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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20196G5071999-06-23023 June 1999 Vynp Assessment of On-Site Disposal of Contaminated Soil by Land Spreading ML20205S4211999-04-16016 April 1999 Non-proprietary Version of Revised Page 4-3 of HI-981932 Technical Rept for Vermont Yankee Spent Fuel Pool Storage Expansion ML20205F6631999-03-0404 March 1999 Jet Pump Riser Weld Leakage Evaluation ML20151U0361998-08-28028 August 1998 Non-proprietary Rev 1 to Holtec Rept HI-981932, Vermont Yankee Nuclear Power Station Spent Storage Expansion Project ML20205F6491998-07-31031 July 1998 Rev 1 to GE-NE-B13-01935-02, Jet Pump Assembly Welds Flaw Evaluation Handbook for Vermont Yankee ML20236G0011998-06-30030 June 1998 Individual Plant Exam External Events ML20247J8341998-05-31031 May 1998 Peak Suppression Pool Temp Analyses for Large Break LOCA Scenarios, for May 1998 ML20247E6521998-04-30030 April 1998 Rev 0 to GE-NE-B13-01935-01, Jet Pump Riser Welds for RS-1 Indications Evaluation Rept for Vermont Yankee ML20247E6351998-04-30030 April 1998 Rev 1 to GE-NE-B13-01935-LTR, Jet Pump Riser Welds Allowable Flaw Sizes Ltr Rept for Vermont Yankee ML20247E6221998-04-30030 April 1998 Final Rept of Rev 0 to 1HQXE, Vynp Unit 1 Recirculation Inlet Riser Ultrasonic Exam A34600, Hydrodynamic Mass & Acceleration Drag Vol of Vermont Yankee ECCS Strainers1998-03-13013 March 1998 Hydrodynamic Mass & Acceleration Drag Vol of Vermont Yankee ECCS Strainers ML20210T5551997-09-10010 September 1997 Addl Benchmarking of BWR Using CASMO-3/SIMULATE-3 ML20210H1111997-07-0707 July 1997 Consequence Evaluation of Vynp Class 1 Piping in Support of ASME Code Case N-560 ML20148D8581997-05-0707 May 1997 Advanced Offgas Follow-up Rept ML20138H3351997-04-28028 April 1997 Tech Specs for Offsite Power ML20138H3081997-04-28028 April 1997 Compliance W/Sbo Regulation ML20107D5951996-04-30030 April 1996 Rev 0 to Vermont Yankee Nuclear Power Station Core Shroud Repair Summary ML20094D8351995-09-22022 September 1995 Method for Power/Flow Exclusion Region Calculation Using LAPUR5 Computer Code ML20086S3141995-07-20020 July 1995 Vynp 1995 Summary Rept for Repairs & Replacements 931001- 950505 ML20086K4581995-06-20020 June 1995 Inside Surface Ultrasonic Technique Capabilities as Demonstrated for Insp of FW Nozzles Final Rept ML20106G5451995-01-17017 January 1995 Investigation of Certain Anonymous Allegations Re Advanced Off-Gas Sys at Vermont Yankee Nuclear Power Station ML20097A5281992-05-29029 May 1992 Rev 1 to Decommissioning Funding Assurance Rept & Certification Submitted Per 10CFR50.33(k)(2),10CFR30.35 & 10CFR50.75,Vermont Yankee Nuclear Power Station ML20101S1261992-05-15015 May 1992 Application to Dispose in Place Contaminated Soil ML20086G4141991-11-0606 November 1991 Emergency Response Exercise Manual 1991 ML20091B2281991-01-31031 January 1991 Simulator Certification Rept,Vermont Yankee Training Dept Jan 1991 ML20247G9901989-06-30030 June 1989 Rev 0 to Vermont Yankee Cycle 14 Core Operating Limits Rept ML20245L1821989-06-30030 June 1989 Method for Generation of One-Dimensional Kinetics Data for RETRAN-02 ML20247G2531989-03-21021 March 1989 Rev 3 to Vermont Yankee Procedure Generation Package ML20151E0111988-07-15015 July 1988 Impact of Alternate Testing on Component & Sys Availability ML20151H9581988-04-30030 April 1988 CASMO-3G Validation ML20154K3351988-04-29029 April 1988 Rept on Containment Safety at Vermont Yankee ML20147G3371988-02-29029 February 1988 Justification for Long-Term Operation for Vermont Yankee Core Spray Nozzle Weld Overlays ML20153H0451987-12-31031 December 1987 Shutdown Assessment of Vermont Yankee Nuclear Power Facility, Interim Rept to State of Vt General Assembly ML20216J6571987-06-25025 June 1987 Dcrdr Summary Rept Suppl for Vermont Yankee Nuclear Power Plant ML20234D8131987-05-31031 May 1987 Cycle 13 Core Performance Analysis ML20206H7331987-03-31031 March 1987 Thermal Effects on Precoat Matl for Spent Fuel Pool Filter/ Demineralizers,Vermont Yankee Nuclear Power Station ML20205Q5421987-03-31031 March 1987 Evaluation of Matl Performance Suitability of New Vermont Yankee Spent Fuel Storage Rack Design ML20207Q3461987-01-12012 January 1987 Justification for Multi-Cycle Operation for Vermont Yankee Core Spray Nozzle Weld Overlays ML20214K6871986-08-31031 August 1986 Vols 1 & 2 to Dcrdr Implementation Task Team Final Rept, Supplementary NRC Matl. W/Two Oversize Encls ML20212Q2731986-08-31031 August 1986 Containment Safety Study ML20204F6001986-07-30030 July 1986 Revised SAR for Vermont Yankee Spds ML20210S2391986-06-25025 June 1986 High Risk:Ge Mark I Pressure-Suppression Design. Public Citizen Press Release Re Natl Coalition of Citizen Groups Petitions NRC to Revoke CPs for New Nuclear Plants Encl ML20203K8191986-04-30030 April 1986 Spent Fuel Storage Rack Replacement Rept ML20204G7371986-04-22022 April 1986 IHSI Weld Package for Vermont Yankee Nuclear Power Station ML20128E4131985-07-0101 July 1985 Dcrdr Summary Rept for Vermont Yankee Nuclear Power Plant ML20128P0891985-05-21021 May 1985 Rept of Investigation Carried Out by Ropes & Gray of Apparent False Documentation of Results of Receipt Insps at Vermont Yankee Nuclear Power Station ML20117A1071985-04-0808 April 1985 Safe Shutdown Capability Analysis ML20154N4811985-01-31031 January 1985 Rev 0 to Mark I Wetwell to Drywell Differential Pressure Load & Vacuum Breaker Response for Vermont Yankee Generation Station ML20101S8291985-01-31031 January 1985 Functional SPDS Sar ML20094M9991984-08-10010 August 1984 Rev 2 to Environ Qualification Master Equipment List 1999-06-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8831999-10-21021 October 1999 Safety Evaluation Supporting Proposed Alternatives to Code Requirements Described in RR-V17 & RR-V18 ML20217G2041999-10-13013 October 1999 Safety Evaluation Supporting Amend 179 to License DPR-28 BVY-99-127, Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With ML20212C2551999-09-17017 September 1999 Safety Evaluation Supporting Amend 175 to License DPR-28 BVY-99-112, Monthly Operating Rept for Aug 1999 for Vermont Yankee.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Vermont Yankee.With BVY-99-109, Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 9908311999-08-19019 August 1999 Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 990831 BVY-99-102, Monthly Operating Rept for July 1999 for Vermont Yankee. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Vermont Yankee. with ML20209J0081999-07-14014 July 1999 Special Rept:On 990615,diesel Driven Fire Pump Failed to Achieve Rated Flow of 2500 Gallons Per Minute.Pump Was Inoperable for Greater than 7 Days.Corrective Maint Was Performed to Reset Pump Lift Setting BVY-99-090, Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With ML20196G5071999-06-23023 June 1999 Vynp Assessment of On-Site Disposal of Contaminated Soil by Land Spreading BVY-99-077, Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With BVY-99-068, Monthly Operating Rept for Apr 1999 for Vynp.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Vynp.With ML20206E8741999-04-29029 April 1999 SER Determined That Flaw Evaluation Meets Rules of ASME Code & Assumed Crack Growth Rate Adequate for Application ML20206D9301999-04-27027 April 1999 1999 Emergency Preparedness Exercise 990427 Exercise Manual (Plume Portion) ML20205S4211999-04-16016 April 1999 Non-proprietary Version of Revised Page 4-3 of HI-981932 Technical Rept for Vermont Yankee Spent Fuel Pool Storage Expansion ML20205K7581999-04-0707 April 1999 Safety Evaluation Supporting Alternative Proposal for Reexamination of Circumferential Welds with Detected Flaw Indications in Plant RPV BVY-99-046, Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With ML20205F6631999-03-0404 March 1999 Jet Pump Riser Weld Leakage Evaluation BVY-99-035, Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With ML20205P8241999-02-28028 February 1999 Rev 2 to Vermont Yankee Cycle 20 Colr ML20203H9881999-02-18018 February 1999 SER Accepting Alternative to 10CFR50.55a(g)(6)(ii)(A) Augmented Reactor Vessel Exam at Vermont Yankee Nuclear Power Station.Technical Ltr Rept Encl ML20203A6951999-02-0404 February 1999 Revised Rev 2,App B to Vermont Yankee Operational QA Manual (Voqam) ML20199K7151999-01-21021 January 1999 Corrected Safety Evaluation Supporting Amend 163 Issued to FOL DPR-28.Pages 2 & 3 Required Correction & Clarification ML20199K6991999-01-20020 January 1999 Safety Evaluation Concluding That Request to Use YAEC-1339, Yankee Atomic Electric Co Application of FIBWR2 Core Hydraulics Code to BWR Reload Analysis, at Vermont Yankee Acceptable ML20199L5951999-01-14014 January 1999 Safety Evaluation Accepting Licensee Proposed Alternative to Code Requirement,Described in Rev 2 to Pump Relief Request RR-P10 Pursuant to 10CFR50.55a(a)(3)(i) BVY-99-071, Corp 1998 Annual Rept. with1998-12-31031 December 1998 Corp 1998 Annual Rept. with BVY-99-001, Monthly Operating Rept for Dec 1998 for Vermont Yankee Nuclear Power Station1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Vermont Yankee Nuclear Power Station ML20198H5481998-12-23023 December 1998 Rev 2 to Vermont Operational QA Manual,Voqam ML20196H8641998-12-0101 December 1998 Cycle 19 Operating Rept BVY-98-163, Monthly Operating Rept for Nov 1998 for Vermont Yankee Nuclear Power Station.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Vermont Yankee Nuclear Power Station.With ML20195C4161998-11-0909 November 1998 SER Accepting Request That NRC Approve ASME Code Case N-560, Alternative Exam Requirement for Class 1,Category B-J Piping Welds BVY-98-154, Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With ML20155B6471998-10-26026 October 1998 Safety Evaluation Accepting Jet Pump Riser Insp Results & Flaw Evaluation,Conducted During 1998 Refueling Outage ML20154N0891998-10-16016 October 1998 Rev 1 to Vermont Operational QA Program Manual (Voqam) ML20154B6951998-10-0101 October 1998 SER Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Vermont Yankee Nuclear Power Station BVY-98-149, Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With ML20239A1361998-09-0202 September 1998 SER Re License Request for NRC Review & Concurrence W/Changes to NRC-approved Fire Protection Program BVY-98-135, Monthly Operating Rept for Aug 1998 for Vermont Yankee Nuclear Power Station.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Vermont Yankee Nuclear Power Station.With ML20151U0361998-08-28028 August 1998 Non-proprietary Rev 1 to Holtec Rept HI-981932, Vermont Yankee Nuclear Power Station Spent Storage Expansion Project ML20237E9221998-08-20020 August 1998 Vynp 1998 Form NIS-1 Owners Summary Rept for ISI, 961103-980603 BVY-98-122, Monthly Operating Rept for July 1998 for Vermont Yankee Nuclear Power Station1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Vermont Yankee Nuclear Power Station ML20205F6491998-07-31031 July 1998 Rev 1 to GE-NE-B13-01935-02, Jet Pump Assembly Welds Flaw Evaluation Handbook for Vermont Yankee ML20236G0011998-06-30030 June 1998 Individual Plant Exam External Events BVY-98-098, Monthly Operating Rept for June 1998 for Vermont Yankee Nuclear Power Station1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Vermont Yankee Nuclear Power Station ML20248C5081998-05-31031 May 1998 Rev 2 to 24A5416, Supplemental Reload Licensing Rept for Vermont Yankee Nuclear Power Station Reload 19 Cycle 20 ML20248C4951998-05-31031 May 1998 Rev 1 to Vermont Yankee Nuclear Power Station Cycle 20 Colr BVY-98-081, Monthly Operating Rept for May 1998 for Vermont Yankee Nuclear Power Station1998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Vermont Yankee Nuclear Power Station ML20247J8341998-05-31031 May 1998 Peak Suppression Pool Temp Analyses for Large Break LOCA Scenarios, for May 1998 ML20247G4001998-05-12012 May 1998 Interview Rept of Ej Massey ML20247E6351998-04-30030 April 1998 Rev 1 to GE-NE-B13-01935-LTR, Jet Pump Riser Welds Allowable Flaw Sizes Ltr Rept for Vermont Yankee 1999-09-30
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Text
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- AN EVALUATION OF THE MATERIAL PERFORMANCE SUITABILITY OF THE NEW VERMONT YANITE SPENT FUEL STORAGE RACK DESIGN By J. R. Hoffman, P.E.
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- BACKGROUND Vermont Yankee is proposing to revise the design of its spent fuel storage racks. The rack design currently in use is an anodized aluminum j structure containing aluminum clad poison material encapsulated in sealed
- cans. The racks are electrically insulated from the stainless steel pool i liner to preclude the possibility of galvanic corrosion.
The new design is fabricated from stainless steel containing aluminum clad poison material in vented cans.
This report will evaluate the suitability of the materials in the new f design for service in the Vermont Yankee spent fuel pool.
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SPENT FUEL POOL ENVIRONMENT The spent fuel pool is nominally pure demineralized water. No special additives are used for chemistry control purposes. The water chemistry l
I control limits are as follows (Reference 1):
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pH 5.8 - 7.5 Conductivity <1.0 micro-mho/cm
! Chloride <500 ppb i Silica <1,000 ppb l Bulk Temperature <150 F MATERIAL PERFORMANCE j The first consideration is suitability of the rack structure for the intended environment. The fuel racks are fabricated from Type 304L stainless i
steel with a controlled maximum carbon content of 0.030 w/o. This material i j has demonstrated outstanding general and localized corrosion resistance in the as-welded condition under the Electric Power Research Institute (EPRI) BWR 1 Alternate Materials Program (Reference (6)). Since the fuel storage pool f environment is considerably less aggressive than the test qualification j conditions, equal or better performance is expected.
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The next consideration is exposure of the poison material to the pool environment. The poison material is a boron carbide matrix clad with Type
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- 1100 aluminum, known by the trademark BORAL. This poison material has been
! -used for many years as a poison material in test reactors. Referende (2) discusses tests performed on BORAL that had been exposed for over 19 years to i
! reactor coolant at the Brookhaven National Laboratory test reactor. No 4-degradation of the BORAL was seen. The surface exposed to the reactor coolant I was covered with a tightly adhering, thin corrosion product.
f Reference (2) also reported the results of testing which exposed BORAL
- for 360 days in water at a pH of 4.1 and 10.4, which brackets the pH range of l the fuel storage pool. No effect due to pH was observed.
Reference (3) reports that corrosion of aluminum is affected by pH, as shown in Figure 1. The Reference (2) results are not necessarily in conflict j with this. It is possible that the corrosion-rate at a pH of.4.1 is sim'ilar j to the rate at a pH of 10.4, both of which are significantly greater than.the f rate at the pH range of the fuel storage pool water.
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1 Reference (4) reports the results of testing and literature research by I
i a manufacturer of similar design fuel storage racks (the rack manufacturer, f Brooks and Perkins, is also the manufacturer of BORAL).
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j The results of this testing are in agreement with-the literature -
)
corrosion at 150 F is negligible.
b a i The vented cavity design results in the BORAL and stainless steel being f
j in contact in the water environment, raising the possibility of galvanic and/or crevice corrosion. This condition was evaluated in Reference (4) at ;
I temperatures as high as 356 F. The reported corrosion rate of the aluminum was 0.1 mils per year. Assuming the thinnest piece of BORAL with the thickest 4
l section of B C matrix, a clad thickness of .007 inches will result. Thus, 4
j the BORAL clad is satisfactory for well over 40 years of life. No corrosion j of the stainless steel was noted.
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- CONCLUSION The general literature and special test reports were reviewed to determine the suitability for service of the Vermont Yankee spent fdel storage racks.
The data show that stainless steel, BORAL, and stainless steel /BORAL couples have been tested in conditions more severe than the fuel storage pool environment with no deleterious effect.
I Weeks, et.al., in Reference 5 report similar finding.
Thus, it is concluded that no technical concerns exist from the standpoint of material serviceability.
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i . Iost solutions contained 1-10 X 10-8 N 1I:02, 68 ppm CaSO., 30 ppm MgSO.,
T '; l 1-2 ppm Nacl (Draley and Ruther). !!!
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( AlO2 -in accord with ! :\
11 Al + NaOH + H2O - NaAIO: + }H: (1) ['
This reaction proceeds rapidly at room temperature, whereas for iron -] j a similar reaction forming NaFeO2and Na:FeO, requires concentrated ti i alkali and high temperatures. 'l i
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Corrosion Characteristics ,'
As mentioned previously, aluminum is characterized by (1) sensitivity to corrosion by alkalies and (2) pronounced attack by traces of Cu ,
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j G . I REFERENCES
- 1. Vermont Yankee Procedure RP-4624, Revision 8 September 29, 1986.
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- 2. General Electric Company Report 78-212-0079, "BORAL From Long-Term Exposure at BNL and Brooks and Perkins," December 14, 1978. '
- 3. Uhlig, Herbert H., Corrosion and Corrosion Control, John Wiley and Sons, 1971.
4 ~. Brooks and Perkins Report No. 577, "The Suitability of Brooks and Perkins Spent Fuel Storage Module for Use in BWR Storage Pool," July 21, 1978.
- 5. Czajkowski, C., J. R. Weeks, and S. R. Potter, " Corrosion of Structural and Poison Material in Spent Fuel Storage Pools." Paper No. 163, National Association of Corrosion Engineers, Corrosion /81 Conference, April 6-10, 1986.
- 6. EPRI NP-2671-LD, " Alternative Alloys for BWR Piping," October 1982.
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APPENDIX A EXCERPT FROM VERMONT YANKEE Procedure RP4624
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. SAWLING A@ TREATWNT OF THE FLEL POOL $YSTEK -- -
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Purpose:
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y' To enable the Chemistry and Health Pnysics' personnel to analyze. and control Fuel Pool chemical parameters, y ,4 i l
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Oiscussion: s
% s Fuel Pool water will be sampled to ?nable a. variety of analyses to be '
performed. Table I .provides a listing of"tne chemical parameters that'will t be monitored, operating limits on the palsmeter, and the governing operating '
a procedure for each.
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The following tables are included's : I
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Table I Fuel Pool Parameters _ . t, s '
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l Table II Precoat Data for Fuel Pool camineralizers ,
References i l .,
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- 1. None 3,. (,
B. Admin. Limits ..
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- 1. See Table I [ l C. Other '~ , ?
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- 1. 0.P. 0630, Water Chemistry
- 2. D.P. 2631, Radiochemical Instrumentation; s
- 3. 0.P. 0640, Chemistry and Health Physics Department Schst:11ng
- 4. D.P. 0641, Procedure for Logging Results of Chemical Analysis ,
- 5. D.P. 0633, Control of Non-Tecn Spec Lab Procedures , . i'; * -r
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- 6. A.P. 6807, Collection and Temporary Storage of @ Records { > N ,
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'} Precautions; q .., /g o I n ...i ",3 m.-
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' l. Appropriate protective clothing should be worn when'. sampling." ,
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( 2. A radiation monitor shou be.NNdduh.ngsahlir.g. ( , j f f ,
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- 3. Avoid spraying Fuel Pool water over the sides of'L% sab5tirsink wnen
! drawing a sangle. '
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, - 'Rzv. 8 j TABLE I FLEL POOL PAR 4ETERS With Aluminum Fuel Pool eter Parameter Equip. In Pool Procedure Domineralizer inlet conductivity at 25'C <1 mo/cm OP 0630 Demineralizer effluent conductivity at 25'C < inlet cond OP 0630 Demineralizer inlet and outlet pH at 25'C Neutral (5.8-7.5) OP 0630 Chloride <0.5 ppm OP 0630 Silica <1 ppm' DP 0633 Heavy Elements (dissolved Fe, Cu, N1) <0.1 ppm OP 0633 Total Solids (insoluble) Influent only <1 ppm DP 0633 Domineralizer activity Effluent < influent OP 2631 Using lab conductivity meter and flow cell, check panel conductivity readings daily.
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APPENDIX B GENERAL ELECTRIC COMPANY Report 78-212-0079 s
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