ML20128F690
| ML20128F690 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 12/18/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128F694 | List: |
| References | |
| GL-89-01, GL-89-1, NUDOCS 9302110508 | |
| Download: ML20128F690 (22) | |
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LON30MERS POWER COMPANY-DOCKET NO. 50-255 PALISADES PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 154 License No. DPR-20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated October 13, 1989 and August 27, 1992, complies with the standards and requirements of the Atomic Enargy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (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 commor.
defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51-of the Commi sion's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to the license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-20 is hereby amended to read as follows:
9302110508 921218 I
PDR ADOCK 05000255 p
leshni. cal Specifications The Technical Specifications contained in Appendices A and B, as revise: through Amendment No.154, are hereby. incorporated in the license.
The licensee shall operate-the facility-in accordance with the Technical Specifications.
3.
This license amendment is effective as of January 1,1993.
FOR THE NUCLEAR REGULATORY COMMISSION Ledyard B. Maish, Director Project Directorate 111-1 Division of Reactor Projects lil/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 18, 1992
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ATTACHMENT TO LICENSE AMENDMENT NO.15a..
FACILITY OPERATING LICENSE NO.-DPR-2Q DOCKET NO. 50-255-Revise Appendix A Technical S)ecifications by removing the pages' identified below and inserting the attacled pages. The revised pages are_ identified by the amendment number and contain marginal lines indicating the areas of-
- change, REMOVE INSERT 1
i it 11 iii lii iv iv v
v vi vii 1-6 1-6 3-113 3-113 3-114 3-115
--- 116 3-117 3-118 3-119 3-120 3-121 3-122 3-123 3-124 3-125 3-126 3-127 3-128 3-129 3-130 3-131 3-132 3-133 4-10 4-10 4-46 4-46 4-47 4-48 4-49 4-50 4-51 4-52 4-53 4-54 4-55
' REMOVE INSERT 4-56 s
4-57 4-58 4-59 4-59a 4-90 4-91 4-92 4-93 4-94 4-95 4-96 4-97 4-98 6-10a 6-11 6-11 6-12 6-12 6-13 6-13 S-14 6-14' 6-15 6-15 6 ---
6-19 6-20 6-21 6-22 6-23 6-24 6-25 6-25b 6-25c 6-25d-6-26 6-26 6 6-28 6-35 6-35 6-36 6-36
.. - =. -.
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PALISADES PLANT TECHNICAL SPECIFICATIONS-TABLE OF CONTENTS l-SECTION DESCRIPTION PAGE NO 1.0 DEFINITIONS 1-1 1.1 REACTOR OPERATING CONDITIONS 1-1 1.2 PROTECTIVE SYSTEMS 1-3 1.3 INSTRUMENTATION SURVE!LLANCE l3 1.4 MISCELLANEOUS DEFINIT 10NT l-4 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2-1 l
2.1 SAFETY LIMITS - REACTOR CORE 2-1 2.2 SAFETY LIMITS - PRIMARY COOLANT SYSTEM PRESSURE 23 2.3 LIMITING SAFETY SYSTEM SETTINGS - RPS 2-4 Table 2.3.1 Reactor Protective System Trip Setting Limits 2-5 B2.1 Basis - Reactor Core Safety Limit 82-1.
B2.2 Basis - Primary Coolant System Safety Limit 82 2 B2.3 Basis - Limiting Safety System Settings B2-3 3.0 LIMITING CONDITIONS FOR OPEPATIOR 31 3.0 APPLICABILITY 3-1 3.1 PRIMARY COOLANT SYSTEM 3 lb 3.1.1 Operable Components 3 lb Figure 3-0 Reactor Inlet Temperature vs Operating Pressure 3-3a 3.1.2 Heatup and Cooldown Rates 3-4 Figure 3-1 Pressure - Temperature Limits for Heatup 39 Figure 3-2 Pressure - Temperature Limits for Cooldown 3 10 Figure 3-3 Pressure - Temperature Limits for Hydro 3 11 l
3.1.3 Minimum Conditions for Criticality 3 12 3.1.4 Maximum Primary Coolant Radioactivity 3 17 3.1.5 Primary Coolant System Leakage Limits 3 20 3.1.6 Maximum PCS 0xygen and Halo en Concentration 23 1
3.1.7 Primary and Secondary Safet Valves 3 25 3.1.8 Overpressure Protection Sys ems 3 25a-3.2 CHEMICAL AND VOLUME CONTROL SYSTEM-3-26 3.3 EMERGENCY CORE COOLING SYSTEM 3 29 3.4 CONTAINMENT COOLING 3 34 3.5 STEAM AND FEEDWATER SYSTEMS 3 38 3.6 CONTAINMENT SYSTEM 3-40 Table 3.6.1 Containment Penetrations and Valves 3-40b 3.7 ELECTRICAL SYSTEMS 3-41 3.8 REFUELING OPERATIONS 3-46 3.9 Deleted 3-50 l
1 Amendment No.31, SI, 57, 85, 108, !!8, 126 150, 154
=
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PALISADES. PLANT TECHNICAL SPECIFICATIONS
- i
. TABLE OF CONTENTS.
t SECTION DESCRIPTION PAGE N0 3.C LIMITING CONDITIONS FOR OPERATION (continued)
-31 3.10 CONTROL R00 AND POWER DISTRIBUTION LIMITS
-3 58 4
3.10.1:
Shutdown Margin Requirements-3 58 3.10.2 Deleted 3 59 ~--
3.10.3 Part Length Control Rods-
-3 59 i
3.10.4 Misaltoned er Inoperable Rod 3-60 1
3.10.5 Regulating @ oup Insertion Limits
-3 60 3.10.6 Shutdown Rod Limits 3-61
- i 3.10.7 Low Power Physics Testina 3-61 J
3.10.8 Center Control Rod Misalignment 3-61 Figure 3-6
- Control Rod Insertion Limits-3 3.11 POWER DISTRIBUTION-INSTRUMENTATION 3-65 l
3.11.1 Incore Detectors
- 3-65.
3.11.2 Excore Power Distribution' Monitoring System 3-66a 1
Figure 3.11-1 Axial Variation Bounding Condition 3 66d 3.12 MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY 3-67=
3.13 Deleted 3 69' 3.14 CONTROL ROOM VENTILATION 3 - 3.15 RFACTOR PRIMARY SHIELD COOLING SYSTEM 3-70a-ll
-?
3.16 ESF SYSTEM INITIATION-INSTRUMENTATION: SETTINGS-13-71 Tatsle 3.16.1:
ESF-System Initiation Instrument Setting Limits
=3 75-3,17 INSTRUMENT /.T!ON'AND CONTROL SYSTEMS-76:
f Table 3.17.1.
Instrument-Re utrements for RPS
-3 78; 1
Table.3.17.2 Instrument Re utrements for ESF Systems -
3-79 Table 3.17.3.
Instrument to ditions for-Isolation-Functions 3-80 Table 3.17.4' Instrument Requirements for= Other Safety Features 3-81~
t 3.18 Deleted- - 82-3.19 IODINE REMOVAL SYSTEM'.-
3-84<
3.20 SHOCK SUPPRESSORS (Snubbers).
3-88=
3,21 MOVEMENT HEAVY LOADS-3-92 3.22-Deleted '
13-96:-
3.23
-POWER DISTRIBUTION LIMITS13-103; 3.23.1 Linear Heat ~ Rate-Table 3.23.1 Linear Heat = Rate' Limits.
L3-103=
3-107:
Table 3.23.2 Radial Peaking Factor Limits.
.-. 107 Table 3.23 3 Power Distribution Measurement Uncertainty 3-107-.
Fi 3.23.2 gure 3.23 - Allowable LHR'vs Peak Power Locatien 3-1081 Radial Peaking Factors 3 111 3.23.3 Quadrant Power Tilt.Tg:
3 112-3.24 Deleted-
'3-1141 e
' 3,25.
ALTERNATE SHUTDOWN SYSTEM:
3-134 Table 3.25.1 Alternate Shutdown Minimum Equipment:
3-135.
- i 11 Amendment No. 27.-53 68, 81,-85, 108, 110L
!!!, I!8,W A1541
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PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION DESCRIPTION PAGE NO 4.0 SURVEILLANCE REOUIREMENTS 4-1 4.1 INSTRUMENTATION AND CONTROL 41 4.1.1 Overpressure Protection Systems 4-1 Table 4.1.1 Frequencies for Testing of RPS Instrumentation 4-3 Table 4.1.2 Frequencies for Testing of EFS Instrumentation 4-6 Table 4.1.3 Frequencies for Testing of Misc. Instrumentation 4-10 4.2 EQUIPMENT AND SAMPLING TESTS 4-13 Table 4.2.1 Minimum Frequencies for Sam ling Tests 4-14 Table 4.2.2 Minimum Frequencies for Equ pment Tests 4 15 Table 4.2.3 HEPA Filter and Charcoal Ad orber Systems 4-15e 4.3 SYSTEMS SURVEILLANCE 4-16 Table 4.3.1 Primary Coolant System Pressure Isolation Yalves 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 S stems 4 28a 4.5.4 Surveillance for Prestressin System 4-29 4.5.5 End Anchorage Concrete Surve 11ance 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 System 4-39 4.6.2 Containment Spray System 4-39 4.6.3 Pumps 4-39 4.6.4 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 FEE 0 VATER SYSTEM 4-45 4.10 REACTIVITY ANOMALIES 4-46 4.11 Deleted 4-46 4.12 AUGMENTED ISI PROGRAM FOR HIGH ENERGY LINES 4 60 4.13 Deleted 4-65 4.14 AUGMENTED ISI PROGRAM FOR STEAM GENERATORS 4-66 4.15 PRIMARY SYSTEM FLOW MEASUREMENT 4-70 i
4.16 ISI PROGRAM FOR SHOCK SUPPRESSORS (Snubbers) 4-71 l
4.17 Deleted 4-75 111 Amendment No. 37, 48,
-63, 67, 68, 85, 108, 122,252.154 l
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3 PALISADr$ PLANT TECHNICAL SPECIFICATIONS
--TABLE OF CONTENTS-SECTION DESCRIPTION PAGE NO
~
4.0-SURVEILLANCERE0VIREMENTS5(Continued):
4.' 18 '
POWER DISTRIBUTION !NSTRUMENTATION-
-4 81 4.18.1 Incore Detectors.
4 81 4.10.2-Excore Monitoring-System
-14 82-4.19 P0WER DISTRIBUTION LIMITS.
4 83:
4.19.1 Linear Heat-Rate 4 83.
4.19.2 Radial Peaking Factors
=4 84
'4.20 MODERATORTENPERATUREC0EFFECIENT.(MTC) 4 85, 4.21-ALTERNATE-SHUTDOWN SYSTEM 4 Table 4.21.1 Alternate Shutdown System Surveillance 4 87 5.0 DESIGN FEATURES 5-li 5.1 SITE
'5-1, 5.2
.CONTAINHENT DESIGN FEATURES-51-5.2.1 Containment Structures 51-5.2.2 Penetrations- -
!5-21 5.2.3 Containment Structure-Cooling Systems-
- 52
- 5.3
- NUCLEARSTEAMSUPPLYSYSTEM(NSS$)!
52-5.3.1 Primary Coolant System 5 2-5.3.2 Reactor" Core and Control 3 5.3.3 Emergency Core Cooling System" 53 5.4 FUEL STORAGE' 5-4
- 5. 4.1 '.
New Fuel Storage 4:
5.4.2 -
Spent Fuel: Storage 5-4a-Figure 5-1
'. site Environment.TLD-Stations F5 5 s
- 6.0 ADMINISTRATIVECONTROLS-6-1
. ~ 6.1.
RESPONSIBILITY: 1 6.21 ORGANIZATION 1-6.2.1 Offsite-and Ossite Organizations-
.6-1 6.2.2 sPlant Staff 6;2-
~
,6. 3
- PLANT-STAFF QUALIFICATIONSI
- 6 Table 5.2. Minimum Shift Crew Composition
' 6-4 7--
6.4 TRAINING' J-6-5:
-6.5-REVIEW AND AUDIT-6-5' 6.5.11 Plant Review Connittee
- 6 6.5.2' Nuclear Performance Assesment Department-6-6a :-
- 6.5.3 -
P1 ant ~ Safety and Licensing:
6-9 iv Amendment Na' 37, 48.
63,- 67. 68,285, 108.:
128,-!34 154:
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4 PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION DESCRIPTION PAGE NO 6.0 ADMINISTRATIVE CONTROLS (Continued) 6.6 Deleted 6-10 6.7 SAFETY LIMIT VIOLATION 6-10 6.8 PROCEDURES AND PROGRAKS 6-11 6.9 REPORTING REQUIREMENTS 6-14 6.9.1 Routine Reports 6 14 6.9.1.a Start up Report 6-14 6.9.1.b Annual Report 6.9.1.c Monthly Operating Report 6-14 6.9.1.d Radioactive Effluent Releases Report I!s i
is 6.9.1.e Radiological Environmental Operating Report 6-15 6.9.2 Reportable Events 6 15 6.9.3 Nonroutine Reports 6 15 6.9.4 Special Reports 6 6.10 RECORD RETENTION 6-26 6.11 RADIATION PROTECTION PROGRAM 6-28 6.12 HIGH RADIATION AREA 6-28 6.13 Deleted 6-33 6.14 Deleted 6-33 6.15 SYSTEMS INTEGRITY 6-33 6.16 IODINE MONITORING 6-33 6.17 POST ACCIDENT SAMPLING 6-34 6.18 0FFSITE DOSE CALCULATION MANUAL 6-35 6.19 PROCE35 CONTROL PROGRAM 6-35 6.20 Deleted 6-36 6.21 SEALED SOURCE CONTAMINATION 6-37 6.22 SECONDARY WATER CHEMISTRY 6-38 v
Amendment No. 37, 48, 63, 67. 68, 85, 108 IIB, 122, 154 t.
ev-1.4 HISCELLANE005 DEFINITIONS (Contd)
I MEMBERfS) 0F THE PUBllC MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the att11ty, its contractors, or its vendors.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
OFFSITE DOSE CALCULATION MANUAL (00CMi The OFFSITE DOSE CALCULATION MANUAL shall contain the current methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm-and trip set points, and in the conduct of the Radiological Environmental Monitoring Program.
The 00CM shall also contain the (1) Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Specification 6.8.4 and (2) descriptions of the information to be included in the Radiological Environmental Operating Report and the Radioactive Effluent Release Report required by Specification 6.9.3.
The PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR 20, 10 CFR 71 Federal and State regulations, and other requirements governing l
the disposal of the radioactive waste.
11TE BOVNDARY The SITE BOUNDARY shall be that line beyond which the land is neither owned nor otherwise controlled by the licensee.
UNRESTRICTED AREA An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY 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 cuarters or for industrial, comercial, institutional, or recreational l
purposes.
I 1-6 Amendment No EJ,154 i
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'R@[R DISTRIBUTION LIMITS:
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13.23.3 M AQRANT POWER TILT - T_
LIMITING CONDITION FOR OPERATION References (1)
FSAR,'.'Section 7.4.2.2-(2)
FSAk, Section 7.6.2.4-i 1
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-(Nextpageis3-134)
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4-
'3-113.
- Amendment No ##, J//,.154T
taste 4.1.3 MinleMe Fregeancies for Checks, Calibratione eruf Testing of Miscellenecus Instrumentetlen and Centrste (Cent'd) i surveliience Chemei DeserfetIon Ftrvt f m Fre e survefiIence Method j
1.
Source Range Routron
- s. Check S
e.
Cosperfecn of both chemet comt rate Indicetlano edwn In
' l Monitore service.
- b. Test P
b.
Internet test efenste.
- c. Cetibrate R
c.
Charrat stignment through museurosent/edjustment of interret test pointe.
2.
Primary Red Positten
- e. Check S
e.
Ceeperleen of output dets with escendary RPts.
~
Indication Systes
- b. Check N
b.
Check of power dependent Insertion tielte senttorfre eyetas.
- c. Cellbrate R
c.
Phyelcetty eneeured red drive positten used te verify system
(
accuracy. Check rod peeltlen interlocks.
3.
Secerulary Rod Positten
- e. Check S
e.
Ceeperleen of out;ma dote with priomry Spit.
Indicetten System
- b. Check n
b.
Some se 2(b) otees.
- c. Cellbrate a
c.
same es 2(c) stove, inctieffne eut-of-seepsence etern ftretten.
S' 4.
Areestenitors I
- a. Check 8
e.
sormet readings observed eruf intemet test alsnote
~
used te verify Inetr1usent aperetlen.
- b. Collbrete E
b.
Exposure to knam externet redtetten source.
p,
- c. Test M
c.
Detector esposed to reesta operated redtatten check eeurce
[g or Inteerst electronic check source.
1-5.
Emergency Plan andf atten
- e. Cellbrate A
e.
Exposure te knam redletten source, j
Instrumente
- b. Test N
b.
Bettery check.
{
I 6.
(Deleted)
(
T.
Pressurizer Levet
- a. Check J
a.
Ceeperleers of two ufde eruf two narrow rence Independent l
Instrueante
- b. Collbrete R
tsvet readings.
f b.
Enaun dif ferential, pressure opptled to sensor.
}
- c. Test M
c.
$1snei to settr retty adjusted with test device.
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4-10 Amendment No. W W, :Hy, W, UN, UN, JM,154
4.10 MKIIVITY ANOPALIES Acolicability Applies to potential reactivity anomalies.
Obiective To require evaluation of reactivity anomalies within the reactor.
'$oecifications Following a normalization of the compute'd 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 predictee steady-state concentrations reaches the equivalent of 1% in reactivity, the Atomic Energy Comission 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 s
Atomic Energy Comission within 30 days.
E1111 To eliminate possible errors in the calculations of the initial reactivity of the core and the reactivity de)1etion rate, the predicted relation between fuel burnup and t1e boron concentration, necessary to maintain adequate control characteristics, must be adjusted (normalized) to accurately reflect actual core conditions.
When rated sower is reached initially, and with the control rod groups in tie desired positions, the boroa concentration is measured 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 of normalization shall be completed after about 10% of the total core 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 unexpected, and its occurrence would be thoroughly investigated and evaluated. The methods employed in calculating the reactivity of the core vs burnup and the reactivity worth of boron 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 react position is always maintained.',1,ve rod in the fully withdrawn References (1) FSAR, Section 3.3.2 4.11 (Deleted)
(Nextpageis4-60) 4-46 Amendment No. 154
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4 ADMINISTRAtlVE CONTR0ls 6.8 PROCEDURES AND PROGRAMS l
6.8.1 Written procedures shall be estabitshed, implemented and maintained covering the activities referent,ed belows a.
The appitcable procedures recomended in Appendix "A" of Regulatory Guide 1.33 Quality Assuranco Program Requirements, as endorsed by CPC 2A, Quality Program Description.
l b.
Rsfueling operations.
c.
Surveillance and test activities of safety related equipment, d.
Site Security 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
- 2enior department manager predestgaated by the Plant General Manager subject to the reviews per Specifications 6.5.1.6 and 6.5.3.
0.a.3 Temporary changes to procedures of Specification 6.8.1 above may be rade provided:
a.
,e intent of the original procedure is not altered, b.
The change is approved by two memb6rs (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.
The determination of the appropriate senior department manager is based on the activities addressed by the specific procedure and will be predesignated in writing by the Plant General Manager.
6-11 l
Amendment No.16,154
--_----- _.... n _.... _., _...
s ADMINISTRATIVE CONTROLS 6.8.4 The following programs shall be established, implemented, and maintained:
a.
Hadioactive Effluent Controls Prooram A program shall be provided conforming with 10 CFR 50.36a for ths control of radioactive effluents and for maintaining the doses to HEMBERS OF THE PUBLIC from radioactive effluents as low as i
reasonably achievable. The program (1) shall be contained in the ODCH (2 shall be implemented by operating )rocedures, and (3) shallinc)luderemedialactionstobetakenwienevertheprogram i
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 ODCH,
- 2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR 20, Appendix B, Table 11, Column 2.
- 3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20,106 and with the methodology and parameters in the ODCH,
- 4) Limitation on the annual and quarterly doses or dose commitment to a HEMBER OF THE FUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR 50,
- 5) Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR 20, Appendix B, Table !!, 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 BOUNDARY conforming to Appendix ! to 10 CFR 50,
- 7) Limitations on the anual and quarterly doses to a HEMBER 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 beycnd the SITE BOUNDARY conforming to Appendix ! to 10 CFR 50,
- 8) Limitations on the annual doce or dose comitment to any HEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR 190.
6-12 Amendment No. 36, 85, 154
.~.
ADMINISTRATIVE CONTROL 5 6.8.4 (continued) b.
Radioloalcal Environmental Monitorina Prooram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the sighest potential exposure pathways, and (2) verifications of the accuracy of the affluent monitortnfi program and modeling of environmental exposure pathways.
"he program shall contained in the 00CM, (ding the following:2) conform to f Appendix ! to 10CFR50,and(3)inclu
- 1) Monitoring, sampilng, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCH.
- 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made-if required by the results of this census, and
- 3) Participation in a Interleboratory 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.
6-13 Amendment No. 36, '154 -
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ADMINISTRATIVE CONTR0l3 6.9 Reoortina_gtquirementi Reports and other written comunications shall be submitted to the NRC in accordance with the requirements of 10 CFR 50.4.
6.9.1 Routine Reports a.
StarSUp Reogn - A sumary report of plant start up and power escalation tes3tng shall be submitted following (1) involving a receipt of an operating license.
planned increase in pow (2) amendment to the license er level has a different desi n or has be,en(3) installation of fuel that manufactured by a different fuel supplier and, ( )the nuclear, therma'or hydraulic modifications that may have significantly altere 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 tbe operating conditions or.
characteristics obtained during the test program and a comp *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 licente conditions based on other comitments shall be included in this report.
Start up reports shall be submitted within (1) 90 days following completion of the start-up test program following resumption or comencement of commercial p(2) 90 days ower operation or, whichever is es(3? 9 months following initial criticality,
- iest.
If the Start Up Report does not cover all three evel.cs (i.e., d resumption or com,encement of initial criticality completion of start up test program an comercial power operation), supplementary reports shall be submitted at least every three months untll all three events have been completed, b.
Annual Reoort An annual. report covering occupational exposure during the current calentar 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 utilityandotherpersonnel(includingcontractors)recelving exposures greater than 100 mrem / year and their associated man Rea exposure accordina to work and job functions, e operations and surveillance, inservice inspection, g, reactor routine maintenance, special maintenance (describe maintenance), waste processing and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD or film badge measurements. Small exposures totaling less than 207, of the individual total dose need not be accounted for.
In the aggrecate received from. at least 807,of the total whole body dose external sources shall be assigned to specific major work functions.
I 6-14 Amendment No. 16, 85, 154 I
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ADMINISTRATIVE CONTROLS 6.9.1 Routine ReDorts (continued) 1120 hlv Operatino Regg.t1 Routine reports of operating t
c.
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.
d.
fltd{gattive Effluent Release Report The Radioactive Effluent Release Report shall be submitted in accordance with 10 CFR 50.36a. The report shall include a sumary of the quantities of radioactive liquid and gaseous 4
effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outilned in the ODCM and PROCESS CONTROL PROGRAM and with 10 CFR 50.36a and Section IV.B.1 of Appe(ndix ! to2) in conformanc 10 CFR 50.
e.
Radiolooical Environmental Doeratino Report The 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 sumaries, 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 the objectives outlined in (1) the 00CM and (2)SectionsIV.B.2,IV.B.3,andIV.CofAppendix!to L0 CFR 50.
6.9.2 Reoortable Events The Comission shall be notified of Reportable Events and a report submitted pursuant to the requirements of 10 CFR 50.73.
6.9.3 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 occurs from plant operation tha)t causes a significant environmental-impact or affects a potential environmental impact. Reports shall be submitted within 30 days.
(Nextpageis626) 6-15 Amendment No 16. W.154
b ADMINISTRATIVE CONTR0lS 6.9 Reoortino Reoutrements (continued) 6.9.4 Soecial Reports 1
4.
Special Reports shall be submitted to the NRC covering the activities identified below pursuant to the requirements of the applicable referenced specifications:
Specification Reporting Area Referente Due i
Prestressing, Anchorage, 4.5.4 90 Days After Liner and Penetration 4.5.5 Completion of Tests the Test *
- A test is considered to he conplete after all associated mechanical, chemical, F 6 Oqts have been completed.
b.
Special reports shall be awe,ed in accordance with 10 CFR 50.4, within the time period spectfled for each report.
6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10 Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated:
G.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 principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
All reportable events as defined in Section 6.9.2.
d.
Records of surveillance activities, inspections and cr ibrations required by these Technical Specifications.
6 26 AmendmentNo.JJ,J/,JJ,Jp),J/J,154
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4 ADMINISTRATIVE CONTROLS k.
Records of secondary water sampling and quality.
l 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 comences and associated installation and maintenance records, Records of training and qualifications for members of the plant s.
staff.
n.
Records 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 20, and shall be i
approved personnelradiationexposure. maintained and adhered to for all operations
- 6. M HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by 10 CFR 20.203(c)(2), each high radiation area in which the I
intensity of rad'ation is greater than 100 mrem /hr but less than 1000 mRein/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be cpntrolled by requiring issuance of a Radiation Work Permit.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose istreceived. Entry into such areas t:ith this monitoring device may be made after the dose rate level in the area has been estabitshed and personnel have been made knowledgeable of them.
- Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties provided they comply with approved radiation protection procedures for entry into high radiation areas.
I 6 28 Amendment No. JJ,/S,#,JpJ,154
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8 ADMINISTRATIVE CONTROLS 6.18 0FFSITE DOSE CALCULATION MANUAt (ODCM)
Changes to 00CMt Shall be documented and records of reviews performed shall be a.
retained as required by Specification 6.10.20.
This documentation shall containt 1)
Sufficient information to support the change tooether with the appro change (s)priate analyses or evaluations justifying the and 2)
A determination that the change will maintain the level of 40 CFR 190,ly impact the a,ccuracy or re 10 CFR 20.106 10 CFR 50.36a and Appendix not adverse affluent, dose, or setpoint calculations.
~
b.
Shall become effective after the review and acceptance by the PRC and the approval of the Plant General Manager.
Shall be submitted to the Comission in the form c.
legible copy of the entire ODCM as a part of or concurren the Radioactive Effluent Releaso 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 change,dclearly indicating the area of the page that was pages change w,as implemented.and shall indicate the date (e.g., month / year 6.19 P_ROCESS CONTROL PROGRAM Changes to the PROCESS CONTR01. PROGRAM:
Shall be documented and records of reviews performed shall be a.
retained as required by Specification 6.10.20. This documentation shall contain:
1)
Sufficient information to support the change together with the ap r priate 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 appitcable regulations, b.
Shall become effective after review and acceptance by the PRC and approval of the Plant General Manager.
6 35 Amendment No g,154
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ADMINISTRATIVE CONTROLS i
6.20 (Deleted) g b
i 6-36 Amendment No M r'154