ML20097E258
| ML20097E258 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 02/06/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Atlantic City Electric Co |
| Shared Package | |
| ML20097E265 | List: |
| References | |
| NPF-57-A-091 NUDOCS 9602130409 | |
| Download: ML20097E258 (13) | |
Text
1 i
p ter ug'o, UNITED STATES
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k NUCLEAR REGULATORY COMMISSION 5
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wAsHINoToN, D.o. 300MH1001 PUBLIC SERVICE ELECTRIC & GAS COMPANY 1
ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.91 License No. NPF-57 1.
The Nuclear Regulatory Comission (the Commission or the NRC) has fo that:
A.
Gas Company (PSE&G) dated JanuaryThe application for 20, 1995, as supplemented by letter dated December 18, 1995, complies with the standards and and the Commission's rules and regulations set fort 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:
(1) 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 set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 of the Commission'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 this license amendment amended to read as follows:and paragraph 2.C.(2) of Facility Operatin 9602130409 960206 PDR ADOCK 05000334 P
l i
- i (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 91, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into the license.
PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of if s date of issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION s
t Jo i F. Stolz, Direc oject Directorate
-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 6, 1996
ATTACIMENT TO LICENSE AMENDMENT NO. 91 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert xvi xvi XXi XXi 3/4 3-97 3/4 3-97 3/4 3-99 3/4 3-99 3/4 3-100 3/4 3-100 3/4 3-102 3/4 3-102 3/4 11-16 3/4 11-16 B 3/4 11-4 B 3/4 11-4 B 3/4 11-5 B 3/4 11-5 6-16a
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREFJi:NTS SECTION PAGE i
Main Condenser.........................................
3/4 11-17 Venting or Purging.....................................
3/4 11-18 3/4.11.3 SOLID RADICACTIVE WASTE TREATMENT........................ 3/4 11-19 3/4.11.4 TOTAL DOSE............................................... 3/4 11-20 3/4,12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM.......................................". 3/4 12-1 Table 3.12.1-1 Radiological Environmental
[
Monitoring Program...............
3/4 12-3 Table 3.12.1-2 Reporting Levels For Radioactivity Concentrations In Environmental Samples..........................
3/4 12-9 Table 4.12.1-1 Detection capabilities For.
Environmental Sample Analysis..... 3/4 12-10 3/4.12.2 LAND USE CENSUS........................................... 3/4 12-13 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM........................ 3/4 12-14 i
HOPE CREEK xvi Amendment No. 91 I
INDEX BASES SECTION FAgg 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY B 3/4 10-1 3/4.10.2 BOD SEQUENCE CONTROL SYSTEM B 3/4 10-1 3/4.10.3 SETTDOWN MARGIN DEMONSTRATIONS.
B 3/4 10-3 3/4.10.4 BECIRCULATION LOOPS B 3/4 10-1 3/4.10.5 CKYGEN CONCENTRATION.
B 3/4 10-1 3/4.10.6 TRAINING STARTUPS B 3/4 10-1 3/4.10.7 SPECIAL INSTRUMENTATION - INITIAL CORE LOADING B 3/4 10-1 l
3/4.10.3 TumanVICE LEAK AND HYDROSTATIC TESTING.
B 3/4 10-2 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration B 3/4 11-1 Dose.
B 3/4 11-1 Liquid Radwaste Treatment System.
B 3/4 11-2 Liquid Holdup Tanks B 3/4 11-2 3/4.11.2 GkSEOUS EFFLUENTS Dose Rate B 3/4 11-2 Dose - Noble Gases.
B 3/4 11-3 Dose - Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form B 3/4 11-3 Gamecus Radwaste Treatment System and
)
Ventilation Exhaust Treatment Systems B 3/4 11-4 g
B 3/4 11-5 Vesting or Purging.
B 3/4 11-5 3/4.11.3 SOLID RADIOACTIVE WASTE TREATMENT B 3/4 11-5 3/4.11.4 wrAL DOSE.
B 3/4 11-5 HOPE CREEK xxi Amendment No.91 I
b h
TABLE 3.3.7.11-1 i
RADIOACTIVE GASEOUS EFFLtJEKT rsuni mkING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 1.
DELETED 2.
FILTRATION, RECIRCULATION AND VENTILATION MONITORING SYSTEM a.
Noble Gas Activity Monitor 1
123 i
i b.
Iodine Sampler 1
125 c.
Particulate sampler 1
125 d.
Flow Rate Monitor 1
122 e.
Sampler Flow Rate Monitor 1
122 3.
SOUTH PLANT VENT MONITORING SYSTEM a.
Noble Gas Activity Monitor 1
123 b.
Iodine Sampler 1
125 c.
Particulate Sampler 1
125 d.
Flow Rate Monitor 1
122 e.
Sampler Flow Rate Monitor 1
112 I
t i'
4 e,',
.m
. ~ _,..
TABLE 3.3.7.11-1 (Continued)
TABLE NOTATION At all times.
I ACTION 122 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via i
this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Otherwise, suspend release of radioactive effluents via this pathway.
)
ACTION 123 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 124 -
DELETED ACTION 125 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> samples are continuously collected with auxiliary sampling equipment as required in Table 4.11.2.1.2-1.
HOPE CREEK 3/4 3-99 Amendment No.91
TABLE 4.3.7.11-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION suxVEILLANC':
R80UIREMIDrrS CHANNEL MODES IN WHICH.
CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REOUIRED
- 1. DELETED l
- 2. FILTRATION, RECIRCULATION, AND VENTILATION MONIMRING SYSTEM
- a. Noble Gas Activity Monitor D
M Rm gm
- b. Iodine Sampler W
N.A.
N.A.
N.A.
- c. Particulate Sampler W
N.A.
N.A.
N.A.
- d. Flow Rate Monitor D
N.A.
R Q
I b
- e. Sampler Flow Rate Monitor D
N.A.
R Q
i i
t
- 3. SOtTTH PLANT VENT MONIMRING SYSTEM
- a. Noble Gaa Activity Monitor D
M R"
Q N
- b. Iodine Sampler W
N.A.
N.A.
N.A
- c. Particulate Sampler W
N.A N.A.
N.A.
- d. Flow Rate Monitor D
N.A.
R Q
- e. Sampler Flow Rate Monitor D
N.A.
R Q
r
~
i I
HOPE CREEK 3/4 3-100 ha d-*
- M 8
r "a
.. -. ~ -. -
e TABLE 4.3.7.11-1 (Continued)
TABLE NOTATION At all times.
1 (1)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
l 3.
Instrument indicates a downscale failure.
(2)
The initial CHANNEL CALIBRATION shall be performed using one.or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration or are NBS traceable shall be used.
I HOPE CREEK 3/4 3-102 Amendment No.g1
MADICACTIVE EFFLUENTS 3.11.2.6 DELETED f
HOPE CREEK 3/4 11 16 Amendment No. 91
... ~ _.. -. -..... =... _.... - - - -.-
RADIOACTIVE EFFLUENTS BASES DOSE - IOD11rE-131. IODINE-133. TRITIUM. AND RADIONUCLIDES IN PARTICULATE FORM (Continued) the requirements in Section III.A of Appendix I that-conformance with the guides of Appendix I be shown by calculational procedures based on models and t
data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the
" Calculation of Annual Doses methodology provided in Regulatory Guide 1.109, to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric iodine-133, conditions. The release rate specifications for iodine-131, tritium,-and radionuclides in particulate form with half lives greater than 8 in the days are dependent upon the existing radionuclide pathways to man, areas at a (1) individual inhalation of airborne development of these calculations were: deposition of radionuclides onto green leafy vegetation radionuclides, (2) with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
3 /4.11.2.4 AND 3 /4.11.2. E GASEQUS RADWASTE TREATMENT AND VENTILATION E TREATMENT The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREA'INENT SYSTEM ensures that the system will be available
~
for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of and the design General Design Criterion 60 of Appendix A to 10 CFR Part 50, objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
3/4.11.2.6 DELETED Amendment No. 91 B 3/4 11-4 HOPE CREEK
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....-. - ~. - -
.... ~ - -. -
-... - ~.. - -. - ~ ~ - - -
i i
RADIOACTIVE EFFLUENTS I
BASES Il 3/4.11.2.7 MAIN CONDENSER J
Restricting the gross radioactivity rate of noble gases from the main condenser provides reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 10 CFR Part 100 in the event this effluent is inadvertently discharged directly f.o the environment without treatment. This specification implements the requirements of General Design criteria 60 and 64 of Appendix A to 10 CFR Part 50.
3/4.11.2 1 VENT 1NG OR PURGING This specification provides reasonable assurance that releases from drywell purging operations will not exceed the annual dose limits of 10 CFR Part 20 for UNRESTRICTED AREAS.
3/4.11.3 SOLID RADIOACTIVE WASTE TREA1 MENT This specification implements the requirements of General Design criterion 60 of Appendix A to 10 CFR Part 50.
The procesa parameters included in establishing the PROCESS CONTROL PROGRAM may include,. but are not limited to waste type, waste pH, waste / liquid /solidifiestion agent / catalyst ratios, waste oil cantent, waste principal chemical-constituents, and mixing and curing time s.
The purpose of the PROCESS CONTROL PROGRAM is to provide quality ast.urance that the solidified waste meets 10 CFR Part 61 requirements.
3 /4.11. A,2,QTAL P12%
l This specification is provided to meet the dose limitations of 40 CFR Part 1
190 thac have been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report' whenever the calculated doses from plant generated radioactive effluents and l
direct radiation exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
For sites 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 2, and if direct radiation doses from the reactor units including outside storage tanks, etc. 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 1
HOPE CREEK B 3 /4 11 si Amandmant W 9
-.. -. _ -. -. ~.
ADMINISTRATIVE CONTROLS d.
Exelosive Gas Monitorino This program provides controls for potentially explosive gas mixtures contained in the Main Condenser offgas Treatment System. The program shall include the limit for hydrogen concentration in the Main Condenser offgas Treatment System and a surveillance program to ensure the limit is maintained. This limit shall be appropriate to the system's design criteria j
(i.e., whether or not the system is designed to withstand a hydrogen explosion).
The provisions of Surveillance Requirements 4.0.2 and 4.0.3 are applicable to the Explosive Gas Monitoring Program surveillance frequencies.
\\.
i HOPE CREEK 6-16a Amendment N6 91 I