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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20059C1861993-12-22022 December 1993 Proposed Tech Specs Amend 186,rev 1 Re Nuclear Organizational Changes ML20058L4371993-12-0909 December 1993 Proposed Tech Specs Amend 187 Including Changes Making PDTS Consistent W/New 10CFR20 Regulations ML20127N3671993-01-19019 January 1993 Proposed Tech Specs Section D6.0,administrative Controls for Proposed Amend 186 ML20246F1241989-07-0505 July 1989 Proposed Tech Specs,Deleting App B in Entirety ML20245H5781989-06-22022 June 1989 Proposed Tech Specs for Amend 109 to License DPR-54 ML20245L0461989-04-27027 April 1989 Proposed Tech Specs for Proposed Suppl 1 to Amend 134 Re Application for Amend to License DPR-54,clarifying Unacceptability of Analysis Allowing Imperfections Greater than 40% of Nominal Tube or Sleeve Wall Thickness ML20235Y6071989-03-0606 March 1989 Proposed Tech Spec Page 4-17,including one-time Extension for Certain Surveillances Required to Be Performed by 890329 ML20245H8911989-02-28028 February 1989 Revised Proposed Tech Specs,Including Pages 3-30a,3-30b, 3-40a,3-45,3-46,4-18a & 4-75 Re Addition of Operating Requirements Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations ML20195F7701988-11-18018 November 1988 Proposed Tech Spec Section 3.4, Steam & Power Conversion Sys ML20206F2881988-11-15015 November 1988 Proposed Tech Specs 4.6.4.f (Page 4-34i) Re Surveillance of Equipment Required to Verify Vital 120 Volt Ac Bus Operability ML20205R8681988-11-0404 November 1988 Proposed Tech Specs Re Local Leakage Rate Tests & Reactor Bldg Containment Integrity ML20205M8971988-10-28028 October 1988 Proposed Tech Specs Re Nuclear Svc Battery Operability & Surveillance Requirements ML20205L2661988-10-25025 October 1988 Proposed Tech Spec Table 3.14-3, Carbon Dioxide Suppression Zones ML20155G2201988-10-0707 October 1988 Proposed Tech Specs Clarifying Operational Mode Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Sys Train ML20155B4591988-09-30030 September 1988 Proposed Tech Spec Sections 1,3,4,5 & 6,reflecting Numerous Editorial Corrections & Administrative Changes ML20155B8481988-09-30030 September 1988 Proposed Tech Specs Re Reactor Protection Sys Trip Setting Limits,Rcs High Point Vents,Leakage & Leak Detection,Reactor Coolant Inventory & Auxiliary Electric Sys ML20154J5611988-09-19019 September 1988 Proposed Tech Specs,Changing Local Leak Rate Test Requirements for Containment Penetrations ML20154D7591988-09-0808 September 1988 Proposed Tech Specs Re Administrative Controls,Onsite & Offsite Organizations & Facility Staff ML20153E6481988-08-31031 August 1988 Proposed Tech Specs on Limiting Condition for Operation Re Containment Isolation Valves ML20207C0831988-07-27027 July 1988 Revised Proposed Tech Specs,Consisting of Rev 1 to Proposed Amend 102,deleting App B ML20196A2281988-06-21021 June 1988 Proposed Tech Specs Providing Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation & Modifying Existing Purge Sys Operation Requirement ML20155K0971988-06-14014 June 1988 Proposed Tech Specs Making Minor Corrections to Table 3.5.5-1, Accident Monitoring Instrumentation,Items 5 & 14 & Table 4.1-1 Items 65 & 92 & Adding Second Note to Table 4.1-1,Item 80 ML20195J4921988-06-10010 June 1988 Proposed Tech Spec Pages 4-69 Through 4-85a,modifying Radiological Effluent Tech Specs to Reduce Count Time Required for prebatch-release Sample Analysis ML20150D1861988-03-17017 March 1988 Proposed Tech Specs,Correcting Typos & Making Further Editorial Changes to Proposed Amend 139,dtd 860129 ML20196G5131988-03-0101 March 1988 Proposed Tech Specs,Revising Tech Spec 4.1-1,Item 44.c & Tech Spec 4.10.1.E.2 Re Total Quantity of Gaseous Chlorine in Restricted Area ML20147F0771988-02-25025 February 1988 Revised Proposed Tech Spec Table 4.1-1 & Tech Spec 4.10.1.E.2,requiring Performance of Surveillances Only When Gaseous Chlorine Onsite ML20149K8621988-02-12012 February 1988 Proposed Tech Spec 6.5.1.6.d,identifying Items Not Requiring Plant Review Committee Review ML20196D9091988-02-11011 February 1988 Proposed Tech Specs,Adding Term Dewatering to Process Control Program ML20149G1781988-02-0808 February 1988 Proposed Page 3-19 to Tech Spec 3.3, Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Sys ML20196B8071988-02-0101 February 1988 Proposed Tech Spec Figure 6.2-2, Nuclear Organization Chart ML20148J3531988-01-13013 January 1988 Proposed Tech Specs,Consisting of Proposed Amend 165,adding Ventilation Radiation Monitor to Interim Onsite Storage Bldg.Related Info Encl ML20149E5971988-01-0606 January 1988 Proposed Tech Spec 3.6,consolidating Applicability Requirement for Containment Integrity in Applicability Statement ML20149E1591987-12-23023 December 1987 Proposed Tech Specs Incorporating Accident Monitoring Instrumentation Recently Installed or Upgraded ML20149E8591987-12-22022 December 1987 Proposed Tech Specs,Establishing New Set Lower Limits of Detection for Prebatch Release & Composite post-release Analyses ML20237D1171987-12-15015 December 1987 Proposed Tech Spec Section 3.5.5, Accident Monitoring Instrumentation & Table 3.5.5-1, Accident Monitoring Instrumentation Operability Requirements, Changing Page Ref & Wording,Respectively ML20236W8671987-12-0303 December 1987 Proposed Tech Spec,Combining Tech Specs 3.3.1.E & 3.3.1.F for Nuclear Svc Cooling & Raw Water ML20236V7961987-11-25025 November 1987 Proposed Tech Spec Figures 6.2-1 & 6.2-2,reflecting Util Corporate Support of Nuclear Safety & Nuclear Organization Chart,Respectively ML20236U3361987-11-25025 November 1987 Proposed Tech Specs Page 1-2b,adding Words to Effect That 3.25 Factor Applicable to Three Consecutive Time Intervals Will Be Reset to Begin After Next Surveillance ML20236U0821987-11-25025 November 1987 Proposed Tech Specs,Consisting of Suppl 1 to Rev 0 to Proposed Amend 164 ML20236S0881987-11-17017 November 1987 Proposed Tech Specs,Consisting of Suppl 2 to Rev 2 to Proposed Amend 147,concerning Diesel Generators ML20236P3511987-11-0606 November 1987 Proposed Tech Specs Re Limiting Condition for Operation of Instrumentation Sys ML20236K3921987-11-0202 November 1987 Proposed Tech Spec Table 6.2-1, Shift Crew Personnel & License Requirements & Pages 6-7 & 6-8,adding non-licensed Personnel,Statement Re Limiting Representation to Minority of Quorom & Lers,Respectively ML20236D6601987-10-23023 October 1987 Proposed Tech Specs,Providing Exception to Requirement That key-operated Shutdown Bypass Switch Not Be Used During Reactor Power Operation ML20235R4261987-10-0303 October 1987 Proposed Radiological Effluent Tech Specs,Incorporating Clarifications & Correcting Editorial Errors ML20235Q5111987-10-0101 October 1987 Proposed Tech Specs Re Comparison of Plant Tech Specs to STS ML20235F5301987-09-22022 September 1987 Proposed Tech Specs Consisting of Supplemental Info to Proposed Amend 147,Rev 2 Re Diesel Generator Outages ML20235F4641987-09-21021 September 1987 Proposed Tech Specs Changing Requirements Re Concentration of Oxygen in Waste Gas Holdup Sys to Provide for When Sys Free of Potentially Explosive Gases,For Example,During Maint ML20234D6591987-09-16016 September 1987 Proposed Tech Specs,Reflecting Addl Organizational Changes Due to Need for Addl Mgt Staffing for Present Outage & from Expansion of long-term Mgt Function ML20238E8351987-09-0808 September 1987 Corrected Tech Spec Page 4-47c to Proposed Amend 151 to License DPR-54,adding ...Will Be Exceeded Prior to Next Scheduled Snubber Svc Life... to Last Paragraph of Tech Spec 4.14f ML20236M3531987-07-31031 July 1987 Proposed Tech Specs,Clarifying Proposed Limiting Conditions of Operation & Addl Surveillance Requirements for Emergency Feedwater Initiation & Control Sys 1993-12-09
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20203H7501997-08-19019 August 1997 Rev 10 to Radiological Environ Monitoring Program Manual ML20203H7351997-02-10010 February 1997 Rev 9 to CAP-0002, Off-Site Dose Calculation Manual ML20203H7231997-01-21021 January 1997 Rev 9 to Radiological Environ Monitoring Program Manual ML20059C1861993-12-22022 December 1993 Proposed Tech Specs Amend 186,rev 1 Re Nuclear Organizational Changes ML20058L4371993-12-0909 December 1993 Proposed Tech Specs Amend 187 Including Changes Making PDTS Consistent W/New 10CFR20 Regulations ML20127N3671993-01-19019 January 1993 Proposed Tech Specs Section D6.0,administrative Controls for Proposed Amend 186 ML20059E0191990-08-0303 August 1990 Rev 0 to CAP-0002, Odcm ML20059E0141990-01-31031 January 1990 Rev 0,App a to CAP-0002, Odcm ML20059E0241989-11-22022 November 1989 Rev 3 to Environ Monitoring & Emergency Preparedness ML20246A4081989-08-16016 August 1989 Rev 5 to Inservice Testing Program Plan ML20245L7281989-07-18018 July 1989 Rev 5 to Administrative Procedure RSAP-0101, Nuclear Organization Responsibilities & Authorities ML20246F1241989-07-0505 July 1989 Proposed Tech Specs,Deleting App B in Entirety ML20246A5221989-06-30030 June 1989 Closure Plan ML20245H5781989-06-22022 June 1989 Proposed Tech Specs for Amend 109 to License DPR-54 ML20246E8551989-04-30030 April 1989 Analysis of Capsule RS1-F Smud Reactor Vessel Matl Surveillance Program ML20245L0461989-04-27027 April 1989 Proposed Tech Specs for Proposed Suppl 1 to Amend 134 Re Application for Amend to License DPR-54,clarifying Unacceptability of Analysis Allowing Imperfections Greater than 40% of Nominal Tube or Sleeve Wall Thickness ML20235Y6071989-03-0606 March 1989 Proposed Tech Spec Page 4-17,including one-time Extension for Certain Surveillances Required to Be Performed by 890329 ML20245G1941989-02-28028 February 1989 Procurement Engineering Assessment Plan Final Rept ML20245H8911989-02-28028 February 1989 Revised Proposed Tech Specs,Including Pages 3-30a,3-30b, 3-40a,3-45,3-46,4-18a & 4-75 Re Addition of Operating Requirements Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations ML20195F7701988-11-18018 November 1988 Proposed Tech Spec Section 3.4, Steam & Power Conversion Sys ML20206F2881988-11-15015 November 1988 Proposed Tech Specs 4.6.4.f (Page 4-34i) Re Surveillance of Equipment Required to Verify Vital 120 Volt Ac Bus Operability ML20205R8681988-11-0404 November 1988 Proposed Tech Specs Re Local Leakage Rate Tests & Reactor Bldg Containment Integrity ML20205M8971988-10-28028 October 1988 Proposed Tech Specs Re Nuclear Svc Battery Operability & Surveillance Requirements ML20205L2661988-10-25025 October 1988 Proposed Tech Spec Table 3.14-3, Carbon Dioxide Suppression Zones ML20155G2201988-10-0707 October 1988 Proposed Tech Specs Clarifying Operational Mode Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Sys Train ML20155B8481988-09-30030 September 1988 Proposed Tech Specs Re Reactor Protection Sys Trip Setting Limits,Rcs High Point Vents,Leakage & Leak Detection,Reactor Coolant Inventory & Auxiliary Electric Sys ML20155B4591988-09-30030 September 1988 Proposed Tech Spec Sections 1,3,4,5 & 6,reflecting Numerous Editorial Corrections & Administrative Changes ML20206A8151988-09-28028 September 1988 Rev 0 to, Effluents & Water Mgt Project Action Plan ML20154J5611988-09-19019 September 1988 Proposed Tech Specs,Changing Local Leak Rate Test Requirements for Containment Penetrations ML20154D7591988-09-0808 September 1988 Proposed Tech Specs Re Administrative Controls,Onsite & Offsite Organizations & Facility Staff ML20153E6481988-08-31031 August 1988 Proposed Tech Specs on Limiting Condition for Operation Re Containment Isolation Valves ML20151K1041988-07-28028 July 1988 Rev 0 to Special Test Procedure STP.668, EFIC High/Medium Decay Heat Test ML20207C0831988-07-27027 July 1988 Revised Proposed Tech Specs,Consisting of Rev 1 to Proposed Amend 102,deleting App B ML20151H6131988-07-15015 July 1988 Rev 0 to Matl Control Dept Action Plan for Rancho Seco Nuclear Generating Station ML20196A2281988-06-21021 June 1988 Proposed Tech Specs Providing Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation & Modifying Existing Purge Sys Operation Requirement ML20155K0971988-06-14014 June 1988 Proposed Tech Specs Making Minor Corrections to Table 3.5.5-1, Accident Monitoring Instrumentation,Items 5 & 14 & Table 4.1-1 Items 65 & 92 & Adding Second Note to Table 4.1-1,Item 80 ML20195J4921988-06-10010 June 1988 Proposed Tech Spec Pages 4-69 Through 4-85a,modifying Radiological Effluent Tech Specs to Reduce Count Time Required for prebatch-release Sample Analysis ML20151R0641988-04-15015 April 1988 Rev 0 to STP.1154, Remote Shutdown Panel Test ML20151X3211988-04-0606 April 1988 Rev 1 to Procedure Development Project Action Plan for Temporary & Interim Procedure Change Incorporation as Procedure Rev ML20151V5871988-04-0202 April 1988 Rev 1 to Sys Engineering Action Plan SYSTEM-012, CRD Breaker Action Plan ML20151X2871988-03-31031 March 1988 Rev 0 to Sys Engineering Action Plan SYSTEM-009, Letdown Cooler Thermal & Hydraulic Shock Prevention ML20150D1861988-03-17017 March 1988 Proposed Tech Specs,Correcting Typos & Making Further Editorial Changes to Proposed Amend 139,dtd 860129 ML20196G5131988-03-0101 March 1988 Proposed Tech Specs,Revising Tech Spec 4.1-1,Item 44.c & Tech Spec 4.10.1.E.2 Re Total Quantity of Gaseous Chlorine in Restricted Area ML20147F0771988-02-25025 February 1988 Revised Proposed Tech Spec Table 4.1-1 & Tech Spec 4.10.1.E.2,requiring Performance of Surveillances Only When Gaseous Chlorine Onsite ML20147B1761988-02-15015 February 1988 Rev 0 to RECM-6878, Radiological Effluent Control Manual ML20148D9931988-02-12012 February 1988 Post-Trip Transient Investigation,Assessment & Reporting ML20149K8621988-02-12012 February 1988 Proposed Tech Spec 6.5.1.6.d,identifying Items Not Requiring Plant Review Committee Review ML20196D9091988-02-11011 February 1988 Proposed Tech Specs,Adding Term Dewatering to Process Control Program ML20149G1781988-02-0808 February 1988 Proposed Page 3-19 to Tech Spec 3.3, Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Sys ML20196B8071988-02-0101 February 1988 Proposed Tech Spec Figure 6.2-2, Nuclear Organization Chart 1997-08-19
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 165- Bases (continued)
The interim Onsite Storage Building has a ventilation system which provides protection against radioactive airborne release. Operation of the ventilation system produces a negative pressure in the building. During operation, the ventilation exhaust flow is continuously monitored. Upon an alarm, the exhaust duct closes and the supply and exhaust fans stop, minimizing any chance of an airborne release. The monitor setpoints are set statistically high enough above background to prevent spurious alarms, yet stop potential radioactive releases when detected. Although no planned airborne radioactive releases are anticipated from this pathway, the ventilation exhaust monitor is listed as a Technical Specification instrument.
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Proposed Amendment No. 165 3-63a f
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.16-1 (Continued)
RADI0 ACTIVE GASES EFFLUENT HONITORING INSTRUMENTATION Minimum Number of Channels Instrument Ooerable Action
- 3. Radwaste Service Area Vent * (continued)
- c. Particulate Sampler 1 Hith the collection device inoperable, effluent releases via this pathway may e Stinue provided continL.o; samples are taken and these 'emples are analyzed in accordance with Table 4.22-1 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- d. System Effluent Flow 1 Hith the flow rate device Rate Device inoperable, effluent releases may continue provided the flow rate used is the maximum design flow rate.
- e. Sampler Flow Rate 1 Hith 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
165- 4. IOS Building Vent
- a. Particulate Monitor 1 Hith the monitoring device inoperable, ventilation flow shall be halted or continuous particulate samples taken in accordance with Table 4.22-1E for
- particulate samples.
- The Radwaste Service Area Vent Monitoring System is not yet functional. I This specification for this system will become effective when it is declared OPERABLE.
Proposed Amendment No. 165 3-69
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.20 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Surveillance Reauirements The maximum setpoints shall be determined in accordance with procedures as described in the OOCH and shall be recorded on release permits.
Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the INSTRUMENT CHANNEL CHECK, SOURCE CHECK, INSTRUMENT CHANNEL CALIBRATION, AND CHANNEL TEST at the frequencies shown in Table 4.20-1.
Records shall be maintained in the Process Standards of all radioactive gaseous effluent monitoring instrumentation alarm / trip setpoints. Maximum setpoints and setpoint calculations shall be available for review to ensure that the limits of Specification 3.18 are met.
BAlfti The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with the methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. 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 Reactor Building Purge Vent, Auxiliary Building Stack and Radwaste Service Area Vent are constant as they use single speed fans.
The Reactor Building Purge Vent has two different flow rates, winter and summer, however administrative controls assure using the correct flow rate where applicable. The actual flow rate of the ventilation systems are periodically determined by surveillance procedures. The flow rate measurement devices are used only as flow indicating devices and not for actual measurement of flow rate. Also, as these 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. 4 165~ The ventilation exhaust flow rate in the Interim Onsite Storage Building is
- constant, as the exhaust fan is a single-speed fan. During operation, the ventilation exhaust flow is continuously monitored for particulate through an isokinetic probe. The monitor setpoints are set statistically high enough above background to prevent spurious alarms, yet stop potential
- radioactive releases when detected.
l Proposed Amendment No. 165 4-65
O O
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS.
Surveillance Standards Table 4.20-1 (Continued)
Instrument Instrument Channel Source Channel Channel Instrument Check Check Calibration Test
- 3. Radwaste Serv.e Area *
- a. Noble Gas Activity Monitor D(I) H Q(2) Q(4)
- b. Iodine Sampler H NA NA NA
- c. Particulate Sampler H NA NA NA
- d. System Effluent Flow Rate Device H NA BY A
- e. Sampler Monitor Flow Rate Measurement Device H NA BY A 165- 4. IOS Building
- a. Particulate
- Monitor S NA R H The Radwaste Service Area Monitoring System is not yet functional. The specification for this system will become effective when it is declared OPERABLE.
Table Notation (1) During releases via this pathway, a check shall be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(2) The Instrument Channel Calibration for radioactivity measurement instrumentation shall be performed using one or more reference standards.
(3) The Channel Test shall also demonstrate that automatic termination of this pathway and control room alarm annunciation occurs if any of the following conditions exist:
- a. Instrument indicates measured levels above the alarm / trip setpoint.
- b. Circuit failure,
- c. Instrument indicates a downscale failure,
- d. Instrument controls not set in operate mode.
Proposed Amendment No. 165 4-67 <
0 NO SIGNIFICANT HAZARDS CONSIDERATION ATTACHMENT II Proposed Amendment No.-165 PAGE 1 OF 3 DESCRIPTION:
Proposed Amendment No. 165 adds a radiation monitor in the Inter-im Onsite Storage Building (IOSB) ventilation system to Technical Specification Table 3.16-1, Radioactive Gases Effluent Monitoring Instrumentation, and associated Table 4.20-1, Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements.
Additionally, a discussion is added to the Bases of Technical Specification 3.16 and 4.20.
REASON FOR CHANGES:
Purpose The Interim Onsite Storage Building (IOSB) is a facility which is constructed to house at least two and one-half years of waste consisting of solidified liquids, compactable trash, and resins.
In addition to storage use, the following activities will be per-formed in the IOSB, including:
- 1. Sorting and segregation of dry active waste,
- 2. Dry waste compaction (box compactor),
- 3. Consolidation of uncompactable waste prior to shipment,
- 4. Laundry inspection, survey, sorting, and storage,
- 5. Respiratory cleaning unit operation,
- 6. Decontamination of equipment and volume reduction of fixed contaminated equipment or gear,
- 7. Encapsulation of solid radioactive material.
The use of the IOSB for sorting and compacting dry waste and the encapsulation of solid radioactive materials produces the poten-tial for airborne release. The IOSB ventilation monitoring sys-tem requires an addition to Technical Specifications to ensure adequate monitoring of building ventilation exhaust.
EVALUATION AND BASIS FOR SAFETY ANALYSIS:
Systems, Subsystems, Components Affected This Technical Specification addition affects the IOSB ventila-tion monitoring system.
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NO SIGNIFICANT HAZARDS CONSIDERATION ATTACHMENT II Proposed Amendment No. 165 PAGE 2 OF 3 Safety Functions of Affected Systems /ComDonents 4
The IOSB has a. building ventilation system which provides protec- l tion against radioactive airborne releases. The IOSB ventilation system operates as follows: Filtered outside air is supplied by two supply fans (AH-2-36-1 and 2) rated at approximately 4400 and 2050 cfm, respectively. Total exhaust flow is performed by one exhaust fan (AH-2-36-3) rated at 8050 cfa, thus maintaining ap-proximately 0.1" wg negative pressure.in the IOSB.
This exhaust flow is monitored continuously with an isokinetic probe. In the event of an alarm, exhaust duct HV-56004 closes, exhaust fan AH-2-36-3 stops, supply fans AH-2-36-1 and 2 stop, and an alarm sounds (locally, in the facility control room, and in the main control room). These automatic actions minimize the chance of an airborne release.
Effects on Safety Functions / Analysis of Effects on Safety Functions The IOSB ventilation system provides protection against radioac- ,
tive airborne releases. Operation of the system produces a nega-4 tivs pressure in the building. During operation, the ventilation exhaust flow is continuously monitored. Upon an alarm, the ex-haust duct closes and the supply and exhaust fans stop, minimi-zing any chance of an airborne release.
The monitor's setpoints are set statistically high enough above '
background to prevent spurious alarms, yet stop potential radio-active releases when detected. No planned airborne radioactive releases are anticipated from this pathway.
, Technical Specification Table 3.16-1 specifies "With the monitor- 4 ing device inoperable, ventilation flow shall be halted or con-tinuous particulate samples taken..." This Action ensures that no unmonitored releases occur through this potential release pathway. Table 4.20-1 dictates a weekly surveillance consisting of an Instrument Channel Check. This is consistent with the re-quirements for other particulate samplers listed in the Table.
1 Summary Proposed Amendment No. 165 adds a radiation monitor in the Inter-im Onsite Storage Building (IOSB) ventilation system to Technical Specification Table 3.16-1, Radioactive Gases Effluent Monitoring Instrumentation, and associated Table 4.20-1, Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements.
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0 NO SIGNIFICANT HAZARDS CONSIDERATION ATTACHMENT II Proposed Amendment No. 165 PAGE 3 OF 3 The use of the IOSB for sorting and compacting dry waste and the encapsulation of solid radioactive materials produces the poten-tial for airborne release. The IOSB ventilation monitoring sys-tem requires an addition to Technical Specifications to ensure adequate monitoring of building ventilation exhaust.
This Technical Specification addition affects the IOSB ventila-tion monitoring system.
Proposed Amendment No. 165 will not involve a significant in-crease in the probability or consequences of an accident pre-viously evaluated because it adds a particulate monitor to Tech-nical Specifications to ensure that no unmonitored releases occur from the Interim Onsite Storage Building. The associated Action statement is consistent with other Particulate Sampler Action statements in Table 3.16-1.
The Proposed Amendment does not create the possibility of a new or different kind of accident from any accident previously eval-uated because the Action statement to be added to Table 3.16-1 is consistent with other Action statements in the Table.
It does not involve a significant reduction in a margin of safety because this Proposed Amendment ensures that no unmonitored re-leases occur from this potential release pathway.
Therefors, Rancho Seco has determined that no significant hazards are involved in the operation of the facility in accordance with Proposed Amendment No. 165.
,