IR 05000443/1986025
| ML20211F995 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/11/1986 |
| From: | Mcfadden J, Shanbaky M, Sherbini S, Weadock T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20211F977 | List: |
| References | |
| 50-443-86-25, NUDOCS 8606190234 | |
| Download: ML20211F995 (17) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-443/86-25 Docket No. 50-443 License No. CPPR-135 Priority
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Category C
Licensee: Public Service of New Hampshire P.O. Box 700 Seabrook, New Hampshire 03874 Facility Name:
Seabrook power Station, Unit 1 Inspection At:
Seabrook, New Hampshire Inspection Conducted: May 5-9, 1986 Inspectors:
,Md MM M-~ N' N (f.McFadden,RadiationSpecialist date
(p 9 T. Weadock, Radiation Specialist
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S. Sherbini, Radiation Specialist date L.
Approved by:
M _5[_Ijs
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d M. Shanbaky, ChlEf, FaciT1 #es Radiation
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Protection Section Inspection Summary:
Inspection on May 5-9, 1986 (Inspection Report No. 50-443/86-25)
Areas Inspected:
Routine, announced preoperational inspection of the occupational radiation protection program including: status of previously identified items, organization and management controls, training and qualifications, external exposure control and personnel dosimetry, internal exposure control and assessment, control of radioactive materials and contamination, surveys, and monitoring, facilities and equipment, and maintaining exposures ALARA.
Three regionally-based inspectors were onsite for this inspection.
Results: No violations were identified.
r606190234 860611 PDR ADOCK 05000443 C=
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DETAILS 1.0 Persons Contacted During the course of this preoperational inspection, the following personnel were contacted or interviewed.
1.1 Licensee Personnel
- H. Anderson, Radwaste Utilities Department Supervisor (NHY)
J. Aune, I&C Technician, (NHY)
M. Campbell, HP Working Foreman, (NHY)
- R. Gregory, Licensing Engineer (UE&C)
- R. Guillette, Assistant Project Construction QA Manager (YAEC)
D. Iseman, I&C Supervisor, (NHY)
- K. Kiper, Licensing Engineer (NHY)
- D. Kochman, Health Physicist, NSG (NHY)
W. Leland, Chemistry and HP Manager (NHY)
- W. Middleton,- QA Staff Engineer (YAEC)
.N. Panzarino, Senior Enginder, RPG (YAEC)
- J. Rafalowski, H.P. Dept. Supervisor (NHY)
- V. Sanchez, Licensing Engineer (YAEC)
- W. Sturgeon, Nuclear Services Manager (NHY)
- J. Warnock, Nuclear Quality Manager (NHY)
S. Westin, Startup Engineer (VTC)
- B. Wolfe, Quality Control Engineer (YAEC)
- Attended the exit interview on May 9, 1986.
Additional licensee employees were contacted or interviewed during this inspection.
1.2 NRC Personnel Attending the Exit Interview A. Cerne, Senior Resident Inspector D. Ruscitto, Resident Inspector 2.0 Purpose The purpose of this preoperational inspection was to review the operational readiness of the licensee's radiation protection program with respect to the following elements:
organization and management controls i.
- selection, training, and qualification of personnel
external exposure control and personnel dosimetry l
. internal exposure control and assessment
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control of radioactive materials and contamination, surveys, and monitoring
facilities and equipment
maintenance of exposures ALARA 3.0 Status of Previously Identified Items 3.1 (Closed); Followup Item (50-443/86-16-01): Further define and document the scope of the Nuclear Services Group's principal health physicist's responsibilities to assist in the appraisal of radiation and contamination control and to evaluate-the overall effectiveness of the Radiation Protection Program. This item is discussed in section 4.0 of this report.
3.2 (0 pen); Follow-up Item (50-443/86-16-02):
Data to support adequacy of beta dose assessment methodology to be gathered / developed.
This item is discussed in section 6.0 of this report.
3.3 (Closed); Follow-up Item (50-443/86-16-03): Availability of dose-calculation-methodology documentation.
This item is discussed in section 6.0 of this report.
3.4 (Closed); Followup Item (50-443/86-16-04): Define who may generate a Radiation Work Permit.
This item is discussed in section 10.0 of tnis report.
3.5 (0 pen); Follow-up Item (50-443/86-16-05): Incorporation of ALARA review recommendations into the Radiation Work Permit. This item is discussed in section 10.0 of this report.
4.0 Organization and Management Controls The licensee's organization and management controls for the radiation protection function were reviewed against criteria contained in:
Seabrook Station Final Safety Analysis Report
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10 CFR 50, Appendix B, "QA Criteria for Nuclear Power Plants"
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Licensee Proposed Technical Specification 6.0, " Administrative Controls"
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Seabrook Station Radiation Protection Program Manual
Seabrook Station Management Manual, Chapter 3, Station Policies; Section 3.3, Interfaces
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The licensee's performance relative to these criteria was reviewed in discussions with licensee representatives and by review of the radiation protection program manual and licensee intra-company business memos.
Documentation of the responsibilities and interfaces between the health physics function and both the radiological chemistry and I&C functions was reviewed. The interface and separation of responsibilities between health physics and radwaste function is being finalized and will be documented in the maintenance program manual. This item will be reviewed in a future inspection.
HP/Radwaste interface documentation Assignment of overall responsibility for the Radiological Environmental Surveillance Program has been delegated to the corporate Nuclear Services Group with health physics providing support services in the area of sampling.
Revisions to the Radiation Protection Program Manuai reflected the
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altered line organization-above the Health Physics Department.
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altered line organization retains the same number of management layers between the Health Physics Department Supervisor and the Station Manager.
A change in the Radiation Protection Manual states the frequency of evaluations of the overall effectiveness of the radiation protection program by the' principal health physicist of the Nuclear Services Group (NSG).
This minimum frequency will also be incorporated into the NSG Management Manual. The licensee stated that this evaluation will be a technical review focusing on effects of changes in the program and on incorporation of new policies and regulations. The principal health physicist's role of assisting in the appraisal of radiation and contamination control was discussed.
This role is to be implemented by review of routinely distributed radiological incident / occurrence reports i
and by direct involvement in the investigation of reports with significant health and safety impact. The procedural change and the further clarification of the scope of the evaluation and review functions adequately addressed an open item (50-443/86-16-01) identified in a I
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previous inspection report.
5.0 Selection, Training, and Qualification The licensee's selection, training, and qualification programs for radiation protection personnel were reviewed against criteria contained in:
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10 CFR 19.12, " Instructions to workers" I
Licensee Proposed Technical Specification 6.0, " Administrative y
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Seabrook Station Radiation Protection Program Manual
Regulatory guide 1.8, " Personnel Selection and Training"
ANSI /ANS 3.1-1978, "American National Standard for Selection and Training of Nuclear Power Plant Personnel" The licensee's performance relative to these criteria was reviewed by discussion with licensee representatives and by review of the rad *ation protection program manual, a licensee intra-company business memo concerning supplemental radiation worker training, and the lesson plan for respiratory protection.
Supplemental radiation worker training for operations personnel, chemistry technicians, and radwaste technicians had been further defined and outlined, and training sessions were scheduled to begin in several weeks. The following area requires further review in a future inspection:
review'of classroom lesson plans and of practical factors segment of supplemental radiation worker training.
The methods for selection and qualification of contractor health physics -
technicians is describad in the Radiation' Protection Program Manual. The licensee's' Procedure HD0 951.04, " Contractor HP Tech Training and Qualification", was not yet in final form and will be~ reviewed in a future inspection.
- HD0951.04, " Contractor HP Tech Training and Qualification"
6.0 External Exposure Control
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The licensee's external exposure control and personnel dosimetry program was reviewed against criteria contained in:
10 CFR 20, " Standards for Protection Against Radiation"
Licensee Proposed Technical Specification 6.0, " Administrative i
l Controls" Seabrook Station Radiation Protection Program Manual The licensee's performance relative to these criteria was determined by
discussions with members of the radiation protection staff, tours of the L
facilities, and review of procedures and records.
An item in a previous inspection report (50-443/86-16-02) identified the
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l need for additional licensee attention to documentation of the licensee's
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technical basis for their beta dose assessment methodology. During this
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inspection, there were additional discussions with the licensee's dosi-metry personnel, and the issue was clarified. The licensee agreed to obtain additional dosimeter response data. This data will be the result of dosimeter irradiations to be performed using Pm-147 beta spectra.
Another open issue from a previous inspection report (50-443/86-16-03)
identified the need for additional documentation for external-dosimetry-calculation methodology.
The licensee has provided a procedure for manual calculation of doses from dosimeter readings. This procedure described the necessary steps for the calculation and provided the equations and
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-parameters to be used in the calculations.
During discussions with the licensee, the fact that computer failure (both computers) would allow access to locked high radiation areas (HRAs)
to any key card holder was identified as a potential problem.
The licensee stated that this situation would be addressed.
This item will be reviewed in a subsequent inspection (50-443/86-25-01).
During a plant walk-down of the areas for which provisions are under way to control as locked HRAs, an unlocked access point to one such area (PDT degassifier) was noted by the inspector and pointed out to the licensee. The licensee stated that an internal review had already recognized this situation and that it sould corrected before the PDT degassier area becomes a locked HRA. This item will be reviewed in a subsequent inspection.
(50-443/86-25-02).
Another area identified as requiring further review in a future inspection was provisions and procedures for locked HRA in containment.
Locked HRAs in containment
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7.0 Internal Exposure Control and Assessment The internal exposure control and assessment program was reviewed against
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criteria contained in:
10 CFR 20, " Standards for Protection Against Radiation"
Licensee Proposed Technical Specification 6.0, " Administrative
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Controls" i
Seabrook Station Radiation Protection Program Manual i
g Seabrook Health Physics Department Operating Procedures
Regulatory Guide 8.15, " Acceptable Programs for Respiratory Protection" t
Regulatory Guide 8.26, " Applications of Bioassay for Fission and l
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- NUREG-0041, " Manual of Respiratory Protection Against Airborne Radicactive Materials"
ANSI N13.1-1969 (R1982), " Sampling Airborne Radioactive Materials in Nuclear Facilities"
ANSI N343-1978, " Internal Dosimetry for Mixed Fission and Activation Products" The licensee's performance relative to these criteria was determined by discussions with members of the radiation protection staff, review of procedures and records, tours of the respiratory protection and internal dosimetry program's facilities, and observation of respirator - fit-booth testing and of whole-body counting.
7.1 Administrative Controls Provisions for supervisory review and evaluation of RWPs for adequacy of-protective equipment required and of pre-job surveys required were reviewed.
The licensee stated that a health physics foreman would be continuously present at the main radiological control point.
A health physics foreman will be reviewing each RWP generated and all data which becomes attached (such as RWP sign-in sheets, SRPD results, air sampling data, other radiclogical surveys, etc.) to i.
completed RWP package before filing.
In addition, all active RWPs are reviewed at least once per week by a health physics supervisor.
Daily review of the exposure status review (ESR), which provides a list of the current individual exposures and exposure limits, accumulated MPC-hours, and alert status, is used as the checkpoint on the MPC-hour calculation process. Daily QC performance data for the whole-body counter and all whole-body counting data receive super-visory review and sign-off.
7.2 Engineering Controls In this area, discussions with the licensee addressed the following:
permanent ventilation systems designed to provide air flow paths from areas of low potential airborne radioactivity areas to potentially high areas and to provide adequate face / capture velocities for hoods / local exhausts and the use of temporary ventilation systems, to the extent practicable, to limit concentrations of airborne radioactivity.
- the use of contamination containments
use of alarming airborne radioactivity monitors at strategic locations
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The licensee has documented a policy to consider the use of engineering controls by statements in the respiratory protection program section and ALARA program section of the Radiation Protection Program Manual and in the operational RWP procedures.
The licensee stated that tent and drip contamination containments
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were available but that the portable ventilation units ordered had not yet arrived. The licensee is evaluating the feasibility of.
using tents for future work on open steam generators based on the limited space available around the steam generators and evaluating alternate containment methods. The licensee has also established a need for a procedure for the use of contamination containments and associated air-handling equipment.
Presently, the available types of voice communication systems for high dose jobs are being reviewed, and no such equipment has yet been selected.
The licensee
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has available and plans to use movable, alarming, continuous-air monitors at strategic locations on a routine basis.
The'following areas / items require further review in a future inspection:
normal plant ventilation system design and testing k
availability of portable ventilation units and procedures for i
use and maintenance 7.3 Respiratory Protection Equipment In response to the inspector's concern about having the respiratory protection policy stated in a higher level administrative document
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than the Radiation Protection Program Manual, the licensee demonstrated that they had already addressed this issue and that a policy statement for inclusion in the Seabrook Station Management Manual was already ready for SORC review.
During review of respirator fit-test procedures, observation of fit-test-booth use, and discussions with the licensee, the inspector noted that only vendor-trained personnel were to be authorized to i
repair respiratory protective equipment. The licensee stated that qualitative fit-testing was only planned to be used in the case where the fit-test booth is not available due to technical difficulties.
There is a procedure covering the qualitative fit-test protocols to l
be used.
Qualitative fit-test protocols will be periodically re-i evaluated on the basis of updated consensus-standard protocols. A minimum fit-factor of 1000 is required when the respirator fit-test booth is used.
The following items require further review in a future inspection:
approved procedure for use of supplied-breathing-air equipment i
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approved procedure for testing supplied-breathing-air quality and for recording test results availability of supplied-breathing air system 7.4 Air Sampling for Assessing Individual Exposure Presently, the procedure covering the routine air sampling program only calls for air sampling'on three levels in the PAB during the months of June through September.
This building has temperature-actuated exhaust fans, and this particular air sampling is intended to provide an estimate of potentially contaminated air that may be exhausted via this path.
The licensee stated that at start-up extensive air sampling throughout the plant will be conducted to identify areas to be added to the routine air sampling program.
The administrative dose control procedures state that air sampling and monitoring throughout the RCA will be directed to monitor ambient airborne conditions and to identify trends and potential problems.
They also state that breathing-zone-area air samples are drawn in preference to general-area air samples.
This is the case when work, with the potential for generation of high levels of airborne radio-activity, is in progress.
The operational RWP procedure requires that airborne conditions be specified based on current data or that they be determined.
The provisions for assessing the significance of alpha and pure beta-emitting airborne radionuclides were discussed with the licensee.
The licensee's Procedure No. HD0958.07, Monitoring for Transuranic (TRU) Radionuclides, calls for routine smear analyses to determine the beta / gamma to alpha ratio as a mechanism to track the significance of TRU activity.
The procedure requires increased smear ratio determinations and air sample ratio determinations when the routine smear ratio determinations drop below predetermined values.
The procedure also requires that analysis for radioisotopic identification be performed periodically but does not require solubility analyses. The licensee stated that solubility analyses will be performed if the ratio falls below a predetermined ratio value.
The licensee also stated that HP review of radiochemical data from reactor coolant analyses will be the mechanism used to track and detect increased significance of pure beta emitters.
These previously mentioned mechanisms are used to support the use of MPC values of 3E-11 (Pu-238)(insoluble) and 9E-9 (Co-60)(insoluble) for unidentified TRVs and unidentified beta / gamma emitters, respectively, for evaluating the significance of air sampling data.
These areas will require further review in a future inspectio.
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- extent of routine air sampling at start-up
basis for MPCs used for unidentified airborne radioactivity l
LLDs for airborne radioactivity determinations 7.5 Bioassays This area was reviewed by touring the bioassay facilities, discuss-
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ions with licensee personnel, observing whole-body counting, and
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reviewing calibration and QC data and whole-body counting procedures and records. Through the use of an integrated computer software option, there is a provision for estimating MP_C-hour exposures (assuming exposure occurred at time of counting) from whole-body counting data. There is also a procedural provision for reviewing in vivo measurements so that trends will be detected. At the time of this inspection, there was not an approved procedure for calibration of the whole-body counter.
The licensee committed to have such a procedure in place by the time of initial fuel load. This item will a
be reviewed in a future inspection (50-443/86-25-03).
At the time of this inspection, a procedure (s), for review of bio-assay results with actions to be taken based on those results and for calculating MPC-hours from bioassay data for correlation with MPC-hours from air sampling data, was (were) not available. The licensee committed to have an approved procedure (s) within six months. This item will be reviewed in a future inspection (50-443/86-23-04).
The following items will require further review in a subsequent inspection:
Technical Basis document for the whole-body counter
quality assurance program for in vitro bioassay 8.0 Control of Radioactive Materials and Contamination, Surveys, and
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Monitoring Licensee programs for the control of radioactive material and contamination and the performance of in plant surveys originally received an overall review in NRC Inspection No. 50-443/86-16.
The current inspection focused on two elements within this area:
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changes and additions to the licensee's supply of survey and sampling instrumentation, and; i
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startup testing, turnover, and calibration of the Radiation Data
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Management System (RDMS).
8.1 Portable Survey, Sampling, and Contamination Monitoring Instruments Previous review (NRC Inspection No. 50-443/86-16) of-the licensee's survey and sampling instrumentation indicated that ample instrumentation was available to provide the capability for performing an adequate survey and sampling program. However, specific instrumentation committed to in Table 12.5-1 of the FSAR was not available during the previous inspection. Outstanding instrumentation necessary to meet these commitments included:
A minimum of two portal monitors An additional two continuous air monitors (CAMS)
An additional 1300 pocket dosimeters.
A concern was also raised during the previous NRC inspection regarding the licensee's intent to use two high-range GM survey instruments in partial fulfillment of the high range ion chamber detection capability committed to in the FSAR.
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The licensee has ordered additional high-range ion chamber portable survey instruments and no longer intends to use GM survey instruments to meet this commitment.
Discussions with cognizant licensee personnel concerning procurement of supplies and instrumentation indicate the following:
Additional pocket dosimeters have been withdrawn from the warehouse and are being tested and calibrated prior to entry into HP inventory.
The committment for two additional CAMS is being met with the use of two GA CAMS originally intended for Unit 2.
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additional two NMC CAMS are being ordered.
- Two Gamma-10 portal monitors have been ordered and will be placed at the guardhouse for monitoring worker exit.
Four IPM-7 standup frisking units have also been ordered; two will be placed at the current control point and two will be used for the intended contractor control point.
The inspector reviewed the licensee's inventory of portable survey instrumentation and the various departmental procedures to insure that both an instrument use and a calibration procedure is available
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for each instrument type.
The inspector noted that no approved
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instrunent use procedure exists for two instruments: the E-520 and the Mini-Rad.
It was also noted that no procedure exists for the
routine sourEe checking of portable survey instruments.
The licensee. indicated that a revision to proceoure HD0955.05,
" Operation of Portable Radiation / Contamination Instrumentation",
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currently in draft form, contains appropriate refer 6nce to the Mini-Rad and the E-520.
The licensee committed to having.this procedure in an approved form prior to fuel load.
The licensee also indicated that posted, controlled instructions are available next to the cart where daily instrument source checks are performed.
This was verified by the inspector.
The licensee additionally indicated that procedure HD0955.31, " Survey Instrument Source Checks",
currently in draft form, would be in an approved form prior to fuel load. Status of these procedures will be reviewed in a subsequent inspection:
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review portable instrument use and source eneck procedures 7 Review of the performance of instrument calibrations in complian'ce with controlling procedures and the review of specific instrument calibration results was not covered during this inspection.
This area will be addressed in a subsequent NRC inspection:
review portable survey instrument calibration 8.2 Radiation Data Management System The licensee's Radiation Data Management System (RDMS) includes area radiation monitors, airborne radioactivity monitors and process and effluent radioactivity monitors and samplers.
The system, supplied
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by,GA. Technologies, links the various detector outputs via a computer hookup to dimlay terminsis in tne Cor. trol Room and at the Health Physics Conto) toint.
NRC inspection effort in this area included a reviar if n-tem testing status, verification of monitor installation, an<
ev' i of monitor calibration procedures.
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_RDMS Testing Status The RDMS consists of seventy-seven fixed location and four mobile monitors. The system is currently in the process of being testea
.and turned over from the startup testing group to the plant
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operating staff.
At the tine of this inspection,_ forty-two monitors were tested and turned over to the plant staff; an additional twenty-two monitors were scheduled to be tested and turned over by May~19, 1986.
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Specific monitors which have been identified by the NRC preopera-tional review team as being applicable to the in plant Health Physics operations are listed in Attachment 1.
This list includes all area radiation monitors and specific in plant airborne activity monitors.
Column 4 of this attachment designates the testing status for each monitor.
Area radiation monitors Nos. 6535A and B and airborne activity monitors Nos. 6506A, B and 6507A, B all have control functions upon detection of a high radiation signal.
The inspector reviewed startup test procedure #1-AT-30, " Radiation Monitoring System Control Inter-face Test," and verified control functions for these monitors were tested.
8.2.2 Verification of Monitor Installation The inspector and selected licensee representatives performed in-field inspection of approximately seventy-five percent of the monitors listed in Attachment I during this inspection to verify installation.
Location and positioning of the various monitors generally appeared adequate for detecting changes in radiological conditions; however two concerns were identified:
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The inspector noted that the air sampling line for the containment air monitor (#6526-1, 2) may not be appropriately situated to obtain a representative sample of containment air.
This line enters containment at approximately - 3 foot elevation, continues for six inches, makes a right angle horizontal bend, and terminates after a straight 12-18 inch run.
Containment air is consequently sampled at a low point in containment within one-half foot of the containment wall.
The licensee produced two memos, dated April 18 and April 25, 1986, which indicated this potential problem had been identified by the licensee.
These memos discussed the licensee's plans to have an outside group perform an evaluation of the sample line location. This study had been previously scheduled but was cancelled due to a shift in the containment leak rate testing schedule. The licensee indicated that an evaluation of the containment air monitor sample location will be performed the next time containment integrity is established, tentatively in June 1986.
The results of this evaluation will be reviewed during a subsequent inspection (443/86-25-05).
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During the RDMS walkdown the inspector noted that the viewing area of certain area monitors is partially blocked or limited by adjacent components.
Examples include the Personnel Hatch monitor (#6536) and the Waste Gas Process Area Monitor (#6551).
The licensee indicated that any positioning problems with the various monitor detectors would be identified during the Health Physics turnover
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review of the system. The Health Physics review of detector location and suitability will be re-examined at a-later date pending completion of the Health Physics turnover review of the system.
Licensee turnover review of RDMS.
8.2.3 RDMS Calibration Calibration and maintenance of the RDMS system will be performed by the plant I&C department once the system has been turned over. The inspector reviewed selected training records and a course syllabus for a four week training course conducted by GA Technologies and determined the Seabrook I&C department has received adequate training on the RDMS system to perform required testing and maintenance.
Secondary transfer sources were provided by the vendor with the RDMS.
These sources are to be used by the licensee to perform in-field calibrations and provide the requisite link back to the original primary calibrations performed by the vendor. This secondary calibration will be used for the initial and follow-up calibrations for the majority of the monitors listed in Attachment I, as indicated in column 5.
However, the licensee has identified specific monitors, due either to their importance or an inability to meet the secondary calibration acceptance criteria, which will receive an initial, primary calibration by the licensee.
These are identified in Attachment I.
The inspector reviewed the status of I&C monitor calibration procedural development.
Column 6 of Attachment I indicates whether calibration procedures were approved and ready for use, under review, or in draft form at the time of this inspection.
Additionally, the inspector reviewed the following draft procedures controlling calibration of the various representative types of monitors (i.e., GM tube, ion chamber, gamma scintillator, beta scintillator).
- IN1660.815, R-6505 Condensor Air Evacuator Discharge Radiation Monitor Calibration,
- IN1660.813, R-6503 Waste Gas Compressor Inlet Radiation Monitor Calibration,
- IN1660.632, R-6555 Administration Building Hot Chemistry Laboratory Radiation Monitor Calibration,
- IN1660.604, R-6518 Fuel Storage Building Spent Fuel Pool High-Range Monitor Calibratio _
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- IN1660.722, R-6531 Waste Processing Building Ventilation Exhaust Radiation Monitor Calibration.
The above procedures appeared adequate for performing in-field secondary monitor calibrations.
Results of individual monitor calibrations will be reviewed during a subsequent inspection in this area:
review calibration data for selected RDMS monitors.
9.0 Facilities-and Equipment Facilities and equipment, not covered during the reviews of other radiation protection program areas, were insp'ected. The areas inspect 2d included:
facilities, equipment, and procedures for decon and repair of contaminated materials / equipment locations for storage of contaminated materials / equipment areas and equipment for personnel decon areas for issue of, dressing in, and storage of protr.ctive clothing availability of temporary shielding materials The following items were identified as requiring further review:
adequacy of facilities and equipment for decon, repair, and storage of contaminated materials / equipment
accountability / control of contaminated equipment es radioactive material
procedures for decon of contaminated equipment 10.0 ALARA The inspector reviewed several procedural changes affecting ALARA program implementation made since the last NRC review of this area (NRC report No. 443/86-16). That inspection identified that the licensee's procedures did not clearly define who may generate a Radiation Work Permit (RWP), or require the attachment of an ALARA review to the RWP.
The following procedures were reviewed during this inspection:
H00958.13, " Generation and Control of Radiation Work Permits and Standing Radiation Work Permits,"
RP6.1, " Requesting and Use of RWP/SRWPs.
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.The inspector verified that procedure RP6.1 now states that a Health Physics Technician is responsible for generating an RWP.
Proposed revisions have been made to procedure HD0958.13 to require the attachment of any completed ALARA review to the RWP; however, at the time of this inspection this procedure had not received final review and approval.
The inspector also reviewed the licensee's draft copy of procedure HD0
'959.01, " Radiation _ Exposure Performance Assessment". This procedure, currently in the -review process, describes the ALARA group's job performance review frequency and indicates when outage reports will be
generated. The current draft copy of this procedure appears adequate for controlling these activities but will receive further NRC review after it is approved for use by the licensee:
review approved procedure HD0959.01 11.0 Exit Interview The inspectors met with the personnel denoted in section 1.0 at the i
conclusion of the inspection on May 9, 1986. The-scope and findings of the' inspection were discussed at that time. At no time during this inspection was written material provided to the licensee by the NRC inspectors.
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Attachment i Status of RDMS Monitors with in-Plant HP Applications Ca l i b ra t ion Moni tor No.
De sc ri pt ion Tvoe Status Ca l i b ra t ion P rocedu re 6534 i n-co re Instrument Seal Table Area P
App roved 6535A,8 Manipulator Crane Area S
Under Review 6536-1,2 Personnel Hatch ( Post LOCA)
Area S
Under Review 6529 Cavity beneath Reactor Vessel Area P
D ra f t fo rm 6537 Chemistry Sampling Room - PAB Area P
App roved 6538 RHR Pump - PAB A rea P
App roved 6539 RHR Pump - PAB A rea P
App roved 6540 Volume control Tank - PAB A rea P
D ra f t Form 6541 PAB Lower Level A rea P
App roved 6542 PAB Lower Level Area P
App roved 6543 PAB Entrance Area P
App roved 6544 PAB Entrance Area P
App roved 6545 Cha rging Pump Area - PAB A rea P
App roved 6546 Cha rg ing Pump Area - PAB A rea P
App roved 6547 Cha rging Pump Area - PAB Area P
App roved 6549 Spent Fuel Pool Area - FSB A rea P
under Review 6576A,8 Containment (Post LOCA)
Area P
D ra f t Fo rm 6508-1,2 PAB - HRAM A rea P
D ra f t Form 6563-1,2 PAB - HRAM Area P
D ra f t Fo rm 6517-1,2 RHR Pump Vault HRAM-PAB A rea P
D ra f t Fo rm
6518 Spent Fue l Area HRAM - FSB Area P
D ra f t Fo rm 6550 Con t ro l Room Area P
App roved 6551 Waste cas Process Area - WTB Area P
Under Review 6552 Encapsulation Area - WTB Area P
App roved 6553 Drumming Station - WTB Area P
Under Review 6554 Waste Management Area Control Panel Area P
Under Review 6570 Solidified Radwaste Storage Area - WTB Area P
Dra f t Form 6571 Compacted Radwaste Storage Area - WTB A rea P
Under Review 6555 Hot Chemistry Lab - A&S Bidg.
Area P
App roved 6556 Decontamination Room - A&S Bldg.
A rea P
under Review 6557 RCA Shop - A&S Bldg.
A rea P
Under Review 6558 RCA Mens Locker Room - A&S Bldg.
Area P
Under Review 6559 RCA Women's Locker Room - A&S Bldg.
A rea P
Under Review 6506A Control Room East Air intake Ai rborne Act.
P
App roved 6506B Control Room East Air intake Ai rborne Act.
P
Under Review 6507A Control Room West Air Intake Ai rborne Act.
P
D ra f t Fo rm 65078 Control Room West Air intake Airborne Act.
P
Under Review 6526-1,2 Conta inment Ai r ( Pa rticulate, Cas) Ai rbo rne Ac t.
P
Dra f t fo rm
- Status ( S, P):
S= Under Sta rtup testing, P = Turned over to plant staff; based on predicted monitor turnover by Mry 19, 1986
- Ca l ibrat ion (1,2): 1 =
Prima ry ca l ibration to be re-done by licensee, 2 = Secondary calibration only to be done by 1icensee.