ML20035B894
| ML20035B894 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/25/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035B895 | List: |
| References | |
| NUDOCS 9304050260 | |
| Download: ML20035B894 (17) | |
Text
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.7 3,qf[ 1g UNITED STATES e
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NUCLEAR REGULATORY COMMISSION o
WASHINGTON. D.C. 20566 -
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SOUTHFRN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA DOCKET NO. 50-361 SAN ON0FRE NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE P
Amendment No.102 License No. NPF-10 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern California Edison Company, et al. (SCE or the licensee) dated November.18,1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulatior.s set forth in 10 CFR Chapter I; B.
The faci.ity 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.
9304050260 930325 PDR ADOCK 0500 1
P
. 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-10 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.102, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and must be fully implemented no later than 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
$.1Mbh h-Q Theodore R. Quay, Director.
Project Directorate V Division of Reactor Projects III/IV/V
'i Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 23, 1993 v
P I
ATTACHMENT TO LICENSE AMENDMENT l
AMENDMENT NO.102TO FACILITY OPERATING LICENSE NO. NPF-10 l
DOCKET NO. 50-361 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal-lines indicating the areas of change. The corresponding overleaf pages are also provided to ma'ntain document 'c tmpleteness.
REMOVE INSERT XVII XVII 6-17 6-17.
6-24 6-24
INDEX ADMINISTRATIVE CONTROLS SECTION EAGE AUTHORITY........................... 6-12 RECORDS 6-12 6.6 REPORTABLE OCCURRENCE ACTION................... 6-13 6.7 SAFETY LIMIT VIOLATION......................
6-13 6.8 PROCEDURES AND PROGRAMS 6-13 6.9 REPORTING RE0VIREMENTS 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES...........
6-15b STARTUP REPORT 6-15b ANNUAL REPORTS 6-16 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6-17 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6-17_
l h0NiHLY 0PERATING REPORT 6-17 REPORTABLE OCCURRENCES 6-18 PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP........... 6-18 THIRTY DAY WRITTEN REPORTS 6-20 HAZARDOUS CARGO TRAFFIC REPORT 6-20 6.9.2 SPECIAL REPORTS 6-20 6.10 RECORD RETENTION.........................
6-20 t
6.11 RADIATION PROTECTION PROGRAM...................
6-22 6.12 HIGH RADIATION AREA 6-22 6.13 PROCESS CONTROL PROGRAM (PCP) 6-23 6.14 0FFSITE DOSE CALCULATION MANUAL 6-24 i
6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS --DELETED i
l SAN ONOFRE-UNIT 2 XVII AMENDMENT NO.4GL,102 m
INDEX LIST OF TABLES TABLE PAGE 1.1 OPERATIONAL M0 DES.........................................
1-7 1.2 FREQUENCY N0TATION........................................
1-8 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS...
2-3 2.2-2 CORE PROTECTION CALCULATOR ADDRESSABLE CONSTANTS..........
2-5 3.1-1 CEA DROP TIME LIMIT5......................................
3/4 1-20a 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION........................
3/4 3-3 i
3.3-2 REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES.........
3/4 3-8 4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS........
3/4 3-10 3.3-3 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION............................................
3/4 3-14 3.3-4 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUE5...............................................
3/4 3-22 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIME5.................
3/4 3-27 4.3-2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS.................................
3/4 3-31 3.3-6 RADIATION MONITORING ALARM INSTRUMENTATION................
3/4/3-35 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..............................................
3/4/3-38 3.3-7 SEISMIC MONITORING INSTRUMENTATION........................
3/4 3-43 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.................................
3/4 3-44 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION...'..............
3/4 3-46 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..............................................
3/4 3-47 3.3-9 REMOTE SHUTDOWN MONITORING INSTRUMENTATION................
3/4 3-49 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..............................................
3/4 3-50 SAN ONOFRE-UNIT 2 XVIII AMENDMENT NO. 83
ADMINISTRATIVE CONTROLS 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 i
before May 1 of each year. The report shall include summaries, interpreta-tions, 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) Sec-tions IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
i 6.9.1.7 DELETED ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
- 6.9.1.8 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted before May I of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste 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.
6.9.1.9 DELETED MONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the safety valves, shall be j
submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.
Any changes to the OFFSITE DOSE CALCULATION MANUAL shall be submitted with the Monthly Operating Report within 90 days in which the change (s) was made effec-tive.
In addition, a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted in accordance with 6.5.2.
- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
r SAN ONOFRE-UNIT 2 6-17 AMENDMENT N0.-63,102 L
h 1
ADMINISTRATIVE-CONTROLS:
i 1
REPORTABLE OCCURRENCES I
6.9.1.11 Th'e REPORTABLE OCCURRENCES of-Specifications 6.9.1.12 and 6.9.1.13-below,' including corrective actions and measures.to prevent recurrence, shall be reported to the NRC.
Supplemental reports may be _ required to fully describe final resolution of occurrence.
In case of corrected or supplemental reports,'a licensee event' report shall be completed and reference shall be-1
.made to the original report date.
PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP b
6.9.1.12 The types of events listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram,.or facsimile transmission to the NRC Regional Administrator, or his designate no -later than the first i
working day ~following the event, with a written followup report within 14 days.
The written followup report shall include,-as a minimum,-a completed copy of a licensee event report' form.
Information provided on the licensee event report form shall be. supplemented, as needed,'by additional narrative i
material to provide complete explanation of the circumstances surrounding the i
event.
I Failure of the reactor protection system or_ other systems subject to-a.
limiting safety system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint i
specified as the limiting safety system' setting in the technical
{
specifications or failure to complete'the required protective function.
,t i
b.
Operation of the unit or affected systems when any parameter or.
operation subject'to a limiting condition for operation is-less-conservative than the least conservative aspect of the Limiting:
Condition for Operation established in the Technical Specifications, j
Abnormal degradation discovered in_ fuel _ cladding, reactor-coolant c.
i pressure boundary, or primary containment.
t i
l SAN ONOFRE-UNIT 2 6-18 AMENDMENT NO. 63
ADMINISTRATIVE CONTROLS An individual qualified in radiation protection procedures who is c.
equipped with a radiation dose rate monitoring device who is responsible for providing positive control over the-activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Exposure Permit.
6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 2000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or health physics supervision.
Doors shall remain locked except during periods of access by personnel under an-approved REP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individua'is in that area.
For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem" that are located within large areas, such as PWR 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 warning device.
In lieu of the stay time specification of the REP direct or remote (such as use of closed circuit TV cameras) continuous surve,illance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.
6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.#
6.13.2 Licensee initiated. changes to the PCP:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2n.
Sufficient information to support the change together with the a.
appropriate analyses or evaluations justifying the change (s);
b.
A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Fed:.ral, State, or other applicable regulations.
Documentation of the fact that the change has*been reviewed and c.
found acceptable pursuant to 6.5.2.
2.
Shall become effective upon review and acceptance pursuant to 6.5.2.
" Measurement made at 18" from source of radioactivity.
- The PCP shall be submitted and approved prior to shipment of " wet" solid radioactive waste.
l i
i SAN ONOFRE-UNIT 2 6-23 AMENDMENT NO. 83
ADMINISTRATIVE CONTROLS 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Comission prior.to implementation.
6.14.2 Licensee initiated changes to.the ODCM:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2n.-
a.
Sufficient information to support the change'together with the appropriate analyses or evaluations-justifying the change (s);-
b.
A determination that the change will maintain the level of.
radioactive effluent control required by 10 CFR 20.106,'40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and i'
not adverself impact the accuracy or reliability of _ effluent,
-l dose, or setpoint calculations.
l c.
Documentation of the' fact that the change has been reviewed and I
found acceptable pursuant to 6.5.2.
2.
Shall become effective upon review and acceptance-pursuant to 6.5.2.
3.
Shall be submitted to the Commission in the form of a complete, legible copy of-the entire ODCM as a part of or concurrent with the i
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, i
clearly indicating the area of the page that was changed, and shall-indicate the date (e.g., month / year) the change was implemented.
i si l
I 1
SAN ONOFRE-UNIT 2 6-24 AMENDMENT NO. 6,102
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UNITED STATES.
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NUCLEAR REGULATORY COMMISSION-i; WASHINGTON, D.C. 20566 0
4,.... 9 i
SOUTHERN CALIFORNIA EDISON COMPANY
'?
SAN DIEGO GAS AND ELECTRIC COMPANY.
.1 THE CITY OF RIVERSIDE. CALIFORNIA i
THE CITY OF ANAHEIM.' CALIFORNIA "f
DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment'No. 91..
License No. NPF-15 1.
The Nuclear Regulatory Commission (the Commission) has found that:
j A.
The application for amendment by Southern California. Edison Company, et al. -(SCE or_ the licensee). dated November 18, 1992,.
I complies with the standards and requirements of the Atomic: Energy Act of 1954, as amended (the Act), and the Commission's
,i regulations setL 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 l
conducted in compliance with the Commission's regulations; 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; 1
and
./
l 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.
1 P
e r
..,y
. 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No._NPF-15 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. 91
, are hereby incorporated in'the license. Southern California Edison Company shall operate the facility in accordance with the. Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and must be fully implemented no later than 30 days from the date of issuance.
TOR THE NUCLEAR REGULATORY COMMISSION h59 Theodore R. Quay, Director Project Directorate V-Division of Reactor Projects III/IV/V Office of Nuclear' Reactor Regulation
Attachment:
Changes to the Technical i
Specifications Date of Issuance:
March 23, 1993
t I
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 91 TO FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT XVI XVI 6-20 6-20 6-26 6-26
?
i i
l l
t
t-
~
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY...............................................
6-1.
6.2 ORGANIZATION 6.2.1 0FFSITE.................................................
6-1 6.2.2 UNIT 5TAFF...............................................
6-1 6.2.3 INDEPENDENT SAFETY ENGINEERING GR0VP....................
6-7 6.2.4 SHIFT TECHNICAL ADVI50R.................................
6-7 6.3 UNIT STAFF QUALIFICATIONS....................................
6-7
)
i 6;3 TRAINING.....................................................
6-8 t
6.5 REVIEW AND AUDIT i
6.5.1 ONSITE REVIEW COMMITTEE FUNCTION.............................................
6-8 COMP 05ITION......................
6-8 ALTERNATES...........................................
6-8 MEETING FREQUENCY....................................
6-9 QU0RUM.....-..........................................
6-9 RESPONSIBILITIES.....................................
6-9 AUTHORITY............................................
6-9 REC 0RDS..............................................
6-10
[
6.5.2 TECHNICAL REVIEW AND CONTR0L............................
6-10 i
6.5.3 NUCLEAR SAFETY GROUP FUNCTION.............................................
6-11 COMP 051 TION..........................................
6-12 CONSULTANTS..........................................
6-12 REVIEW...............................................
6-12 AUDIT5................................................
6-13 SAN ONOFRE-UNIT 3 XV
t INDEX ADMINISTRATIVE CONTROLS SECTION E.A_G.f i
AUTHORITY 6-13 RECORDS 6-13 6.6 REPORTABLE OCCURRENCE ACTION...................
6-14 6.7 SAFETY LIMIT VIOLATION......................
6-14 6.8 PROCEDURES AND PROGRAMS 6-14 i
6.9 REPORTING RE0VIREMENTS 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES............ 6-18 STARTUP REPORTS 6-18 ANNUAL REPORTS........................
6-19 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT......
6-20 ANNUAL RADI0 ACTIVE EFFLUEN1 RELEASE REPORT..........
6-20 l
MONTHLY OPERATING REPORT...................
6-20 REPORTABLE OCCURRENCES....................
6-21 PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6-21 THIRTY DAY WRITTEN REPORTS..................
6-22 HAZARD 0US CARGO TRAFFIC REPORT................
6-23 6.9.2 SPECIAL REPORTS 6-23 6.10 RECORD RETENTION.........................
6-23 6.11 RADIATION PROTECTION PROGRAM...................
6-24 6.12 HIGH RADIATION AREA 6-24 6.13 PROCESS CONTROL PROGRAM (PCP) 6-26 6.14 0FFSITE DOSE CALCULATION MANUAL 6-16 6.15 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS -- DELETED t
I SAN ONOFRE - UNIT 3 XVI AMENDMENT NO. -M, 91
ADMINISTRATIVE CONTROLS 48 nours prior to the first sample in which the limit was exceeded; (4)-Graph of the 1-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the spe-cific activity of the primary coolant exceeded the radiotodine limit.
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 I of each year. The report shall include summaries, interpre-tations, and analysis of trends of the.results of the Radiological Environ-mental 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, ar.d IV.C of Appendix i to 10 CFR Part 50.
6.9.1.7 -- DELETED ANNUAL PADI0 ACTIVE EFFLUENT RELEASE REPORT
- 6.9.1.8 The Annual Radioactive Effluent Release 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 a summary of the quantities of radioactive liquid and gaseous effluents and solid waste 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 1 to 10 CFR Part 50.
6.9.1.9 -- DELETED MONTHLY OPERATING REPORT 6.9.1.10 Routine. reports of operating statistics and shutdown experience, including documentation of all challenges to the safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.
i Any changes to the 0FFSITE DOSE CALCULATION MANUAL shall be submitted with the Mcnthly Operating Report within 90 days in which the change (s) was made effec-tive.
In addition', a report of any major changes to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted in accordance with 6.5.2.
- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
3 i
SAN ONOFRE-UNIT 3 6-20 AMENDMENT NO. +3; 91
-0 ADMINISTRATIVE CONTROLS REPORTABLE OCCURRENCES 6.9.1.11 The REPORTABLE OCCURRENCES of Specifications 6.9.1.12 and 6.9.1.13 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental re describe final resolution of occurrence. ports may be required to fully
. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.
PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.12 The types of events listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Regional Administrator of the Regional Office or his designate no later than the first working day following the event, with a written followup report-within 14 days.
The written followup report shall include, as a minimum, a completed copy of a licensee event report fo mi.
Information provided on the licensee event report form shall be supplemented, as needed, by additional narratis. material to provide complete explanation of the circumstances surrounding the event.
Failure of the reactor protection system or other systems subject to a.
limiting safety system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective
- function, b.
Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the Limiting Condition for Operation established in the Technical Specifications.
Abnormal degradation discovered in fuel cladding, reactor coolant c.
pressure boundary, or prime'y containment.
Reactivity anomalies involving disagreement with the predicted value d.
of reactivity balance under steady-state conditions during power operation greater than or equal to 1% Ak/k; a calculated reactivity
~;
balance indicating a SHUTDOWN MARGIN less conservative than specified in the Technical Specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of mare than 0.5% ak/k; or occurrence of any unplanned criticality.
Failure or malfunction of one or more components which prevents or e.
could prevent, by itself, the fulfillment of the functional require-ments of system (s) used to cope with accidents analyzed in the SAR.
f.
Personnel error or procedural inadequacy which prevents or could i
prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accidents analyzed in the SAR.
SAN ONOFRE-UNIT 3 6-21 AMENDMENT NO. 73
ADMINISTRATIVE CONTROLS-6.13.1 The PCP shall be approved by the Commission prior to implementation.f 6.13.2 Licensee initiated changes to the PCP:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2n.
a.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s);
b.
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.
c.
Documentation of the fact that the change has been reviewed and found acceptable pursuant to 6.5.2.
2.
Shall become effective upon review and acceptance pursuant to 6.5.2.
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 te the ODCM:
1.
Shall be documented a:.d records of reviews performed shall be t
retained as required by Specification 6.10.2n.
a.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changc(s);
b.
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 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.
c.
Documentation of the fact that the change has been reviewed and found acceptable pursuant to 6.5.2.
2.
Shall become effective upon review and acceptance pursuant to 6.5.2.
3.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the l
report in which any change to the ODCM was made.
Each change shall t
be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
6.15 MAJOR CHANGES TO RADIDACTIVE WASTE TREATMENT SYSTEMS -- DELETED
- The PCP shall be submitted and approved prior to shipment of " wet" solid radioactive waste.
SAN ONOFRE-UNIT 3 6-26 AMENDMENT NO. M 91
,