ML20008E427
| ML20008E427 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/01/1958 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| References | |
| NUDOCS 8101070150 | |
| Download: ML20008E427 (18) | |
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400:1 2/27/57 O
4 etruT OeEn_i_r.12n 400 GENERAL Since the Yankee project has progressed only to the preliminary engineering and design stage, plant operation is covered in broad and general terms.
Rules and procedures are indicated, and the concept of safe, effective and regulated operation is outlined.
The Yankee Plant Operator s' Manual will replace this section when the Final Hazards Summtry is filed as an amendment to this application.
Location of the Yankee atomic electric plant in the Commonwealth of Massachusetts subjects the plant and its oper-ating personnel to license requirements of Massachusetts, as well as of tne Atomic Energy Commission.
Currently, the areas of licensing activity of these agencies are only slightly over-lapping.. The newly formed Massachusetts Commission on Atomic Energy has not yet defined its position in regard to licensing.
Plant operations, in any event, are conducted in such a way as to meet the requirements of federal and local licensing author-ities and inspection programs.
In addition, the entire plant is operated in a manner consistent with the best industrial practices for large electric generating facilities.
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401 PLANT ORGANIZATION i
Sixty-two to sixty-six full time employees are neces-sary for plant operation.
The larger number may be required de-pending upon the number of guard stations, manning of those stations, and the national security situation.
The plant organ-ization chart is shown on Figure 26.
All employees within the fenced periphery of the plant have appropriate. security clear-ances, since this is a restricted access area under control of i
the plant security. officer.
Based on current regulations, the minimum background training.and license requirements which are adhered to in staffing the plant are as follows:
Job CateRory Training and License Plant Superintendent Nuclear plant experience, tech-nical degree and license as re-quired in Part 55, AEC Regula-tions.
Chief Engineer-Nuclear plant experience, techni-cal degree and license as re-quired in Part 55, AEC Regula-4
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tions; 1st class cperating engi-neer's license, Commonwealth of v
Reactor Supervisor Nuclear plant operation experi-4 ence; license as required in Part 55, AEC Regulations; technical
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degree' desired.
Maintenance Supervisor Nuclear plant background and steam plant maintenance experi-ence; technical degree preferred.
Technical Services Technical degree; industrial hy-Supervisor giene and radiation background; nuclear and steam plant instru-mentation background desired.
Watch Engineers' 2nd class operating engineer's license, Commonwealth of Massachusetts; license as re-
. uired in Part 55, AEC Regula-q tions.
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i PL ANT SUPERINTENDENT I
I Security 8 Clerical Operation 8 Maintenance Technical Services
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SECURITY OFFICER CHIEF ENGIN EERh ------ TECHNICAL SUPERVISOR B
OF I
I GUARDS 5-9 Industrial Hygiene Control CLERICAL 2 and Chemistry and Test MAINTENANCE R E ACTOR WATCH R ADIO CHEMIST l CONTROL ENG. I SUPERVISOR SUPERVISOR ENGINEERS 5 CHEMIST I
INSTR. MEN 3
TECHNICIAN I
TEST TECH.
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g NURSE I
m G) l DOCTOR I
>h STORE S I
CONTROLROOM
( Consulting )
2._, 2 FUEL HANDLING l OPERATORS 9 i
NX MECHANICAL 6
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HOUSE YARD, Id O0 CRANE LABOR 5
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TURBINE COOLING WATER OWNER COMPANY
-4 OPERATORS 5 DISPOSAL MEN 5 EMPLOYEES 2
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. Job Category Training and License Radio-Chemist Technical training as required.
Control Engineer Technical training as required.
Turbine Operators Operating engineer's license, Commonwealth of Massachusetts,
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as required.
Control Room Operators Two per shift; at least one with license as required in Part 55, AEC Regulations.
-Nurse (Male)
Medical-and radiation dosimetry background.
Other Employees Specific technical or adminis-trative training not a prerequi-i site.
These employees are.
trained under.a Company training program to perform satisfactorily j
the duties'of their stations.
The Chief Engineer is in a position of overall operat-ing-. authority in the plant.
Pending clarification of operating s,
authority between Massachusetts ateam plant operator. licensing and AEC nuclear plant operating. licensing,.it is considered possible that both licenses.can.be acquired by him.
The plant organization is adequate for plant operation,
'7 routine maintenance and. refueling, and for performing most main-tenance within the vapor container, except steam generator re-placement. ~The plant is.not. staffed on a permanent' basis to do major repair or overhaul.of the primary plant, since this is anticipated to be infrequent and unpredictable.
I Normally,- the plant operating crews do the refueling of the reactor while.the regular maintenance crew performs primary and steam plant maintenance during the-shutdown.
If either pri-E mary plant or steam-electric plant maintenance is expected-to be extensive during.a'particular shutdown. period,, sufficient.outside maintenance workers-are' brought in to take care.of the steam-elec-tric work and thus release the plant maintenance. force for work on the~ primary plant,.only.
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. Currently, the-Yankee technical;staffaincludes six ex-
- perienced nuclear engineers.. In addition. consulting arrangements are in effect with the following individuals..and organizations
4 Dr. Theos J. : Thompson, Nuclear EngineeringI.M.I.T.
- h Professor James M. Austin,. Meteorology, M.
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General K. D. Nichols, Washington, D.C.
Nuclear Development Corporation of America, White Plains, N.Y.
Dr. Shields Warren, Deaconess Hospital, Boston, Massachusetts It is planned that, after plant operation begins, Yankee will continue to maintain a central office in Boston.
The officers and staff of this office will include competent engineering and management personnel.
In addition, the Company will retain con-sultants.
Specialized technical services will be acquired through contract arrangements, as needed.
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402 PERSONNEL TRAINING Plant Supervisory and Technical Training Nuclear plant training of supervisory personnel and technical graduates of utility companies, now owners of Yankee, was initiated during June, 1951, when technical graduates were lent to AEC contractors for training.
Yankee now has technical 1
personnel, directly employed or on call with member companies, materials, construction, test and with theoretical, design,he STR, EBR I and II,tals Corporatio operation experience on t BORAX I and III, EBWR, APDA-PRDC, LMFR, and with the Nuclear Me e
Supervisory-technical training of Yankee employees is continuing 4
at APDA-PRDC and Argonne National Laboratory.
As the plant opera-tion phase approaches, Yankee plans to arrange with the AEC for additional personne1' training required under Part 5$, AEC Regula-tions.
s Plant Operator Training Plant operator training in nuclear theory, plant de-vices and operation will be initiated about one year prior to plant start-up.
Plant' operators will be drawn from owner compan-ies' steam plant operating staffs.
At the time of reassignment to the Yankee plant, these operators will be thoroughly experi-Q-
enced in large steam-electric plant operation, and will hold 1
v appropriate operators' licenses issued by the Massachusetts Department of Public Safety.
Four nuclear plant training pro-grams for operators will be instituted as follows:
Lecture courses conducted by Yankee and f
Westinghouse Commercial Atomic Power Activities engineers.and scientists.
On-the-job training by_ construction liaison and preoperational component and systems test programs.
Operators will perform pre-nuclear start-up tests on the entire plant under the direction of Westinghouse'and Yankee engineers.
Additional training on pressurized water re-actor plants similar to Yankee,as required i
by the AEC.leadingit<o Part 55-licenses.
Continuing educational programs.for all em-ployees on plant ~ hazards, radioactivity and i
security, conducted by plant supervisory personnel.
Continuing training programs will be-conducted.for plant personnel and member company personnel leading to.the licensing of b(s) a pool-of technical personnel.and operators in anticipation of.a steady growth of the atomic electric' business.
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s 403:1 2/27/57 403 INITIAL PLANT INSPECTION AND TESTING
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Plant inspection and testing leading to full scale operation is divided into three phases.
Manufacturer's Component Tests and Inspections Test, construction code and cleanliness requirements accompany each specification or purchase order for equipment.
Hydrostatic, leak, metallurgical, electrical and other tests per-formed by the supplying manufacturer are described in detail on the specification sheet,together with the requirements fcr test witnessing by an inspector, when and if required.
Fabrication and cleanliness standards, including final cleaning and sealing, are described, together with shipping procedures.
The specifications and tests are in accordance with State Regulations, National Society Codes, and the best indus-trial practices.
Plant Systems Inspection and Tests As each component is received it is carefully checked to determine that it was shipped accord [ng to specifications, had the proper inspection approval and that no damage occurred rw in transit.
Construction, field fabrication, and erection are
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handled only by competent personnel under construction permits issued by the appropriate authorities, using materials and techniques that conform with applicable State and National Society Codes.
Following erection, a plant component and systems test program will be carried out prior to loading nuclear fuel.
Checkout test specifications will be written for all systems, and tests will be performed by the plant operating staff under the direction of the technical staff of Yankee and its contrac-tors.
Systems test approval is by appropriate authority, and is coordinated with the AEC inspection operation.
Initial testing of the vapor container is performed by the fabrication and erection contractor under the direction of the Stone & Webster Engineering Corporation.
Nuclear Start-up and Tests Following completion of the systems test program, in-cluding main coolant loop flushing and hydrostatic testing, the nuclear start-up program is initiated.
A summary of the initial tests following loading of the nuclear fuel is as follows:
Cold Critical
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Control Rod Worth Boron Coefficient of Reactivity
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Pressure Coefficient of Reactivity
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Temperature Coefficient of Reactivity Effects of Coolant Flow Control Rod Drive Scram Circuitry Heat Balance vs Nuclear Instrument Calibration Lcw Power Part Power Shutdown Cooling by Natural Circulation Water Conditioning Shielding Monitoring and Alarm Manual Control Automatic Temperature Control Overall Plant and Core Evaluation n
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During the final stages of construction and preliminary systems testing, the manufacturer's manuals on all plant equip-ment will be accumulated.
These manuals will be used as a basis for preparing the Yankee Plant Operators' Manual and for the on-the-job training program of systems testing and operator educa-tion.
Normal operating procedures affecting each plant station will be detailed in the manual, together with start-up and emergency procedures.
The minimum number of plant operators for normal opera-tion is six, which includes:
1 guard; 2 control room operators; 1 watch engineer; 1 turbine operator; 1 monitoring and auxiliary system man.
Other supervisory personnel are "on call" at all times at residences in close proximity to the plant.
The plant is manned on a 24 hr a day basis, 365 days per year, to produce electric power as a base load station.
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405 EMERGENCY PROCEDURES Emergency procedures are put into effect whenever the monitoring and alarm system indicates the presence of excessive radioactivity or that a primary plant rupture has occurred.
When such alarms are given, the control room operator reduces load and shuts down the entire plant.
Even in the absence of any alarm, the control room operator may shut down the plant if, in his judgment, an unsafe or abnormal condition exists.
The sequence of events following a major accident, such as a rupture of the primary plant, is as follows:
The steam and nuclear plant is secured while putting the chemical shutdown or safety injection system in-to operation.
All plant personnel, not essential for securing the plant, proceed immediately by predetermined evacu-ation rettes to the guardhouse at the periphery fence 1,000 ft from the plant proper.
Plant shift personnel considered essential for safely securing the ' steam and reactor plant, including the watch engineer, two control room operators, the tur-bine operator and the monitoring and auxiliary system man, assemble at the shielded control room.
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All plant supervisors not on duty at the time, includ-ing the superintendent, chief engineer and reactor supervisor, are called to the guardhouse where they receive protective equipment and take charge in order to prevent further damage.
The monitoring man provides himself and the emergency essential operating crew with oxygen tank type gas masks and then makes a radioactivity survey of the plant area using portable and plant monitoring equip-ment.
The reactor operators follow established emergency pro-cedures, as outlined in the operators. manual, to mini-mize plant damage, determine conditions within the vapor container, determine whether core melting has occurred and determine radioactivity levels within the vapor container.
The operators establish telephone contact with the guardhouse and further direct the continued evacuation of nonessential personnel from the guardhouse, based on area monitoring readings and the probable condition of the plant.
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The site weather stations and area monitoring sta-tions give indications in the control room of weather conditions and radioactivity levels at the plant site and neighboring areas.
Calculations of the direct radiation hazard following a major loss of coolant accident indicate that a 2 1/2 hr exposure period is allowable at the periphery fence, 1,000 ft from the vapor container.
At the nearest Drivate dwelling exposed to direct radiation, 4,000 ft away, an exposure period of several weeks is allowable.
The air-borne radiation hazard must be evaluated at the time of an accident based on the leak rate and prevailing meteorological conditions.
Portable radi-ation monitoring equipment is available in the guard-house for use by technical services personnel for local monitoring operati-:.a.
Essential personnel evacuate the plant proper upon re-lief or when the plant is deemed secured.
Relief shifts of essential personnel are made up at the guard-house where the necessary protective equipment is issued.
Relief personnel are rotated as required to restrict radiation exposure to less than maximum permissible emergency doses until the plant is completely secured.
Return to the. plant proper following a major accident is governed by radioactivity levels and the extent of A
damage.
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i.06 Rsrust1xo pRoCsouRss The detailed description of refueling procedures will appear in the Yankee Plant Operators' Manual.
Normally, the re-fueling operation is performed by the reactor operating crews under direction of the reactor supervisor.
Reactor shutdown for refueling is determined by the remaining excess reactivity at power, statistical radiation damage information on fuel damage vs. burn up obtained from in-pile tests on similar fuel assemblies, and the radioactive contamination of the primary systema due to fuel assembly cladding failures.
The general sequence of events following determination of scheduled shut-down is as follows:
Reduce the hydrogen level in the main coolant system to equilibrium concentrations at one atmosphere and room temperature by operation of the purification system after shutting down the corrosion control-hydrogen injection system.
Secure plant and start controlled cool down to 100 F while injecting boric acid into the main coolant system to the desired concentration.
Open the vapor container stack valve and purge the con-()
tainer of any accumulated air-borne and gaseous radio-activity at allowable release rates which are based on AsC criteria and meteorological conditions.
Open the access hatch and enter the. vapor container.
Loosen the reactor vessel head as described in the operators' manual.
Flood the reactor shield tank cavity to a depth of 25 ft with borated water containing 1.6 g of boron per liter as boric acid.
Release the reactor control rod dr$ve shafts from their mechanisms, leaving the control rods in a down position in the core.
Remove the reactor vessel head and internals, such as control rod drive shafts, core hold-down ring, and upper core support barrel, and store in the shield tank cavity:under water.
Remove the spent fuel by the fuel handling system under water, using proper health and safety monitor-ing equipment and maintaining adequate ventilation.
Remove single fuel assem.blies beginning at the (l
center of the core and working outward.
Changing the location of fuel. assemblies from the outer region of the core to the center may or may not be
406:2 2/27/57 nIJ done based on further considerations of two-region or single-region core loadings.
Transfer removed fuel assemblies to the spent fuel pit and store under water in the racks provided.
- Normally, a dissolved chemical neutron absorber is not required in the spent fuel pit water in order to maintain the stored fuel assemblies suberitical.
Introduce new fuel from the storage vault, through the spent fuel pit, to the shield tank cavity, and lower into the reactor by reverse operation of the fuel handling system.
Replace any reactor control rod required.
Control rod withdrawal is monitored by period meter instrumenta-tion.
The control rods and extensions are withdrawn from the core into the shield tank cavity where the control section is separated from the extension at the break joint.
The control rod is handled by the fuel handling system in the same way as a spent fuel assembly.
Start-up of the plant after refueling is outlined in detail in the Yankee Plant Operators' Manual.
g-)3 Spent fuel is stored at the plant for a period of time, after which the fuel assemblies are shipped in air-cooled coffins, each coffin carrying several fuel assemblies.
Shipping cask loading is performed by the spent fuel pit manipulator and is accomplished under water.
Shipment of spent fuel to the re-processing plant is by rail or truck.
Appropriate fuel transfer and accountability procedures are used throughout.
407:1 2/27/57 O
407 RADIOLOGICAL HEALTH AND SAFETY a
The plant equipment for radioactivity monitoring is used by the plant technical services personnel to maintain safe working conditions at the plant proper.
The basic cri-terion for shielding design is 1/10 the allowable dosage of 300 mrem per 40 hr week at all stations manned full time.
A shielding evaluation program after nuclear start-up ascertains that the basic design criterion is not exceeded.
Maintenance operations may subjset plant personnel to higher levels of radio-activity for short periods of time; however, complete records on each employee are maintained to insure that no individual receives radiation doses in excess of tolerance.
Four area monitoring stations for air-borne activity are located external to the plant fenced periphery.
One sta-tion is located near the plant hilltop stack.
The other ihree stations are at selected locations with reference to the plant and hilltop stack stations.
These stations are simple beta-gamma counter installations which are provided principally, for determining an unsafe condition following an accident.
The signals from these stations and the weather stations are sent to the radiation monitoring panel in the control room.
Control and monitoring of liquid discharges are de-em scribed in Sections 208 and 210.
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A site radioactivity monitoring program for background determinations is currently in operation which will monitor liquid, gaseous and solid discharges during normal plant opera-tion to insure that radioactivity levels do not exceed the maxi-mum pernissible concentrations prescribed in Handbook 52, U.S.
Bureau of Standards.
The radiological health and safety activities are under the direction of the technical services supervisor, assisted by a radio-chemist, a male nurse, and five monitoring and auxiliary system men, on a one per shift basis.
Medical services of a con-sulting nature are available on a contract basis.
Film badges are worn by all plant personnel during normal plant operation.
During maintenance periods, both dosimeters and film badges are worn.
The film badge service is available on a contract basis with no developing facility pro-vided at the plant site.
Continuous personnel exposure records are maintained by the male nurse.
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408 etinT xilur.exance inn accesa During normal operation the plant vapor container is closed.
Temperatureandradioact1vitybuildupwithinthecon-
,tainer are monitored.
When access into the vapor container is corporakedinthePlantOperatorsgeneral safeguards applyI details of which will be desired Manual.
The reactor is shut.dcnnt.
The shielding design of the reinforced concrete struc-ture supporting the reactor does not provide for access to the vapor container with the reactor at high power levels.
- Likewise, the closed vapor container ventilation system limits access.
If only minor adjustment or maintenance is required, which can be accomplished without hazard from the high pressure primary plant system, the following sequence applies:
Following reactor shutdown, the ventilation system is operated with monitored and controlled discharge to the plant stack.
The main coolant system is not depressurized, but slowly drops fron 2,000 psia because af radiation heat losses.
Boric acid solution is injected into the main coolant in sufficient quantity to keep the reactor shut down.
( w) c The main coolant pumps remain in intermittent service, as required to limit the rate of temperature drop and equalize temperatures in the system.
The pressurizer is operated manually to maintain the system pressure at levels suitable for pump operation.
The closed television circuit is aperated to determine conditions within the vapor container.
The maintenance crew entering the vspor container is outfitted with proper clothing and tank type gas masks.
Its entry is preceded by a monitoring and decontamination man from technical services.
Entrance is made by way of the doubit door personnel access hatch, and minor repairs are accomplished.
Major maintenance within the vapor container, such as steam generator tube plugging, is performed on a deferred main-tenance schedule at the time of complete plant shutdown and de-pressurization.
The plant power level it reduced by closing the inlet and outlet main stop valve in
-ny. defective main cool-ant loop.
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All maintenance c elations on contaminated equipment or s
in contaminated areas are supervised by technical services to see that proper decontamination procedures and radioactivity safe-guards are observed.
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409:1 2/27/57 409 ROUTINE TESTING PROGRAMS In addition to initial plant start-up testing, routine testing is scheduled continuously.
Main Coolant System Hydrostatic Testine Any alterations to the high pressure coolant system subsequent to the start-up hydrostatic test are followed by a hydrostatic test to prove the integrity of the new weld or com-ponent.
Whenever the reactor vessel head is removed for re-fueling, the primary plant is hydrostatically tested.
6 Steam Generator Testine and Insrection The steam generators are deemed by the Massachusetts Department of Public Safety to cone under the ASME Boiler and Pressure Vessel Code,Section I, and must receive annual physical inspection in addition to the main coolant system hydrostatic tests.
Hand holes are incorporated in the steam generator design, and the decontamination system is operated to allow physical inspection.
4 Radioactivity
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A continuous program of site radioactivity testing began in October 1956.
Soil, water, air and plant and animal matter testing for radioactivity are carried on throughout the 4
l life of the plant, and thereafter, as required.
Following plant i
start-up, additional radioactivity testing is carried on by the plant Technical Services Department and by subcontract.
Plant discharges are monitored on a continuous basis by the monitor-ing system and, in addition, local monitoring and testing is carried on to ascertain the nature and concentration of the liquid, gaseous and solid discharges.
Test records are main-tained.
Instrumentation and Control Nuclear and steam plant instrumentation testing is on j
a continuous basis.
Automatic and manual controls of the plant are checked through a continuous test program and records are maintained.
l Water Chemistry All water in use in the nuclear and steam plant under-goes daily testing.for the determination of gaseous, dissolved, and suspended impurities.
Log sheet records are maintained.
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410 PLANT SECURI_TY AND SPECIAL NUCLEAR MATERIALS TRANSFER AND ACCOUNTABILITY Plant security is under the direction of the security officer who has charge of security education and handling of classified material.
All security procedures at the plant are consistent with AEC regulations.
Since there is only one normal point of access for traffic through the chain link fence only one guardhouse is pro-vided at the facility.
The guardhouse is nanned at all times by at least one properly authorized guard.
Normal turnstile access for individuals and gate access for motor vehicles are provided.
Exclusion area details are shown on drawing 9699-FY-7A.
Normally, a second guard or continuous chain link periphery patrol are not required.
The exclusion area plan pro-vides for an interior chain link fence and a three strand, barbed wire perimeter fence, which is considered to bc a barrier to pre-vent trespassing on the plant property.
Access for a slow speed freight railroad, the Hoosac Tunnel & Wilmington Railroad, is provided through the periceter fence by automatic gate control from the guardhouse.
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