Proposed Tech Specs Changing 3.3.7.1-1 to Reduce Alarm Setpoint for Condenser Air Ejector Pretreatment Noble Gas Activity Monitor from Current ValueML20073P652 |
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River Bend ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
05/14/1991 |
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From: |
GULF STATES UTILITIES CO. |
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To: |
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Shared Package |
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ML20073P651 |
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References |
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NUDOCS 9105220165 |
Download: ML20073P652 (5) |
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Category:TECHNICAL SPECIFICATIONS
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Sources - Operating ML20117K1071996-08-29029 August 1996 Proposed Tech Specs Re Reactor Vessel Matl Surveillance Program Capsule Withdrawal Schedule ML20117G7401996-08-29029 August 1996 Proposed Tech Specs 3.1 Re Reactivity Control Systems ML20116J3151996-08-0707 August 1996 Proposed Tech Specs,Submitting TS Bases Pages for Revs Performed Since 951001 Approval of TS Bases ML20116L6321996-08-0101 August 1996 Proposed Tech Specs Re Primary Containment/Drywell Hydrogen Mixing Sys & Drywell Isolation Valves ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20112E7831996-05-30030 May 1996 Proposed Tech Spec 3.8.3 Re Incorporation of 5-start Air Pressure Design Criterion for Div III DG ML20117H3271996-05-20020 May 1996 Proposed Tech Specs Re Change in Co Name from Gulf States Utils Co to Entergy Gulf States,Inc ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20094N7741995-11-22022 November 1995 Proposed Tech Specs,Clarifying Info Contained in License Amend Request (LAR) 95-21 ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20094N0091995-11-20020 November 1995 Proposed Tech Specs Eliminating Selected Response Time Testing Requirements ML20094B0001995-10-26026 October 1995 Proposed Tech Specs,Consisting of Change Request 95-10, Deleting TS 5.5.12, Biofouling Prevention & Detection, & Various Editorial Corrections ML20093L7361995-10-24024 October 1995 Proposed Tech Specs 3.6.1.1 Through 3.6.1.3 Re Containment Sys ML20087J5451995-08-17017 August 1995 Proposed Tech Specs Re Engineered Safety Sys Which Responds to Fuel Handling Accident Conditions ML20084L4541995-05-30030 May 1995 Proposed Tech Specs Re Request for Exemption from App J, Primary Reactor Containment Leakage Testing for Water- Cooled Power Reactors ML20084L5001995-05-30030 May 1995 Proposed Tech Specs,Allowing TS 3/4.6.2.2, Drywell Bypass Leakage, Tests to Be Performed at Intervals as Long as Five Yrs Based on Demonstrated Performance of Drywell Structure ML20078M1171995-02-0808 February 1995 Proposed Tech Specs Page Re Secondary Containment Automatic Isolation Dampers ML20077S4401995-01-18018 January 1995 Revised Pages of Proposed Tech Specs Re Conversion to TS Based on NUREG-1434, Improved TS Rev 0 ML20078H0881994-11-10010 November 1994 Proposed Tech Specs Reflecting Clarifications to LAR 91-11 ML20024J3341994-10-0404 October 1994 Proposed Tech Spec Removing one-hour Requirement for Completing Noble Gas & Tritium Sampling & Analysis ML20073B2381994-09-12012 September 1994 Proposed TS 3/4.2.2, APRM Setpoints ML20072U7901994-09-0808 September 1994 Proposed Tech Spec 3.10.2, Special Test Exceptions - Rod Pattern Control Sys ML20064L6481994-03-15015 March 1994 Proposed Tech Specs,Reflecting Removal of Turbine Overspeed Protection Sys Requirements ML20064C0961994-03-0303 March 1994 Proposed Tech Specs,Reflecting Relocation of Response Time Limits to Usar,Per GL 93-08 ML20063K3721994-02-22022 February 1994 Proposed Tech Specs 3.6.1.8 & 3.6.1.9 Re Penetration Valve Leakage Control Sys Air Compressor ML20063A6301994-01-14014 January 1994 Proposed Tech Specs Reflecting Removal of Component Lists ML20059G8181994-01-14014 January 1994 Proposed Tech Specs Re Surveillance Test Interval & Allowed Outage Time Extension Request 1999-07-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210H2901999-07-30030 July 1999 Proposed Tech Specs Pages,Extending Operation of RBS from Current Licensed Power Level of 2894 Mwt to Uprated Power Level 3039 Mwt ML20205P8701999-04-15015 April 1999 Proposed Tech Specs,Implementing Bwrog/Ge Enhanced Option I-A (EI-A) Reactor Stability long-term Solution ML20205L7321999-04-0808 April 1999 Proposed Tech Specs,Removing Notes That Refer to Specific Cycles,Per LAR 1998-15 Re Change to TS 2.1.1.2, Reactor Core Safety Limits ML20206R9351999-01-12012 January 1999 Proposed Tech Specs Re Refueling Equipment Interlocks Required Actions ML20199C1881999-01-0808 January 1999 Revised Page 7 to Rev 13 of RBS Security Training & Qualification Plan ML20198E8091998-12-16016 December 1998 Proposed Tech Specs Pages Re Change to TS Safety Limit 2.1.1.2,changing Two Recirculation Loop MCPR Limit from 1.13 to 1.12 & Single Recirculation Loop MCPR Limit from 1.14 to 1.13 ML20196A1401998-11-20020 November 1998 Proposed Tech Specs Adding 3.10.9, Control Rod Pattern - Cycle 8, to Support Startup from Outage Planned for Early Dec 1998 ML20154H3691998-10-0808 October 1998 Proposed Tech Specs Implementing BWROG Enhanced Option I-A Reactor Stability Long Term Solution as Documented in NEDO-32339,Rev 1, Reactor Stability Long-Term Solution, Enhanced Option I-A ML20153H0311998-09-23023 September 1998 Proposed Tech Specs Changing Specific Gravity Acceptance Criteria for Div III Battery ML20153E8111998-09-22022 September 1998 Proposed Tech Specs Deleting License Conditions Associated with Transamerica Delaval,Inc EDGs ML20217J0951998-04-21021 April 1998 Proposed Tech Specs Bases Update Package for Revs Implemented Since Last Submittal Through Refuel Outage 7 ML20216F1941998-04-0909 April 1998 Proposed Tech Specs License Condition 2.C(13) Re Partial Feedwater Heating & Final Feedwater Temp Reduction RBG-44355, Cycle 8 Startup Physics Test Summary1998-01-19019 January 1998 Cycle 8 Startup Physics Test Summary ML20202F0361997-11-26026 November 1997 Rev 0 to IST Plan for Pumps & Valves Second Ten-Yr Interval ML20216E4861997-09-0505 September 1997 Proposed Tech Specs Re APRM Setpoints,Reactivity Anomalies & RPS Instrumentation ML20210K2131997-08-15015 August 1997 Proposed Administrative Changes to TS 2.1.1.2 W/Note to Indicate Operating Cycle for Which SLMCPR Value Has Been Approved & TS 5.6.5 W/Note Providing Link to Specific GE Documents Used in Approving SLMCPR Changes for Given Cycle ML20217J0481997-08-0505 August 1997 Proposed Tech Specs 2.1.1.2, Reactor Core (Safety Limits), Increasing Two Recirculation Loop MCPR Limit to 1.13 & Single Recirculation Loop MCPR Limit to 1.14 ML20151L6041997-07-31031 July 1997 Proposed Tech Specs,Requesting Approval of Change to TS 3.6.1.8, Penetration Valve Leakage Control Sys, for Upcoming Outage ML20196J7741997-07-30030 July 1997 Proposed Tech Specs Clarifying Surveillance Requirements 3.6.4.2.1 & 3.6.4.2.2 to Match Corresponding Changes to NUREG-1434 ML20134A7021997-01-20020 January 1997 Proposed Tech Specs to License NPF-47,enhancing Operation of Plant to Allow Operation at 100% Power W/Lower Core Flows & Use of Flow Control Spectral Shift Strategies to Increase Cycle Energy ML20133M0451997-01-10010 January 1997 Proposed Tech Specs 3.4.11 Re RCS Pressure & Temp Limits ML20140F0151996-12-26026 December 1996 Rev 6 to RSP-0008, ODCM Procedure ML20134M2271996-11-15015 November 1996 Proposed Tech Specs,Changing TS SL 2.1.1.2, Reactor Core (Sl), Which Increases Two Recirculation Loop MCPR Limit from 1.07 to 1.10 & Single Recirculation Loop MCPR from 1.08 to 1.12 ML20134M0151996-11-15015 November 1996 Proposed Tech Specs 3.8.1 Re AC Sources Operating ML20134M2061996-11-0606 November 1996 Proposed Tech Specs,Permitting Increase in Allowable Leak Rate for MSIVs & Deleting Penetration Valve Leakage Control Sys & Ms Positive Leakage Control Sys Requirements ML20129J4231996-10-24024 October 1996 Proposed Tech Specs 3.8.1 Re A.C. Sources - Operating ML20117K1071996-08-29029 August 1996 Proposed Tech Specs Re Reactor Vessel Matl Surveillance Program Capsule Withdrawal Schedule ML20117G7401996-08-29029 August 1996 Proposed Tech Specs 3.1 Re Reactivity Control Systems ML20116P1341996-08-0808 August 1996 Technical Requirements Manual ML20116J3151996-08-0707 August 1996 Proposed Tech Specs,Submitting TS Bases Pages for Revs Performed Since 951001 Approval of TS Bases ML20116L6321996-08-0101 August 1996 Proposed Tech Specs Re Primary Containment/Drywell Hydrogen Mixing Sys & Drywell Isolation Valves ML20113F2271996-06-12012 June 1996 Rev 0 to Calculation PI-0103-00203.002-101, Ampacity Derating Evaluation ML20117L2581996-06-0404 June 1996 Proposed Tech Specs Re Replacement Page for Ltr RBG-42764, Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks1996-05-31031 May 1996 Proposed Tech Specs 3.9.1 Re Refueling Equipment Interlocks ML20112E7831996-05-30030 May 1996 Proposed Tech Spec 3.8.3 Re Incorporation of 5-start Air Pressure Design Criterion for Div III DG ML20117H3271996-05-20020 May 1996 Proposed Tech Specs Re Change in Co Name from Gulf States Utils Co to Entergy Gulf States,Inc B130180, Surveillance Specimen Program Evaluation for River Bend Station1996-04-30030 April 1996 Surveillance Specimen Program Evaluation for River Bend Station ML20107E4681996-04-18018 April 1996 Proposed Tech Specs Re Fuel Loading W/Control Rods Withdrawn or Removed from Defueled Core Cells ML20094N7741995-11-22022 November 1995 Proposed Tech Specs,Clarifying Info Contained in License Amend Request (LAR) 95-21 ML20094M8001995-11-20020 November 1995 Proposed Tech Specs Re Drywell Leak Rate Testing Requirements ML20094N0091995-11-20020 November 1995 Proposed Tech Specs Eliminating Selected Response Time Testing Requirements ML20094B0001995-10-26026 October 1995 Proposed Tech Specs,Consisting of Change Request 95-10, Deleting TS 5.5.12, Biofouling Prevention & Detection, & Various Editorial Corrections ML20093L7361995-10-24024 October 1995 Proposed Tech Specs 3.6.1.1 Through 3.6.1.3 Re Containment Sys ML20108B5941995-10-0101 October 1995 Rev 5A to River Bend Station Offsite Dose Calculation Manual Procedure ML20087J5451995-08-17017 August 1995 Proposed Tech Specs Re Engineered Safety Sys Which Responds to Fuel Handling Accident Conditions ML20084L5001995-05-30030 May 1995 Proposed Tech Specs,Allowing TS 3/4.6.2.2, Drywell Bypass Leakage, Tests to Be Performed at Intervals as Long as Five Yrs Based on Demonstrated Performance of Drywell Structure ML20084L4541995-05-30030 May 1995 Proposed Tech Specs Re Request for Exemption from App J, Primary Reactor Containment Leakage Testing for Water- Cooled Power Reactors ML20078M1171995-02-0808 February 1995 Proposed Tech Specs Page Re Secondary Containment Automatic Isolation Dampers ML20077S4401995-01-18018 January 1995 Revised Pages of Proposed Tech Specs Re Conversion to TS Based on NUREG-1434, Improved TS Rev 0 ML20078H0881994-11-10010 November 1994 Proposed Tech Specs Reflecting Clarifications to LAR 91-11 1999-07-30
[Table view] |
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ATTACKMENT-PROPOSED GULt STATES UTILITIES COMPANY RIVER BEND STATION DOCKET 50-458/ LICENSE NO. NPF-47 RADIATION MONITORING INSTRUMENTATION (90-24)
LICENSING DOCUMENT INVOLVED: TECHNICAL SPECIFICATIONS ITEM: Table 3.3.7.1-1, Item 4a REASON FOR REQUESTt In accordance with 10CFR50.90, Gulf States Utilities Company (GSU) is- requesting a change to Technical Specification Table 3.3.7.1-1, #
" Radiation Monitoring Instrumentation," to reduce the alarm setpoint for the condenser air ejector pretreatment noble gas activity monitor from the current value of 2.48 E(4) mR/hr to 3410 mR/hr.
DISCUSSION During a review of Stone & Webster Engineering Corporation (SWEC)
Calculation PR(c)-509-1, errors were detected by GSU personnel in the calculation of the alarm setpoint for the condenser air ejector pretreatment noble gas activity monitor (offgas pretreatment l
monitor). The calculational errors resulted in a non-conservative value for the offgas pretreatment high alarm setpoint, which was incorporated into Technical Specification (T/S) Table 3.3.7.1-1, Item 4a. This condition was reported to the staff as a condition outside the design basis of-the plant in Licensee Event Reports (LER)90-005, Revisions 0, 1 and 2, dated April 2, 1990, August 31, 1990, and December 27, 1990, respectively. This change request is being submitted as a portion of the corrective action for this LER.
-SWEC reviewed the methodologies used in establiehing the original
) T/S setpoint for this _ monitor. This review identified two l methodology errors which resulted in the following non-conservative -
setpoint values:
- 1. A conceptual error in the methodology used regarding 'che
! distribution of activity flow rates at piping branch-points.
L This led to calculation of setpoints that were independent of.
offgas system operating modes (i.e., startup operation-versus normal operation).
Page 1 of 4 9105220165 910514 PDR ADOCK 05000458 P PDR
- 2. The use of " stretch" reactor thermal power (105%) as the basis for the total steam-to-main condenser mass flow rate. The Technical Specifications f or River . Bend Station specify a total activity release rate limit which is based on 100%
reactor thermal power. Thus, the basis for the original T/S setpoint is inconsistent with the Technical Specification limit.
SWEC Calculation PR(c)-509-1 was superseded by GSU Calculation No.
G13.18.9.5-19-0, which recalculated the alarm setpoint using this revised methodology. The setpoint for full power operation was reduced from the original T/S setpoint 2.48 E(4) mR/hr to the current setpoint 546 mR/hr via Modification Request (MR) 90-0036.
- Subsequent operation, particularly during the monitoring of leaking fuel assemblies, demonstratec that the new alarm setpoint was conservative. A detailed review of the assumptions in Calculation G13.18.9.5-19-0 indicated that the setpoint had been calculated for full power operation to maximize steam and non-condensable flow to the condenser. In addition, ofigas flow had been assumed to be equal to system start-up flow, to maximize radionuclide concentrations at the pretreatment monitor. However, these assumptions were incompatible.
For full power operations, reactor main steam flow is 12,474,347 lbs/hr and offgas flow is less than 50 scfm. The calculation which resulted in a conservative setpoint of 546 mrem /hr assumed that ,
offgas flow could be as high au the maximum system startup flow of 250 scfm. When the appropriate system flow rate of 50 scfm was used, the high alarm setpoint was calculated to be 3410 mRom/hr.
To ensure that this setpoint was correct, the operation of the main condenser offgas and air removal systems was reviewed. During plant startuo, approximately 95 percent of the non-condensable gases are' removec from the main condenser by the air removal system compressors. Th se are filtered and monitored prior to release from the main p?.snt exhaust. During this time, the offgas system is in startup with its charcoal adsorber beds bypassed to prevent wetting of the charcoal. The offgas system is not in operation until the air removal compressors are shutdown and the charcoal adsorber beds are placed in the " treat" mode. This is done with offgas system flow less than 50 scfm. Therefore, the offgas flow used to calculate an alarm setpoint of 3410 mrem /hr is valid.
Based on this recalculation, the offgas pretreatment radiation monitor setpoints are being revised via a new MR. A comparison between the original T/S, current, and final T/S setpoints is provided below. All setpoint figures are in units of mrem /hr.
Page 2 of 4
Original Current Final Setpoint Function I/J Setooint Setooint T/S Se J ooint Control Room Alarm 2.48 E(4) 5.46 E(2) 3.41 E(3) and TS 3.3.7.1 LCO Emergency Plan NOUE 4.08 E(4) 9.43 E(2) 5.88 E(3)
Emergency Action Level 3 Emergency Plan Alert 4.08 E(5) 9.43 E(3) 5.88 E(4)
Emergency Action Level 1 In addition to affecting the Technical Specifications, the above calculation methodology errors also affect the Updated Safety Analysis Report (USAR) Section 13.3, " Emergency Plan", Table 13.3-1. As a result of correcting the errors in the calculation, two Emergency Action Level setpoints will also be reduced.
SIGNIFICANT HAZARDS CONSIDERATIOll:
In accordance with the requirements of 10CFR50.92, the following discussions are provided in support of the determination-that no significant hazards are created or increased by tho change proposed by this submittal.
- 1. The proposed change would not increase the probability or consequences of a previously evaluated accident because:
The existing Technical' Specification alarm setpoint is non-conservative. The proposed change will decrease the alarm setpoint, providing operations personnel with earlier detection of high radioactivity levels in the offgas system upstream of the holdup pipe.
- 2. The proposed change would not reate the possibility of a new or different kind of accident from any previously evaluated because:
The proposed change will only reduce an alarm setpoint to a more conservative value. This change does not involve the potential for a new accident type, since plant design and alarm functions are unchanged.
- 3. The proposed change would not involve a significant reduction in the margin of safety because:
l Margins of safety are enhanced since this change would. reduce L the offgas pretreatment monitor alarm setpoint to a more conservative value.
Page 3 of 4
Based on the_above, GSU has determined that the proposed change does not (1) involve significant increase in the probability or consequences of an accident previously evaluated, (2) create the probability of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety and therefore, does not involve a significant hazard consideration.
REVISED TECHNICAL SPECIFICATION:
The requested revision is provided in the Enclosure.
SCHEDULE FOR ATTAINIEG COMPLIANCE:
GSU is currently in full compliance with the applicable Technical Specification requirements. GSU e? quests this change be effective upon receipt.
NOTIFICATION OF STATE PERSONNEL:
A copy of this amendment request has been provided to the State of Louisiana, Department of Environmental Quality -
Radiation ,
Protection Division.
ENVIRONMENTAL IMPACT APPRAISAL:
GSU has reviewed the proposed license amendment against the criteria of 10CFR51.22 for environmental considerations. The proposed changes do not involve a significant hazards consideration, nor increase the types and amounts of ef fluents that may be released offsite, nor significantly increase individual or cumulativo occupational radiation exposures. Based on the foregoing, GSU concludes that the proposed change meets the criteria given in 10CFR51.22(c)(9) for a categorical exclusion from the requirement for an Environmental Impact Statement.
l l
Page 4 of 4
.. i
, TABLE 3.3.7.1 <
Q -
g RAOIATION MONITORING INSTRUMENTATION 8
$ MINIMUM CHANNELS APPLICABLE- ALARM / TRIP e INSTRUMENTATION OPERABLE CONDITIONS SETPOINT ACTION c :-
i 5
- 1. Main Control Room 4" ,
" Ventilation Radiation
! Monitor i
! a. Local Intake 2 1,2,3,5 and
- b. Remote Intake 1 $ 0.97 x 10 5 pCi/ccg ,)
1,2,3,5 and 5 0.97 x 10 5 pC1/cc 71 k ;
- 2. Area Monitor
- a. Fuel Building ,
Spent Fuel ' 1 -< 15 mR/hr(,) 71 E' !
g Storage Pool S S
to 3. Main Condenser Offgas 5 di Post-Treatment System
- Effluent Monitoring System i
- a. Noble Gas Activity :
Monitor - (Providing Alarm and Automatic ;
Termination of '
Release). 1 1 5.08 x 105 cpm 72
- 4. Condenser Air Ejector Pretreatment i Radioactivity Monitor >
(Prior to Input to I Holdup System) i
- a. Noble' Gas Activity 3430 i Monitor' 1 ** $-2.18 x 104 mR/hr(,) 73 ,
i
.