled the requiremen The data indicated that samples were collected from the three eJevations at the required frequenc Procedure PD.,.15.4.001, 11 Routine Surveys - Schedule, 11 developed pursuant to Technical Specification 6.11, requires radiation and contamination surveys be made daily in certain clean areas and controlled access area The inspector reviewed radiation and contamination survey data for the period April 10-25, 1979 to determine if the licensee ful-filled the requiremen The data indicated that the surveys were performed as require No items of noncompliance were identifie Annual Exposure Report Technical Specification 6.9.1.5 requires that an annual exposure report be submitted to the Director of Inspection and Enforcemen The inspector verified that the report was submitted to the Director on March 5, 197 *
1 Exit Interview The inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on May 25, 1979.: The inspector summarized the purpose and the scope of the inspection, and the findings as presented in this report.