ML20056D700
| ML20056D700 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 08/09/1993 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20056D663 | List: |
| References | |
| NUDOCS 9308170339 | |
| Download: ML20056D700 (13) | |
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-3.1,6 ' LEAKAGE-Apolicability Applies to reactor coolant leakage from the reactor coolant system and the j makeup and purification system.
Ob.iectiva .!
'i To' assure that any reactor coolant leakage does not _ compromise the safe !
operation of the facility. j Specification ,
3.1.6.1 If the total reactor coolant leakage rate exceeds 10 gpm, the reactor j shall be placed in hot shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection. q 3.1.6.2 If unidentified reactor coolant leakage (excluding normal evaporative - .y losses) exceeds one gpm or if any reactor. coolant leakage is L evaluated as unsafe, the reactor shall be placed in hot shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection. ]
3.1.6.3 If primary-to-secondary leakage through the steam generator tubes -
exceeds I gpm total for both steam generators,- the reactor shall be '
placed in cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> of detection. !
3.1.6.4 If any reactor coolant leakage exists through a nonisolable fault in- 1 an RCS strength boundary (such as the. reactor vessel, piping ~, valve ;
body, etc., except the steam generator tubes), the reactor shall be ;
shutdown, and cool-down-to the cold shutdown condition shall' be !
initiated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection. 3 3.1.6.5 'If reactor shutdown is required by Specification 3.1.6.1, 3.1.6.2, 3.1.6.3, or 3.1.6.4, the rate of shutdown and the conditions of. J shutdown shall be determined by the safety evaluation for each case, d 3.1.6.6 Action to evaluate the safety implication of~ reactor coolant leakage j shall' be initiated within four hours of detection.- The nature, .as. l well as the magnitude, of the leak shall be considered in this n evaluation. The safety evaluation shall assure that the . exposure of !
offsite personnel to radiation is within the limits.of Specification .l 3.22.2.1. 1 3.1.6.7 If reactor shutdown is required per Specification 3.1.6.1, 3.1.6.2, 3.1.6.3 or 3.1.6.4, the reactor shall not' be restarted until the leak .
is repaired or until~ the problem is otherwise corrected. !
3.1.6.8 When the reactor is critical and above 2 percent power,' two reactor
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coolant leak detection systems of different operating' principles shall be in operation for the Reactor Building.with one of the two- !
systems sensitive.to radioactivity. The systems sensitive to ,
radioactivity may be out-of-service for no more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> j provided a sample.is taken of the Reactor Building. atmosphere every !
eight hours and analyzed for radioactivity and two'other maans are .l available to detect leakage. j a
3-12 l j
Amendment No. J7,-129 1
-(12-22-78) !
9308170339 930909 .
q PDR -ADOCK 05000289 .
P PDR. _
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Bases (Continuedi When reactor _ coolant leakage occurs to the intermediate cooling closed cooling water system, the leakage is indicated by both the intermediate cooling water monitor (RM-L9) and the intermediate cooling closed cooling water surge tank liquid level indicator, both of which alarm in the control room. Reactor coolant leakage to this receptor ultimately could result in radioactive gas leaking to the environment via the unit's auxiliary and fuel handling building vent by way of the atmospheric vent on the surge tank.
When reactor coolant leakage occurs to either of the decay heat closed cooling water systems, the leakage is indicated by the affected system's radiation monitor (RM-L2 or RM-L3 for system A and B, respectively) and surge tank liquid level indicator, all four of which alarm in the control room.
Reactor coolant leakage to this receptor ultimately could result in radioactive gas leaking to the environment via the unit's auxiliary and fuel handling building vent by way of the atmospheric vent on the surge tank of the affected system.
Assuming the existence of the maximum allowable activity in the reactor coolant, a reactor coolant leakage rate of less than one gpm unidentified leakage within the reactor or auxiliary building or any of the closed cooling water systems indicated above, is a conservative limit on what is allowable before the limits of Specification 3.22.2.1 would be exceeded. Thisisshownl as follows: if the specific activity of the reactor coolant is 130/i uCi/ml and the gaseous portion of it (as identified by UFSAR Table 11.1-2) is discharged to the environment via the unit's auxiliary and fuel handling building vent, the yearly whole body dose resulting from this activity at the site boundary, using an annual average X/Q = 4.5 x 10-' sec/m', is 0.34 rem.
This may be compared with the gaseous effluent dose rate specified in T.S.
3.22.2.1 of 0.5 rem / year whole body dose.
When the reactor coolant leaks to the secondary sides of either steam generator, all the gaseous components and a very small fraction of the ionic components are carried by the steam to the main condenser. The gaseous components exit the main condenser via the unit's vacuum pump which discharges to the condenser vent past the condenser off-gas monitor. The condenser off-gas monitor will detect any radiation, above background, within the condenser vent.
However, buildup of radioactive solids in the secondary side of a steam generator and the presence of radioactive ions in the condensate can be tolerated to only a small degree. Therefore, the appearance of activity _ in the condenser off-gas, or any other possible indications of primary to secondary leakage such as water inventories, condensate demineralizer activity, etc., shall be considered positive indication of primary to secondary leakage and steps shall be taken to determine the source and quantity of the leakage.
3-14 Amendment No. JJ, EE, 77, J79, 149
3.21 RADI0 ACTIVE EFFLUENT INSTRUMENTATION 3.21.1 RADI0 ACTIVE LIOUID EFFLUENT INSTRUMENTATION -
LIMITING CONDITION FOR OPERATION 3.21.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.21-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.22.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (0DCM).
APPLICABILITY: At all times
- ACTION:
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluent monitored by the affected channel or declare the -
channel inoperable.
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown I in Table 3.21-1. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in '
the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner.
- For FT-84, and RM-L6, operability is not required when discharges are positively controlled through the closure of WDL-V257.
- For RM-L12 and associated IWTS/IWFS flow interlocks, operability is not required when discharges are positively '
controlled through the closure of IW-V72, 75 and IW-V280, 281.
- For FT-146, operability is not required when discharges are positively controlled through the closure of WDL-V257, IW-V72, 75 and IW-V280, 281.
- BASES .:
The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid t effluent during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding ten ,
times the effluent concentrations of 10'CFR Part 20. '
t 3-96 Amendment No. 7E, ES, 177, 173 l
q 3.21.2 RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.21.2 The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 3.21-2 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.22.2.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the 0FFSITE DOSE CALCULATION MANUAL (0DCM).
APPLICABILITY: As shown in Table 3.21-2.
ACTION:
- a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive effluent monitored by the affected channel or declare the channel inoperable.
- b. With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.21-2. Exert best efforts to return the instrumentation to OPERABLE status within.30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner.
BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluent during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR 20.1301.
The low range condenser offgas noble gas activity monitors also provide data for determination of steam generator primary to secondary leakage rate.
Channel operability requirements are based on an ASLB Order No. LBP-84-47 dated October 31, 1984, and as cited in 20 NRC 1405 (1984).
3-100 Amendment No. 77, Jp), 177, J57, 173
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.3.22- RADI0 ACTIVE EFFLUENT 3.22.1 LIOUID EFFLUENT
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3.22.1.1' CONCENTRATION-
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LIMITING CONDITION FOR OPERATION 3.22.1.1 lhe concentration of radioactive material released at anytime from the unit to unrestricted areas-(see Figure 5-3) shall be limited to ten times the concentrations specified in 10 CFP Part 20.1001-20.2401, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 3 x 10-' uCi/cc total activity.
APPLICABILITY: At all times ACTION: _,
With the concentration of radioactive material released from the unit to ,
unrestricted areas exceeding the above limits, immediately restore '
concentration within the above limits.
BASES This specification is provided to ensure that the coicentration of radicTctive materials released in liquid waste riflue nt from the unit to unrestricted areas will be less than ten times the cancentration levels specified in 10 CFR Part 20.1001-20.2041, Appradix r.7, -Table 2. This <
limitation provides additional assurance that *.ha ievels of radioactive materials in bodies of water outside the site will not result in exposures with(1)-theSectionII.AdesignobjectivesofAppendixI,10CFRPart50,to{
a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.1301 to the
- population. The concentration limit for noble gases is based upon the assumption the Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the :
methods described in International Commission on Radiological Protection (ICRP) Publication 2. ;
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i 3-106 l Amendment No. 72, J77, 157, 173
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a RADI0 ACTIVE EFFLUENTS LICUID HOLDUP TANKS LIMITING CONDITION FOR OPERATIONS-3.22.1.4 The quantity of radioactive material contained in each of the following tanks shall be limited to less:than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.
- a. Outside temporary tank APPLICABILITY: At all times.
ACTION:
- a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of 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.
BASES 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 20.1001-20.2401 Appendix B, Table 2, Column 2, at the nearest .}-
potable water supply and the nearest surface water supply in an unrestricted area.
3-110 Amendment No. 72
RADI0 ACTIVE EFFLUENT 3.22.2 GASEOUS EFFLUENT 3.22.2.1 DOSE RATE LIMITING CONDITION FOR OPERATIONS ,
3.22.2.1 The dose rate due to radioactive materials released in gaseous effluent from the site (see Figure 5-3) shall be limited to the following:
- a. For noble gases: less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, and
- b. For I-131, I-133, tritium and all radionuclides in particulate form with half lives greater than 8 days: less than or equal to 1500 mrem /yr to any organ. j APPLICABILITY: At all times.
i ACTION:
With the release rate (s) exceeding the above limits, immediately i decrease the release rate to comply with the above limit (s). I BASES The specification provides reasonable assurance that the annual dose at the site boundary from gaseous effluent from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas while providing sufficient operational flexibility in establishing effluent monitor setpoints. These gaseous release rates provide reasonable assurance that radiaactive material discharged in gaseous effluent will not result in the exposure of a MEMBER OF THE PUBLIC in an unrestricted area, either within or .
outside the site boundary, to annual average concentrations exceeding the i values specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the site boundary, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase ,
in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the site boundary to less than or equal to 500 mrem / year ,
to the total body or to less than or equal to 3000 mrem / year to the skin. -
These release rate limits also restrict, at all times, the corresp7nding thyroid dose rate above ba:.kground to a child via the cow-milk pathway to i less than or equal to 1500 mrem / year for the nearest cow to the plant.
I 3-111 Amendment No. 72, D7, 173 1
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RADI0 ACTIVE EFFLUENTS ,
3,22.4 TOTAL DOSE i LIMITING CONDITION FOR OPERATION .
3.22.4 The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and to radiation from l uranium fuel cycle sources shall be limited to less than or equal to i 25 mrem to the total body or any organ except the thyroid, which shall be limited to less than or equal to 75 mrem.
APPLICABILITY: At all times. !
ACTION:
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With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of !
Specifications 3.22.1.2.a, 3.22.1.2.b, 3.22.2.2.a, 3.22.2.2.b. ,
t 3.22.2.3.a, or 3.22.2.3.b, calculations should be made including direct radiation contributions from the unit and from outside t storage tanks to determine whether the above limits of Specification 3.22.4 have been exceeded. If such is the case, prepare and submit i to the NRC Region I Administrator within 30 days, a Special Report i which defines the corrective action to be taken to reduce subsequent ;
releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(b),
- shall include an analysis which 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 describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceed the above s limits, and if the release condition resulting in violation of 40 ;
CFR 190 has not already been corrected, the Special Report shall ;
include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely ;
request, and a variance is granted until staff action on' the request- :
is complete. #
BASES !
This specification is provided to meet the dose limitations of i 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.2203. This ) :
Gecification requires the preparation and submittal of a Special Report j whenever the calculated doses from plant generated radioactive effluents and' '
direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites i
3-119 !
- Amendment No. H , 129 e
. . containing up to 4 reactors, it is highly unlikely that the resultant dose to a member.of the public will exceed the dose limits of 40 CFR Part 190 if the ,
individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of ,
action that should result in the limitation of the annual dose to a member of :
the public to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the ;
release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(b), is considered to be a timely request and fulfills the l .
requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications 3.22.1.1 and 3.22.2.1. An individual is not i considered a member of the public during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. ,
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3-119a i a
Amendment No. 129 l l
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, 1. A tabulation on an ennual basis of the number of_ station, utility, and other personnel (including contractors) for ,
whom monitoring was required, receiving exposures greater t than 100 mrem /yr and their associated man rem exposure-according to work and job functions, (e.g., reactor r operations and surveillance, inservice inspection, routine maintenance, special aiaintenance (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 20% of the individual total i 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.
(This tabulation supplements the requirements of Section 20.2206 of 10 CFR Part 20.)
4 6-12a !
Amendment No. 157 ;
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r '" RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:
- a. Records of normal station operation including power levels and periods of operation at each power level.
- b. Records of principal maintenance activities, including inspection, repairs. substitution, or replacement of principal items of equipment related to nuclear safety.
- c. All REPORTABLE EVENTS.
- d. Records of periodic checks, tests and calibrations.
- e. Records of reactor physics tests and other special tests related to nuclear safety.
- f. Changes to procedures required by Specification 6.8.1.
- g. Deleted
- h. Test results, in units of microcuries, for leak tests performed ,
on licensed sealed sources :
- 1. Results of annual physical u.ventory verifying accountability of licensed sources on record.
- j. Control Room Log Book.
- k. Shift Foreman Log Book.
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6-20 ;
Amendment No. 72,77,129,177, JJJ, JJP, JES, 173 I
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- 6,10.2 The following records shall be retained for the duration of Operating License DPR-50 unless otherwise specified in 6.10.1 above.
. a. Records 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. Routine unit radiation surveys and monitoring records.
- d. Records of doses received by all individuals for whom monitoring was required.
- e. Records of radioactive liquid and gaseous wastes . released to the environment, and records of environmental monitoring surveys.
- f. Records of transient or operational cycles for those facility components which affect nuclear safety for a limited number of transients or cycles as defined in the Final Safety Analysis Report.
- g. Records of training and qualification for current members of the unit staff.
- h. Records of in-service inspections performed pursuant to these Technical Specifications.
- i. Records of Quality Assurance activities required by the Operational Quality Assurance Plan.
- j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
- k. Records of reviews by the Independent Onsite Safety Review Group.
- 1. Records of analyses required by the radiological environmental monitoring program,
- m. Records of the service lives of all safety related hydraulic snubbers including the date at which the service life. commences .
and associated installation and maintenance records.
- n. Records of solid radioactive shipments.
- o. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
6-21 Amendment.No. 77, 77, J27,:J)7, Jff, Jfp, JSP, 173
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 20.1601 of 10 CFR 20:
- a. Each High Radiation Area in which the intensity of radiation at 30 cm (11.8 in.) is greater than 100 mrem /hr. deep dose but less than 1000 mrem /hr. shall be barricaded and conspicuously posted as a High Radiation Area, and personnel desiring entrance shall obtain a Radiation Work Permit (RWP). Any individual or group of individuals entering a High Radiation Area shall (a) use a continuously indicating dose rate monitoring device or (b) use a radiation dose rate integrating device which alarms at a pre-set dose level (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), or (c) assure that s radiological control technician provides positive control over activities within the area and periodic radiation surveillance with a dose rate monitoring instrument.
- b. Any area accessible to personnel where an individual could receive in any one hour a deep dose in excess of 1000 mrem at 30 (11.8 in.) cm but less than 500 rads at one meter (3.28 ft.)
from sources of radioactivity shall be locked or guarded to prevent unauthorized entry. The keys to these locked barricades shall be maintained under the administrative control of the respective Radiological Controls Supervisor.
The Radiation Work Permit is not required by Radiological Controls personnel during the performance of their assigned radiation protection duties provided they are following radiological control procedures for entry into High Radiation Areas.
P 6-22.
Amendment Nos. JJ,75,72,77,195,Jp7,JRP,173