ML20091R518
| ML20091R518 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/08/1984 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20091R502 | List: |
| References | |
| NUDOCS 8406150157 | |
| Download: ML20091R518 (18) | |
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~ OYSTER CREEK NUCLEAR GENERATING STATION y PROVISIONAL OPERATING LICENSE NO..DPR-16 DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST.NO. 120 Applicant' hereby request the Conunission to change Appendix A to the aDove
- . , captioned license as follows
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- 1. ? Sections to be changed:
Figure'6.2.2 and Sections 6.3.1, 6.8.1, and 6.9.3.
- 2. Extent of changes:
2..
e See Attachment 1
- 3. Changes' requested:
t See .*u.tachment 1
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- 4. Discussion:
The primary reason for this change request is-to submit a Plant Engineering 1-I organization which is more responsive to the continuing operations and' maintenance needs of the Oyster Creek Facility.and to enhance the -
i administrative capabilities of the organization.-
The reorganization ~will achieve this by: 4
- a. Reducing the number'of direct interfaces to both the Plant Engineering 1 l Director and the Manager - PlantLEngineering. 4 m
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- - b.- Provide a three Manager structure'with specific' responsibilities ~in the areas of' Operations, Maintenance,;and Support..
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- c. Provide direct' interfaces with Plant Engineering for the related~
l organizations of the Oyster Creek division and'GPUN.
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- d. Assigning specific responsiblity to'a' dedicated group for dischancing;
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-the administrative functions of Plant Engineering.
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'Another change that is being made within1the organization'at' Oyster 1CreekL
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- cis that'the position of Manager, Radiological Controls has been upgraded to the Director. level. LThe Technical Specification requirements for this.'
-position. remain the'same..
l- :Thethird)reasonforthis*changerequest(istosubmit-two-(2)otherchanges:
to the~ administrative section of.the Technical; Specifications,n These;
. changes are an updating of the requirements _for written procedures'in-
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.! ,1 effect'for: Oyster Creek and the addition ofLthe NUREG-0737' requirement for1
- a specialTreport that-is to be submitted'.after;the failure of,for challenge ~
,to, Relief and Safcty valves.. .
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m ATTACHMENI 1
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Sunmary of Tech. Spec. Change Request No.120 Current . Proposed No.. Tech. Spec. Tech Spec. Extent of Change Justification 1 Figure 6.2.2 Figure 6.2.2 Figure redrawn to reflect reorganization GPUN approved Page 6-4 Page 6-4 of Oyster Creek Onsite Organization within administrative change-Plant Engineering, Plant Operations, and Radiological Controls
- 2. Specification Specification Title Cnange; presently Cnemistry Manager, GPUN approved 6.3.1 6.3.1 to be changed.to Manager-Plant Chemistry administrative change Paragraph 6 Paragraph 7
- Page 6-6 Page 6-5
- 3. Specification Specification Title Change; presently Manager Plant GPUN approved 6.3.1 .
6.3.1 .
Engineering, to be changed to Managers- administrative change Paragraph 4 Paragraph 4 Plant Engineering Page 6-6 Page 6-6 4.. Specification; Specification Title Change; presently Manager Core,. GPUN approved
.6.3.1. .
6.3.1 to be changed to Core Manager- administrative change Paragraph 1 Paragraph 5 fPage 6-6 Page 6-6
- 5. . Specification, Specification Title Change; presently Manager / Deputy GPUN approved 6.3.1 6.3.1 Radiological Controls, to be changed to administrative change Paragraph 5' Paragraph 6 Radiological Controls Director.
Page 6-6' Page 6-6 6.. . Specification Specification Change of requirements for written GPUN approved
' procedures in effect administrative change 6.8.1 6.8.1 Page 6-15 Page 6 :7.- Specification Specification -Correction of spelling of Enforcement Correct an existing 6.9 6.9 . typographical error Page 6 Page 6 8. '
Specification Addition of the requirement for a special report NUREG-0737 requirement
~6.9.3.F- that is to be submitted after the failure of,
-Page 6-22 or. challenge to, Relie2 and Safety Valves that might not constit.ute an LER.
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VICE PRESIDENT ONSITE ORGANIZATION a DIRECTOR OYSTER CREEK DEPUTY DIRECTOR OYSTER CREEK dANAGER
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NUCLE AR SAFETY SAFETY REVIEW MANAGER PLANT ENGINEERING MANAGER PLANT PLANT OPERATIONS MAN AGER PL ANT MAINT.8 CONST "
RADIOLOGICAL CONTROLS
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DIRECTOR MATERIEL DI RE CTOR ADMINISTR ATION DI RE CTOR DIRECTOR,0C OYSTER CREEK MANAGER MAINTENANCE OPERATIONAL MAINTENANCE, MANAGER RADWASTE RADIULOGIC AL FIELO
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ENGINEERING - PM, AND SURVEILL ANCg OPERATIONS - OPERATIONS MANAGER MANAGER OC MANAGER SUPPORT ~
MANAGER PLANT
". ENGINEERING OPER ATION S RADIOLOGICAL CONTROLS i GROUP SUPERVISOR' SHIFT SITE FIRE GROUP SHIFT ~~ '
PROTECTION COORDIN ATOR SUPERVISOR RADIOLOGICAL CONTHOLS V S
- 1 TECHNICIANS MANAGER OPERATIONS CONTROL ROOM
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ENetNEERIN3 OPERATORS RADIOLOGIC AL ENGINEERING eei MANAGER,OC CORE leANAGER EQUIPMENT l l OPERATORS TECHNI C AL NOTE I-THE MANAGER PL ANT OPERATIONS eea STAFF AND THE GROUP SHIFT SUPERVISOR SHIFT STAFFING REOUIRE SENIOR REACTOR OPERATORS MANAGER PLANT e 1/ SHIFT LICENSES.THE CONTROL ROOM OPERATORS CHEMISTRY ** 2/SHIF T RADIOLOGICAL SUPPORT REQUIRE A RE ACTOR OPERATOR LICENSE. es e 3 /SH IF T ( I M AY BE A RADwASTE OPERATOR)
( MANAGER OC 6-4
p q 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 The members of the facility staff shall meet or exceed the following qualifications:
Vice President & Director / Deputy Director Requirements: Ten years total power plant experience of which three years must be nuclear power plant experience. A maximum of four years of academic training may fulfill four of the re."naining seven years of required experience. Both must be capable of obtaining or possess a Senior Reactor Operator's License.
Plant Operations Director Requirements: Eight years total power plant experience of which-three years must be nuclear power plant experience. A maximum of two years of academic or related technical training may fulfull two years of the remaining five years of required experience. The Plant Operations Director must be capable of obtaining or possess a Senior Reactor Operator's License.
Plant Engineering Director Requirements: Eight years of responsible positions related to power gen: ration, of which three years shall be nuclear power plant experience. A maximum of four of the remaining five years of experience may be fulfilled by satisfactory completion of academic or related technical training.
Manager-Plant Administration s Requirements: Eight years total power plant experience of which four
! years must have been in nuclear power plant experience. %e Manager should possess a four year college degree or equivalent in Business Administration or an Engineering discipline.
Manager-Plant Operations
' Requirements: Eight years total power plant experience of which three' years must be nuclear power plant experience. A maximum of two' years of acaderpic or related technical training may fulfill two of the '
remaining five years of required experlence. W e Manager Plant.
Operations must possess a Senior Reactor Operator's License.
Manager-Plant Chemistry Requirements: Five years experience in chemistry of which a minimum of one year shall be in radiochemistry at an operating nuclear power.
plant. A maximum of four years of this five. year ~ experience may be fulfilled by related technical or academic training.
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Safety Review Manager Requirements: Eight years total power plant experience of which three
- years must be nuclear power pJant experience. A maximum of two years of academic or related techni;al training may fulfill two of the remaining five years of required experience.
Manager-Plant Materiel Requirements: Seven years of total power plant experience of wnich one year must be nuclear power plant experience. Wo years of academic or related technical-training may fulfill two of the remaining six years of required experience.
Area Supervisor-Instrument and Computer Maintenance Requirements: Five years of experience in instrumentation and control, of which a minimum of one year shall be in nuclear 4 instrumentation and control at an operating nuclear power plant. A maximum of four years of this five year experience may be fulfilled by related technical or academic training.
Managers-Plant Engineering The engineers in charge of technical support shall have a Bachelor's Degree in Engineering or the Physical Sciences and have three years of professional level exp3rience in nuclear services, nuclear plant operation, or nuclear engineering, and the necessary overall nuclear background to determine when to call consultants and contractors for dealing with complex problems beyond the scope of owner-organization expertise.
Core Manager At the time of initial core loadina or appointment to the position, whichever is later, the responsible person shall have a Bachelor's Degree in Engineering or the Physical Sciences and four years experience or a graduate degree and three yea;s exy.rience. Wo of these years shall be nuclear power plant experience. The experience shall be in such areas as reactor physics, core measurements, core heat transfer, and core physics testing programs. Successful coupletion of a reactor engineering training program (such as the.12 week concentrated prograrrs offered by NSS.Vendurs).may be equivalent to one year's nuclear power plant experience.
Radiological Controls Director (Reports Offsite) -l Requirements: Bachelor's' degree or the equivalent in a science or engineering subject, including some-formal training in radiation protecton. Five years of professional experience in applied radiation-prote": tion. (Master's degree equivalent to one year experience and Doctor degree equivalent to two years experience where coursework related to radiation protection-is involved.) Three years of this-
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. professional experience should be in applied radiation protection work
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-in a nuclear facility dealing with radiological problems similar to those encountered in nuclear power stations.
M&C' Director, O.C.
t Requirements: Seven years of total power plant experience of which one year must be nuclear power plant experience. Two years of academic or related technical training may fulfill two of the remaining six years of required experience.
Shift Technical Advisor Requirements: Bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.3.2 Each member of the radiation protection organization for which there is a comparable position described in ANSI N18.1-1971-shall meet or exceed the minimum qu. ifications specified therein, or in the case of radiation protection t.whnicians, they shall have at least one year's continuous experience in applied radiation protection work in a nuclear facility dealing with radiological problems similar to those encountered in nuclear power stations, and shall have been certified ,
by the Mgr/ Deputy Radiological Controle,:as qualified-to perform assigned functions. 'Ihis certification must be based on an NRC ,
approved, documented program consisting of classroom training with appropriate examinations and documented positive findings by..
responsible supervision that the individual has demonstrated his '
ability to perform each specified procedure and assigned function with-an understanding of its basis and purpose. '
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6.4 TRAINING _
6.4.1 A retraining program for operators shall be maintained under the' direction of the Manager Plant Training Oyster Creek and shall meet--
the requirements and recommendation of Appndix A of 10CFR Part 55.
Replacement training programs, the content of which'shall: meet'thel requirements of 10CFR Part 55, shall be conducted under the' direction of the Manager Plant Trainir.g Oyster creek for' licensed operators 'and
' Senior Reactor Operators..
6.4.2 .
A' training program for the Fire Brigade shall-be maintained'under the
! direction of the Manager Plant Training Oyster Creek.~
6-71 .
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6.7 SAFETY LIMIT VIOLATION 6.7.l' The following actions shall be taken in the event a Safety Limit is violated:
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- n. If any Safety Limit is exceeded, the reactor shall be shut down imediately until the Comission authorizes the resumption of operation.
- b. The Safety Limit violation shall be reported to the Comission and the Vice President and Director Oyster Creek.
- c. A Safety Limit Violation Report shall be prepared. The report shall be submitted to the Vice President and Director Oyster Creek.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of.the violation upon facility coirponents systems or structures, and (3) corrective action taken to prevent recurrence.
- d. The Safety Limit Violation Report shall be submitted to the Comission within 10 days of the. violation.
6.8 PROCEDURSS
[ 6.8.1 Written procedures shall be established, implemented, and maintained that meet or exceed the requirements of the Nuclear Regulatory Guide 1.33 (the applicable revision is identified in the GPU Nuclear Operational Quality Assurance Plan) and as provided in 6.8.2 and 6.8.3 below.
6.8.2 Each procedure and administrative policy of 6.8.1~above, and changes thereto, shall be reviewed as described in 6.5.1.1 and approved as described in 6.5.1 prior to implementation and periodically as specified in the Administrative Procedures.
6.8.3 Teaporary changes to procedures 6.8.1 above may be made provided:
- a. The intent of the original procedure is not altered.-
- b. The change is approvided by two members of GPUNC Management Staff authorized under Section 6.5.1.12 and knowledgeable in the area affected by the procedure. .For changes which may affect the operational status of facility _ systems or equipment, at.least one of these individuals ah11 be a member of facility management or supervision holding a Senior Reactor Operator's License on the facility.
- c. The change is' documented, subsequently reviewed and approved as described'in 6.8.2 within 14 days of implementation.
6-15 Amendment No. 69 ,
6.9 EIPORTING RIOUIREMEES
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- 1. In addition to the applicable reporting requ,irements of 10, CFR. the l
., following id'e ntified reports shall be submitted to the Director of the appropriate Regional Office of Inspection and Enforcement unless otherwise noted. -
6.9.1 ROUTINE RIPORTS
. a ." Startup Report. A sunmay report of plant startup and power escalation testing shall be submitted f oloving (1) receipt of an operati:g license, (2) amendment to the license involving a planned increase in power level, (3') installation of fuel that has a different design or has been manuf actured by a different fuel supplier , and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of th'e plant. -The r'eport shall address each of the tests identified in the FSAR and ,
shall in general include a description of the measured values of the * * -
operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions .and ,
specifications. .Any corrective actions that were required to obtan .
satisf actory eperation shall also be decribed. Any additional specified details required in license conditions based on other co==itments shall be included in this report.
Startup reports shall be submitted within (1) 90 da's y following ce=piction of the.startup test program, (2) ' 90 days 'f ollowing resumption, or commencement of connercial power operation, or (3) 9
=enths following initial criticality, whichever is earliest. If the S t ar tup Report does not cover all three events (i.e., initial criticality, cc=pletion of .startup test program, and. resumption or ~
co==encement of ce=m'ercial power operation), supplemetary reports shall be' submitted at least every three months until all three ~
events have been. completed. , _
- b. Annual Excesure Data Report. Routine exposure data reports covering the operatics of the facility during the previous calendar year shall be submitted prior to March 1 of each year.. Reports.
. shall contain a tabulation on an annual basis of the nunbar of station, utility, and other personnel (including contractors) 1 -
receiving expesures greater than 100 mrem / year and their associated l nan ren exposure according to work and job functions (This tabulation supplements the requirements of 10 CFR 20.407), e.g. , -
reacter operations and surveillance, inservice inspection, routine saintenance, special naintence (de s cribe maintance), vasta processing', and refueling. The dose assignment to 'various ' duty -
. func tiens =ay be es ti=ates based on pocket dosimeter, TLD, or film badge seasurements. Small exposures totalling less than 20% of. the individual total dose need net be accounted for. In the aggregate, at least 80% of the total whole body ' dose recieved from external sources shall be assigned to specific major work functions,
- c. Me:thlv Oeerating Report. Routine reports - of operating -
statistics and shutdown experience shall be submitted on a month'ly .
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i 6-16 Amendment No. 69 4 i-
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20 estimates of the likely resultant exposure to individuals
. cnd to population groups, and assumptions upon which estimates are based shall be provided.
1 (c). If statistically significant variations of offsite environmental concentrations with time are observed, correlation of these results with effluent release shall be provided.
(d). Results of required leak tests performed on sealed sources if the tests reveal the presence of 0.005 microcuries or more of removable contamination.
- d. Inoperable Fire Protection BIuipment (3.12)
- e. Core Spray Sparger Inservice Inspection (Table 4.3.1-9)
Prior to startup of each cycle, a special report presenting the results of the inservice inspection of the Core Spray Spargers during each refueling outage shall be submitted to the Comission for review.
- f. Failures and challenges to Relief and Safety Valves Failures and challenges to Relief and Safety Valves which do not constitute an LER will be the subject of a special report submitted to the Commission within 60 days of the occurrence. A challenge is defined as any automatic actuation (other than during surveillance or testing) of_ Safety or Relief Valves.
6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:
- a. Records and logs of facility operation covering time interval at each power level.
- b. Records and logs of principle maintenance activities, inspections, repair and replacement of principal items of equipment related to-nuclear safet.y.
- c. Reportable occurrence reports.
- d. Records of surveillance activities, inspections and calibrations required by these technical specifications.
- e. Records of reactor tests and experiments.
- f. Records of changes made to operating procedures.
- g. Records of radioactive shipments
- h. Records of sealed source leak tests and results.
- i. Records of annual physical inventory of all source material c,f record.
6-22 Amendment No. 69
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6.10.2 ~
, _The following. records shall be retained for the duration of the '
Facility Operating License:
- a. Record and drawing changes reflecting facility design
.; modifications made to systems and equipment described in the Final' Safety Analysis Report, b., Records of new irradiated fuel-inventory, fuel transfers and' assembly burnup histories.
- c. Records of facility radiation and contamination sucVeys.-
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- d. Records of radiation exposure for all individuals entering i radation control areas.-
- e. records of gaseous and liquid radiactive material released,to
- the environs.
- f. Records of-transient or operational cycles for those facility couponenets designed for a limited number of transients or cycles.
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, 9 Records of training and qualification for current members of, j' the plant staff.
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- h. Records of inservice inspections performed pursuant to these technical specifications.
h 1. Records of: reviews performed for changes made to procedures
! or equipment or reviews.of tests and experiments' pursuant to 10 CFR 50.59.
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i 'j. Records of' reviews by the Independent Onsite Safety l Review j' Group.
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! -k. Records for Environmental Qualification which are covered l under the provisions for paragraph 6.14.
t 6.10.3-
- Quality Assurance Records shall beLretained as specified by the.
Quality Assurance Plan.
- f. 6.11 RADIATION PROTECTION PROGRAM '
Procedures for personnel radiation protection shall be prepared f consistent with the requirements of-10 CFR.20 and:shs11 be-4 1 approved, maintained and adhered to for all operations" involving personnel radiation exposure.
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6.12-(Deleted) '
a 6-23I Amendment 69' 5
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May 14, 1984 Reply to Notice of Violation Inspection 84-06 Letter dated April 12, 1984 Page 3 of 5 Action Taken to Prevent Recurrence A Nuclear Group Directive (NGD) will be written to encompass all aspects of the ISI Program at Beaver Valley Power Station.
Site Administrative Procedures (SAPS) will ta developed to delineate responsibilities to the various station groups involved with the IST Program. The SAPS will also identify the a,rproval process for the program. .
An IST Manual will also be developed which will contain specific Code requirements and the method by which the Station will accomplish these commitments.
Date Upon Which Full Compliance Will Be Achieved Full compliance will be achieved with the completion of the administrative procedures and the IST Manual . These actions are expected to be complete by October 1, 1984
_ Specific Actions Taky In response to the specific items listed in the Notice of Violation as examples of the lack of management controls for the IST Program, the following actions have been or will be taken:
- 1. Hydrogen recombiners valves M0V-1HY-201A and M0V-1HY-201B are required to be tested quarterly in accordance with ASME Section XI IWV-3410, and the valves were not being tested quarterly. These valves-had specifi-cally been denied relief from quarterly testing in a letter dated June 29, 1982 from NRC to Beaver Valley.
Actions Taken:
OSTs 1.46.6 and 1.46.7 have been written to ensure that valves MOV-1HY-201A and M0V-1HY-201B are tested quarterly as required by the Code. In addition, a review was performed by the Duquesne Light Company Quality Assurance Unit to identify any other discrepancies with the June 29, 1982-NRC letter. The administrative procedures being developed will specify that all testing will be performed in accordance with the Code unless specific relief has been granted.
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- 6-4 . Amendment No. JIe fe "I M G9 4
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-63' FACIL11* STAFF QUALIFICATIONS .
6.3.1 - . . 4 -
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The Ee.n*>crs of the facility staff shall :eet er exceed the folleving qualificaticus : ,
Mee President & Director / Deputy Director
. - Require =ents: Ten years total power plant experience of which three years =ust be nuclear power plant experience. A nazi =u= uf four years of acade=ic training may fulfill four of *the remaining seven years of required experience. Both = cst be capable of obtaining or possess a Senior Reactor Operator's License. -
,- Plant Operations Director Re quirements : Eight ye.srs' total power, plant experience of whic5 three years must be nuclear power plant' experience. A maximum of two years of academic or related technical training may fulfill two -
years of the remaining five years of required experience. The Plant Operations Director must be capable of obtaining or possess a Senior Reactor Operator's License'. .
Plant Engineering Director .
I llequire=ents: Eight years of responsible positions related to power" g enera t(o_n, of which three years shall be nnelear power plant ,
. ^. experience. A maximum of four of the remaining five years of
, experience may be fulfilled by satisfactcry ceipletion 'of academi-or related technical training.
- Manager Plant Administration Requirenents: Eigh~t years total power plant experience of which
. four years must have been in nuclear power plant experience. Th e Manate.: should possess a four year college degree or equivalent in .
', Business Administration er an Engineering discipline. .
- Manager Plent Operations
[' Re qui reme n'ts : Eight years total power plant experience of which I
three years must .be nuclear power plant ' experience. A maxi =um of two years of academic or related technical training may fulfill two -
i- of the remaining five years of required experience. The Manager.
! Plant Operations must possess a Senior Reactor Operator's License.
Safety Review Manager Requirements : Eight years total power plant experience of which three years must be nuclear power plant experience. A maximum of two years of academic or related technical training may fulfill two of the remaining five years of required experience.
e em.
e e 6-5 hendbent No. N, fs, 9
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. b b4e T d $ptc. (Q Mannger Cora Enginaaring ,U s .
% At"the time. of initial core leading or appointment to the. position, F - - whichever is later, the responsible person shall have a Bachelor's '
Degree in .Engideering or the Physical Sciences and four years experience or a graduate degree and three years experience. Two of these years shall be nuclear power plant experience. The experience shall be in such areas as reactor physics, core measurements , core heat. transfer, and core physics testing programs. Succe s s ful
- - coupletion of a reactor engineering training program (such as the 12 '
week concentrated programs of fered by NSS Vendors) nay be equivalent to one year's nuclear power plant experience.
Manager Plant Materiel -
Requirements: Sev'en years of total power plant experience of which one year must be nuclear power plant experience. Two years of* '
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academic or related technical training may fulfill two of the
- remaining six years of required experience. ,
Area Supervisor Instrument & Comnuter Maintenance .
Requirements: Five years of experiesce in ins trumentation and control, of which a minimum of one year shall be -in nuclear instrumentation and control at an- operating nuclear power plant . A
, max 6 m of four years of this five year ~ experience may be ful fille'd by related technical or academic training. ,
t Manager F1 Tnt Engineering The engineer in charge of . technical support shall have a Bachelor's
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Degree in Engineering or the Physical Sciences and have three years -
of professional level experience in nuclear services, nuclear plant operation, or nucled engineering, and the necessary overall nuclear background to determine when to call consultants and contractors fer .
dealing with complex problems beyond the scope of owner-organizagion .
expertise. .
Mar / Deputy Radiological Controls (Reports Offsite) ,
' Requirements: Bachelor's degree or the equivalent in a science or
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- engineering subject, including some fornal training in radiation protection. Five years of professional experience in applied radiation protection. (Master's degree ' equivalent to one year experience and Doctor's degree equivalent to two years experience where coursework related to radiation protection is involved.) Three years of this professional experience should be in applied radiation protection work in a, nuclear facility dealing with radiological -
problems similar to those encountered in nuclear power stations.
!- Chemistry Manager ,
Requirements: Five years experience in chemistry of which a m'inimum of one year shall be in radiochemistry at an operating' nuclear power e
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.. 6-6 , Amendment No. g g
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' picnt. A naximum of four years of this five year experiesca =ay b fulfilled by related technical or acade=ic training.
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b M&C Director, O.C.
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Requirements: . Seven years of total power plant experience 'of which one year must be nuclear power plant experience. Two years of academic' or related technical training may fulfill two of the remaining six years of required experience. -
Shift Technical Advisor -
Requirements: 3 ache' lor's degree er equivalent in a scientific or engineering discipline with specific training in plant design, and -
response -and analysis of the plant for transients and accidents. ,
6.3.2 ,,
4 Each member of the radiation protection organization for dich there is a comparable position described .in ANSI N18.1-1971 shall meet or .
exceed the minimum qualifications specified therein, or in the case of radiation protection technicians, they shall have at least one year's continuous experience in applied radiation protection work in
-a nuclear facility dealing with radiological problems similar to those encountered in nuclear power stations, and shall have been certified by the Mgr/ Deputy Radiological Con ~trols , as qualified,to' perform assigned functions. This certification must be based on an' NRC approved, documented program consis tiing' of classroem training
- with spir ~o~priate examinations and docenented positive findings by
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re'sponsible supervision tha t the individual has demonstrated his ability to perf orm each s pecified procedure and assigned function
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with an understanding of its basis and purpose.
6.4 TRAINING b4.1
- 3 A retraining program for operators shall be maintained under the direction of the Manager Plant Training Oyster Creek and shall meet
- ' the requirements and recommendation of Appendix A of 10CFR Part 55.
Replacement tri.ining prograns, the content of which shall meet the l.
~
requirements of 10CFR Part 55, shall be conducted under the l~. direction of the Manager Plant Training Oyster Creek for licensed l
operators and Senior Reacter operators. ,
6.4.2 t A training program for the Fire 3rigade shall be maintained under the direction of ' the Manager Plant Training Oyster Creek. ,
4 S
6-7 Amendment No. 6 9 S
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- 6. 7.1 - ,
The . following acticus shall be taken in the event a Safety Limit is '
violated:
- a. If' any Safety Limit is exceeded, the reactor shall be shut down immed ia t ely until the Cc==ission authorices the resump' tion of operation.
- b. -. The Saf e ty Limit . violation shall be repcrted to ,the Cc= mission and the Vice President & Director Dyster Creek,
- c. . A - Saf ety Limit Violation Report shall-be prepared. The report shall be submitted to the Vice President & Director Dyster Creek.
-This report shall describe (1) applicable circu= stances preceding the violation, (2) effects of the violation upon facility ecmponents sys tems . or s tructures, and (3) correotive action taken to prevent recurrence.
d.- The Safety Limit Vi'olation Report shall be submitted to the
- ' Commission within 10 days of the violation.
6.8 PROCEDURIS -
6.8.1' .
Written pr'idedures shall be established, i=plemented., and maintained that meet or' exceed the requirements of Section 5.2 and 5.3 of American National Standard N18.7-1976- and Appendix "A" of the Nuclear Regulatory Comission's Regulatory Guide 1.33-1972 except as
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4
. provided in 6.8.2 and 6.8.3 below. .
6.8.2 ,
Each procedure and administrative policy of 6.8.1 above, and changea -
thereto, shall be reviewed as described in 6.5.1.1 and approved as -
described in 6.5.1 prior to implementation and periodically as-specified in the Administrative Procedures. ,.
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! 6.8.3 - .
Temporary changes to procedures 6.8.1 above may be made provided:
f1
~ a. ' The intent of the original procedure is not altered.
- b. The change is approved by two members of GPUNC Management Staff p authorized under Section 6.5.1.12 and knowledgeable in the area affected by the procedure. For changes which may affec't the
. ' operational status of facility systems .or equipment, at least one of these individuals shall be a member of f acility management or supervision holding 'a Senior Reactor Operator's License on the facility.
A
- c. The change is documented, subsequently reviewed and approved as
- described in 6.8.2 witida 14 days of implementation.
6-15 Amendment No. g g .
p 6.9 RIPORTING7 REQUIREMENTS CW Tuk . bp .
'.- In addition to the applicable reporting requirements of 10,CFR, the .
_. following id'entified reports shall be submitted to the Director of <
the appropriate Regional Office of Inspection and Inforcement unless otherwise noted. -
6.9.1 ROUTINE REPORTS a ." Startup Report. A su=may report of plant startup and power escalation testing shall be submitted f olowing (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier , and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of th's plant'. The r'eport shall address each of the tests identified in the FSAR and . .
shall in general include a description of the measured values of the * * -
operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions .and ,
s pecifica tions. .Any corrective actions that were required to obtan .
satisf actory operation shall also be decribed. Any additional specified details required in license conditions based on' other -
conmitments shall be included in this report.
Startup reports shall be submitted within (1) 90 da'ys following completion of the,startup test program, (2) 90 days 'f ollowing resumption, or co=mencement of coumercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the S t ar t.up Report does not cover all three events (i.e., initial criticality, co=pletion of .startup test program, and. resumption or ,
co==encement of co=m'ercial power operation), supplemetary reports
.shall be' submitted at lea s t every three months until all three .
events have been. completed. . .
- b. Annual Exposure Data Report. Routine exposure data reports covering the operatien of the f acility during the previous calendar year shall be submitted prior to March 1 of each year. Reports.
- , shall contain a tabulation on an annual basis of the number of l - station, utility, and other personnel (including contra c t or s )
- receiving exposures greater than 100 mrem / year and their associated
- man re= exposure according to work and job functions (This tabulation supplements the requirements of 10 Cnt 20.407), e.g. , -
reactor operations and surveillance, inservice inspection, routine maintenance, special caintence (describe maintence), vaste processing', and refueling. The dose as signmen t to various duty functions may be es ti=ates based on pocket dosimeter, TLD, or film badge =easurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose recieved from external j
sources shall be assigned to specific major work functions.
- c. Monthlv Ooeratier Report. Routine reports of operating statistics and shutdown experience shall be sub=itted on a monthly I
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l l
' se-6-16 i l
A=endment Fo. 69
b\x(fR.X\I 4.,k b h. P .
20 ostinctes of tho'likely r$3ulten exponu o ind-vidualo L cod to pspulation grcups, and acsumpticu epon .
'. which estimates are based shall be provided. .<.
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.- (c). If statistically significant variations of offsite evironmental conc ~entrations with time are ob s e rv e d ,
correlation of these results with effluent release shall be provided. . .
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(d).
. Results of required leak tests' performed cut sealed sources if the tests reveal the presence o~f 0.005 nicrocuries or nore of removeable contamination.
If
- d. Inoperable Fire Protection Equipment (3.12)
- e. Core Spray Sparger Inservice Inspection (Table 4.3.1-9) .
Prior to startup of each cycle, a special report presenting the
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. results of the inservice inspection of the Core Spray spargera during each refueling outage shall be submitted "to the Commission, -
for review. -
6.10 RECORD RE m rION 6.10.1 .
The following records shall be retained for at least five years:
- a. Recoris'and legs of facility operation covering time interval at each power level. ,
- b. Records and logs of pr.inciple maintenance activities, .
inspections, repair and replacement of principal items of equipment
- related to nuclear safety.
- c. Reportable occurrence reports. , ,
- d. Records of su:veillance activities, inspections and calibrations, required by these technical specifications. .
! - e. Records of reacter tests and experiments. ,
( -
- f. Records cf changes made to operating procedures. .
l l g. Records of radioactive shipments.
- h. Records cf sealed source leak tests and results.
l l i. Records cf annual physical inventory of all source caterial of l
record.
6.10.2 The following reccrds shall be retained for the duration of the l .
6-22 Amendment No. 6 9 n
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MY $h, h .
Q Faci' lite Operating Lican g:, ,
- a. Recorf and drawing changes reflecting facility design
' ' '~
nodifications made to systems and equipment described in the' Final Safety Analysis Report.- ,
- b. Reccrds of new and irra*diated fuel inventory, fuel transfers and -
asse=bly burnup histories. .
- c. Records of facility radiation and contamination surveys.
~
- d. Records of radiation exposure for all individuals entering radiation control areas.
e.. Records of gaseous and liquid radioactive material released to the environs.
- f. Records of transient or operational cycles for those facilitiy components designed for a limited number of transients or cycles.
- g. . Records of training and qualitication for current, members of the p not staf f.
- h. Records of inservice inspections performed pursuant to these technical specifications. ,
- i. Records of reviews performed for changds made to procedures or equipment _cr reviews of tests and experiments pursuant to 10 CFR 50.59. -
- j. Records of revievs by the Independent Orisite Safety Review
Group.
- k. Reecrds for Envircamental Qualification which are covered under the provisions of paragraph 6.14 6.10.3
' . Quality Assurance Records shall 'be retained as specified by the
- Quality Assurance Plan. .
6.11 RADIATION PROTECTION PROGRAM ,
Procedures for persennel radiation protection shall be prepared
_ . . consistent with the requirements of 10 CFR 20 and shall be approved,
=aintained and adhered to for all operations involving personnel radiatien exposure.
. 6.12 (Deleted) .
(
! 6-23 Amendment No. 69 ,
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