ML20056H312
| ML20056H312 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/30/1993 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20056H307 | List: |
| References | |
| NUDOCS 9309090139 | |
| Download: ML20056H312 (13) | |
Text
l ADMINISTRATIVE CONTROLS COMPOSITION 6.5.1.2 The 50RC shall be composeo of the:
t Chairman:
General Manager - Hope Creek j
Operations i
Member and Vice Chairman:
Operations Manager l
Member and Vice Chairman:
Technical Manager l
Member and Vice Chairman:
Maintenance Manager Member:
Maintenance Engineer 4
Member:
Technical Engineer Member:
Radiation Protection N ~ e r CI,m; etry Me..eger 9 g
Member:
Rei;etien "retectien Er.gineer er 1
Chemistry S;irdmm te Member:
Onsite Safety Review Engineer Member:
Operating Engineer ALTERNATES 1
- 5. 5.1. 3 All alternate members shall be appointed in writing by the j
SORC Chairman.
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Only designated Vice Chairmen or the General Manager - Hope Creek i
a.
Operations may act as Chairman of a SORC meeting.
b.
No more than two alternates to members shall participate as voting
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members in 50RC activities at any one meeting.
i.t Alternate appointees will only represent their respective department.
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c.
d.
Alternates for members will not make up part of the voting quorum
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when the member the alternate represents is also present.
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MEETING FREQUENCY 6.5.1.4 The 50RC shall meet at least once per calendar month and as convened by the 50r Nairman or his designated alternate.
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QUORUM I
l 6.5.1.5 h.c quorum of the 50RC necessary for the performance of the'50RC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least four members including alternates.
RESPONSIBILITIES 6.5.1.6 The 50RC shall be responsible for:
a.
Review of:
(1) Upper tier administrative procedures within the scope of Regulatory Guide 1.33 (2/78), and changes thereto and (2) Newly created procedures or changes to existing HOPE CREEK 6-7 Amenoment No.52 j
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9309090139 930830
INSTRUMENTATION
_RA'0I0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FCR OPERATION 3.3.7.10 The radioactive liquid effluent monitoring instrumentation enanrel shown in Table 3.3.7.10-1 shall be OPERABLE with their Alarm / Trio Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceedec.
The Alarm / Trio Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (00CM).
APPLICABILITY:
At all times.
ACTION:
With a radioactive liquid effluent monitoring instrumentation cnannel c.
Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive licuic effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
b.
With less than the minimum number of radioactive liquid effluent monitoring iristrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.10-1. ~ Exert best efforts to return the instruments :::
OPERABLE status,yithin 30 days and, if unsuccessful, explain in the nextI5emiannual! Radioactive Effluent Release Report pursuant to Spec-ification 6.9.1.7 why this inoperability was not corrected in a timely manner.
The provisions of Specification 3.0.3 are not applicable.
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c.
SURVEILLANCE REQUIREMENTS 4.3.7.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3.7.10-1.
I HOPE CREEK 3/4 3-91 Amendment No. 19 9'
XNSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LXMITING CONDITION FOR OPERATICN 3.3.7.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their Alarm / Trip 5etpoints set to ensure that the limits of Specifications 3.11.2.3 and 3.11.2.6 are not exceeced.
The Aiarm/ Trip 5etcoints of these channels meeting Specification 3.11.2.1 shall ce determined ar.d adjusted in accordance with the methodology ano parameters in the ODCM.
APPLICABILITY-As shown in Table 3.3.7.11-1.
ACTION:
With a radioactive gaseous efficent monitoring instrumentation a.
channel Alarm / Trip Setpoint less conservative than requirzd by the above specification, immediately suspend the release of radioactive gaseous ef fluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint 50 it is acceptably conservative.
b.
With less than the minimum number of radioactive gaseous effluent monitoring-instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.11-1.
Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the nextlSemiannualfRadioactive Effluent Release Report pursuant to Specification 6.9.1.7 why this inoperability was not corrected in a timely manner, The provisions of Specification 3.0.3 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3.7.11-1.
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HOPE CREEK 3/4 3-96 Amendment No.19
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i TABLE 4.11.1.1.1-1 (Continued) j TABLE NOTATION cThe principal gamma emitters for which the LLD specification applies exclusively are:
Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, and Ce-141.
Ce-144 shall also be measured, but with an LLD of 5 x 10 6 This does not mean that only these nuclides are ** be considered.
Other peaks that are identifiable, together with those el f.J_ abo 9b nuclides, h
shall also be analyzed and reported in the 15emianr;ua j Radioactive Effluent Release Report pursuant to Specification 6.9.1.7.
dA composite sample is one in which the quantity of liquid samples is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.
'A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of a system that has an input flow during the 1
continuous release.
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1 HOPE CREEK 3/4 11-4 i
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RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING' CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in any outside temporary tank shall be limited to less than or equal to 10 curies, exclud ng i
tritium and dissolved or entrained noole gases.
APPLICABILITY: At all times.
ACTION:
With the quantity of radioactive material in any of tha above +.a-ks a.
exceeding the above limit, immediately suspend all additions of radioactive material to the tank, 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. and desctibe the events leading to this condition in the nextlSemiannualFRaaioactive Effluent Aelease Report, pursuant to Specification 6.9.1.7.
b.
The provisions of Specification 3.0.3 are not applicable.
1; 1.
SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above tanks shall be determined to be within the above limit by analyzing a repre-sentative sample of the tank's contents at least once per 7 days when radio-active materials are being added to the tank.
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HOPE CREEK 3/4 11-7 Amendment No.19 x,
TABLE 4.11.2.1.2-1 (Continued)
TABLE NOTATICNS
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(b)The principal gama emitters for which the LLD specification applies ex are the following radionuclides:
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xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co v
I-131, Cs-134, Cs-137, Ce-141 and Ce-144 in iodine and particulate rele i
i This list does not mean that only these nuclices are to be considered Other gamma peaks that are identifiable, togethe Effluent Release Report pursuant to Specification 6.9.1.7.
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(c) Sampling and analysis shall also be performed following shutdown, st or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER w i
1-hour period.
This requirement does not apply if (1) analysis shows l
that the DOSE EQUIVALENT I-131 concentration in the primary coolant has
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i not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
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i (d) Tritium grab samples shall be taken at least once per 7 days from the sp fuel pool area, whenever spent fuel is in the spent fuel pool.
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s (e)The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation i
made in accordance with Specificatipns 3.11.2.1, 3.11.2.2, and 3.11.2.3.
(f) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.
Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 15% of RATED THERMAL POWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and ana i
within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.
j, When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10.
i This requirement does not apply if (1) analysis shows that the DOSE i
j EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
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HOPE CREEK 3/4 11-11 Amendment No. 28
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c RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION (Continued) l ACTION:
(Continued)
The soecific locations'from which samples were unavailable may then be deleted from the monitoring program.
Pursuant to Specifica-i tion 6.9.1.8, identify the cause of the unavailability of samples tra identify the new,Jocation(s) for obtaining replacement samples in the~
nextliggiannua H Radioactive Effluent Release Report pursuant to Speci-fication 5.9.1.8 and also incluce in the report a revised figure (s) and table for the ODCM reflecting the new location (s).
j d.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS
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4.12.1 The radiological environmental monitoring samples shall be collected
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pursuant to Table 3.12.1-1 from the specific-locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of i
Table 3.12.1-1 and the detection capabilities required by Table 4.12.1-1.
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HOPE CREEK 3/4 12-2 Amendrent No 19
TABLE 3.12.1-1 (Continued)
TABLE NOTATIONS (2) Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be pro-vided for each and every sample location in Table 3.12.1-1 in a table and figure (s) in the 00CM.
Refer to NUREG-0133, " Preparation of Radiological Ef fluent Technical Specifications for Nuclear Power Plants, October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, sea-sonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.
If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period.
All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.
It is recognized that, at times, it may not be possible or practicable to con-tinue to obtain samples of the media of choice at the most desired loca-tion or time.
In these instances suitable specific alternative media and locations may be chosen for the particular pathway in question and appro-priate substitutions made within 30 days in the Radiological Environmental Monitoring Program given in th,e,0DCM.
Pursuant to Specification 6.14, submit in the next!SemiannuaH Radioactive Effluent Release Report documen-tation for a change in the ODCM including a revised figure (s) and table for the 00CM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new location (s) for obtaining samples.
(2)0ne or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addi-l tion to, integrating dosimeters.
For the purposes of this table, a thermo-I luminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.
Film badges shall not be used as dosimeters for measuring direct radiation.
The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.
(3) Airborne particulate sample filters shall be analyzed for gross beta radio-activity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay.
If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
(4) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
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l (5)The " upstream sample" shall be taken at a distance beyond significant influence of the discharge.
The " downstream" sample shall be taken in an area beyond but near the mixing zone.
" Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence.
Salt water shall be sampled only when the receiving water is utilized for recreational activities.
HOPE CREEK 3/4 12-7 1
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i RADf0 LOGICAL ENVIRONMENTAL MONITORIhG 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence ar.d the nearest garden" of greater than 50 m2 2
(500 ft ) producing broad leaf vegetation.
APPLICABILITY:
At all times.
ACTION:
With a land use census identifying a location (s) that yields a cal:.-
a.
lated dosa or dose commitment greater than the values currently being calculated in SpectLication 4.11.2.3, identify the new location (s) in the nextlsmatannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.
b.
With a land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently.
being obtained in accordance with Specification 3.12.1, add the new location (s) to the radiological environmental monitoring program within 30 days.
The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program af ter October 31 of the year in which this land use census was conducted.. PursuanttoSpecificgton6.9.1.8, identify the new location (s) in the next/Jialanngilj Radioactive Ef fluent Release Report and also include in the report a revised figure (s) and table for the 00CM reflecting the new location (s).
1 The provisions of Specification 3.0.3 are not applicable.
c.
I SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, visual survey, aerial survey, or by consulting local agriculture authorities.
The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.
- Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors <
with the highest predicted D/Qs in lieu of the garden census.
Specifications for broad leaf vegetation sampling in Table 3.12.1-1, Part 4.c., shall be followed, including analysis of control samples.
4 HOPE CREEK 3/4 12-13 Amendment No. 19 w.
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ADMINISTRATIVE CONTROLS i
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (Continued) after the radiciodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiciodine concentrations; (3)
Clean up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one otner radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the staaey-state level; and (5)
The time duration when the specific activity of the primary coolant exceeced the radiciodine limit.
W 3GIAnnJAL RADIOACTIVE EFFLUENT RELEASE REPORT
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- 6. 9.1. 7 ":.tir.: radioactive release reports c, ring she operation of the N. !.k..b..I.i.N.,. Ib.-..N., k. 5.. '-..,fm..$$.N.b...',. b...$.,
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-begin ith th: Ot: Of ir.iti:1 riti::1ity. "
io accorbece-em.Aw eg,e@!?.elttHcy,59];
e The radioactive effluent release report [,shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid wasta released from the unit as. outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting
)
Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-cooled Nuclear Power Plants,"ltavision 1 June 1974, with data sumanarized on a quarterly basis following the format of Appendix 8 thereof.
The radioactive efflue release report t; te c r itt:d.ithi-50 ty: efte J;.im e ry 1 O f ; ; ; h j ; ; r hall include an annual summary of hourly meteorological data collected over the previous year.
This annual senary may be either in the fors of an hour-by-hour listing of wind speed, wind direction, and atmos-pheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distrybutions of wind speed, wind direction, and atmos-oneric stability. +T'.i:
n report shall include an assessment of the radia-
~ g[i/
tion doses due to the radioactive liquid and gaseous affluents released from the unit or station during the previous calendar year. +Mreport shall w
also include an assessment of t w radiation doses from radioactive liquid and gaseous affluents to WSERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 5.1.1-1) during the report period. All assumptions used in asking these assessments, i.e., specific activity, exposure time and location, shall be included in these reports.
The historical annual average meteorology or the meteorological conditions concurrent with the time of release.ot radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous patnway with the OFFSITE DOSE CALCULATION MANUAL (00CM).The assessm doses.
The M er.r el madioactive Effluent Release Report shall identify those radiological environmental sasole parameters and locations where it is not possible or practicable to continue 1
to obtain samples of the media of choice at the most desired location or time.
In addition, the cause of the unavailability of samples for the pathway and the new location (s) for obtaining replacement samples should be identified.
The report should also include a revised figure (s) and taale(s) for the 00CM reflecting the new location (s).
HOPE CREEK
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i ACMINISTRATIVE CONTROLS Y
5E* " "tL RADI0 ACTIVE EFF.LUENT RELEASE REPORT (Continued) i Tne radioactive ef fluent release recort t+4: r.biitted eitH - 50 day: :'tcr
-h e,, 1, c' :::P,c: #shall also include an assessment of radiation doses to the likely most excosed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium f uel cycle sources (includipg doses from primary effluent patn-ways and direct radiation) for the previous 12 consecutive months to show con-formance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation.
Acceptable methods for calculating the cose contribu-tion from liquid and gaseous ef fluents are given in Regulatory Guide 1.109, Rev. 1.
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j The radioactive effluent release shall include the following information for eacn class of solid waste (as defined by 10 CFR 61) shipped offsite during the report period:
i a.
Container volume, Total curie quantity (specify whether determined by measurement or b.
estimate),
Principal radionuclide (specify wnether determined Dy measurement c.
or estimate),
d.
Type of ;a te (e.g., spent resin, compact dry waste, evaporator bottoms),
Type of container (e.g., LSA, Type A, Type B, Large Quantity), and e.
f.
Solidification agent (e.g., cem nt, urea formaldehyde).
The radioactive effluent release report 'shall include unplanned releases from the site to the UNRESTRICTED AREA of radioactive materials in gaseous and liquid effluents on a quarterly basis.
Tne radioactive effluent release reportis shall include any changes to the PROCESS CONTROL PROGRAM (PCP), OFFSITE 005E CALCULATION MANUAL (00CM) or radio-active waste systems made during the reporting period.
MONTHLY OPERATING REPORTS
- 6. 9.1. 8 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Docu-ment Control Desk, Washington, D.C. 20555, with a copy to the Regional Admin-istrator of the Regional Office no later than the 15th of each month following the calendar month covered by the report.
CORE OPERATING LIMITS REPORT
- 6. 9.1. 9 Core operating limits shall be established and documented in the PSE&G generated CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following Technical Specifications:
3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 3/4.2.3 MINIMUM CRITICAL POWER RATIO 3/4.2.4 LINEAR HEAT GENERATION RATE l
i HOPE CREEK 5-20 Amendment n 34
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ADMiNISTRATIVECONTROLS PROCESS CONTROL PROGRAM (PCP) (Continued) 6.13.2 Licensee initiated changes to the PCP:
1.
Shall be submitted to the Commission in thelSemiannuallRadioactive Ef fluent Release Report for the period in which the change (s) was made.
This submittal shall contain:
Sufficiently detailed information to totally support the a.
rationale for the change without benefit of additional or supplemental information; a.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; b.
A determinatfor that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c.
Documentation of the fact that the chenge has been reviewed and found acceptable by the 50RC.
2.
Shall become effective upon review and acceptance by the 50RC.
6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee initiated changes to the ODCH:
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Shall be submitted to the Commission in theisemiannuallRadioactive Effluent P-lease Report for the period in which the change (s) was j
made.
Th'e submittal shall contain:
i a.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supple-mental information.
Information submitted should consist of a
' package of those pages of the ODCM to be changed with each page numbered and provided with an appr? val-and date box, together with appropriate analyses or evaluations justifying the change (s);
b.
A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determination; and c.
Documentation of the fact that the change has been reviewed and found acceptable by the 50RC.
2.
Shall become effective upon review and acceptance by the 50RC.
6.15 MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 6.15.1 Licensee initiated major changes to the radioactive waste system (liquid, gaseous and solid):
1.
Shall be reported to the Commission in the UFSAR for the period in l
which the evaluation was reviewed by 50RC.
The discussion of each change shall contain:
l HOPE CREEK 6-24 Amendment No. 52
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INDEX
'C A'JMINISTRATIVE CONTROLS f
SECTION
--PAGE ANNUAL REP 0RTS............................................
6-17 ANNUAL RADIOLOGICAL ENVIRONNENTAL OPERATING REPORT........
6-18 i
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ISEMIANNUAL] RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT....
6-19 i
i MONTHLY OPERATING REP 0RTS.................................
6-20 i
CORE OPERATING LIMITS REP 0RT..............................
6-20 l
l 6.9.2 SPECIAL REP 0RTS...........................................
6-21 6.10 RECORD RETENTION..............................................
6-21 t
6.11 RADIATION PROTECTION PR0 GRAM..................................
6-22
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i 6.12 HIGH RADIATION AREA...........................................
6-22 6.13 PROCESS CONTROL PROGRAM (PCP).................................
6-23 i
6 14 0FFSITE DOSE CALCULATION MANUAL (0DCM)........................
6-24 2
6.15 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND t
t SOLID WA5TE TREATMENT SYSTEM5.................................
6-24 i
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l HOPE CREEK xxvi Amendment No. 34 OCT 2 01989 w
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