ML20059F153
| ML20059F153 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 01/06/1994 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059F158 | List: |
| References | |
| NUDOCS 9401130168 | |
| Download: ML20059F153 (12) | |
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UNITED STATES
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WASHINGTON. D.C. 20555-0001 NUCLEAR REGULATORY COMMISSION PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-275 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 License No. DPR-80 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (the licensee) dated July 7, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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; 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 satisfied.
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. DPR-80 is hereby amended to read as follows:
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9401130168 940106 l
PDR ADOCK 05000275 P
i
, (2)
Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised i
through Amendment No. 85, are hereby incorporated in the license.
Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION dw 0
^^ty Theodore R. Quay, Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 6, 1994 t
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 205$MKc1 PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 DIABLO CANYON NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. DPR-82 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (the licensee) dated July 7, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Ccomission's regulations set forth in 10 CFR Chapter 1;
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 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; 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 satisfied.
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. DPR-82 is hereby amended to read as follows:
. (2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 84, are hereby incorporated in the license.
Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION hitcb w h oy Theodore R. Quay, Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 6, 1994 i
i i
ATTACHMENT TO LICENSE AMENDMENTS MENDMENT NO. 85 TO FACILITY OPERATING LI' CENSE NO. DPR-80 AND AMENDMENT NO. 84 TO' FACILITY OPERATING LICENSE NO. DPR-82 i
DOCKET NOS. 50-275 AND 50-323 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by i
the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages are also included, as appropriate.
1 REMOVE INSERT
'I Page 5 of 6 Page 5 of 6 B 3/4 11-1 B 3/4 11-1 6-15a 6-15a 6-15b 6-15b 6-15c j
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APPENDIX A TO LICENSE N05. DPR-80 AND DPR-82 DIABLO CANYON NUCLEAR POWER PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS (NUREG-1151)
LIST OF EFFECTIVE PAGES Pace No.
Amendment No.
Pace No.
Amendment No.
B 3/4 3-5 67/66 B 3/4 10-1 B 3/4 4-1 B 3/4 10-2 B 3/4 4-2 27/26 8 3/4 11-1 85/84 B 3/4 4-2a 27/26 B 3/4 12-1 B 3/4 4-3 Title Page B 3/4 4-4 5-1 B 3/4 4-5 18/17 5-2 B 3/4 4-6 5-3 B 3/4 4-7 54/53 5-4 24/23 8 3/4 4-8 54/53 5-5 13/11 B 3/4 4-9 54/53 5-6 8/6 B 3/4 4-10 54/53 5-7 B 3/4 4-11 54/53 6-1 75/74 B 3/4 4-12 54/53 6-2 29/28 B 3/4 4-13 54/53 6-3 29/28 B 3/4 4-14 6-4 59/58 B 3/4 4-15 6-5 75/74 8 3/4 4-16 6-6 59/58 B 3/4 5-1 6-7 43/42 B 3/4 5-2 65/64 ***
6-7a 41/40 1
8 3/4 5-2a 72/71 6-8 75/74 B 3/4 5-3 14/13 6-9 75/74 8 3/4 6-1 65/64 ***
6-10 68/67 B 3/4 6-2 65/64 ***
6-11 68/67 8 3/4 6-3 14/13 6-12 68/67 B 3/4 6-4 73/72 6-13 75/74 B 3/4 7-1 6-14 41/40 B 3/4 7-2 75/74 6-15 B 3/4 7-2a 75/74 6-15a 85/84 B 3/4 7-2b 77/76 6-15b 85/84 B 3/4 7-2c 77/76 6-15c 85/84 8 3/4 7-3 6-16 43/42 B 3/4 7-4 66/65 #
6-17 67/66 B 3/4 7-5 66/65 #
6-18 78/77 B 3/4 7-6 75/74 6-19 71/70 B 3/4 7-7 75/74 6-20 68/67 B 3/4 7-8 6-21 67/66 8 3/4 8-1 44/43 6-22 67/66 B 3/4 8-2 44/43 6-23 67/66 B 3/4 8-3 B 3/4 8-3a T4773 B 3/4 9-1 46/45 B 3/4 9-2 46/45 B 3/4 9-3 70/69 DIABLO CANYON - UNITS 1 1 2 PAGE 5 0F 6 Amendment Nos. 85 & E
BADI0ACTIVR EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 Relocated to RMCP.
3/4.11.1.2 Relocated to RMCP.
3/4.11.1.3 Relocated to RMCP.
3/4.11.1.4 LIOUID 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 tank's contents, the resulting concentrations would be less than the limits of 10 CFR 20.1001 - 20.2401, Appendix B. Table 2, Column 2, at l
l the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 Re1 coated to RMCP.
3/4.11.2.2 Relocated to RMCP.
3/4.11.2.3 Relocated to RMCP.
3/4.11.2.4 Relocated to RMCP.
3/4.11.2.5 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the GASE0US RADWASTE SYSTEM is maintained below the flanrnability limits of hydrogen and oxygen.
Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
I 3/4.11.2.6 GAS STORAGE TANKS The tanks included in this specification are those tanks for which the quantity of radioactivity contained is not limited directly or indirectly by another Technical Specification.
Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting whole body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.5 rem. This is consistent with Standard Review Plan 11.3, Branch Technical Position ETSB 11-5, " Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure," in NUREG-0800, July 1981.
3/4.11.3 Deleted 3/4.11.4 Deleted DIABLO CANYON - UNITS 1 & 2 B 3/4 11-1 Amendment Nos.85 & 84 l
,j A0k N 5ita*IVE CONTROLS PE :!?Ut!5 AND PRDGRAMS (Continued)
Se:onca y Water Chemistry c.
A program for sonitoring of secondary water chemistry to inhibit steam generator tube degradation.
This program shall include-1)
Identification of a sampling schedule for the critical variables and control points for these variables, 2)
Icentification of the procedures used to measure the values of the critical variables, 3)
Identification of process sampling points, including monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, 4)
Fre:ecsres for the recording and management of data.
5)
Procedures defining corrective actions for all off-control point chemistry conditions, and 6)
A p ocedu'e identifying:
(a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of ac-inistrative events required to initiate corrective action, c.
fe:ku: Method for Detectininc Sub:coline Marcin Reacter Coolant System subcooling r.argin.A prograe which incluce the following:
This program shall
- )
Training of personnel, and 2)
Procedures for monitoring.
Posta:cident Samplino e.
A program which will ensure the capability to obtain and analyze rea: tor coolant, radioactive fodines and particulates in plant gaseous of fluents, and containment atmosphere samples under actident conditions.
The program shall include the following:
1)
Training of personnel.
2)
Procedures for sampling and analysis, and 3)
Provisions for maintenance of sampling and analysis equipment.
DI ALD CANYON
- UNITS 1 & 2 6 15
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6)
Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appro-priate 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 comitment conforming to Appendix ! to 10 CFR Part 50, 7)
Limitations on the dose rate resulting from radioactive material released in gaseous effinents from the site to areas at or beyond the SITE BOUNDARY shall be limited to the following:
a.
For noble gases:
Less than or equal to a dose rate of 500 mrem /yr to the whole body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and b.
For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem /yr to any orp n.
8)
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR part 50, 9)
Limitations on the annual and quarterly doses to MEMBERS 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 each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and 10)
Limitations on the annual dose or dose comitment 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.
Radiolooical Environmental Monitorina Procram A program shall be provided to monitor the radiation and radio-nuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2 of the effluent monitoring program a)nd modeling of environmentalverific exposure pathways. The program shall (1) be contained in the RMCP, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
i 1
1)
Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ERMP, DIABLO CANYON - UNITS 1 & 2 6-15b Amendment Nos. 85 & 84
r a 8
A0vN5 RATIVE CONTROLS f.9 REPORTING REOUIREMENTS ROU**NE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the NRC in accordance with 10 CFR 50.4.
STARTUP REPORTS 6.9.1.1 A sumary report of plant startup and power escalation testing shall be submitted following:
(1)receiptofanoperatinglicense (2)amendmentto the license involving a planned increase in power level, (3), installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
6.9.1.2 The initial Startup Report shall address each of the startup tests identified in Chapter 14 of the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfac-tory operation shall also be described. Any additional specific details recuired in license conditions based on other commitments shall be included in this report. Subsequent Startup Reports shall address startup tests that are necessary to demonstrate acceptability of the change and/or modification.
E. 9.1. 3 Startup Reports shall be submitted within:
(1) 90 days following completion of the startup test program, (2) 90 days following resumption or comencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of comercial power operation), sup>1ementary reports shall be submitted at least every three renths until all tiree events have been completed.
ANNUAL REPORTS
- 6.9.1.4 Annual Reports covering the activities of the unit as described below during the previous calendar year shall be submitted prior to March 31 of'each year. The initial report shall be submitted prior to March 31 of the year following initial criticality.
Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility and other personnel (including contrac-tors) receiving exposures greater than 100 arem/yr and their associated man -
- A single submittal may be made for a multiple-unit plant. The submittal
.should combine those sections that are common to all units at the plant.
DIABLO CANYON - UNITS 1 & 2 6 16 Amendment Nos. 43 and 42 llll 1 6 9006
A;b N STErivf CONTRDL5 PE:"EDURES AN2 PRDGRAMS (Continued)
Se:enda y Water Chemistry c.
A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation.
This program shall faclude:
1)
Identification of a sampling schedule for the critical variables and control points for these variables, 2)
Identification of the procedures used to measure the values of the critical variables, 3)
Identification of process sampling points, including monitoring the discharge of the condensate pumps for evidence of condenser in-leakage.
4)
Fre:edures for the recording and management of data, 5)
Pro:edures defining corrective actions for all off-control pcint chemistry conditions, and 6)
A p*ocedure identifying:
(a) the authority responsible for the ac-inistrative events required to initiate corrective c.
Ee ku: Met 5cd for Deteerininc Subecelino Marcin A program which will ensure the capability to accurately monitor the Rea:ter Coolant System subcooling margin.
This program shall in:Tuce the following:
1 1)
Training of personnel, and 2)
Procedures for monitoring, Posta:cident Samplina e.
A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous of fluents, and cor.tainment atmosphere samples under actident conditions.
The program shall include the following:
i 1)
Training of personnel.
2)
Procedures for sampling and analysis, and 3)
Provisions for maintenance of sampling and analysis equipment.
D2 AB.O CANYON - UNITS 1 & 2 6-15
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) f.
Containment Polar and Turbine Buildina Cranes A program which will ensure that:
- 1) the position of the contain-I ment polar cranes precludes jet impingement from a postulated pipe rupture; and 2) the operation of the turbine building cranes is consistent with the restrictions associated with the current Hosgri seismic analysis of the turbine building. This program shall include the following:
1)
Training of personnel, and 2)
Procedures for the containment polar and turbine building cranes operation.
g.
Radioactive Effluent Controls Procram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the RMCP, (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:
1)
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance requirements and setpoint determination in accordance with the methodology in the ODCP, 2)
Limitations on the concentrations 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 20.1302 and with l
l the methodology and parameters in the ODCP, 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 each unit to UNRESTRICTED AREA 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 ODCP at least every 31 days, DIABLO CANYON - UNITS 1 & 2 6-15a Amendment Nos. 85 & 84 l
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ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6)
Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appro-priate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31 -day i
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 from the site to areas at or beyond the SITE BOUNDARY shall be limited to the following:
a.
For noble gases:
Less than or equal to a dose rate of 500 mrem /yr to the whole body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and b.
For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to a dose rate of 1500 mrem /yr to any organ.
8)
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY ccnforming to Appendix ! to 10 CFR part 50, 9)
Limitations on the annual and quarterly doses to MEMBERS OF 1HE 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 each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, and 10)
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.
Radioloaical Environmental Monitorina Procram A program shall be provided to monitor the radiation and radio-nuclides 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 accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the RMCP, (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 ERMP, DIABLO CANYON - UNITS 1 & 2 6-15b Amendment Hos. 85 & 84
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) h.
Radiolooical Environmental Monitorino Procram (Continued) 2)
A Land Use Census to ensure that changer in the use of areas at and beyond the SITE BOUNDARY are identif',ed and that modifications to the monitoring program are made if required by the results of this census, and f
3)
Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in the environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
L DIABLO CANYON - UNITS 1 & 2 6-15e Amendment Hos, 85 & 84
r s A**:N!STRATIVE CONTROLS E.9 REPORTING REQUIREMENTS ROU :NE REPORTS 6.9.1 In addition to the applicable reportinD requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the NRC in accordance with 10 CFR 50.4.
STARTUP REPORTS 6.9.1.1 A sumary report of plant startup and power escalation testing shall be submitted following:
(1)receiptofanoperatinglicense (2)arendmentto the license involving a planned increase in power level, (3), installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
E.9.1.2 The initial Startup Report shall address each of the startup tests identified in Chapter 14 of the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfac-tory operation shall also be described. Any additional specific details recuired in license conditions based on other comitments shall be included in this report. Subsequent Startup Reports shall address startup tests that are necessary to demonstrate acceptability of the change and/or modification.
6.9.1.3 Startup Reports shall be submitted within:
(1)90daysfollowing completion of the startup test program, (2) 90 days following resumption or i
comencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of comercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
ANNUAL REPORTS
- 6.9.1.4 Annual Reports covering the activities of the unit as described below during the previous calendar year shall be submitted prior to March 31 of'each year. The initial report shall be submitted prior to March 31 of the year following initial criticality.
Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility and other personnel (including contrac-tors) receiving exposures greater than 100 arem/yr and their associated man -
'A single submittal may be made for a multiple-unit p....c.
The submittal
.thould combine those sections that are comon to all units at the plant.
j DIABLO CANYON - UNITS 1 & 2 6-16 Amendment Nos. 43 and 42 JH' J * ?os"