ML17342A538
| ML17342A538 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/13/1986 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17342A537 | List: |
| References | |
| GL-83-43, GL-85-19, NUDOCS 8605200334 | |
| Download: ML17342A538 (9) | |
Text
0
~
any consecutive 6 month period, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.3 within 30 days indicating the number of hours above this limit.
b.
With the specific activity of the primary coolant greater than I.O microcurie per gram DOSE EQUIVALENT I-l3I for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line shown on Figure 3.I-I, be in a SHUTDOWN condition with average reactor coolant temperature less than 500 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- c. With the specific activity of the primary coolant greater than l00/E microcuries per gram, be in a SHUTDOWN condition with average reactor coolant temperature less than 500 F
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
2.
For all modes of operation a.
With the specific activity of the primary coolant greater than I.O microcurie per gram DOSE EQUIVALENT I-I3I or greater than I00/ E microcuries per gram, perform the sampling and analysis requirements of item I.h.l of Table 4.I-2 until the specific activity of the primary coolant is restored to within its limits.
f BbP5200334 Bb0000250 PgR
@DOCK 0>
P>R P
3.1-5 Amendment Nos.
and
SC ECLIfIVE VCEt%MfNT C~ANT NICLEANIRVlbV OOAND SIRE VKS tNTSIOITN'OXLXAN ITSNIT
%MLITT A%LRANCK COIONTTEE VICS HISOBIf NXLKNSFNATIOS OINECTIN NECIKlkLICÃNENN VN:K~IICKNT QNMSXNICI tESXCT IIANi&ISNT IOEiaSNTINTION VCKtaagaNT
~ SNttLT,
~TSTEIItLaMSN~
FNLKONIKES VICE FISSIOENT TUNCT HNS'QEQ IIANAOIR NXLEASKARST SENVICES NOCLfANERICH ENVICSS STJtt SISNE42 I OIFAITKCMANRATIONARFACIQT ILANAIIISNTNQ TECNNICAL$&tORf SASPKRIN~
TUFT tOON'NCLEJA Amendment Nns.
~
~
VICE PRKSIDENI'INNEY POINT MXLEAR N~~~~~~%~~0~~~~
gPglNTggg QUALITYASSWANX j/////////////////
J r
MICLEARENERSY SERVICES STAFF INALTHPHYSICS REFER TO FIR ILS-I'II g9,'A%%%~XQ'Nfrrrr///rrk WI1 Ii OPERATINRI INALITY SLÃ%RINT CNITNL MICLEAR SLPSWIQSI 1
TECINICAL OEPARTl%NT 8$%RVISIN SAFETYAle FIRE PROTECTION TRAINIIO RPNVIQSI MICLEARONROY SERVICES STAFF FIRE PROTKCTIINI AONlNISTRATKQ REFKR TO FIILdd-I SiTE BIIKKRIIM llANASKR SAFETY EMIIIRKRIIM SRQS'HAIRHAN
%ALTH PHYSICS Ql%RVI 0%RATINS I%IIISTRY SLl%RVIQSI SLI%RVIQSI INSTRO%1IT Ale CIITRO.
SL$%RVIQQ ASSISTANT 8$%NNTKIIOIT
%CHANICAL IIAINIKNANX MICLEAR ASSISTANT SPKRINRNXNT ELECTRICAL IIAINTKNAICE MXXEAR RAOIATIOI REACTIR PROTECTIQI EN8 IEGER t5AN PLAN'LI%RVISNI MXLEAR RAOIO CHRIST QIIFT TECMIICAL AOVIQNI MN'.LEAR WATCH OSIER
- 1. SENIOR OPERATOR LICENSE
- 2. OPERATOR LICOISE LICENSEO POISOWEL ON SHIFT AS QNWN INTAOLEd2-I MICLEARCONTIHS.
CENTER OPERATOR IN.ICENSKO 0%RATISIS PLANT ORBANIZATIONCHART FIQLNEILS&
Amendment Nos.
and
6.5.1.8 RECORDS The Plant Nuclear Safety Committee shall maintain written minutes of each meeting and copies shall be provided to the Vice President - Nuclear Operations and Chairman of the Company Nuclear Review Board.
6.5.2 COMPANY NUCLEAR REVIEW BOARD (CNRB) 6.5.2.1 FUNCTION The Company Nuclear Review Board shall function to provide independent review and audit of designated activities in the areas of:
a.
Nuclear power plant operations.
b.
Nuclear engineering.
c.
Chemistry and radiochemistry.
d.
Metallurgy.
e.
Instrumentation and control.
f.
Radiological safety.
g.
Mechanical and electrical engineering.
h.
Quality assurance practices.
6.5.2.2 COMPOSITlON The CNRB shall be composed of the following members:
1.
Chairman:
2.
Member:
3.
Member:
0.
Member:
5.
Member:
6.
Member:
7.
Member:
S.
Member:
9.
Member:
10.
Member:
Group Vice President - Nuclear Energy Vice President - Nuclear Operations Vice President
- Engineering, Project Management, and Construction Chief Engineer Power Plant Engineering Director - Nuclear Licensing Director - Quality Assurance Manager - Nuclear Energy Services Manager - Nuclear Fuels Senior Project Manager - Power Plant Engineering Group Vice President 6-9 Amendment Nos.
and
g.
With untreated gaseous effluents exceeding the limits of 3.9.2.e pursuant to Specification 3.9.2.e.2, submit a report which includes the following information:
(1)
Identification of the inoperable equioment or subsystems and the reason for inoperability, (2)
Action(s) taken to restore the inoperable equipment to OPERABLE status, and (3)
Summary description of action(s) taken to orevent a
recurrence.
h.
With the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC from all uranium fuel cycle sources exceeding the limits of Technical Specification 3.9.2.h, submit a report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.9.2.h and includes the schedule for achievinq conformance with those limits.
This report, as defined in 10 CFR Part 20.005c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report.
It shall also descr ibe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.
If the estimated dose(s) exceeds the limits of Specification -3.9.2.h and if the release condition resulting in violation of 00 CFR Part 190 has not already been corrected, the report shall include a request for a variance in accordance with the provisions of 00 CFR Part 190.
Submittal of the report is considered a timely
- request, and a variance is granted until staff action on the request is comolete.
i.
With the measured levels of radioactivity in environmental samples as a result of plant effluents pursuant to Specification 0.12.1.b, submit a
report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential dose to a MEMBER OF THF PUBLIC is less than the limits of Specifications 3.9.1'.b, 3.9.2.b and 3.9.2.c.
j.
Whenever the results of steam generator tube inspections fall into Category C-3 of Table 0.2-3, a Special Report shall be submitted within 30 days and prior to resumption of plant operation.
This report shall provide a
description of investigations conducted to'etermine cause of the tube degradation and corrective measures taken to prevent recurrence.
Reference T.S. 0.2.5 5.c.
Amendment Nos.
and
The Radioactive Effluent Release Report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.I-I) during the report period.
AlI assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports.
The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents, and determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses.
Approximate and conservative approximate methods may be used in lieu of actual meteorological measurements.
The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATIONMANUAL(ODCM).
The Radioactive Effluent Release Report to be submitted 60 days after January I
of each year shal I also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases for the previous calendar year.
Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide I. I 09, March I 976.
The Radioactive Effluent Release Report shall also include the results of specific active tyanalysis in which the primary coolant exceeded the limits of Specification 3.I.4.2.a.
The following information shall be included:
I) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was
- exceeded,
- 2) Fuel burnup by core region,
- 3) Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded,
- 4) History of de-gassing operations, if any, starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was
- exceeded, and
- 5) The time duration when the specific activity of the primary coolant exceeded I.O microcurie per gram DOSE EQUIVALENTI-I 3 I.
The Radioactive Effluent Release Reports shall include the following information for each class of solid waste (as defined by IO CFR Part 6I) shipped offsite during the report period:
a.
- Volume,
- b. Total curie quantity (specific whether determined by measurement or estimate),
c.
Principal radionuclides (specify whether determined by measurement or estimate),
d.
Type of waste (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms),
e.
Type of container (e.g.,
LSA,,
Type A,
Type B,
Large Quantity), and
- f. Solidification agent or absorbent (e.q.,
- cement, urea formaldehyde).
6-2l Amendment Nos.
and
The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made "during the reporting period.
The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the OFFSITE OOSE CALCULATIONMANUAL(ODCM) and the PROCESS CONTROL PROGRAM (PCP) as well as a listing of new locations for dose calculations and/or environmental monitoring:
a.
Necessitated by the unavailability of environmental samples, pursuant to Specification 4.I2.l.c; report shall also include the causes for unavailability of samples b.
Identified by the land use census pursuant to Specification 4.I 2.2.
6.9.4.b ANNUAL RAOIOLOGICAL ENVIRONMENTAL OPERATING REPORT+
Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May I of each year.
The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and information based on trend analysis of the results of the radiological environmental surveillance activities for the report
- period, including a
comparison, as appropriate, with preoperational
- studies, with operational controls and with previous environmental surveillance reports and an assessment of the observed impact of the plant operation on the environment.
The reports shall also include the results of land use censuses required by Specification 4.I 2.2.
The Annual Radiological Environmental Operating Reports shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the Table and Figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision I, November l 979.
In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
+
single submittal may be made for a multiple unit station.
6-22 Amendment Nos.
and
0 The reports shall also include the following: a summary description of the radiological environmental monitoring program; at least two legible maps++ covering all sampling locations keyed to a table giving distances and directions form the centerline of the plant vent stack; the results of the lnterlaboratory ~ornparison Program required by Specification 4. I 2.3; discussion of all deviations from the sampling schedule of Table 4.I2-I, and discussion of all analyses in which the LLD required by Table 4.12-3 was not achievable.
- 6. I 0 RECORD RETENTION
- 6. IO.I The following records shall be retained for at least five (5) years:
a.
Records and logs of facility operation covering time interval at each power level.
b.
Records and logs of princioal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
AlI REPORTABLE EVENTS.
d.
%~cords 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 verifying accountability of sources on record.
++ One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.
6-23 Amendment Nos.
and
0