ML20074A984
| ML20074A984 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/29/1983 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20074A985 | List: |
| References | |
| TAC-51426, TAC-51427, TAC-51428, TAC-51429, NUDOCS 8305170233 | |
| Download: ML20074A984 (10) | |
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UNITED STATES 8'
N NUCLEAR REGULATORY COMMISSION
,E WASHINGTON, D. C. 20556
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SOUTHERN CALIFORNIA EDIS0N COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 17 License No. NPF-10 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment for the San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and The City of Anaheim, California (licenseas) dated February 24, 1983, as supplemented by letters dated March 4,1983, April 14,1983, and April 19, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will cperate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; C.
There is reas_onable assurance (1) that the activities ' authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; 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.
8305170233 830504 PDR ADOCK 05000361 P
3
.2.
Accordingly, the license is hereby amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and changing paragraphs 2.C(2) and 2.C(19)1 of Facility Operating License No. NPF-10 to read as follows:
(2). Technical Specifications The Technical-Specifications contained in Appendix A and the Environ-
~
mental Protection Plan contained in Appendix B, as revised through Amendment No.17, are hereby incorporated in the license. SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection. Plan.
(19)i. Post Accident Sampling System (NUREG-0737 Item II.B.3) 1.
By June'1,1983, SCE shall substantially complete all of the PASS procedures identified in Enclosure 3 of the SCE letter of April 14, 1983.
2.
Prior to September 1,1983, SCE shall maintain in effect all compensatory measures other than the PASS. that are identified in the SCE letter of April 14, 1983,- that are not already covered by Technical Specification surveillance requirements.
By September 1,1983, the PASS shall be operable and the post 3..
accident sampling program shall be implemented.
4.
Until September 1,1983, SCE shall provide monthly progress reports on PASS testing, surveillance, maintenance and modifications, and' operator-training.
3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION MM.
DarrellG.E{icensing senhut, Director Division of L Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications l
Date of Issuance: APR 2 9 E63 l
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4.
. APR 2 91983 3-ATTACHMENT TO LICENSE AMENDMENT N0. 17~
FACILITY OPERATING LICENSE NO.'NPF-10 DOCKET NO. 50-361 2
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.- The revised pages are identified by Amen &ient number and contain vertical lines indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages.
Amendment Page Overleaf Page 6-15 6-16 i
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AO'41GISTRATIVE CONTROLS-b.
.In-Plant Radiation lionitorina A program. which will ensure the capability to accurately datermine the airborne iodine concentration in vital areas under accident conditions.
This program shall include the followingi (i) Training of personnel, (ii)
Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis equipment.
c.
Secondary Water Chemistry A program for monitoring of secondary water chemistry.to inhibit' steam generator tube degradation.
This program shall include:
Identification of a sampling schedule for the critical variables (i)_ and control points for these variables, (ii)
Identification of the procedures used to measure the values of the critical variables, (iii)
Identification of process sampling points, including monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, (iv)
Procedures for the recording and management of data, (v)
Procedures defining corrective actions for all off-control point chemistry conditions, and (vi) A procedure identifying (a) the authority responsible'for the interpretation of the data, and (b) the sequence'and timing of administrative events required to initiate corrective action.
d.
Pcst-Accident Sampling A' program *'which will ensure the capability to obtain and analyze reactor coolant, radioac.tive iodines and particulates in plant gaseous effiuents, and c'ontainment atmosphere samples under accident conditions.
The program
- shall include the training of personnel, the procedures.for sampling and analysis and the provisions for maintenance of sampling and analysis equipment.
6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 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 Regional Administrqtor unless otherwise noted.
- tiot required to be implemented until September 1, 1983.
SAN ONOFRE-UNIT 2 6-15 AMENINENT NO.17 L_ _
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ADMINISTRATIVE CONTROLS II.
, STARTUP REPORT t
6.9.1.1 A-summary report of plaat startup and power escalation testing shall be submitted following (1) receipt of an operating licens'e, (2) amendment to the license involving a planned increase in power leyel..(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 startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a compari-son of these values with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be i
described.
Any additional specific details required in license conditions ~
based on other commitments shall be included in this report.
6.9.1.~3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or r
commencement 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 commercial operation)' supplementary reports shall be submitted at least every three months until all three events have
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been compl.eted.
L
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l' ANNUAL REPORfS*
6.9.1.4 Annual reports covering the activities of the. unit as described below
.for the previous calendar year shall be submitted prior to March 1 of.each year. -The initial report shall be' submitted prior to March 1 of the year fo11cking initial criticality.
l 6.9.1.5 Reperts required on an annual basis.shall inclu'de a tabulation on an i
annual basis of the number of_ station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated manrem exposure according to work and job functi6ns,** e.g., reactor operations and' surveillance, 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, TLD, or film badge measurements.
Small' exposures totalling less than 20 percent of the individual total dose need not be accounted for.
In the aggregate, at i
least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
a 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.
AA This tabulation supplements the requirements of S20.407 of 10 CFR Part 20.
SAN ONCFRE-UNIT 2 6-16 L
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION g
E WASHINGTON, D. C. 20666
%,.....,4 SOUTHERN CALIFORNIA EDIS0N COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY.OF ANAHEIM, CALIFORNIA DOCKET N0. 50-362 SAN ON0FRE. NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 5 License No. NPF-15 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment for the San Onofre Nuclear Generating Station, Unit 3 (the facility) filed by the Scuthern California Edison Company on behalf of itself and San Diego Gas and Electric Company, The' City.of Riverside and The City of Anaheim, California (licensees) dated February 24, 1983, as supplemented by letters dated -
March 4, 1983, April 14, 1983, and April 19,1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended.
(the Act) 3nd the Commissions regulations as set forth in 10 CFR.
Chapter I; B.
The facility will cperate in conformity with the application, as amended, the provisions'of the Act, and the regulations of the-Commission;' '
C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical' to the common defense and security or to the health and safety of the public; 4
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.
L..
~
. 2.
Accordingly, the license is hereby amended by-changes to the Technical
. Specifications' as indicated in the attachment to this license amendment, and changing paragraphs 2.C(2) and 2.C(17)d of Facility Operating License
~No. NPF-15 to read as'follows:
(2) Technical' Specifications The Technical Specifications contained in' Appendix A and the Environ-mental Protection Plan contained in Appendix B, as revised through Amendment No. 5, are hereby incorporated in the license. SCE shall operate the facility in accordance with the Technical Specifications-and the Environmental Protection Plan..
(17)d Post Accident Sampling System (NUREG-0737 Item II.B.3)
.By June 1,1983,-SCE shall.substantially complete all of th'e 1.
PASS procedures identified in Enclosure 3 of the SCE letter of April 14, 1983.
2.. Prior to September 1,1983, SCE shall maintain in effect all compensatory measures other than the PASS that are -identified in the SCE letter'of April ~14, 1983, that are not already covered by Technical Specification surveillance requirements.
3.
By September 1,1983, the PASS shall be operable and the post accident sampling program shall be implemented.
4.
Until September 1, ~1983, SCE shall provide monthly progress reports on PASS testing, sreveillance, maintenance and
~
mo,di /ications, and operator training.
4 3.
This amendment is effective as of the'date of issuance.
FOR THE' NUCLEAR REGULATORY COMMISSION tlh.-
af Darrell G. Eisenhut, Director Division ~of Licensing
. Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: APR 2 91983 u
s APR 2 01983 ~
, ATTACHMENT TO LICENSE AMENDMENT NO. 5 FACILIT'Y OPERATING LICENSE NO. NPF-15'
. DOCKET NO. 50-362 Replace the following pages of the. Appendix A Technical Specifications'with the enclosed pages. The revised pages are identified by Amendment number and'contain vertical lines indicating the area of change.. Also to-be replaced are the following overleaf pages to the amended pages.
Amendment Page Overleaf Page.
6-16 6-15 L.
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ADMINISTRATIVE CONTROLS-g.
PROCESS CONTROL PROGRAM implementation."
h.
OFFSITE DOSE CALCULATION MANUAL implementation.-
1.
Quality Assurance Program for effluent and environmental-monitoring, using the guidance in Regulatory Guide 4.15 Rev.1, February 1979.
j.
Modification of Core. Protection Calculator (CPC) Addressable
- Consta,nts.
NOTE: Modification to the CPC addressable constants based on information obtained through the Plant Computer - CPC data link shall not be made without c
prior-approval of the Onsite Review Committee.
6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be approved by the Station Manager; or by (1) the Deputy Station Manager, (2) the Manager, Operations, (3) the Manager, Maintenance, (4) the Manager, Technical, or-(5) the Manager, Health Physics as previously designated by the Station Manager; prior to implementation and shall be reviewed periodically as set forth in administrative procedures.
6.8.3. Temporary changes to procedures of 6.8.1 above may be made provided:
1-The intent of the original procedure is not, altered.
a.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on
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the unit affected.
The change is documented, reviewed and approved by the Station c.
Manager; or by (1) the Deputy Station Manager, (2) the Manager, L
Operations, (3) the Manager, Maintenance,-(4) the Manager, Technical, or (5) the Manager, Health Physics as previously designated by the Station Manager; within 14 days of implementation.
6.8.4 The following programs shall be established, implemented, and maintained:
a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive-fluids during a serious transient or accident to as low as practical levels.
The systems include the high pressure safety injection recirculation, the shutdown cooling system, the reactor coolant sampling system (post-accident sampling piping only), the containment spray system, i
the radioactive waste gas system (post-accident sampling return piping only) and the liquid radwaste system (post-accident sampling return piping only). The program shall include the following:
(i)
Preventive maintenance and periodic visual inspection requirements, and
-(ii) Integrated leak test requirements for each system at refueling cycle intervals or less.
- See Specification 6.13.1 1
SAN ONOFRE-UNIT 3 6-15 I
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In-Plant Radiation Monitoring
~ A program which will ensure the capability to accurately dotarmine the airborne iodine concentration in vital areas utide r accident conditions'..Th'is program shall include the following:
(i) Training of-personnel, (ii)
Procedures for monitoring, and (iii). Provisions for maintenance of sampling and analysis equipment.
c.
Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam. generator tube degradation.
This program shall include:
(i)
Identificatio'n of a sampling schedule for the critical variables.
and control points for these variables, (ii)
Identification of the procedures used to' measure the values 'of the critical ^ variables, (iii)
Identification of process sampling points, including monitoring-t.he' discharge ~of the condensate pumps for evidence of condenser-in-leakage, (iv)
Procedures for the recording and management of' data, (v) Procedures defining corrective actions for all off-control-point chemistry conditions, and-(vi) A procedure identifying (a).the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.
d.
Post-Accident Sampling A program
- which will ensure the capability to obtain and analyze
-reactor coolant, radioactive iodine.s and particulates.in plant gaceous' effluents, and containment atmosphere samples under accident ~
vonditions.
The program
- shall include the training of personnel, w.
thi. procedures for sampling and analysis and the provisions for maintenance of sampling and' analysis equipment.
6.9 REPORTING FEQUIREMENTS ROUTINE REPORTS AND REPORTABLE CCCURRENCES 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 Regional Administrator unless otherwise noted.
' Not required to be implemented until September 1, 1983.
-SAN ONOFRE-UNIT 3'
~6-16 AMENDENT NO. 5
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