ML20215K458
| ML20215K458 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/19/1987 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20215K456 | List: |
| References | |
| NUDOCS 8706250332 | |
| Download: ML20215K458 (10) | |
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Primary Coolant System.. Pressure Isolation Valves Specification:
Periodic leakage testing (a).on each valve listed in j
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1 table:4.3.1 shall be' accomplished prior to exceeding 600 psig reactor pressure every time the plant is placed'in j
the cold shutdown condition for refueling, each time the i
plant is placed in a cold shutdown' condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceeding 9 months, whenever the valve is moved whether by manual actuation or due to -flow conditions, and af ter returning the valve to service af te:.aintenance, repair or replacement work is performed.
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Reactor Coolant System Leakage 1.
Unidentified leakage rate shall be calculated at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
2.
Total leakage rate (identified and unidentified) shall be calculated at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, j
3.
A channel calibration of the primary containment sump flow integrator and the primary containment equipment drain tank flow integrator shall be conducted at least Once per 18 months.
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-Bases:
l Numerous data are available relating integrated flux and the change in 1
Nil-Ouctility Transition Temperature (NDTT) in various steels.
The base
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metal has been demonstrated to be relatively insensitive to^ neutron j
irradiation (see expected NDT changes in FDSAR-Table IV-1-1, and Figures IV-2-0 and IV-2-10).
The"most conservative data has been used in Specification 3.3.
The integrated flux'at the vessel wall is calculated 1
from core physics data and will.be measured using flux monitors installed inside the vessel.
The measurements of the neutron flux at the vessel wall will be used to check and if necessary correct, the calculated data to.
determine an accurate flux.
From this a conservative NDT temperature gan be 1
determined. Since no shift will occur until an integrated flux of 10 /
nyt is reached, the confirmation can be made long before an NDTT shift would
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occur.
The inspection program will reveal problem areas should they occur, before a leak develops.
In addition, extensive visual inspection for leaks will be made on critical systems. Oyster Creek was designed and constructed prior to 1
1' Dd To satisfy ALARA requirements, leakage may be measured indirectly (as C
from the performance of pressure indicators) if accomplished in accordance 02 o with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with the leakage p
criteria.
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- NRC Order dated April 20, 1981 Corrected:
1/28/86 asa' OYSTER CREEK 4.3-2 Amendment: 82, 97, i
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- q NOTES TO FIGURE 6.2.1 i
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- 1. 'The. project engineers,. the shif t' technical advisors, and core engineering manager assigned to the nuclear plant site will report to the Vice l
President' Technical Functions.
2.
The quality assurance, emergency planning and radiological and' l
environmental controls functions assigned to the nuclear plant site'will I
report to. the.Vice President. Quality and Radiological Controls.
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3.
The security, materials management, personnel and. general administrative,-
I and training and education functions assigned to the nuclear plant-site j'
will report to the Vice President Administration.
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The Nuclear Safety Assessment, Licensing, and Long Range Planning functions will report to-the Vice President Planning & Nuclear Safety.
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5.
The conduct of all Oyster Creek modifications, construction, and maintenance activities'will be the responsiblity of the Maintenance,-
ConstructionLand Facilities Director - Oyster Creek, who will report to the Vice President Maintenance, Construction and Facilities.
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0YSTER CREEK 6-4 Amendment No. 50, 59, 69,
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OYSTER CREEK I
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6.3-FACILITY STAFF QUALIFICATIONS 6.3.1 The members of the f acility 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 remaining 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.
i Plant Engineering Director Requirements:
Eight years of responsible positions related to power generation, 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 satisf actory completion of academic or related technical training.
Manager-Plans and Programs l
Requirements:
Eight years total power plant experience of which four years must have been in nuclear power plant experience.
The Manager should possess a four year college degree or equivalent in Business Administration or an Engineering discipline.
Manager-Plant Operations o
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.
The 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.
I 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 fulfull two of the remaining five years of required experience.
0YSTER CREEK 6-6 Amendment Nos: 50,59,65,69,78,
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 of experience in instrumentation 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 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 experience in nuclear services, nuclear plant operationi 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.
I Core Engineering Manacer At the time of initial core loading 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 years experience. Two of these years shall be nuclear power plant experience.
The experience shall be in such areas as e
reactor physics, core measurements, core heat transfer, and core physics testing programs.
Successful completion of a reactor engineering training program (such as the 12 week concentrated programs offered by NSS Vendors) 3 may be equivalent to one year's nuclear power plant experience.
Radiological Controls Director l
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 1
protection.
(Master's degree equivalent to one year experience and l
Doctor's degree equivalent to two years experience where coursework related 1
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.
Maintenance, Construction, and Facilities Director-0C Requirements: Semn 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.
0YSTER CREEK 6-7 Amendment Nos: 69,78,
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i 6.5.'3' AUDITS-6.5.3.1 ' Audits of f acility activities shall be performed under the cognizance of the Vice President Quality and Radiological Controls.
These Jaudits shall encompass:
i a.
The conformance of f acility operations to provisions contained.
i within the Technical Specifications and applicable license conditions at least once 'per 12 months.
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b.
The parformance, training and qualifications ~of the facility j
staff at least once per 12 months.
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c.
The results of actions taken to correct deficiencies occurring in
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facility equipment, structures, systems or method of. operation 1
that affect nuclear safety at least once per six months.
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d.
The Facility Emergency Plan and implementing procedures at least
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. once per 12 months.
The'F'acility Security Plan and implementing procedures at least e.
once per 12 months.
f.
The Fire Protection Program and implementing procedures at.least once per 24 months.
j-g.
The performance of a:tivities required by the Operational Quality Assurance flan to meet the criteria of Appendix 'B',10CFR50, at least once per 24 months.
h.
The' radiological environmental monitoring program and the results thereof at.least once per,12 months.
i.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at-least.once per 24 months.
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The. PROCESS CONTROL PROGRAM and implementing procedures for radioactive wastes at least once per 24 months.
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. Any other area of facility operation considered appropriate by the 10SRG or the Office of the President-GPUNC.
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6.5.3.2 Audits of the following shall be performed under the cognizance
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of the Vice President - Technical Functions:
i a.
An independent fire protection and loss prevention program inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
b.
An inspection and audit of the fire protection and loss c
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prevention program, by an outside qualified fire consultant at 0
intervals' no greater than 3 years.
0YSTER CREEK 6-12 Amendment No.:
69, 89, 108
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QUALIFICAT10N5Y U
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6.5.4.5 -10SRG engineers shall have eithy (1);a Bachelor's Degree in D
EngineeringorappropriatePhysicaljGinceandthreeyearsof
- E professional level experience in the nuchtr power field which may include g
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technicalsupportingfunctionsor(OIeightyearsof' appropriate j:
experience in nuclear power plant nedtfons and/or technologye Credit D{3, toward experience will' be given 9r advance deyrees on a one-to-ore basis r
up to-a maximum of two years.
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RECORDS
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6.5.4.6 Reports' of fyaYuatiy.r ard assessmepts encompassqd in Section s,,
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1.5.4.3 shall'be prep 4ryd, auprv,d, ud tri.nsci,'ttes to the Nuclear Safety A; >',O,
assessment Director,.0ysp;/ Craf,pred Pls.ning & Nuclear ' Safety Myfision Vice Prdsident, and,jthe san,agcaunt posMon.vyespepsitle.for the tcreas mf jt
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6.6,R,,CPORIABLd EVENT ACTION
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6.6.lfhtfoiyowingactionsshallbetakenforREPORTABLEkVENTS:
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,1 f,.a. _ Tha Commissicr. shall be notified and a report submitted purstiant
', fto the reaeffetpts of Sectiop'60.73 to 10 CFR Part 50; and
,it b y. EWh REPORTKdLE EVENT stial)..be reported to thricognizant manager
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, and' the cognizhnt' division Vice President and the Vice President
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& Ofrector Oyster Creek.
The functionally cognizant division staff shall prepare.c Licensee Event Report (LER) in accordance
yrith the guidacce outlined in 10 CFR 50.73(b).
Copies of all
/ such reportv shall.de submitted to the functionally cognizant division Vice President and the Vice President Director & Oyster Creek.
,'6.P,3AFETY lit 1IT VIGLAIICC 6.7.'l ThefadowingactionsshallbetakenintheeventaSafetyLimitis violated:
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If any Safety Limit is ex.ceeded, the reactor shall be shut down imraediately until tne Cownission authorizes the resumption of operation.
b.
The Safety Limit violation shall be reported to the Commission l-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
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f acility components systems or structures, (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission within 10 days of the violation.
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OYSTER CREEK 6-14 Amendment No.:
69, 78, 84, 108 t--
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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 safety.
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All Licensee Event Reports.
d.
Records of surveillance activities, inspections and calibrations required by these technical specifications.
e.
Records of reactor tests and experiments.
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Records of changes made to operating procedures, g.
Records of radioactive shipments l
h.
Records of. sealed source leak tests and results.
1.
Records of ' annual physical inventory of all source material of record.
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 and irradiated fuel inventory, fuel transfers and assembly burnup histories, c.
Records of facility radiation and contamination surveys.
i 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 f acility components designed for a limited number of transients or cycles.
g.
Records of training and qualification for current members of the plant staff.
h.
Records of inservice inspections perfrmed pursuant to these technical l
specifications.
i OYSTER CREEK 6-19 Amend.aent Nos:
69, 108,