IR 05000423/1985019
| ML20126M117 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/10/1985 |
| From: | Cioffi J, Shanbaky M, Jason White NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20126M097 | List: |
| References | |
| 50-423-85-19, NUDOCS 8506200240 | |
| Download: ML20126M117 (18) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-423/85-19 Docket No.
50-423 License No. CPPR-113 Priority
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Category C
Licensee:
Northeast Nuclear Energy Company P.O. Box 270 Hartford, Connecticut 06141-0270 Facility Name: Millstone Nuclear Power Station, Unit No.3 Inspection At: Waterford, Connecticut Inspection Conducted: May 7-10,1985/
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Inspectors:
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J. R.
it 5e ~ r~ ad t'i Specialist
/ dat'e,-
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[t [j J. A.pofff, Radiation Sp'ecialist
/dat6 Approved by:
-9ff I//
///4[M M. M. ~ShanbaEy, Chief, PWRydiation
' date Safety Section Inspection Summary:
Inspection on May 7-10, 1985 (Report No. 50-423/85-19)
Areas Inspected:
Routine, unannounced safety inspection to review pre-opera-tional status of areas pertaining to radiation protection and radioactive waste i
management, including organization, personnel training and qualifications, fa-
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cilities and equipment, and procedure development.
The inspection involved 70 hours8.101852e-4 days <br />0.0194 hours <br />1.157407e-4 weeks <br />2.6635e-5 months <br /> onsite by two region-based inspectors.
Results:
No violations were identified within the areas inspected.
8506200240 850612 PDR ADOCK 05000423 G
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DETAILS 1.0 Persons Contacted
- W. D. Romberg, Station Superintendent
- R. Herbert, Station Services Superintendent
- 0. Miller, Startup Manager K. Gray, Staff Assistant
- F. Perry, Assistant Radiation Protection Supervisor
- B. Granados, Health Physics Supervisor M. Pearson, Operations Assistant
- R. Sachetello, Radiation Protection Supervisor M. Brown, Instrument and Control Supervisor
- R. Enoch, Instrument and Control Group Leader
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P. O'Connell, Staff Assistant
- R. Lager, Chemistry Supervisor
- L. Wadeau, Northeast Utilities Staff
- Denotes attendance at the Exit Interview conducted May 13, 1985.
2.0 Purpose The purpose of this inspection was to review the pre-operational status of the unit in regard to radiation protection program development.
Included in this review was examination of organization and management controls, personnel training and qualification, facilities and equipment, and status of procedures for surveys, contamination control, and initial startup surveillance.
3.0 Status of Previously Identified Items
3.1 (Closed) Bulletin (78-BU-07) Protection Afforded by Air-Line
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Respirators and Supplied-Air Hoods.
The licensee's procedure SHP 4931, Rev. 3, dated April 9, 1985, pertains to issuance and use of air-line respirators and supplied air hoods. The procedere contains instructions that are consistent with the precautionary provisions of the bulletin and adequately addressed all of the concerns that were identified.
3.2 (0 pen) Bulletin (78-BU-08) Radiation Levels From Fuel Element Transfer Tubes FSAR 12.3.1.2 implies that Fuel Element Transfer Tube shielding has been enhanced at the Containment wall interface and in the space between the Containment and Fuel Handling Building. An internal memorandum, NES-24078, dated April 16, 1981 also indicates that the shielding had been modified for a design basis of 50 millirem / hour
at the shield and 5 millirem per hour at the personnel access hatch;
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and referenced drawings 12179-EC-51R for the in-containment modifi-cation and 12179-EL-49R for the modification to the fuel element-tube between the Containment and Fuel Handling Building. The FSAR further described a security fence in place to prevent inadvertent occess to the space between the Containment and Fuel Handling Buildings.
The security fence was not installed, but is being carried as an open item by the licensee pending the completion of construction in the area. The licensee was able to produce drawing 12179-EV-261A-2,
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which is depicted in the FSAR, but was unable to produce as-built drawings, or drawings 12179-EC-51R and 12179-EL-49R that described the shielding applied to the tube.
This item remains open pending verification of shielding and FSAR statements by review of associated as-built drawings, and the instal-lation of the security fence between the buildings.
3.3 (0 pen) 76-CI-03 (Circular) Radiation Exposure in Reactor Cavities.
The licensee has not initiated any action to address the concerns expressed in this circular.
Review of the Containment Building and accesses to the areas under the reactor vessel and adjacent to thimble guide tubes indicate that significant action in terms of engineered controls and administrative procedures need to be developed.
4.0 Fuel Receipt Activities The licensees actions relative to fuel receipt were examined against the following criteria:
Operation Procedure 3211A, "New Fuel Assembly and RCCA Receipt and
Inspection" Rad Waste Procedure RW36006, " Receipt of Radioactive Material"
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Health Physics Procedure HP4905, " Radiological Surveys"
Special Nuclear Material License Application, dated January 28, 1985
Supplement to Special Nuclear Material (SNM) License Application,
dated March 20, 1985 Special Nuclear Material License No.1950, dated April 16, 1985
On May 8, 1985 the inspector witnessed the licensee's efforts relative to receipt of seven containers of new fuel (container nos. 82, 45, 77, 144, 115, 156 and 137).
The licensee's staff performed extensive surveys of the truck and contents; and provide escort to the Fuel Handling Building.
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Areas were properly posted and personnel restrictions and RWP requirements were established.
Continuous coverage was maintained during all fuel
inspections and transfer activities.
The personnel providing radiological control were verified to have been trained and qualified in accordance with the SNM license conditions.
Sufficient radiological surveys were taken and evaluated during work
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performance, including venting of containers prior to opening. All survey results were recorded and documented with the fuel receipt packages.
No unexpected loose surface contamination was found., and dose rates in close proximity to the new fuel were less than 5 millirem per hour.
Personnel dosimetry was required for all personnel involved in the fuel receipt activity.
The licensee's performance was determined to be in accord with the condi-tions of the SNM license.
5.0 Radiation Monitoring System The Millstone Unit No. 3 Radiation Monitoring System (RMS) is a micro-processor based network of process and area monitors designed to detect, indicate, annunciate and record radioactivity levels associated with operation of the plant.
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The as-built system includes, fifteen ventilation monitors with dual chan-
nel capabilit" sixteen liquid process monitors, and thirty-seven area l
radiation monitors.
Control of all functions, such as recording, display, and computation is centralized in the RMS computer system which consists of two PDP 11/34
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minicomputers.
The computers are normally linked by synchronous serial
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interfaces but can be operated independently for diagnostic and software development purposes.
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The system is controlled by an operator console in the control room, a l
color CRT, a keyboard and a printer to produce a picture of the CRT l
displays. A second-terminal is located in the health physics facility
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space.
The monitors are linked to the computer system by seven data loops, two for IE monitors and five for non-1E monitors.
Two Category 1E control
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room cabinets are provided for recording, indication and control of the 1E monitors for the purpose of alarm scanning, data logging, display, data i
i recording and retrieval.
Since the RMS system is an integral part of the plant design, there was concern when the vendor agency, KAMAN Instruments, Inc., became incapable
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of supporting the system. However, the licensee's Instrument and Control, and Computer Support organizations were able to acquire significant detail and information concerning the design of the system including hardware and software components; and have amassed a technical capability that appears able to continue with the startup, test, maintenance and repair of the system.
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As of May 10, 1985, the status of the system was as depicted in Attach-ment 1.
The operational status of the RMS will continue to be followed in subsequent inspections of this area. (50-423/85-19-01)
The licensee has initiated surveillance procedure development (i.e., for operation, testing and calibration) for RMS units that are expected to be addressed by Technical Specifications. Attachment II depicts the status of these procedures as of May 4, 1985.
RMS devices which are not addressed by Technical Specification are operated, tested and calibrated in accordance with generic procedures developed for each instrument type. Attachment III depicts the status of
these procedures as of April 24, 1985.
- ThestatusofRMSprocedureswillcontinuetobefollowedinsubse(uent inspections of this area.
(50-423/85-19-02)
While the RMS system and associated procedures are not yet complete, remaining actions have been scheduled to support full system operability by start-up.
Sufficient management attention has been directed to this area and system status is being monitored on a weekly basis to assure system readiness.
Health Physics personnel, though having responsibilities to monitor and utilize the RMS, have not been subjected to any training on the capabi-lities of the system, operation, and how to interrogate the system. A simulated system has been established for reactor operator training, but has not been used for instructing health physics personnel.
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l This item will remain open pending completion of training for health physics personnel in RMS operation.
(85-423/85-19-03)
l No violations were identified in this area.
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6.0 Status of Start-up Survey Procedure The licensee's startup procedure was reviewed against Regulatory Guide 1.68, " Initial Test Programs for Water-Cooled Nuclear Power Plants", and
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Final Safety Analyses Report, Chapter 14, " Initial Startup Test Phase" to
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establish the status of planning for initial surveys for power ascent.
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Procedures for startup surveys have not yet been developed, however, the responsibility for writing startup survey procedures has been assigned to i
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the corporate Health Physics staff.
In addition to using TLDs on phantoms and performing gamma and neutron surveys of +he containment penetration areas, licensee representatives stated that hey plan to test the response of the GM detectors and ionization chambers in the subatmospheric condi-tions of the containment during power ascent.
The procedure for the startup survey will be reviewed in a future inspection (50-423/85-19-04).
7.0 Radiation Protection Organization and Staffiag The licensees radiation protection organization and management controls was reviewed against:
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Millstone 3 Final Safety Analysis Report, Chapter 12, " Radiation Protection"
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Millstone 3 Final Safety Analysis Report, Chapter 13, " Conduct of Operations" The radiation protection organization for Millstone Unit 3, as depicted in Figure 1, parallels the organization already in place for Units 1 and 2.
The Station Superintendent has the ultimate responsibility for the health physics program.
The Radiological Services Supervisor reports directly to the Station Superintendent and implements the program for all three Millstone units.
Reporting to the Radiological Services Supervisor is the Health Physics Supervisor.
The Health Physics Supervisor for the Millstone site manages three Radia-tion Protection Supervisors, one for each unit, and one Radiation Protec-t!on Supervisor-Support, who administers the external dosimetry program, wrole body counting program, respiratory protection program and the maintenance and calibration of radiation instrumentation for Units 1 and 2.
Discussions with licensee representatives indicated that the Radiation Protection Supervisor-Support will supply support activities for Unit 3 also.
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The Radiation protection supervisor of Unit 3 has one assistant radiation protection supervisor and ten technicians to administer the health physics program at Unit 3.
Additional contractor support will be acquired as needed for startup.
8.0 Personnel Selection, Training and Qualifications The training and qualifications for the radiation protection staff were reviewed against:
Millstone 3 Final Safety Analysis Report, Chapter 12,
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" Radiation Protection" Regulatory Guide 1.8, Revision 1, " Personnel Selection and Training"
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ANSI N18.1 - 1971, " Selection and Training of Nuclear Power Plant Personnel" Regulatory Guide 8.8, "Information Relevant to Ensuring that
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Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable" Regulatory Guide 8.27, " Radiation Protection Training for Personnel
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at Light-Water-Ccoled Nuclear Power Plants."
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All radiation protection staff attended a two week health physics course taught at the corporate training center in Berlin, Connecticut.
In addf-tion, a Unit 3 systems course was given for the Unit 3 health physics technicians to acquaint them with the systems and layout of the plant.
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The Millstone site training facility conducts additional training courses, such as Emergency Monitoring Training. Annual Requalification Training of the health physics personnel is scheduled to take place in June, however, the lesson plans have not yet been written. These lesson plans containing course content, and the results of the requalification of personnel will be reviewed in a subsequent inspection (50-423/85-19-05).
All radiation protection personnel met the qualifications specified in the Final Safety Analysis Report.
9.0 Portable Survey, Sampling and Contamination Monitoring Instruments The supplies of equipment for Unit 3 were reviewed against commitments made in the Final Safety Analysis Report, Chapter 12, " Health Physics Program", by discussions with the Radiation Protection Supervisor-Unit 3, the Radiation Protection Supervisor-Support, the Assistant Radiation Protection Supervisor, a tour of the instrumentation storage facility,
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and observation of the supplies of equipment.
The inspector found sufficient supplies of all portable survey, sampling, and contamination monitoring instruments, with the exception of one type of alpha scintillation ratemeter specified in the FSAR.
Discussions with licensee personnel indicated that the range specified for the alpha scin-tillation rate meters (0-2 million DPM) was not typical for alpha counting equipment.
There are sufficient supplies of alpha ratemeters in the range of 0 to 500,000 disintegrations per minute on site.
Licensee represen-tatives stated that this matter would be reviewed, and resolved prior to start-up.
The status of this item will remain open until reviewed in a subsequent inspection (50-423/85-19-06).
The inspector examined the supplies of emergency equipment placed outside of the control room.
There was sufficient supplies of calibrated instru-mentation, pumps for air sampling, and protective clothing, and a copy of emergency procedures in the locker in the event of an emergency.
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10.0 Equipment for Personal Dosimetry The inspector reviewed the supplies of pocket dosimeters (PICS) against the commitments made in the FSAR. Although there were sufficient supplies of PICS in the ranges 0 to 500 milliroentgens, 0 to 2000 milliroentgens,
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and 0 to 100 roentgens, the PICS in the ranges 0 to 1000 milliroentgens and 0 to 5000 railleroentgens were not in sufficient numbers with respect
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to the committents in the FSAR. Additionally, there were insufficient supplies of pocket dosimeter chargers in.the health physics office at Unit 3.
The supplies of this equipment will be reviewed in a subsequent
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inspection (50-423/85-19-07).
11.0 Facilities i
The facilities associated with the radiation protection program were re-viewed against the plan presented in Millstone Unit 3 Final Safety Analysis Report, Chapter 12, " Health Physics Program".
The. licensee's provisions and capabilities were determined from discus-
sions with licensee personnel, and a tour of the health physics and chemistry facilities, and the plant.
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The arrangement of the health physics facilities is currently unresolved.
Discussion with Unit 3 personnel indicate that the facility, as described
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in the FSAR, does not have sufficient space for calibration of equipment, personnel and equipment decontamination, storage of equipment and sup-plies, a counting room sufficient for the requirements of the equipment, i
I facilities for the whole body counter, respiratory protective equipment,
and dosimetry issue.
Licensee management is aware of the lack of suffi-cient space at the Unit 3 facility and is considering additional buildings centrally located to the three units for Health Physics activities.
i However, in the interim, there are sufficient facilities available to perform whole body counting; and respirator and dosimetry issuance at Units 1 and 2.
It is currently the licensee's plan to remove physical barriers
i between Unit 3 and the rest of the site by start-up to take advantage of facilities at Units 1 and 2.
This matter will remain open pending the decision on the use of space and facilities for Health Physics functions of Unit 3 (50-423/85-19-08).
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l 12.0 Status of Health Physics Procedures for Surveys and Contamination Control i
The inspector reviewed the Health Physics procedures relative to the l
criteria contained in:
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10 CFR 20.101, " Radiation dose standards for individuals in
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restricted areas" 10 CFR 20.201, " Surveys"
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l-10 CFR 20.202, " Personnel Monitoring"
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10 CFR 20.203, " Caution Signs, Labels, Signals, and Controls"
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Final Safety Analysis Report (FSAR), Chapter 12, " Health Physics Program"
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The licensee's provisions and capabilities related to the above criteria were determined from discussions with licensee personnel, a review of the procedures for surveys and contamination control, and a tour of the plant.
Unit 3 personnel have generally adopted the current and approved proce-
dures developed by the corporate health physics staff and Units 1 and 2.
With few exceptions, these procedures define a program of acceptable radiological control for Unit 3 activities. The licensee continues to make unit specific changes as necessary.
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Contamination control for Unit 3 is still being developed.
Discussions with licensee representatives indicate that areas within the containment, auxiliary building, fuel handling building, engineered safety features t
building, and turbine building have been informally evaluated for frisking stations, portal monitors, and dressing facilities.
The licensee plans to utilize the same type of contamination control used in Unit 2 (that is, dressing areas and frisking areas located very close to sources of con-tamination to prevent spreading contamination to otherwise clean areas).
i Within the scope of this review, the following concerns were raised with
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two existing procedures:
Procedure SHP 4909, Revision 0, " Personnel Monitoring and Decontam-
ination" states in step 8.3.5 that Health Physics personnel or l
medical personnel could decontaminate the eyes, ears, nose, or throat i
of contaminated personnel using an isotonic solution and flushing the areas. The inspector determined that health physics personnel were
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not trained in proper flushing of eyes, ears, nose, and throat, and in the use of isotonic solutions for such situations. Additionally, I
the procedure for skin decontamination listed eleven steps using increasingly corrosive chemicals.
The licensee was unable to provide evidence that such chemicals and treatments were available.
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Procedure SHP 4905, Revision 6, " Radiological Surveys", contained
typographical errors in equations used to determine alpha activity.
Also the self-absorption factor was not included in the calculation of activity on filter papers.
In the same procedure, in counting filter paper wipes for beta activity, the procedure stated to fold paper over the filter and f
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count the wipe in that configuration to prevent accidental contam-ination of the counting equipment.
However, no correction was made for the efficiency of counting beta activity with paper over the wipe.
The licensee stated that these procedures were under current revision and some of these deficiencies were already identified. These pro-cedures will be reviewed in a future inspection (50-423/85-19-09).
13.0 Exit Meeting The inspectors met with licensee representatives (denoted in Paragraph 2)
on May 7, 1985, to discuss the scope and findings of the inspection. At no time during this inspection was written material provided to the licensee by the inspector.
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ATTACHMENT 1 Radiation Monitoring System Status Instrument Turned Field Communications Number (Mark No.)
Over Tested Loop Established Comments Ventilation / Gas Monitors
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3HVRRE10A/B 3-4 mos. before testing 3HVRRE19A/B 3-4 mos. before testing 3HVRRE11A/B X
Being Tested 3HVRRE12A/B X
Test Starts 5/10 3HVRRE13A/B X
Being Tested 3HVRRE14A/B X
Test Starts 5/13 3HVRRE15A/B X
Test Starts 5/13 3HVRRE16A/B X
Being Tested 3HVRRE17A/B X
X Fuel Building P/G 3HVRRE18A/B X
X Waste Bu'ilding P/G 3HVCRE91A/B 3CMSRE22A/B 3HVZRE09A/B 3HVQRE49A/B X
Parts Missing 3HVCRE16A/B
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ATTACHMENT 1, Continued Radiation Monitoring System Status
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i Instrument Turned Field Communications Number (Mark No.)
Over Tested Loop Established Comments Liquid Process Monitors i
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3CHSRE69 X
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3CNARE47 X
X Conductivity meter failed
3DASRE50 3LWSRE70
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3LWCRE65 X
S/W change required 3CNDRE07 X
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3SSRRE08 j
35WPRE60A/B X
Test Starts 5/17 3GWSRE48
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3ARCRE21
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3MSSRE75 X
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3MSSRE76 X
Connector failed
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3MSSRE77 X
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3MSSRE78 X
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3MSSRE79 X
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A-3 ATTACHMENT 1, Continued Radiation Monitoring System Status Instrument Turned Field Communications Number (Mark No.)
Over Tested Loop Established Comments Area Monitors 3RMSRE16 X
Start Test / Calibration 5/13 3RMSRE17 X
Start Test / Calibration 5/13 3RMSRE18 X
Start Test / Calibration 5/13 3RMSRE19 X
Start Test / Calibration 5/13 3RMSRE20 X
Start Test / Calibration 5/13 3RMSRE21 X
Start Test / Calibration 5/13 3RMSRE22 X
Start Test / Calibration 5/13 3RMSRE24 X
Start Test / Calibration 5/13 3RMSRE25 X
Start Test / Calibration 5/13 3RMSRE28 X
Fuel Building Spent Fuel Cask Area 3RMSRE29 X
X Fuel Building Spent Fuel Cask Area 3RMSRE31 X
Start Test / Calibration 5/13 3RMSRE32 X
Start Test / Calibration 5/13 3RMSRE33 X
Start Test / Calibration 5/13 3RMSRE34 X
Start Test / Calibration
5/13 3RMSRE35 X
Start Test / Calibration 5/13 3RMSRE36 X
X Fuel Pool 3RMSRE37 X
Start Test / Calibration 5/13 L
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ATTACHMENT 1, Continued
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Radiation Monitoring System Status
Instrument Turned Field Communications l
Number (Mark No.)
Over Tested Loop Established Comments
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l Area Monitors
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3RMSRE04*
X Start Test / Calibration t
5/13 f
i 3RMSRE05*
X Start Test / Calibration l
5/13 3RMSRE41*
X Start Test / Calibration
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5/13
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3RMSRE42*
X Start Test / Calibration
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5/13 l
3RMSRE01 X
Start Test / Calibration
5/13 3RMSRE02 X
Start Test / Calibration 5/13 3RMSRE03 X
Start Test / Calibration i
5/13 3RMSRE06 X
X Fuel Building Decon Area
3RMSRE07 X
Start Test / Calibration
5/13 3RMSRE08 X
X Spent Fuel Bridge i
3RMSRE09 X
Start Test / Calibration 5/13
3RMSRE10 X
Start Test / Calibration 5/13
3RMSRE11 X
Start Test / Calibration
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5/13 i
3RMSRE12 X
Start Test / Calibration
5/13 3RMSRE13 X
Start Test /Calioration 5/13
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3RMSRE14 X
Start Test / Calibration
5/13
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3RMSRE15 X
Start Test / Calibration i
5/13 3RMSRE38 X
Start Test / Calibration
5/13 l
3RMSRES2 X
Start Test / Calibration
5/13 i
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" Category 1E Monitors
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A-5 ATTACHMENT II RMS Surveillance Procedure Summary Procedure Number Monitor Identification Status / Comment 3449801 3HVR-RE19A/B SLCRS Part/ Gas Cal. Proc.
Draft 3450F01 3CND-RE07 Waste Neut. Sump Rad. Monitor Cal. Draft 3450J01 3LWC-RE65 Regen. Evap. Rad. Monitor Cal.
Draft 3450K01 3SSR-RE08 S/G Blowdown Rad. Monitor Cal.
Draft 3449J01 3HVQ-RE49 ESF Part & Gas Rad. Monitor Cal.
In Development 3449H01 3RMS-RE04/05 Cont. HR Inter. 51'4" CTMT.
Cal. Proc.
In Development 3449G01 3HVC-RE16A/B Control Bldg. Inlet Cal. Proc.
In Development 3449A11 3HVR-RE10A/B Vent Part/ Gas 66'6" Aux Bldg.
In Development Oper. Test 3449B11 3HVR-RE19A/B SLCRS Part/ Gas Oper. Test In Development 3449D11 35WR-RE60A/B Cont. Recirc. Cool Outlet In Development Oper. Test 3449E11 3RMS-RE41/42 Fuel Drop Monitor 51'4" Oper.
In Development Test 3449G11 3HVC-RE16A/B Control Bldg. Inlet Oper. Test In Development 3449H11 3RMS-RE04/05 Cont. HR Inter. 51'4" CTMT.
Oper. Test In Development 3450F11 3CND-RE07 Waste Neut. Sump Rad. Monitor In Development Oper. Test 3450011 30AS-RE50 Turb. Weldg. Floor Drains Rad.
In Development Monitor Oper. Test 3450H11 3LWS-RE70 Liquid Waste Rad. Monitor Oper.
In Development Test 3450J11 3LWC-RE65 Regen. Evap. Rad. Monitor Oper.
In Development Test 3450K11 3SSR-RE08 S/G Blowdown Rad. Monitor Oper.
In Development Test 3449A01 3HVR-RE10A/B Vent Part/ Gas 66'6" Aux. Bldg. Draft Cal. Proc.
3449C01 3 CMS-RE22A/B CTMT Atmos. Part/ Gas Cal. Proc. In Development 3449C11 3 CMS-RE22A/B CTMT Atmos. Part/ Gas Oper. Test Draft 3449001 35WP-RE60A/B TM Recirc. Cool Outlet Cal.
In Development Proc.
3449E01 3RMS-RE41/42 Fuel Drop Monitor 51'4" Cal.
In Development Proc.
3449E21 Fuel Pool Storage Criticality Monitor PORC Approved 3449E31 Fuel Pool Storage Crit. Monitor Oper.
PORC Approved Test 3449F01 3HV2-RE09A/B Recom. Cub. A/B Exh. 7'6" In Development Cal. Proc.
3449F11 3HVZ-RE09A/B Recom. Cub. A/B Exh. 7'6" In Development Oper. Test l
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A-6 ATTACHMENT II, Continued RMS Surveillance Procedure Summary Procedure Number Monitor Identification Status / Comment 3449J11 3HVQ-RE49 ESF Part & Gas Rad. Monitor In Development Oper. Test 3450001 3 MSS-RE75, 76, 77, 78 Main Stm. Rel. Line In Development A-D Cal. Proc.
3450011 3 MSS-RE75, 76, 77, 78 Main Stm. Rel. Line In Development A-D Oper. Test 3450E01 3 MMS-RE79 Turb. Drv. Aux. FDW Pump Dsch.
In Development Cal. Proc.
3450E11 3 MMS-RE79 Turb. Drv. Aux. Fdw. Pmp. Osch.
In Development Oper. Test 3450G0F 30AS-RE50 Turb. Bldg. Floor Drains Rad.
In Development Monitor Cal.
3450H01 3LWS-RE70 Liquid Waste Rad. Monitor Cal.
In Development
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A-7 ATTACHMENT III RMS Generic Procedure Summary Generic I&C.
Monitor No. (GPIC)
Procedure No.
Identification Status / Comment 20.01 3490B01 Kaman Science (KMG-HRN) Radiation Draft
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Monitor 20.02 3490002 Kaman Science (KMG-HRH) Radiation Draft Monitor 20.03 3490B03 Kaman Science (KMPG) Radiation In Review
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20.04 3490B04 Kaman Science (KML) Radiation Monitor Draft 20.05 3490B05 Kaman Science (KMG) Radiation Monitor Draft i
20.06 3490106 Kaman Science Hydrogen Vent Monitor In Review l
20.07 3490B07 Kaman Science Hydrogen Recombiner In Review i
Monitor 20.08 3490B08 Kaman Science (KMA-HR) Radiation In Review i
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20.09 3490B09 Kaman Science (KMA-MR) Radiation In Review Monitor
20.10 3490816 Kaman Science (KMA) Radiation Monitor Draft
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20.11 3490B11 Kaman Science Fuel Failure Monitor In Review
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20.12 3490812 Kaman Science Service Water Effluent In Review i
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A-8 FIGURE 1
Radiation Protection Organization Superintendent Station Services Y
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Radiological Services Supervisor k
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Health Physics Supervisor
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Radiation Radiation Radiation Radiation Protection Protection Protection Protection Supervisor Supervisor Supervisor Supervisor
Support Unit 1 Unit 2 Unit 3
Assistant Radiation Protection
Supervisor linit 1 iealth Physics Technicians (10)
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