ML20235R426
| ML20235R426 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/03/1987 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20235R409 | List: |
| References | |
| TAC-64735, TAC-64736, NUDOCS 8710080046 | |
| Download: ML20235R426 (176) | |
Text
{{#Wiki_filter:, _ _ ._. ATTACHMENT 2 Administrative and Editorial Changes to Rancho Seco Technical Specifications per Proposed Amendment No.155
'l 8710000046 871003 PDR ADOCK 05000312 P
PDR
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS Page Section 1-7 1.16 RESTRICTED AREA 1-7 1.17 SITE BOUNDARY 1-7 1.18 DOSE EQUIVALENT I-131 1.19 MEMBER (S) 0F THE PUBLIC 1-7 MAXIMUM HYPOTHETICAL INDIVIDUAL 1-8 155> 1.21 1.22 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL 1-8 1.23 LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM 1-8 1.24 VENTILATION EXHAUST TREATMENT SYSTEMS 1-9 PURGE - PURGING 1-9 1.25 1.26 VENTING 1-9 1.27 RADI0 ACTIVE EFFLUENT 1-9
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2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2-1 i 4 2.1 SAFETY LIMITS, REACTOR CORE 2-1 2.2 SAFETY LIMITS, REACTOR SYSTEM PRESSURE 2-4 2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE INSTRUMENTATION 2-5 3.0 LIMITING CONDITIONS FOR OPERATION 3-1 3.1 REACTOR COOLANT SYSTEM 3-1
.3.1.1 Operational Components 3-1 3.1.2 Pressurization, Heatup, and Cooldown Limitations 3-3 3.1.3 Minimum Conditions for Criticality 3-6 3.1.4 Reactor Coolant System Activity 3-8 3.1.5 Chemistry 3-10 Proposed Amendment No. 155 ifa 1
g _ _ RANCHO SECO UNIT 1-TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued) Section Page 3.14.5 Fire Hose Stations 3-57 3.14.6' Fire Barrier Penetration Fire Seals 3-58 155><-3.15 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-60 3.16- RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3-63 3.17 LIQUID EFFLUENTS 3-70 3.17.1 Concentration 3-70 1
-3.17.2 Dose 3-71 3.17.3 Liquid Holdup Tanks 3-72 155>< 3.17.4 Liquid Eff'1uent Radwaste Treatment 3-72a 3.18 GASE0US EFFLUENTS 3-73 3.18.1 Dose Rate 3-73 155, 3.18.2 Dose-Noble Gases 3-74 3.18.3 Dose-Iodine-131, Iodine-133. Tritium, and Radioactive Materials in Particulate Fonn 3-75 L
3.18.4 Gaseous Radwaste Treatment 3-78 - 3.18.5 Gas Storage Tanks 3-79 3.19 DELETED ,
< 3.20 DELETED 3.21 SOLID RADIOACTIVE WASTES 3-80 3.22 RADIOLOGICAL ENVIRONMENTAL MONITORING 3-81 l
3.23 LAND USE CENSUS 3-87 3.24 EXPLOSIVE GAS MIXTURE 3-89 3.25 FUEL CYCLE DOSE 3-90 : 3.26 INTERLABORATORY COMPARISON PROGRAM 3-92 Proposed Amendment No. 155 iv
RANCHO SECO UNIT 1 .
. TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued)
Page Section , 4-47 4.14 SHOCK SUPPRESSORS-(SNUBBERS) 4-48 4.15 RADI0 ACTIVE MATERIALS SOURCES 4 49 4.16 Reserved . 4-51 4.17 STIAMGENERATORS Steam Generatur Sample Selection and Inspection 4-51 4.17.1 Steam Generator Tube Sample Selection and Inspection 4-51 4.17.2 I.nspection Frequencies 4-52 4.17.3 4.17.4 Acceptance Criteria 4-53 4.17.5 Reports 4-54. 4.17.6 OTSG Auxiliary Feedwater Header Surveillance 4-54 4.17.7 4-55 Inspectjon Acceptance Criteria and Corrective Actions-4.17.8 Reports 4-55 4.18 FIRE SUPPRESSION SYSTEM SURVEILLANCE 58
'155>< 4.19 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION 4-63 4.20 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 4-65 .
4.21 LIQUID EFFLUENTS 4-69 4.21.1 Concentration 4-69 15 5> < 4. 21. 2 Doses 4-72 4.21.3 Liquid Holdup Tanks 4-73 155> 4.21.4 Liquid Effluent Radwaste Treatment 4-73a Proposed Amendment No. 155 Vi _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _m _ . . _ . . . _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ -_._ - _ _ . _ _ _ _ _ _
I RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Cortinued) Section Page 155> 4.22 GASEOUS EFFLUENTS 4-74 4.22.1 Dose Rate 4-74 4.22.2 Dose-Noble Gases 4-77 4.22.3 Dose-Iodine-131, Iodine-133, Tritium, add Radioactive Materials in Particulate Form 4-79 4,22.4 Gaseous Radwaste Treatment 4-79 4.22.5 Gas Storage Tanks 4-80 4.23 Deleted 4-79 4.24 Deleted 4-80 4 4.25 SOLID RADIOACTIVE WASTES 4-81 4.26 RADIOLOGICAL ENVIRONMENTAL MONITORING 4-83
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4.27 LAND USE CENSUS 4-86 I 4.28 EXPLOSIVE GAS MIXTURE 4-87 4.29 FUEL CYCLE DOSE 4-89 'f 4.30 INTERLABORATORY COMPARISON PROGRAM SURVEILLANCE REQUIREMENT 4-90 4.31 NUCLEAR SERVICE ELECTRICAL BUILDING EMERGENCY HEATING 4-91 , VENTILATION AND AIR CONDITIONING 5.0 DESIGN FEATURES 5-1 i 5.1 SITE 5-1 l 155> 5.1.1 Exclusion Area 5-1 5.1.2 Low Population Zone 5-1 ! 5.1.3 Site Boundary for Gaseous Effluents 5-1 l 5.1.4 Site Boundary for Liquid Effluents 5-1 4 Proposed Amendment No. 155 vii h________
d 155> RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued) Page Section 5-2 5.2 CONTAINMENT 5.2.1 Reactor Building 5-2 Reactor Building Isolation System 5-3 5.2.2 5.3 REACTOR 5-4 5.3.1 Reactor Core 5-4 5.3.2 Reactor Coolant System 5-4 5.4 NEW AND SPENT FUEL STORAGE FACILITIES 5-6 5.4.1 New Fuel Inspection and Temporary Storage Rack 5-6 5.4.2 New and Spent Fuel Storage Racks and Failed 5-6 Fuel Storage Container Rack 5.4.3 New and Spent Fuel Temporary Storage 5-6 5.4.4 . Spent Fbel Pool and Storage Rack Design - 5-6 3 Proposed Amendment No. 155 *
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I < l I RANCHO SECO UNIT.1 TECHNICAL EFECIFICATIONS , ' TABLE OF CONTENTS (Continued). l l
'Section Pace 6 ADMINISTRATIVE CONTROLS 6-1 6.1- RESPONSIBILITY 6-1 6.2 ORGANIZATION 6-1 6.3 FACILITY STAFF QUALIFICATIONS 6-3 6.4 -TRAINING 6-3 6.5 REVIEW AND AUDIT 6-3 i
155++ 6.5.1 Plant Review Connittee 6-3 6.5.2 Manaaement Safety Review Committee 6-6 138+ 6.5.3 Technical steview and Control 6-3
- 6.5.4 Audits 6-9 6.6 REPORTABLE OCCURRENCE ACTION 6-10 6.7 SAFETY LIMIT V10LATION 6-11 Ri 6.8 PROCEDURES 6-11 j 6.9 REPORTING REQUIREMENTS 6-12 6.10 RECORD RETENTION 6-13 6.11 RADIATION PROTECTION PROGRAM 6-14 6.12 RESPIRATORY PROTECTION PROGRAM - Deleted 6.13 HIGH RADIATION AREA 6-15 6.14 ENVIRONMENTAL QUALIFICATION 6-16 6.15 PROCESS CONTROL PROGRAM (PCP) 6-17 1554 6.16 0FFSITE DOSE CALCULATION AND RADIOLOGICAL MONITORING e PROGRAM MANUALS 6-18 6.17 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS !
[ LIQUID. GASEOUS. AND SOLIO1 6-19 6.18 POSTACCIDENT SAMPLING 6-22 Proposed Amendment No.138, nev. 2 Proposed Amendment No. 155 viii )
l l RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST OF TABLES ( Page Section ' 1-10 155>4 1.9-1 FREQUENCY NOTATION 2-9 2.3-1 REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS 3-27
- 3. 5.1-1 INSTRUMENTS OPERATING CONDITIONS 3.5.5-1 ACCIDENT MONITORING INSTRUMENTATION OPERABILITY REQUIREMENTS 3-38b 3-40 3.6-1 SAFETY FEATURES CONTAINMENT ISOLATION VALVES 3.7-1 VOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3-4la 3-41b 3.7-2 YOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 3.12-1 SAFETY RELATED HYDRAULIC SNUBBERS 3-51a-e 3.14-1 FIRE DETECTION INSTRUMENTS FOR' SAFETY SYSTEMS 3-55' 3.14-1 INSIDE BUILDING FIRE HOSE STATIONS 3-57a 3.15-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-61 3.16-1 RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION 3-64 Ai. 3-83
- 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.22-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS 3-86 IN ENVIRONMENTAL SAMPLES ,
4.1-1 INSTRUMENT SURVEILLANCE REQUIREMENTS 4-3 4.1-2 MINIMUM EQUIPMENT TEST FREQUENCY 4-8 4.1-3 MINIMUM SAMPLING FREQUENCY 4-9 4.2-1 CAPSULE ASSEMBLY WITHDRAWAL SCHEDULE AT DAVIS-BESSE 1 4-12b 4.10-1 ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-42 , 4.10-2 OPERATIONAL ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-22a l Proposed Amendment No. 155 ix j 9
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o.; . l-- , RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST 0F TABLES (Continued): Page Section ! 4.14-1 DESIGNATED SAFETY RELATED HYDRAULIC SNUBBERS FUNCTIONALLY 4-47d e TESTED ONLY AS REQUIRED BY THE SNUBBER' SEAL REPLACEMENT-PROGRAM 4.17-1. MINIMUM NUMBER OF STEAM GENERATORS TO BE. INSPECTED- 4-56 j
.DURING INSERVICE INSPECTION 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-57 4.17-2B STEAM GENERATOR TUBE INSPECTIGN (SPECIAL LIMITED AREA)' 4-57a )
4.17-3 OTSG AUXILIARY FEEDWATER HEATER SURVEILLANCE 4-57b,c 4.19-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING. INSTRUMENTATION 4-64 I SURVEILLANCE REQUIREMENTS 4.20-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 4-66 l SURVEILLANCE REQUIREMENTS l 4.21-1 RADI0 ACTIVE LIQUID WASTE ShMPLING AND ANALYSIS PROGRAM 4-70
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l 4.22-1 RADICACkIVEGASEOUSWASTESAMPLINGANDANALYSISPROGRAM 4-75
.4.26-1 MAXIMUM VALUES,FOR THE LOWER [IMITS OF DETECTION (LLD). 4-84 1 'if-4.28-1 EXPLOSIVE GAS MIXTURc INSTRUMENTATION SURVEILLANCE 4-88 REQUIREMENTS ,
6-2 : 138s 6.2-1 MINIMUM SHIFT CREW COMPOSITION I i Proposed Amendment No. 138, Rev. 2 Proposed Amendment No.155 X e
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS , LIST OF FIGURES (Continueo) Figure 3.5.2-7 Core Imbalance vs. Power Level, O to 40 EFPD 3.5.2-8 Core Imbalance vs. Power Level, after 30 EFPD 3.5.2-9 Core Imbalance vs. , Power Level, after 300 EFPD with APSRs Withdrawn 3.5.2-10 Deleted 3.5.2-11 ' Deleted 3.5.2-12 Deleted 3.5.4-1
- Incore Instrumentation Specification Axial Imbalance Indication 3.5.4-2 Incore Instrumentation Specification Radial Flux Tilt Indication j 3.5.4-3 Incore Instrumentation Specification i
3.18-1 General Layout of Site 4.13-1 Main Steam Inservice Inspection 4.13-2 Main Feedwater Inservice Inspection l 1 4.13-3 Main Steam Dump Inservice Inspection 155> 5.1-1 Exclusion Area 5.1-2 Low Population Zone 5.1-3 Site Boundary for Gaseous Effluents
< 5.1-4 Site Boundary for Liquid Effluents 138> 6.2-1 SMUD Corporate Support of Nuclear Safety to Rancho Seco 4 6.2-2 Nuclear Organization Chart Proposed Amendment No. 138, Rev. 2 Proposed Amendment No. 155 xii
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'155>. i:
l TABLE 1.9-1 ' ( 1 - FREQUENCY NOTATION l l l -f NOTATION FREQUENCY 1 I j S At least once per.12 hours. 1 At least once per 24 hours. J 0~ i
'W At least once per 7 days. ,
l: M At least once per 31 days. ' q - At least once per 92 days. SY At least once per 184 days. A At least once per 12 months R At least once per 18 months. BA At least once per 24 months S/U Prior to each reactor startup. P Completed prior to each release. NA No, t applicable. a Proposed Amendment No. 155 1-10 4 e 1
I - RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls RESPONSIBILITIES (Continued) l h. Performance of special reviews and investigations and reports 138>< thereon as requested by the AGM, Nuclear Power Production. 138> 1. Review of the Plant Security Plan and changes thereto. i J. Review of the Emergency Plan and changes thereto.
- k. Review of changes to the PROCESS CONTROL PROGRAM, the DFFSITE ,
155> DOSE CALCULATION MANUAL and the RADIOLOGICAL ENVIRONMENTAL
- MONITORING PROGRAM MANUAL. (See Specifications 6.15 and 6.16.)
- 1. Review of major changes to the Radioactive Waste Treatment Systems (Liquid, Gaseous and Solid), and all information required
< by Specification 6.17.
l 155> m. Review of any accidental, unplanned, or uncontrolled release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence, anu the forwarding of these reports to the Nuclear Plant Mhnager and to the
< MSRC.
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AUTHORITY I 6.5.1.7 The Plant Review Comittee shall: 138>< a. Recommend in writing to the AGM, Nuclear Power Production approval or disapproval of items considered under 6.5.1.6(a) through 155>< (m) above,
- b. Render determinations in writing with regard to whether or not 155>< each item considered under 6.5.1.6(a) through (e), and (1) above constitutes an unreviewed safety question.
- c. Provide imediate written notification to the Chairman of the Management Safety Review Comittee of disagreement between the 138> PRC and the AGM, Nuclear Power Production; however, the AGM, 4 Nuclear Power Production shall have responsibility for resolution of such disagreements pursuant to 6.5.1.1 above.
RECORDS 6.5.1.8 The Plant Review Committee shall maintain written minutes of each j 138> meeting and copies shall be provided to the AGM, Nuclear Power
< Production and the Chairman of the Management Safety Review ,
Committee. Proposed Amendment No. 138, Rev. 2 Proposed Amendment No. 155 6-5 \
- L RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS
'
- Administrative Controls 138>< 6.5.4 (Continued) .
- a. - The conformance of facility oj>eration to all provisions contained within the Technical Specifications and, applicable license conditions at least once per year.
- b. The perfomance, training and qualifications of' the District's entire facility technical staff at least once per. year.
- c. The result of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or methods of operation that affect nuclear safety at least once per six 138,4- months for those changes not previously audited,
- d. The performance of all activities required by the Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per two (2) years.
- e. The Facility Emergency Plan and implementing procedures at least once per two (2) years.
- f. The Facility Security Plan and implementing procedures at least once per two (2) years,
- g. Any other area of facility operation considered appropriate by 138'> < the MSRC, Deputy General Manager, Nuclear or the General Manager.
- h. Compliance with fire protection requirements and implementing procedures at least once per two (2) years.
,d
- i. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified .,
offsite licensee personnel or an outside fire protection firm.
,j . An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than three (3) years.
- k. The radiological environmental monitoring program and the results thereof at least once per 12 months.
- 1. The OFFSITE DOSE CALCULATION MAtlVAL and implementing procedures at least once per 24 months.
155> m. The PROCESS CONTROL PROGRAM and implementing procedures for
< processing and packaging of radioactive wastes from liquid sy<, tens at least once per 24 months. ,
155> n. The performance of activities required by the Quality Assurance
< Program for Effluent Control' and Environmental Monitoring.
138, Audit reports of reviews encompassed by Section 6.S.4 shall be forwarded to the General Manager, USRC Chairuan, and to the managenent
, positions responsible for the areas reviewed within
< 30 davs ef ter cerraletion.
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f < RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS , <
}, 1 Administrative Controls g
6.7 SAFETY LIMIT VIOLATI6 1 j ' s / 6.7.1 The following actions shafdhe 'cah' in the event a Safety,aii it,is violated: 4 1, The provisions of 10 CFi 50.W (c) (1) (1) and 10 CFR 30l? shall a. be complied with. X h' a- , 138> b. The NRC Operaticns Center shall be notified by telephone as soon I F as possible and in all cases within one hour. The Director, i Nuclear Operations and Maintenance, the AGM, Nuclear ?ower Production, and the Chaiman of the MSRC shall be notified
< within 24 hours.
- c. A Safety Limit Violation Report shall be prepared. The report ' I shall be reviewed by the PRC. This report shall describe (1) -
1 applicable circumstances preceding the violation, (2) effects of the violation upon facility compc-nents, systems or structures, and (3) corrective action taken to ,9revent recurrence.
<y <
- d. The Safety Limit Violation Report shisl be submitted to the 138> Commission, the MSRC, and the AGM, Nuclear Power Production,
< within 14 days of the violation.
6.8 , PROCEDURES' 6.8.1 Written procedures shall be established, implemented ar.d maintained , covering the activities referenced t'elow:
- a. The applicable procedures Sc'omended in Appendix "A" of Regulatory Guide 1.33, Nov%ber 1972} ij t l
.l -
I b. Refueling operations., '
- c. Surveillance and test activitie;s of s'afety related equipment. I
- d. Security Plan implementation. -
- e. Emergency Plan implementaticra. ,
- f. Fire Protection Procedures implementation.
155> g. PROCESS CONTROL PROGR44 implementation.
- h. OFFSITE DOSE CALCULATION MANUAL implementation.
- 1. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MAHUAL implementation.
J. Quality Assurance Program for the Effluent Control and Environmental Monitoring using the guidance of Regulatory Guide
< 4.15, Revision 1, February 1979.
138> 6.8.2 Each procedure of 6.8.1 above and changes thereto shall, be reviewed
< and approved as set forth in Specification 6.5. i Proposed Amendment No.138, Rev. 2 froposed Amendment No. 155 6-11
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iz \ - RANCHO SECO UNIT 1 P TECHNICAL SPECIFICATIONS
- ,' Administrative Controls ;
6.8 PROCEDURES (Continued) 6.8.3 Temporary changes to procedure 6.8.1 above may be made provided:
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- a. The intent of the original procedure is not altered.
;' b. The change is approved by two members of the plant management s staff, at least one of who:n holds a SeMor Reactor Operator's
[ License on the unit affected. t, i
' ', c. The charge is documented, reviewed by the PRC and approved by the Plant Superintendent within seven (7) days of implemen-
~- tation.
"6.9 REPORTING REQUIREMENTS 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 Director of the Regional Office of Inspection and Enforcement unless otherwise noted.
Startup Report 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitt following (1) Receipt of an operating license; (2)
'- amentnent of the license involving a planned increase in power level; (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier; and (4) modifications that :nay have significantly altered the nuclear, thermal or hydraulic performance of the plant. The 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 comparison of these values with design predictions and specifications. Any corrective acticns that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
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- 6. 9.1.2 - dartup reports shall be submitted within (1) Ninety (90) days follo'ang completion of the startup test program; (2) Ninety (90) days following resumption or commencement of commercial power operation; or (3) Nine (9) months following initial criticality, whiclaver is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test *:
progrno and resumption or commencement of conraercial power operaf; ion), supplementary reports shall be submitted at least every .?)3 . three (3) nonths until all three events have been completed. l s Propo M Amendment No. 155 s i,-12
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I n D RANCHO SECO. UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls
'155>< 6..9 2 Radiological Reports 6.9.2.1. Annual Radiological Reports Annual reports covering the activities of the unit;~ as described l 155>- below, for the previous calendar year chall be submitted as follows:
6.9.2.1.1 Annual Occupational' Radiation Exposure Report The Annual Occupational Radiation Exposure Report shall be submitted to the Commission within the first calendar quarter of each calendar year in compliance with 10CFR20.407. 6.9.2.1.2 Annual Exposure Report The Annual Exposure Report shall be submitted to the Commission within the first cale1dar quarte'r of each calendar year in 4 accordance with the (,oidance contained in Regulatory Guide 1.16. 6.9.2.2 Annual Radiological Environmental Operating Repor_t 155>< 6.9.2.2.1 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar 155>< year khall be submitted prior to May 1 of each year. g' 155>< 6.9.2.2.2 The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activ6 ties for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports, and an . - assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the 155 o Land Use Census required by Specification 3.23. If hannful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem. 155>< l Proposed Amendment No. 155 6-12a
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls
.6.9.2.2.2 (Continued) -
- 155>< The Annual Radiological Environmental Operating Repor'ts shall 138> include summarized and tabulated results of all radiological 14 envi.ronmental . samples taken during the report period. In the
, v eve.nt .that some results are not a~ ailable.for inclusion.with the report, the report shall be.. submitted noting and explaining' the reasons for 'the missing results. The. missing data'shall be sub'mitted as soon as possible in a supplementary report.
The reports shall also include the following: a summary 155> description of the Radiological Environmental Monitoring
< Program; including . sampling methods for each sample type,. size and physical characteristics of.each sample type, sample preparation methods, analytical' methods, and measuring equipment usedL a map of all sampling locations keyed to a table giving dist'ances and directions from one reactor; the result'of land use censuses,. and.the results of-licensee participation in 'the Interlab' Comparison Program. The innual . report shall also .
155> include informatiori related to 5 specification 4.29, Uranium Fuel
< Cycle Dose.
6.9.2.3 Se"niannual ' Radioactive' Effluent Release Report 155><' Routine Se'miannual Radioactive Effluent Release Reports covering.the
- operatioit ofgthe' unit .during 'the previou_s .six moriths of operation shall be submitted within 60 days after January 1 and. July' 1 of 'each year. -
155>< ~ 155>< 6.9.?.3.1. The Semiannual Radioactive Effluent Release Reports shall include a summary of the ' quantities o.f radioactive liquid arid gaseou_s effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and ~' Reporting Radioactivity in Solid WastesJand Releases of Radioactive. Materials in Liquid' and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," with data summarized on a quarterly basis, following the format of Appendix B thereof. 155> The Semiannual Radioa.ctive Effluent Release Report shall i_nclude a summary of hourly meteorological data collected over the
< report period.
Proposed Amendment No.138, Rev. 2 Proposed Amendment No.155 6-12b 4 h ___ _ _ _ _ _ _ - _ _ _ _ _ _ _
p RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.9.2.3.1 Continued) 155o The Semiannual Radioactive Effluent Release Reports shall include an assessment of the radiation doses from radioactive gaseous and liquid effluents to individuals due to their 155 o activities inside the site boundary (Figures 5.1-3 and 5.1-4) during the report period. All assumptions used in making these assessments (e.g., specific activity, exposure time, and location) shall be included in these reports. 155 o The Semiannual Radioactive Effluent Release Reports shall include the following infonnation for all unplanned releases to unrestricted areas of radioactive materials in gaseous and liquid effluents:
- a. A description of the event and equipment involved.
- b. Cause(s) for the unplanned release.
- c. Actions taken to prevent recurrence.
- d. Consequences of the unplanned release.
The radioactive effluent release reports shall include an assesshent of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar . I quarter, as outlined in' Regulatory Guide 1.21. The assessment of radiation doses shall be performed in accordance with the 1554 0FFSITE DOSE CALCULATION MANUAL (ODCM). The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the - PROCESS CONTROL PROGRAM (PCP), RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL and 0FFSITE DOSE CALCULATION MANUAL (0DCM) pursuant to Specifications 6.15 and 6.16 as well as any major changes to Liquid, Gaseous or Solid Radwater Treatment Systems pursuant to Specification 6.17. The Semiannual Radioactive Effluent Release Report shall include tables for comparison with Specifications 3.17.2, 3.18.2, and 3.18.3. The July-December report shall include a summary table for comparison with the annual values in Specifications 3.17.2, 3.18.2, and 3.18.3. The Semiannual Radioactive Effluent Release Report shall also include events described in Specifications 3.17.1, 3.17.3, ( 3.18.1 and 3.20. Proposed Amendment No. 155 6-12c l k I
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls I 6.9.2.3.1 Continued) 155> ' The Semiannual Radioactive Effluent Release Report shall include the following infomation for each type of solid waste shipped offsite during the report period: a.' Container volume,
- b. Total curie quantity (determined by measurement or estimate),
- c. Principal radionuclides (determined by measurement or
- estimate),
- d. Type of waste (e.g., spent resin, compacted dry waste evaporator bottoms),
- e. Type of container (e.g., LSA, Type A, Type B, High j Integrity), and L f. Solidification agent (e.g., cement)..
MONTHLY REPORT 6.9.3 Routine reports of operating statistics, including narrative sumary of operating and shutdown experience, of lifts of the Primary System , ;;j : Safety Valves or EMOVs, of major safety related maintenance, and tabulations of facility changes, tests or experiments required pursuant to 10 CFR 50.59(b), shall be submitted on a monthly basis to the Office of Director of Inspection and Enforcement, U. 'S. Nuclear Regulatory Commission, Washington, D. C. 20555, with a copy to .the ' Regional Office, postmarked no later than the 15th day of each month following the calendar month covered by the report. LICENSEE EVENT REPORT l- 6.9.4 The LICENSEE EVENT REPORTS of Specification 6.9.4.1 below, including l corrective actions and measures to prevent recurrence, shall be I reported to the NRC as Licensee Event Reports. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a License Event Report shall be completed and reference shall be made to the original report date, pursuant to the requirements of 10 CFR 50.73. 4
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Proposed Amendment No. 155 6-12d
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls LICENSEE EVENT REPORT 6.9.4.1 The types of events listed below shall be the subject of written l reports to the Director of the Regional Office within thirty (30) ; days of occurrence of the event. The written report shall include, i as a minimum, a completed copy of a licensee event report form, pursuant to 10 CFR 50.73 and the guidance of NUREG-1022.
- a. (1) The completion of any nuclear plant shutdown required by the plant's Technical Specification; or (ii) any operation or condition prohibited by the plant's Technical Specifications; or (iii) Any deviation from the plant's Technical Specifications authoiized pursuant to 10 CFR 50.54(x). l
- b. Any event or condition that resulted in the condition of tiie nuclear power plant, including its principal safety barriers, being seriously degraded, or that resulted in the nuclear power plant being:
(i) In an unanalyzed condition that significantly compromised plant safety; (ii)inaconditionthatwasoutsidethedesignbasisofthe plant; or
+
(iii) In a condition not covered by the plant's operating and emergency procedures.
- c. any natural phenomenon or other external condition that posed an actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of duties necesscry for the safe operation of the nuclear power plant.
- d. Any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS). However, actuation of an ESF, ,
including the RPS, that resulted from and was part of the i preplanned sequence during testing o,r reactor operation need not be reported.
- e. any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to:
- 1. Shut down the reactor and maintain it in a safe shutdown '
condition; Proposed Amendment No.155 b- -
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls LICENSEE EVENT REPORT
- 2. Remove residual heat;
- 3. Control the release of radioactive material; or
- 4. Mitigate the consequences of an accident.
- f. Events covered in paragraph 6.9.4.1.e of this section may include one or more procedural errors, equipment failures, and/or discovery of design, analysis, fabrication, construction, and/or procedural inadequacies. However, individual component fa,ilures need not be reported pursuant to this paragraph if redundant equipment in the same . system was operable and available to perform the required safety function.
- g. Any event where a single cause or condition caused at least one independent train or channel to become inoperable in multiple systems or two independent trains or channels to become inoperable in a single system designed to:
- 1. Shut down the reactor and maintain it in a safe shutdown condition;
- 2. Remove residual heat;'
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- 3. Control- the release of radioactive material; or 3
- 4. Mitigate the consequences of an accident.
- h. 1. Any airborne radioactivity release that exceeded 2 times the applicable concentrations of the limits specified in Appendix B, Table II of 10 CFR 20 in unrestricted areas, q when averaged over a time period of one hour. l
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- 2. Any liquid effluent release that exceeded 2 times the limiting combined Maximum Permissible Concentration (MPC)
(see Note 1 of Appendix B to 10 CFR 20) at the point of entry into the receiving water (i.e., unrestricted areal for_all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour.
- 1. Any event that posed an actual threat to the safety of the nuclear power plant or significantly hampered site personnel in l
)
the performance of duties necessary for the safe operation of the nuclear power plant including fires, toxic gas releases, or radioactive releases.
- j. Failure of the pressurizer EMOVs or Primary System Safety Valves.
Proposed Amendment No.155 e e l _ - _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ . 1
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS j Administrative Controls Special Reports i 6.9.5 Special reports shall be submitted to the Regional Administrator, j
. Region V Office, within the time period specified for each report. j These. reports shall be submitted covering the activities identified i'
below pursuant to the requirements of the applicable reference specification: A. A one-time only, " Narrative Summary of Operating Experience" will be submitted to cover the transition period (calendar year 1977). B. A Reactor Building Structural integrity report shall be submitted within ninety (90) days of completion of each of the l l following tests covered by Technical Specification 4.4.2 (the integrated leak rate test is covered in Technical Specification 4.4.1.1). -
- 1. . Annual Inspection
- 2. Tendon Stress Surveillance
- 3. End Anchorage Concrete Surveillance
- 4. Liner Plate Surveillance C. Inserhice Inspection Program 4 D. Inoperable Accident Monitoring Instrun>entation 30 days (3.5.5)
E. Status of Inoperable Fire Protection Equipment F. Inocerable Emergency Control Room /TSC Ventilation Room Filter System n G. Radioactive Liquid Effluent Dose 30 days (3.17.2) H. Noble Gas Limits 30 days (3.18.2) I. Radioiodine and Particulate 30 days (3.18.3) 155> J. Gaseous and Liquid Radwaste Treatment 30 days (3.18.4 and 3.17.4)
< K. Radiological Environmental Monitoring Program 30 days (3.22)
L. Monitoring Point Substitutions 30 days (3.22) 155>< M. Solid Radioactive Wastes 30 days (3.21) N. Fuel Cycle Dose 30 days (3.25) 155>< 0. Land Use Census 30 days (3.23) P. Steam Generator Tube Inspection 30 days (4.17.5) Proposed Amendment No. 155 155>< 6-129
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS i Administrative Controls
- b. ' Records of new and f rradiated fuel inventory, fuel transfers and
- assembly burnup histories.
- c. Records of facility radiation and conta' mination surveys. -
.d. Records of radiation exposure for all-individuals entering radiation control ~ areas.
- e. Records of gaseous.and liquid radioactive material released to the environs.
- f. Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
- g. Records of-training and qualification for current members of the plant operating staff.
- h. - Records of in-service inspections performed pursuant to these Technical Specifications.
- 1. . Records of Quality Assurance activities required by the QA Manual.
- j. Records of reviews performed for changes made to procedures or equipmen't or reviews of tests and experiments pursuant to 10 CFR 50.59.
N
- k. Records of meetings of the PRC and the MSRC.
- 1. Records- for Environmental Qualification which are covered under the provisions of. paragraph 6.14. .
155>< m. Records for the Radiological Environmental Monitoring Program.
- n. Records of the maintenance of all hydraulic snubbers listed in Table 3.12-1.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20, and shall be aoproved, maintained and adhered to for all ' operations involving personnel radiation exposure. 9 6.12 - Deleted 4 Proposed Amendment No. 155 6-14 l'
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls i 6.15 PROCESS CONTROL PROGRAM (PCP) t 6.15.1 Function 3 I 155> The PROCESS CONTROL PROGRAM shall contain the sampling, analysis, and
- formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured.
6.15.2 Changes A. The PCP shall be approved by the Commission prior to implementation. B. Licensee initiated changes to the PCP shall:
- 1. Be submitted to the Commission by inclusion in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was/were made and shall contain:
- a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information;
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- b. A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and i,
4
- c. Documentation of the fact that the change has been reviewed and found acceptable by the Plant Review Committee.
- 2. Become effective upon review and acceptance by the PRC, unless otherwise acted upon by the Commission through written notification to the Licensee.
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Proposed Amendment No.155 6-17 m _ _ _ _ _ _ _ _ _
)
l 1 1 1 RANCHO SECO UNIT 1 ]
. TECHNICAL SPECIFICATIONS ;
1 Administrative Controls j 1 155>< 6.16 0FFSITE DOSE CALCULATION AND RADIOLOGICAL ENVIRONMENTAL MONITORING' FRtXaRAM MANUAL 5 i 6.16.1 Function j 155> 6.16.1.1 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall describe the methodology and parameters to be used in the calculation of offsite 4 doses due to the release of radioactive material in gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCO's contained in these Technical Specifications. Methodologies and calculational procedures acceptable to the Commission are contained in various Regulatory Guides as noted in the. bases of applicable LCO's. 6.16.1.2 The RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) MANUAL shall be a manuel containing the description of the Rancho Seco Radiological Environmental Monitoring Program. The REMP manual shall contain a description of the environmental samples to be collected, the sample locations, sampling frequencies, and sample analysis criteria. 6.16.2 Any changes to the ODCM or REMP MANUAL shall be made as follows:
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Licensee-initiated changes: A.
- 1. Shall be submitted to the Commission by inclusion in the 155> Semiannual Radioactive Effluent Release Report for the 4 period in which the change (s) was/were made and shall contain:
~
- a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental infomation. Information .
submitted should consist'of a package of those pages ! 155>4 of the ODCM and the REMP MANUAL to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);
- b. A determination that the change will not reduce the accuracy or reli'.oility of dose calculations or setpoint deter:.f nations; and i
c Documenta$on of the fact that the change has been reviewea and found acceptable by both the PRC and MSRC.
- 2. Shall become effective upon a date specified and agreed to by both the PRC and MSRC following their review and acceptance of the change.
Proposed Amendment No. 155 6-18 L-___ _- _- _
RANCHO SECO UNIT 1 b
. TECHNICAL SPECIFICATIONS
[ Administrative Controls 6.17 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (LIQUID, GASEOUS, 1 AND SOLID) 6.17.1 Function The radioactive waste treatment system (liquid, gaseous, and solid) 155>< 'are those systems described in the facility Updated Safety Analysis Report or Hazards Summary Report, and amendments thereto, which are
- used to maintain that control over radioactive materials in gaseous and liquid effluents and.in solid waste packaged for offsite shipment required to meet the LCOs set forth in these Specifications.
6.17.2 Major changes to the radioactive waste systems (liquid, gaseous, and 138> solid) shall be 'made by the following method. For 'the purpose of this
< specification, " major changes' is defined in Specification 6.17.3.
.138> Licensee-initiated changes: ,
- 1. The Commission shall be informed of all changes by the inclusion of a suitable discussion of each change in the Semiannual Radioactive Release Report for the period in which the changes were made. The discussion of each change shall contain:
- a. A summary of the evaluation that led to the determination that the change could be made in accordance with_10 CFR 50.59;
- b. Sufficient infonnation to support the reason for the change without benefit of additional or supplemental information; lW
- c. A description of the equipment, components, and processes involved, and the interfaces with other plant systems;
- d. An evaluation of the change with regard to the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste if different from those previously predicted in the license application and amendments thereto; ,
155> e. An evaluation of the change with regard to the expected maximum exposures to a MEMBER OF THE PUBLIC in the
< UNRESTRICTED AREA and to the general population if different from those previously estimated in the license application and amendments thereto; Proposed Amendment No. 138, Rev. 2 Proposed Amendment No.155 6-19
s RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS ~ APPENDIX B
^
PAGE 1 1.0 DEFINITIONS 2.0 ENVIRONMENTAL PROTECTION CONDITIONS , 4 2.1 Deleted 2.2 Deleted 2.3 Deleted 2.4 Deleted 2.5 Deleted
- 155>< 2.6 Deleted 20 3.0 NON-RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE PROGRAMS 25 3.1 Erosion 25 3.2 Drift Contaminants 25 3.3 Deleted 3.4 Noise 26 3.5 Fogging 27 3.6 Deleted
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4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 31 4.1 Deleted 4.2 Deleted 4.3 Deleted 4.4 Deleted 4.5 Deleted . _d 4.6 Deleted 4.7 Deleted 4.8 Deleted 4.9 Deleted 4.10 Deleted 5.0 ADMINISTRATIVE CONTROLS 42 l
, 5.1 Responsibility 42
-5.2 Organization ' 42 5.3 Review and Audit 42 5.4 Action to be taken in Event of Violation of an Environmental Protection Limit 43 5.5 Procedures 44 5.6 Plant Reporting Requirements 44 5.7 Records Retention 46 5.8 Deleted i
l Proposed Amendment 155 , 1 l t
I
,155>
\ THIS PAGE HAS BEEN DELETED iii I
4 Proposed Amendment No. 155 t j g
- i l
= j
;v . j
4 155>. . l t-l'
\ THIS PAGE HAS 'BEEN DELETED i
( Proposed Amendment No.155
ATTACHMENT 3 Bases for Lower Limit of Detection Values for Rancho Seco Liquid Effluents i
4
's BASES FOR LOWER LIMIT OF DETECTION VALUES FOR RANCHO SECO LIQUID EFFLUENTS 4
M INTRODUCTION i 6 In a previous transmittal .1 to USNRC Region V, a statist- l ical basis for lower limit of detection (LLD) of radio-J nuclide concentrations in Rancho Seco effluents was estab- I lished. As indicated in that document, as the background for the analysis.of interest is lowered, the ratio of the dose represented by the LLD to the Technical Specification value also lowers. (Fig. 1) In the limit, as the background approaches 0, the ratio approaches 0.5. l The Sacramento Municipal Utility District proposes in this document a program which utilizes LLD's for the the liquid effluents at values which result in this ratio of 221 This program features a comprehensive management control and oversight process and dose tracking system. This approach is considered appropriate dce to the unusual characteristics . of the Rancho Seco site in which the liquid outfall of the site is the headwater of Clay Creek. Also, during much of the year, this flow also is a large part of the flow of Hadselville and Laguna Creeks. l The objective of this program is to achieve and maintain compliance to 10 CFR Part 50, Appendix I in a manner specific to the unusual environmental setting of the Rancho Seco site. 1 1 _ _ _ _ _ _ _ _ ________ _ _ _ _ _ i
J
'~
1 %. jLJ1 HISTORY The origina1LTechnica1' Specifications-for liquid efflue'nts were based on'two premises: (Fig. 2) (1) The concentrations in 10 CFR Part 20 applied; (2). Normal operation precluded radioactivity in the. secondary system, and thus'in the liquid effluents. , e However, steam generator 1 tube leaks developed. Radioact-l
'ivity began to. appear frequently in the liquid effluent in 1981.
In 1984, liquid effluent Technical Specifications were adopted which contained LLD values which corresponded directly to the values used for the " standard plant". These
~
values were used \ until it was determined that the calculated 1 doses associated with these values were somewhat in excess of the Technical Specification values. (Fig. 3) At that time, interim LLD's were adopted to bring the situation more _ in agreement with Appendix I. (Fig. 4) 4 Usage factors on the stream system also changed in 1985. Prior to 1985, the stream system was extensively used by area residents downstream from the site boundary fence.
. Individuals claimed to have large consumption of aquatic foods from this aren. After 1984, information from these )
individuals indicated that usage of the stream system upstream from Laguna creek has essentially stopped. In addition, the area shown in Figure 5 was posted as a "No 2
~
Trespassing, No Hunting, No Fishing" area. During the period 1981-84, a database was established for the quantities of radionuclides released in the liquid effluent. The data for gamma emitters are presented in Table 1. Note that Cs134 and Cs137 together comprise nearly half of the activity. These values are used as the histor-ical radionuclides mix for dose and LLD calculations.
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a h a 3
J_d DOSE 6EQ CONCENTRATION CALCULATIONS 3.1 Dose Calculation for Historical Mix The projected dose calculation methodology used at Rancho l Seco is based on Regulatory Guide 1.109 as implemented by the LADTAP software. This methodology was used to determine the fraction of total dose associated with each. radionuclides in the historical mix for the total body and for the most limiting organ for the nuclide. It was found that virtually all dose to the thyroid ir due to iodines, so the contri-bution from iodines was separated from the rest. The results are presented in Table 2. This table clearly indicates that Cs134 and Cs137 cre by far the major contri-butors to dose at 97.8% of the total body dose and 97.6% of the limiting organ dose. (Except thyroid)
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The FIRST PROPOSAL is that Cs134 and Csl37 will be 1 indicators for dose for all gamma-emitting radionuclides except iodines. Table 3 contains the resulting dose fractions. The usage factors established before 1985 will continue to be used to provide conservatism until the land use census currently underway has been completed and the data evaluated. 3.2 Concentration (LLD) Calculations In the methodology as implemented by LADTAP, dose is propor-tional to the total quantity of activity released, all other i factors being constant. Three of these factors are under operational control. (Fig. 6) The others are built in to the database for the Offsite Dose Calculation Manual. (ODCM) I
4
'o The three factors under operational control include: (Fig.
6) (1) Annual volume of liquid effluent released from Regenerant Hold-Up Tanks A & B (RHUT A & B) (2) Concentration of radioactive materials in the effluent (3) Flow rate at the site outfall. The flow rate at the site outfall is normally held constant at 5000 1 10% gpm.. The concentrations in question are the LLD's to be established. The annual volume through RHUT's A
& B is also considered to be constant at 20 million gallons.
With Cs134 and Cn137 as the dose indicators for all gamma emitters, except iodines, the concentration equivalent of dose at the Technical Specification values of 3 mrem total body and 10 mren organ is illustrated in Figure 7. A The SECOND PROPOSAL is to place the LLD equivalent of dose at 50% of the Technical Specification values. (Fig. 7) 3.3 Laboratory Significance The proposed LLD's are achievable with a modest upgrade in equipment in the facilities which are available. Counting
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times of 4000-6000 seconds are expected. State-of-the-art equipment and specialized facilities are not required to support the plant with reasonable delays. I l l 5 i
i f
'i,_Rl MANAGEMENT ANDLADMINISTRATIVE CONTROLS 4.1 Management Control-System The effluent control program has been in a continuous state of evaluation and. improvement since late 1985. One result has been to develop a comprehensive Effluent Oversight Control Program.
(EOCP) This program defines policy, responsibilities, and interfaces. The EOCP is derived from a foundation of Technical Specifications, Regulatory Guides, and Safety Analysis Report, Industry Standards, j and Standard District Instructions. (Fig. 8) It addresses all effluent. paths (gaseous, liquid, solid), below regulatory convern, and related programs such as meteorology. The policy document (Fig. 8) is the Effluent Oversight Control Management Process. It defines the functional areas which are subject to EOCP and the responsibilities of each organization
.which is linked to the Program. Indirect linkages, such as Training Department, are included. Ultimate responsibility for the Program at Rancho Seco is placed on the Chief Executive Officer, Nuclear. The Manager, Environmental Protection is responsible for the implementation of the Program.
The implementing document (Fig. 8) for the Management Process is the Effluent Control Manual. This manual addresses the following: . (1) EOCP goals and objectives (2) Measures of organizational performance, management involvement, and Station trends 6
(3) Functional and organizational interfaces (4) Definition of data and information management systems. As indicated, (Fig. 8) the Effluent Control Manual provides the interfaces among effluent control, offsite dose calculation, environmental monitoring, solid radwaste process control, engineering, and other related programs. The ALARA manual defines ALARA goals and objectives for all Rancho Seco functions, including EOCP. 4.2 Administrative and Operational Controls These ecntrols include three principal components: l (1) Definition of LLD's (2) Administrative limits for dose associated with effluent releases (3) Dose tracking. 4.2.1 The historical mix of radionuclides released in Rancho Seco liquid effluent provides the basis for establishing LLD's. The preceding discussion has shown that the presence or absence of dose associated with these releases can be very adequately indicated by a combination of Csl34, CS137, and I131. The concept of setting the LLD's at a concentration equivalent to 50% of the Technical Specification values has also been developed. The resulting LLD's for liquid effluent offsite dose tracking purposes are shown in Table 4. 4.2.2 The District recognizes that the specification of LLD's at relative high fraction of 0.5 of Technical Specif-7 l
ication requires consideration of a relatively large
" unknown dose". (Fig. 9) The THIRD PROPOSAL accounts for the " unknown" by establishing an offsite dose administrative limit which is the difference between the Technical Specification value and the LLD equiva-lent. Numerically, the administrative limits become:
.)
Total Body ~-- 1.5 mrem Any organ -- 5.0 mrem j For convenience, during the balance of this present- l ation all references will be to the total body number l of 1.5 mrem. l i If it becomes necessary to consider exceeding this administrative limit, a management and technical review will be peEformed to determine the available options. 1 Unless a monthly composite has an unexpectedly high ! result as described below, the dose tracking system 1 would provide early indication that exceeding the administrative limit is forecast. 4.2.3 The District has established and used a dose tracking system for liquid effluent releases. This system would' be modified to best suit the 50% LLD and the 1.5 mrem administrative limit. The existing sampling, monit-oring and reporting system will be used until the Radiological Effluent Information Management System (REIMS) becomes operational. All dose calculations are performed in accordance with ODCM methodology. Manage-8
ment approval is required prior to all releases. The information flow for dose tracking will be as follows: (Fig. 10) (1) Prerelease dose calculation (2) Postrelease dose calculation (3) Weekly review of release records and update of dose calculation (4) Monthly composite of all REUT A & B releases (5) Monthly inclusion of composite results in the dose calculation (6) Monthly update of the remaining operating margin (7) Quarterly review of all release data, recalcu-lation of dose and update of operating margin (8) Semiannual effluent report preparation. The doses when calculated are plotted on a cumulative chart and compared to a target vector. (Fig. 11) The relative position of t'eh cumulative dose line to the target is used as basis for decisions to perform opera-tions such as recycling and demineralizing. The update of the operating margin is performed to account for results obtained from the composite sample. The purpose has both positive and negative aspects. On the positive side, the remaining operating margin may be increased because the actual concentrations of radionuclides in the composite are less than the average of the LLD's and observable concentrations obtained in the release analyses. (Fig. 12) The negative is that the composite analyses may result in 9
unexpectedly.high average concentrations with an accom-panying reduction in the remaining operating margin. 73 4.3 . Radiological Effluent Information Management System A computer-based effluent information system is in the initial stages of installation. A schematic of this system is shown in Figure 13. As. indicated, Radiation Protection, Chemistry, Environmental Programs, and Health' Physics. Support will be 1, inked to a common database. One signif-icant advantage to this' system is that the personnel who perform prerelease dose calculations will be using the same model as those who perform the followup weekly and monthly calculations. Features such as data-in-erpected-range prompting'are to be included.. Personnel will be trained and the system will be carefully phased in and customized to
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Rancho Seco over'a period of a few months. Initial-produc-Y ! tion operation is scheduled for August 1, 1987. I i
)
1 10
M
SUMMARY
I The basis for a surveillance Technical Specification for 10 l l CFR Part 50 Appendix I compliance has been presented. Table 5 summarizes this Technical Specification. This Technical Specification establishes a method for compliance which takes into account the unique limnology of the Rancho Seco I site and the limitations of a well-equipped process analyt-ical laboratory. It provides reasonable assurance that the design guides in Appendix I will not be substantially exceeded
<nven under nominally adverse conditions. As bacicap and confirmation of the effluent control program, the District operates a comprehensive environmental monitoring program in the liquid effluent pathway.
j,,_Q REFERENCES ,
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6.1 Oesterling, R. G., Development of Target Dose Values for Appendix 1 I Compliance, March 16, 1987 r 1 l 11 1
) >\
LOWER LIMIT OF DETECTION SPECIFICATION: (r INSERT FOR TECIIHICAL SPECIFICATION TADMS 4.21-:1, 4.21-2 an E4.22-1' '
> n
- a. (1) The lower limit of detection (LLD) for a radionuelldo presented in this table is tze: largest concentration, expressed in microcuries'per ua.it volume, which is required to be detected in order to achieve conpliance with the applicable regulation, given stated opeteting conditions and calculation methodology.
(2) TheLLDofaradioanalysissystemisthaNvaluewhichwill indicate the presence or absence of radioactivity in a sample when the probabilities of a f alse pcsitive and of a false negative determination ate stated. The probabilities I of false positive and false nogative are taken as equal at 0.05. The equation for LLD in microcuries per unit volume is given by the equation: LLD = 2.71 + 3.29(Br)0.5 3.Y0E4(YEVT) (3) Definitions of terms: 2.71 = factor to account for Poisson distribution at very low background sount rates 4 When background is estimated from a blank whicn haa 'oeen counted for a specific period, the following appliee-B = estimated background (counts) t s
=b t b
b = blank background (counts) tb = blank count time (seconds) ts = sample count time (seconds) t s r=1+ b 3.70E4 = disintegrations /second/ microcurie Y= yield of radiochemical processes, i.e., the product of all factors such as emission fraction, chemical yield, etc. E= counting efficiency (count / disintegration) V= sample volume Table 4.21-1 -- milliliter Table 4.21-2 -- milliliter Table 4.22-1 -- cubic centimeter
rz-- ,
'C* I
.s , ., ' '
[1 - erp(-At g)]exp(-At c)
%" T=
;r-g
;o .( e 0
A = decay constant (seconds -1) tc = time h om midpoint of collection period to start I
>f- of countirig ,
9 g- q (4)O WhenJsupectroscopy is used to analyze the sample, the j fo: lowing LLD equation is used: ! lr .
+ 4.65(B)O.5 i .'f, " ,2~23.70E4(YEVT) 1 Whsre Ex'is the counts in the Region of Interest.
j j
.f '
~
1 ,. l~, \
? , '
pt , ,n , a , , >- ,
.% 'l y .
9 5 \ 4
. >f t} 3 /\ '.
f , it _j [ s ,
"t k
s %
'+
i i l ) g
\
F
.(
- t. , .
l ; l BASIS FOR TECHNICAL SPECIFICATION LLD The equation for lower limit of detection is taken from Curriel, with minor modifications, as follows:
- 1. The systematic error has been determined to be negligible with respect to random error.
- 2. The factor "exp(-Atc)" to correct for decay time from
. collection to analysis is added for completeness.
- 3. The correction factor (2.71) for very low counts is added.
- 4. The nu symbol was replaced by "r".
Reference
- 1. Currie, L.A., Lower Limit of Detection: Definition and Elaboration 91 a Proposed Position foJt Radiological Ef fluent and Environmental Measurements, NUREG/CR-4007, Sept. 1984 1
)
a LOWER LIMIT OF DETECTION SPECIFICATION: i INSERT FOR TECHNICAL SPECIFICATION TABLE 4.26-1
- a. (1)'.The lower limit of detection (LLD) for a radionuclides presented in.this table is the largest concentration, expressed in picocuries per unit sample, which is required to be detected in order to achieve compliance with the applicable regulation, given stated operating conditions and calculation' methodology.
(2).' The-LLD of a radioanalysis system is that value which will indicate the presence or absence of' radioactivity in a sample when the probability of a false positive and of a false negative determination is stated. The probabilities of false-positive and false negative are taken as equal at 0.05. The. equation for LLD in picocuries per unit sample is given'by the equation: bb " 2.71 + 3.29(Br)0.5 3.70E4(YEVT) (3) Definitions of terms: 2.71 = factor to account for Poisson distribution at very low background count rates When background is estimated from'a blank which has been counted for:a specific period, the following applies: B= estimated background (counts) tg
=b t b
b = blank background (counts) tb = blank count time.(seconds) ts = sample count time (seconds) tg r=1+ t b 3.70E4 = disintegrations /second/ microcurie Y= yield of radiochemical processes, i.e., the product of all factors such as emission fraction, chemical yield, etc. E= counting efficiency (count / disintegration) V= sample volume in liters or cubic meters, or mass in kilograms 4 [1 - exp(-At g)]exp(-Aty T= y 1 = decay constant (seconds -1) tc = time from midpoint of collection period to start of counting (4) When spectroscopy is used to analyze the sample, the following LLD equation is used: LLD = 2.71 + 4.65(B)0.5 3.70E4(YEVT) Where B is the counts in the Region of Interest. l
BASIS FOR TECHNICAL SPECIFICATION LLD The equation for lower limit.of detection is taken from Currie l, with minor modifications, as follows:
- 1. The systematic error has been determined to be negligible with respect to random error.
.2. The factor "exp(-Atc)" to correct for decay time from collection to analysis is'added for completeness.
- 3. The correction factor (2.71) for very low counts is added.
- 4. The nu symbol was replaced by "r".
Reference
- 1. Currie, L.A., LQwRI Limit 2f Detection: Definition add Elaboration of a Proposed Position fqr Radiological Effluent and Environmental. Measurements, NUREG/CR-4007, Sept. 1984 1
9 1981-84 HISTORICAL MIX OF RADIONUCLIDES IN RANCHO SECO LIQUID EFFLUENTS ACTIVITY NUCLIDE FRACTION Cs137 0.307 Co58 0.261 Cs134 0.162 GRMMR Co60 0.068
. Mn54 0.032 EMITTERS La190 0.009
~
Ag110m .0.006 EXCLUDING 'Cs136 0.004 6 Hb95 0.0'04 IODINES' Cr51 0.003 Fe59 0.002 U Ba190 0.001 Na29 8E-9 ZrS5 GE-9 CoS7 , 1E-9 Sr89 2E-5 l I131 0.125 IODINES l 1133 0.015 , 9 TABLE 1 l - - _ _ - _ _ - - - _ - - - .- i
+ 4 DOSE FRACTIONS FOR ERCH NUCLIDE FORJTHE- 1981-84. MIX DOSE FRACTION FOR NUCLIDE TOTAL LIMITING NUCLIDE BODY ORGAN Cs137 0.525 0.595 Cs134 0.453 0.381 Co60 0.011 0.006 Mn54 0.004 0.006 i CoS8' O.004 0.004 GRHMR i Cs136 0.003 0.001 '
Ag110m 1E-4 SE-9 EHITTERS F 59 1E-9 '1E-9
.g Hb95 6E-6 0.006 '
EXCLUDING Ba190 4E-6 7E-9 Sr89 . 2E-6 2E-5 J
-10 DINES Ze95 1E-6 2E-5 CoS7 4E-7 6E-7 La190 SE-7 3E-5 Cr51 1E-7 2E-6 Na24 7E-8 2E-8 I131 SE-9 0.9996 10 DINES 1133 SE-7 4E-9 TABLE 2 L
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r ' S E N D O O N I T I S O L TE R E 8 8 7 C D AI T - - - I E S R E E E U N RU I T I TC O L I 2 5 5 N O C L - N R L . . . P I L E O EC t I P T C 1I I M
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. 2 :.. 2 L - LOWER LIl1ITS OF DETECTIDs CONCENTRATION l
[HICROCURIES\ NUCLIDE (HILLILITERj Cs it- ' . 2E-8 Cs137 5.5E-8 .
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. R V I E E A N V A E M R R C O E U R E P N R Q S E S L T P L MU E
T I S S T L A S O U S ER P S - M E O C R
I' ATTACHMENT 4 PROPOSED AMENDMENT NO.155
/
i i 1 1 l l l w_-_--_-
t Revision 1 Effective Pages Tech Spec Safety Analysis
.(1) 1- 9 Page 6 (2) 3-61 Page 13 (3) 3-62 Page 14 (4) 3-64 Page 25 (5) 3-65 Page 26 (6) 3-66 Page 27 (7) 3-67 Page 28 (8) 3-68 Page 29 (9) 3-69 Page 30 (10) 3-70 Page 33 (11) 3-72 Page 39 (12) 4-63 Page 88 (13) 4-64 Page 90 (14) 4-65 Page 93 (15) 4-69 Page 101 (16) 4-70 Page 105 (17) 4-71 Page 106 (18) 4-71a Page 106a (19) 4-71b Page 106b (20) 4-72 Page 108 (21) 4-72b Page 111 (22) 4-72c Page 112 (23) 4-72d Page 112a (24) 4-72e Page 112b (25) 4-76 Page 121 (26) 4-76a Page 121a (27) 4-76b Page 121b (28) 4-85 Page 139 (29) 4-85a Page 139a (30) 4-85b Page 139b
RANCHO SECO UNIT l' TECHNICAL SPECIFICATIONS TABLE OF CONTENTS Section Page 1.16. RESTRICTED AREA 1-7 1.17 SITE BOUNDARY 1-7 1.18 DOSE EQUIVALENT I-131 1-7 1.19 MEMBER (S) 0F THE PUBLIC 1-7 155> 1.21 MAXIMUM HYP'0THETICAL INDIVIDUAL 1-8 1.22 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM' MANUAL 1-8 1.23 LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM 1-8 1.24 VENTILATION EXHAUST TREATMENT SYSTEMS 1-9 1.25 PURGE - PURGING 1-9 1.26 VENTING 1-9 1.27 RADI0 ACTIVE EFFLUENT 1-9 4 \ 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2-1
.!!! 2.1 . SAFETY LIMITS, REACTOR CORE 2-1
- 2. 2 . SAFETY LIMITS, REACTOR SYSTEM PRESSURE 2-4 2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE INSTRUMENTATION 2-5 ,
3.0 LIMITING CONDITIONS FOR OPERATION 3-1 3.1 REACTOR COOLANT SYSTEM 3-1 3-1 3.1.1 Operational Components 3.1.2 Pressurization, Heatup, and Cooldown Limitations 3-3 3.1.3 Minimum Conditions for Criticality 3-6 3.1.4 Reactor Coolant System Activity 3-8 3.1.5 Chemistry 3-10 i Proposed Amendment No. 155 i l-L iia j i l C
4 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS-TABLE OF CONTENTS (Continued) Section' Page 3.14.5 Fire Hose Stations' 3-57 3.14.6 Fire Barrier Penetration Fire Seals 3-58 3-60 155>< 3.15 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3.16 RADI0 ACTIVE GASE0US EFFLUENT NONITORING INSTRUMENTATION 3-63 3.17 LIQUID EFFLUENTS 3-70 3.17.1 Concentration 3-70 3.17.2 Dose 3-71 3.17.3 Liquid Holdup Tanks 3-72 155>< 3.17.4 Liquid Effluent Radwaste Treatment 3-72a 3.k8 GASEOUS EFFLUENTS 3-73 3.18.1 Dose Rate 3-73 155> 3.18.2 Dose-Noble Gases 3-74 2 3.18.3 Dose-Iodine-131, Iodine-133, Tritium, and Radioactive Materials in Particulate Form 3-75 3.18.4 Gaseous Radwaste Treatment- 3-78 .) 3.18.5 Gas Storage Tanks 3-79 3.19 DELETED
< 3.20 DELETED 3.21 SOLID RADI0 ACTIVE WASTES 3-80 3.22 RADIOLOGICAL ENVIRONMENTAL HONITORING 3-81 3.23 LAND USE CENSUS 3-87 3-89 I 3 24 EXPLOSIVE GAS MIXTURE 3.25 FUEL CYCLE DOSE 3-90 3.26 INTERLABORATORY COMPARISON PROGRAM 3-92 i
i Proposed Amendment No.155 iv
\
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued) Section Page 4.14 'SH0CK SUPPRESSORS (SNUBBERS) 4-47 4.15 RADI0 ACTIVE MATERIALS SOURCES 4-48 4.16 Reserved 4-49 i 4.17 STEAM GENERATORS 4-51 4.17.1 Steam Generator Sample Selection and Inspection 4 4.17.2 Steam Generator Tube Sample Selection and Inspection 4-51 4.17.3 Inspection Frequencies 4-52 4.17.4 Acceptance Criteria 4-53 ! 4.17.5 Reports 4-54 4.17.6 OTSG Auxiliary Feedwater Header Surveillance 4-54 4.17.7 Inspection Acceptance Criteria and Corrective Actions 4-55 4.17.8 Reports 4-55 4.18 FIRE SUPPRESSION SYSTEM SURVEILLANCE 4-58 155>< 4.19 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4-63
~
4.20 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 4-65 4.21 LIQUID EFFLUENTS 4-69 4.21.1 Concentration 4-69
~
155>< 4.21.2 Doses 4-72
;l 4.21.3 Liquid Holdup Tanks 4-73
, 1 155> 4.21.4 Liquid Effluent Radwaste Treatment 4-73a Proposed Amendment No. 155 vi
6 RANCHO SECO UNIT-1
< TECHNICAL SPECIFICATIONS.
TABLE OF CONTENTS (Continued) Section Page
, 155> 4.22 GASEOUS EFFLUENTS ,} 4 4.22.1 Dose Rate 4-74
.h 4.22.2 Dose-Noble Gases 4-77 4.22.3 Dose-Iodine-131, Iodine-133, Tritium,-and Radioactive
~
Materials in Particulate Form 4-79 4.22.4 Gaseous Radwaste Treatment 4-79 4.22.5 Gas Storage Tanks 4-80 4.23 Deleted- 4-79 4.24 Deleted 4-80 4 4.25 SOLID RADI0 ACTIVE WASTES 4-81 4.26 RADIOLOGICAL ENVIRONMENTAL MONITORING 4-83
'4.27
\
LAND USE CENSUS 4-86 IE - 4.28 EXPLOSIVE GAS MIXTURE 4-87 4.29 FUEL CYCLE DOSE 4-89 4.30 INTERLABORATORY COMPARISON PROGRAM SURVEILLANCE REQUIREMENT 4-90 4.31 NUCLEAR SERVICE ELECTRICAL BUILDING EMERGENCY HEATING 4-91 VENTILATION AND AIR CONDITIONING 5.0 DESIGN FEATURES 5-1 5.1 SITE 5-1 155> 5.1.1 Exclusion Area 5- 1 5.1.2 Low Population Zone 5-1 5.1.3 Site Boundary for Gaseous Effluents 5-1 j 5.1.4 Site Boundary for Liquid Effluents 5-1 { Proposed Amendment No. 155 i 1 vii 1
3
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.y RANCHO SECO UNIT- 1i c TECHNICAL SPECIFICATI0ir5' ,
i ; <./ i TABLE OF CONTENTS (Continued) s i Page Section, i 5.2 CONTAINMENT 5-2 5-2 '"- ' 5.2.1 Reactor Building
'h 5.2.2 Reactor Building isolation pystem . 5-3 5.3 REACTOR 5- 4 5.3.1 Reactor Core 5-4 4
5.3.2 Reactor' Coolant System 5-4 5.4 NEW AND: SPENT FUEL STORAGE FACILITIES 5-6 /
- l 5.4.1 NevFuel Inspection and Temporary Storage Rack 5-6 5.4.2 New and Spent Fuel Storage Racks and Failed 5-6 Fuel Storage Container Rack 5.4.3 New and Spent Fuel Temperary Storage 5-6 5.4.4 ppentFue\1 Pool and Storage Rack Design 5-6
>I ;
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l-Proposed Amendment No.155 viia
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F RANCHO SECO UNIT 1
' TECHNICAL SPECIFICATIONS 4- 't u , .
- 1, a <y ' y,<t TABLE OF CONTENTS (Continued)
/ \
l 3 , e ,
, , l ', c '.f '
Section ;- P_ age ; 6~ ADMINISTRATIVE CONTROLS 6b I 6.1 RESPONSIBILI 6-1 6.2 6-1 ORGANIZATION 7 l* 6.3 FACILITY STAFF QUALIFICATIONS 6-3 l 1 6.4 TRAINIVG 0 6-3 6.5 REVIEW AND AUDIT 6-3
., 5 155
- 6.5.1 Plant Review Committee 6-3 '
6.5.2 ManaaementSafety'ReviewCommittee 6-6 1384 6.5.3 Technical Review and Control 6-8 fr j
+ 6.5.4 Audits 6k9 6.6 REPORTABLE OCCURRENCE ACTION .6-10 6.7 SAFETY LIMIT VIOLATION 6-11 3 T 6.8 r 6'-11
. J_0.CiDJJRES 6.9 REPORTINGfif0VIREMENTS 6-12 d I 6.10 RECORD RETENTION ,
6-13 ' 6.11 'RADIATI,0N PROTECTION PROGRAM 6-14 I 6.12 RESPIRATORY PROTECTION PROGRAM - Deleted J 6.13 HIGH RADIATION AREA 6-15 I ef 6.14 JE-NVIRONMENTALQUALIFICATION 6-14 -ly e
/ i 6.15 PROCESS CONTROL PROGRAM (PCP) i 6-17 .,.
I 155+ 6.16 0FFSITE DOSE CALCULATION AND RADIOLOGICAL MPNITOR d' I
& P,ROGRAM MANUALS q 6-10 i l
6.17 hAJORCHANGESTORADI0ACTIVEWASTETREATMENTSYSTEMS #) )
-{A10010. GASEOUS. AND SOLID) 6213 6.18 POSTACCIDENT SAMPLING 6-22 Proposed Amendment No.138. Rev. 2 I Propcsed Amendment No. 155 vii) i ,
p _ _ _ _ _ _ - - - - - _ _ _ h. b'b u ., N . Qp?; w , b y,. (3 ' c p
<- ERANCHO SECO UNIT 1
,d-i ->- TECHNICAL ~ SPECIFICATIONS y
2 o 2- . LIST OF TABLES ^ ef 7(5 y 3 t
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/ Section i Page f: L 1-10 155 e .]*t.9 ^1 ) .a ' ' FREQUENCY NOTATION
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# 2.5-1 / REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS 2-9 g < -
INSTRUMENTS OPERATING CONDITIONS 3-27
- 3.5.1-1 [
3.5.5-1 " ACCIDENT MONITORING INSTRUMENTATION OPERABILITY REQUIREMENTS 3-38b j
.6-l' SAFETY FEATURES CONTAINMENT ISOLATION VALVES 3-40
,.3.7-1 VOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3-41a d# 3.7-2 VOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 3-41b 2a12-1 SAFETY'RELATED HYORAULIC SNUBBERS 3-Sla-e 3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS 3-55 4 h!3,14-1 INSIDE BUILDING FIRE HOSE STATIONS 3-57a
; 3 3.15-1 3-61 RADI0ACT{VELIQUIDEFFLUENTMONITORINGINSTRUMENTATION 3.16-1 RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION 3-64 J e 3-83 f 3.22-1 rah 10 LOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.22-2 REP'IRTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS 3-86 Ih;ENVIRONMENTALSAMPLES _
4.1-1 INSTRUfENT SURVEILLANCE REQUIREMENTS 4-3 4.1-2 MINIMUM EQUIPMENT TEST FREQUENCY 4-8 4.1-3 MINIMUM SAMPLING FREQUENCY 4-9 r . f- 4.2-1 CAPSULE ASSEMBLY WITHDRAWAL SCHEDULE AT DAVIS-BESSE 1 4-12b 4,: 4.10-1 ENVIRONMENTAL RADIATION MONITORING PROGRAM- 4-42
, 4.10-2 OPERATIONAL ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-22a 35i ,
s ( q\)! 9
.g .. Proposed Amendment No. 155 ix 9 i 1
t
t RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST OF TABLES (Continued) Section- Page 4-47d,e 4.14 DESIGNATED SAFETY RELATED HYDRAULIC SNUBBERS FUNCTIONALLY l TESTED ONLY AS REQUIRED BY THE SNUBBER SEAL REPLACEMENT PROGRAM 4;17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED 4 DURING INSERVICE INSPECTION 4.17-2A- STEAM GENERATOR TUBE INSPECTION' 4-57 4.17-28 -STEAM GENERATOR TUBE INSPECTION (SPECIAL LIMITED AREA) 4-57a 4.17-3 OTSG AUXILIARY FEEDWATER HEATER SURVEILLANCE' 4-57b,c 4.19-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4-64 SURVEILLANCE REQUIREMENTS 4.20-1 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION 4-66 SURVEILLANCE REQUIREMENTS 4.21-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAh 4-70 4.22-1 RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM 4-75 4.26-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) 4-84
$i:
4.28-1 EXPLOSIVE GAS MIXTURE INSTRUMENTATION SURVEILLANCE 4-88 . REQUIREMENTS 6-2
~
138>< 6.2-1 MINIMUM SHIFT CREW COMPOSITION Proposed Amendment No. 138, Rev. 2 Proposed Amendment No. 155 X
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST OF FIGURES (Continued) Figure 3.5.2 Core Imbalance vs. Power Level, O to 40 EFPD 3.5.2-8 Core Imbalance vs. Power Level, after 30 EFPD 3.5.2-9 Core Imbalance vs. Power Level, after 300 EFPD with APSRs Withdrawn 3.5.2-10 Deleted-3.5.2-11 Deleted 3.5.2-12 Deleted 3.5.4-1 Incore Instrumentation Specification Axial Imbalance Indication 3.5.4-2 Incore Instrumentation Specification Radial Flux Tilt Indication 3.5.4-3 Incore Instrumentation Specification 3.18-1 General Layout of Site
~
4.13-1 Main Steam Inservice Inspection 4.13-2 Main Fee'dwater Inservice Inspection g! 4.13-3 Main Steam Dump Inservice Inspection . 155> 5.1-1 Exclusion Area 5.1-2 Low Population Zone 5.1-3 Site Boundary for Gaseous Effluents
< 5.1-4 Site Boundary for Liquid Effluents 138> 6.2-1 SMUD Corporate Support of Nuclear Safety to Rancho Seco
< 6.2-2 Nuclear Organization Chart Proposed Amendment No. 138, Rev. 2 Proposed Amendment No.155 xii
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Definitions 1.11 FIRE SUPRESSION SYSTEMS l 1.11.1 The FIRE SUPRESSION WATER SYSTEM shall consist of water sources, pumps and distribution piping with associated sectionalizing control of isolation valves. Such valves include yard hydrant valves and the first valve ahead of the water flow alarm device on each sprinkler header, hose standpipe or spray system riser which protect nuclear safety components. 1.11.2 The FIRE SUPRESSION CARBON DIDXIDE SYSTEM shall consist of a CO2 source and distribution piping with sectionalizing control valves which protect nuclear safety components. 1.12 STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of: -
- a. A test schedule for n systems, subsystems, trains or designated components obtained by dividing the specified test interval into n equal subintervals.
- b. The testing of one system, subsystem, train or designated components during each subinterval.
155> 1.13 PROCESS CONTROL PROGRAM g PROCESS CONTROL PROGRAM (PCP) - The PROCESS CONTROL PROGRAM shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured. 1.14 SOLIDIFICATION SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides ( f ree-standing) . 4 Proposed Amendment No. 155 1-6
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Definitions l 1.15 0FFSITE DOSE CALCULATION MANUAL (ODCM) I l _155>. The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall be a manual containing the description of the methodology, algorithms and parameters to be used in the calculation of offsite doses
< resulting from the release of radioactive material _ in gaseous and liquid effluents and in the calculation of gaseous and liquid 155>< effluent monitoring instrumentation alarm / trip setpoints.
1.16 RESTRICTED AREA That portion of the site property, the access to which is controlled by security fencing, equipment and personnel. 1.17 SITE B0UNDARY 155>< Site Boundaries are defined by Figures 5.1-1 through 5.1-4. 1.18 DOSE EQUIVALENT I-131 The DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose 155> via the inhalation pathway as the quantity an~d isotopic mixture of I-131, 1 t132, I-133, I-134 and 1-135 actually present. The thyroid dose conysrsion factors used for this calculation shall be those listed in ICRP Publication 30, " Limits for Intakes of g < Radionuclides hy Workers," 1979. - 1.19 MEMBER (S) 0F THE PUBLIC MEMBER (S) 0F THE PUBLIC shall include all individuals who by _ virtue of their occupational status have no formal association with the plant. This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal. Job function, occasionally enter an area that is controlled hy the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials. Proposed Amendment No. 155 1-7
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Definitions 155> 1.21 MAXIMUM HYPOTHETICAL INDIVIDUAL The MAXIMUM HYP0THETICAL INDIVIDUAL is characterized as " maximum" with regard to food consumption, occupancy, or other usage or exposure pathway parameters in the vicinity of Rancho Seco that would' represent an individual or composite of individuals with habits greater than usually expected for the average of the population in general. No single individual would be expected to be exposed to all the potential effluent exposure pathways at the
" maximum" value.
The MAXIMUM HYP0THETICAL INDIVIDUAL is a hypothetical receptor of radiological exposure (mrem) resulting from the discharge of radioactive effluent (curies). The methodology to convert curies into mrem is described in the ODCM. The purpose of the ODCM calculation is to compare the resultant effluent exposure or dose ! with the numerical guides for design objectives in 10CFRbO, Appendix 1. The MAXIMUM HYPOTHETICAL INDIVIDUAL concept is consistent with its use in the US NRC Regulatory Guide 1.109 and 10CFR50, Appendix I. The MAXIMUM HYP0THETICAL INDIVIDUAL concept is NOT used to demonstrate compliance with 10CFR20.106. 1.22 RADIOLOG1 CAL ENVIRONMENTAL MONITORING PROGRAM (REMP) MANUAL gij The. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMPJ MANUAL shall be a manual containing the description of the Rancho Seco radiological environmental monitoring program. The REMP MANUAL shall contain a description of the environmental samples to be collected, the sample locations, sampling frequencies, and sample analysis criteria. 1.23 LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM i The LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM is the system ) designed and installed to reduce the quantity of radioactive materials in liquid effluents by collecting liquid effluent and providing processing for the purpose of reducing the total radioactivity prior to its release to the environment. Proposed Amendment No. 155 1-8
3 155> RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Definitions 1.24 VENTILATION EXHAUST TREANENT SYSTD4 The VENTILATION EXHAUST TREATi4ENT SYSTB4S are systems designed and installed to reduce gaseous radioiodine or radioactive material in 1 particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing fodines or particulate from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREANENT SYSTE4S components. 1.25 PURGE - PURGING PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. 1.26 VENTING YENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during
- p. VENTING. Vent, used in system names, does not imply a VENTING
- process.
1.27 RADI0 ACTIVE EFFLUENT Effluent shall be designated as RADI0 ACTIVE EFFLUENT when the radiochemical analysis of an appropriate sample of the effluent results in the detection of radioactive material above the Lower Limits of Detection as defined in Tables 4.21-1, 4.21-2 and 4.22-1. ! Proposed Amendment No. 155 1-9 - _ _ - _ _ _ _ _ _ _ _ _ Y
155> TABLE 1.9-1 L FREQUENCY NOTATION NOTATION FREQUENCY S At.least once per 12 hours. l D At least once per 24 hours. W At least once per 7 days. M At least once per 31 days. Q' At least once per 92 days. SY At least once per 184 days. f A: At least once per 12 months R At least once per 18 months. BA At least once per 24 months S/U Prior to each reactor startup.- P Completed prior to each release. NA Not applicable.
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k i Proposed Amendment No. 155 1-10
l RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.4 STEAM AND POWER CONVERSION SYSTEM Appi f cability Applies to the operability of the turbine cycle during normal operation and for the removal of decay heat. Objective - To specify minimum conditions of the turbine cycle equipment necessary to assure the required steam relief capacity during normal operation and the capability to remove decay heat from the reactor core, i
- Specification >
152> 3.4.1 The reactor coolant system shall not be brought or remain above 280F with irradiated fuel in the pressure vessel unless the following conditions are met: ; A. Capability to remove decay heat by use of two steam generators as specified in 3.1.1.2. - B. One atmospheric dump valve per steam generator shall be operable. C. A minimum of 250,000 gallons of water shall be available in l i the condensate storage tank. D. Two main steam system safety valves are operable per steam generator. E. Both auxiliary feedwater trains (i.e., pumps and their flow paths) are operable. F. Both trains of main feedwater isolation on each main feedwater line are operable. G. Four independent backup instrument air bottle supply systems for ADVs and MFW, SFW, and AFW valves are operable. With less than the above required components operable, be on decay
< heat cooling within 72 hours.
Proposed Amendment No. 152 3-23 _________________.._.__________J
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 155>< 3.15 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent vnitoring instrumentation channels shown in Table 3.15-1 shall be OPERABLE with their alarm / trip setpoints set to ensure 155> that the limits of Specification 3.17.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the
< methodology contained in the OFFSITE DOSE CALCULATION MANUAL (0DCM).
Applicability During the release of radioactive effluents via the pathways identified in Table 3.15-1. Action a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than a value which will ensure that the limits of Specification 3.17.1 are met, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take 155> the ACTION shown in Table 3.15-1. Exert best efforts to return the instrument to OPERABLE status within 30 days and, if unsuccessful, explain 13 the next Semiannual Radioactive Efflpent Release Report pursuant to Specification 6.9.2.3 why
< the inoperability was. not corrected in a timely manner.
2 Bases 155>< During normal operations, radioactive contaminated water from primary system leaks and drains is processed in a liquid radwaste system and recycled into the Reactor Coolant Makeup System or otherwise reused in the controlled areas - 155> of the plant. Secondary system water is normally released from the plant. The secondary system water, if it contains radioactive material is released 4 through the ' A' and 'B' Regenerant Hold-Up Tanks (RHUTs). During periods of primary to secondary leakage, or when the sumps are contaminated, administrative controls require the turbine building sumps liq'uia effluent to 155>< be diverted to the ' A' and 'B' Regenerant Hold-Up Tanks. 155> Demineralized reactor coolant can be transferred from the Demineralized Reactor Coolant Storage Tank (ORCST) to the ' A' and 'B' Regenerant Holdup Tanks for sampling, processing, and eventual discharge offsite as required by
< operational constraints.
Under normal conditions, the once througi, steam generators have no blow down. If a blow down is required during periods of priinary to secondary leakage, all water will be retained and processed in the radwaste system or diverted to the ' A' and 'B' Regenerant Hold-Up Tanks. Proposed Amendment No.155 3-60
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS i Limiting Conditions for Operation 3.15. (Continued) 155> Bases' (Continued) Radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of radioactive liquid effluents. The alann/ trip setpoints for these instruments shall be calculated in accordance with the methodology contained in the ODCM to ensure that the alann/ trip will occur prior to exceeding the limits of 10 CFR Part 20.106. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix. A to 10 CFR Part 50.
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1 i Proposed Amendment No. 155 3-60a 4
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RANCHO SECO UNIT 1 i TECHNICAL SPECIFICATIONS Limiting Conditions for Operation
-Table 3.15-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Number of Channels Instrument Operable Action
- 1. Gross Radioactivity Monitors. Providing Automatic Termination of Release 155> a. Retention Basin 1 With the monitor inoperable, Effluent Discharge effluent releases may be resumed Monitor provided that prior to initiating a release from the retention basin: g' a
- 1. At least two independent' samples are analyzed .in accordance with Specification 4.21.1.
- 2. At least two technically
\ qualified members of the .
Facility Staff independently J verify the release-rate
- calculations and discharge line valving.
Otherwise, suspend release of radioactive effluents via this pathway.
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l l l Proposed Amendment No. 155 3-61 _ ____O
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.15-1 (Continued) RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION l Minimum Number
- l. of Channels Instrument Operable Action 155> .2. Flow Measurement Devices
- a. Regenerant Hold-Up 1 With the flow measurement device Tank Discharge Line inoperable, releases to the retention Total Flow basins may continue provided the total flow can be determined hy a tank level device or pump performance curves.
- b. Waste Water Flow Rate 1 With the flow rate measurement I
< and Totalizer device inoperable, effluent releases l f {
via this pathway may continue provided the flow rate is estimated 155> \ at least once per 4 hours during
< retention basin releases.
2 1 I Proposed Amendment No. 155 ! 3-62 , 1
RANCHO SECO UNIT 1 i TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.16 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent monitoring instrumentation channels shom in
- Table 3.16-1 shall be OPERABLE with their alarm / trip setpoints set to ensure.
155+ . that the limits of Specification 3.18.1 (a) are not exceeded. The alarm / trip . setpoints of these channels shall be determined in accordance with the ! 4 methodology contained in the ODCM. Continuous samples of the gaseous effluent t
.for radioiodines and radioactive particulate material shall be taken as indicated in table 3.16-1. l Applicability During release via the pathways identified in Table 3.16-1.
Action a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoir,t less conservative than a value 155+ sich will ensure that the limits of Specification 3.18.1 are met, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably 4 conservative.
- b. With less than the minimum number of radioactive gaseous 3 effluent monitoring instrumentation channels OPERABLE, take the- 1 155+ ACTION shom in Table 3.16-1. Exert best efforts to return the !
instrument to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.2.3 why 4 the inoperability was not corrected in a timely manner. Bases ! 155+ The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases radioactive of gaseous ; effluents. The alarm / trip setpoints for these instruments shall be calculated ] 4 in accordance with the methodology contained in the ODCM to ensure that the l alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.106. i The OPERABILITY and use of this instrumentation is consistent with the ! requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR 1 Part 50. 155+ The Auxiliary Building Stack is the effluent release point for the Waste Gas System and the Auxiliary Building Stack Noble Gas Activity monitor will j perform the necessary Waste Gas System release termination. The monitor alarms and terminates a Waste Gas Decay Tank release automatically 4 if the activity exceeds the setpoint limits. l l l ' 1 Proposed Amendment No. 155 3-63 i l l l l L__._________ I
RANCHO SECO UN1T 1 TECHNICAL SPECIFICATIONS , 3.16 (Continued Limiting Conditions for Operation l Bases (Continued) l 155> The condenser air ejector exhaust has an individual noble gas monitor. Thi s l system exhausts into the Auxiliary Building ventilation system. Therefore, i the Auxiliary Building Stack is the effluent release point and will alarm upon release of environmentally significant radioactive gases. l Fuel Storage Building exhaust is directed to the Auxiliary Building stack where the exhaust will be filtered and monitored for any activity prior to being released to the atmosphere. I 1
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i Proposed Amendment No. 155 3-63a
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.16-1 RADI0 ACTIVE GASES EFFL'UENT MONITORING INSTRUMENTATION Minimum-Number ! of Channels Instrument Operable Action
- 1. - Reactor Building Purge Vent
- a. Noble Gas Activity 1 With the monitor channel alarm / trip i Monitor providing setpoint less conservative alarm and automatic than required by Specification ,I 155> termination of 3.18.1, immediately suspend the
< release.
- release or declare the channel inoperable. lh With the monitor inoperable, .;
effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed in accordance with Table 4.22-1 within 24 hours. s.
- b. Iodine Sampler 1 With the collection device W inoperable, effluent releases via this pathway may continue provided ,,
155> continuous samples are taken within one hour af ter the monitor is A declared inoperable and these $ samples are analyzed in accordance
< with Table 4.22-1 within 24 hours. **
- c. Particulate Sampler 1 With the collection device inoperable, effluent releases via this pathway may continue provided 155> continuous samples are taken within one hour af ter the monitor is-declared inoperable and these samples are analyzed in accordance with Table 4.22-1 within 24 hours. **
- See Table 3.5.5-1 for action required when this monitor is considered an l accident monitor.
** Interruption of continuous sampling is allowed for periods not to exceed one hour.
Proposed Amendment No. 155 l 3-64 (
)
A RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.16-1 (Continued) . RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION Minimum Number of Channels Instrument- Operable Action
- 1. Reactor Building Purge Vent (continued)
- d. System Effluent Flow 1 With the flow rate device Rate Device inoperable, effluent releases may continue provided the flow rate used is the maximum 155>- design flow rate or the measured flowrate, whichever
< is greater.
- e. Sampler Flow Rate 1 With the flow rate device Measurement Device inoperable, effluent releases via this pathway may continue provided the flow rate is g estimated and recorded at .
least once per 4 hours. I 1 i i Proposed Amendment No. 155 l 3-65 ! l i
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS , Limiting Conditions for Operation Table 3.16-1 (Continued) RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION Minimum Number of Channels Instrument Operable Action
- 2. Auxiliary Building Stack 155> a. Noble Gas Activity 1 With the monitor inoperable, Monitor providing effluent releases via this pathway alarm
- may continue provided grab samples are taken at least once per 12 hours l and these samples are analyzed in accordance with Table 4.22-1 within
< 24 hours.
- b. Iodine Sampler 1 With the collection device inoperable, effluent releases via this pathway may continue provided 155> s continuous samples are taken within one hour after the monitor is declared inoperable and these
)- samples are analyzed in accordance ' with Table 4.22-1 within 24 hours. **
- c. Particulate Sampler 1 With the collection device inoperable, effluent releases via this pathway may continue provided 155> continuous samples are taken within one hour af ter the monitor is I declared inoperable and these j samples are analyzed in accordance l with Table 4.22-1 within 24 hours. ** l\
- See Table 3.5.5-1 for action required when this monitor is considered an accident monitor. .
** Interruption of continuous sampling is allowed for periods not to exceed one hour.
Proposed Amendment No. 155 3-66
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.16-1 (Continued) RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION I Minimum l Number ! of Channels Instrument Operable Action ! 2. Auxiliary Building Stack (continued)
- d. System Effluent Flow 1 With the flow rate device Rate Device inoperable, effluent releases via this pathway may continue provided the flow rate used is the maximum 155> design flow rate or the measured A 4 flowrate, whichever is greater. GA,
- e. Sampler Flow Rate l' With the flow rate device inoperable, Measuring Devices effluent releases via this pathway may continue provided the flow rate is estimated and recorded at least once per 4 hours.
155> f. Waste Gas 1 With the monitor channel alarm / System ( Auxiliary trip setpoint less conservative Building Stack than required by Specification
< Monitor) 3.18.1, immediately suspend the 3- release or declare the channel inoperable.
With the monitor inoperable, the contents of the tank (s) may be released to the environment provided that prior to initiating the release:
- a. At least two independent samples of the tank's contents are analyzed, and
- b. At least two technically qualified members of the
. Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.
Proposed Amendment No. 155 3-67 ! 1 L-____-_____._m.___ ____
L f I RANCHO SEC0 UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.16-1 (Continued) RADIOACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION Minimum Number of Channels Instrument Operable Action 155> 3. Auxiliary Building !
< Grade Level Vent
- a. Noble Gas Activity 1 With the monitor channel alarm / IA !
Monitor
- trip setpoint less conservative than lg 155>< required by Specification 3.18.1,
'immediately suspe,id the release or declare the channel inoperable. !
With the monitor inoperable, effluent releases via this pathway may continue provided grab samples .l are taken at least once per 12 hours ; and these samples are analyzed in ! s accordance with Table 4.22-1 within ; 24 hours. ! l 0 b. Iodine Sampler 1 With the collection device ! inoperable, effluent releases via ; this pathway may continue provided 155> continuous samples are taken within one hour af ter the monitor is ; declared inoperable and these l samples are analyzed in accordance with Table 4.22-1 within 24 hours. **
- See Table 3.5.5-1 for action required when this monitor is considered an !
accident monitor.
** Interruption of continuous sampling is allowed for periods not to exceed J 1
one hour. 1
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Proposed Amendment No. 155 3-68 1 i
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Tabl e ' 3.16-1 (continued) RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION Minimum Number of Channels Instrument' Operable Action 155> 3. Auxiliary Building 4 Grade' Level. Vent (continued)
- c. . Particulate Sampler 1 With the collection device inoperable, effluent releases via this pathway may continue provided continuous samples are ,
L155> taken within one hour af ter the !
' monitor is declared inoperable and these samples are analyzed ,
in accordance with Table 4.22-1
< within 24 hours.**
- d. System Effluent Flow 1 With the flow rate device .
Rate Device inoperable, effluent releases may continue provided the flow g rate used is the maximum design 155> flow rate or the measured
< flowrate, whichever is greater.
- e. Sampler Flow Rate 1 With the-flow rate device
. Measurement Device inoperable, effluent. releases via this pathway may continue provided the flow rate is estimated and recorded at least once per 4 hours.
155>< 155> ..** Interruption of continuous sampling is allowed for periods not to exceed
< one hour.
Proposed Amendment No. 155 3-69 4 ___m.__.__.m. _
155> j RANCHO SEC0 UNIT 1 1 TECHNICAL SPECIFICATIONS ) J Limiting Conditions for Operation 3.17 LIQUID EFFLUENTS 3.17.1 Concentration 155> The concentration of radioactive material released in liquid j effluents at any time beyond the Site Boundary For Liquid Effluents (see Figure 5.1-4) shall be ifmited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entra{ned noble gases, the concentration shall be limited to 2x10- pC1/ml total activity. Applicability At all times Action
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With the concentration of radioactive material released from the site 155> exceeding Specification 3.17.1, immediately restore concentration within the
< specification limits and report the event in the next Semiannual Radioactive l Effluent Release Report pursuant to Specification 6.9.2.3. '
Bases This Specification is provided to ensure that the concentration of radioactive materials released in' liquid waste effluents from the site to areas beyond the 155> Site Boundary For Liquid Effluent (see Figure 5.1-4) will be less than the li concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column
- 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in
< exposures within the limits of 10 CFR Part 20.106 to MEMBER (S) 0F THE PUBLIC.
The concentration limit for dissolved or entrained noble gases is based upon 155>< the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. Proposed Amendment No. 155 3-70
RANCHO SECO UN!T 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.17.2 Dose 155>< The dose or dose commitment to a MAXIMUM HYP0THETICAL INDIVIDUAL from radioactive materials in liquid effluents released beyond the 155>< Site Boundary For Liquid Effluents (see Figure 5.1.4) shall be limited to: 155> a. Less than or equal to 1.5 mrem to the total body and to less than or equal to 5.0 mrem.to any organ during any calendar quarter; and,
- b. Less than or equal to 3 mrem to the total body and to less
< than or equal to 10 mrem to any organ during any calendar year.
Applicability At all times Action a. With the calculated dose or dose commitment from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 155>< 30 days a Special Report pursuant to Specification 6.9.5. This { Report will identify the cause(s) for exceeding the limit (s) ! and define the corrective actions to be taken to reduce the 1 155>< releases of radioactive material in liquid effluents and the i proposed corrective actions to be taken to assure that ! subsequent releases will be in compliance with the above limits. l 1 Bases '\ I l 3 This specification is provided to implement the requirements of Sections II. A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II. A of Appendix I. The ACTION statements provide the required operating flexibility and at the same o time implement the guides set forth in Section IV.A of Appendix I to assure _ that the releases of radioactive material in liquid effluents will be kept "as 155>< low as is reasonably achievable." The dose calculation methodology in the ODCM implement the requirements in Section III.A of Appendix I that confonnance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCH for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of; Evaluating Compliance with 10 CFR Part 50, Appendix I,"
Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the 155> Purpose of Implementing Appendix I," April 1977. There is reasonable assurance that the operation of the facility will not result in radionuclides concentrations in finished drinking water that are in excess of the
< requirements of 40 CFR 141.
Proposed Amendment No. 155 3-71 l l
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.17.3 Liquid Holdup Tanks The quantity of radioactive material contained in each of the 155>< following tanks shall be limited to less than or equal to 10 Curies, excluding tritium and dissolved or entrained noble gases: 1 155> a. "A" and "B" Regenerant Holdup Tanks
- b. Borated Water Storage Tank
- c. Demineralized Reactor Coolant Storage Tank
- d. Miscellaneous Water Holdup Tank
< e. Outside Temporary Tanks Applicability At all times Action With the quantity of radioactive material in any of the listed tanks exceeding the above limit, immediately suspend all additions of radior'tive material to the tank, within 48 hours reduce the tank conte't:. *ot within the limit, and describe the events leading to this eNQtion in the next Semiannual Radioactive Effluent Release Repon ,
4 Bases 155> The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System or the LIQUID EFFLUENT RADWASTE TREATMENT
< SYSTEM.
Restricting the quantity of radioactive material contained in the specified outdoor tanks provides assurance that in the event of an 155> uncontrolled release of the tank's contents, the resulting
< concentration at the nearest potable water supply and the nearest surface water supply in an unrestricted area would be less than the limits of 10 CFR 20, Appendix B, Table II, Column 2. The limit 155>< applies to each tank individually.
155> Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the A tank contents and that.do not have tank overflows and surrounding Q area drains connected to the liquid radwaste treatment system or the
< LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM.
Proposed Amendment No. 155 3-72
O RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 155> 3.17.4
- Liquid Effluent Radwaste Treatment The LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM shall be OPERABLE.
The appropriate portions of the system shall be used to reduce the quantity of radioactive materials in liquid effluents prior to their discharge to ensure that projected ddses due to the liquid effluent beyond the Site Boundary For Liquid Effluents (see Figure 5.1-4) will not exceed the requirements of Specification 3.17.2. Applicability At all times. Action 1
- a. With the LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM inoperable for more than 31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.5 a Special Report which includes the following information:
- 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability,
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- 2. Actiop(s) taken to restore the inoperable equipment to OPERABLE status, and 3
- 3. Summary description of action (s) taken to prevent a recurrence.
Bases The OPERABILITY of the LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM ensures that this system will be available for use whenever liquid effluents require - treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept i "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A > to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM were specified as the dose design objectives set forth in Section II.A of Appendix 1,10 CFR Part 50, for liquid effluents.
- The installation of the LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM is not complete. This specification will become effective when the system is
< declared operable.
J Proposed Amendment No. 155 3-72a 1 l 4
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.18 GASEOUS EFFLUENTS 3.18.1 Dose Rate The dose rate due to radioactive materials released in gaseous : 155> effluents from the site to areas at or beyond the Exclusion Area ! 4 (see Figure 5.1-1) shall be limited to the following values: 155> a. The dose rate limit for noble gases shall be less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin; and,
- b. The dose rate limit for Iodine-131, Iodine-133, tritium, and for all radioactive materials in particulate form with half lives greater than 8 days shall be less than or equal to 1500
< mrem /yr to any organ.
Applicabili ty At all times Action 155> With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the limit (s) given in Specification 3.18.1 and report the event in the6.9. to Specification nex{2.3. Semiannual Radioactive Ef, fluent Release Report pu m Bases This specificatfor. is provided to ensure that the dose rate from gaseous 155> effluents at any time at the Exclusion Area Boundary (Figure 5.1-1) will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The _ annual dose limits are the doses associated with the concentration of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR. Part 20.106 (b)(1)). For' individuals who may at times be within the Exclusion Area Boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates 4 above background to'an individual at or beyond the Exclusion Area Boundary to less than or equal to 500 mrem /yr to the total body or to less than or equal to 3000 mrem /yr to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via l 155> 4 the inhalation pathway to less than or equal to 1500 mrem /yr. Proposed Amendment No. 155 3-73 l l l _
RANCHO SECO UNIT 1 ( TECHNICAL SPECIFICATIONS y l I i Limiting Conditions for Operation l 155> 3.18.2 Dose-Noble Gases The air oose due to noble gases released in gaseous effluents to areas Wt or beyond the She Boundary For Gaseous Effluents (see 'f Figure 5.1-3) shall be limited tn the follodng: / i - t
- a. During any calendar quartw', to less than or equ.11 to 6 mrad lO. for gamma radiation and less than or equal to 10 mrad for beta radiation; and, n
I
- b. During ar(y calendar year, to less than $t equal to 10 mrad for gamma radiation'and to less than or equal to 20 mrad forLoeta
< radiation, t Applicability At all times Action 7 a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding'any of the above limits, prepare and submit to the Commission within 30 days a Special Report pursuant to Specification 6.9.5. This Report will identify the cause(s) for exceeding the limit (s) and define the corrective action (s) to be 155x taken to red'ne the release of radioactive noble gases in gaseous effluents dnd the proposed corrective action (s) to be taken to assure!that'?vhsequent relenes will be in complidnce witu the above !
. limits. y t
-Bases This' specification is provided to implement the requirements of Sections li.B.
IM. A, and IV. A of Atendix I,10 CFR Part 50. The Limiting Condition for Operation implementh the guides set forth in Section II.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the Quides set forth in Section IV.A of Appendix I to assure that the releaseM of radioactive material in gaseous effluents will be kept "as low as' is reasonably achievable". The Surveillance Requirements implement ' L 155> the requirements in Section III.A of Appendix I;that conformance with the l guides of Appendix I be shown by calculational procedures based on models and > data such that the actual exposure of an individual through the appropriate rathways is unlikely to be substantially underestimated. The dose . calculations established in the ODCM for calculating the doses dee to the petual release rates of radioactive noble gases in gaseous eff1 bents are consistent with the inenodology provided in Regulatory Guide 1 Y.)9.
" Calculation of Annual'00ses to Man from Routine Releases of Rolctor Effluents ;
for the Purpose of Evkluatir,g Ccmp11ance with 10 CFR Part 50,' Appendix I," Revision 1, October 16/7 and Regulatory Guide 1.111. " Method:; for Estimating ') Atmospheric Transport and Diepersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Readtors", Revision 1 July 1977. The ODCH equetJons provided for Determining that the air doses at the Site Boundary for Caseous Effluents (Figure 5.1-3) are based upon the historical average atmos.pheric
< ' conditions. l Proposed Amendment 10. 155 3-74 ,
1
s RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 155> 3.18.3 Dose-todine-131, Iodine-133, Tritium and Radioactive Matt.-l'als' in Particulate Form. The dose or dose cornitment to a MAXIMUM HYP0THETICAL INDIVIDUAL from Iodine-131, Iodine-133, tritium, and radioactive materials in parti:ulate form with half-lives greater than eight days in gascous , J effleents released to areas at or beyond the Site Boundary for I Gaseous Effluents (see Figure 5.1-3) shall be limited to the following:
- a. During any calendar quarter to less then or equal to T.6 mrem o to any organ; and,
- b. During any calendar year, to less than or equal to 15 mrem to
< any organ.
Applicability At all times Action With tac' calculated dose or dose commitment f rom the release of 155> Iodine-131, Iodine-133, tritium, and radioactive materials in particulate form with half-lives greater than eight days in gaseous effluents e.xceeding any of the above limits, prepare and submit to the Commission within 30 dayr, a Special Report pursuant to Specification 6.9.5. This Report will identify the cause(s) for a exceeding the-limit and defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent release will be in compliance' with
< the above annual limits.
Bases This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix 1. The ACTION statements provide the required operating flexibility 'and at the same time implement the guides set fo.th in Section IV. A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III. A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate patnaays is unlikely to be < substantially underestimated. f 155>< Proposed Amendment No. 155 3-75
1 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions.for Operation 3.18.3 :(cons;f.t_ued) a-Bases. (continued) 155> The .0DCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology
" provided in. Regulatory Guide 1.109, " Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance
W with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111, " Methods: for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors", Revision 1, g
(,b' . July 1977." These equations also provide for estimating doses based upon the
< jhlstorical average atmospheric conditions, f 155> The' release rate specifications for radioiodines and radioactive materials in particulate form are dependent on the existing radionuclides pathways to man in 4 areas at or be!,9nd the' Site Boundary for. Gaseous Effluents (Figure 5.1-3).
The pathways which were examined in the development of these calculations are: (1) iadividual inhalation of airborne radionuclides, (21 deposition of radionuclides onto green leafy vegetation with subsequent consumption by man,- (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the
,, , grounW with subsequent exposure of man.
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i i y Proposed Amendment No.155 ) 3-76 .: e e
'g d.
1
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_ _ _ _ . _ _ _ _ _ __ _ _ _ _ _ _ m L'=* u
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIMITING CONDITIONS FOR OPERATION PA 155> This page has been intentionally left blank, i
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I: Proposed Amendment No.155 3-77 l
l
- l -
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS l Limiting Conditions for Operation 155> 3.18.4 Gaseous Radwaste Treatment I The Waste Gas System and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of these systems shall be used to reduce radioactive materials in gaseous waste prior to their discharge such that projected gaseous effluent to areas at and beyond the Site Boundary for Gaseous Effluents (see Figure 5.1-3)
< are within the requirements of Specifications 3.18.2 and 3.18.3.
155>< Applicability At all times. Action
- a. With gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 155>< days, a Special Report pursuant to Specification 6.9.5 which includes the following information:
- 1. Explanation of why gaseous radwaste was being discharged without treatment, identification of the equipment or !
subsystems not OPERABLE and the reason for inoperability. ;
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE .
statu .
- 3. Sumary description of action (s) taken to prevent a recurrence.
Bases 155>< The OPERABILITY of the Waste Gas System and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous , effluents require treatment prior to release to the environment. The 155> requirement that the appropriate portions of these systems be used, when
< specified, provides reasonable assurance that the releases of radioactive i materials in gaseous effluents will be kept "as low as is reasonably l achievable." This specification implements the requirements of 10 CFR Part J 50.36a, General Design Criterion 60 of Appendix' A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The j specified limits governing the use of appropriate portions of the systems were 155>< specified as the dose design objectives set forth in Sections II.B and II.C of Appendix I,10 CFR Part 50, for gaseous effluents.
Proposed Amendment No. 155 3-78 i I
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation l 155>< 3.18.5 Gas Storage Tanks l The quantity of radioactivity contained in each waste gas decay tank 155>< shall be limited to less than or equal to 135,000 curies of noble gases (considered as Xe-133). Applicability At all times Action 155> a. With the quantity of radioactive material in any waste gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release
< Report, pursuant to Specification 6.9.2.3.
Bases Restricting the quantity of radioactivity contained in each waste gas decay tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to an individual at the 155>< exclusion area boundary (See Figure 5.1-1) will not exceed 500 mrem. This is consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure." Potential atmospheric releases from a waste gas decay tank are evaluated assuming design coolant activities (see page 14D-25 Vol. VI FSAR). Based on
}; primary coolant activity as shown in Table 140-7, the decay tank is assumed to hold the activity associated with the off-gas from one reactor coolant system degassing with no credit taken for decay.
Calculation of the limiting decay tank activity based on the coolant activity limit of Technical Specification 3.1.4 yields a maximum decay tank inventory - of 98,414 Ci (Ref. FSAR Table 14D-23). In order for the decay tank inventory to reach the limiting condition for operation, coolant activity would have to exceed the Technical Specification 3.1.4 limit on coolant activity and this would require a reactor shutdown, thus preventing a further increase in gaseous activity. Therefore, it is conservative to require that the online waste gas decay tank 155>< be sampled daily upon reaching the reactor coolant system limiting activity value (43/E) to ensure the 135,000 curies equivalent Xe-133 is not exceeded. Once the coolant is below the limiting activity, there is no requirement to sample waste gas decay tanks except for discharging. Proposed Amendment No. 155 3-79
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.21 SOLID RADI0 ACTIVE HASTES 155- The solid radwaste systems shall be OPERABLE and used in accordance with a PROCESS CONTROL PROGRAM for the SOLIDIFICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR 20 and 10 CFR 71 prior to shipment of radioactive wastes from the
- site, j Applicability At all times Action 155- Hith the provisions of the PROCESS CONTROL PROGRAM not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive
- wastes from the site.
Bases The OPERABILITY of the solid radwaste system ensures that the system will be available for use whenever radwastes require processing and packaging prior to being shipped offsite. This specification implements the requirements of ' 10 CFR 50.36a and General Design Criterion 60 of Appendix A to 10 CFR 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM 155-- may include, but are not limited to waste type, waste pH, waste / liquid / solidification agent / catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times. Proposed Amendment No. 155 3-80 ( - - - - - - - _ _ _ - - - - - - - - - -
a RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Opera. tion 3.22 RADIOLOGICAL ENVIRONMENTAL MONITORING 155>< The Radiological Environmental Monitoring Program shall be conducted as specified in Table 3.22-1. Applicability At all times Action 155>< a. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 3.22-1, prepare and submit to the 155> Commission, in the Annual Radiological Environmental Operating
< Report required by Specification 6.9.2.2, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. (Deviations are permitted from the required sampling schedule if specimens are unobtainable due to 155>< hazardous conditions, or seasonal unavailability.)
- b. With the level of radioactivity in an environmental sampling medium 155>< exceeding the reporting level of Table 3.22-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days af ter the level of radioactivity has been determined, a Special 155>< Report pursuant to Specification 6.9.5 which includes an evaluation of any release conditions, environmental factors or other aspects which caused the reporting limits to be exceeded. This report will define cor'rective actions to reduce emissions such that potential 155> exposures will meet Specification 3.25. When more than one of the g radionuclides in Table 3.22-2 are detected in the sampling medium,
< this report shall be submitted if:
Concentration (1) + Concentration (2) + . . . >1.0 reporting level (IT reporting leven m 155> When radionuclides other than those in Table 3.22-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifications 3.17.2, 3.18.2, and
< 3.18.3. This report is not required if the measuren level of radioactivity was not the result of plant effluents; however, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
155>< c. With milk or fresh leafy vegetation samples unavailable from any of the sample locations required by Table 3.22-1, prepare and submit to 155> the Commission within 30 days a Special Report pursuant to
< Specification 6.9.5 which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples. The locations from which samples were unavailable may then be deletea from Table 3.22-1 provided the locations from which the 155> replacement samples were obtained are added to the Radiological
< Environmental Monitoring Program as replacement locations, if available.
Proposed Amendment No. 155 3-81 s
A RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS' Limiting Conditions for Operation 3.22 (continued) Bases 155>< The Radiological Environmental Monitoring Program required by this specification provides measurements of radiation and of radioactive materials . i in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the 155> station operation. This monitoring program implements Section IV.B.2 of-Appendix I to 10 CFR 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and ODCM modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, l Revision 1, November 1979. The specified monitoring program is in effect at this time. Program changes may be initiated based on operational experience, 3 and changes in regional population or agricultural practices. The sample ) locations have been listed in the RADIOLOGICAL ENVIRONMENTAL MONITORING
< PROGRAM (REMP) MANUAL to retain flexibility for making changes as needed.
155> The detection capabilities required in Table 4.26-1 are state-of-the-art for routine environmental measurements in industrial laboratories. The LLD's for drinking water meet the requirement of 40 CFR 141.
< \
W , l l Proposed Amendment No. 155 3-82
RANCHO SECO UNIT 1 TECHNICAL-SPECIFICATIONS Limiting Conditions for Operation Table 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM' Sampling and Exposure Pathwe Number of Collection Type and Frequency and/or Sample Samples
- Frequency of Analysis
- 1. AIRBORNE A. Radiciodine 8 Continuous oper- Radiof odine canis-and Parti- ation of sampler ter. Analyze at 155>< culates with sample least once weekly collection as for I-131.
required by dust loading but at. Particulate least once per sampler. Analyze week. for Gross Beta radioactivity at 155>< least 24 hours following filter change.- Perform gamma isotopic analysis on each sample where gross
\ beta activity is greater than 10 155>
times the yearly 1 4 mean of control samples for the . same sample period. . Perform gamma iso-topic analysis on composite (by location) for particulate filters sample at least once per quarter.
- 2. DIRECT Greater than 40 At least once Gamma dose. At RADIATION locations with 2 per quarter. least once per dosimeters at each quarter.
location. 155><
- Sample locations are shown in the REMP MANUAL.
I Proposed Amendment No. 155 ) 3-83 1
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.22-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sanpling and Exposure Pathway Number of Collection Type and frequency and/or Sample Samples
- Frequency of Analys;s
- 3. WATERBORNE 155> a. Surface 1 Composite Gamma isotopic sample collected and tritium monthly ** analysis of each composite. !
3 Grab sample Gamma isotopic and collected tritium analysis of monthly. each sample. l
- b. Runoff 1 Grab sample Gamma isotopic and collected tritium analysis of fortnightly, each sample,
- c. Ground \2 At least once Gamma isotopic, per quarter. and tritium 3,
analysis of each
- sample.
- d. Mud and 2 At least once Gamma Isotopic Silt semi-annually. analysis of
< One pint sample each sample. -
of the top 3" of material 2 ft. from sho reline.
- Sample locations are shown in the REMP MANUdl.
155>< ** Applicable when sampler is declared operational. Proposed Amendment No.155 3-84
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation-I l: Table 3.22-1 (Continued)- RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1 Sampling and Exposure Pathway Number of Collection Type and Frequency and/or Sampie- Sampies* Frequency of Analysis l
- 4. INGESTION 155> a. Milk 4 At least weekly Gamma isotopic when animals analysis and I-131 analysis of are on pasture; at least once each sample.
per month at other times.
.b. Fish and 3 At least Gamma isotopic Inverte- quarterly. One analysis on edible brates samp1e of each portion of each species as sample.
listed in the REMP MANUAL.
- c. Food \ 4 At time of har- Gamma isotopic vest. One sam- analysis on pie of each of edible porti.on "y
< the several of each sample, classes of food products as shown in the
.i REMP MANUAL.
- Sample locations are identified in the REMP MANUAL. i 155x ]
I Proposed Amendment No. 155 ! 3-85
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)
i m b ( L L A ) 3 0 0 0 T 1 6 7 0 N k/ 3 E lf M iC N Mp O ( R I V N - E ) t N e I h w S S s , N N ig 4 4, 4 4 4 3 3 O O Fk 0 0 0 0 0 , 0 0 1I I
/ 1 1 1 1 1 1 1 T T s f TA A l C x x x x x x x .
I C 2 R e p e NI - T v ( 3 1 3 1 2 1 2 u UF 2 N e l I 2 E L a OC C g , v CE 3 N e EP O n t 1 SS e C i a 4 l t l) 1 OL b Y r yJ HA a T o cm t CC T I p i / r NI V e t1 a AN I R rC P RH T ap 9 C C P( 0 0 2 R E A 0 1 2 F T 0 es C I D ne rs 0 A oa 4 R bG r s R i r i O Ao F s i S h . L tr E e V ,t E sh L eg
) ) l u G ) b b pa N a ( ( md I ( a T ) 4 3 2 3 2 2 2 2 sd R 1 0 0 0 0 0 0 0 2 0 0 0 0 n O r/ 1 1 1 1 1 1 1 3 5 1 4 ra P e1 e E tC x x x x x x x tt R ap x. an W( 2 1 4 1 3 3 4 2 wer ga np i
k r no _ s if _ i a r s - 0 t dl _ y 4 9 8 0 5 5 1 4 7 4 e a _ 3 5 5 5 6 6 9 3 3 3 1 b rt l a - - - - - - - 1 1 1 - oo n H n e o o n b - - - a s FT _ M F C C Z N I s s L s A - C C - o )) Z r a B G r (( ab 5 5 _ 1
__w - _ s 1 RANCHO SECO UNIT 1 ' TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 4 3.23 LAND USE CENSUS A land use census shall be conducted annually and shall identify the j location of the nearest milk animal, the nearest residence and the nearest garden
- of greater than 500 square feet producing fresh 155>< leafy vegetation in each of the 16 meteorological sectors within a ,
distance of five miles. j l 155> The Land Use Census shall also include information relevant to the liquid effluent pathway and gaseous effluent pathway such that the 0FFSITE DOSE CALCULATION MANUAL (0DCM) and the RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL can be kept current witn the
< existing environmental and societal uses surrounding Rancho Seco.
Applicabili ty At all times Action
- a. With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently 155>< being calculated in Specifications 4.21.2, and 4.22.3, identify the new locations in the next Annual Radiological Environmental Operating Report,
- b. With a lan'd use census identifying a location (s) that yields a [
calculated dose or dose commitment (via the same exposure pathway)
- 20 percent greater than at a location'from which samples are currently being obtained in accordance with Specification 3.22, add the new location (s) to the Radiological Environmental Monitoring -l 155> Program within 30 days or submit a Special, Report to the Commission l pursuant to Specification 6.9.5 that identifies the cause(s) for ~
exceeding these requirements and the proposed corrective actions for
< precluding recurrence. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose i cornitment(s) (via the same exposure pathway) may be deleted from this monitoring program af ter (October 31) of the year in which this land use census was conducted. Identify the new location (s) in the 155>< next Annual Radiological Environmental Operating Report and also include in the report a revised figure (s) and table for the RENP manual reflecting the new location (s). i
- Broad leaf vegetation sampling may be performed at the site boundary in the 155>< direction sector with the highest D/Q in lieu of the garden census. ]
Proposed Amendment No. 155 3-87
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS 3.23 (Continued) Bases This specification is provided to ensure that changes in the use of 155> unrestricted areas are identified and that modifications to the Radiological
< Environmental Monitoring Program and the ODCM are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure.
pathways via leafy vegetation will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimtim garden size, the following assumptions were used: (1) that 20 percent of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage); and (2) a vegetation yield of 2 kg/ square meter. 155> In addition, by gathering information on the liquid effluent pathway and the gaseous effluent pathway, the census will ensure that proper radiological environmental monitoring and radioactive effluent controls are in place for
< the adequate protection of the health and safety of the general public.
\
101 l l 1 I l i l Proposed Amendment No.155 3-88 l
RANCHO SECO UN!T 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.25 FUEL CYCLE DOSE 155> The dose or dose commitment to any real HEMBER OF THE PUBLIC due to releases of radioactive material in gaseous and liquid effluents and to direct radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which is
< limited to less than or equal to 75 mrem) over 12 consecutive months. !
Applicability At all times Action 155> a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.17. 2. a, 3.17.2. b, 3.18.2.a . 3.18.2.b, 3.18. 3.a or 3.18. 3.b , or exceeding the reporting levels of Table 3.22-2, calculations shall be made including direct radiation contributions (including outside storage tanks, etc.) to determine whether the above limits of Specification 3.25 have been exceeded.
- b. If the above limits have been exceeded, prepare and submit to the Commission within 30 days, a Special Report pursuant to Specification 6.9.5 that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes This i the schedule fo\r achieving conformance with the above limits.
Special Report, as defined in 10 CFR Part 20.405(c). shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE ! a PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, over 12 consecutive months that includes the release (s) covered by this report. It shall also describe levels of l radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.
- c. If the estimated dose (s) exceed the above limits, and if the release condition resulting in the violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provision of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until
< staff action on the request is complete.
Bases 155> This specification is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the j calculated doses from plant radioactive effluents exceed twice the numerical l guides for design objective doses of Appendix I or exceeds the reporting l levels for the Radiological Environmental Monitoring Program. For the Rancho l Seco site it is unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the plant remains within twice the numerical guides for design objectives of 10 CFR 50 Appendix I and if 4 direct radiation (outside storage tanks, etc.J is kept small. The Special j Proposed Amendment No. 155 3-90 j
i' RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS , Limiting Conditions for Operation 3.25 (Continued) Bases (Continued) 155> Report will describe a course of action which should result in the limitation of the dose to a MEMBER OF THE PUBLIC for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any MEMBER OF THE PUBLIC is evaluated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190 is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is
< engaged-in carrying out any operation which is part of the uranium fuel cycle.
\ .
i 1 i Proposed Amendment No. 155 { 3-91 1 l l 1
- - _ - - _ i
L 1' RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS. l List. ting Conaitions'for Operation 1
- i. 3.26 INTERLABORATORY COMPARIS0N PROGRAM l
The contractor performing the analysis of radiological environmental 155>< monitoring samples for radioactive materials shall participate in an Interlaboratory Comparison Program approved by the Commission. Applicability At all times Action With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the commission 155> in the Annual Radiological Environmental Operating Report pursuant
< to Specification 6.9.2.2.
Bases The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental-monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR 50. R i Proposed Amendment No. 155 3-92
I RANCHO SECO UN!T 1 TECHNICAL SPECIFICATIONS Surveillance Standards - Table 4.1-1 (Continued) INSTRUMENT SURVEll. LANCE REQUIREMENTS * . Test Calibrate Remarts !
. Channel Description Check
- 42. Reactor But141pg drain NA NA' R accesmalation tank level M(1) NA NA (1) Checkfunctioning functioning.o f
- 43. Incore neutron detectors including computer readout and/or etcorder rtadout.
155> 44. a. Process radiation W R monitoring systen Q
, b. Area radiation H 4 monitoring systes W Q W NA R
- c. Containment Arta Monitors
- 45. Emergency plant radiation (1) Battery chect M(1) NA R Instruments M(1) NA R (1) Check functioning
- 46. Environmental air monitors Q(1) NA R (1) Sattery check
- 47. Strong motion at;celerometer
- 48. Auxiliary Feedwster Start Cirt: ult
- a. Phase imbalance /Under-3
- V\ S 'NA R Power RCP i
- b. Low Main feedwater ,
R + Pressurt
- HA N H NA R
- 49. Pressurizer Water f.evel '
- 50. Auxiliary Feedwater Flow M NA R Rate ,
- 51. Reactor Coolant System -
Subcooling Margin Monitor M NA R 52 OH0Y Power Position Indicator { Primary Detector) H HA R
- 53. CHOV Position Indicator (Backup Detector)
M HA R T/C or Acoustic ,
- 54. EHOV Block Yalve Position R Indicator M HA
- 55. Safety Yalve Position Indicator (Primary Detector)
H HA R T/C
- 56. Safety Valve Posit' ion Indicator (Backup Detector)
Acoustic H MA R Proposed Araendment 155 4.7h
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 155>< 4.19 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Surveillance Requirements 155> The maximum setpoint shall be determined in accordance with methodology as described in the Offsite Dose Calculation Manual (0DCN) and shall be recorded
< on the release permits.
Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the INSTRUMENT CHANNEL CHECK, SOURCE CHECK, INSTRUMENT CHANNEL CALIBRATION, AND CHAhNEL TEST at the frequencies shown in Table 4.19-1. 155>< Records shall be maintained in accordance with the Process Standards of all radioactive liquid effluent monitoring instrumentation alarm / trip setpoints. Maximum setpoints and setpoint calculations shall be available for review to 155>< ensure that the limits of Specification 3.17.1 are met. Bases 155> The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in
< liquid effluents during actual or potential release of radioactive liquid effluents. The alarm / trip setpoints for these instruments shall be calculated 155>< in accordance with the methodology contained in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.106. j p The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. j l
l I i l 1 1 Proposed Amendment No. 155 4-63 L
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards
, Table 4.19-1 l
RADI0 ACTIVE LIQUID EFFLUENTi40NITORING INSTRtl4ENTATION { SURVEILLANCE REQUIRCiENTS ] Instrument Instrument , Channel Source Channel Channel Instrunient Check Check Calibration Test
- 1. Gross Radioactivity Monitors Providing Alarm and Automatic Isolation 155> a. Retention Basin D P RI2) QII)
Ef fluent Discharge M onitor
- 2. Flow Monitors
- a. Regenerant Hold-up D(3) NA R Q I Tank Discharge Line Total Flow
- b. Waste Water Flow D(3) NA R Q Rate and Totalizer
) l I i Proposed Amendment No. 165 4-64 L__________
, RANCHO SECO UNIT 1 L, - TECHNICAL SPECIFICATIONS Surveillance Standards 155> TABLE 4.19-1 (Continued)
TABLE NOTATION (1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the-following conditions exists:
- 1. Instrument indicates measured levels above the alarm /tt ip setpoint.
- 2. Circuit failure.
- 3. Instrument indicat'se a downscale failure.
- 4. Instrument controls not set in' operate mode.
(2) The INSTRUMENT CHANNEL CALIBRATION shall be performed using one or more l reference standards i (3) Tie INSTR 0 MENT CHANNEL CHECK shall consist of verifying indication of flow during periods of release. INSTRUMENT CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.
-p Proposed Amendment No. 155 4-64a
~
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.20 RADIOACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION Surveillance Requirements 155> The maximum setpoints shall be determined in accordance with methodology described in the OFFSITE DOSE CALCULATION MANUAL (0DCM) and shall be
< recorded on release permits.
Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by perfonnance of the INSTRUMENT CHANNEL CHECK, SOURCE CHECK, INSTRUMENT CHANNEL CALIBRATION, AND CHANNEL TEST at the frequencies shown in Table 4.20-1. 155>< Records shall be maintained in accordance with the Process Standards of all radioactive gaseous effluent monitoring instrumentation alarm / trip setpoints. Maximum setpoints and setpoint calculations shall be available for review to 155>< ensure that the limits of Specification 3.18.1 are met. Bases-The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in 155> gaseous effluents during actual or potential releases of radioactive gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated
< in accordance with the methodology contained in the ODCM to ensure that the-alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.106.
s The OPERABILITY and use of this instrumentation is consistent with the requirements and General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The flow rates in the Auxiliary Building Stack and Auxiliary Building Grade 155> Level Vent are constant as they use single speed fans. The Reactor Building Purge Vent has a constant release rate. However, releases from the Reactor Building may be at three different flowrates, winter, summer or minipurge. Administrative controls assure that the correct flowrate is used. The flow rate measurement devices are used only as flow indicating devices and A not for actual measurement of flow rate. The actual flow rate of the 41 ventilation systems are periodically detennined by surveillance procedures. The flow rate devices must be removed from the ventilation system for the channel test, and in addition transported to the manufacturer for
< calibration. The frequencies have been set as shown in Table 4.20-1.
Proposed Amendment No. 155 4-65
RANCHO SECO UNIT 1 'l TECHNICAL SPECIFICATIONS- i 1 Surveillance Standards: l Table-4.20-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENT 5 Instrument Instrument Channel Source Channel Channel Instrument Check Check Calibration Test
- 1. Reactor Building
-Purge Vent- ,
- a . Noble Gas 155>< Activity Monitor D M(4) R(3) QIII
- b. Iodine Sampler W _NA NA NA
- c. Particulate Sampler' W NA NA NA
- d. System Effluent 155>< Flow Rate Device D NA R Q(6)
- e. Sampler Mohitor Flow Rate
;g 155>< Measurement Device D NA R Q
- 2. Auxiliary Buf1 ding .
Stack
- a. Noble Gas 155>< Activity Monitor D(5) M R(3) Q(7)
- b. Iodine Sampler W NA NA NA
- c. Particulate Sampler W NA NA NA
- d. System Effluent 155>< Flow Rate Device D , NA R Q(6)
- e. Sampler Monitor Flow Rate 155>< Measurement Device D NA R Q 155><
Proposed Amendment No.155 4-66
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Tab 1'e 4.20-1 '(Continued) i Instrument Instrument Channel Source Channel Channel Instrument Check Check Calibration Test 155,4 3'. Auxiliary Buf1 ding Grade Level Vent
'155><- 'a. Noble Gas D M R(3) g(2)
Activity Monitor
- b. Iodine Sampler W NA NA NA
- c. Particulate W NA NA NA Sampler 155>< d. System Effluent D NA R Q .
I Flow Rate Device 155>< e. Sampler Monitor 0 NA R Q Flow Rate Measurement Device
. \
155>< ll k i 1 i q i Proposed Amendment No. 155 , 4-67 )
./ .f
155> RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards I Table 4.20-1 (Continued) l l TABLE NOTATION i (1) The CHANNEL TEST shall also demonstrate that automatic isolation of this ) pathway and control room alarm annunciation occurs if any of the i following conditions exists:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in operate mode.
I?) The CHANNEL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
\
- 4. Instrument controls not set in operate mode.
E (3) The INSTRUMENT CHANNEL CALIBRATION shall be performed using one or more reference standards. (4) A check shall be performed prior to each release. (5) A check shall be perfomed prior to each release via a Waste Gas Decay Tank ( s) . (6) To be performed when device is accessible and conditions do not pose a personnel safety hazard (i.e., potential main steam safety actuation). (7) The CHANNEL TEST shall also demonstrate that the Waste Gas System automatically isolates and that control room annunciation occurs if any of the following conditions exist:.
- 1. Instrument indictes measured levels above the ' alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in operate mode.
Proposed Amendment No. 155 4-68
L RANCHO SECO UNIT 1 L TECHNICAL SPECIFICATIONS Surveillance Standards 4.214 LIQUID EFFLUENTS 4.21.1 Concentration Surveillance Requirements The concentration of radioactive material at any time in liquid effluents released from the site shall be continuously monitored in accordance with Table 3.15-1. The liquid effluent continuous monitor having provisions for automatic termination of liquid releases, as listed in Table 3.15-1, shall be used to limit the concentration of radioactive material released at any time from the 155>< site to areas beyond the site boundary to the limits given in Specification 3.17.1. The radioactivity content of each batch of liquid effluent to be discharged shall be determined prior to release by sampling and analysis in accordance with Table 4.21-1. The results of pre-release analyses shall be used with the 155> calculational methods in the OFFSITE DOSE CALCULATION MANUAL (0DCM) to assure
< that the concentration at the point of release is limited to the limits of Specification 3.17.1.
155>< , Bases i g- This Specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to areas beyond the site boundary for liquid effluent will be less than the concentration levels 155>< specified in 10 CFR Part 20, Appendix B. Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within the limits of 155>< 10 CFR Part 20.106 to MENBER(S) 0F THE PUBLIC. The' concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is i 155>< the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. 155> There are no continuous releases of radioactive uaterial in liquid effluents from the plant. All radioactive liquid effluent releases from the plant are by batch method. Proposed Amendment No. 155 4 69 l l I I
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.21-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Sampling Minimum Analysis Type of Activity Lowr Limit Liquid Release Frequency Frequency Analysis Of Detection Type (LLD) (uCi/ml)(a) 155o Each Batch Mn54 1E-7 A. Batch Waste lease Tanks b,d(Re .) Each Batch Fe59 4E-7 P P CoS8 SE-7 Co60 1E-7 Zn65 SE-7 Mo99 SE 7 1 ! Bo140 4E-8 Cs134 4E-8 Cs136 ' 4E-8 Cs137 SE-8 Cel41 SE-7 Ce144 SE-7 (c) i 1 k31 1 x 10-8 Dissolveo and 1 x 10-5 Entrained Gases (Gamma Emitters) 1 x 1rr5 o (
)
Pr posed Amendment No. 155 4-70 :
= .
- ( y; ' ...
,r ;
);9 a,'.
w , RANCH 0'SECO UNIT 1 TECHNICAL' SPEC.tFICATIONS b Surveillance Standards TABLE 4.21-1 (Continued) RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Table Notation 155> :a. (1) The lower limit'of detection (LLD) for a radionuclides presented in this table is the largest concentration,. expressed in microcuries
;, :/, .per milliliter, which is required to be detected, if present, in d '
< or+ der to achieve conG11ance with the Aimits of Specification 3.17.1 g
d10ER20, Appendix B,2 Table II, Co1LE:n 2). (2) The LLD of a radiaanalysiu system is that value which will indicate-the presence or absence of radioactivity in a sample when the j probability of a false positive find of a' f alse negathe h ,jr determination is stated. .The probabilities's of false positive and j '. c .N' ( microcuries false negative are taken 'as equal at 0.05. The equation for LLD in ", per milliliter is given by the equation: , l
.1,LD [ 2.71 + 3.29(Br)0.5
, , 3.70E4(YEVT) \ ;
4 ' o
+ where 2.71 7 actor
- f. to account for Poisson distributim at very low background count rates. />
\fg ., is a .t , ,
,~
y g', When background is estimated from a blank which has 6 ep counted for a specific period, the following applies:
) , ,
, ') i B = estimated background (counts)
F =b t [f 3 O Y , h b = blank background (counts) s tb = blank count time (seconds) ts = sample count time (seconds) t 4
. r=1+ s 4 ( tb l
Proposed Amendment No. 155 4-71 / l l 1 j
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS
~ Surveillance Standards TABLE 4.21-1 (Continued)
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Table Notation 155> 3.70E4 = disintegrations /second/ microcurie a f.b Y = yield'of radiochemical process, i.e., the product of all factorsD such as emission fractionfchemical. yield,' etc. , E = counting efficiency (count / disintegrations) V = sample volume (milliliters) T=[1-edp(ite)]exp(-Atc) t A 3 where A = decay constant (seconds -1)- te = time from midpoint of collection to start of counting
.(3) When spectroscopy is used to analyze the sample, the following LLD equation is used.
LLD = 2.71 + 4.65(B)0.5 i 3.70E4 (YEVT)
< Where B is the counts in the Region Of Interest.
i l Y.'
, 1 Proposed Amendment No.155 i
4-71a 4
RANCHO.SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.21-1. (Continued)
-RADI0 ACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM Table Notation
- b. A b'atch' release' is the discharge of liquid wastes of discrete volume 1 A-155-~ , from the 'Aor 'B' Regenerant Holdup Tanks. Prior to. sampling, each 4D batch will be isolated, and then thoroughly mixed, to assure
<j > representative sampling.
c.10ther peaks which are' measureable and identifiable, together with the 155- 1,f sted nuclides, shall also be identified and reported. Nuclides which u" - are not observed for the' analysis shall be reported as "less than" the instrument's LLD, and.shall not be reported as being present. The "less
" # ,.s than" values.shall not be used in the ODCM evaluations. However.. if the a nuclide is. measured and identified at a value less than the Table 4.21-1 LLD value, it shall be reported and. entered into the ODCM evaluations.
#f 155-- d. Miscellaneous Water. Evaporator release is via the gaseous pathway.
g
.e 1
j .,,1 5'
.T' o
, ,N
- y. '
af i Proposed Amendment No. 155 4-71b 1,' , .. ' a -
^
I ' RANCHO SECO UNIT 1
. TECHNICAL SPECIFICATIONS Surveillance Standards 4.21.2 Doses Dose Calculations 155> Cumulative dose contributions and cumulative dose projections associated with the release of. liquid RADI0 ACTIVE EFFLUENTS from the site (see Figure 5.1-4) shall be determined in accordance with the sampling and analyses specified in A Tables 4.21-1 and 4.21-2 and the methodology described in the Offsite Dose Calculation Manual (0DCM) at the following frequencies:
g
- a. Prior to the initiation of a release of liquid RADI0 ACTIVE EFFLUENT and, upon completion of each release, a dose calculation update shall be made; and, i
- b. Monthly, based on gamma-emitter and tritium analyses of liquid ,
RADI0 ACTIVE EFFLUENT releases during the previous calendar month and the .{ results of analyses performed on composite samples shall be added to the monthly dose calculation. i A dose tracking system and administrative dose limits shall be established and maintained. Operating parameters shall be adjusted in accordance with methodology described in the ODCM such that the dose values at any time, when projected to the endsof the applicable time period, do not exceed the doses
< specified in Technica'l Specification 3.17.2.
I Bases This specification is provided to implement the requirements of Sections II.A, III. A. and IV.A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and, at the same time, implement the guides set forth in Section IV.A of Appendix I which 155> assures, by definition, that the releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable." The dose
< calculations methodology in the ODCM implements the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual 155><
Proposed Amendment No. 155 4-72
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards exposure-of-an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid: effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Dose to Man from Routine Releases of Reactor Effluent for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.13. " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. 155- The results from composite samples during the period 1981 through 1984 indicates that Cs-137, Cs-134, Co-58 and Co-60 constitute 80 percent of the historical mix of gamma emitting radionuclides in plant liquid effluents. Another 13 percent consists of I-131. When the thyroid is separated as a limiting organ, 97.8 percent of the total body dose and 97.6 percent of the limiting organ dose are due to Cs-134 and Cs-137. Essentially 100 percent of the thyroid dose is due to I-131. The activity analysis of Cs-134, Cs-137 and I-131 at the Lower Limits of Detection specified in Table 4.21-1 are based on an estimated annual plant radioactive effluent outflow of 20 million gallons per year with an average dilution flowrate of 5,000 gallons per minute. These Lower Limits of Detection equate to an offsite dose commitment of approximately 50 percent of the guidelines specified in 10CFR50, Appendix I and provide an adequate basis for determining the presence or absence of dose due to other radionuclides in plant liquid effluents, when no other indications are revealed during sample analysis. The Lower Limits of Detection specified in Table 4.21-2 equate to an offsite dose commitment of approximately 10 percent of the 10CFR50, Appendix I guidelines. The dose tracking system ensures that the dose limits prescribed in Technical Specification 3.17.2 will not be exceeded at the 95 percent confidence level. The methodology presented in the ODCM provides for adjustment of operational and analysis parameters to factor in variables such as annual radiological liquid effluent release volume, discharge canal flow rate, and current cumulative dose. The dose tracking system provides for prompt updating of cumulative dose and contains feedback mechanisms to assure that the target dose values are not i exceeded. The tracking system also contains review and approval of batch I radiological liquid effluent releases at multiple management levels. There is also reasonable assurance that the operation of the facility will not result in radionuclides concentrations in finished drinking water that
- are in excess of the requirement of 40CFR141.
Proposed Amendment No. 155 4-72a 155-
155o RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.21-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM dampling Minimum Analysis lype of Activity Lowr Limit Liquid Release frequency Frequency Analysis (c) Of Detection Type (LLD) (uCi/ml)(a) Each Batch Composite (d) H3 1 X 10-5 A. Batch Waste lease Tanks b (Re)- P M Cr51 3 x 10-5 Mn54 1 x 10-7 Fe59 4 x 10-7 CoS8 5 x 10-7 Co60 1 x 10-7 Zn65 5 x 10-7 Sr89 3 x 10-8 Sr90 3 x 10-8 Zr95 6 x 10-7 Nb95 1 x 10-8 Ag110m 1 x 10-7
*1131 1 x 10-8 Cs134 9 x 10-9
*Cs136 4 x 10-8 Cs137 1 x 10-8 A
*Ba140 4 x 10-8 [Q Ce141 5 x 10-7 Cel44 5 x 10-7 Gross Alpha 1 x 10-7
*For these short-lived isotopes, the LLD specified in Tables 4.21.1 and 4.21-2 are met during pre-release analysis, and as such the LLD does not have to be met for the composite sample analysis.
l l ( Proposed Amendment No. 155 l 4-72b
)
L_-.________--
155> RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.21-2 (Continued) RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Table Notation a.- (1) The lower limit of detection (LLD) for a radionuclides presented in this table is the largest concentration, expressed in microcuries per milliliter, which is required to be detected, if present, in order to achieve compliance with the limits Of Specification 3.17.2-(10CFR50, Appendix I). (2) The LLD of a radioanalysis system is that value which will indicate the presence or absence of radioactivity in a sample when the probability of a false positive and of a false negative determination is stated. The probabilities of false positive and false negative are taken as equal at 0.05. The equation for LLD in microcuries per milliliter is given by the equation: LLD = 2.71 + 3.29(Br)0.5 b 3.70E4(YEVT) where 2.71 = factor to account for Poisson distribution at very low backgroundhountrates. When background is estimated from a blank which has been counted for a specific period, the following applies: B = estimated background (counts) b b = blank background (counts) tb = blank count time (seconds) ts = sample count time (seconds) r=1+t 3 4 tb Proposed Amendment No. 155 4-72c
l 155> RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.21-2 (Continued) RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Table Notation 3.70E4 = disintegrations /second/ microcurie Y = yield of radiochemical process, i.e., the product of all factors such as emission fraction, chemical yield, etc. E = counting efficiency (count / disintegrations) V = sample volume (milliliters) T=[1-exp(-Ats)]exp(-Ate)_ A where 1 = decay constant (seconds -1) tc = time from midpoint of collection to start of counting (3) When spectroscopy is used to analyze the sample, the following LLD equation is used: LLD = 2.'71 + 4.65(B)0.5 3.70E4 (YEVT) Where B is the counts in the Region Of Interest. l 1 Proposed Amendment No. 155 4-72d l __ -_ _ _ __Y
155k RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards TABLE 4.21-2 (Continued) RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM
- b. A batch release is the discharge of liquid wastes of. discrete volume from the A or B Regenerant Holdup Tanks. Prior to sampling, each batch will be isolated, and then thoroughly mixe6 to assure representative sampling.
- c. Other peaks which are measureable and identifiable, together with the listed nuclides, shall also be identified and reported.. Nuclides which are not observed for the analysis shall be reported as "less than" the instrument's LLD, and shall not be reported as being present. The "less than" values shall not be used in the ODCM evaluations. However, if the nuclide is measured and identified at a value less than the Table 4.21-2 LLD value, it shall be reported and entered into the ODCM evaluations.
h d A composite sample is one in which the quantity of liquid samples is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
\
l Proposed Amendment No. 155 4-72e 4
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.21.3 Liquid Holdup Tanks
- Surveillance Requirements The quantity of radioactive material contained in each tank listed in Speci.fication 3.17.3 shall be determined to be within the specified limit by analyzing a representative sample of the tank's contents at least weekly when radioactive materials are being added to the tank.
Bases Restricting the quantity of radioactive material contained in the specified outdoor tanks provides assurance that in the event of an uncontrolled release 155> of the tank's contents, the concentration at the nearest potable water supply
< and the surface water supply in an unrestricted area would be less than the-limits of 10 CFR Part 20, Appendix 0, Table II,_ Column 2.
\
1
- Tanks included in this specification are those outdoor tanks that are not surrounded by liners,' dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the j' liquid radwaste treatment system or the LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM.
S l Proposed Amendment No. 155 4-73 i
. J
- r. ! RANCHO SECO UNIT 1
' TECHNICAL SPECIFICATIONS Surveillance Standards 155> 4.21.4
- Liquid Effluent Radwaste Treatment Surveillance Requirements Doses due to liquid releases to unrestricted areas shall be projected at least once per 31 days in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (0DCM) when LIQUID EFFLUENT RADWASTE TREATMENT SYSTEMS are not being fully utilized. The installed LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM shall be considered OPERABLE by meeting Specifications 3.17.1 and 3.17.2.
Bases The OPERABILITY of.the LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM ensures that. this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions cf this system be used when specified provides assurance that the release of radioactive materials in liquid effluents will be kept "as low as is reasonable achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10'CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as the. dose design objectives set forth in Section II. A of Appendix I,10 CFR Part 50, for liquid effluents. \ 11:
" Ine installation of the LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM is not complete. This specification will become effective when the system is declared operable.
I t i Proposed Amendment No.155 4-73a
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.22 GASEOUS EFFLUENTS 4.22.1 Dose Rate Surveillance Requirements j 155> The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits in Specification 3.18.1 in accordance with the
< methodology described in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
The noble gas effluent continuous monitors, as listed in Table 3.16-1, shall use monitor setpoints to limit the dose rate in unrestricted areas to the . 155>< limits in Specification 3.18.1. l The release rate of radioactive materials, other than noble gases, in gaseous effluents shall be detemined by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, l specified in Table 4.22-1. l 155> The dose rate due t3 Iodine-131, Iodine-133, tritium, and all radioactive material in particulate form with half-lives greater than 8 days released in gaseous effluents, shall be determined to be within the limits in Specification 3.18.1 by using the results of the sampling and analysis program specified in Table 4.22-1, and in accordance with the methodology described in
< the 00CM. \
Jl Bases This specification is provided to ensure that the dose rate at any time at the 155> Exclusion Area Boundary (Figure 5.1-1) from gaseous effluents will be within
< the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance 155> that radioactive material discharged in gaseous effluents will not result in
< the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)(1)). For individuals who may at times be within the Exclusion Area Boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above 155> background to an individual at or beyond the Exclusion Area Boundary to less
< than or equal to 500 mrem / year to the total body or to less than or equal to 3,000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via 155> the grass-cow-milk-infant pathway to less than or equal to 1,500 mrem / year for 4 the nearest dairy cow to the plant.
Proposed Amendment No.155 4-74
l RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.22-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Sampling Minimum Analysis Type of Activity Lower Limit Gaseous Release Frequency Frequency Analysis - of Detection Type (LLD) a (uC1/ml) 155>< A. Waste Gas P P Storage Tank Each Tank Each Tank Principal Gamma 1 x 10-4 Grab Emitters (f) Sample 155> B. Reactor Building P P Purge Vent Each Purge Each Purge (b,e,1) Principal Gamma 1 x 10-4 Grab Emitters (f)
< Sample (b,e,1)
H-3 1 x 10-6 155>< C. Auxiliary M(b,c.e) M(b) Principal Gamma 1 x 10-4 Building Stack, Grab Emitters (f) Sample
\ H-3 1 x 10-6 155> D. Auxiliary M(b) M(b) Principal Gamma 1 x 10-4 Building Grade Grab Emitters (f)
Level Vent Sample H-3 1 x 10-6 155>< E. All Release Continuous W(d) 1-131 1 x 10-12 Types as listed Charcoal 155>< in A,B,C,D above Sample I-133 1 x 10-10 Continuous W(d) Particulate Principal Gamma 1 x 10-11 Sample Emitters (f)
. (I-131, Others) ..
155> Continuous M Gross Alpha (h) 1 x 10-AA Composite Particulate Sample
< Sr-69, Sr-90(g) 1 x 10-11 Continuous Noble Gas Noble Gases 1 x 10-6 155>< Monitor Gross Beta and Gamma as Xe-133 Proposed Amendment No. 155 4-75
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.22-1 (Continued) RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM Table Notation 155> a. (1) The lower limit of detection (LLD) for a radionuclides presented in this table is the largest concentration, ~ expressed in microcuries l Ai per unit volume, which is required to be detected, if present, in ILM order to achieve compliance with the limits of Specifications 3.18.1, 3.18.2 and 3.18.3. (2) The LLD of a radioanalysis system is that value which will indicate the presence or absence of radioactivity.in a sample when the probability of a false positive and of a false negative determination is stated. The probabilities'of false positive and false negative are taken as equal at 0.05. The equation for LLD in microcuries per cubic centimeter is' given by the equation: LLD = 2.71 + 3.29(Br)0.5 3.70E4(YEVT) where 2.71 = factor to account for Poisson distribution at very low background count rates. When backg'round is estimated from a blank which has been counted for a specific period, the following applies: 1 B = estimated background (counts) t
=b s tb gi b = blank background (counts) tb = blank count time (seconds) ts = sample count time (seconds) r=1+t 3 tb 4
Proposed Amendment No.155 4-76
.155>
RANCHO.SEC0 UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.22-1 (Continued) RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM Table Notation 3.70E4 = disintegrations /second/ microcurie lb Y = yield of radiochemical process, i.e..' the product of all factors such as emission. fraction, chemical yield, etc. E = counting efficiency (count / disintegrations) V = sample volume (cubic centimeters) . where A = decay constant (seconds -1) tc = time from midpoint of collection to start of counting (3) When spectroscopy .is used to analyze the sample, the following LLD equation is used: LLO = 2.71 + 4.65(B)0.5 g 3.70E4 (YEVT) Where B is the counts in the Region Of Interest.
- b. Analysis shall also be performed when gross beta or gamma activity anaylsis of readtor coolant indicates greater than 10 uCi/ml and after each 10 pCi/ml increase in the gross beta or gamma activity analysis.
I
- c. Tritium grab samples shall be taken at least once per seven days from the ventilation exhaust from the auxiliary building stack during refueling and anytime fuel is in the spent fuel pool and the pool temperature exceeds 110"F. Below 110"F there is essentially no evaporation from this source. ;
i I l l I Proposed Amendment No. 155 4-76a
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.22-1 (Continued) RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM Table Notation i 155>< d. Samples shall be changed at least weekly and analyses shall he completed within 48 hours. Sampling and analysis shall also be perfomed when reactor coolant indicates 10 C1/ml gross beta gamma activity and every 10pCi/ml increases thereafter. When samples collected for less than 24 hours are analyzed, the corresponding LLD's maybe increased by a factor of 10.
- e. Tritium grab samples shall be taken at least daily during refueling activities.
155> f. Principle gamma emitters for which the LLD applies are: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-135m, and Xe-138 for gaseous samples and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, (or Tc99m), Cs-134, Cs-137, Ce-141, and Ce-144 for particulate samples. This list does not mean only these nuclides will be detected and reported. Other peaks that are measurable and identifiable shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report, pursuant to S) edification 6.9.2.3. Nuclides which are below the LLD for the analysis s1all be reported as "less than" the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclide. However, if the nuclide is measured and identified at a value less than its predetermined LLD value, it shall be reported and entered into the ODCM evaluations.
- g. Gross beta analysis performed on a monthly basis for each environmental t release particulate sample. If any one of these samples indicates greater than 1.0 E-11 pCi/cc gross beta activity then a Sr-89, Sr-90 analysis will be performed on those samples exceeding this value.
- h. Gross alpha perfomed on a monthly basis for each environmental release particulate sample. This fulfills the requirements of perfoming a h monthly composite.
- i. Af ter purging seven reactor building volumes, a technical evaluation, prior to reinitiation of a purge following an out of service period, may be conducted in lieu of sampling and analysis.
Proposed Amendment No. 155 4 u_____
~ --- -' 155> RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 155>< 4.22.2 Dose-Noble Gases ; Dose Calculations 155> Cumulative air dose contributions for the calendar quarter and calendar year shall be determined in accordance with the methodology described in the OFFSITE DOSE CALCULATIONAL MANUAL (0DCM) at least
< monthly.
Bases This specification is provided to implement the requirements of Sections II.B. III.A, and IV.A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the l guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that 155> conformance with the guides of Appendix I be shown by calculational
< procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantia 1'ly underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates '; 155>< of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"' Revision 1, October 1977 and Regulatory Guide 1.111, " Methods -
for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," 155> Revision 1. July 1977. The ODCM equations provided for determining the air doses at the Site Boundary for Gaseous Effluents (Figure 5.1-3) and are based upon the historical average atmospheric
< conditions.
I i l Proposed Amendment No. 155 4-77 L _ __ _ _ _ _ _ _ _ _ _ _ _
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance ' Standards l 155> 4.22.3 Dose-Iodine-131, Iodine-133, Tritium, and Radioactive Materials in Particulate
< Fo nTI.
Dose Calculations 155> Cumulative dose contributions for the calendar quarter and calendar year period shall be determined in accordance with the methodology described in the
< (00CM) 0FFSITE DOSE CALCULATION MANUAL at least monthly.
Bases This specification is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be 155> substantially underestimated. The 00CM calculational methods for calculating 4 the doses due to the\ actual release rates of the subject materials are j consistent with the methodology provided in Regulatory Guide 1.109,
" Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"
Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations 155>< also provide for estimating doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, and 155>< radioactive material in particulate form are dependent on the existing radionuclides pathways to man at or beyond the Site Boundary for Gaseous Effluents (Figure 5.1-3). The pathways which are examined in the development of these calculations are: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man. I Proposed Amendment No. 155 4-78 l I
)
[ L RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS E Surveillance Standards l 155>< 4.22.4 Gaseous Radwaste Treatment Surveillance Requirement 155> Doses due to gaseous releases to areas at and beyond the Site Boundary For Gaseous Effluents (see Figure 5.1-3) shall be projected at least once per 31 days in 'accordance with the methodology and parameters in the 0FFSITE DOSE CALCULATION MANUAL (0DCM) when Gaseous Radwaste Treatment Systems are not being fully utilized. The installed VENTILATION EXHAUST TREATMENT SYSTEM and Waste Gas System shall 4 be considered OPERABLE by meeting Specifications 3.18.1, 3.18.2 and 3.18.3. Bases 155> The operability of the Waste Gas System and the VENTILATION EXHAUST TREATMENT SYSTEMS ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The
< requirement that the appropriate portions of systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General '
Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of\ appropriate portions of the systems were specified as ' 155>< the dose design objectives set forth in Sections II.B and II.C of Appendix I, g 10 CFR Part 50, for gaseous effluents. i l l Proposed Amendment No. 155 4-79 , 4 4
'(.
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 155>< 4.22.5 .. Gas Storage Tanks-Surveillance Requirements The quantity of radioactive material contained in each waste gas decay tank 155>< shall be determined to be within the limit in. Specification 3.18.5 at least daily when radioactive materials are being added to the tank and the Reactor Coolant System activity exceeds the limits of Specification 3.1'.4. Bases Restricting the ' quantity of radioactivity' contained in each waste gas decay tank provides assurance that in the event of an uncontrolled release of the-155> . tank's contents, the resulting total body exposure to an individual at the
< exclusion area boundary (see Figure 5.1-1) will not exceed 500 mrem.. This is consistent with Standard Review Plan 15.7.1, " Waste Gas System Failure." .
Calculations have shown that the reactor coolant activity must exceed the limits of Specification 3.1.4 before the' waste gas decay tank activity
- 155>< approaches the limits of Specification 3.18.5.
\
2 J . Proposed Amendment No. 155 4-80 1 L'
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.25 SOLID RADIOACTIVE WASTES Surveillance Requirements 155> 4.25.1 The solid radwaste systems shall be demonstrated OPERABLE at least once per 92 days by:
- a. Operating the solid radwaste system at least once in the previous 92 days in accordance with the PROCESS CONTROL PROGRAM, or
- b. Verification of the existence of a valid contract for SOLIDIFICATION to be performed by a contractor in accordance with a PROCESS CONTROL PROGRAM.
< 4.25.2 The PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION of at lease one representative test specimen from at least every tenth batch of each type of wet radioactive waste (e.g.,
filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions).
- a. If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent te'st verifies SOLIDIFICATION. SOLIDIFICATION of the batch may
'g then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM.
- b. If the' initial test specimen from a batch of waste fails to vertfy SOLIDIFICATION,*the PROCESS CONTROL PROGRAM shall provide for the collection.and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.15, to assure SOLIDIFICATION of subsequent batches of waste.
155>< Bases 155> The OPERABILITY of the solid radwaste system ens'ures that the system will be available for use whenever solid radwastes require processing and packaging
< prior to being shipped offsite.
This specification implemts the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing 'the PROCESS CONTROL PROGRAM may include, but are not limiteo to waste type, waste pH, waste / liquid / solidification agent / catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times. Proposed Amendment No. 155 4-81
RANCHO SECO UNIT 1 - TECHNICAL SPECIFICATIONS Surveillance Standards e 4.25 (Continued). i Bases 155> The OPERABILITY of the solid radwaste system ensures that the system will be available for use whenever solid radwastes require processing and packaging
< - prior to being shipped offsite.
\ -
Proposed Amendment No. 155 4-82
\
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS. l Surveillance Standards li 4.26 RADIOLOGICAL ENVIRONMENTAL MONITORING Surveillance Requirements The radiological environmental monitoring samples shall be collected per Table 155> 3.22-1 from the locations shown in the RADIOLOGICAL ENVIRONMENTAL MONITORING 4' PROGRAM (REMP) MANUAL and shall be analyzed to the requirements of Tables 3.22-1 and 4.26-1. Bases 155>< The Radiological Environmental Monitoring Program required by this specification provides measurements of radiation and.of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby implements Section IV.B.2 of Appendix I to 10CFR50 and supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of 155>< the effluent measurements and ODCM modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. The specified monitoring program is in effect at the present time. Program changes may be initiated based on operational experience and chang s in regional population or agricultural practices. The 155>< sample locations have been listed in the REMP MANUAL to retain flexibility for g making changes as needed. 155> The detection capabilities requir.ed by Table 4.26-1 are state-of-the-art for
- routine environmental measurements in industrial laboratories. The LLD's for drinking water meet the requirements of 40 CFR 141.
)
Proposed Amendment No. 155 4-83 l l 1 l J
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1 l RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS 4 Surveillance Standards Tab'le 4.26-1 (Continued) MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a, d Table Notation 155>- a. (1) The lower limit of detection (LLD) for a radionuclides presented in this table is the largest concentration, expressed in picocuries_ per unit sample, which is required to be detected if present, in order to achieve compliance with .the appli regulation, given stated operating conditions and calculation methology. (2) The LLD of a radioanalysis system is that value which will indicate the presence or absence of radioactivity in a sample when the probability of a false positive and of a false negative determination is stated. The probabilities of false positive and false negative are taken as equal at 0.05. The equation for LLD in picocuries per unit sample is given by the equation: LLD = 2.71 + 3.29(Br)0.5 3.70E4(YEVT) h 2.71 =\factor to account for Poisson distribution at very low background count rates. When background is estimated from a blank which has been counted for a specific period, the following applies: B = estimated background (counts) t
=b 3 tb b = blank background (counts) h tb = blank count time (seconds) ts = sample count time (seconds) r=1+ s tb Proposed Amendment No.155 4-85 4
f
- RANCHO SECO UN1T 1
' TECHNICAL-SPECIFICATIONS Surveillance Standards Table 4.26-1 (Continued)
' MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a, d Table Notation-3.70E4 = disintegrations /second/ microcurie' L Y = yield of radiochemical process l
, E = counting efficiency (count / disintegrations)
V = sample volume (liters) or mass (kilograms) T = [1-exp(-Ate)]exp(-Atc)_ A where x = decay constant (seconds'-1). tc =.. time from midpoint of collection to start of counting (3) When spectroscopy is used to analyze the sample, the following LLD
. equation is used:
LLD + 2.71 + 4.65(B)0.5 3 70E4 (YEVT) Where B is the counts in the Region Of Interest. ) Proposed Amendment No.155 4-85a
-(
l
n 155>. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards Table 4.26-1 (Continued) MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)a, d Table Notation (4) Analyses shall be performed in such a manner that the stated LLD's will be achieved under routine conditions. Occasionally, background d
' fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLD's unachievable. In such cases, the contributing.
factors will be identified and described in the Annual Radiological Environmental Operating Report.
- b. LLD for drinking water.
- c. LLD sgown ig for composite analysis. For individual samples, 5x10 pC1/m3 is the LLD.
- d. Other peaks whic.h are measurable and identifiable, together with the nuclides in Table 4.26-1, shall be identified and reported.
155>< e. Total for parent and daughter.
\
l l Proposed Amendment No. 155 i i 1 I i C____________.________ _ _ _ . .
j RANCHO SECO UNIT 1
. TECHNICAL SPECIFICATIONS f Surveillance Standards .,t" y ; '
4.27 LAND USE CENSUS s, '-{; Surveillance Requirements. The land use census shall be conducted annually by using methods tifdwill provide the best results, such as door-to-door survey, aerial survty, or by ' consulting local agriculture authorities.. -
\
1554 The land use census or portions. thereof, shall be conducted.during the
- appropriate time of the year .to provide the best results.
Reoorts The.results of the land use census shall be included'in the Annual Radiological Environmental Operating Report, , 1 '~ Bases , This specification is provided to ensure that changes in 'the)0se of 155- unrestricted areas are identified and that modifications c tcribe RADIOLOGICAL
- ENVIRONMENTAL MONITORING PROGRAM MANUAL and ODCM are made If required by the results of this census. This census satisfies the requirkmerits of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the/ census to gardens of greater than 500 square feet provides assurance that significant exposure i pathways via leafy vegetables will be identified and monitored, since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of. leafy vegetable assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: (1) that 20 percent of the garden was used for growing broad-leaf vegetation (i.e.,similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/ square meter.
155- In addition, by gathering information on the liquid effluent pathway and the gaseous effluent pathway, the census will assure that proper radiological environmental monitoring and radioactive effluent controls are ih place for
- the adequate protection of the health and safety of the general,bublic.
y/ 4 ( l l
,\
,a L
Proposed Amendment No. 155 4-86 i l
- f. '
f RANCHO SECO UNIT 1 l TECHNICAL SPECIFICATIONS Surveillance Standards j , 4.29 FUEL CYCLE DOSE Surveillance Requirements Cumulativt dose contributions from liquid and gaseous effluents shall be 155> determined in accordance with Specifications 4.21.2, 4.22.2, and 4.22.3 and in
< accordance with the OFFSITE DOSE CALCULATION MANUAL (0DCM).
-155> Ct.mulative dose contributions from direct radiation (including outside storage tanks, etc.) shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). This requirement is applicable only under
< conditions set forth in the Action Statement of Specification 3.25.
Reports l , Special reports shall be submitted as required under Specification 3.25. [ Bases This specification is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive-effluents exceed twice the numerical 155> guides for design objective doses of hpendix I or exceeds the reporting levels for the Radiological Environmerital Monitoring Program. For the Rancho Seco site, it is unlikely that the resultant dose to a MEMBER OF THE PUBLIC 4 will exceed the dose limits of 40 CFR 190 if the plant remains within twice the numerical guides for design objectives of 10 CFR 50, Appendix I and if direct radiation (outside storar,,e' tanks, etc.) is kept small. The Special Report will describe a course of action which should result in the limitation of the dose to a MEMBER OF THE PUBLIC for 12 consecutive months to within the . 40 CFR 190 limits. For the pwposes of the Special Report, it may be assumed that the dose commitment to 7.e MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible! with the exception that dose contributions from other nuclear fuel cycle' ncilities at the shme site or within a radius of 5 miles must be considerid. If the dose to any MEMBER OF THE PUBLIC is evaluated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC' staff action is completed. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation which;1s part of the uranium
< fuel, cycle.
Proposed Amendment No. 155 4-89
4 j RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Design Features
- 5. DESIGN FEATURES 155> 5.1 SITE The Rancho Seco reactor is located on the 2,480 acres owned by Sacramento Municipal Utility District, 26.m11es north-northeast of Stockton and 25 miles southeast of the City of Sacramento, California. The minimum distance to the boundery of the exclusion area, as defined in 10 CFR 100.3, shall be 2,100 feet.
5.1.1 Exclusion Area The EXCLUSION AREA shall be shown in Figure 5.1-1. 5.1.2 Low Population Zone The LOW POPULATION ZONE shall be shown in Figure 5.1-2. 5.1.3 Site Boundary For Gaseous Effluents The SITE BOUNDARY FOR GASEOUS EFFLUENTS shall be shown in Figure 5.1-3. 5.1.4 Site Boundary For Liquid Effluents The SITE B0UNDARY FOR LIQUID EFFLUENTS shall be shown in Figure i < 5.1-4. , 1 Proposed Amendment No. 155 5-1 l .
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l l 1: al - 1 -l = { . l l l i Proposed Amendment No. 155 5-5 es' 3 $4 4
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls RESPONSIBILITIES (Continued)
- h. Performance of special reviews and investigations and reports 138>< thereon as requested by the AGM, Nuclear Power Production.
138> 1. Review of the Plant Security Plan and changes thereto.
- j. Review of the Emergency Plan and changes thereto.
- k. Review of changes to the PROCESS CONTROL PROGRAM, the 0FFSITE 155> DOSE CALCULATION MANUAL and the RADIOLOGICAL ENVIRONMENTAL
< MONITORING PROGRN4 MANUAL. (See Specifications 6.15 and 6.16.)
- 1. Review of major changes to the Radioactive Waste Treatment Systems (Liquid, Gaseous and Solid), and all information required
< by Specification 6.17.
155> m. Review of any accidental, unplanned, or uncontrolled release of radioactive material to the environs including the preparation and i fomarding of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence, and the forwarding of these reports to the Nuclear Plant Manager and to the '
< MSRC.
l
\
AUTHORITY
.!i 6.5.1.7 The Plant Review Committee shall:
138>< a. Recommend in writing to the AGM, Nuclear Power Production approval or disapproval of items considered under 6.5.1.6(a) through 155>< (m) above.
- b. Render determinations in writing with regard to whether or not 155>< each item considered under 6.5.1.6(a) through (e), and (1) above constitutes an unreviewed safety question,
- c. Provide immediate written notification to the Chairman of the Management Safety Review Committee of disagreement between the 138> PRC and the AGM, Nuclear Power Production; however, the AGM,
< Nuclear Power Production shall have responsibility for resolution of such disagreements pursuant to 6.5.1.1 above.
RECORDS i 6.5.1.8 The Plant Review Committee shall maintain written minutes of each 138> meeting and copies shall be provided to the AGM, Nuclear Power ,
< Production and the Chairman of the Management Safety Review Committee.
Proposed Amendment No. 138, Rev. 2 Proposed Amendment No. 155 65 I
m RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 138>< 6.5.4 (Continued)
- a. The conformance of facility operation to all provisions contained within the Technical Specifications and applicable license conditions at least once per year.
- b. The performance, training and qualifications of the Of strict's '
entire facility technical staff at least once per year.
- c. The result of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or' metho(s of operation that affect nuclear safety at least once per six 138>< months for those changes not previously audited,
- d. The performance of all activities required by the Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per two (2) years.
- e. The Facility Emergency Plan and implementing procedures at least once per two (2) years.
- f. The Facility Security Plan and implementing procedures at least once per two (2) years.
- g. Any other area of facility operation considered appropriate by
-138>< the MSRC, Deputy General Manager, Nuclear or the General Manager.
- h. Complian\ce with fire protection requirements and implementing procedures at least once per two (2) years.
- 1. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
- j. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than three (3) years.
- k. The radiological environmental monitoring program and the results thereof at least once per 12 months.
- 1. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months. ,
155> m. The PROCESS CONTROL PROGRAM and implementing procedures for l < processing and packaging of radioactive wastes from liquid systems at least once per 24 months. l 155> n. The performance of activities required by the Quality Assurance
< Program for Effluent Control and Environmental Monitoring.
138> Audit reports of reviews encompassed by Section 6.5.4 shall be J forwarded to the General Manager, MSRC Chairman, and to the management i positi.ons responsible for the areas reviewed within
< 30 days af ter completion.
'PrbposedAmendment'No.138,Rev.2 Proposed Amendment No. 155 6-10 t s.
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.7 SAFETY LIMIT VIOLATION' 6.7.1 .The following actions shall be taken in the event a Safety Limit is
. violated:
- a. The provisions of 10 CFR 50.36 (c) (1) (1) and 10 CFR 50.72 shall be complied with.
138> b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Director, Nuclear Operations and Maintenance, the AGM, Nuclear Power Production, and the Chainnan of the MSRC shall be notified
< within 24 hours,
- c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
- d. The Safety Limit Violation Report shall be submitted to the 138> Commission, the MSRC, and the AGM, Nuclear Power Production,
< within 14 days of the violation.
6.8 PROCEDURES c 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below: , I
- a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33', November 1972. -
b.. Refueling operations, i
- c. Surveillance and test activities of safety related equipment.
- d. Security Plan implementation. i
- e. Emergency Plan implementation, j
- f. Fire Protection Procedures implementation.
155> g. PROCESS CONTROL PROGRAM implementation.
- h. OFFSITE DOSE CALCULATION MANUAL implementation.
- 1. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL implementation.
- j. Quality Assurance Program for the Effluent Control and Environmental Monit'oring using the guidance of Regulatory Guide
< 4.15, Revision 1, February 1979.
138> 6.8.2 Each procedure of 6.8.1 above and changes thereto shall be reviewed
< and approved as set forth in Specification 6.5.
Proposed Amendment No. 138, Rev. 2 Proposed Amendment No. 155 6-11 l l
RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS Administrative Controls -
, - 6.8 PROCEDURES (Continued) 1 6.8.3 Temporary changes to procedure 6.8.1 above may. be made provided:
- a. The intent of the original procedure is not altered,
- b. The change is vproved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
The chenge is docunsr.ted, reviewed by the PRC and approved by
~
c. the Plant Superintendent within seven (7) days of implemen-tation. 6.9 REPORTING REQUIREMENTS 6.9.1 In addition to the applicable reporting requirements of Title 10,
- Code of Federal Regulations, the following reports shall De submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.
Startup Report 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitt following (1) Receipt of an operating license, (2) amendment of the license involving a planned increase in power level; (3) Installation of fuel that has a different design or has been manufactured by a different fuel supplier; and (4) 1- modifications that may have significantly altered the nuclear, thermal or hydraulic performance of the plant. The 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 comparison of ~ these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report. 6.9.1.2 Startup reports shall be submitted within (1) Ninety (90) days following completion of the startup test program; (2) Ninety (90) days following resumption or commencement of commercial power operation; or (3) Nine (9) months following initial criticality, whichever is earliest. If the Startup Report does not cover all l three events (i.e., initial criticality, completion of startup test ) program and resumption or commencement of commercial power l operation), supplementary reports shall be submitted at least every three (3) months until all three events have been completed. Proposed Amendment No. 155
- 6-12 f
.4
, T. I h __ _ _ _ _ _ _ _ _ -
)
RANCHO SECO UNIT 1 i TECHNICAL SPECIFICATIONS l Administrative Controls 155>< 6.9.2 Radiological Reports 6.9.2.1 Annual Radiological Reports Annual reports covering the activities of the unit, as described j 155> below, for the previous calendar year shall be submitted as follows: 6.9.2.1.1 Annual Occupational Radiation Exposure Report i l The Annual Occupational Radiation Exposure Report shall be 3 submitted to the Commission within the first calendar quarter of each calendar year in compliance with 10CFR20.407. 6.9.2.1.2 Annual Exposure Report The Annual Exposure Report shall be submitted to the Commission within the first calendar quarter of each calendar year in
< accordance with the guidance contained in Regulatory Guide 1.16.
6.9.2.2 Annual Radiological Environmental Operating Report 155>< 6.9.2.2.1 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar 155>< year shall be submitted prior to May 1 of each year. 155>< 6.9.2.2.2 The Annual Radiological Environmental Operating Reports shall y include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance . reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the 155>< Land Use Census required by Specification 3.23. If hannful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem. 155>< Proposed Amendment No. 155 6-12a
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.9.2.2.2 (Continued) i 155>< The Annual Radiological Environmental Operating Reports shall 138> include summarized and tabulated results of all radiological
< environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
The reports shall also include the following: a summary 155> description of the Radiological Environmental Monitoring
< Program; including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; the result of land use censuses, and the results of licensee participation in the Interlab Comparison Program. The annual report shall also 155> include information related to Specification 4.29, Uranium Fuel
< Cycle Dose.
6.9.2.3 Semiannual Radioactive Effluent Release Report 155>< Routine Semipnnual Radioactive Effluent Release Reports covering the operation of the unit during the previous six months of operation shall be submitted within 60 days after January 1 and July 1 of each 1 year. 155>< 155>< 6.9.2.3.1 The Semiannual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21 " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," with data summarized on a quarterly basis, following the format of Appendix B thereof. 155> The Semiannual Radioactive Effluent Release Report shall include a summary of hourly meteorological data collected over the
< report period. ,
1 Proposed Amendment No. 138, Rev. 2 Proposed Amendment No. 155 6-12b l l e - _ _ _ _ _ - _ - _ _ _ _ - - _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ .
RANCHO SECO UNIT 1 L ' TECHNICAL SPECIFICATIONS Administrative Controls M 6.9.2.3.1. Continued) 155><. The Semiannual . Radioactive Effluent Release Reports shall L include an assessment of the radiation doses from radioactive L gaseous and liquid effluents to individuals due to their l 155><: activities inside the site boundary (Figures 5.1-3 and 5.1-4) during the report period. , ~ All assumptions used in' making assessments (e.g., specific activity, exposure time, and . these
-location). shall be included in these reports.
155><. The Semiannual Radioactive Effluent. Release Reports shall include the following infomation for all unplanned releases to unrestricted areas of radioactive materials in gaseous and liquid effluents:
- a. A description of the event and equipment involved.
- b. - Cause(s) for the unplanned release.
- c. Actions taken to prevent recurrence.
- d. Consequences of the unplanned release. ,
i The radioactive effluent release reports shall include an assessment of radiation doses from the radioactive liquid and ' gaseous effluents released from the unit during each calendar quarter, as outlined in Regulatory Guide 1.21. The assessment of radiation doses shall be perfomed in accordance with the 155> 0FFSITE DOSE CALCULATION MANUAL (ODCM). The Semiannual Radioactive Effluent Release Reports shall include any changes made during' the reporting period to the PROCESS CONTROL PROGRAM (PCP), RADIOLOGICAL ENVIRONMENTAL d MONITORING PROGRAM MANUAL and 0FFSITE DOSE CALCULATION MANUAL- .j (0DCM) pursuant to Specifications 6.15 and 6.16 as well as any 1 major changes to Liquid, Gaseous or Solid Radwater Treatment Systems pursuant to Specification 6.17. The Semiannual Radioactive Effluent Release Report shall include tables for comparison with Specifications 3.17.2, 3.18.2, and 3.18.3. The July-December report shall include a sumary table for comparison with the annual valuestin Specifications 3.17.2, 3.18.2, and 3.18.3. The Semiannual Radioactive Effluent Release Report shall also include events described in Specifications 3.17.1, 3.17.3, 3.18.1 and 3.20. Proposed Amendment No. 155 6-12c i - - - _- - t
j i RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.9.2.3.1 Continued) 155F The Semiannual Radioactive Effluent Release Report shall include the following information.for each type of solid waste shipped offsite during the report period:
- a. Container volume, '
- b. Total curie quantity (determined by measurement or estimate),
- c. Principal radionuclides (determined by measurement or estimate),
- d. . Type of waste (e.g., spent resin, compacted dry waste evaporator bottoms),
- e. Type _ of container (e.g., LSA, Type A, Type B, High Integrity),and
- f. Solidification agent (e.g., cement).
MONTHLY REPORT 6.9.3 Routine repo,rts of operating statistics, including narrative summary of operating and shutdown experience, of lifts of the Primary System Safety Valves or EMOVs, of major safety related maintenance, and 3 tabulations of facility changes, tests or experiments required pursuant to 10 CFR 50.59(b), shall be submitted on a monthly basis to the Office of Director of Inspection and Enforcement, U. S. kuclear Regulatory Commission, Washington, D. C. 20555, with a copy to the Regional Office, postmarked no later than the 15th day of each month ~ following the calendar month covered by the report. LICENSEE EVENT REPORT 6.9.4 The LICENSEE EVENT REPORTS of Specification 6.9.4.1 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC as Licensee Event Reports. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a License Event Report shall be completed and reference shall:be made to the original report date, pursuant to the requirements of 10 CFR 50.73. 4 Proposed Amendment No.155 6-12d
4- e-r p'- RANCHO SECO UNIT 1~. TECHNICAL SPECIFICATIONS-
. Administrative Controls LICENSEE EVENT REPORT 6.9.4.1 The types of events listed below shall be the sub, Ject of written reports to the Director of the Regional Office within thirty (30) days of occurrence of the event. The written' report shall include, as' a minimum, a' completed copy of a licensee event report form, pursuant to 10 CFR 50.73 and the guidance of NUREG-1022. -;
- a. (i) ' The completion of any nuclear plant shutdown-required by the plant's Technical Specification; or (11) any operation or condition prohibited by the plant's Technical Specifications; or (iii) Any deviation from the plant's Technical Specifications authorized pursuant to 10 CFR 50.54(x).
- b. Any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded, or that resulted in the nuclear power plant being:
(i) . In an unanalyzed condition that significantly compromised plant safety; (ii) In a condition that was outside the design basis of the p1' ant; or
< (iii) In a condition not covered by the plant's operating and emergency procedures.
- c. any natural phenomenon or other external condition that posed an actual threat to the safety of the nuclear' power plant or ~
significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear power plant.
- d. Any event or condition that resul.ted in manual or automatic actuation of any Engineered Safety Feature (ESF), including the Reactor Protection System (RPS). However, actuation of an ESF, including the RPS, that resulted from and was part of the preplanned sequence during testing or reactor operation need not be reported. -
l e. any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to:
- 1. Shut down the reactor and maintain it in a safe shutdown condition; 1 Proposed Amendment No. 155
- 1. 155H 6-12e ,
1 l
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls LICENSEE EVENT REPORT i
- 2. Remove residual heat;
- 3. Control the release of radioactive material; or
- 4. Mitigate the consequences of an accident. !
- f. Events covered in paragraph 6.9.4.1.e of this section may include one or more procedural errors, equipment failures, and/or discovery of design, analysis, fabrication, construction, and/or procedural inadequacies. However, individual component failures need not be reported pursuant to this paragraph if redundant equipment in the same system was operable and available to perform the required safety function.
- g. Any event where a single cause or condition caused at least one independent train or channel to become inoperable in multiple ,
systems or two independent trains or channels to become inoperable in a single system designed to:
- 1. Shut down the reactor and maintain it in a safe shutdown condition;
- 2. Remove residual heat;
\
- 3. Control the release of radioactive material; or "4 4. Mitigate the consequences of an accident.
Any airborne radioactivity release that exceeded 2 times
- h. 1.
the applicable concentrations of the limits specified in Appendix B, Table II of 10 CFR 20 in unrestricted areas, _.! when averaged over a time period of one hour.
- 2. Any liquid effluent release that exceeded 2 times the limiting combined Maximum Permissible Concentration (MPC)
(see Note 1 of Appendix B to 10.CFR 20) at the point of entry into the receiving water (i.e., unrestricted area) for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour.
- i. Any event that posed an actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear power plant including fires, toxic gas releases, or radioactive releases.
- j. Failure of the pressurizer EMOVs or Primary System Safety Valves.
Proposed Amendment No. 155 l l l l L _ _ _ . _ . ...___.______.__________________i
RANCHO SECO UNIT 1 i TECHNICAL'SPECIFICAT!0NS l' Administrative Controls Special Reports 1 6.9.5 Special reports shall be submitted to the Regional Administrator,_ Region Y Office, within the time perio.d specified for each report. 1 These reports shall be submitted ' covering the activities identified below pursuant to the requirements of the applicable reference 1 specification: l, l A. A one-time only, " Narrative Sununary of Operating Experience" I will be submitted to cover the transition period (calendar year 1977). B. A Reactor Building Structural integrity report shall be submitted within ninety (90) days of completion of each of the following tests covered by Technical Specification 4.4.2 (the integrated leak rate test is covered in Technical Specification 4.4.1.1).
- 1. Annual Inspection
- 2. Tendon Stress Surveillance
- 3. End Anchorage Concrete Surveillance
- 4. Liner Plate Surveillance C. Inserv(ceInspectionProgram D. Inoperable Accident Monitoring Instrumentation 30 days (3.5.5) i; E. Status of Inoperable Fire Protection Equipment F. Inoperable Emergency Control Room /TSC Ventilation Room Filter System ,
G. Radioactive Liquid Effluent Dose 30 days (3.17.2) i H. Noble Gas Limits 30 days (3.18.2)
- 1. Radioiodine and Particulate 30 days (3.18.3) 155> J. Gaseous and Liquid Radwaste Treatment 30 days (3.18.4 and 3.17.4)
< K. Radiological Environmental Monitoring Program 30 days (3.22)
L. Monitoring Point Substitutions 30 days (3.22) 155>< M. Solid Radioactive Wastes 30 days (3.21) N. Fuel Cycle Dose 30 days (3.25) , 155>< 0. Land Use Census 30 days (3.23) P. Steam Generator Tube Inspection 30 days (4.17.5) Proposed Amendment No. 155 155>< 6-129
f RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls
- b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
- c. Records of facility radiation and contamination surveys.
- d. Records of radiation exposure for all individuals entering radiation control areas.
- e. Records of gaseous and liquid radioactive ' material released-to -
the environs.
- f. Records of transient or operational cycles for those facility components designed for a limited number'of transients or cycles.
- g. Records of training end qualification for current members of the plant operating staff.
- h. Records of in-service inspections performed pursuant to these Technical Specifications.
- i. Records of Quality Assurance activities required by the QA Manual.
- j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
1 k. Records of meetings of the PRC and the MSRC.
- 1. Records for Environmental Qualification which are covered under the provisions of paragraph 6.14.
~
155x m. Records for the Radiological Environmental Monitoring Program.
- n. Records of the maintenance of all hydraulic snubbers listed in Table 3.12-1.-
, 6.11 RADIATION PROTECTICN PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving l personnel radiation exposure. 6.12 - Deleted Proposed Amendment No. 155 6-14 l l i t_ i
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.15 PROCESS CONTROL PROGRAM (PCP) 6.15.1 Function 155> The PROCESS CONTROL PROGRAM shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive. wastes from liquid systems is assured. 6.15.2 Changes A. The PCP shall be approved by the Commission prior to implementation. B. Licensee initiated changes to the FCP shall:
- 1. Be submitted to the Commission hy inclusion in the
< Semiannual Radioactive Effluent Release Report for the period in which the change (s) was/were made and shall contain:
- a. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; b.\ A determination that the change did not reduce the overall conformance of the solidified waste product to U existing criteria for solid wastes; and
- c. Documentation of the fact that the change has been reviewed and found acceptable hy the Plant Review Committee. .
- 2. Become effective upon review and acceptance by the PRC, l unless otherwise acted upon by the Commission through written notification to the Licensee.
b Proposed Amendment No. 155 6-17 l Q__---__________________
f RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls j 155>< 6.16 0FFSITE DOSE CALCULATION AND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL 5 6.16.1 Function 155> 6.16.1.1 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall describe the methodology and parameters to be used in the calculation of offsite
< ' doses due to the release cf radioactive material in gaseous and liquid effluents and in the calculation of gaseous and liquid' effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCO's contained in these Technical Specifications. Methodologies and calculational procedures acceptable to the Commission are contained in varf ous Regulatory Guides as noted in the bases of applicable LCO's.
.6.16.1.2 The RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) MANUAL shall be a manual- containing the description of the Rancho Seco Radiological Environmental Monitoring Program. The REMP manual shall contain a description of the environmental samples to be collected, the sample locations, sampling frequencies, and sample analysis criteria.
6.16.2 Any changes to the ODCM or REMP MANUAL shall be made as follows:
\
A. Licensee-initiated changes: A 1. Shall be submitted to the Commission by inclusion in the 155> Semiannual Radioactive Effluent Release Report for the
< period in which the change (s) was/were made and shall contain:
- a. Sufficiently detailed information to totally support )
the rationale for the change without benefit of additional or supplemental information. Information submitted should consist of a package of those pages 155>< of the ODCM and the REMP MANUAL to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the change (s);
- b. A determination that the change will not' reduce the accuracy or reliability of dose calculations or setpoint determinations; and
- c. Documentation of the fact that the change has been reviewed and found acceptable by both the PRC and MSRC.
- 2. Shall become effective upon a date specified and agreed to i
by both the PRC and MSRC following their review and acceptance of the change. Proposed Amendment No. 155
1 RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls 6.17 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS (LIQUID, GASEOUS, AND SOLID) 6.17.1 Function The radioactive waste treatment system (liquid, gaseous, and solid) 155>< are those systems described in the facility Updated Safety Analysis Report or Hazards Summary Report, and amendments thereto, which are used to maintain that control over radioactive materials in gaseous and liquid effluents and in solid waste packaged for offsite shipment required to meet the LCOs set forth in these Specifications. 6.17.2 Major changes to the radioactive waste systems (liquid, gaseous, and 138> solid) shall be made by the following method. For the purpose of this
< specification, " major changes' is defined in Specification 6.17.3.
138> Licensee-initiated changes:
- 1. The Commission shall be informed of all changes by the inclusion of a suitable discussion of each change in the Semiannual Radioactive Release Report for the period in which the changes were made. The discussion of each change shall contain:
- a. A summary of the evaluation that led to the determination ttgat the change could be made in accordance with 10 CFR 50.59; l' b. Sufficient information to support the reason for the change without benefit of additional or supplemental information;
- c. A description of the equipment, components, and processes involved, and the interfaces with other plant systems;
- d. An evaluation of the change with regard to the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of sclid waste if different from those previously predicted in the license application and amendments thereto; 155> e. An evaluation of the change with regard to the expected maximum exposures to a MEMBER OF THE PUBLIC in the
< UNRESTRICTED AREA and to the general population if different from those previously estimated in the license application and amendments thereto; Proposed knendment No.138, Rev. 2 Proposed Amendment No. 155 6-19
L RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS-TABLE OF CONTENTS APPENDIX B PAGE i 1.0 DEFINITIONS 1 { 2.0 ENVIRONMENTAL PROTECTION CONDITIONS 4 2.1 Deleted 2.2 Deleted 2.3 Deleted 2.4 Deleted 2.5 Deleted 155>< 2.6 Deleted 20 3.0 NON-RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE PROGRAMS 25 3.1 Erosion 25 3.2 Drift Contaminants 25 3.3 Deleted 3.4 Noise 26 3.5' Fogging 27' 3.6 Deleted 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 31' J 4.1 Deleted 4.2 Deleted. 4.3 Deleted 4.4 Deleted 4.5 Deleted 4.6 Deleted 4.7 Deleted 4.8 Deleted 4.9 Deleted 4.10 Deleted 5.0 ADMINISTRATIVE CONTROLS 42 5.1 Responsibility 42 5.2 Organization 42 5.3 Review and Audit 42 5.4 Action to be taken in Event of Violation of an Environmental Protection Limit 43 5.5 Procedures 44 5.6 Plant Reporting Requirements 44 5.7 Records Retention 46 5.8 Deleted Proposed Amendment 155 1
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4 Proposed Amendment No. 155
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