SER Re Allowable Control Room Inleakage to Meet Habitability Requirements.Reduction in Allowable Control Room Inleakage for Completed Control Room to 590 Cfm RecommendedML20138F486 |
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Grand Gulf ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
10/16/1985 |
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From: |
NRC |
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To: |
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Shared Package |
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ML20138F434 |
List: |
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References |
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TAC-56445, NUDOCS 8510250274 |
Download: ML20138F486 (3) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
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Util Needs to Revise Package to Address Programmatic Improvements Identified ML20055F9081990-07-16016 July 1990 Safety Evaluation Accepting Criticality Analysis for Cycle 5 Fuel in Spent Fuel Storage Racks ML20055G0341990-07-16016 July 1990 Safety Evaluation Re Boraflex Gaps in Spent Fuel Racks. Storage Racks Can Safely Accomodate Max Reactivity of Unit 1 Cycle 1 Through Cycle 4 Fuel.Storage Rack Surveillance Program Acceptable for long-term Storage of Spent Fuel ML20246D8021989-08-21021 August 1989 Safety Evaluation Granting 880524 Requests for Relief from Certain Requirements of ASME Code,Section XI ML20246B6311989-08-17017 August 1989 Safety Evaluation Supporting Amend 25 to License NPF-62 ML20247G7041989-07-21021 July 1989 SER Accepting Licensee Commitment to Install ex-core Neutron Flux Monitoring Instrumentation Meeting Requirements of Reg Guide 1.97,Rev 2,prior to Restart Following Fourth Refueling Outage ML20245A8251989-04-17017 April 1989 SER Re Proposed Changes to Administrative Controls Section of Tech Specs Concerning Min Shift Crew Composition,Unit Staff Qualifications,Training,Plant Safety Review Committee & Safety Review Committee Composition.Changes Unacceptable ML20244D5291989-04-14014 April 1989 Safety Evaluation Supporting Util Actions in Response to Generic Ltr 83-28,Position 4.5.2, Testing of Reactor Trip Sys. Justification for Not Testing Reactor Mode Switch or Backup Scram Valves Provided ML20248J9001989-04-0505 April 1989 Safety Evaluation Accepting Licensee Statements Confirming That Vendor Interface Program Exists W/Nsss Vendor for Components Required for Performance of Reactor Trip Function ML20151P0291988-08-0505 August 1988 Safety Evaluation Supporting Generic Ltr 83-28,Position 4.5.1 Re on-line Testing of Reactor Trip Sys ML20234D9021987-12-30030 December 1987 Safety Evaluation Supporting 870612,0814,1026 & 1119 Relief Requests from First 10-yr Interval Inservice Insp Program Requirements of Section XI of ASME Code ML20149E7091987-12-30030 December 1987 Safety Evaluation Supporting Amend 41 to License NPF-29 ML20234C7671987-12-23023 December 1987 Safety Evaluation Granting 870612,0814,1026 & 1119 Requests for Relief from Certain Section XI ASME Code Requirements Re First 10-yr Interval Inservice Insp Program ML20236B1021987-10-15015 October 1987 Safety Evaluation of 870630 Submittal Supplemented on 870821 & 0911 Re Deferral of Certain Insps of Tdi Div II Emergency Diesel Generators.Deferral of Certain Design Review & Quality Revalidation Baseline Insps Approved ML20235V1701987-10-0707 October 1987 Safety Evaluation Re 861022 Rev 2 to Process Control Program (PCP) for Processing & Packaging of Wet Radwastes.Pcp Acceptable ML20234A9471987-09-0404 September 1987 Safety Evaluation Re Util 870702 Submittal Re Containment Isolation for Various Instrument Lines.Util Proposed Alternate Basis to Meet GDC 55 to 10CFR50 App a Acceptable ML20237H1711987-08-21021 August 1987 Safety Evaluation Supporting Util 851014,870403 & 870622 Submittals Providing Info Re ATWS-related Design Features, Alternate Rod Injection,Standby Liquid Control Sys & Recirculation Pump Trip ML20236M3841987-07-31031 July 1987 Safety Evaluation on Generic Ltr 83-28,Items 3.1.1,3.1.2, 3.2.1 & 3.2.2 Re post-maint Testing.Licensee Programmatic Controls & Procedures for post-maint Testing of Components in Reactor Trip & safety-related Sys Acceptable ML20215J1351987-05-0404 May 1987 Safety Evaluation Re Spill of Sulphuric Acid at Plant on 860322.Licensee Monitoring & Recovery Sys Adequate to Contain & Eliminate Existing Acid Plume.No Addl Measures Recommended ML20210C3391987-04-30030 April 1987 Safety Evaluation Accepting Licensee 870129 Proposed Solution to Concern Re Control of Activities within Exclusion Areas ML20204J1451987-03-23023 March 1987 SER Supporting Licensee Responses to Humphrey Concerns on Safety of Mark III Containment Design ML20207R1051987-03-0505 March 1987 Safety Evaluation Supporting Util 861125 Rept on Conformance to Reg Guide 1.133,Rev 1, Loose-Part Detection Program for ...Sys of Light Water Cooled Reactors. License Condition 2.C(14) Adequately Addressed ML20212M3861987-03-0404 March 1987 Safety Evaluation Accepting Util 861223 Response to IE Bulletin 79-26, Boron Loss from BWR Control Blades, Per License Condition 2.C.(12) ML20212G3421987-01-12012 January 1987 Safety Evaluation Accepting Util 850228 & 860214 Submittals on Conformance to Reg Guide 1.97,Rev 2 ML20207N2761987-01-12012 January 1987 SER Supporting License Condition 2.C.(17) Which Replaces Check Valve Disc in Train B Feedwater Line Into Which Cold Water from Condensate Storage Tank Injected by RCIC ML20211P3901986-12-12012 December 1986 SER Supporting Util 860825 Request for Rev to Relief Request I-00007 Seeking Relief from Surface Exam for Welds within Flued Heads & Guard Pipes ML20214W8161986-12-0808 December 1986 Safety Evaluation Granting Util 861015 Request for Release from Commitment to Compare Performance of on-line Instrumentation Vs Grab Sampling Techniques 1999-09-23
[Table view] Category:TEXT-SAFETY REPORT
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ENCLOSURE SAFETY EVALUATION CONTROL ROOM HABITABILITY GRAND GULF NUCLEAR STATION, UNITS 1 AND 2 INTRODUCTION Section 6.4 of the staff's Supplement No. 6 (SSER 6) to the Safety Evaluation Report related to Operation of Grand Gulf Nuclear Station (GGNS), Units 1 and 2 (NUREG-0831) provided staff's evaluation of control room habitability for the present stage of completion of Grand Gulf Unit 2. The GGNS control room is shared between Units 1 and 2. The Unit 2 part of the control room is partially completed and construction of Unit 2 is being held in abeyance. In SSER 6 staff concluded that for operation of Unit 1, concurrent with construction of Unit 2, the allowable control room inleakage rate of 760 cfm requested by licensee in its. February 6,1984, letter was acceptable, licensee had stated in its February 6,1984, letter that after Unit 2 construction was completed the allowable control room inleakage could be reduced to 590 cfm. In SSER 6 staff indicated that it would review control room habitability systems for simultaneous operation of Units 1 and 2 with respect to allowable control room inleakage prior to operation of Unit 2. License Condition 2.C.(38) allowed a leak rate of 590 cfm for operation of Unit I with Unit 2 in its present stage of completion and no ongoing construction of the Unit 2 portion of the control room and allowed a leak rate of 760 cfm for operation of Unit I concurrent with con-struction of the Unit 2 portion of the control room.
The present safety evaluation was made to determine the allowable control room leak rate for simultaneous operation of Units 1 and 2. Based on its evaluation and conclusion described below, the staff will condition the Unit 2 operating license to limit allowable control room inleakage for the completed Unit 1 and Unit 2 control room to 590 cfm.
EVALUATION By letter dated February 6,1984, the licensee provided the results of scale model tests from which atmospheric dispersion coefficients relating accidental releases of radioactivity and control room doses may be estimated. The NRC staff independently, calculated the dispersion coefficients and control room doses.
We have reviewed the wind tunnel tr M r w lures and results. The tests were conducted using 1:240 scale modelt o @ 3: clear station structures with two complete units including cooling to, vers, and with Unit I with its natural draft cooling tower and a partially completed Unit 2. Gaseous tracers were released from the modeled auxiliary building vents and sampled at 20 locations on the west face and at 16 locations on the top of the control building. A wind velocity profile in the vertical direction was simulated in the wind tunnel.
The tests were conducted with a tunnel wind speed of 10 fps at a reference height of 9.6 inches, during which the tests are relatively independent of 8510250274 e51016 PDR ADOCK 0 % 4d6 F
friction as represented by the Reynolds number (i.e., XU/Q constant when the wind speed, u and source term, Q, are varied in proportion to one another).
The effects of wind direction were simulated by rotating the scaled structures on a turntable. Tests by wind direction were made for releases from the inboard and outboard vents of Units 1 and 2. XD/Q was calculated from measurements at each sampling location for each test. We concluded from our review of the test documentation and results that the experiment was well designed and that the resulting concentrations can be used for evaluation of control room habitability for Grand Gulf. Units 1 and 2.
The wind tunnel test results provided a basis for evaluation by the staff of atmospheric dispersion for use in the habitability evaluation of the Grand Gulf control room. The wind tunnel test results show that the highest relative con-centrations (XU/Q) usually occurred on the roof of the control room. The r maximum XG/Q value for releases from Unit 1 vents was measured as 4.2 x 10 goftgp m for the inboard vent during west winds.
Unit 2 vents was measured as 1.1 x 10y-3 Thg m - for rooftop the inboardmaximum XU/Qnorth-vent during value from northeast winds. However, the HVAC system intakes for the control room are located near ground level and on the west face of the control building. The maximum XU/Q values on thg fage of the building near the HVAC intakes were l indicated to be 1.4 x 10- m for both inboard a Unit I during south-southwest winds and 2.0 x 10-gdmcytboard vent vent
- for inboard releases from releases from Unit 2 during northeast winds. Thus, the limiting relative concentration (XGf0) {or evaluation of control room habitability fue tg inleakage is 1.1 x i
10- m- and due to ventilation intake is 2.0 x 10 m- . These Xu/Q values were each divided by wind speed (u) at the percentiles given in the Murphy-Campe methodology for pertinent time intervals following an accident. The wind speeds at the percentiles were obtained by analysis of the onsite wind data at the 49.4m level for the time periods August 1972 through July 1974 and the 1976 calendar year. The wind direction and occupancy factors were also taken from the Murphy-Campe methodology.
The results of these analyses are as follows:
Intake Time Wind Direction Occupancy Wind X/Q Period Factor 3 Factor Speed (m/s) (sec/m )
0 - 8 hr. I 1 1.2 1.7 x 10-4 8 - 24 hr. 0.88 1 1.6 1.1 x 10-4 1 - 4 days 0.75 0.6 2.1 7.1 x 10 4 - 30 days 0.50 0.4 3.0 3.3 x 10-5 It was assumed that all containment leakage in the first two minutes of a release of radioactivity would escape instantaneously into the environment, and that following this first two minute period the standby gas treatment system would filter and exhaust containment leakage at a rate of 4000 cfm. All other assumptions were as described in the SER, NUREG-0831, September 1981.
CONCLUSION The computed control room doses are 0.2 rem whole body and 20 rem thyroid. These doses are less than the dose criterion of General Design Criterion 19, 10 CFR Part 50, Appendix A, with which the control room design is in conformance. The protection of control room occupants against chlorine gas is obtained by the automatic isolation of the normal ventilation system and the provision of com-pressed air breathing apparatus, and is not affected by the inleakage rate. We conclude that the licensee's proposed control room inleakage of 590 cfm for simultaneous operation of Units 1 and 2 is acceptable.