ML20101J709
| ML20101J709 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/27/1984 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20101J713 | List: |
| References | |
| NUDOCS 8412310107 | |
| Download: ML20101J709 (10) | |
Text
O LEroq'o UNITED STATES "g
NUCLEAR REGULATORY COMMISSION n
E WASHINGTON, D. C. 20555 s.,...../
GPU NUCLEAR CORPORATION AND JFRSEY CENTRAL POWER AND LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION AMENDPENT TO PROVISIONAL OPERATING LICENSE Amendment No. 78 License No. DPR-16 1.
The Nuclear Regulatory Commission (tha Commission) has'found that:
A.
The application for amendment by GPU Nucleer Corporation and Jersey Central Power and Light Company (the licensees) dated June 8, 1984 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facili y will operate in confornity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable essurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations.
D.
The issuance of this amendment will not be inimical to the common l
defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's reguletions and all applicable requirements have been satisfied.
4 8412310107 841227 DRADOCK05000g
, 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C(?) of Provisional Operatino License No. DPR-16 is hereby amended tc read as follows:
(2) Technical Specifications The Technical Specifications contained in Apoendices A and B, as revised through Amendment No. 78, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULAT Y COMMISSION John A. Zwolinski, Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuanc,e:
ATTACHMENT TO LICENSE AMENDMENT NO. 78 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by the captiored amendment number and contain vertical lines indicating the area of change.
Remove Pages Replace Paoes 6-4 6-4 6-5 6-5 6-6 6-6 6-7 6-7 6-15 6-15 6-2?
6-22 6-23 6-23 6
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6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Tne members of the facility staff shall meet or exceed the following qualificationa:
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 remaining seven years of required experience. Both must be capaole 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 generation, of which three years shall be nuclear power plant experience. A 1.wrimum of four of the remaining five years of experience may be fulfilled by satisfactory completiortof academic or relate.d technica2 training.
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Manager-Plant Administration Requirements: Eight years total power plant experience of which four years must have been in nuclear power plant experience. h e Manager snould possess a four year college degree or equivalent in Business Administration or an Engineering discipline.
Manager-Plant Operations a
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, n e Manager Plant Operations must possess a Senior Reactor Operator's License.
Manager-Plant Chemistry Requirements: Five years experience in chemistry of wnich 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.
6-5 Amendment No. p, 581, 56, ps, 78
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.
Manager-Plant Materiel 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.
Area Supervisor-Instrument and Computer Maintenance Requirements: Five years o'f experience in instr'umentation and control, of which a minimum of one year shall be in nuclear 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 academi'c' 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 s
professional level experience 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 i
expertise.
Core-Manager At. the time of initial core loading or appointment to the position, whichever is lateG 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 years experience. Two of j
these years shall be nuclear power plant experience. The experience shall De in such areas-as reactor physics, core measurements, core heat transfer, and core physics testing programs. Successful ccupletion of a reactor engineering training program (such as the 12 week concentrated programs offered by NSS Vendors) may be equivalent to one year's nuclear power plant experience.
I Radiological Controls Director (Reports Offsite)
Requirements: Bachelor's degree or the equivalent in a science or engineering subject, including some formal' 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 6-6 Amendment No. 6)l, 78
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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 iri nuclear power stations.
M&C Director, O.C.
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 tnere is a comparable position descrioed in ANSI N18.1-1971 shall meet or exceed the minimum qualifications specified therein, or in the c&se 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 sinilar to those
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encountered in nuclear power stations. and shall have been certified by the Radiological Controls Director', as qualified to perform assigned functions. Bis certification Jnust ce cased on an IEC approved, documented program consisting of classroom training with i
appropriate' examinations and documented positive findings by responsiole supervision that the individual nas demonst~ rated his ability to perform each specified procedure and assigned function with an understanding of its' basis an purpose.
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 rectznmendation of Appendix A of 10CFR Part 55.
Replacement training p'rograms, the content of which shall meet the requirements of 10CFR Part 55, shall be conducted under the direction l
of the Manager Plant Training Oyster creek for licensed operators and Senior Reactor Operators.
6.4.2 A training program for the Fire Brigade snall be maintained under the direction of the Manager Plant Training Oyster Creek.
6-7 AmendmentNo.fd,78
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6.7 SAFETY LIMIT VIOLATION 6.7.1
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The following act' ions shall be taken in the event a Safety Limit is violated:
a.
If any Safety Limit is exceeded, the reactor shall be shut down imediately until the Comission authorizes the resunption of operation.
b.
Se Safety Limit violation shall be reported to the Comission and the Vice Presic. ant 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 snall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components systems' or structures, and (3) corrective action taken to prevent s
recurrence.
d.
S e Safety Limit Violation Report shall be submitted to the Comisision within 10 days of the violation.
6.8 PROCEDURES,
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Written procedures shall.be established, inplemented, and maintaine'd that meet or exceed. the recuirements of the Nuclear Regulatory: Commission's Regulatory Guide 1.33 (the applicable revision is identified in the GPU Nuclear Operational Quality Assurance Plan) and as provided iri 6.8.2 and 6.8.3 below.
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6.8.2 Each procedure and administrative policy of 6.'8.1 above, hnd 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 l
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specified in the Administrative Procedures.
l 6.8.3 hmporary changes to procedures 6.8.1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
S e change is approvided by two members of GPUNC Managenent Staff authorized under section 6.5.1.12 and knowledgeable in the area affected by the procedure. For changes which may affect the l
operational status of facility systems or equipment, at least cne of l
these individuals shall be a member of facility management or supervision holding a Senior Reactor Operator's License on the facility.
c.
W e change is documented, subsequently reviewed and approved as described in 6.8.2 within 14 days of implementation.
6-15 Amendment No.
, 78 m
6.10.2 s
'me 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 and irradisted fuel inventoryi fuel transfers and assembly 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 gaseods and liquid radiactive material released to.
the environs.
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f-Records of transient or operational cycles for those facility components designed for a limit'ed number of transients or cycles.
g.
Records of training and ipalification for current members of the plant staff.
h.
Records of inservice inspections performed pursuant to these technical specifications.
- i. Records.of reviews performed for changes made to procedures or equipment.or. reviews of tests and experiments. pursuant to 10 CFR 50.59.
.j. Records of reviews by the Independent Onsite Safety Review Group.-
.k.
' Records for Environmental Qualification which are covered under the provisions'for 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 personnel radiation protection shall be prepared consistent with.the requirements of 10 CFR 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 (Deleted)
Amendment [78 6-23
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20 estimates of tha liksly ruultant 4xposure to individuals and to populction groups, and assumptions upon which estimates are based shall be provided.
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(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 Spipment (3.12)
Core Spray Sparg'er Inse'vice Inspection (Table 4.3.1-9) r e.
Prior to startup of each cycle, a special report presenting the results of the inservice inspection of the Cor6 Spray Spargers during each refueling outage shall'be submitted to the Comnission for review.
l f.
Failures and challenges to Relief and Safety Valves I
Failures and challenges to Relief and Safety Valves which do not constitute an LER will be the subject of a special report suomitted to the Comission.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.,
s 6.10 RECORD RETENTION B
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.
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b.
Records and logs of principle maintenanc.e. activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
Reportable occurrence reports.
Records of surveillance 'ctivities, inspections and calibrations d.
a required by these technical specifications, e.
Records of reactor tests and experiments.'
f.
Records of changes made'to operating procedures."
9 Records of radioactive shipments h.
Records of sealed source leak tests and results..
- i. Records of annual physical inveMory of all source mat'erial of record.
6-22 AmendmentNo.p,78 i
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