Proposed Tech Specs Changing UFSAR by Increasing Max Rod Internal Pressure in Spent Fuel Pool from 1,200 to 1,300 PsigML20154C102 |
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Oconee  |
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Issue date: |
09/30/1998 |
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DUKE POWER CO. |
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ML15112A259 |
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NUDOCS 9810060145 |
Download: ML20154C102 (3) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20155C6391998-10-26026 October 1998 Proposed Tech Specs Tables 4.1-1 & 4.1-2,revised Surveillance Frequency of Refueling Outage to 18 Months ML20154C1021998-09-30030 September 1998 Proposed Tech Specs Changing UFSAR by Increasing Max Rod Internal Pressure in Spent Fuel Pool from 1,200 to 1,300 Psig ML20236V9611998-07-27027 July 1998 Corrected TS Bases Pages 3.5-30b of 961211 & 3.16-2 of 970205,correcting Amend Numbers ML20236T5171998-07-20020 July 1998 Proposed Tech Specs Re one-time Extension to Functional Test Frequencies for Hydraulic & Mechanical Snubbers ML20236R1901998-07-16016 July 1998 Proposed Tech Specs Extending TS Surveillances TS 4.20.2(a), Table 4.20-1,items 1,2 & 4,TS 4.1-1,Table 4.1-1,items 8,9,10 & 11 & TS 4.5.1.2.1,item b(1) ML16141B0771996-11-18018 November 1996 Errata to TS 3.7,which Removes Criteria for Battery & Battery Charger Specific Svc Tests ML16141A9291995-06-29029 June 1995 Proposed Tech Specs Re Mgt Positions Authorized to Approve Such Items as Procedures & Procedure Changes,Station Mods, TS Amends & Reportable Events ML16141A8111994-04-20020 April 1994 Proposed Tech Spec Table 4.1-2, Min Equipment Test Frequency ML16141A7981994-04-12012 April 1994 Proposed Tech Specs Re Technical Review & Control Activities ML15261A4281994-02-24024 February 1994 Proposed TS 4.6, Emergency Power Periodic Testing ML20044C9581993-05-0404 May 1993 Proposed TS 4.7.1, Control Rod Trip Time Test ML18032A3441987-05-29029 May 1987 Proposed Tech Specs,Clarifying Trip Level Setting in Table 3.2.A for Standby Gas Treatment Sys Relative Humidity Heater ML15264A2511984-09-11011 September 1984 Proposed Tech Specs Supporting Operation of Facility at full-rated Power During Cycle 9 ML15223A8931983-05-19019 May 1983 Proposed Tech Spec Changes Re Core Protection Safety Limits, Protective Sys Max Allowable Setpoints & Rod Position Limits ML16134A6761982-08-11011 August 1982 Proposed Tech Spec Revisions Re Reload Design Calculations for Cycle 7 ML16134A6731982-05-0303 May 1982 Proposed Tech Spec Changes Re Core Protection Safety Limits, Protective Sys Max Allowable Setpoints & Rod Position Limits ML15223A7671982-01-12012 January 1982 Proposed Revisions to Tech Spec Section 3.1.2 Re Heatup Cooldown & Inservice Test Limitations for RCS ML16148A4421981-11-13013 November 1981 Proposed Tech Spec Revision Re Core Protection Safety Limits Protective Sys Max Allowable Setpoints & Rod Position Limits ML16148A4351981-10-28028 October 1981 Proposed Revision to Tech Spec Figure 3.5.2-4B2,allowing Cycle 5 to Run at 100% Full Power W/Axial Power Shaping Rods Fully Inserted ML16148A4281981-08-19019 August 1981 Proposed Revision to Tech Spec Figures 3.5-16a,3.5.19a, 3.5-22 & 3.5-25a Re Extension of Operating Limits ML15223A7321981-05-29029 May 1981 Proposed Tech Specs 2.1-2,2.1-3,2.1-7,2.3-5,3.2-1,3.2-2, 3.3-1,3.3-2,3.3-3,3.3-4,3.3-5,3.3-6,3.5-9,3.5-10,3.5-15, 3.5-15a & b,3.5-18,3.5-18a,b,c,d & e,3.5-21,3.5-21a & B, 3.5-24,3.5-24a & b,3.8-2 & 3.8-3 Re Core Protection ML15112B0161981-04-20020 April 1981 Revised Tech Specs Pages Per Order Modifying License, Requiring Periodic Surveillance Over Life of Plant & Specifying Limiting Conditions for Operation of Primary Coolant Sys Pressure Isolation Valves ML15112A9721980-10-24024 October 1980 Revised Tech Spec Pages Per 801024 Order for Mod of Licenses Re Environ Qualification of safety-related Electrical Equipment ML16134A6651980-08-25025 August 1980 Proposed Tech Specs Revision for Cycle 6 ML16148A3351980-07-16016 July 1980 Proposed Revision to Tech Spec 3.3.1.c Allowing Continued Operation of Unit 2 of Full Rated Power While Maint Continues on HPI Pump Until 800718 ML19318B9731980-06-24024 June 1980 Proposed Tech Spec Interpreting Term Operable as Applied to Various Tech Spec Requirements ML19317H3061980-04-10010 April 1980 Model Tech Specs for PWRs & BWRs ML19317H3191980-02-21021 February 1980 Nuclear Data Link Spec,Revision 0,Draft 5 ML15238B2061980-01-15015 January 1980 Model Tech Specs for Fire Protection Program ML16148A2691979-11-16016 November 1979 Proposed Changes to Tech Spec Pages 2.1,2.3,3.2 & 3.5. Changes Affect Core Protection Limits,Reactor Protective Sys Max Allowable Setpoints & Vol Requirements for Borated Water Storage Tank ML19317D2701978-09-25025 September 1978 Proposed Tech Spec 3.5.2 Re Control Rod Group & Power Distribution Limits & Table 4.1-2 Re Min Equipment Test Frequency ML19317D2621978-09-18018 September 1978 Proposed Revisions to Tech Specs 2.1,2.3,3.2 & 3.5 Re Core Protection Safety Limits & Protective Sys Max Allowable Setpoints ML19317D2731978-09-0606 September 1978 Revised Tech Spec Page,Figure 2.3-2A,re Protective Sys Max Allowable Setpoints ML19317D2491978-08-22022 August 1978 Proposed Revision to Tech Specs 4.18 Re Hydraulic Shock Suppressors (Snubbers) ML19322B9961978-08-21021 August 1978 Proposed Revision to Tech Spec 2.3 Re Cycle 5 ML19329A2791978-08-0707 August 1978 Facility Tech Specs 3.9.9 Through 3.9.11 to Control Waste Water Pond Radioactivity ML19312B7931978-07-17017 July 1978 Proposed Tech Spec 3.1.6.4,changing Steam Generator Leak Rate Limit ML19308D6271978-06-28028 June 1978 Tech Spec Change Request Re Paragraph 2.B(6),stipulating That Byproduct & SNM Associated W/Four Fuel Assemblies Acquired by Fl Power Corp from Duke Power Co Previously Irradiated in Oconee 1 May Be Possessed ML19317D2301978-06-26026 June 1978 Proposed Tech Specs 2.1,2.3,3.2,3.5 & 4.1 Required to Support Operation of Unit 1 at Full Rated Power During Cycle 5,including Core Protection Safety Limits & Protective Sys Mac Allowable Setpoint ML19316A6501978-06-22022 June 1978 Proposed Replacement Page for Tech Spec 4.1-2 Re Min Equipment Test Frequency ML19316A5381978-06-14014 June 1978 Proposed Changes to Tech Specs Re thermal-hydraulics Analysis.Revision to BAW-1486, Unit 3,Cycle 4 Reload Rept ML19312B8161978-06-12012 June 1978 Proposed Tech Specs 3.8,4.4 & 4.6 Re Fuel Loading & Refueling,Structural Integrity & Emergency Power Periodic Testing ML19317D2341978-06-0909 June 1978 Proposed Tech Spec 3.9 Deleting Requirements Not Applicable to Liquid Effluent Monitoring Sys Due to Installation of Offline Monitor ML19317D2221978-06-0808 June 1978 Proposed Tech Spec 3.1 Allowing Max 1 Gallon Per Minute Leakage Through Steam Generator Tubes Prior to Initiation of Unit Shutdown ML19317D2121978-06-0202 June 1978 Proposed Tech Spec 4.2 Allowing re-insp of Reactor Coolant Outlet Nozzles at Future Refueling Outage ML19316A5271978-05-30030 May 1978 Proposed Revisions to Tech Specs 2.3,3.2 & 3.5.2.4 to Support Cycle 4 Operation at Full Power ML19312B7971978-04-27027 April 1978 Proposed Tech Spec 6.4,incorporating Operating Procedure Requirements Re B&W Small Break ECCS Analysis ML19312B8091978-04-20020 April 1978 Proposed Tech Spec 3.3 Incorporating New Tech Spec 3.3.8 Requiring Operability of Three HPI Pumps for Each Unit During Power Operation Above 60% Full Power ML19317D2001978-03-20020 March 1978 Proposed Tech Spec 3.5 Including 6.03% Quadrant Power Tilt Limit & Provision for Notifying NRC If Tilt Exceeds 3.5% ML19317D2131978-02-21021 February 1978 Proposed Tech Spec 3.1. Incorporating Revision to Pressurization,Heatup & Cooldown Limitations.B&W to Util Re Corrections to Errors Discovered in B&W Rept BAW-1436 Encl 1998-09-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211A9881999-08-18018 August 1999 Rev 5 to DPC Nuclear Security Training & Qualification Plan ML20204B4141999-03-27027 March 1999 Revised Oconee Nuclear Station Selected Licensee Commitments, List of Effective Pages ML20155C6391998-10-26026 October 1998 Proposed Tech Specs Tables 4.1-1 & 4.1-2,revised Surveillance Frequency of Refueling Outage to 18 Months ML20154L7191998-10-0505 October 1998 Rev 8 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20154C1021998-09-30030 September 1998 Proposed Tech Specs Changing UFSAR by Increasing Max Rod Internal Pressure in Spent Fuel Pool from 1,200 to 1,300 Psig ML20236V9611998-07-27027 July 1998 Corrected TS Bases Pages 3.5-30b of 961211 & 3.16-2 of 970205,correcting Amend Numbers ML20236T5171998-07-20020 July 1998 Proposed Tech Specs Re one-time Extension to Functional Test Frequencies for Hydraulic & Mechanical Snubbers ML20236R1901998-07-16016 July 1998 Proposed Tech Specs Extending TS Surveillances TS 4.20.2(a), Table 4.20-1,items 1,2 & 4,TS 4.1-1,Table 4.1-1,items 8,9,10 & 11 & TS 4.5.1.2.1,item b(1) ML20217F2841998-04-20020 April 1998 Rev 7 to DPC Nuclear Security & Contingency Plan, for Oconee,Mcguire & Catawba Nuclear Stations ML20141F1521997-06-25025 June 1997 Rev 4 to Nuclear Security Training & Qualification Plan ML16141B0771996-11-18018 November 1996 Errata to TS 3.7,which Removes Criteria for Battery & Battery Charger Specific Svc Tests ML20134K5401996-10-31031 October 1996 Rev 6 to Chemistry Manual 5.1, Emergency Response Guidelines ML20117J0181996-08-15015 August 1996 Revised Chapter 16 of Oconee Selected Licensee Commitments Manual ML20095H1291995-12-0505 December 1995 Rev to ONS Selected Licensee Commitments (SLC) Manual, Revising SLC 16.6.1, Containment Leakage Tests to Reflect Current Plant Configuration & Update Testing Info ML20091P2461995-08-21021 August 1995 Rev to ONS Selected Licensee Commitments Manual ML16141A9291995-06-29029 June 1995 Proposed Tech Specs Re Mgt Positions Authorized to Approve Such Items as Procedures & Procedure Changes,Station Mods, TS Amends & Reportable Events ML16141A8581995-01-0909 January 1995 Revs to Oconee Selected Licensee Commitments Manual ML16141A8111994-04-20020 April 1994 Proposed Tech Spec Table 4.1-2, Min Equipment Test Frequency ML16141A7981994-04-12012 April 1994 Proposed Tech Specs Re Technical Review & Control Activities ML15261A4281994-02-24024 February 1994 Proposed TS 4.6, Emergency Power Periodic Testing ML15224A3521993-10-26026 October 1993 Safety Assurance Directive 6.1, Oconee Nuclear Site Safety Assurance Emergency Response Organization ML20044C9581993-05-0404 May 1993 Proposed TS 4.7.1, Control Rod Trip Time Test ML20045F0721993-04-0707 April 1993 Rev 9 to Corporate Process Control Program Manual ML20097D9451992-05-28028 May 1992 Rev 11 to Training & Qualification Plan ML20096C2561992-04-30030 April 1992 Public Version of Revised Crisis Mgt Implementing Procedures (Cmip),Including Rev 46 to CMIP-1,Rev 39 to CMIP-4,Rev 45 to CMIP-5,Rev 49 to CMIP-6,Rev 48 to CMIP-7,Rev 42 to CMIP-9 & Rev 3 to CMIP-15 ML20096D5451992-04-0707 April 1992 Public Version of Revised Crisis Mgt Implementing Procedures (Cmip),Including Rev 45 to CMIP-1,Rev 27 to CMIP-13 & Notification of Deletion of CMIP-8.Procedure CMIP-8 Reserved for Future Use ML16131A5241992-03-0101 March 1992 Rev 35 to ODCM Generic Section ML20092M5891992-02-0606 February 1992 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 43 to CMIP-1,Rev 43 to CMIP-5,Rev 33 to CMIP-8,Rev 25 to CMIP-13,Rev 6 to CMIP-18,Rev 4 to CMIP-22 & Rev 38 to CMIP-4 ML20094H2391992-01-0101 January 1992 Rev 33 to McGuire Nuclear Station Odcm ML20094H2511992-01-0101 January 1992 Rev 34 to Catawba Nuclear Station Odcm ML16131A5221992-01-0101 January 1992 Rev 32 to Oconee Nuclear Station Odcm ML20087F3931991-12-11011 December 1991 Public Version of Rev 13 to Crisis Mgt Implementing Procedure CMIP-11, Emergency Classification - Mcguire. W/ 920121 Release Memo ML20086K8831991-11-18018 November 1991 Public Version of Revised Crisis Mgt Implementing Procedures (Cmips),Including Rev 42 to CMIP-1,Rev 29 to CMIP-2,Rev 42 to CMIP-5,Rev 12 to CMIP-11 & Rev 37 to CMIP-21 ML20086G7711991-10-16016 October 1991 Public Version of Revs to Crisis Mgt Implementing Procedures (Cmip),Including Rev 41 to CMIP-1,rev 37 to CMIP-4,rev 41 to CMIP-5,rev 46 to CMIP-6 & CMIP-7,rev 32 to CMIP-8,rev 40 to CMIP-9,delete CMIP-12 & Rev 24 to CMIP-13 ML20082C7441991-06-11011 June 1991 Public Version of Rev 13 to Crisis Mgt Implementing Procedure CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20081J9841991-06-10010 June 1991 Rev 3 to EDA-1, Procedure for Estimating Food Chain Doses Under Post-Accident Conditions ML20076A7241991-06-10010 June 1991 Public Version of Crisis Mgt Implementing Procedures, Including Rev 39 to CMIP-1,rev 28a to CMIP-2,rev 44 to CMIP-7,rev 39 to CMIP-9 & Rev 10 to CMIP-11 ML20081K0101991-06-0606 June 1991 Rev 8 to EDA-3, Offsite Dose Projections for McGuire Nuclear Station ML20072S0521991-03-15015 March 1991 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station ML16148A9621991-02-13013 February 1991 Public Version of Rev 10 to CMIP-12, Crisis Mgt Implementing Procedure ML20066G3621991-02-0101 February 1991 Public Version of Crisis Mgt Implementing Procedures, Including Rev 28 to CMIP-2,Rev 34 to CMIP-4,Rev 38 to CMIP-5,Rev 43 to CMIP-6,Rev 42 to CMIP-7,Rev 29 to CMIP-8, Rev 37 to CMIP-9 & Rev 34 to CMIP-21 ML20082P7611991-01-0101 January 1991 Rev 30 to Odcm,Catawba Nuclear Station ML15217A1291991-01-0101 January 1991 Rev 29 to Odcm,Oconee Nuclear Station ML20072S9621991-01-0101 January 1991 Public Version of Rev 12 to Crisis Mgt Implementing Procedure CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20082P7711991-01-0101 January 1991 Rev 31 to Odcm,Mcguire Nuclear Station ML20072P9621990-11-0808 November 1990 Rev 9 to Crisis Mgt Implementing Procedure CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20028H2211990-10-31031 October 1990 Public Versions of Revised Crisis Mgt Implementing Procedures,Including Rev 37 to CMIP-1,Rev 27a to CMIP-2,Rev 33 to CMIP-4,Rev 37 to CMIP-5 & Rev 42 to CMIP-6 ML20059F4301990-08-22022 August 1990 Public Version of Rev 27 to Crisis Mgt Implementing Procedure CMIP-2, News Group Plan ML20063Q2721990-08-14014 August 1990 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 36 to CMIP-1,Rev 32 to CMIP-4,Rev 36 to CMIP-5,Rev 41 to CMIP-6,Rev 40 to CMIP-7,Rev 27 to CMIP-8,Rev 35 to CMIP-9 & Rev 7 to CMIP-11 ML20043F4841990-05-23023 May 1990 Public Version of Crisis Mgt Implementing Procedures, Consisting of Rev 20 to CMIP-13 & Deletion of CMIP-15 & CMIP-17 1999-08-18
[Table view] |
Text
..
j.
Oconce Nuclear Station v
15.1I Fuel Handling Accidents 5
Where:
t h bubble rise time, seconds i,
5' d = effective bubble diameter, em 5
Since the mimmum water depth over a dropped fuel assembly is less than 23 feet (21.34 feet), the assumed 5
iodine DF must be less than 100, according to Reg. Guide 1.25, and calculated with comparable
./
5 conservatism as done in Reg. Guide 1.25. Using the above relationship, with a water depth of 21.34 feet, M*he fuel - "h[ qual to 19 (Reference OSC-6070).
a comparable DF is e 5
J$4et A ff$McM I'N#'
5 T
y. :;r pressufe, at a Spent Fuel Pool bulk temperature of 150 F.
M"M e L 5
less than 1200 psig[ based on the present TACO 2 computer code licensing limit of 2200 psia at operating 5
system condition (Reference FSAR Section 4.2.3.1.3, " Fuel Thermal Analysis").
e85ct i D 5
The hetivity released from the water's surface is released within a two-hour period as a ground release.
5 The atmospheric dilution is calculated using the two-hour ground release dispersion factor of 2.2 x 104 5
sec/m2 5
The totalintegrated dose (2-br EAB) to the whole body at the 1-mile exclusion distance is 0.185 Rem and l.-
5 the thyroid dose at the same distance is 52.45 Rem. These values are far below the limits given in L
5 10CFR100 of 25 Rem whole body and 300 Rem thyroid.
.5 15.11.2.2 Base Case Fuel Handling Accident inside Containment l
l 5
In 1977, the NRC asked Oconee to evaluate the offsite dose consequences for a fuel handling accident l
5 inside containment, per the guidance given in Reg. Guide 1.25. Since the shallow end of the fuel transfer l
5 canalis at an elevation of 816.5 feet, the same iodine decontammation factor used for the Fuel Handling l
5 Accident in the Spent Fuel Poolis used for the Fuel Handling Accident inside Contamment. The activity l
5 released from the refueling water is released as a ground release, which has an atmosphenc dispersion 5
factor of 2.2 x 104 sec/m2. There is no credit taken for any containment closure / integrity resulting in the 5
released activity from the refueling water going straight outside.
l i
5 Using the fuel assembly gap inventory in Table 15-1, and assuming all 208 fuel pins are damaged, the 5
two-hour EAB dose is 0.185 Rem to the whole body and 52.45 Rem to the thyroid. These values are 5
appropriately within the guidelines given in 10CFR100 (appropriately within means 100 Rem to the 5
thyroid), and are identical to the base case Spent Fuel Pool Fuel Handling Accident described in Section l
l 5
15.11.2.1, " Base Case Fuel Handling Accident in Spent Fuel Pool."
l S
1 5.:11.2.3 Supplemental Cases of Fuel Handling Accidents l-5 To provide additional information as to the sensitivity of various input assumptions into the offsite dose 5
consequences of the fuel handling accident, additional supplemental cases are described here.
5 CASE A:
5 If the radioisotope release from the spent fuel pool water's surface is assumed to be captured by the Spent 5
Fuel Pool Ventilation System, resulting in an elevated release, (atmospheric dispersion factor is equal to 5
3.35 x 10-5 sec/m3) and assuming that the Spent Fuel Pool Filters are 90% efficient for the removal of elemental and particulate iodine, and 70% efficient in the removal of organic iodine, the resultant 5
two-hour offsite dose is calculated to be 1.2 Rem thyroid and 0.021 Rem whole body at the exclusion 5
area boundary (EAB).
5 CASEB:
9810060145 980930
~
2 of k PDR ADOCK 05000269 (31 DEC 1997)
P PDR
-.. ~.... -
l L r, Attcchment.4 l'
Markup of UFSAR Change L'
I l
INSERT A-(Section-15.11.2.1. Dace 15-34)
H Duke will use a DF equal to 89 for a maximum rod internal pressure in the spent fuel pool of 1300 psig-for the fuel
-handling accident analysis per reference 21. lThis was justified in Reference 21 using the WCAP-7828 methodology described above.
P I
INSERT B (Section 15.11.2.1, oace 15-34) cnr is calculated to be less-than 1300 psig (based on the present TACO 3 computer code licensing limit of a proprietary value above nominal system pressure at operating system conditions)~.
t i.
I i
Oconee Units 1, 2,
and 3 3 of 4 i
m_
15.16 Post-Accident Hydrogen Control Oconee Nuclear Station
-5 15.16.7. REFERENCES 1
- 1. Shure, K., Fission Product Decay Energy, WAPD-BT-24, December 1961.
1
- 2. Allen, A. O., The Radiation Chemis:ry of Water and Aqueous Solutions, D von Nostrand Co., Inc.,
1961.
1
- 3. Morrison, D. L, An Evaluation of the Applicability of Existing Data to the Analytical Description of I
a Nuclear. Reactor Accident, Quarterly Progress Report for April through June,1968, BMI-IB44, July 1
1%8.
1
- 4. Zittel, II. E.,
Radiolysis Studies, ORNL Nuclear Safety Research and Development Program 1
, Bi-monthly Report for September-October 1967, ORNieTM-2057, Nov. 27,1967.
1
- 5. Coward, II. F., Jones, G. W., Limits of Flammability of Gases and Vapors, Bureau ofMines Bulletin 1.
503.
I
- 6. Markstein, G., " Instability Phenomena in Combustion Waves',4th Symposium on Combustion.
~
1
- 7. Shapiro, A.
M., Mofette, T.
R., Hydrogen Flammability Data and Application to PWR 1
Loss-of-Coolant Accident, WAPD-SC-545, September 1957.
I
- 8. Coleman, L F., et al, Large-Scale Fission Product Transport Experiments, BNWL 926, pp. 2.1 to 1
2.21, Dec.1968.
I
- 9. Stinchcombe, R. A., Goldsmith, P., " Removal of lodine from Atmosphere by Condensing Steam",
1 Journal ofNuclear Energy Parts A/B 20, pp. 261 to 275,1966.
1
- 10. Stinchcombe, R. A., Goldsmith, P., Clean.up of Submicron Particles by Condensing Steam, 1
AERE-M-1213.
- 11. Goldsmith, P., May, F. G., 'Diffusiophoresis and Thormophoresis in Water Vapor Systems", Aer$ sol I
1 Science, C. N. Davies, Ed., Academic Press, Inc., New York, New York, pp. 163-194 (1966).
I
- 12. liyland, E. L, ' Design Criteria, Contamment liydrogen Recombiner System (Rev. 0)," Duke Power 1.
Company, June 24,1983.
I
- 13. II. B. Tucker (Duke) letter to II. R. Denton (NRC) dated October 20,1986.
5
- 14. Regulatory Guide 1.7 (Rev 2), " Control of Combustible Gas Concentrctions in Containment i
5 Following a Loss-of-Coolant Accident' l
5
- 15. OSC - 6191 (Rev. 0), ' Reanalysis of Oconee liydrogen Recombiner and Purge System Requirements' S
- 16.,Wiens, L A. (NRC) letter to J. W. Ilampton (Duke) dated February 7,1996.
5
- 17. OSC - 123 (Rev.1), " Activity on l'ilter RB liydrogen Purge' 5
- 18. OSC - 6534 (Rev. 0), 'llydrogen Purge Cart Operator Dose Rate' j
5
- 19. OSC - 3781 (Rev. 5), " Documentation of Maximum Ilypothetical Accident (MiiA). Dose Model For 5
Oconee Nuclear Station' i
5
- 20. OSC - 6064 (Rev.1), ' Estimated' Radiation Dose Rates in the Aux 2hary Building Following a Large l
5 Break IDCA" l
1 TIIIS IS TIIE LAST PAGE OF TiiE CIIAPTER 15 TEXT PORTION.
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s c:.e4 9Mc 'lo h (31 DEC 1997) l l