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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) ML20248F4781998-06-0101 June 1998 Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20198L3331997-12-18018 December 1997 Safety Evaluation Supporting Approval of Proposed Merger of Atlantic Energy,Inc,& Delmarva Power & Light Co ML20198S2161997-10-24024 October 1997 Safety Evaluation Accepting Proposed Change to Provisions Identified in Rev 14 of PBAPS QAP Description Re Nuclear Review Board Meeting Frequency ML20212G8301997-10-24024 October 1997 Safety Evaluation Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively ML20217J5631997-10-0909 October 1997 Safety Evaluation Supporting Amend 225 to License DPR-56 ML20217J6161997-10-0707 October 1997 Safety Evaluation Re Alternative to Reactor Pressure Vessel Circumferential Weld Insps for Plant,Unit 3 ML20211L6241997-10-0303 October 1997 Safety Evaluation Authorizing Licensee Proposed Use of Code Case N-516-1 to Weld Modified Suction Strainer in Suppression Chamber at Plant ML20217D8161997-09-30030 September 1997 Safety Evaluation Supporting Amend 224 to License DPR-56 ML20211D6201997-09-17017 September 1997 SER Accepting VT-2 Examiner Qualification Request for PECO Energy Company,Peach Bottom Atomic Power Station,Units 2 & 3 ML20216G5601997-09-0404 September 1997 Safety Evaluation Supporting Amends 220 & 223 to Licenses DPR-44 & DPR-56,respectively ML20217M8001997-08-19019 August 1997 Safety Evaluation Supporting Amends 219 & 222 to Licenses DPR-44 & DPR-56,respectively ML20149L2841997-07-23023 July 1997 Safety Evaluation Accepting Licensee Relief Request RR-22 for Plant,Units 2 & 3 ISI Program ML20140B0371997-05-30030 May 1997 Safety Evaluation Accepting QAP Description Change ML20135B4111997-02-19019 February 1997 Safety Evaluation Supporting Amends 218 & 221 to Licenses DPR-44 & DPR-56,respectively ML20149L8681996-11-15015 November 1996 SER Accepting Core Spray Piping Insp & Flaw Evaluation for Plant,Unit 2 ML20149L2441996-01-29029 January 1996 Safety Evaluation Accepting Insp & Evaluation Methodology for Operation of Unit 3 Core Shroud for Duration of Current Operating Cycle,Performed in Response to GL 94-03 ML20058F5641993-11-19019 November 1993 SE Accepting Util 930305 Response to NRC Bulletin 90-01, Suppl 1, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20057B6441993-09-16016 September 1993 SER Concluding That Safe Shutdown Capability at Plant, Satisfies Requirements of Section Iii.G & Iii.L of App R to 10CFR50 ML20126H9031992-12-23023 December 1992 Safety Evaluation Granting Relief from Inservice Insp Requirements for Facilities ML20127N4941992-11-17017 November 1992 Safety Evaluation Accepting Util 120-day Response to Suppl 1 to GL 87-02 ML20062C7501990-10-26026 October 1990 Safety Evaluation Re Evaluation of Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow ML20246E0331989-08-21021 August 1989 SER Supporting Util Response to Generic Ltr 83-28,Item 2,1 (Parts 1 & 2).Programs Exist for Identifying safety-related Components Required for Reactor Trip Function & Vendor Interface W/Nmss Vendor for Required Components ML20205A8801988-10-31031 October 1988 Safety Evaluation of Util Plan for Restart of Peach Bottom Atomic Power Station ML20148P3351988-04-0101 April 1988 SER Accepting Util Responses to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Program for All safety-related Components ML20148E6301988-01-15015 January 1988 SER Accepting Util 840116,0927 & 850805 Responses to Generic Ltr 82-33,Item 6 Re Compliance w/post-accident Monitoring Instrumentation Guidelines of Reg Guide 1.97 Concerning Emergency Response Facilities ML20236D0541987-10-22022 October 1987 Safety Evaluation Supporting Util Repts on Computer Program Analyses Methods Intended for Use in Part of Plant Core Reload Analyses ML20235D2431987-09-22022 September 1987 Safety Evaluation Re Proposed Onsite Storage of Liquid Oxygen & Hydrogen for Implementation of Hydrogen Water Chemistry.Permanent Hydrogen Water Installation Acceptable ML20209H0201987-04-24024 April 1987 Safety Evaluation Supporting Util Re Torus Attached Piping Mods - Mark I Program ML20204C1001986-07-24024 July 1986 Safety Evaluation Supporting Listed Util Responses & Actions Reviewed During Insp on 840913-19 Re Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 ML20141F6071986-04-0808 April 1986 Safety Evaluation Granting Util Requests for Relief from Inservice Insp Requirements of ASME Code,Section XI ML20209C3141986-03-20020 March 1986 Safety Evaluation Supporting Shroud Head Connection Replacement at Facility,Per Util 860107 Submittal 1999-09-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20151Y2901998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbaps,Units 2 & 3. with ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 ML20237B9531998-08-10010 August 1998 Specification for ISI Program Third Interval,Not Including Class Mc,Primary Containment for Bpaps Units 2 & 3 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20237A5351998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pbaps,Units 2 & 3 ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) ML20236M3471998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbaps,Units 2 & 3 ML20249C4791998-06-0202 June 1998 Rev 6 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20248F4781998-06-0101 June 1998 Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20248M3001998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pbaps,Units 2 & 3 ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20249C4751998-05-0707 May 1998 Rev 5 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20247G0721998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Pbaps,Units 2 & 3 1999-09-30
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ENCLOSURE y
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO HYDROGEN WATER CHEMISTRY IMPLEMENTATION I PHILADELPHIA ELECTRIC COMPANY I DOCKET NUMBER 50-277 AND 50-278
1.0 INTRODUCTION
By letters dated May 27 and August 24, 1987, the licensee submitted the safety evaluation for the storage of liquid hydrogen and oxygen and additional information relating to the implementation of hydrogen water chemistry for review and approval.
2.0 EVALUATION The BWR Owner's Group submitted " Guidelines for Permanent BWR Hydrogen Water Chemistry Installations," 1987 Revision (hereafter referred to as the Guidelines), for staff review. By letter from James E. Richardson, NRC, dated July 13, 1987 to G. H. Neils, BWR Owners Group II for Intergranular Stress Corrosion Cracking Research, the staff accepted the Guidelines for referencing in licensee requests for approval of a permanent hydrogen water chemistry facility. The licensee states that the liquid hydrogen and oxygen storage and injection systems are sited, designed and installed in accordance with the recommendations provided in the Guidelines.
2.1 Liquid Hydrogen Storage The liquid hydrogen storage tank, with a maximum capacity of 20,000 gallons of cryogenic liquid at approximately 100 psig and -425'F, will be located 1180 feet away from the nearest safety-related structure, which is the plant stack. The next nearest safety related structure is the Unit 3 reactor building, which is 1700 feet away. The system also incorporates provisions for temporary gaseous hydrogen supply via trucks. In the unlikely event of an explosion of the tank containing 20,000 gallons of cryogenic hydrogen, the peak positive reflected overpressure at the plant stack and Unit 3 reactor building were calculated by the staff to be 1.5 psi and 2.5 psi respectively.
The fireball diameter, duration and thermal flux (Unit 3 reactor bui wascalculatedbythestafftobe20 feet,5.2secondsand1.44Kw/m} ding) respectively. The hydrogen storage area is in conformance with the Guidelines in that there is sufficient separatici distance from safety-related structures so that the thermal flux from the burring gas fire-ball or the blast overpressure from hydrogen explosion vill not ause failure of the safety-related structures. For small liquid hydrogen releases, Figure 4-7 from the Guidelines indicates that for the nearest safety-related structure air intake (1180 feet), the flannability limit would be exceeded at a leakage rate in excess of 1.1 kg/sec (liquid hydrogen piping hole size of 0.44 inches diameter). Based on the above, liquid hydrogen piping design should be either (1) totally seismically supported; (2) seismically designed and supported up to and including a structural anchor downstream of excess flow check valves; or (3) seismically supported up to and including a structural anchor downstream 8709250167 870922 PDR ADOCK 05000277 P PDR
of a flow limiting device which restricts flow to less than 1.1 kg/sec to prevent the intake of flammable concentrations of hydrogen into safety-related air intakes.
The licensee utilized option (2) above which is acceptable.
2.2 Liquid Oxygen Storage The liquid oxygen storage tank, with a maximum capacity of 11,000 approximately above grade)y 150 psig and -300 F, will be located 260 feet39away feet (gallons at from the nearest safety-related air intakes, which is the electromechanical equipment room and cooling tower air intake. The next nearest safety-related air intake is the reactor building HVAC.
also incorporates provisions for temporary oxygen supply by truck.TheFigure system 4.8 of the Guidelines indicates that the oxygen concentration at the nearest safety-related air intake will be less than 30 volume % should failure of the liquid oxyger. tank result in instantaneous vaporization of the liquid oxygen. At concentrations ignitable materials of less willthan not 30 volume % oxygen the effective combustibility of increase.
facility is acceptable. Therefore, the liquid oxygen storage 2.3 Hydrogen Injection System Hydrogen gas from the storage site is delivered at approximately 1000 psig to Units 2 and 3 where it is injected uniformly into the suction piping of the three reactor feed pumps in each Unit.
The supply line to the existing hydrogen storage tubes for generator cooling ties into the systems fill line.
The reactorhydrogen flow rate will be approximately 60 scfm into the suction of the feed pumps.
socket weld fittings. The hydrogen piping is stainless steel, schedule 160, with The distribution piping from the hydrogen storage tank to the turbine building building is 3/4 inch in size. is one inch while the injection pipe inside the turbine following. The injection of hydrogen is tripped by the SCRAM High area hydrogen concentration / area temperature Offgas oxygen concentration High hydrogen injection flowrate Less than 20% power Low hydrogen injection pressure Operator request The major safety features of the system include:
Area Hydrogen Concentration / Temperature Monitors
I 3
Vent / Purge System with External Flame Arrestors Low Pressure Hydrogen Isolation Excess Flow Check Valves Hydrogen Isolation Spool Pieces for Maintenance Use ,
Zero-Leakage Bellows Seal Hydrogen Valves The area hydrogen monitors are located in seven hydrogen collection shrouds which contain injection system components that may leak (e.g., valves, instruments, spool pieces, etc.). When hydrogen concentrations exceed 2%
(lower flammability limit is 4%), an alarm is annunciated in the main control :
room. The injection system is automatically shut off at 3% hydrogen. All instruments within the shrouds are of explosion proof design. Temperature monitors are also included in the shroud to isolate the system in the event nf an ignited hydrogen leak. Excess flow check valves are located outdoors in the l common supply header and indoors on each unit's distribution piping. Each excess flow check valve will isolate the hydrogen distribution system if the flowrate is 150 percent of the normal flowrate passing through it. As an added precaution no hydrogen injection piping will be routed in safety-related structures or areas containing safety-related equipment.
The hydrogen injection system meets the Guidelines by providing maximum system integrity, early detection of hydrogen leaks, excess flow protection and automatic system shutdown if a failure is detected.
2.4 0xygen Injection System Oxygen gas is delivered at approximately 100 psig to the injection point on the off-gas system preheater inlet piping to the recombiner. The oxygen flow is proportional to hydrogen flow (ratio is approximately 1:2) and a final adjustment is made based on off-gas excess oxygen. Hydrogen water chemistry suppresses oxygen in the reactor coolant and also reduces the oxygen in the condensate /feedwater. Oxygen is also' injected into the suction piping of the "B" condensate pump to maintain recommended dissolved oxygen levels of 20-60 ppb for feedwater pipe corrosion control. The oxygen flow to the condensate pump suction will be automatically isolated on low condenser vacuum.
The oxygen piping is copper with brazed fittings. The distribution piping from the oxygen storage facility to the turbine building is one and a half inch diameter (0.075 inch wa'". thickness) while the feed pump injection piping inside the turbine building is 1 inch in size (0.065 inch wall thickness). The condensate injection piping is half inch in diameter (0.065 inch wall thickness).
Following a trip of the hydrogen injection system the flow of oxygen to the recombiner will be held constant for a short time to permit hydrogen and oxygen carryover to return to a stoichiometric ratio.
t-
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~4-Since oxygen supports combustion, an excess flow check valve is installed in the oxygen injection line to shut off oxygen flow should an oxygen line break or leak occur. This will reduce oxygen concentrations and limit the spread of potential fires. Oxygen injection lines are not run through areas housing safety related equipment. The oxygen injection system meets the Guideline recommendations.
2.5 Radiation protection The staff has reviewed the licensee's submittal regarding the radiological implications of the dose rate increases associateu with_N-16 activity increases during hydrogen injections into the reactor system. The review addresses the radiation protection /ALARA measures for hydrogen water chemistry, in accordance with 10 CFR 20.1(c) and Regulatory Guide 8.8, "Information Relevant to Ensuring the Occupational Radiation Exposures at Nuclear Power Stations Will be as Low as is Reasonably Achievable." (ALARA)
One objective of the hydrogen water chemistry program is to determine general in-plant and site boundary dose rate increases due to hydrogen addition. The licensee has stated that radiation protection /ALARA practices will be implemented. Additionally, the licensee has stated that data will be obtained for shielding design should additional shielding be necessary.
The increased dose rate due to higher N-16 activity levels will result in an increase in site dose rate during operation with hydrogen water chemistry.
The increased dose will be primarily to non-radiation workers located in the administration building and other support structures but not to workers in the plant. Hydrogen injection can be turned off for as much as eight hours, resulting in a rapid decrease in N-16 activity levels, without losing the IGSCC mitigation benefits. During the hydrogen injection shutdown time, work can be performed in areas, such as near the turbine, at reduced N-16 dose rates.
Radiation protection practices implemented for hydrogen water chemistry operation will ensure ALARA in accordance with Regulatory Guide 8.8 and are, therefore, acceptable.
2.6 Fuel Surveillance The licensee plans to implement a fuel surveillance program as suggested in Section 6.1.5 of the Guidelines. Four fuel bundles containing pre-characterized Zircaloy fuel components will be inserted at the start of the first cycle under hydrogen water chemistry. These pre-characterized fuel bundles shall be inspected following each of the first three fuel cycles under hydrogen water chemistry for unexpected corrosion of deposits which could be related to hydrogen water chemistry. Normal fuel performance has been experienced at Dresden-2 since the implementation of hydrogen water chemistry in 1983.
2.7 Water Chemistry Contro_1 Integranular stress corrosion cracking can be mitigated by suppressing the dissolved oxygen concentration by hydrogen injection and traintaining high purity in the reactor coolant. This process, referred to as hydrogen water
I ,
l chemistry, requires the attainment of two parameters: The electrochemical corrosion potential of stainless steel must be less than -230my, Standard Hydrogen Electrode (SHE) and the water conductivity must be less than 0.3 micro Siemens per centimeter at 25 C. The licensee will have a policy statement and implementing corporate procedure for commitment to the BWROG Guidelines for Hydrogen Water Chemistry by the end of 1987.
2.8 Site Visit The staff visited the Peach Bottom Statien on August 11, 1987 to review the design and installation of the hydrogen water chemistry facility. Discussions were conducted to clarify information submitted by the licensee for incorpora-tion into this safety evaluation. System drawings and layouts were reviewed.
Finally, the tour of the hydrogen water chemistry facility was beneficial in verifying the staff's evaluation. The following areas were looked at:
liquid hydrogen storage facility liquid oxygen storage facility hydrogen injection system crack arrest verification system and electrochemical potential monitor hydrogen water chemistry control panel in main control room.
The site visit supports the staff's conclusion that the hydrogen water chemistry system is acceptable.
3.0 CONCLUSION
S On the basis of the above evaluation, the staff finds that the proposed changes and hydrogen water chemistry installation are in accordance with the BWROG (1987 Revision) " Guidelines for Permanent Hydrogen Water Chemistry Installations."
Since the staff has accepted the Guidelines for referencing in licensee requests for a permanent hydrogen water chemistry installation ( NRC letter to G. H.
Neils dated July 13,1987), the proposed changes are acceptable.
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