ML20086K358
| ML20086K358 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/09/1991 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20086K361 | List: |
| References | |
| NUDOCS 9112130063 | |
| Download: ML20086K358 (11) | |
Text
fo INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER UISTRIBUTION LIMITS 3/4.2.1. AXIAL FLUX DIFFERENCE..................................
3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR..........
3/4 2-4 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR..............
3/4 2-8 3/4.2.4 QUADRANT-POWER-TILT RATIO......
3/4 2-12 3/4.2.5 DNB PARAMETERS.......................
3/4 2-15 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION......................
3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION........................
3/4 3-15 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring....................................
3/4 3-41 Movable Incore Detectors..........
3/4 3-46 Seismic Instrumentation.................................
3/4 3-47 Meteorological Instrumentation..........................
3/4 3-50 Remote Shutdown Instrumentation..........................
3/4 3-53 Accident Monitoring Instrumentation......................
3/4 3-56 Explosive Gas Monitoring Instrumentation.................
3/4 3-67 Loose-Part Detection Instrumentation....................
3/4 3-72 SUMMER - UNIT 1 IV Amendment No. 79, 104 9112130063 911209 PDR ADC;CK 05000395 P
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INDEX LIMITING CONDITION 5 FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Liquid Holdup Tanks.....................................
3/4 11 Settling Pond...........................................
3/4 11-2 3/4.11.2 GASE0US EFFLUENTS Explosive Gas Mixture.................................
3/4 11-4 i
Gas Storage Tanks.......................................
3/4 11-5 4
SUMMER - UNIT 1-XI Amendment No. 104
INDEX 4
BASES SECTION PAGE 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS.......................................
B 3/4 11-1 3/4.11.2 GASE0US EFFLUENTS......................................
B 3/411-2 SUMMER - UNIT 1 XVI Amendm3r.t No. 104
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INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY.................................................
6-1 6.2 ORGANIZATION 6.2.1 0FFSITE.
6-1 6.2.2 UNIT STAFF.............
6-1 6.2.3 INDEPENDENT SAFETY'ENGIhEERING GR0VP........................
6-3 6.2.4 ' SHIFT TECHNICAL ADVISOR....................................
6-3 6.3 UNIT STAFF QUALIFICATIONS.....................................
6-3 6.4 TRAINING.....................................................
6-3 5.5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY REVIEW COMMITTEE
. Function....................................................
6-4 Composition.................................................
6-4 Alternates..................................................
6-4 Meeting Frequency...........................................
6-4 Quorumi.....................................................
6-4 Responsibilities............................................
6-4 Authority...................................................
6-5 Records.....................................................
6-6
- 6.5.2 NUCLEAR SAFETY REVIEW COMMITTEE Function.....................................
6-6 Composition.................................................
6-6 Alternates..................................................
6-6 Consultants.................................................
6-6 Meeting Frequency...........................................
6-7 Quorum.........
6-7 I
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'UMMER - UNIT 1.
XVIII Amendment No. 104
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,INDEX ADMINISTRATIVE CONTROLS SECTION PAGE Review....................................
6-7 Audits...................
6-8 Authority...
6-8 Records...............
6-9 6.5.3 TECHNICAL REVIEW AND CONTROL Activities..............................................
6-9 6.6 REPORTABLE EVENT ACTI0N.......................................
6-10 6.7 SAFETY LIMIT VI0LATION.......................................
6-10 6.8 PROCEDURES AND PR0 GRAMS................................
6-11 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS Startup Report..............................
6-13 Annual Report....
6-13 Annual Radiological Environmental Operating Report..........
6-14 Semiannual Radioactive Effluent Release Report..............
6-14 Monthly Operating Report..................
6-16 Core Operati ng _ Limi ts Report............................
6-16 6.9.2 SPECIAL REP 0RTS.............................................
6-17 6.10 RECORD RETENTION............
6-17 6.11 RADIATION PROTECTION PR0 GRAM.................................
6-18 6.12 HIGH RADIATION AREA..........................................
6-18 SlHMER'- UNIT 1 XIX Amendment No. 35,88, 104
6-INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.13 PROCESS CONTROL PROGRAM.....................................
6-19 6.14 0FFSITE DOSE CALCULATION MANUAL............................
6-20 SUMMER - UNIT 1 XX Amendment No. 5,104
4 INSTRUMENTAT,IR LOOSE-PART DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION
~
3.3.3.10 The loose part detection system shall be OPERABLE.
APPLICABILITY:
MODES 1 and 2 ACTION-a.
With one or more loose part detection system channels inoperable for acre than 30 days, prepare and submit a Special Report to the Commis-sion pursuant to Specification 6.9.2 withir the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s)
.to OPERABLE status.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.10 -Each channel of the loose part detection system shall be demonstrated OPERABLE by performance of:
a.
A CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
An ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days, and c.
A CHANNEL CALIBRATION at least once per 18 months.
SUhMER - UNIT 1 3/4 3-72 Amendment No.
RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS LIQUID HOLOUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radicar.tive n.aterial contained in each of the following tanks shall be limited to Ins than or e and dissolved or entrained noble gases. qual to 10 curies, excluding tritium a.
Condensate Storage Tank b.
Outside Temporary Storage Tank APPLICABILITY:
At all times.
ACTION:
a.
ith the quantity of raaioactive mai.crial in any of the above listed
.anks exceeding the above limit, immediately suspend all additions or radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
b.
The provisions of Specificstions 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of th; tank's contents at least once per 7 days wnen radioactive materials-are being added to the tank.
i SUMMER - UNIT 1 3/4 11-1 Amendment No. 104 l
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RADI0 ACTIVE EFFLUENTS 3/4.11.2-GASE0llsEFFLUENE EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.
APPLICABILITY:
At all times.
ACTION:
a.
With the concentration of oxygen in the waste gas holdu) system greater than 2% by volume but less than or equal to 4% ay volume, restore the concentration cf oxygen to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
b.
With the concentration of oxygen in the waste gas holdup system greater than 4% by volume, immediately suspend all additions of
-waste gases to the system and reduce the concentration of oxygen to less than 4% by volume within l' hour and less than or equal to 2%
by volume within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, c.
The provisions of Specifications 3.0.3 and 3.0.a are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.5~ The concent' ration of hydrogen and oxygen in the waste gas holdup system shall-be determined to be within the above limits' by continuously monitoring the waste gases in the waste gas holdup system with the hydrogen g
and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.1 g
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SU41ER - UNIT 1 3/4 11-4 Amendment lio. 104 l
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f).
.'4 3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.3 Not Used-3/4.11.1.4 LIQUID HOLDUP TANKS Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B,_ Table II, Column 2, at_the nearest potable water supply and the nearest surface water supply in an unrestricted area.
3/4 11.1.5 SETTLING PONDS TheLinventory limits of the settling ponds (SP) are based'on limiting the consequences of an uncontrolled release of the pond inventory.
The expression
.in Specification 3.11.1.5 assumes the pond inventory is uniformly mixed, that the pond is located in an uncontrolled area as defined in 10 CFR 20,.and that the concentration limit in Note 1 to Appendix B of 10 CFR 20 applies.
The batch limits of: slurry to the chemical treatment ponds assure thht
- radioactive material in the slurry transferred to the SP are "as low as is reasonably achievable" in accordance with 10 CFR 50.36a.
The expression in 5pecification'4.11.1.5 assures no batch of slurry will be transfured to the
.3P unless the sum of the ratios-of the activity of the radionuclides
.to-their respe:tive concentration limitation is less than the ratio of the 10 CFR 50,-Appendix I,Section II.A, total body level to-the 10.CFR 20, 105(a),
= whole body. dose -limitation, or-that:
- I 3 mrem /yr = 0.006 ~
~ J y 500 mrem /y.r twhere c.-=cadiqactiveslurryconcentrationforradionuclide"j"enteringthe 3
unrestricted area SP, in microcuries/ milliliter C. = 10 CFR 20,de -['j", in microcuries/ milliliter.ndix B, Table II, Column 2, conc Ap J.
radionucli
)
For the design of filter /demineralizers usina yowder resin, the slurry wash l
volune and the weight of resin.used per-. batch is hxed-by the cell surf ace -area and the slurry volume to resin weight ratio is constant-at 100 milliliters / gram of wet,-drained resin with a moisture content of approximately 55 to 60% (oulk-density of about 58 pounds per cubic-feet).
The wet' drained slurry density is SUMMER'- UNIT 1-B 3/4 11-1 Amendment No. 104 m
89-.-u g, y g; egw 47 egg--4-g g
g 4
---Ain p
-9 g
-pem.-
g a
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RADI0 ACTIVE EFFLUENTS BASES 3/4 11.-l.5 SETTLING PONOS (Continued) approximately 1 gr/ml and the absorption characteristic for gamma radiation is essentially that of water.
Thereforc,
- j C)
O' ml/gm) < 0.006, and z g < 'g pCi/am
,1 j
pct /ml Where the terms are defined in Specification 4.11.1.5.
-The batch limits provide assurance that activity input to the SP will be minimized, and a means of identifying radioactive material in the inventory limitation of Specification 3.11.1.5.
3/4.11.2 GASE0US EFFLUENTS
-3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixture. antained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen, Automatic control features are included in the systta a prevent the hydrogen and oxygen concentrations from reaching these flammal'H w limits.
These automatic control features include isolation of the source of hydrogen and/or oxygen to reduce the concentration below the flammability limits. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be cor, trolled in conformance with the requirements of General Design Criterion'60 of Appendix A to 10 CFR Part 50.
3/4.11.2.6 -GAS STORAGE: TANKS Restricting the' quantity of radioactivity contained in each gas storage tank'provides assurance-that in the event of an uncontrolled release of the tank s-contents, the resulting total body exposure to an individual at the l-l-
nearest exclusion area boundary will not exceed 0.5 rem.
This is consistent with Stanoard. Review I=an 15.7.1, " Waste Gas System Failure".
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l SUMMER - UNIT 1 B 3/4 H"2 Amendment No. 104 L