ML20050A248
| ML20050A248 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 01/26/1977 |
| From: | Knapp P, Neely D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20050A245 | List: |
| References | |
| 50-003-76-16, 50-247-76-36, 50-286-76-36, 50-3-76-16, NUDOCS 8203310632 | |
| Download: ML20050A248 (20) | |
See also: IR 05000003/1976016
Text
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$c p - , , U. S. NUCLEAR REGULATORY CCMMISSION l OFFICE OF INSPECTION AND ENFORCCiENT REGION I 50-003/76-16 50-003 50-247/76-36 50-247 IE Inspection Report No: 50-286/76-36 Docket No: 50-286 DPR-5 Licensee * Consolidated Edison Company of New York, Inc License No: DPR-26 DPR-64 4 Irvine Place Priority: -- D New York, New York 10003 Category: C C Safeguards ' E Location: Buchanan, New York Type of Licensee: PWR, 615 MWt (B&W)-PWR 2758 MWt (W)-PWR 3025 MWt (W) Type of Inspection: Management Meeting ' Dates of Inspection: December 20-21, 1976 Unit 1, Decemoer 13, 19/o Dates of Previous '.. pect m Unit 2 & 3, December 20-23, 1976 Reporting Inspector: \\ h j ._gg _7 7 %.a D. R. Neely, Radiation \\peckalist S DATE Accompanying Inspectors: NONE DATE , . DATE i DATE P. J. Knapp, Chief, Radiation Other ying Pers support section DME \\g_ Reviewed By: ' a "# 1 -E- 77 cx P. J . 'Kn a p'p , Ch i e f ', RadiApion Support Section, DA7g - Fuel Facility and Materials Safety Branch . - 8203310632 770126 ' PDR ADOCK 05000003 G PDR - 9 >
.
. . - . , . ' . , 1 SUMMARY OF FINDINGS . Enforcement Action , None. Management Meeting The management meeting was conducted at Buchanan, New York on December 21, 1976. The following personnel were in attendance: i . Consolidated Edison of New York, Incorporated Mr. E. Kessig, Acting Manager, Nuclear Pover Generation Department Mr. E. McGrath, Manager, Nuclear Power Generation Department (Designee) Mr. S. Wisla, Radiatior. Safety Director Region I, Office of Inspection and Enforcement, USNRC Mr. P. Knapp, Chief, Radiation Support Section Mr. D. Neely, Radiation Specialist Purpose and Scope . The purpose of the meeting was to review the licensee's response to the letter dated November 18, 1976, from J. P. O'Reilly, Director, Region I, Office of Inspection and Enforcement to W. J. Cahill, Jr., Vice President, Consolidated Edisen Company of New York, Incorporated. Discussions during the meeting were based on the document entitled " Consolidated Edison Company of New York, Inc., Indian Point Station Upgrading Program for Radiation Protection," attached as Enclosure A, which was presented the day before, together with supporting information by licensee representatives. Proposals by a consulting firn to accom- , plish parts of the station upgrading program were discussed. Problems identified by this document and proposed corrective actions were analyzed to determine whether its implementation could be expected to produce an improved Radiation Protection Prograc and eliminate repeated findings of items of noncompliance. . . ~ .: . .. - - -
. . ' < . . 2 ' Areas not fully covered by the document were identified and discussed. Licensee representatives provided amplification and explanation of several listed areas. It was concluded that implementation of the upgrading program would make a significant contribution toward improving the Radiation Protection Program. However, it was also agreed that the document did not cover all of the necessary areas with sufficient specificity to permit reliance on the words alone. Licensee representatives emphasized that their overriding intent was to establish an effective program and that the document was intended to demonstrate this intent rather than define a narrow and limited upgrading program. The NRC representatives stated that serious effort has been put forward toward accomplishing the action described in the letter, dated November 18, 1976, and that the implementation of the upgrading program combined with the subjects discussed in the meeting could be expectel to result in an improved Radiation Protection Program. The licensee representatives stated that they intended to implement the program according to the schedule shown in the plan. The NEC representatives stated that the Radiation Protection Program would be monitored closely over the next several months of inspection effert. _ e l - ~~ . - - ,
,. . ' ' '
ENCLOSL'RE A < ' . t , , . . Consolidated Edison Co. of N.Y., Inc. Indian Point Station Upgrading Program for Radiation Protection - - . December 15, 1976 l l ' I' -- _ _ . ,
' . . . 1977 PLAN FOR UPGRADING Ih*DIAN POINT'S PADIATION . PROTICTION PROGPJd4 , , The Radiation Protection Program at Indian Point has been reviewed to determine its effectiveness and identify oppor- tunities for improvements. Inputs from various sources were analyzed including: 1. N.R.C. inspection reports over the past two years; 2. Reports from our self-inspection program
(station, Department and Corporate); e i
3. Meetings with_Cperations, Maintenance and ' Radiation Protection groups; 4. An audit of the program conducted by Pe_ter- Gertz Consultants, Inc. These inputs were categorized and common opportunities for ,
l improvements were identified. Corrective action was de- i l veloped for each identified item and a sch2dule for com- ' pletion was assigned. This schedule indicates the time frame when the item would be .cted upon. i l . . , t e 4 e . W '*9
. . - . . -2- . Controls to assure that acticns are ccmpleted within the . scheduled date include: 1. Weekly review or progress by Station Per- sonnel who have been assigned as Action Coordinator for each corrective action identified. A progress report shall be submitted to the Plant Manager indicating percent completion. The Action Coordin- ator is listed on the attached chart. . . 2. Semi-monthly review by the Department - . Manager. , 3. Monthly review by the Assistant vice Presid,ent Pcwer Supply. 4. Monthly review by the Radiation Safety Sub-Committee. 5. Inspection visits by the Senior Vice President Power-Supply. The frequency of these visits to be determined accor- , ding to the p cgress of the program. ! . M %
- i . i . , ,- - - . , e Specific actions datailed in the attached chart are described below. It is noted that additional opportunities for i= prove- ment may be determin<d during the course of the program. These items will be added to the plan and a schedule for implementa- , tion assigned. Adjustments in the schedule due to changing plant conditions may also be necessary. These adjustments may be authorized . by the Assistant Vice President only and will be documented. Manageme.t and .3dministration i . To provide increased facilities and an efficient environment for the E.P. Technician and Supervisor, a new office will be constructed for the Supervisory Group. The existing Health Physics Office will be utilized by the Technicians as an area to record data, calculate results and fill out reports. The current counting rocm will be devoted solely to counting work and will become part of the Controlled Area with no access av'allable from the Uncontrolled Area. With the proposed organization changes, the Radiation Safety Sub-Section will no longer have respcnsibility for training, calibration of instruments, environmental monitoring and atten- dant functions. . ~ . , l
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The nu=ber of Health Physics Technicians will be increased from the present permanent complement of 9 regular to a total of 15 fully qualified technicians. A supervisor frcm the present complement will be transferred to the . Training Sub-Section to supervise all -Radiation Safety - Training. Two supervisors will be hired from outside sources. This will increase the number of H.P. Supervis- ors by one (1). This supervisor will provide assistance in record-keeping and Unit No. 1 Health Physics. _ Improving Technician effectiveness is considered a Manage- ment responsibility in that proper training and procedures provided by Management would greatly increase the E.P. - Technicians' effectiveness. To 'this end we have contrac- ted with NUS Corp. of Rockville, Maryland for a training course for Eealth Physics Technicians. We expect to have NUS Corp. review all H.P. procedures currently in force t at Indian Point. Following a review of the recommendation by NUS, the procedures will be revised as necessary. The proposal received from NUS indicates that review would be accomplished in three phases. . Phase 1: Review of procedures. Phase 2: Review of actual Health Physics per- , .formance. ! . Phase 3: Report of findings and recommendations. . . . . . -, - _ .
~e - ~. - , . .
t a ' As indicated on the attached chart, the training course for H.P. Technicians will begin in February 1977 following the Basic Course for plant personnel. This training would be f , formalized classroom training in basic concepts, methods , ~ and procedures.
Control of Hich Radiation Areas - , l - To correct the problem of uncontrolled access to High Rad- iation Areas we have contracted for the replacement of the gates in Unit No. 2 and 3 with the self-closing . type. The j installation of these gates is contingent upon receipt of { ' material from the contractor. When these gates have been installed, SAO-111 will be~revie'wed and revised accordingly to reflect the need for a change in key control and inspec- l tion by Watch personnel. ,
9 We have instituted the policy of establishing a control point i at the entrance to the Vapor Containment (VC). This con- l ! trol point serves as a means of preventing unauthorized ac- '
cess to a High Radiation Area. The control point is manned [ i i by personnel, usually Health Physics Technicians, with writ- ' ten instructions to ensure that personnel entering the v.C. l
are knowledgeable of the provisions of the Radiation Work
! Permit specifically issued for the entry and that the proper
! t i dosimetry and protective clothing are worn. !
, 4 l .
-d . .. _. . _ - -_ _ - - .
- . . . s . . Besides properly posting the entrance to the vapor Contain-
ment, the establishment of a control point at the V.C. clear- ly establishes the fact that the entire V.C. is a' High Rad- iation Area. Other areas within the V.C. are also posted for information and these are routinely inspected for up- dating and adequacy. In addition, all areas within the Con- trolled Area are an integral part of the Corporate Inspection Program which was originally established for the Unit No. 2 refueling outage. This inspection program will continue for six months and includes a weekly inspection by a cognizant member of the Operating Staff and a monthly inspection by a Corporate Staff Member. ' Radiation Surveys - We have discontinued the use of the CAM for the determin- ation of airborne radioactivity exposure until such time as an evaluation of hose factors is conducted and instruc- tions in the use of this device are clearly understood by ' all Technicians. We are however continuing the use of the , CAM for providing indication of changes in airborne radio- , activity levels. . k .. . _ _ - ,.
7- . , -
. . . In the meantime, we have instituted the use of grab sam- pling in all cases where there is. a significant potential ' for airborne exposure. To establish an absolute airborne activity MFC, an evalua- tion is being made by performing a complete isotopic analy- sis of plant air sa=ples. This analysis will include alpha and Sr-90 determinations and is being performed by Teledyne Isotopes, Inc. , ,
i We are currently making a survey of our in-plant monitoring ' i ' equipment with a view toward upgrading and determining the . need for additional equipment. Increased ionization chamber type instrumentation and improved smear counting capability are currently recognized as among our requirements. Current requirements for evaluations to be perforned in con- nection with radiation surveys are dictated by SAO-105, H.P. procedures and various established routines, e.g., watch du- sies and periodic tests. To insure adequacy of surveys these documents and routines will be reviewed during the in- P depth analysis by NUS Corp. (see Management and Administra- tion) with relation to survey methods e.g. beta and extre- mity monitoring, and clear guidelines will be established. ' Instruction have been issued in those areas currently found , deficient. - ' . O. h PM M --
-v - . . . ) - . , l In addition, we are currently reviewing SAO-105 with respect - 1 i to the issuance of a Radiation . ark Permit. It will be re- ' vised to provide that a R.W.P. ma'y be issued for a finite period not exceeding seven days. This change will provide greater cognizance by Eealth Physics personnel of work that- is actually being performed. Radiation surveys will neces- sarily be kept current since a new survey is required with .each R.W.P. issued. Upon re-issuing a R.W.P., Health Phy- sics personnel must be contacted at which time the radio- logical conditions will be re-evaluated. . Personnel Monitoring . The problem of discrepancies between dosimeter and film badge exposure has been reviewed and our policy has been changed to require accepting the dosimeter values where the reported exposure is higher than the film badge re- sults by 20% or more unless an investigation is conducted and it is clearly established that a lower value should be ' used. SAO-120 will be revised to reflect this change. We are also investigating the use of an in-house TLD' system. t Our current evaluation will consist of a three month test ! in which station yellow badge personnel will be issued TLD badges. The use of this system as a supplemert to or re- placement for film badges will be evaluated at that time. , ! 1 - n , , . . - -
u ao T- . , ,
.. - . The intent of SAC-120 in establishing administrutive limits more restrictive than 10 CFR 20 has aluays been to provide a basis for review of exposure in accordance with ALARA practices. These ad=inistrative 14-i ts are intended as cyproximate values at which time such reviews would be per- formed. SAO-120 will be revised to better reflect this . intent. The current practice of allowing personnel to obtain their own film badge frem the fil= badge rack is a source of po- tantial problems. Plans include having the guard or secur- ity desk personnel hand out the badges as required.
- To strengthen control over contractor personnel, we have in- structed the Command Post Security Group to inform the Rad- , lation Protection Sub-Section of the admission expiration date of each contractor. We will remove the contractors film badge from the badge rack at that time. Should the con- - . tractor return to the site within the same month, he will - i r have to submit additional exposure history to be recorded
i on the NRC-4 form. This will help to eliminate the poten- . ! tial for exceeding the quarterly exposure limit for Contrac- tors working at multiple sites. ' i , & ! I i 1 - , I l -~ . - . -.
. . . . . . . .. ~
r . - - 10 - -
Improvement In And Conformity to Procedures , , Conformity to procedures both by the worker and Health Phy- sics Technician can be directly correlated to training, pro- cedures, superviscry follow-up, and cocnunications. As stated in the Porter-Gert: Audit Report, workers appear - to have a lack of regard for the Radiation Safety Program. A basic Radiation Protection training course has been scheduled which emphasizes control of radiation exposure I and methods of of protection against the spread of contam- ! ination. We feel such a course developed by a consultant I - will add to the workers understanding of the need for a Rad- ! iation Safety Program at indian Point and alleviate or nul- lify most concerns. This course together with the course , for Health Physics Technicians and the review of procedures discussed in Management and Administration will help elim- , inate the problem of failure to follow procedures. ire also plan to increase our supervisor complement by hiring an individuni experienced in the concepts of nuclear power
plant health physics. . I
. . ! I < . ' _ M T - - -
O
s , '. _ 11 _
To increase ecmmunicatiens flow we have established monthly Union / Management meetings at which time the Radiation Pro- 1 L taction Program and ALARA principles are discussed and any concerns or questions by the employees will be answered. . Controlline Contamination The practice of multiple use of protective clothing at Indian Point is to be discontinued. Lab coats and the practice of , . I reusing unlaundered Anti-C clothing will be phased out. l
I . j Instructions designed to prevent the spread of contamination ' from operating bays to adjacent. roadways have been issued. , These instructions involve the areas in which a potential exists for the spread of contamination from the Controlled Area and usually involves the loading of waste shipment trucks. o Jul integral part of instructions for the technicians at the control point established at the V.C. is observation of per- ! sonnel as they exit the V.C. Frisking and step-off pad pro- cedures are observed to assure proper techniques are used. l To further reduce the potential for the spread of conta=in- l ation, decontamination efforts to reduce the level of con- ' tamination and the number of areas contaminated will be in-
I creased during Unit cutages. .. l -e ~ - - -. - . - - - . _ , . . - - , , -- . , - -.
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . - 12 - - 4 . . Training , A contract to provide radiation protection training at the
Indian Point Station has been awarded to NUS Corporation of
Rockville, Maryland. Two separate courses will be given: j ? - . r 1) Basic Radiation Protection Training Course i for gene'al employee ~ training and a
2) Basic Health Physics Technician Training ' > Course
i The Basic Radiation Protection Training course will require , 1-1.5 days of classroom training for each employee. This course is scheduled to begin December 29, 1976 and continue to February 4, 1977. Additional sessions may be required depending upon the availability of plant personnel. The i
basic course will cover health physics fundamentals neces- sary to understand the reasoning behind procedures, rules . . and regulations, reduction of radiation exposure and pro- tection against the spread of contamination in various work- l ing conditions. Basic respiratory protection techniques will be demonstrated in this tmployee training requirements t I listed in 10 CFR 19.12.
! i
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_ _ _ . _ _ _ _ _ _ _ _ ___ .. - 13 - . . . , . .. - - . ' The training outline includes: ,. , Responsibilities Basic Definitions of Radioactivity and Units of - Measurements Biological Effects Exposure Limits Area Definitions and Signs Reduction of Radiation Exposure Measurement of Radiation
? Radiation Work Permit i Protection Against Contamination . Measurement of Contamination Airborne Radioactivity '
o Incidents Evacuations The Basic Health Physics Technician Training Course as out- lined will require about 3 full days. This course is sche- duled to begin on February 6 Three sessions are currently . planned. Additional sessions may be necessary depending on the availability of the Technicians. . w. F* 7 i . _.. . . _ _ _
_- _ _ ___ ______ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . 14 - - . < - . The training outline for the Basic Health Physics Technician ' Course includes: . Detection of Radiation Air Sc.mpling Techniques Techniques in Dose Rate and Contamination Surveys Types and Characteristics of Instrumentation General Shielding Determination Personnel Decontamination Techniques Protective Clothing Requirements Contamination Control General Regulatory Requirements . . 5 5 l ? .. 4 . - . _ _ _ , _ _ . _ _ ,
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