ML20118A394
| ML20118A394 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/27/1992 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML18058B029 | List: |
| References | |
| NUDOCS 9209020350 | |
| Download: ML20118A394 (19) | |
Text
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1 8
4 ENCLOSURE Consumers Power Company Palisades Plant Docket 50-255 8
i i
l-RADIOLOGICAL TECHNICAL SPECIFICATION RELOCATION Proposed Pages j
August 27, 1992 L
k 18 Pages
- 92090203S0 920827-
- PDR ADOCK 000002S5-
~ P-PDR 4
~.
. - _.,,,. -.,.... _ _. _.,.. -... ~. _, _. _ _ _ _ _ _ _ _
e PALISADES PLANT TECilNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A SECTION DESCRIPTION PAGE N0 3.0 LIMITING CONDITIONS FOR OPERATION (Continued) l 3.23 POWER DISTRIBUTION LIMITS 3-103 3.23.1 Linear Heat Rate (LHR) 3-103 Table 3.23.1 Linear Heat Rate Limits 3-107 Table 3.23.2 Radial Peaking Factor Limits, F 3 107 Fig. 3.23 1 Allowable LHR as a Function of heak Power Location 3-108 Fig.-3.23-2 Allowable LHR-as a function of Burnup 3 109 Fig. 3.23-3 Allowable-LHR as a Function of Peak Power Location i
for Interior and Narrow Water Gap Fuel Rods 3-110 3.23.2 Radial Peaking Factors 3-111 3.23.3 Quadrant Power Tilt - Tq 3 112 3.24 (Deleted) 3.25 ALTERNATE SHUTOOWN SYSTEM 3-134 Table 3.25.1 Alternate Shutdown Minimum Equipment 3-lh I
?
i l
l iii Amendment No. J/,,4E,E3,E/,EE,EE, l
195,117,151,
)
l :-.
PAllSADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A SECTION DESCRIPTION PAGE N0 4.0 SURVEILLANCE REQUIREMENTS 4-1 4.1 INSTRUMENTATION AND CONTROL 4-1 4.1.1 Overpressure Protection Systems 4-1 Table 4.1.1 Minimum frequencies for Checks, Calibrations and Testing of Reactor Protective System 4-3 Table 4.1.2 Minimum frequencies for Checks, Calibrations and Testing of Engineered Safety feature Instrumentation Controls 4-6 Table 4.1.3 Minimum frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls 4-10 4.2 EQUIPMENT AND SAMPLING TESTS 4-13 Table 4.2.1 Minimum Frequencies for Sampling Tests 4-14 Table 4.2.2 Minimum Frequencies for Equipment Tests 4-15 Table 4.2.3 HEPA Filter and Charcoal Adsorber Systems 4-15c 4.3 SYSTEMS SURVEILLANCE 4-16 Table 4.3.1 Primary Coolant System Pressure Isolation Valves 4-19 Table 4.3.2 Miscellaneous Surveillance Items 4-23 4.4 Deleted-4-24 4.5 CONTAINMENT TESTS 4-25 4.5.1 Integrated Leakage Rate Tests 4-25 4.5.2 Local Leak Detection Tests 4-27 4.5.3 Recirculation Heat Removal Systems 4-28a 4.5.4 Surveillance for Prestressing System 4-29 4.5.5 End Anchorage Concrete Surveillance 4-32 4.5.6 Containment Isolation Valves 4-32 4.5.7 Deleted 4-32a 4.5.8 Dome Delamination Surveillance 4-32a 4.6 SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS TESTS 4-39 4.6.1 Safety injection Systrm 4-39 4.6.2 Containment Spray System 4-39 4.6.3 Pumps 4-39 4.6.4 Valves (Deleted) 4-40 4.6.5 Containment Air Cooling System 4-40 4.7 EMERGENCY POWER SYSTEM PERIODIC TESTS 4-42 4.7.1 Diesel Generators 4-42 4.7.2 Station Batteries 4-42 4.7.3 Emergency Lighting 4-43 4.8 MAIN STEAM STOP VALVES 4-44 4.9 AUXILIARY FEEDWATER SYSTEM 4-45 4.10 REACTIVITY AN0MAllES 4-46 4.11 (Deleted) l iv Amendment No. E7, EE,EE3E7,EE,EE JE9,128,JJf,
8 0
PAllSADES PLANT TECHNICAL SPECIFICATIONS JABLE OF CONTENTS - APPENDlX A S((110N DISCRIPTION PAGE N0 4.0 SURVElllANCE REQV181]iUlb (Continued)
Table 4.11-3 Detection Capabilities for Environmental Sample Analysis 4-57 4.11.1 Bases for Monitoring Program 4-59a 4.11.3 Bases for Land Use Census 4-59a 4.11.5 Bases for Interlaboratory Comparison Program 4 59a 4.12 AUGMENTED INSERVICE INSPECTION PROGRt.M FOR HIGH ENERGY LINES OUTSIDE OF CONTAINMENT 4-60 Fig. 4.12 A Augmented Inservice inspection Program - Main Steam Welds 4 63 Fig. 4.12 B Augmented Inservice Inspection Program - Feedwater Line Welds 4-64 4.13 REACTOR INTERNALS VIBRATION MONITORING (DELETED) 4-65 4.14 AUGMENTED INSERVICE INSPECTION PROGRAM FOR STEAM GENERATORS 4-66 Table 4.14.1 Minimum Number of Steam Generators to be Inspected During Inservice Inspection 4-69a Table 4.14.2 Steam Generator lube Inspection 4-69b 4.15 PRIMARY SYSTEM FLOW MEASUREMENT 4-70 4.16 INSERVICE INSPECTION PROGRAM FOR SHOCK SUPPRESSORS (SNUBBERS) 4-71 4.17 FIRE PROTECTION SYSTEM (Deleted) 4 76 4.18 POWER DISTRIBUTION INSTRUMENTATION 4-81 4.18.1 Incore Detectors 4-81 4.18,2 Excore Monitoring System 4-82 4.19 POWER DISTRIBUTION LIMITS 4-83 4.19.1 Linear Heat Rate 4 83 4.19.2 Radial Peaking Factors 4-84 4.20 MODERATOR TEMPERATURE COEFFECIENT (MIC) 4-85 4.21 ALTERNATE SHUTDOWN SYSTEM 4-86 Table 4.21.1 Alternate Shutdown System Montoring Instrumentation Surveillar.ce Requireents 4-87 4.22 (Deleted) 4.23 (Deleted) 4.24 (Delet)d) l v
Amendment No. 37,fE,EE,E/,EE,EE, JPE,JJE, Ill, Jfl,151,
4 PALISADES PLANT TECHNICAL SPECIFICATIONS lABLE OF CONTENTS - APPENDIX A SECTION DESCRIE11QH PAGE N0 1
5.0 DESIGN FEATURES 5-1 5.1 SITE 5-1 5.2 CONTAINMENT DESIGN FEATURES 5-1 5.2.1 Containment Structures 5-1 5.2.2 cenetrations 5-2 5.2.3 Containment Structure Cooling Systems 5-2 5.3 NUCLEAR STEAM SUPPLY SYSTEM (NSSS) 5-2 5.3.1 Primary Coolant System.
5-2 5.3.2 Reactor Core and Control 5-3 5.3.3 Emergency Core Cooling System 5-3 5.4 FUEL STORAGE 5-4 5.4.1 New fuel Stcrage 5-4 5.4.2 Spent fuel Storage 5-4a Figure 5-1 Site Environment TLD Stations 5-5 6.0 AQHINISTRAllyE CONTROLS 6-1 6.1 RESPONSIBillTY 6-1 6.2 ORGANIZATION 6-1 6.2.1 Offsite and Onsite Organizations 6-1 6.2.2 Plant Staff 6-2 6.3 PLANT STAFF QUALIFICATIONS 6-3 Table 6.2-1 Minimum Shift Crew Composition 6-4 6.4 TRAINING 6-5 vi Amendment No EE,JPE,JpE J27,J3E,
PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS APPENDIX.A SECTION DESCRIPTION PAGE N0 6.0 ADMINISTRATIVECONTROLS(Continued) 6.5 REVIEW AND AUDIT 6-5 6.5.1 Plant Review Committee (PRC) 6-5 6.5.2 Nuclear Safety Services Department (NSSD) 6-6a 6.5.3 Plant Safety and Licensing 69 6.6 (Deleted) 6 10 6,7 SAFETY LIMIT VIOLATION 6 10 6.8 PROCEDURES AND PROGRAMS 6-10 6.9 REPORTING REQUIREMENTS 6-14 6.9.1 Routine Reports 6-14 6.9.2 Reportable Events 6-15 6.9.3
.0ther Reporting Requirements 6-18 6.9.3.1 Routine Report 6 18 6.9.3.1.A Radioacti"a Effluent Releases Report 6-18 6.9.3.1.B Annual Radiological Environmental Operating Report 6-18 6.9.3.2 Nonroutine Reports 6 18 6.9.3.3 Special Reports 6-26 6.10 RECORD RETENTION 6 26 6.11 RADIATION PROTECTION PROGRAM 6-28 6.12 HIGH RADIATION AREA 6-28 6.17 (Deleted) 6-33 6.14 (Deleted) 6-33 6.15 SYSTEMS INTEGRITY 6-33 6.16.
10 DINE MONITORING 6-33 6.17 POST ACCIDENT SAMPLING 6 34 6.18 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6-35 6.19 PR0;ESS CONTROL PROGRAM (PCP) 6 35 6.20 (Deleted) l 6.21 SEALED SOURCE CONTAMINATION 6-37 6.22 SECONDARY WATER CHEMISTRY 6-38 vii Amendment No. JpE, JJp, J27, p
1 1.4 MISCELLANE0US DEFINITIONS (Contd)
MEMBER (S) 0F THE PUBLIC MEMBER (S) 0F THE PUBLIC _ shall include all persons who are not occupationclly associated with the plant.
This category does not include employees of the utility, its contractors or vendors.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
3FFFTTE 00jiE_ CALCULATION MAMIAL (00CM) 1he 0FFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methcdology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm /TL :p Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also ;ontain the (1) Radiological Effluent Controls-and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information should be included in the Annual Radiological Environmental Operating Semiannual Radioactive Effluent Release Repor+t required by Specifications 6.9.3.lA and B.
The PROCESS CONTROL PROGRAM shall contain the current formula, sampling, anal 3 0es,- tests and determinations _to be made to ensure that the processing L
and packaging of solid radioactive wastes based on demonstrated processing of L
actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Part 20, 61 CFR Part 71 State regulations l
burial ground requirements and other requirements governing the disposal of solid radioactive waste.
l-SITE B0UNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned nor otherwise controlled by the licensee, UNRESTRICTED AREA L
An UNRESTRICTED AREA shall be any area at or beyond the SITE B0UNDARY access to which is not controlled by the licensee for purposes of protection of
-individuals from exposure to radiation and radioactive materials or, any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional and/or recreational purposes.
I l-6 Amendment No EE, l
,=.
POWER DISTRIBUTION LIMITS 3.25.3 DUADRANT POWER TILT - Ty LIMITING CONDITION FOR OPERATION References-(1)
FSAR, Section 7.4.2,2 (2)
FSAR, Section 7,6.2.4 (Next page is 3-134) l 3-113 Amendment No_EE, Jff,
(.
I
~
f l
l TABLE 4.1.3 l
l Minimum Frequencies for Checks, Calibrations ard Testing of Miscellaneous instrumentation and Controls (Cont'd)
Surveil 1ance Channet Descripticn Function Fre pency Surveittance Method I
Comerison of both channel count rate indications when in l
1.
Source Range Neutron
- a. Check S
a.
- service, l
Monitors
- b. Test P
b.
Internal test signals.
Channel aliget through measurecent/ adjustment of internal
- c. Calibrate R
c.
l test points.
l Corparison of output data with secondary RP1S.
2.
Primary Rod Position
- a. Check a.
l Indication System
- b. Check M
b.
Check of power dependent insertion limits monitoring system.
Physically sessured rod drive position used to verify system I
- c. Calibrate R
c.
accuracy. Check rod position interlocks.
]
I l
Comparison of output data with primary RPIS.
3.
Secondary Rod Position
- a. Check S
a.
I Indication System
- b. Check M
b.
Same as 2(b) above.
Same as 2(c) above, including out-of-sequence alarm function.
- c. Calibrate R
c.
f l
l Normal readings observed and internal test signals l
4.
Area Monitors
- a. Check D
a.
used to verify instrument operation.
f
- b. Calibrate 2
b.
Exposure to known exter<el radiation source.
Detector exposed te remote operated radiation check swrce l
- c. Test M
c.
l or integrat electronic check source.
5.
Emergency Plan Radiatico
- a. Calibrate A
a.
Exposure to known radiation source.
Instruments
- b. Test M
b.
Battery check.
6.
(Deleted)
Conparison of two wide and two narrow range independent 7.
Pressurizer Level
- a. Check S
a.
- b. Calibrate R
tevet readings.
Instruments b.
Known dif f erential pressure applied to sensor.
Signal to meter relay adjusted with test device.
- c. Test M
c.
4-10 Amendment No. 3Q', 37/, Vy, SV,1/%/, IJ /, JJ,
+
-4.10 REACTIVITY ANOMALIES Apolicability Applies to potential reactivity anomalies.
Ob_iective To require _ evaluation of reactivity anomalies within the reactor.
Specifications.
Following a. normalization of the computed boron concentration as a function of burnup, the actual-boron concentration of the primary coolant shall be periodically compared with the predicted value.
If the difference between the observed and predicted steady-state concentrations reaches the equivalent of 1% in reactivity, the Atomic Energy Commission shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and an evaluation as to the cause of the discrepancy shall be made and reported to the Atomic Energy Commission within 30 days.
Basis To eliminate possible errors in the calculations of the initial reactivity of-the core and the reactivity depletion rate, the predicted relation between_ fuel burnup and the boron concentration, necessary to maintain adequate control characteristics, must be adjusted (normalized) to accurately reflect actual core conditions.
When rated power is-reached initially,_ and with the control rod groups.in the desired positions,.the boron concentration is measureo and the predicted curve is adjusted to this point..As power
~
operation proceeds, the measured boron concentration is compared with the predicted concentration and the slope of the' curve relating
'burnup and reactivity is compared with that predicted.
This process L
of normalization shall. be completed after about 10% of the total core l:
burnup.
Thereafter, actual boron concentration can be compared with prediction and the reactivity-status of the core: can be continuously _
evaluated.
Any reactivity anomaly greater than 1% would be i
unexpected, and its occurrence'would be thoroughly investigated and l
evaluated.
The methods employed in calculatino the reactivity of the l
core vs burnup and the reactivity worth of boru vs burnup are given in the.FSAR.
The value of 1% _is considered a safe limit since a shutdown margin of at least 2% with the most reactive rod in the fully withdrawn position is.always maintained.'"
References (1) FSAR, Section 3.3.2 (Next page-is 4-60) 4-46 l
Amendment No.
l ADMINISTRATIVE CONTROLS 6.5.3.4 AUTHORITY-The Plant Safety and Licensing staff shall determine those issues significant to nuclear safety which require review by the Plant Review Committee from items considered under Specification 6.5.3.3.a through d.
For those items not referred to PRC, Plant Safety and Licensing shall recommend in-writing to plant management approval or disapproval of items considered under 6.5.3.3.
6.5.3.5 -RECORDS Reports of Plant Safety and Licensing activities pursuant to Specification 6.5.3.3 shall be submitted monthly to PRC, 6.6 (Deleted) 6.7' SAFETY LIMIT VIOLATION 6.7.1 The following actions-shall be taken in the event a safety limit is violated:
a.
The reactor shall be shut down immediately and not restarted until the Commission authorizes resumption of operation (10.CFR50.36(c)(1)(i)(A)).
b.
The safety limit violation shall be reported within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to the Commission in accordance with 10 CFR 50.36, as well as to the Vice President - Nuclear Operations and to the NPAD.
c.
A report shall be prepared in accordance with 10 CFR 50.36 and 6.9 of this specification.
(The safet report shall be reviewed by the-PRC.) y limit violation and the d.
The report shall be submitted within 14 days to the Commission (in accordance with the requirements of 10 CFR 50.36 Vice President - Nuclesr Operations and to the NPAD.), to the 6.8 PROCEDVRES AND PROGRAMS 6.8.1
- Written procedures shall be established, implemented and maintained covering the activitier, referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33 Quality Assurance Program Requirements, as endorsed by CPC-2A QAPD.
b.
Refueling operations.
c.
Surveillance and test activities of safety-related equipment.
6-10 Amendment No. J7, 7E, Jf), J27, JfE,
4 4
ADMINISTRATIVE CONTROLS d.
.i' ?
curity Plan implementation.
e.
Site Emergency Plan implementation, f.
Site Fire Protection Program implementation.
6'8.2
- Procedures and changes shall be approved prior to implementation by the appropriate
- senior department manager predesignated by tte Plant General Manager subject to the reviews per Specifications 6.5.1.6 and 6.5.3.
6.8.3
- Temporary changes to procedures of Specification 6.8.1 above may be made provided:
a.
The intent of the original procedure-is not altered.
b.
The change is approved by two members (or designated alternates) of the PRC, at least one of whom holds a Senior Reactor Operator
-License.
.c.
The change is documented, subsequently reviewed by Plant Safety and Licensing within 30 days of issuance and approved by the appropriate
- senior department manager predesignated by the Plant General Manager.
-6.8.4
- The following programs shall be established, implemented, and maintained:
a.
Radioactive Effluent Controls Proaram A program shall be provided conforming with 10 50.36a for the-control of radioactive effluents and for maintaining the doses to MEMBERS Of THE PUBLIC from radioactive effluents as low as
' reasonably achievable The program (1)- shall be contained in the shall be imblemented by operating 3rocedures, and (3)
ODCM (2)lude remedial actions to be taken wienever the program shall inc limits are exceeded. The program shall include the following elements:
- 1) Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,
-
- The determination of the appropriate senior department manager is based on the activities addressed by the specific procedure arid will be predesignated in writing by the Plant General Manager.
6-11 Amendment No. J/, 7E, Jp), JJ7
1 ADMINISTRATIVE CONTROLS 6.8.4a Radioactive Effluent Controls Proaram (Continued) 2)
Limitations on the concentrations of radioactive material released in liquid ef fluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table 11, Column 2.
3)
Monitoring, sampling, ar analysis of radioactive liquid and gaseous effluents i iccordance with 10 CFR 20.106 and with the methodology c. parameters in the ODCM, 4)
Limitation on the annual and quarterly doses er dose commitment to a MEMBER OF THE PUBL'C from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5)
Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE B0UNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table 11, Column 1.
6)
Limitations on the annual and quarterly air doses resulting from noble gaseous released in gaseous effluents from each unit to areas beyond the SITE B0UNDARY conforming to Appendix 1 to 10 CFR Part 50, 7)
Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133 tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas bcyond the SITE B0UNDARY conforming to Appendix I to 10 CFR Part 50, 8)
Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190, b.
Radiolonical Environmental Monitorina Prooram A program shall be provided to monitor the radiation and radionuclides in the envirora of the plant.
The program shall provide (1) representative reasurements of radioactivity in the highest potential exposure pathways, and (2) verifications of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1 be containedintheCDCM,(21conformtotheguidanceof.}4ppendix 1 to 10 CFR Part 50, and (3) ircluding b e following:
6-12 Amendment No.
1 6DMINISTRATIVE CONTROLS i
6.8.4b Radioloaical Environmental Monitorina Proaram (Continued) 1)
Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in.the ODCM.
2)
A Land Use Census to ensure that changes in the use of areas at and beyond the SITE B0UNDARY are identified and that modifications to the-monitoring program are made if required by the results of this census, and 3)-
Participation in a Interlaboratory Comparison Program to ensure that independent checks on the. precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
I l
l 6-13 Amendment No.
ADMINISTRATIVE-CONTROLS 6.9 Reportina Reauirements Reports and other written communications shall be submitted to the NRC in accordance with the requirements of 10CFR50.4.
J 6.9.1 Routine Reports Start-Vo Report - A summary report of plant start-u escalation testing shall be submitted following (1)p and power a.
receipt of planned increase in pow (2) amendment to the license involving a an operating license, er level, has a different desi n or has been(3) installation of fuel that manufactured by a different fuel supplier and, ( ) modifications that may have significantly altere the nuclear, thermal or hydraulic performance of the plant.
The report shall address each of the required tests and shall, in general, include a description of the measured values of the operating conditions or characteristics obtained during the test program and a compe.rison of these values with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
Start-up reports shall be submitted within (1) 90 days following completion of the start-up test programfollowingresumptionorcom ower operation or, (3) 9 months following initial criticality, whichever is earliest.
If the Start-Up Report does not cover all three events (i.e., initial criticality, completion of start-up test program and resumption or commencement of co.nmercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
b.
Annual Report - An annual report covering occupational exposure during-the current calendar year to supplement requirements of 10 CFR 20.407 should be submitted prior to March 1 of each year.
This annual report shall include:
A tabulation on an annual basis of the number of station, utility-and other personnel (including contractors) receiving exposures greater than 100 mrem / year and their associated man Rem exposure according to work and job functions, eg, reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste 6-14 l
AIncorporated 10/21/87 Amendment No. M,
per 51 FR 40303
=-
+
kDMINISTRATIVECONTROLS 6.9.lb Reoortina Reouirements (Continued) processing and refueling.
The dose
- assignment to various duty functions may oe estimates based on pocket dosimeter, TLD or film badge measurements.
Small exposures totaling less tien 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
c.
Monthly Operatina Repor_t. - Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the NRC to arrive no-later than the fifteenth of each month following the calendar month covered by the report.
A 6.9.2 Reportable Events The Commission shall be notified of Reportable Events and a repnrt submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50.
(Next page is 6-18) l 6-15 l
l -
JIncorporated 10/21/87 Amendment No JE, M, EE, l
per 51 FR 40303 j
6.9.3 OLhgr Reportina R_qquirements 6.9.3.1 Routine Reports A.
Radioactive Effluent Release Report The Radioactive Effluent Release Report shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.
The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
B.
Annual Radiological Environmental Operatina Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.
The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.
The material provided shall be consistent with tha objectives outlined in (1) the 00C and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix 1 to 10 CFR Pcrt 50.
6.9.3.2 Nonroutine Reports A report shall be submitted in the event that (a) the Radiological Environmental Monitoring Programs are not substantially conducted as described in the ODCM or (b) an unusual or important event l
occurs from plant operation that causes a significant environmental impact or affects a potential environmental impact.
Reports shall be submitted within 30 days.
(Next page is 6-26) 6-18 Amendment No. /E,EE,JpE,
ADMINISTRATIVE CONTROLS
- k. - Records of secondary water sampling and quality **
1.
Records of the service lives of all hydraulic and mechanical snubbers covered by Specification 3.20.
This shall-include the date at which the service life commences and associated installation and maintenance records.
m.
Records,of training and qualifications for members of the plant staff.
n.
Record:; of reactor tests and experiments.**
o.
Records if reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR, Part 20, and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12-HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by Paragraph 20.203(c)(2) or 10 CFP 20, each high radiation area in which the intensity of radiation is greater than 100,re,/hr but less than 1000 mrem /hr shall be barricaded and conspicoulsly posted as a high radiation area and entrance thereto shall-be controlled by requiring issuance of a Radiation Work Permit.' Any individual or group of individuals permitted ta enter such areas shall be provided with or accorpanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate ir the area, b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset in_tegrated dose is received.
Entry into such areas with this monitoring device may'be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.
- Health Physics personnel or personnel escorted by Health Physics personnel l
shall-be _ exempt fram the RWP 1ssuance requirement during the performance of their assigned radiation protection duties provided they comply with approved I
radiation protection procedures for entry into high radiation areas.
- Effective with the issuance of Amendment No.108.
6-28 L
Amendment No. JE,fE,ES,JpE, l
l
6.18 O!_E. SITE DOSE CALCVLAT10" MANUAL (00M 1 Changes to ODCH:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.20.
This documentation shall contain:
1)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)
A determination that the change will maintain the level of radioactive effluent cont.ol required by 10 CFR 20.106, 4 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability off effluent,- dose, or setpoint calculations, b.
Shall become effective after the review and acceptance by the PRC and the approval of the Plant General Manager, c.
Shall be submitted to the Commission in the form of a compete, legible copy of the entire ODCM asa a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changad, and shall indicate the date (e.g.,
month / year) the change was implemented.
6.19 PROCESS CONTROL PROGRAM (PCP)
Changes to the PCP a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.20.
This documentation shall contain:
1)
Sufficient'information to support the change together with the appropriate analyses or evaluation justifying the change (s) and 2)
A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
b.
Shall become effective after review and acceptance by the PRC ani approval of the Plant General Manager.
6-35 Amendment Nm E8, l
._ ~