ML20211N547
| ML20211N547 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/08/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211N544 | List: |
| References | |
| NUDOCS 9909130019 | |
| Download: ML20211N547 (38) | |
Text
I-
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UNITED STATE 3 go g
g NUCLEAR REGULATOR / COMMISSION
't WASHINGTON, D.C. 20555 0001
'+9..... g o
g PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.121 License No. NPF-57 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Public Service Electric & Gas Company (PSE&G) dated March 29,1999, as supplemented June 21,1999, complies with the standards and requirements of the Atomic Energy 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 tha 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 common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been sul;ufied.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as~
indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-57 is hereby amended to read as follows:
9909130019 99090s PDR ADOCK 05000354 P
I
. (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
121, 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 its date of issuance, and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION A
ames W. Cliffo d, Chief, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 8, 1999
\\
ATTACHMENT TO LICENSE AMENDMENT NO.121 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 i
Replace the following pages of the Appendix "A" Technical Specifications with the attached
. revised pages. The revised pages are identified by Amendment number and contain marginal
- lines indicating the areas of change.
Remove Insert li ii lx lx j
xv xv xvi -
xvi xviii xviii xxl xxl xxil xxii xxiv xxiv xxv xxv 1-4 1-4 j
4'"
1-6 1-6 i
18' 1-8 3/4 3-91 3/4 3-91 3/4 3-92 3/4 3-92 3/4 3-93 3/4 3-94 3/4 3 ---
3/4 3-96 3/4 3-97 3/4 3-98 3/4399-I 3/4 3-100 3/4 3-101 3/4 3-102 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-2 3/4 11-3 3/4 11-3 3/4 11-4 3/4 11-4 3/4 11-5 3/4 11-6 3/4 11-7
-3/4 11-8 3/4 11-9 3/4 11-10 3/4 11-11 3/4 11-12 3/4 11-13 3/4 11-14 i
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3/4 11-15 3/4 11-16 l
3/4 11-18 3/4 11-18 3/4 11-19
- 3/4 11-20 3/4 12-1.
3/4.12-1 3/4 12-2 3/4 12-3
'3/4 12-4 3/4 12-5 3/4.12-6 3/4 12-7
- 3/4 12-8 3/4 12-9 3/4 12-10 3/4 12-11 3/4 12-12 3/4 12-13 3/4 12-14 6-16b 6-16b 6-16c.
6-16d 6-18 6-18 6-19 6-19 6-20 6-20 6-22 6-22 6-23 6-23 l
6-24.
6-24 6-25 6-25 B 3/4 3-6 B 3/4 3-6 B 3/411-1 B 3/411-1 B 3/411-2
- B 3/411-2 83/411-3 B 3/411 ---
B 3/411-5 B 3/411-6 B 3/412-1 B 3/412-1 B 3/412-2 l
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INDEX DEFINITIONS
-SECTION b
DEFINITIONS (Continued)
PAGE 1.26 OFF-GAS RADWASTE TREATMENT SYSTEM.................
1-4 1.27 OFFSITE DOSE CALCULATION MANUAL 1-4 1
l 1.28 OPERABLE - OPERABILITY............................
1-5 I
1.29 OPERATIONAL COND TION - CONDITION.................
1-5 1.30 PHYSICS TESTS 1-5 1.31 PRESSUBE BOUNDARY LEAKAGE 1-5 1.32 PRIMARY CONTAINMENT INTEGRITY 1-5 1.33 PROCESS CONTROL PROGRAM 1-6 1.34 PURGE-PURGING 1-6 1.35 RATED THERMAL POWER..............................
1-6 i
1.36 REACTOR PROTECTION SYSTEM RESPONSE TIME..........
1-6
)
1 1.37 REPORTABLE EVENT.................................
1-6 1.38 ROD DENSITY 1-6 1.39 SECONDARY CONTAINMENT INTEGRITY..................
1-7 1.40 SHUTDOWN MARGIN 1-7 1.41 SITE BOUNDARY 1-7
)
i 1.42 Not Used.........................................
1-J[
l 1.43 SOURCE CHECK 1-8 1.44 SPIRAL RELOAD....................................
1-8 l
1.45 SPIRAL UNLOAD....................................
1-8 1.46 STAGGERED TEST BASIS 1-8 1.47 THERMAL POWER....................................
1-8 1.48 TURBINE BYPASS SYSTEM RESPONSE TIME 1-9 HOPE CREEK ii Amendment No.121
r INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE_
Table 3.3.7.4-1 Remote Shutdown Monitoring Instrumentation.
3/4 3-75 i
Table 3.3.7.4-2 l
Remote Shutdown Systems Controls.
3/4 3-77 Table 4.3.7.4-1 Remote Shutdown Monitoring Instrumentation Surveillance Requirements 3/4 3-82 Accident Monitoring Instrumentation 3/4 3-84
)
Table 3.3.7.5-1 Accident Monitoring Instrumentation.
3/4 3-85 Table 4.3.7.5-1 Accident Monitoring Instrumentation Surveillance Requirements 3/4 3-87 Source Range Monitors 3/4 3-88 Traversing In-Core Probe System.
3/4 3-89 3/4.3.8 DELETED 3/4 3-103 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION 3/4 3-105 Table 3.3.9-1 Feedwater/ Main Turbine Trip System Actuation Instrumentation 3/4 3-106 HOPE CREEK ix Amendment No.121
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Leve1............................
3/4 9-17 Low Water Leve1.............................
3/4 9-18 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY................
3/4 10-1 3/4.10.2 ROD WORTH MINIMIZER..........................
3/4 10-2 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS...............
3/4 10-3 3/4.10.4 RECIRCULATION LOOPS..........................
3/4 10-4 3/4.10.5 OXYGEN CONCENTRATION.........................
3/4 10-5 3/4.10.6 TRAINING STARTUPS..............
3/4 10-6 3/4.10.7 SPECIAL INSTRUMENTATION - INITIAL CORE LOADING.................................
3/4 10-7 3/4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING.......
3/4 10-8 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Liquid Holdup Tanks..........................
3/4 11-2 3/4.11.2 GASEOUS EFFLUENTS Main Condenser................................ 3/4 11-17 HOPE CREEK xv Amendment No.121
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.11.3 Deleted 3/4 11-18 3/4.11.4 Deleted 3/4 11-18 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 Deleted 3/4 12-1 3/4.12.2 Deleted 3/4 12-1 3/4.12.3 Deleted 3/4 12-1 i
l 6
1 HOPE CREEK xvi Amendment No.121 J
I?!DEX BASES SECTION PAGE INSTRUMENTATION (Continued)
Remote Shutdown Monitoring Instrumentation and Controls................................B 3/4 3-5 Accident Monitoring Instrumentation........... B 3/4 3-5 Source Range Monitors......................... B 3/4 3-5 Traversing In-Core Probe System...............B 3/4 3-5 3/4.3.8 DELETED.......................................B 3/4 3-7 3/4.3.9 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION...............................
B 3/4 3-7 Figure B3/4 3-1 Reactor Vessel Water Level.... B 3/4 3-8 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM..........................B 3/4 4-1 3 / 4. 4. 2 SAFETY /RELIE F VALVES.......................... B 3 / 4 4 -la 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.....................B 3/4 4-3 Operational Leakage...........................B 3/4 4-3 3/4.4.4 CHEMISTRY.....................................B 3/4 4-3 3/4.4.5 SPECIFIC ACTIVITY.............................B 3/4 4-4 3/4. 4. 6 PRESSURE / TEMPERATURE LIMITS................... B--
/7'4-5 Table B3/4.4.6-1 Reactor Vessel Toughness...........B 3/4 4-7 l
Figure B3/4.4.6-1 Fast Neutron Fluence (E>1Mev) at (1/4)T as a Function of Service life........ B 3/4 4-8 HOPE CREEK xviii Amendment No.121
[
INDEX BASES SECTION PAGE 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.l' PRIMARY CONTAINMENT INTEGRITY.............. B 3/4 10-1 3/4.10.2 ROD WORTH MINIMIZER........................
B 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS............. B 3/4 10-1 3/4.10.4 RECIRCULATION LOOPS........................ B 3/4 10-1 3/4.10.5 OXYGEN 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 3/4.10.8 INSERVICE LEAK AND HYDROSTATIC TESTING..... B 3/4 10-2 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Liquid Holdup Tanks........................ B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS Main Condenser............................. B 3/4 11-1 3/4.11.3 Deleted
.................................. B 3/4 11-2 3/4.11.4 Deleted....................................
B 3/4 11-2 HOPE CREEK xxi Amendment No.121
INDEX BASES SECTION PAGE 3/4.12 RADIOLOGICAL ENVIRONML' ITAL MONITORING 3/4.12.1-Deleted.
B 3/4 12-1 3/4.12.2 Deleted.
B 3/4 12-1 3/4.12.3 Deleted.
B 3/4 12-1 b
5 HOPE CREEK xxii Amendment No.121
i INDEX ADMINISTRATIVE CONTROLS i
i I
SECTION PACE 6.1 RESPONSIBILITY.......................................
6-1 I
6.2 ORGANIZATION.........................................
6-1 1
6.2.1 ONSITE AND OFFSITE ORGANIZATIONS................
6-1 l
J 6.2.2 UNIT STAFF......................................
6-1 Figure 6.2.1-1 (Deleted)............................
6-3 Figure 6.2.2-1 (Deleted)............................
6-4 1
Table 6.2.2-1 Minimum Shift Crew Composition Single Unit Facility..................
6-5 6.2.3 S H I FT TECHN ICAL ADVI SOR.........................
6-6 6.3 UNIT STAFF QUALIFICATIONS............................
6-6 6.4 TRAINING.............................................
6-6 6.5 REVIEW AND AUDIT (THIS SECTION DELETED).............
6-6 6.6 REPORTABLE EVENT ACTION..............................
6-14 6.7 SAFETY LIMIT VIOLATION...............................
6-14 6.8 PROCEDURES AND PROGRAMS..............................
6-15 6.9 REPORTING REQUIREMENTS...............................
6-17 6.9.1 ROUTINE REPORTS....................................
6-17 STARTUP REPORT.....................................
6-17 l
ANNUAL REPORTS.....................................
6-17 l
)
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.
6-18 i
ANNUAL RADIOACTIVE EFFLr-NT RELEASE REPORT.........
6-19 l
MONTHLY OPERATING REPORTS..........................
6-20 J
CORE OPERATING LIMITS REPORT.......................
6-20 6.9.2 SPECIAL REPORTS....................................
6-21 HOPE CREEK xxiv Amendment No. 121 l
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r INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.10 RECORD RETENTIOt1....................................
6-21 6.11 RADIATION PROTECTION PROGRAM........................
6-23 6.12 HIGH RADIATION AREA.................................
6-24 6.13 PROCESS CONTROL PROGRAM (PCP).......................
6-25 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM).............. 6-25 6.15 Deleted.............................................
6-25 HOPE CREEK xxv Amendment No.121 l
L.
DEFINITIONS LINEAR HEAT GENERATION RATE 1.21 LINEAR HEAT GENERATION RATE (LHGR) sitall be the heat generation per unit length of fuel rod.
It is the integral of the heat flux over the heat transfer area associated with the unit length.
LOGIC SYSTEM FUNCTIONAL TEST 1.22 A LOGIC OYSTEM FUNCTIONAL TEST shall be a test of all logic components, i.e., all relays and contacts, all trip units, solid state logic elements, etc, of a logic circuit, from sensor through and including the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by an'y series of sequential, overlapping or total system steps such that the entire logic system is tested.
MAXIMUM FRACTION OF LIMITING POWER DENSITY 1.23 The MAXIMUM FRACTION OF LIMITING POWER DENSITY (MFLPD) shall be highest value of the FLPD which exists in the core.
MEMBER (S) OF THE PUBLIC 1.24 MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant.
This category does not include employees of the utility, it contractors or vendors.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.
MINIMUM CRITICAL POWER RATIO 1.25 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in the core.
OFF-GAS RADWASTE TREATMENT SYSTEM 1.26 An OFF-GAS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting reactor coolant system offgases from the main condenser evocaation system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
OFFSITE DOSE CALCULATION MANUAL 1.27 The OFFSITE DOSE CALCULATIONAL MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program.
The ODCM shall also contain (1) the Radioactive Effluent Conwrols ana Radioloy1 cal Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report required by Specifications 6.9.1.6 and 6.9.1.7.
I HOPE CREEK 1-4 Amendment No.121
p.
I DEFINITIONS PROCESS CONTROL PROGRAM 1.33 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packing 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 Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
I PURGE - PURGING q
1.34 PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such manner that replacement air or gas.is required to purify the confinement.
l RATED THERMAL POWER 1.35 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3293 MWT.
I REACTOR PROTECTION SYSTEM RESPONSE TIME 1.36 REACTOR PROTECTION SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids.
The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.
REPORTABLE EVENT 1.37 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
ROD DENSITY 1,38 ROD DENSITY shall be the number of control rod notches inserted as a fraction of the total number of control rod notches.
All rods fully inserted is equivalent to 100% ROD DENSITY.
l HOPE CREEK 1-6 Amendment No.121 l
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i DEFINITIONS.
SOLIDIFICATION cl.42 Not used.
SOURCE CHECK 1.43 A SOURCE CHECK-.shall be the qualitative assessment of channel response.when the channel sensor is exposed to:a source of
' increased radioactivity.
SPIRAL RELOAD 1.44 A SPIRAL RELOAD is a core loading methodology employed to i
L refuel the core after a complete core-unload.
During 'a
.3PIRAL RELOAD the fuel is to be loaded into individual l control cells (four bundles surrounding a control blade) in a
{
-spiral fashion centered on an SRM moving outward..Before initiating a SPIRAL RELOAD, up to four bundles may be. loaded
'in-the four-bundle locations immediately surrounding.each of the'four SRMs to obtain the required channelLcount rate.
L 1.45 A SPIRAL UNLOAD is a core unloading methodology employed to I
defuel when the complete' core is to be unloaded.
The core j
unload is performed by first removing the fuel from the outermost control cells (four bundles surrounding a control blade).
Unloading continues in a spiral fashion by removing fuel from the outermost periphery to the interior of the' core, symmetric about'the SRMs, except for the four bundles L
around each'of the four SRMs.- When sixteen or less fuel bundles are in the core,'four around each of the four SRMs, there is no need to maintain the. required channel count rate.
I STAGGERED TEST BASIS.
1.46 A STAGGERED TEST BASIS shall consist of:
l
,a.
A test schedule for n systems, subsystems, trains or otherLdesignated components obtained by dividing the specified test interval into n equal subintervals.
b.
The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
. THERMAL POWER 1.47 THERMAL ~ POF.R shall be the total reactor core heat transfer rate to-the reactor coolant.
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HOPE CREEK 1-8 Amendment No. 121 l
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i INSTRUMENTATION 3.3.7.10 Deleted 3.3.7.11-Deleted d_,..
1 HOPE CREEK 3/4 3-91 Amendment No.121 I
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r THIS PAGE INTENTIONALLY BLANK PAGES 3/4 3-93 THROUGH 3/4 3-102 HAVE BEEN DELETED l
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i HOPE CREEK 3/4 3-92 Amendment No.121
[:
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i 3/4.11 RADIOACTIVE EFFLUENTS
'3/4.11.1 LIQUID EFFLUENTS 3.11.1.1 Deleted 3.11.1.2 Deleted 3.11.1.3 Deleted 1
HOPE CREEK 3/4 11-1 Amendment No. 121
RADIOACTIVE 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, excluding tritium and dissolved or entrained noble gases.
APPLICABILITY:
At all times.
ACTION:
With the quantity of radioactive material in any of a.
the above tanks 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 describe the events leading to this' condition in the next Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.
b.
The provisions of Specification 3.0.3 are not applicable.
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 representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
HOPE CREEK 3/4 11-2 Amendment No.121 t.
c RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS 3.11.2.1 Deleted 3.11.2.2 Deleted 3.11.2.3 Deleted 3.11.2.4 Deleted 3.11.2.5 Deleted 3.11.2.6 Deleted i
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HOPE CREEK 3/4 11-3 Amendment No.121 l
THIS PAGE INTENTIONALLY BLANK PAGES 3/4 11-5 THROUGH 3/4 11-16 HAVE BEEN DELETED
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l HOPE CREEK 3/4 11-4 Amendment No. 121
RADIOACTIVE EFFLUENTS
-3.11.2.8 Deleted
.3.11.3 Deleted-3.11.4 Deleted PAGES 3/4 11-19 THROUGH 3/4 11-20 HAVE BEEN DELETED l.
I HOPE CREEK 3/4 11-18 Amendment No.121 l
1
- 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 Deleted 3/4.12.2 Deleted 3/4.12.'3 Deleted' PAGES 3/4 12-2 THROUGH 3/4 12-14 HAVE BEEN DELETED HOPE CREEK 3/4 12-1 Amendment No.121
ADMINISTRATIVE CONTROLS 6.8.4.f Primary Containment Leakage Rate Testing Program A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as required by 10CFR50.54(o) and 10CFR50, Appendix J, Option B, as modified by approved exemptiens..
This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program", dated September 1995.
The peak calculated containment internal pressure for the design basis loss of coolant accident, P.,
is 48.1 psig.
The maximum allowable primary containment leakage rate, L.,
at P.,
shall be 0.5% of primary containment air weight per day.
Leakage Rate Acceptance Criteria are:
Primary containment leakage rate acceptance criterion is less a.
than or equal to 1.0 L,.
During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are less than or equal to 0.6 L for Type B and Type C tests and less than or equal to 0.75 L, for Type A tests; b.
Air lock testing acceptance criteria are:
1)
Overall air lock leakage rate is less than or equal to 0.05 L, when tested at greater than or equal to P.,
2)
Door seal leakage rate less than or equal to 5 scf per hour when the gap between the door seals is pressurized to greater than or equal to 10.0 psig.
The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.
The provisions of Specification 4.0.3 are applicable to t;.u TT'Itary Containment Leakage Rate Testing Program.
6.8.4.g.
Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBER (S) OF THE PUBLIC from radioactive effluents as low as reasonably achievable.
The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.
The program shall include the following elements:
HOPE CREEK 6-16b Amendment No.121
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)
- 1) Limitations on the operability of ladioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,
- 2) Limitations on the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, 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 ODCM,
- 4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50,
- 5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days,
- 6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50,
- 7) 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 Part 20, Appendix B, Table II, Column 1, i
I HOPE CREEK 6-16c Amendment No.121
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.8.4.g.
Radioactive Effluent Controls Program
- 8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, j
- 9) Limitations on the annual and quarterly doses to a MEMBER 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 the unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,
- 10) Limitations on venting and purging of the containment through the Reactor Building Ventilation System, Hardened Torus Vent, or the FRVS to maintain releases as low as reasonably achievable, and
.w
- 11) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
h.
Radiological Environmental Monitoring Program 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 highest potential exposure pathways, and (2) verification of the i
accuracy of the effluents monitoring program and modeling of the environmental exposure pathways.
The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
- 1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM,
- 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 l
- 3) Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy f
of the measurements of radioactive materials in environmental j
sample matrices are performed as part of the quality assurance program for environmental monitoring.
HOPE CREEK 6-16d Amendment No. 121
ADMINISTRATIVE CONTROLS g
inservice inspection, routine maintenance, special maintenance
[ describe maintenance), waste processing, and refueling). The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or self reading dosimeter measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole-body dose received from external sources should be assigned to specific major work functions; and b.
Documentation of all challenges to main steamline safety / relief valves.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 The Annual 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 summaries, 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 ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
l HOPE CREEK 6-18 Amendment No. 121 l
1 ADMINISTRATIVE CONTROLS 4
l' ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1.7 The Annual Radioactive Effluent Release Report cever..g the operation of the unit during the previous calendar year shall be submitted by May 1 of each year.
The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid wastes released from the unit.
The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP.and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
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C HOPE CREEK 6-19 Amendment No.121 l
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ADMINISTRATIVE CONTROLS 1
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-Document Control Desk, Washington, 7.C.
20555, with a copy to the UEhkr Administrator, Region 1, 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 i
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HOPE CREEK 6-20 Amendment No.121 l
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ADMINISTFGVrIVE CONTROLS RECORD RETENTION (Continued) h.
Records of annual physical inventory of all sealed..ource material of record.
6.10.3 The following-records shall be retained for the duration of the unit
{
Operating License:
I Records and drawing changes reflecting unit design modifications l
a.
made to systems and equipment described in the Final Safety Analysis Report.
b.
Record; of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories.
l Records of radiation exposure for all individuals entering c.
radiation control areas.
d.
Records of gaseuca and liquid radioactive material released to the environs.
e.
Records of transient or operational cycles for those unit components identified in Table 5.7.1-1.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the unit staff.
l h.
Records of inservice inspections performed pursuant to these Technical Specifications.
l i.
Records of quality assurance activities required by the Quality l
Assurance Program.
l 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 SORC meetings and activities of the Nuclear Review Board (and activities of its predecessor, the Offsite Safety Review (OSR) staff).
1.
Records of the snubber service life monitoring pursuant to Technical Specification 4.7.5.
I Records of analyses required by the radiological environmental m.
monitoring program which would permit evaluation of the accuracy of the analyses at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.
n.
Records of reviews performed for changes made to the OFFSITE DOSE CALCULATIONAL MANUAL and the PROCESS CONTROL PROGRAM.
1 HOPE CREEK 6-22 Amendment No. 121
7; ADMINISTRATIVE CONTROLS l
6.11 RADIATION PROTECTION PROGRAM 6.11.1 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.
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HOPE CREEK 6-23 Amendment No.121 t.
ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION APEA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203 (c) (2) of 10 CFR-Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr* shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP) * *. 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 radiation monitoring device which continuously indicates the a.
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 is ree -ived. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them.
c.
A radiation protection qualified individual (i.e.,
qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive centrol over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Radiation Protection Supervisor in the RWP.
6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of I
the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose greater than 1000 mrem
- shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Senior Nuclear Shift Supervisor on duty and/or the radiation protection supervision. Doors shall remain locked except during periods of access by personnel under an approved l
RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrem
- that are located within'large areas, such as the containment, where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted, and a flashing light shall be activated as a warnino device. In lieu of the stay time specification of the RWP, continuous surveillance direct or remote (such as use of closed circuit TV canst 0f7','may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.
- Measurement made at 18 inches from source of radioactivity.
- Radiation protection personnel or personnel escorted by radiation
-protection personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.
HOPE CREEK 6-24 Junendment No. 121
p ADMINISTRATIVE-CONTROLS L
6.13 PROCESS CONTROL PROGRAM (PCP) l l
Changes to the PCP:
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a.
Shall be documented and records of reviews performed shall be l
retained as required by' Specification o.10.3.n.
This documentation shall contain:
(1)
Sufficient information'to support the change together with l
the appropriate analyses or evaluations justifying the changes (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 applicable regulations.
b.
Shall become effective after review and acccptance by the SORC and the approval of the Plant General Manager.
6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) l Changes to the ODCM:
I a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3 This documentation shall contatn:
- 1) Sufficient information to support the change together with the l
appropriate analyses or evaluations justifying the changes (s)
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- 2) A de+ *mination that the change will maintain the level of radioas
- effluent control required by 10 CFR 20.106, 40 CFR Part 1s0, 10 CFR 50'36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
b.
Shall become effective after review and acceptance by the SORC and the approval of the Plant General Manager.
l-Shall be submitted t'o the Commission in the form of a complete, c.
legible copy of the entire ODCM as a part of or ccncurrent with the Annual Radioactive Effluent Release 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 pages, clearly indicating the area of the page that was changed, and r!.all indicate the ' ate (e.g., month / year) the change was implemented.
6.15 Deleted HOPE CREEK 6-25 Amendment No.121 m
INSTRUMENTATION BASES 1
MONITORING INSTRUMENTATION (Continued) 3/4.3.7.8 The material originally contained in Section 3/4.3.7.8 was deleted with the issuance of the Full Pawer license.
However, to maintain numerical continuity between the succeeding sections and existing station procedural references to those Technical Specifications Sections 3/4.3.7.8 has been
.1 intentionally left blank.
3/4.3.7.9 LOOSE-PART DETECTION SYSTEM THIS SECTION DELETED 3/4.3.7.10 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Deleted i
3/4.3.7.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INS *RUMENTATION l
Deleted l
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1 HOPE CREEK B 3/4 3-6 Amendment No.121
3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 Deleted
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3/4.11.1.2 Deleted 3/4.11.1.3 Deleted 3/4.11.1.4 LIQUID HOLDUP TANKS The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System.
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 l
UNRESTRICTED AREA.
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 Deleted 3/4.11.2.2 Deleted l
3/4.11.2.3 Deleted 1
3/4.11.2.4 Deleted 3/4.11.2.5 Deleted 3/4.11.2.6 Deleted I
l 3/4.11.2.7 MAIN CONDENSER l
Restricting the gross radioaativity 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 to the environment without treatment.
This specification implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.
HOPE CREEK B 3/4 11-1 Amendment No.121
RADIOACTIVE EFFLUENTS BASES 3/4.11.2.8 Deleted 3/4.11.3 Deleted 3/4.11.4 Deleted PAGES B 3/4 11-3 THROUGH B 3/4 11-6 HAVE BEEN DELETED i
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HOPE CREEK B 3/4 11-2 Amenciment No. 121
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES l
'3/4.12.1 Deleted 1
3/4.12.2 Deleted 3/4.12.3 Deleted PAGE B 3/4 12-2 HAS BEEN DELETED 1
l HOPE CREEK B 3/4 12-1 Amendment No.121
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