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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217B4471999-10-0707 October 1999 Safety Evaluation Supporting Amends 159 & 150 to Licenses NPF-10 & NPF-15,respectively ML20211R0571999-09-0909 September 1999 Safety Evaluation Supporting Amends 158 & 149 to Licenses NPF-10 & NPF-15,respectively ML20212A2391999-09-0707 September 1999 Safety Evaluation Supporting Amends 157 & 148 to Licenses NPF-10 & NPF-15,respectively ML20211N0511999-09-0303 September 1999 SER Approving Exemption from Certain Requirements of 10CFR50.44 & 10CFR50 App A,General Design Criterion 41 to Remove Requirements from Hydrogen Control Systems from SONGS Units 2 & 3 Design Basis ML20211H8621999-08-23023 August 1999 Safety Evaluation Accepting Licensee Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20211E9441999-08-19019 August 1999 Safety Evaluation Supporting Amends 156 & 147 to Licenses NPF-10 & NPF-15,respectively ML20211F2211999-08-19019 August 1999 Safety Evaluation Supporting Amends 155 & 146 to Licenses NPF-10 & NPF-15,respectively ML20209G8991999-07-12012 July 1999 Safety Evaluation Supporting Amends 154 & 145 to Licenses NPF-10 & NPF-15,respectively ML20207A0211999-05-13013 May 1999 Safety Evaluation Supporting Amends 153 & 144 to Licenses NPF-10 & NPF-15,respectively ML20206G6561999-04-27027 April 1999 SER Accepting Proposed Exemption from 10CFR50.71(e)(4) for SONGS Units 2 & 3 ML20206D1461999-04-26026 April 1999 Safety Evaluation Supporting Amend 152 to License NPF-10 ML20205Q6221999-04-19019 April 1999 Safety Evaluation Authorizing Proposed Alternative to Use Wire Penetrameters for ISI Radiography in Place of ASME Code Requirement ML20205R0371999-04-16016 April 1999 SER Approving Proposed Deviation from Approved Fire Protection Program Incorporating Technical Requirements of 10CFR50,App R,Section III.0 That Applies to RCP Oil Fill Piping ML20205N2691999-04-0909 April 1999 Safety Evaluation Supporting Amends 151 & 143 to Licenses NPF-10 & NPF-15,respectively ML20203J1981999-02-12012 February 1999 Safety Evaluation Supporting Amends 149 & 141 to Licenses NPF-10 & NPF-15,respectively ML20203J1131999-02-12012 February 1999 Safety Evaluation Supporting Amends 150 & 142 to Licenses NPF-10 & NPF-15,respectively NUREG-0800, Safety Evaluation Supporting Amends 148 & 140 to Licenses NPF-10 & NPF-15,respectively1999-02-0909 February 1999 Safety Evaluation Supporting Amends 148 & 140 to Licenses NPF-10 & NPF-15,respectively ML20206N6281998-12-16016 December 1998 Safety Evaluation Supporting Amends 145 & 137 to Licenses NPF-10 & NPF-15,respectively ML20196A6161998-11-23023 November 1998 Safety Evaluation Supporting Amend 136 to License NPF-15 ML20154B7211998-10-0101 October 1998 Safety Evaluation Approving Licensee Request to Implement Alternatives Contained in Code Case N-546 for Current Interval at Songs,Units 2 & 3 Until Code Case Approved by Ref in Reg Guide 1.147 ML20197D0161998-09-0909 September 1998 Safety Evaluation Supporting Amends 141 & 133 to Licenses NPF-10 & NPF-15,respectively ML20239A1431998-08-26026 August 1998 Safety Evaluation Supporting Amends 140 & 132 to Licenses NPF-10 & NPF-15,respectively ML20249C7361998-06-19019 June 1998 Safety Evaluation Supporting Amends 139 & 131 to Licenses NPF-10 & NPF-15,respectively ML20203E7301998-02-17017 February 1998 SER Accepting 980105 Request to Use Mechanical Nozzle Seal Assembly as Alternate Repair Method,Per 10CFR50.55a(a)(3)(1) for Plant,Units 2 & 3 ML20202J1111997-12-0303 December 1997 Safety Evaluation Supporting Amends 137 & 129 to Licenses NPF-10 & NPF-15,respectively ML20210T0631997-08-29029 August 1997 Safety Evaluation Approving Application Re Proposed Restructuring of Enova Corp,Parent Company of San Diego Gas & Electric Co by Establishment of Holding Company W/Pacific Enterprises ML20134C9261996-10-0303 October 1996 Safety Evaluation Supporting Amends 131 & 120 to Licenses NPF-10 & NPF-15 ML20128L7231996-10-0303 October 1996 Safety Evaluation Supporting Amend 158 to License DPR-13 ML20094J5991995-11-0202 November 1995 Safety Evaluation Supporting Amends 126 & 115 to Licenses NPF-10 & NPF-15,respectively ML20091R3581995-08-23023 August 1995 Safety Evaluation Supporting Amends 124 & 113 to Licenses NPF-10 & NPF-15,respectively ML20086U0231995-07-26026 July 1995 Safety Evaluation Supporting Amends 123 & 112 to Licenses NPF-10 & NPF-15,respectively ML20086M2951995-07-14014 July 1995 Safety Evaluation Supporting Amends 120 & 109 to Licenses NPF-10 & NPF-15,respectively ML20084F6591995-05-17017 May 1995 Safety Evaluation Supporting Amends 119 & 108 to Licenses NPF-10 & NPF-15,respectively ML20081J7151995-03-17017 March 1995 Safety Evaluation Supporting Amends 118 & 107 to Licenses NPF-10 & NPF-15,respectively ML20080P3171995-02-28028 February 1995 Safety Evaluation Supporting Amends 117 & 106 to Licenses NPF-10 & NPF-15,respectively ML20078Q4101995-02-13013 February 1995 Safety Evaluation Supporting Amends 115 & 104 to Licenses NPF-10 & NPF-15,respectively ML20076M3671994-10-27027 October 1994 Safety Evaluation Supporting Amends 113 & 102 to Licenses NPF-10 & NPF-15,respectively ML20063F1671994-02-0404 February 1994 Safety Evaluation Supporting Amends 110 & 99 to Licenses NPF-10 & NPF-15,respectively ML20058B1241993-11-19019 November 1993 Safety Evaluation Accepting Proposal to Leak Rate Test SI Tank Outlet Check Valves by Using Leak Test Method Described in OM-10,Paragraph 4.2.2.3(c) ML20057G3071993-10-18018 October 1993 Safety Evaluation Granting Licensee 930616 Relief Request B-12 Re Hydrostatic Testing of Certain Welds in 4 Inch Line from Main Steam Header to Auxiliary Feedwater Pump ML20056E2441993-08-0303 August 1993 Safety Evaluation Supporting Amends 108 & 97 to Licenses NPF-10 & NPF-15,respectively ML20056E0851993-08-0202 August 1993 Safety Evaluation Accepting Licensee 890308,910301 & 911217 Responses to NRC Bulletin 88-011 Re C-E Owners Group Program for Evaluation of Pressurizer Surge Line Thermal Stratification ML20056D6421993-07-27027 July 1993 SER Approving Licensee 930305 Relief Requests B-10,B-11 & Code Case N-496 ML20128P8401993-02-17017 February 1993 Safety Evaluation Supporting Amend 153 to License DPR-13 ML20125A4341992-12-0303 December 1992 Safety Evaluation Accepting Alternative Exam Methods Per 10CFR50.55a(a)(3)(i) & Addl Info Re Auxiliary Feedwater Sys Lube Oil Cooling,Per ISI Relief Requests B-7,B-8 & B-9 & Code Case N-481 ML20085K3981991-10-0909 October 1991 Safety Evaluation Supporting Amends 100 & 89 to Licenses NPF-10 & NPF-15,respectively ML20081K1821991-06-17017 June 1991 Safety Evaluation Supporting Amends 95 & 85 to Licenses NPF-10 & NPF-15,respectively ML20081F2171991-06-0303 June 1991 Safety Evaluation Supporting Amends 94 & 84 to Licenses NPF-10 & NPF-15,respectively ML20247N3731989-08-30030 August 1989 Safety Evaluation Supporting Amends 76 & 64 to Licenses NPF-10 & NPF-15 ML20246N4321989-08-25025 August 1989 Safety Evaluation Supporting Corrected Amends 74 & 62 to Licenses NPF-10 & NPF-15,respectively 1999-09-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217B4471999-10-0707 October 1999 Safety Evaluation Supporting Amends 159 & 150 to Licenses NPF-10 & NPF-15,respectively ML20217E3381999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Songs,Units 2 & 3 05000361/LER-1999-005-01, :on 990831,loss of Physical Separation in Control Room,Occurred.Caused by Personnel Error.Creacus Train a Was Returned to Standby on 9908311999-09-23023 September 1999
- on 990831,loss of Physical Separation in Control Room,Occurred.Caused by Personnel Error.Creacus Train a Was Returned to Standby on 990831
ML20212A1471999-09-13013 September 1999 Special Rept:On 990904,condenser Monitor Was Declared Inoperable.Difficulties Encountered During Component Replacement Precluded SCE from Restoring Monitor to Service within 72 H.Alternate Method of Monitoring Was Established ML20211R0571999-09-0909 September 1999 Safety Evaluation Supporting Amends 158 & 149 to Licenses NPF-10 & NPF-15,respectively ML20212A2391999-09-0707 September 1999 Safety Evaluation Supporting Amends 157 & 148 to Licenses NPF-10 & NPF-15,respectively ML20211N0511999-09-0303 September 1999 SER Approving Exemption from Certain Requirements of 10CFR50.44 & 10CFR50 App A,General Design Criterion 41 to Remove Requirements from Hydrogen Control Systems from SONGS Units 2 & 3 Design Basis 05000206/LER-1999-001-02, :on 990808,unattended Security Weapon Was Discovered Inside Pa.Caused by Posted Security Officer Falling Asleep.Officer Was Relieved of Duties,Pa Access Was Removed & Officer Was Placed on Investigatory Suspension1999-08-31031 August 1999
- on 990808,unattended Security Weapon Was Discovered Inside Pa.Caused by Posted Security Officer Falling Asleep.Officer Was Relieved of Duties,Pa Access Was Removed & Officer Was Placed on Investigatory Suspension
ML20211Q8201999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Songs,Units 2 & 3. with ML20211H8621999-08-23023 August 1999 Safety Evaluation Accepting Licensee Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20211E9441999-08-19019 August 1999 Safety Evaluation Supporting Amends 156 & 147 to Licenses NPF-10 & NPF-15,respectively ML20211F2211999-08-19019 August 1999 Safety Evaluation Supporting Amends 155 & 146 to Licenses NPF-10 & NPF-15,respectively ML20210P4791999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 3 ML20210P4731999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 2 05000361/LER-1999-004-01, :on 990708,automatic Tgis Actuation Occurred. Caused by Small Leak in Suction Side of Tgis Train a Sample Pump.Small Leak Repaired1999-08-0606 August 1999
- on 990708,automatic Tgis Actuation Occurred. Caused by Small Leak in Suction Side of Tgis Train a Sample Pump.Small Leak Repaired
ML20210Q6521999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Songs,Units 2 & 3 ML20210L2771999-07-30030 July 1999 SONGS Unit 3 ISI Summary Rept 2nd Interval,2nd Period Cycle 10 Refueling Outage U3C10 Site Technical Services 05000362/LER-1999-005, :on 990630,discovered LTOP Sys Relief Valve Setpoint Was Higher than Allowed by Ts.Cause Indeterminate. Subject Valve Will Be Disassembled & Inspected to Determine Caused of High Setpoint.With1999-07-28028 July 1999
- on 990630,discovered LTOP Sys Relief Valve Setpoint Was Higher than Allowed by Ts.Cause Indeterminate. Subject Valve Will Be Disassembled & Inspected to Determine Caused of High Setpoint.With
05000362/LER-1999-006, :on 990623,EDG 3G003 Was Inadvertently Made Inoperable.Caused by Operators Aligning EDG to Inoperable Automatic Voltage Regulator.Licensee Will Revise Process of Locating Tags.With1999-07-26026 July 1999
- on 990623,EDG 3G003 Was Inadvertently Made Inoperable.Caused by Operators Aligning EDG to Inoperable Automatic Voltage Regulator.Licensee Will Revise Process of Locating Tags.With
ML20209G8991999-07-12012 July 1999 Safety Evaluation Supporting Amends 154 & 145 to Licenses NPF-10 & NPF-15,respectively ML20209C9281999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Songs,Units 2 & 3. with 05000362/LER-1999-003-01, :on 990513,reactor Manually Tripped Due to Loss of Main Feedwater.Caused by Open Relay Contact in Output of Feedwater Regulation Control Sys.Faulty Relay Was Replaced1999-06-11011 June 1999
- on 990513,reactor Manually Tripped Due to Loss of Main Feedwater.Caused by Open Relay Contact in Output of Feedwater Regulation Control Sys.Faulty Relay Was Replaced
05000362/LER-1999-004, :on 990515,reactor Manually Tripped Due to Feedwater Control Valve Opening.Caused by Faulty Valve Positioner.Faulty Positioner Was Replaced1999-06-11011 June 1999
- on 990515,reactor Manually Tripped Due to Feedwater Control Valve Opening.Caused by Faulty Valve Positioner.Faulty Positioner Was Replaced
ML20195D3061999-06-0202 June 1999 Safety Evaluation of TR SCE-9801-P, Reload Analysis Methodology for San Onofre Nuclear Generating Station,Units 2 & 3. Rept Acceptable ML20195H5491999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Songs,Units 2 & 3 05000362/LER-1999-002-01, :on 990328,RWST Outlet Isolation Valve Failed to Open After Being Closed for Testing.Caused by Degradation of Valve.Rwst Oulet Valve Was Repaired.With1999-05-20020 May 1999
- on 990328,RWST Outlet Isolation Valve Failed to Open After Being Closed for Testing.Caused by Degradation of Valve.Rwst Oulet Valve Was Repaired.With
ML20207A0211999-05-13013 May 1999 Safety Evaluation Supporting Amends 153 & 144 to Licenses NPF-10 & NPF-15,respectively ML20196L3221999-05-11011 May 1999 SONGS Unit 2 ISI Summary Rept 2nd Interval,2nd Period Cycle-10 Refueling Outage ML20206H2611999-05-0505 May 1999 Part 21 Rept Re Defect Found in Potter & Brumfield Relays. Sixteen Relays Supplied in Lot 913501 by Vendor as Commercial Grade Items.Caused by Insufficient Contact Pad Welding.Relays Replaced with New Relays ML20206S7281999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Songs,Units 2 & 3 ML20206G6561999-04-27027 April 1999 SER Accepting Proposed Exemption from 10CFR50.71(e)(4) for SONGS Units 2 & 3 ML20206D1461999-04-26026 April 1999 Safety Evaluation Supporting Amend 152 to License NPF-10 ML20205Q6221999-04-19019 April 1999 Safety Evaluation Authorizing Proposed Alternative to Use Wire Penetrameters for ISI Radiography in Place of ASME Code Requirement ML20205R0371999-04-16016 April 1999 SER Approving Proposed Deviation from Approved Fire Protection Program Incorporating Technical Requirements of 10CFR50,App R,Section III.0 That Applies to RCP Oil Fill Piping ML20205N2691999-04-0909 April 1999 Safety Evaluation Supporting Amends 151 & 143 to Licenses NPF-10 & NPF-15,respectively ML20205G2611999-04-0101 April 1999 Special Rept:On 990328,3RT-7865 Was Removed from Service. Monitor Is Scheduled to Be Returned to Service Prior to Mode 4 Entry (Early May 1999) Which Will Exceed 72 H Allowed by LCS 3.3.102.Alternate Method of Monitoring Will Be Used ML20205Q0981999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Songs,Units 2 & 3 05000362/LER-1999-001-01, :on 990211,TS 3.0.3 Entered Due to Both Chilled Water Trains Being Inoperable.Warm Main Condenser Discharged Water Diverted in Salt Water Cooling (Swc)(Bs) Intake.With1999-03-12012 March 1999
- on 990211,TS 3.0.3 Entered Due to Both Chilled Water Trains Being Inoperable.Warm Main Condenser Discharged Water Diverted in Salt Water Cooling (Swc)(Bs) Intake.With
05000361/LER-1999-002, :on 990208,pressurizer Safety Valves Were Above TS Limit.Caused by Setpoint Drift.Sce Submitted License Amend Application on 980904 Requesting Tolerence Be Changed to +3/-2%.With1999-03-10010 March 1999
- on 990208,pressurizer Safety Valves Were Above TS Limit.Caused by Setpoint Drift.Sce Submitted License Amend Application on 980904 Requesting Tolerence Be Changed to +3/-2%.With
05000361/LER-1999-001, :on 990201,automatic Start of EDG Was Noted. Caused by Workers Closing Breaker 2A0418 by Discharging Closing Springs.Operators Restored SDC in Approx 26 Minutes. with1999-03-0303 March 1999
- on 990201,automatic Start of EDG Was Noted. Caused by Workers Closing Breaker 2A0418 by Discharging Closing Springs.Operators Restored SDC in Approx 26 Minutes. with
ML20204F8101999-02-28028 February 1999 Monthly Operating Repts for Songs,Units 2 & 3.With ML20203J1131999-02-12012 February 1999 Safety Evaluation Supporting Amends 150 & 142 to Licenses NPF-10 & NPF-15,respectively ML20203J1981999-02-12012 February 1999 Safety Evaluation Supporting Amends 149 & 141 to Licenses NPF-10 & NPF-15,respectively NUREG-0800, Safety Evaluation Supporting Amends 148 & 140 to Licenses NPF-10 & NPF-15,respectively1999-02-0909 February 1999 Safety Evaluation Supporting Amends 148 & 140 to Licenses NPF-10 & NPF-15,respectively ML20202F7041999-01-21021 January 1999 Special Rept:On 990106,SCE Began to Modify 2RT-7865.2RT-7865 to Allow Monitor to Provide Input to New Radiation Monitoring Data Acquisition Sys.Monitor Found to Exceeds 72 H Allowed Bt LCS 3.3.102.Alternate Monitoring Established ML20206H2101998-12-31031 December 1998 SCE 1998 Annual Rept ML20199F0771998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Songs,Units 2 & 3 ML20206N6281998-12-16016 December 1998 Safety Evaluation Supporting Amends 145 & 137 to Licenses NPF-10 & NPF-15,respectively ML20198A6731998-12-11011 December 1998 Special Rept:On 981124,meteorological Sys Wind Direction Sensor Was Observed to Be Inoperable.Caused by Loss of Communication from Tower to Cr.Sensor Was Replaced & Sys Was Declared Operable on 981204 ML20196D8901998-11-30030 November 1998 Non-proprietary Reload Analysis Methodology for Songs,Units 2 & 3 1999-09-09
[Table view] |
Text
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UNITED STATES g
NUCLEAR REGUl ATORY COMMISSION If WASHINGTON, D.C. 2064 6 0001 i
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0. 126 TO FACILITY OPERATING LICENSE NO. NPF-10 AND AMENDMENT NO. 115 TO FACILITY OPERATING LICENSE NO. NPF-15 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA SAN ON0FRE NUCLEAR GENERATING STATION. UNITS 2 AND 3 DOCKET NOS. 50-361 AND 50-362
1.0 INTRODUCTION
By letter dated August 1, 1995, and as supplemented by letter dated October 18, 1995, Southern California Edison Company, et al. (SCE or the licensee) submitted a request for changes to the Technical Specifications (TS) for San Onofre Nuclear Generating Station, Unit Nos. 2 and 3.
The propose changes would revise TS 3/4.3.2, " Engineered Safety Features Actuation System Instrumentation," Table 3.3-3.
Table 3.3-3 includes the requirements for the minimum number of toxic gas isolation system (TGIS) trains operable. This request is a one-time-only change to extend the allowed TGIS outage times during replacement of TGIS instrumentation.
The proposed changes would add a note to TS Table 3.3-3 for each unit. This note states that, on a one-time basis during the replacement of the existing TGIS instrumentation, compensatory actions would be taken in lieu of the standard actions required by TS Table 3.3-3.
The October 18, 1995, supplemental letter provided additional clarifying information and did not change the initial no significant hazards consideration determination which was published in the Federal Reaister on September 13, 1995 (60 FR 47625).
2.0 BACKGROUND
The General Design Criteria (GDC) as defined in Appendix A to 10 CFR Part 50 serve to establish the principal requirements needed for the design, fabrication, construction, testing, and performance of a facility's safety related structures, systems, and components that provide reasonable assurance that a facility can be operated safely. GDC 4, " Environmental and missile 9511150378 951102 DR ADOCK 05000361 PDR
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- 1 design bases," requires, in part, that those components important to safety be appropriately protected from events and conditions outside the nuclear plant.
GDC 19, " Control room," requires that a control room be provided from which i
actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident. conditions.
The relevant acceptance criteria for the control room habitability are located in Regulatory Guide 1.78, " Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release," and Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release."
Further guid&nce is provided by Chapter 6.4, " Control Roon Habitability System," of the Standard Review Plan (NUREG-0800).
SONGS Units 2 and 3 have a shared control room, with a common control room i
emergency air cleanup system (CREACUS).
The CREACUS contains two redundant i
emergency filtration trains, each equipped with an emergency ventilation supply unit and an air conditioning unit. Two independent TGIS channels 3
(Channels A and B), located at the outside air intake for the normal air conditioning unit, protect the control room occupants from a toxic release at or in the vicinity of the plant. TGIS analyzers monitor for high 1
concentrations of butane, propane, ammonia, and chlorine. When the technical specification (TS) limit for a toxic chemical release is reached, the toxic gas isolation system (TGIS) automatically isolates the control room and initiates CREACUS operation in the recirculation mode.
Both TGIS channels are required by TS 3/4.3.2 to be operable in all modes of operation; Action 14 of TS Table 3.3-3 states that should one channel be inoperable it must be l
restored within 7 days or the CREACUS must be initiated and maintained in the isolation mode within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
If no TGIS channels are operable, Action 15 of TS Table 3.3-3 states that CREACUS must be initiated and
{
maintained in the isolation mode within I hour.
i l
The licensee states that the only TGIS ammonia and butane analyzers have been rendered obsolete due to advances in the field of analytical instrumentation.
The increasing unavailability of replacement parts because of the manufacturer's decision to discontinue the manufacturing of the analyzers is another factor in the licensee's decision to replace the analyzers. The relative age of the TGIS is also a growing concern since the ammonia analyzers j
need more frequent maintenance and have experienced several spurious trips.
j The proposed addition of Note 1 to TS Table 3.3-3 will, on a one-time basis for the duration of the TGIS instrumentation replacement interval, replace I
Actions 14 and 15 with the compensatory measures outlined in the licensee's October 18, 1995, letter to the NRC.
]
3.0 EVALUATION The TGIS was installed in the SONGS control room because the location, frequency and size of toxic substances near or on the site were such that manual isolation of the control room could not be credited quickly enough to ensure the safety of control room personnel.
In order to provide for an
.. equivalent level of safety during the TGIS instrumentation replacement period, tha licensee has,'in its letter dated August 1, 1995, as supplemented by letter dated October 18, 1995, committed to the following:
1.
Replacement activities will be performed on one channel of TGIS at a time. After the first channel of instrumentation is replaced, both channels of TGIS will be operable for a 7-to-30-day period to assure proper operation of the new instrumentation before the second channel of instrumentation is replaced.
2.
To improve reliability of TGIS operation, preventive maintenance will be performed on the operable channel cf TGIS instrumentation before the other TGIS train is replaced.
3.
The operable channel of TGIS may experience spurious actuations during periods of construction involving extensive cutting and welding work within the cabinet that contains both channels of TGIS.
During these periods the control room will be isolated with CREACUS initiated and maintained in the isolation mode and the operable TGIS channel will be in bypass.
4.
The control room is not designed to remain in an isolated mode for extended periods of time (toxic gas releases which the TGIS is designed to mitigate are expected to dissipate to acceptable levels in less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
If the licensee cannot restore one train of TGIS after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of control room isolation, the operators will return control room ventilation to normal operation.to allow the control room air quality to return to normal.
If this situation should arise, the licensee has committed to have dedicated personnel stationed in locations where observation of potential significant toxic releases can be accomplished.
These individuals will be in continuous communication with the control room to provide the operators with rapid notification of any accidents involving potential toxic releases.
This will provide the operators with sufficient time to manually isolate the control room before toxic releases can intrude into the control room and provides a level of safety that is comparable to that experienced in normal plant operation with the TGIS available.
The staff has compared the compensatory measures outlined above to the design basis and current TS requirements for the TGIS, and concludes that the I
compensatory measures committed to by the licensee provide an equivalent level l
of protection to the control room operators. During all phases of the TGIS instrument replacement activities, sufficient measures will be available to protect control room personnel from being adversely affected by events involving toxic releases.
For these reasons, the staff finds the licensee's proposed addition of Note 1 to TS Table 3.3-3, allowing a one-time exception to Actions 14 and 15, acceptable.
a 9 i
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the California State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDEPSIION i
The amendments change requirements with respect to the installation or use of i
a facility component located in the restricted area as defined in 10 CFR Part 20 and change surveillsnce requirements. The NRC staff has determined that the amendments involve no significant increase irs the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards considera-tion, and there has been no public comment on such finding (60 FR 47625).
Accordingly, the anendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c}(9).
Pursuant to 10 CFR 51.22(b) no 4
environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
E. A. Brown Date:
November 2, 1995 1
l I