ML20127B849
| ML20127B849 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/05/1993 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127B851 | List: |
| References | |
| NUDOCS 9301130163 | |
| Download: ML20127B849 (44) | |
Text
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'n UNITED STATES 3k i
NUCLEAR REGULATORY COMMISSION
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WA'sHINGTON. D C. 20%5 gv PUBllC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NQGLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No.139 License No. DPR-70 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated August 2, 1991, and supplemented by letter dated September 30, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.
There is reasonable assurance: (1) that the activities authorized by this amendment can be conWeted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:
9301130163 930105
- DR -ADOCK-0500 2
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. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.139, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
Also, the license is amended by replacing Paragraph 2.C.(5) on page 4 of facility Operating License DPR-70 with the following:*
(5) PSE&G shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report, and as approved in the NRC Safety Evaluation Report dated November 20, 1979, and in its supplements, subject to the following provision:
PSE&G may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
4.
This license amendment is effective as of its date of issuance and shall be-implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
[k%Iro.
h1d SU Charles L. Miller, Director Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i
Attachments:
1.
Page 4 of License DPR-70 2.
Changes to the Technical Specifications Date of Issuance:
January 5,1993
- Page 4 is attached, for convenience, for the composite license to reflect this change.
ATTACHMENT 1 TO LICENSE AMENDMENT NO.139 FACILITY OPERATING LICENSE NO. DRP-70 DOCKET NO. 50-272 Revise License DPR-70 as follows:
Remove Paae Insert Paae 4
4
i
. (1) Maximum Power level Public Service Electric and Gas Company is authorized to operate the facility at a steady state reactor core power level not in excess of 3338 megawatts (one hundred percent of rated core power).
Prior to attaining the one hundred percent power level, Public Service Electric and Gas Company shall complete the preoperational tests, startup tests and other items identified in Attachment I to this amended license in the sequence specified. is an integral part of this amended license.
(2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Deleted Per Amendment 22, 11-20-79 (4)
Less than four tooo Operation Public Service Electric and Gas Company shall not operate the reactor at power levels above P-7 (as defined in Table 3.3-1 of Specification 3.3.1.1 of Appendix A to this license) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation have been submitted by the licensees and approval for less than four loop operation at power levels above P-7 has been granted by the Commission by Amendment of this license.
(5)
PSE&G shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report, and as approved in the NRC Safety Evaluation Report dated November 20, 1979, and in its supplements, subject to the following provision:
PSE&G may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
Amendment No. 2 f,,Jr,139
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ATTACHMENT 2 TO LICENSE AMENQljfNT NO.110 FACILITY OPERATING LICENSf_NO. DPR-70 DOCKET NO.50-27R Revise Appendix A as follows:
Remove Paoes Insert Paaes Index IV Index IV Index VII Index VII Index XIV Index XIV 3/4 3-49 3/4 3-49 through 3/4 3-52 3/4 3-50 3/4 3-51 3/4 3-52 3/4 7-32 3/4 7-33 3/4 7-34 3/4 7-35 3/4 7-36 l
l 3/4 7-37 3/4 7-38 3/4 7-39 3/4 7-40 l
3/4 7-41 3/4 7-42 B 3/4 3-3 B 3-4 3-3 B 3/4 7-7 8 3-4 7-7 8 3/4 7-8 l:
2-ATTACHMENT 2 T0 llCENSE AMENDMENT NO. 139 FACIllTY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Paagi insert Paaes 6-2 6-2 6-7 6-7 6-24 6-24 6-25 6-25 6-26 6-26 6-27 6-27 6-28 6-28 6-29 6-29 6-30
_____m_
INDEX LIMITDC CCtIDITIQ1S FOR OPERATION At1D SURVEIIDJ1CE REQUIRDOES SECTIG1 FIGE J/4.2 IWER DISTRIDlJrIQi IJMITS 3/4.2.1 AXIAL FIUX DIFTERDICE 3/4 2-1 3/4.2.2 HEAT FIIJX IDF OIAtalEL FACIOR 3/4 2-5 3/4.2.3 NUCIEAR DTIHALEY FDP OIANNEL FACIOR 3/4 2-9 3/4.2.4 QUADRAlff EWER TILT RATIO 3/4 2-11 3/4.2.5 DUB PARAMETERS 3/4 2-13 s
3/4.3 INS'IRJMDTTATION 3/4.3.1 REACIOR TRIP SYSTD{ INSTRUMDITATION 3/4 3-1 3/4.3.2 DIGINEERED SAFEIY FENIURE ACIUATION SYSTD4 INSTRUMDTTATION 3/4 3-14 3/4.3.3 10NI'IORING INSIHJMDTTATION Radiation Monitoring Instrumntation 3/4 3-35 Movable Incore Detcctors 3/4 3-39 Seismic Instrumntation 3/4 3-40 Meteorological Instrumntation 3/4 3-43 Remote Shutdown Instru mntation 3/4 3-46 l
Accident Monitoring Instrumntation 3/4 3-53 Radioactive Liquid Effluent Monitoring Instrumntation 3/4 3-58 Radioactive Gascous Effluent Manitoring Instrumntation 3/4 3-64 3/4.3.4
'IURBINE OVERSPEED PROTECTION 3/4 3-70 SALD4 - UNIT 1 IV Amentent No.
139
IlI_DG LIMrrDC 00NDITIO1S FOR OPERATIOi MD SURVEILLANCE RDQUIRDOUS SECTIQi P_ AGE 3/4.7 PIRTP SYSTDG 3/4.7.1 TURBDIE CYCII Safety Valves......
3/4 7-1 Auxiliary Feedvater System 3/4 7-5 Auxiliary Fcal Storage Tank...........
3/4 7-7 Activity
.3/4 7-8 Main Steam Line Isolation Valves
.3/4 7-10 3/4.7.2 STFRi GDIERAIOR PRESSURE /TD4PERATURE LIMITATIQi
.3/4 7-14 3/4.7.3 CIMCtIDir COOLDU WATER SYSTDi
.3/4 7-15 3/4.7.4 SUNICE WATER SYSTD4
.3/4 7-16 3/4.7.5 FIJDOD PROTECTION
.3/4 7-17 3/4.7.6 COtfrROL ROct4 D4ERGDICY AIR
(
03NDI*IONDU SYSTD4...............
3/4 7-18 3/4.7.7 AUXILIARY IUIIDDG EXHAUST AIR FILTRATION SYSTD4
.3/4 7-22 3/4.7.8 SEALED SOURCE C3tfrAMDIATION..
.3/4 7-26 3/4.7.9 SNUBBERS 3/4 7-28 SALD4 - UNrr 1 VII Amerdment No.
139 l
DIDEX BASES SECTIGi PAGE 3/4.7 PIRE SYSTEMS 3/4.7.1 7URBDIE CYCE.
. B 3/4 7-1 3/4.7.2 STEAM GHTERATOR PRESSURE / TEMPERATURE LIMITATIQi B 3/4 7-4 3/4.7.3 00iKtIDE C00 LUG WATER SYSITM
. B 3/4 7-4 3/4.7.4 SERVICE WATER SYSTDi
. B 3/4 7-4 3/4.7.5 FIOOD ITulwnGi
. B 3/4 7-5 3/4.7.6 CDtTIBOL POcti D4ERGDiCY AIR CONDITIONDU SYSITM.
. B 3/4 7-5 3/4.7.7 AUXILIARY IIJIIDDG EXHAUST AIR FILTRATION SYSID4...
..... B 3/4 7-5 l
3/4.7.8 SEAIED SOURCE CDtEAMINATIOT.
. B 3/4 7-5 3/4.7.9 SNUBBERS
.. B 3/4 7-6 l
l
[
3/4.8 EECTRICAL IWER SYSTDiS 3/4.8.1 A. C. SCURCES ard AND 3/4.8.2 OtEITE F0WER DISTRIBUI' ION SYSTDiS.
. B 3/4 8-1 3/4.8.3 EECIRICAL EQUIRiDE PROIECIIVE DEVICES.
. D 3/4 8-1 1
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l SAIIM - UNIT 1 XIV Amerriment No. 139
PAGES 3/4 3-49 '11HOMI 3/4 3-52 ARE INIT2TFIOtMILY BIN {$
rw SALDi - UNIT 1 3/4 3-49 thturJh 3-52 Amentrent ib.139
Il61RUMDEATIQ1 BASES 3/4.3.3.6 THIS SECI' ION DEIEIED 3/4.3.3.7 _AOCIDDR FONITORIl0 IRS"IPUMDRATIm
'Ihe OPERABILITY of the accident monitoring instnmmtation ensures that sufficient informtion is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the Recmnendations of Regulatory Guide 1.97, " Instrumentation for Light-Water-cooled Nuclear Power Plants to Assess Plant Cbniitions During and Following an Accident," Dr-h r 1975.
?
3/4.3.3.8 RADIOACTIVE IJGJID EFFIUDF FONITORIIC INSTRIMNI'ATICH The radioactive liquid effluent instnnnentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alann/ trip setpoints for these instruments shall be calculated and adjusted in accordance with the procedures in the ODW to ensure that the alam/ trip will occur prior to exceeding the limits of 10 CHI Part 20. 7he OPERABILITY and use of this instnmentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of A@endix A to 10 CFR Part 50. 7he purpose of tank level indicating devices is to assure the detection and control of leaks that if not controlled could potentially result in the transport of radioactive materials to UIEESTRICIED AREAS.
3/4.3.3.9 PADIGACTIVE GASEXXE EFFIUDE 10NITORING DUIPUMEtEATIN The radioactive gaseous effluent instrunentation is provided to monitor and control, as applicable, the releases of radioactive naterials in gaseous affluents durire actual or potential releases of gaseous effluents. The alarny' trip setpoints for these instnnnents shall be calculated and adjusted in accordance with the procedures in the ODW to ensure that the alarty' trip will occur prior to excmiing the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controllirg) the correntrations of potentially explosive gas mixtures in the waste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirenents of General Design Criteria 60, 63, and 64 of Appeniix A to 10 CER Part 50.
SAIDI - UNIT 1 B 3/4 3-3 Amendment No.139
PLMfr SYS'IDiS BASES SNUBBERS (Continued)
To provide assurance of snubber functional reliability, a representative sanple of the installed snubbers will be functiomlly tested during plant shutdowns at 18-nonth intervals. CbservM failures of these sanple snubbers shall require functional testirrJ of additional units.
Perinanent or other exenptions frun the surveillance program for iniividual ch may be granted by the canntission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performrxl to qualify the snubbers for the applicable design corditions at either the otrpletion of their fabrication or at a 9*-Emt date. Snubbers so exemptM shall be listed in the list of irdividual snubbers indicatiry the extent of the exemptions, ifydraulic snubbers ard mechanical snubbers n:ay each be treated as a different entity for the above surveillan program.
'Ihe service life of a snubber is evaluatrd via mnufacturer inpit ard informtion throtxJh consideration of the snubber service conditions ard associated installation ard mintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high tenperature area, etc... ). 'Ibe requirement to monitor the snubber service life is included to ensure that the snubbers periodically uMergo a performnce evaluation in view of their age aM operatirq corditions. 'Ihese records will provide statistical bases for future consideration of snubber service life. 'Ihe requirements for the maintenarm of records and the snubber servi life review are not intended to affect plant operation.
i t
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l SAIDi - UNIT 1 B 3/4 7-7 Anerdment No.139
l AD41NISIBATIVE COtTITOIS FACILITY STAFF (Continued) b.
At least one licensed Reactor Operator shall be in the control Icam when fuel is in the reactor.
In addition, at least one licensed Senior Reactor Operator shall be in the Control Roca area at all tires.
c.
All CDRE ALTERATIOtiS shall be observed and directly supIvised by a li nsed Senior Reactor Operator who has to other concurrent responsibilities duriry this cperation, d.
'Ihe amount of overtire wrked by plant staff mcsters performirg safety-related functions must be limited in accortimco with the NRC Policy Statement on wrkiry hours (Generic Intter No. 82-12).
e.
'Ihe Qxnating Ergineer, Senior Nuclear Shift Supervisors, ard l
Nuclear Shift Supervisors shall each hold a senior reactor operator license. N Nuclear Control Operators shall hold reactor operator licenses.
f.
h Operations Manager shall meet one of the following:
l (1) Hold an SFO license.
(2) Have held an SRO license for a similar unit (IHR).
SAID4 - UNIT 1 6-2 Amendment No. 139 l
ALNINISTRATIVE OJtfITOLS 6.2.3 SHIFT TF)3FICL1 AU/ISOR 6.2.3.1 The Shift Technical Advisor shall serve in an advisory capacity to the Senior Nuclear Shift Supervisor on matters pertaining to the engineering aspects assuriM safe operation of the unit.
6.2.3.2 The Shift Technical Advisor shall have a Bachelor's Degree or cquivalent in a scientific or engineering discipline with specific training in plant design and response and amlysis of the plant for transients ard accidents.
6.3 FACI.JJTY STAFF CUALIFICATIONS 6.3.1 Each nenber of the facility staff shall meet or exceed the minina qualifications of ANSI N18.1-1971* for cmparable positions ex&pt for the irdividual designated as the Radiation Protection Rmager who shall meet or exceed the qualifications of Regulatory Guide 1.8, Septenber 1975, and the licensal cperators who shall canply with the requirunents of 10CFR55.
6.4 TPAINING 6.4.1 A retraining ard replacemnt training program for the facility staff shall:
- 1) be coortlimted by each functional level mnager (Department Head) at the facility ard mintained urder the direction of the !bnager - Ibclear Training
- 2) meet or exceed the raglircuents ard rm #rdations of Section 5.5 of ANSI N18.1-1971 for all affected positions except licensed operators and F
- 3) canply with the requirements of 10CFRSS for licensed operators.
The Operatiors lunager shall recet one of the followirg:
1)
Hold an SPD license.
- 2) Have held an SBO license for a similar unit (IHR).
SAIIM - UNIT 1 6-7 Amench:ent No.139 l
l
AIMINISTFATIVE CENITOIS d.
Source of waste and processing splayed (e.g., dewatered spent resin, cxrpacted dry waste, evaporator bottams),
Type of container (e.g., ISA, Type A, Type B, large Qaantity), and e.
f.
Solidification agent or aboorbent (e.g., cement, urea fomaldehyde).
'Ihe Radioactive Effluent Release Reports shall include a list of descriptions-of unplanned releases from the site to UlmESTRICIED AREAS of radioactive materials in gaseous ard liquid effluents made during the reporting period. -
'Ihe Radioactive Effluent Release Reports shall include any ctianges made during the reportiry period to the PROCESS CDi(ITOL PROGRAM (PCP) and to the OFESI'IE DOSE CALCUIATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental ronitoring identified by the land use census pursuant to Specification 3.12.2.
RADIAL PEAKING FACIOR LIMIT REIVRT 6.9.1.9
'Ihe F limits for Rated 'Ihermal Power (FXY ) for all corie planes XY containirg bank "D" control rods and all unrodded core planes, and the plot of predictcd heat flux hot channel factor times relative power (F *Pg ) vs.
Axial Core Height with the limit envelope shall be provided to the NRC Wmnt Control Desk with copies to the Regional Administrator and the Resident Inspector. 'Ihe Report shall be provided to the nr-ission upon issuance.
In acklition, in the event that the limit should change, requiring a new subnittal or submittal of an amended Peakiry Factor Limit Report, it will be submitted upon issuance.
SPECIAL REIORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory rweimion, tw,nmnt Control Desk, Washington, D.C. 20555, with a copy to the Administrator, UStGC Region I within the time period specified for each report.
6.9.3 Violations of the requirements of the fire protection gvgam described in the Updated Final' Safety Analysis Report _ wilich would have adversely affected the ability to achieve and maintain safe shutdown in the event of a fire shall be -subnitted to the U. S. Nuclear Regulatory Ctanirsion, n,,,n=nt Control Desk, Washirgton, DC 20555, with a copy to the Regional Administrator of the Regional Office of the NRC via the Licensee Event Report System within 30 days.
SAIDi - UNIT 'l 6-24 Amerdment No.139 er,
n v-e,
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e 1-~,,
AD4DilSIRATlVE COfflTOIS 6.10 RECORD RErDTTIOti In addition to the applicable recod retention requirenents of Title 10, Code of Federal Regulations, the follcuirg rerds shall be retaincd for at least the mininzm period indicated.
6.10.1 The followirg reconis shall be retaincd for at least five years:
a.
Records ard logs of unit operation covering tim interval at each pcuer level.
b.
Records ard logs of principal mintenance activities, inspections, repair and replacenent of principal items of equipment related to nuclear safety.
c.
All REPORTABIE EVD7IS subnittcd to the Cammission, d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
e.
DELETED f.
Records of changes mde to Operatiry Procedures required by Specification 6.8.1.
g.
Records of radioactive shipments.
h.
Records of scaled source and fission detector leak tests and results.
i.
Records of annual physical inventory of all sealed scurre material of record.
j.
Records of reviews perfonned for charges mde to prWires or reviews of tests ard experiments, pursuant to 10GR50.59.
6.10.2 'Ihe follcuiry records shall be retained for the duration of the Unit operatiry License:
a.
ReccIds ard drawing charges reflectirg unit design modifications made to systems ard equirnent described in the Final Safety Analysis Report, pursuant to 10CFR50.59.
b.
Records of new ard irradiated fuel inventory, fuel transfers ard assenbly burnup histories.
SAID4 - UNIT 1 6-25 Amndment No.139
1 AD{DilSTRATIVE 00tf1TOIS c.
Rooords of radiation exposure for all individuals enterirg radiaticn control areas.
d.
Records of gaseous and liquid radioactive material released to the
- environs, c.
Recortis of transient or operatiomi cycles for those facility components identified in Table 5.7-1.
f.
Records of reactor tests and experirents.
g.
Records of training ard qualification for curInnt uth of the plant staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assuranca activitics required by the QA Minual.
j.
DEETED k.
Records of SORC meetirgs and activities of OSR (and meetirgs of its prn W m r, the Nuclear Review Board).
1.
Records for Environmental Qualification which are covered under the provisions of Paragraph 6.16.
m.
Records of the service lives of all hydraulic ard mechanical snubbers includirg the date at which the servios life armences ard associated installation ard maintenance records.
n.
Records of secondary water samplirg ard water quality.
o.
Records of analyses required by the radiolcgical envinna:ntal monitorire program which would permit evaluation of the accuracy of the amlysis at a later date. 'Ihis should irclude procedures effective at specified times and QA records showirg that these procedures were followed.
6.11 RADIATION PRCTTECTION PROGRAM Pru:edures for personnel radiation protection shall be preparsi consistent with the requirements of 10 CFR Part 20 ard shall be approved, maintained ard adherrd to for all operations involving perr e el radiation exposure.
SAI M - UNIT 1 6-26 Anerdment No.139
ADGTISIPATIVE CoffITOLS 6.12 HIGH PADIATION ARFA 6.12.1 In lieu of the "contml device" or "alam signal" requind 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 mram/hr* but less than 1000 nre:y'hr shall be barricaded aM conspicucusly posted as a High Padiatico Area and entrance thereto shall be controlled by issuarce of a Radiation Exposure Permit **. Any inilvidual or group of irdividuals pemitted to enter such areas shall be pruvided with or acccrpinied by one or more of the followirg:
A radiation monitorirq device which continuously indicates-the a.
radiation dose rate in the area.
b.
A radiation ronitoring device which continuously integrates the radiation dose rate in the area a M alarms when a preset integrated dose is received. Entry into such areas with this monitorirg device may be made after the dose rate level in the area has been establishcd and personnel have been made knowledgeable of them.
c.
A health physics qualificd individual (i.e., cpalified in radiation protection procedurec) with a radiation dose rate monitorirq device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specificd by the Radiation Work Permit.
6.12.2 In addition to the requirements of 6.12.1, areas accessible to pereml with radiation levels
- such that a major portion of the body could receive in one hour a dose greater than 1000 mrem shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained urder the administrative control of the Senior Nuclear Shift Supervisor on-duty and/or Senior Supervisor - Radiation Protection.
Doors shall remain locked except durirq periods of access by personnel under an approved Radiation Work Permit which shall specify the dose rate levels in the immcdiate work area and the maximum allcuable stay time for irdividuals in that area.
For individual areas accessible to personnel with radiation levels
- 'Ihis is normally defined as the level at a distance of 18 inches frtra the source or accessible surface.
- Radiation Protection Personnel or personnel escorted by Radiation Protection Perscnnel shall be exempt from the FWP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise followiry plant radiation protection procedures for entry into high radiation areas.
SAI m - UtiIT 1 6-27 Amendment No. 139
AIMINISIWsTIVE 00tTITOLS sud1 that a mjor portion of the body could receive in one hour a dose in excess of 1000 mrem that are located within large ainas, sudi as WR containment, where no enclocure exists for purposes of lockirg, and no enclosure can be reasonable constructed arourd the irdividual areas, then that area shall be raped off, conspicuously posted ard a flashing light shall be activated as a warning device.
In lieu of the stay time specificaticn of the FMP, direct or renote (such as use of closed circuit 'IV canras) continuous surveillance my be mde by personnel qualified in radiation protection pro durus to provide positive exposure control over the activities within the area.
6..J3 l'ROCESS C)tTITOL ITOGPR4 (FCEl 6.13.1
'Ihe ICP shall be approvcd by the Cartission prior to inplenentation.
6.13.2 Licensee initiated changes to the FCP:
1.
Shall be submitted to the cornission in the Semiannual Radioactive Effluent Release Report for the period in which the charge (s) was mde. 'Ihis subrtittal shall contain:
a.
Sufficiently detailed information to totally support the rationale for the charge without benefit of additional or supplemental informtion; b.
A detennnation that the charge did not rtduce the overall conformnce of the solidified waste product to existiry criteria for solid wastes; ard c.
Documentation of the fact that the change has beet' reviewcd and found acceptable by the SORC.
2.
Shall beccrac effective upon review ard acceptame ay the SORC.
SAIDi - UNIT 1 6-28 Amendnent No.139
AEMDiISTRATIVE CNIPOLS 6.14 Oqyrir DOSE CAlmIATION FRUAL (OCOO 6.14.1 The ODCM shall be approved by the rwmninnion prior to inplementation.
6.14.2 Licensee initiated changes to the ODCM:
1.
Shall be subnitted to the Ctanission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:
Sufficiently detailed information to totally support the a.
rationale for the charge without benefit of additional or supplemental information.
Information subnitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with an apptwal and date box, together with appropriate analyses or evaluations justifying the charge (s);-
b.
A'detemination that the change Will not reduce the acairacy or reliability of dose calculations or setpoint determination; and c.
rw,wntation of the fact that the change has been reviewed and found acceptable by the SORC.
2.
Shall beccre effective upon review and ao ptance by the SORC.
6.15 MAJOR CHANGES TO RADIOACTIVE LIOUID, G\\SEOUS AND SOLID WASTE TREATMENT SYSTDG 6.15.1 Licensee initiated major changes to the radioactive waste system (liquid, gaseous ard solid):
1.
Shall be reported to the (W'minnion in the UFSAR for the period.
in which the evaluation was reviewed by (SORC).- The dia,3naion of each change shall contain:
a.
A suntiary of the evaluation that led to the determinatial that the charge could be made in accordance with 10CFR50.59;-
b.
Sufficient detailed information to totally support the reason for the charge withaat benefit of additional or -
supplemental information; SAIIM - UNIT 1 6-29 Amendment No.139
,,4-
ADiINISIRATIVE C NIFOIS A detailcd description of the equignent, caponents ard c.
processes involved and the interfaces with other plant systems; d.
An evaluation of the charge, which shcus the pruiicted releases of radioactive mterials in liquid aM mela effluents ard/or quantity of solid waste that differ frm those previously predicted in the license application aM amndments thereto;-
An evaluation of the charge, which shows the expected e.
mximm exposures to individual in the unmstricted area ard to the general population that differ from those previously estimted in the license alplication ard amerdments thereto; f.
A ccrparison of the predictcd releases of r:vMmetive materials, in liquid ard gaseous effluents ard in solid waste, to the actual releases for the period prior to when the changes are to be made; g.
An estimte of the exposure to plant operating personnel as a result of the change; and h.
Documentation of the fact that the charge was reviewed and fourd acceptable by the (SORC).
2.
Shall becme effective upon review ard acceptance by the Sorc.
6.16 DNIROtMDTTAL CUALIFICATION 6.16.1 All safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of: Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class lE Electrical Equipmnt in Operating Reactors" (DOR Guidelines); or, NUREG-0588
" Interim Staff Ibsition on Environmental Qualification of Safety-Related Electrical Equipnent," Demmber 1979. Cbpies of these documents are attached to Order for Modification of License No. DPR-70 dated October 24, 1980.
6.16.2 Ctrplete and auditable records shall be available ard raintained at a central location which describe the environmental qualification method used for all safety related electrical equiprnt in sufficient detail to h=nt the degree of capliance with the DOR Guidelines or NURB3--0588. Such records should be updated and maintained current as equignent is replaced, further tested, or otherwise further qualified.
SAIDI - UNIT 1 6-30 Amendment No. 139
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-3" UNITED STATES n
i ci NUCLEAR REGULATORY COMMISSION:
WASHINoToN, D.C. 20566 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 117 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found-that:
A.
The application for amendment filed by the-Public Service Electric &-
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City _ Electric Company (the licensees) dated August 2, 1991, and supplemented by letter dated September 30,~1992,-
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; i
B.
The facility will ' operate in conformity with the application, the provisions of-the Act,' and the rules and regulations of the Commission; C.
There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and:
safety -of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth-in-10 CFR-
- Chapter I; i
D.
The issuance of.this amendment will not be inimical to the common-l 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 _ B awf ad by changes to the Technical! Specifica-tions as indicated in the allumment to this license amendment, and paragraph 2.C.(2) of Facilit.) Uperating License No. DPR-75 is hereby amended to read as follows:
,.c4
. (2) 11Eb.nical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.117, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
Also, the license is amended by replacing Paragraph 2.C.(10) on page 7 with the following and adjusting pages 8-9-10 and 11 of Facility Operating License DPR-75:*
(10)
Fire Protection PSE&G shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report, and as approved in the NRC Safety Evaluation Report dated November 20, 1979, and in its supplements, subject to the following provision:
PSE&G may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
4.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 0x Lo A
Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation-
Attachment:
1.
Pages 7, 8-9-10, and 11 of License DPR-75 2.
Changes to the Technical Specifications Date of Issuance: January 5, 1993
- Pages 7, 8-9-10, and 11 are attached, for convenience, for the composite license to reflect this change.
ATTACHMENT 1 TO LICENSE AMENDMENT NO. 117 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise License DPR-75 as follows:
Remove Paaes lpsert Paaes Page 7 Page 7 Page 8 Page 9 Page 8-9-10 Page 10 Page 11 Page 11 l
- (d) Complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the D0R Guidelines or NUREG-0588.
Such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified to document complete compliance by June 30, 1982.
(e) Within 90 days of receipt of the equipment qualification safety evaluation, the licensee shall either (i) provide missing documentation identified in Sections 3 and 4 of the equipment qualification safety evaluation which will demonstrate compliance of the applicable equipment with NUREG-0588, or (ii) commit to corrective actions which will result in documentation of compliance of applicable equipment with NUREG-0588 no later than June 30, 1982.
(10) Eire protection PSE&G shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report, and as approved in the NRC Safety Evaluation Report dated November 20, 1979, and in its supplements, subject to the following provision:
PSE&G may make changes to the approved fire protection-program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
Amendment No. /,6,117
- 9 -
PAGES 8, 9, AND 10 ARE INTENTIONALLY BLANK Amendment No. X,,2Y, 117
. (11) Containment Isolation (Section 6.2.3. Sucolements 4 and 5)
Within 90 days after issuance of the license, PSE&G shall demonstrate to the satisfaction of the NRC that the present contair. ment isolation provisions for the main feedwater lines comply with the requirements of General Design Criterion 57 under all postulated accident conditions, or propose a design change that will achieve compliance.
If necessary, the design change shall be implemented during the first refueling outage.
(12) Main Condenser (Section 14.0. Supplement 4)
Prior to exceeding 50 percent power, PSE&G shall complete the preoperational testing of the remaining three of six circulators to be tested in the main condenser for the circulating water system.
(13)
River Traffic Accidents (Section 2.2.1. Supolement 1)
PSE&G shall also report for the Salem facility any information reported for the Hope Creek facility relating to circumstances which suggest that the risk from flammable gas clouds (resulting from river traffic accidents on the Delaware River) varies significantly from that previously considered.
l l
l-i Amendment No. AC JRr, 117 l
l l
ATTACHMENT 2 TO LICENSE AMENDMENT NO. 117 FAClllTY OPERATING LICENSE N0. DPR-75 DOCKET N0. 50-311 Revise Appendix A as follows:
Remove Paaes Insert Paaes Index IV Index IV Index Vil Index VII Index XIV Index XIV 3/4 3-46 3/4 3-46 through 3/4 3-49 3/4 3-47 3/4 3-48 3/4 3-49 3/4 7-27 thru 3/4 7-30 3/4 7-31 3/4 7-32 3/4 7-33 3/4 7-34 3/4 7-35 3/4 7-36 3/4 7-37 3/4 7-38 3/4 7-39 B 3/4 3-2 B 3/4 3-2 8 3/4 7-7 B 3/4 7-7 B 3/4 7-8
I ATTACHMENT 2 TO LICENSE AMENDMENT NO. 117 FAClllTY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Paaes Insert Paaes 6-2 6-2 6-7 6-7 6-24 6-24 6-25 6-25 6-26 6-26 6-27 6-27 6-28 6-28 6-29 6-29 6-30
1 DIDEX l
LIMITDG CONDITIGE FOR OPERATIOi AND SURVEILIRICE RD2UIRE24DfIS HLXJ1QLi PAGE 3/_4_._2 TWER DISTRIHRIOT LDEIS 3/4.2.1 AXIAL FIUX DIFFERDiCE................................ 3/4 2-1 3/4.2.2 HEAT FIUX MCrr GANNEL FACIOR......................... 3/4 2-5 3/4.2.3 RCS FIN RATE AND R.................................. 3/4 2-9 3/4.2.4 QUADRATE IOWER TILT RATIO............................ 3/4 2-13 3/4.2.5 DIB PARAMETERS....................................... 3/4 2-16 3/4.3 IllSITUMDTTATION 3/4.3.1
' REACIOR TRIP SYSTD4 INSTRUMDTrATION.................. 3/4 3-1 3/4.3.2 D13DIEERED SAII. Y FEA'IURE ACIUATION SYSTD{
T DETUMDfIATION...................................... 3/4 3-14 3/4.3.3 MONINiG INSTRUMDfrATION Radiation Monitoring Instrumentation................. 3/4 3-38 Movable Irr: ore Detectors............................. 3/4 3-42 Remote Shutdcun Instrumentation...................... 3/4 3-43 l
Accident Ibnitority Instrumentation.................. 3/4 3-50 Radioactive Liquid Effluent Monitoring Instrumentation...................................... 3/4 3-53 Radioactive nawls Effluent Monitorirg Instrumentation...................................... 3/4 3-59 3/4.3.4
'IURBINE OVERSPEED PPDrECTIQi......................... 3/4 3-65 SAID4 - UNIT 2 IV Amendment No. 117
DIDEX LDUTDG CDNDITIONS FOR OPERATIGi AND SURVEIUAG RKUIRDOfIS SECTION pts 3/4.7 PIRfr SYSTENS j
3/4.7.1 TURBINE CYCIE i
Safety Valves........................................ 3/4 7-1 Auxiliary Feodwater System........................... 3/4 7-5 Auxiliary Feed Storage Tank.......................... 3/4 7-7 4
Activity............................................. 3/4 7-8 Main Steam Line Isolation Valves..................... 3/4 7-10 3/4.7.2 STEAM GDIERNIOR PRESSURE /TD4PERATURE LIMITATIQi........................................... 3/4 7-11 4
3/4.7.3 OCHEONDir OOOLI G WATER SYSTEM....................... 3/4 7-12 3/4.7.4 SERVICE WATER SYSTEN................................. 3/4 7-13 4
3/4.7.5 FICOD PROTECTION..................................... 3/4 7-14 i
3/4.7.6 CDifIFOL ROCH EMERGDICY AIR 4
CONDITICNDU SYSTD4.................................. 3/4 7-15 4
i 3/4.7.7 AUXILIARY EUIIDDE EXHAUST AIR FILIRATIOT SYSIDi.................................... 3/4 7-18 3/4.7.8 SEAT Fn SOURCE CDifrAMDIATION.......................... 3/4 7-21 3/4.7.9 SNURRERS............................................. 3/4 7-23 SAIDi - UNIT 2 VII Anen11,uit. No. 117
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BASES SECTIOf PAGE 3/4.7 PLNfr SYSTEMS 3/4.7.1 TURBINE CYCLE......................................... B 3/4 7-1 3/4.7.2 STEAM GDIERATOR PRESSURE / TEMPERATURE LIMITATIQ1............................................ B 3/4 7-4 3/4.7.3 COMPONDff COOLIIG WATER SYSTEM........................ B 3/4 7-4 3/4.7.4 SERVICE WATER SYSTEM.................................. B 3/4 7-4 3/4.7.5 FLOOD PROTECTIOl...................................... B 3/4 7-5 3/4.7.6 00tfrROL ROCM EMERGDiCY AIR CONDITIQmG SYSTEM................................... B 3/4 7-5 3/4.7.7 AUXILIARY IUILDDG EXI%UST AIR FILTRATIOT SYSTEM..................................... B 3/4 7-5 3/4.7.8 SEAIED SCURCE C0ffrAMINATIOi........................... B 3/4 7-5 3/4.7.9 SNUBBERS..............................................B 3/4 7-6 3/4.8 ELECTRICAL POWTR SYSTFNS 3/4.8.1 A. C. SCURCES and AND 3/4.8.2 ONSITE ICWER DISIRIBUTIOT SYSTENS.....................B 3/4 8-1 l
3/4.8.3 ELECIRICAL D2UIINDIT PROTECTIVE DEVICES...............B 3/4 8-1 l
l SALIM - UNIT 2 XIV Amentnent No.117 J
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'IN OIUtABILITY of the nrnable incore detectors with the specified minin2rn otrplerent of equip ont ensures that tN neasuruments obtained frau use of this systen accurately reprecent the spatial neutron flux distributico of the reactor corn. The OlDRABILITY of this systan is detonstrated by irradiatirq oach detector used and normlizirg its respective cutput.
For the pupoco of reasurity F (Z) or Ih, a full incorn flux mp is 9
used. Quarter-core flux raps, as defined in WCAP-8648, Jurw31976, my be us(xi in recalibration of the exoore routrcn flux detection systtra, and full irrore flux mpa or synretric incore thinbles my be used for nonitoring the QUAIEN(r IOWIR TIIfr PATIO when one Ptuer Pange Channel in irgerable.
2/_4. 3. 3. 3 SEISMIC DiSITUMDTTATIOi 10rPKUDuD 3/4.3.3.4 !"frEDf0132iICAL INSITUMDTTATIOi
!UrIELUIRED 3/4.3.3.5 IUM7FE S1UIU34N DISTIMDfrATIQi
'Ihe OPERABILITY of the Irrote chutdcun instnr:entaticn ensurus that sufficient capability is availabic to permit shutdcun arri mintemnce of IUr STANDEN of the facility frun locations cutside of the control rocan. This capability is required in the event control rocan habitability is Icst and is ccmsistent with General Design Critericn 19 of 10 CIR 50.
l 3/4.3.3.6
'HIIS SECTIOi DE.IETED 3/4.3.3.7 ACCIDENr PGI'IDRIlO INS 110MD7FATIOT The OPERABILITY of the accident monitorirg insttu:entaticn ensures that sufficient informatico is available on selected plant parancters to ucnitor and -= these variables followirg an accident. This capability is consistent with the P - ndations of Prqulatory Guide 1.97, "Instrunentation for Light-Water Cooled Nuclear Pomr Plants to Assess Plant Orslitions turity ard Follcuirg an Accident," Doocrber 1975 and IURD2-0578, IMI-2 Lesscns Imarnod Task Form Status Report ard Short-7bnn Reotrucrxiaticos."
SAID4 - UNIT 2 B 3/4 3-2 Arendrent No. 117 i
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3/4.7 IYNIr SYUIT213 IWSIB i
S U10EIG (Contin wll To provide assurance of snubber functiomi reliability, a representative sanple of the installed snumers will be functiomlly testtd during plant shutdcuns at 18-nonth intervalg observcd failures of those sarple snubbers chall require functiomi testcr; of acklitional units.
Ibrmrent or other exemptions from the surveillaroe program for irdividual snuWers my be grantcd by the Cormission if a justifiable basis for exemption is presented ard, if a[plicable, snuWer life destructive testing was perforwxi to qualify the snubbers for the applicable design conditions at either the otrpletion of their fabrication or at a succequent date. Snutbers so exenpted shall be listed in the list of irrlividual snutbers irdicatiry the extent of the exemptions.
Itydraulic snubbers ard mechanical snu&ers my each be truated as a dif ferent entity for the above surveillancu prcgram.
l
'Ihe service life of a snutber is evaluated via mnufacturer input and informtion through consideration of the snutber service conditions and associated installation ard mintemnce records (newly installed snubber, seal replaced, sprirn replacxd, in high radiation area, in high tenperature area, etc... ). 'Jhe rcquirenent to nonitor the snubber scivioe life is included to ensure that the snubbers pericdically urdergo a performnco evaluaticn in view of their age ard operatiry conditions. 'Ihese records will provide statistical bases for future consideration of snut2.er service life. 'Ihe requirenents for the mintemnce of records ard the snutinr servloe life review are not interded to affect plant cperation.
SA11E - UNIT 2 B 3/4 7-7 Anendnent 16.
117
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AI24INISITMTIVE OctTITtDIE FACILITI STAFF (Continued) b.
At least one licenned Reactor Operator shall be in the control room when fuel is in the reactor.
In acklition, at least ena li.nsed Senior Reactor Operator shall be in the Control Room area at all tines.
All CORE AIJIU aTIotts shall be observed and directly supezvised by a c.
limnsed Senior Reactor Operator who has to other carcurrent responsibilities durirg this operation.
d.
The amount of overtinn worked by plant staff mtrabers performity safety-related functions nust be limited in accortlance w'.th the NRC Policy Statcrent on working hours (Gernric Intter No. 82-12).
e.
The Operating Engineer, Senior Nuclear Shift Supervisors, and l
Nuclear Shift Supervisors shall each hold a senior reactor operator licence. The Nuclear control Operators shall hold reactor operator lica n s.
f.
The Operations Manager shall meet one of the followirg:
l (1) lloid an SFO limnse.
(2) llave hold an SFO limme for a similar unit (IVR).
SAIDi - U!IIT 2 6-2 Amendment No.
117
AUiUfI!TI1WTIVE ODtil10LS b2.3 SillPL HX1RH.C6L 6fH KCB 6.2.3.1
'Ihe Shift Todinical Mvisor rhall serve in an advisory capacity to the Senior Nuclear Shift Supervisor on mattcIs pertainity to the orgineerity I
as cts assurirg safe operation of the unit.
1 6.2.3.2
'Ihe Shif t 'Itchnical Mvisor chall have a Bachelor's Dogree or equivalent in a scientific or ergineerirn discipline with specific trainity in plant design ard response aid arnlysis of the plant for transients ard accidents.
6.3 FACILIT/17FAFF CUALIFICATIQtM 6.3.1 121ch rumber of the facility staff shall meet or exceed the minirum qualifications of NISI N18.1-1971* for cxxinrable positions exoopt for the irdividual desigrnttd as the Padiation Protection Marwyer who rhall moet or excxxd the qualifications of Regulatory Guide 1.8, September 1975, arvi the j
limnral operators who shall comply with the rcquirements of 10CFR55, 6.4
'IIqIHILO 6.4.1 A letrainity ard replacement trainity program for the facility staff chall:
- 1) be coordinat.
- L; each functioral level marager (Departrent Head) at the facility acJ mintaincd urder the diluction of the Kirnger - Nuclear Trainirg
- 2) meet. r exceed the requircaents and reocrt:ntdations of Section 5.5 of NJSI N18.1-1971 for all affectcd positions except licensed operators ard
- 3) cmplf with the requirunents of 10CFR55 for licencal operators.
'Ihe operations Runger chall meet one of the followirg:
- 1) Hold an SIO lim _nse.
- 2) Have held an 510 license for a s12nilar unit (IHR).
SAID4 - UNIT 2 6-7 Anerdment No. 117 Te.W-me mTur'--w='
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Att411HS'HRATIVE CIXTHOIf2 d.
Source of waste and proccasily eq>loyed (e.g., dewatered spent resin, atmpactM dr'f waste, evaporator bottcru),
c.
Type of container (e.g., ITA, Type A, type B, large Quantity),
aM f.
Solidification agent or absortent (e.g., cement, urea formldchyde).
'1ho Padioactive Effluent Release Reports nhall incitde a list of descripticrs of unplanned releases frun the site to UNRESTRICTED AREAS of radioactive mterials in gasecus ard liquid effluents mde during the reportirg period.
'1he Radioactive Ef fluent Release Poports chall include any charges nyle durirq the reportiry period to the Pf0 CESS CDifDOL IPOGRN4 (ICP) ard to the OFTSITE DCGE CAICUIATIOt1 WNUAL (ODQi), as well as a listiry of new locaticos for doce calculations ard/or environmntal nonitorirg identificd by the lard use mnsus pursuant to Specification 3.12.2.
BADIAL ITAKILO FACIOR LlHTT PfdOJH' 6.9.1.9
'Ihe F limits for Rated Therml Ftuer (FXY ) for all core planes XY containirn bank "D" control rods and all unrulled corn planes, and the plot of prcdicted heat flux hot channel factor times relative power (F *Pg ) vs.
Axial Core Height with the limit envolcpe shall be provided to the NRC Documnt control Desk with copies to the "rjional Mministrator ard the Resident Inspector. '1ho Report shall be prwided to the Otrmissicn upon issuance.
In addition, in the event that the limit should change, requirirg a new sulmtittal or sutstittal of an anendcd IbT. king Fbctor Limit Report, it will be subnitted upon issuance.
SPDCIAL REIORI'S 6.9.2 Special reports shall be subnitted to the U.S. Nuclear Regulatory Ctruissjon, Docunent Control Desk, Washirgton, D.C. 20555, with a copy to the Mministrator, USNRC Region I within the time period specified for each Inctt.
6.9.3 Violations of the requirements of the fire protecticn program described in the Updated Fiml Safety Analysis Report which would have adversely affected the ability to achieve and mintain safe shutdown in the event of a fire shall be subnitted to the U. S. Nuclear Rcqulatory Otrmission, Wmnt Control Desk, Washington, DC 20555, with a copy to the Regional Mministrator of the Regional Office of the NRC via the Licensee Event Report System within 30 days.
SAlai - UrnT 2 6-24 Amendment No. 117 I
_ _ _. _ _. _ _. _ _ _ _ __. ~.. _ _ _ _
4 AD{INIfiIFATIVE Ctf(IBOIS 6.10 RDCORD REIDTTICH l
In addition to the applicable record retention requirments of Title 10, Cbde of Federal Bety.Ilations, the following records shall be retained for at least the minimum period irdicated.
6.10.1 '1he following records shall be retaincd for at least five years a.
Reconis and logs of unit operation otnering tine interval at each pcuer level, b.
Records ard logs of principal mintenarr.e activities, inspections, repair and replacement of principal item of equipmnt related to nuclear safety.
l c.
All REFORTABIE EVD7IS subnitted to the Camission.
I d.
Records of surveillance activities, inspections ard calibrations rrquired by these Technical Specifications.
e.
DElfrED f.
Records of changes mde to Operating Procedures required by Specification 6.8.1.
g.
Records of radioactive r.hipmats.
h.
Records of sealed source and fission detector leak tests and Insults.
1.
Records of annual physical inventory cf all sealed sourt:e mterial of record.
j.
Records of reviews performed for changes mde to procedures or reviews of tests ard experiments, pursuant-to 10CER50.59.
6.10.2 '1he following records shall be retained for the duration of the Unit Operatiry License:
a.
Records ard drawiry changes reflectirq unit design modifications mde to systenu ard equipr,cnt described in the Final Safety Analysis Report, pursuant to 10CIR50.59.
b.
Ra:ords of _ new and irradiated fuel inventory, fuel transfers ard assembly burnup histories.
SAIDi - UNIT 2 6-25 Amentnent No.
117 i
..-.i
l l
MMDWIn%TIVE OctTITOL9 c.
Records of radiaticri exposure tir all irdividuals enttrity radiaticci cmtrol areas.
d.
Records of gaseous ard liquid radioactive mterial released to the environs.
Rormrds of trunsient or operaticral cycles for thoce facility e.
cmponents identifirx1 in Table 5.7-1.
f.
Records of reactor tests ard experiments, g.
Reconis of trainim and cpilificaticri for current nubers of the plant staff.
h.
Poconis of in-service inspections perforwxt purannt to these Technical Spocifications.
1.
Records of Qtality Ancurance activities required by the @ lunual.
j.
DEUTED k.
Records of SORC meetirgs ard activities of OGR (and moctirgs of its pruix w or, the Nuclear Review Board).
1.
Rooords for Envirumental Qualification which are cxnered under the provisions of Paragraphs 2.C(7) and 2.C(8) of Facility Operatiry Liocree DIR-75.
m.
Recortis of the service lives of all hydraulic ard mechanical snutters ircludity the date at uttich the carvice life comences and associated installation and maintenance records.
n.
Records of socmdary water sanpliry ard water quality, o.
Records of arnlyses ruquired by the radiolcgical environmental monitorirg prcgram which would permit evaluaticri of the accuracy of the aralysis at a later cbte. 'nds chculd irclude procedures effective at specificd times ard @ records showirg that these precedures were followed.
6.11 RADIATICtf EwiwnCt1 FRGWi Procedures for personnel radiaticx1 protecticri shall be prepared consistent with the requiruments of 10 CFR Part 20 arvi shall be approved, maintaired ard adhered to for all operations involviry perscrinel radiation exposure.
4 SAIDi - UNIT 2 6-26 Amderit No.
I17 l
AIMDilSTRATIVE CW10Ili fad 2 IIIGI PADIATIOff AREA 6.12.1 In lieu of the " control device" or "alann sigml" requirtd by paragrarh 20.203(c)(2) of 10 CIR Part 20, eadi high radiation arm in which the in*ensity of radiation is greater than 100 mruy'hr* but less than 1000 mrunVhr shall be barricadcd and conspicuously posted as a liigh Radiaticn Area ard entrance thereto shall be controlled by incuance of a Padiation Exposure Permit **. Any irdividual or group of irdividuals penuitted to enter sudi areas shall be prtnidcd with or acccrpanied by one or more of the followirgs a.
A radiation tronitoring devicx which continuously irdicates the radiation dose rate in the area.
b.
A radiation nonitority device which continuously integrates the radiation doce rate in the area ard alarrs when a pruset integrated doce is Inceived.
Entry into such areas with this mmitorirg device my be mde af ter the dose rate level in the area has been established ard personnel have been mde krruledgeable of thorn.
c.
A health physics qualified irdividual (i.e., qualified in radiation protection procedures) with a radiation doce rate monitorirg device who is responsible for providirg positive control over the activities within the area ard shall perfonn periodic radiatico surveillance at the frequency specificd by the Radiation Work Permit.
6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel with radiation levels
- such that a mjor portion of the body could receive in one hour a dose greater than 1000 mran shall be pruvided with locked dcors to prevent umuthorized entry, ard the keys shall be maintained urder the administrative control of the Senior Nuclear Shift Supervisor on duty ard/or Senior Supervisor - Radiation Protection.
Doors shall remin locked except during pericds of anrm by personnel urder an approved Radiation Work Fonnit which shall specify the dose rate levels in the irwdiate work area ard the nucimum allcuable stay tim for individuals in that area.
For inlividual areas accessible to personnel with radiation levels a 'Ihis is ronully defined as the level at a distance of 18 irrhes frun the scurce or accessible surface.
- Radia+. ion Protection-Personnel or personnel escorted by Radiation Prutection Personnel shall be exempt frczn the IMP issuance requittront durity the performnce of their assigned radiation protection duties, provided they are otherwise follcwing plant radiation protection procxdures for entry into high radiation areas.
SAIIM - UtTIT 2 6-27 Amerdmerit No.-
117
+s 1
MMINIS7T&TIVE EtIDOIS such that a mjor portion of the body oculd roccive in one hour a dooo in excess of 1000 mrum that are lccated within large areas, such as IHR containment, where no enclecuro exists for pnposes of lockirg, and no enc 1ccure can be reasomble constructed around the 3rdividual areas, then that area shall be ropcd off, conspicucusly pcsted ard a flashirg light shall be activated as a warnirg device.
In lieu of the stay tirn specification of the IMP, direct or ruoto (such as use of clocod ciruult TV cameras) ocotinuous surveillance may be mde by personnel qualified in radiation protection procedures to prvvide pccitive expecure control over the activities within the area.
6.13 ILQTE>S ctTHOk ITogPRi (TCE) 6.13.1 The ICP shall be approved by the Ccmission prior to inplcunentation.
6.13.2 Licensee initiated changes to the TCP:
1.
Shall be subnittcd to the Conmission in the Semiannual Rviloactive Effluent Release Report for the period in ktlich the charge (s) was mde. 'Ihis sutnittal chall contain:
a.
Sufficiently detailed informtion to totally support the rationale for the charge withcut benefit of additioral or supplemental informtion; b.
A determimtion that the change did not reduce the overall conformrm of the solidified waste product to existirn criteria for solid wastes; ard c.
Documentation of the fact that the charge has been reviewed and fourd acceptable by the SORC.
2.
Shall bectro effective upon review ard acceptance by the SORC.
l l
l l-l SAU24 - LWIT 2 6-28 Amendment No. I17
AIMINISTFATIVE C0tTITOIS s
6.14 OFTSITE DOGE CAILUIATIOff MAfUAL (CDCM) 6.14.1 'Ihe ODCM shall be approved by the Ocnnission prior to irplmentaticn.
6.14.2 Licensoe initiatrd changes to the ODCM:
1.
Shall be suinitted to the Cmmission in the Samianntal Radioactive Effluent Release Report for the period in which the chargo(s) was mde. This subnittal shall contains a.
Sufficiently detailed infomation to totally support the ratiomle for the change without benefit of adiitional or supplenental infomation.
Infomstion submitted should ocmsist of a pckage of those pages of the OD04 to be darged with each pge numbered aM providcd with an approval and date box, together with appropriate analyses or evaluations justifyiry the charge (s);
b.
A detemimtion that the charge will ret reduce the accuracy or reliability of doce calculations or setpoint determimtion; and c.
Documntation of the fact that the charge has been reviemi and fourd acceptable by the SORC.
2.
Shall becan offective upon review ard acceptance by the SORC.
h15 MTOR OWUES 10 PADICACTIVE LICUID. CASIIXJS AND SOLID WSTE TREATMF2{p EGES 6.15.1 Licensee initiatcd mjor charges to the radioactive waste system (liquid, gaseous ard solid):
1.
Shall be reported to the Ctanission in the UFEAR for the period in which the evaluation was reviewed by (SORC). The Mm_ssico of each change shall contain:
A sinmary of the evaluation that led to the detennimtion that a.
the charge could be mde in accordance with 10CFR50.59; b.
Sufficient detailed infomation to totally sugx>rt the reason for the charge without benefit of adiitional or supplemental infomation; SAIDi - UNIT 2 6-29 Amerdment No. I17
ALMINISI1MTIVE 00tflTOIE2 c.
A detailed description of the equirrent, merents ard procesacs involved ard the interfaces with other plant systans; d.
An evaluation of the charge, which shows the prudicted releases of radioactive materials in liquid ard gaseous effluents and/or cpantity of solid waste that differ frun those previcusly predicted in the license applicaticri and amerdmnts thereto; e.
An evaluation of the charge, which nhows the expected msx1 rum c>qxx;ures to individual in the unrestricted area ard to the general population that differ frtxn those previously estinsted in the licence application and amendments thereto; f.
A cargnrison of the predictal releases of radioactive materials, in liquid ard gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes arm to be made; g.
An estimate of the expocure to plant operatlJg personnel as a result of the change; ard h.
Immntation of the fact that the charge was reviewed ard fourd acceptable by the (SORC).
2.
Shall boccano offective upon review and acceptance by the SORC.
SAIIM - WIT 2 6-30 Amendmert No. 117 f
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