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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20209H5051999-07-14014 July 1999 Proposed Tech Specs Pages 3.1-15 & 3.1-17 of Table 3.1.1 ML20209E0951999-07-0707 July 1999 Proposed Tech Specs,Changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20212H5441999-06-18018 June 1999 Proposed Tech Specs Reflecting Installation of Addl SFP Storage Racks That Will Accommodate Increase in Spent Fuel Assemblies Beyond Existing Storage Capacity of SFP as Described in Licensing Rept ML20195D0761999-06-0303 June 1999 Proposed Tech Specs,Permitting Plant Operation with Three Operable Recirculation Loops ML20205P8531999-04-15015 April 1999 Proposed Tech Specs,Modifying Number of Items in Sections 2 & 3 of Tss,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4 ML20198K0671998-12-23023 December 1998 Proposed Tech Specs Pages 3.8-2 & 4.8-1,changed to Specify Surveillance Frequency of Once Per Three Months ML20195C6561998-11-10010 November 1998 Proposed Tech Specs Section 5.1.A,removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7501998-11-0505 November 1998 Proposed Tech Specs,Modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20151V5091998-09-0303 September 1998 Proposed Tech Specs 3.4.A.10.e & 3.5.A.2.e Re Condensate Storage Tank Level ML20237D9591998-08-21021 August 1998 Proposed Tech Specs Removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 ML20237B2221998-08-0606 August 1998 Proposed Revised Tech Specs Pages for Change Request 205,dtd 961031,correcting Minor & Inadvertent Editorial Changes in Locations Where Changes Have Not Been Proposed ML20236T1211998-07-23023 July 1998 Proposed Tech Specs Pages for Amend to License DPR-16,to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17) ML20236T4981998-07-21021 July 1998 Proposed Tech Specs Re Reactivity Control ML20236T4811998-07-21021 July 1998 Proposed Tech Specs Re Changes to Administrative Controls ML20236J1431998-06-30030 June 1998 Proposed Tech Specs,Consisting of Revised Page 3-5 Re RPV Pressure/Temp Limits ML20236H2181998-06-29029 June 1998 Proposed Tech Specs,Modifying EDG Insp Requirement Previously Submitted in Entirety ML20248K2851998-05-28028 May 1998 Proposed Tech Specs Re That Such First Type a Test Required by Primary Containment Leakage Rate Testing Program Be Performed During Refueling Outage 18R ML20197G2771997-12-23023 December 1997 Proposed Tech Specs Reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station ML20197J2561997-12-10010 December 1997 Proposed Tech Specs Changing Pages 2.3-6,2.3-7,3.1-11, 3.1-14,3.1-16,3.4-8,3.8-2,3.8-3,4.3-1,4.5-13 & 6-1 ML20210L3311997-08-15015 August 1997 Proposed Tech Specs,Incorporating Note Which Indicates That Proposed Change to SL Mcrp Applicable for Current Operating Cycle (Cycle 16) Only ML20135C2001996-11-27027 November 1996 Proposed Tech Specs Pages 4.7-1,4.7-2,4.7-3 & 4.7-4 Re Surveillances for Station Batteries ML20129K3401996-11-12012 November 1996 Proposed Tech Specs,Consisting of Change Request 224, Implementing Revised 10CFR20, Stds for Protection Against Radiation Effective 910620 ML20134H0541996-10-31031 October 1996 Proposed Tech Spec,Requesting Deletion of Table 3.5.2 ML20129C0691996-10-10010 October 1996 Proposed Tech Specs,Clarifying Functional Requirement to Provide Interlock Permissive Which Ensures Source of Cooling Water Available Via Core Spray Sys Prior to Depressurization ML20129A5731996-10-10010 October 1996 Proposed Tech Specs,Revising Addl Group of Surveillances Where Justification Completed Following Receipt of Amend 144 ML20134F4101996-10-0404 October 1996 Proposed Tech Specs 2.1.A & 3.10.C to Reflect Change in SLMCPR & Revise Operating CPR Limit for Stability, Respectively ML20117E7061996-08-23023 August 1996 Proposed Tech Specs,Proposing New pressure-temp Limits Up to 22,27 & 32 EFPY Based on Predicted Nilductility Adjusted Ref Temp for Corrresponding EFPY of Operation ML20115G2101996-07-17017 July 1996 Proposed Tech Specs,Allowing Implementation of 10CFR,App J, Option B ML20113A8641996-06-19019 June 1996 Proposed Tech Specs Table of Contents,1.24 Re Footnote to definition,1.25 Re Definition,Section 3.5.A.3b Re Containment,Section 4.5 Re Containment,Bases for Section 4.5 & Section 6.9.3.b Re Reporting Requirements ML20111A3841996-05-0707 May 1996 Proposed Tech Specs,Adopting Provisions of STS NUREG-1433, Rev 1,dtd 950407,Sections SR 3.0.1,3.0.3 & Associated Bases ML20107E7751996-04-15015 April 1996 Proposed Tech Specs 5.3.1 Re Handling Heavy Loads Over Irradiated Fuel ML20101J7681996-03-28028 March 1996 Proposed Tech Specs,Modifying Statements in TS & Bases to Correctly Reflect Ref Parameter for Anticipatory Scram Signal Bypass ML20101J6091996-03-25025 March 1996 Proposed Tech Specs,Deleting Spec Which Requires Thorough Insp of EDG Every 24 Months During Shutdown ML20100J9151996-02-23023 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20100H9971996-02-22022 February 1996 Proposed Tech Specs 3.7-1,3.7-2,4.7-1 & 4.7-2 Re Deletion of TS Requirement to bi-annually Inspect EDG & Mod of Spec Re AOT ML20095C1031995-12-0505 December 1995 Proposed Tech Specs Re Rev of Submittal Date for Annual Exposure Data Rept Bringing Plant Into Conformance w/10CFR20.2206 & Relaxing Overly Restrictive Administrative Requirement ML20086A7161995-06-26026 June 1995 Proposed Tech Specs Re Performance of Reactor Shutdown & Drywell to Inspect Snubbers in Svc for Only 12 Months ML20080P6501995-02-28028 February 1995 Proposed Tech Specs Change Request 225 Re Change to Page 6-4 of Tech Spec Section 6.5.1.12.Change Consistent w/NUREG-1433,STSs General Electric Plants,BWR/4,Rev 0,dtd 920928 ML20078N3791995-02-0808 February 1995 Proposed Tech Specs Re Oyster Creek Spent Fuel Pool Expansion ML20078Q6481994-12-15015 December 1994 Revised TS & Bases Pages to Section 3.1 of TS Change Request 191 ML20078M1431994-11-25025 November 1994 Proposed TS 5.3.1.E,allowing 2,645 Fuel Assemblies to Be Stored in Fuel Pool ML20072S2921994-09-0202 September 1994 Proposed Tech Specs Supporting Rev of APRM Channel Calibr Interval from Weekly to Quarterly ML20072L4741994-08-19019 August 1994 Proposed Tech Specs Control Rod Exercising & Standby Liquid Control Pump Operability Testing ML20070E3411994-07-0808 July 1994 Proposed Tech Specs Re Improved Protection to Safety Related Electrical Equipment from Loss of Capability ML20078A7731994-06-24024 June 1994 Proposed Tech Specs Reflecting Removal of Recirculation Flow Scram ML20069M8231994-06-15015 June 1994 Proposed Tech Spec 2.3.D, Reactor High Pressure,Relief Valve Initiation ML20070R5261994-05-12012 May 1994 Proposed TS Sections 3.1 & 4.1 for Protective Instrumentation ML20029E0451994-05-0606 May 1994 Proposed Tech Specs Clarifying Requirements for Demonstrating Shutdown Margin ML20065M9991994-04-19019 April 1994 Proposed Tech Specs Updating & Clarifying TS 3.4.B.1 to Be Consistent W/Existing TS 1.39 & 4.3.D Re Five Electromatic Relief Valves Pressure Relief Function Inoperable or Bypassed During Sys Pressure Testing ML20029C7571994-04-15015 April 1994 Proposed TS Change Request 215,deleting Audit Program Frequency Requirements from TS 6.5.3 & Utilize Operational QA Plan as Controlling Document 1999-07-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212B5741999-09-0505 September 1999 Rev 11 to 2000-ADM-4532.04, Oyster Creek Emergency Offsite Dose Calculation Manual ML20209H5051999-07-14014 July 1999 Proposed Tech Specs Pages 3.1-15 & 3.1-17 of Table 3.1.1 ML20209E0951999-07-0707 July 1999 Proposed Tech Specs,Changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20212H5441999-06-18018 June 1999 Proposed Tech Specs Reflecting Installation of Addl SFP Storage Racks That Will Accommodate Increase in Spent Fuel Assemblies Beyond Existing Storage Capacity of SFP as Described in Licensing Rept ML20195D0761999-06-0303 June 1999 Proposed Tech Specs,Permitting Plant Operation with Three Operable Recirculation Loops ML20205P8531999-04-15015 April 1999 Proposed Tech Specs,Modifying Number of Items in Sections 2 & 3 of Tss,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4 ML20198K0671998-12-23023 December 1998 Proposed Tech Specs Pages 3.8-2 & 4.8-1,changed to Specify Surveillance Frequency of Once Per Three Months ML20195C6561998-11-10010 November 1998 Proposed Tech Specs Section 5.1.A,removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7501998-11-0505 November 1998 Proposed Tech Specs,Modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20151V5091998-09-0303 September 1998 Proposed Tech Specs 3.4.A.10.e & 3.5.A.2.e Re Condensate Storage Tank Level ML20237D9591998-08-21021 August 1998 Proposed Tech Specs Removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 ML20237B2221998-08-0606 August 1998 Proposed Revised Tech Specs Pages for Change Request 205,dtd 961031,correcting Minor & Inadvertent Editorial Changes in Locations Where Changes Have Not Been Proposed ML20236T1211998-07-23023 July 1998 Proposed Tech Specs Pages for Amend to License DPR-16,to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17) ML20236T4811998-07-21021 July 1998 Proposed Tech Specs Re Changes to Administrative Controls ML20236T4981998-07-21021 July 1998 Proposed Tech Specs Re Reactivity Control ML20236J1431998-06-30030 June 1998 Proposed Tech Specs,Consisting of Revised Page 3-5 Re RPV Pressure/Temp Limits ML20236H2181998-06-29029 June 1998 Proposed Tech Specs,Modifying EDG Insp Requirement Previously Submitted in Entirety ML20248K2851998-05-28028 May 1998 Proposed Tech Specs Re That Such First Type a Test Required by Primary Containment Leakage Rate Testing Program Be Performed During Refueling Outage 18R ML20197G2771997-12-23023 December 1997 Proposed Tech Specs Reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station ML20197J2561997-12-10010 December 1997 Proposed Tech Specs Changing Pages 2.3-6,2.3-7,3.1-11, 3.1-14,3.1-16,3.4-8,3.8-2,3.8-3,4.3-1,4.5-13 & 6-1 ML20210L3311997-08-15015 August 1997 Proposed Tech Specs,Incorporating Note Which Indicates That Proposed Change to SL Mcrp Applicable for Current Operating Cycle (Cycle 16) Only ML20135C2001996-11-27027 November 1996 Proposed Tech Specs Pages 4.7-1,4.7-2,4.7-3 & 4.7-4 Re Surveillances for Station Batteries ML20129K3401996-11-12012 November 1996 Proposed Tech Specs,Consisting of Change Request 224, Implementing Revised 10CFR20, Stds for Protection Against Radiation Effective 910620 ML20134H0541996-10-31031 October 1996 Proposed Tech Spec,Requesting Deletion of Table 3.5.2 ML20129C0691996-10-10010 October 1996 Proposed Tech Specs,Clarifying Functional Requirement to Provide Interlock Permissive Which Ensures Source of Cooling Water Available Via Core Spray Sys Prior to Depressurization ML20129A5731996-10-10010 October 1996 Proposed Tech Specs,Revising Addl Group of Surveillances Where Justification Completed Following Receipt of Amend 144 ML20134F4101996-10-0404 October 1996 Proposed Tech Specs 2.1.A & 3.10.C to Reflect Change in SLMCPR & Revise Operating CPR Limit for Stability, Respectively ML20117E7061996-08-23023 August 1996 Proposed Tech Specs,Proposing New pressure-temp Limits Up to 22,27 & 32 EFPY Based on Predicted Nilductility Adjusted Ref Temp for Corrresponding EFPY of Operation ML20115G2101996-07-17017 July 1996 Proposed Tech Specs,Allowing Implementation of 10CFR,App J, Option B ML20113A8641996-06-19019 June 1996 Proposed Tech Specs Table of Contents,1.24 Re Footnote to definition,1.25 Re Definition,Section 3.5.A.3b Re Containment,Section 4.5 Re Containment,Bases for Section 4.5 & Section 6.9.3.b Re Reporting Requirements ML20111A3841996-05-0707 May 1996 Proposed Tech Specs,Adopting Provisions of STS NUREG-1433, Rev 1,dtd 950407,Sections SR 3.0.1,3.0.3 & Associated Bases ML20107E7751996-04-15015 April 1996 Proposed Tech Specs 5.3.1 Re Handling Heavy Loads Over Irradiated Fuel ML20101P1561996-03-31031 March 1996 Rev 9 to Oyster Creek Nuclear Generating Station Pump & Valve IST Program ML20101J7681996-03-28028 March 1996 Proposed Tech Specs,Modifying Statements in TS & Bases to Correctly Reflect Ref Parameter for Anticipatory Scram Signal Bypass ML20101J6091996-03-25025 March 1996 Proposed Tech Specs,Deleting Spec Which Requires Thorough Insp of EDG Every 24 Months During Shutdown ML20100J9151996-02-23023 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20100H9971996-02-22022 February 1996 Proposed Tech Specs 3.7-1,3.7-2,4.7-1 & 4.7-2 Re Deletion of TS Requirement to bi-annually Inspect EDG & Mod of Spec Re AOT ML20095C1031995-12-0505 December 1995 Proposed Tech Specs Re Rev of Submittal Date for Annual Exposure Data Rept Bringing Plant Into Conformance w/10CFR20.2206 & Relaxing Overly Restrictive Administrative Requirement ML20086A7161995-06-26026 June 1995 Proposed Tech Specs Re Performance of Reactor Shutdown & Drywell to Inspect Snubbers in Svc for Only 12 Months ML20080P6501995-02-28028 February 1995 Proposed Tech Specs Change Request 225 Re Change to Page 6-4 of Tech Spec Section 6.5.1.12.Change Consistent w/NUREG-1433,STSs General Electric Plants,BWR/4,Rev 0,dtd 920928 ML20078N3791995-02-0808 February 1995 Proposed Tech Specs Re Oyster Creek Spent Fuel Pool Expansion ML20078Q6481994-12-15015 December 1994 Revised TS & Bases Pages to Section 3.1 of TS Change Request 191 ML20078M1431994-11-25025 November 1994 Proposed TS 5.3.1.E,allowing 2,645 Fuel Assemblies to Be Stored in Fuel Pool ML20073F9501994-09-26026 September 1994 Revised Plan for Long Range Planning Program for Oyster Creek Nuclear Generating Station ML20073F9411994-09-26026 September 1994 Revised Plan for Long Range Planning Program for TMI Nuclear Station Unit 1 ML20072S2921994-09-0202 September 1994 Proposed Tech Specs Supporting Rev of APRM Channel Calibr Interval from Weekly to Quarterly ML20072Q4251994-08-20020 August 1994 Rev 0 to Oyster Creek Nuclear Generating Station Sea Turtle Surveillance,Handling & Reporting Instructions for Operations Personnel ML20072L4741994-08-19019 August 1994 Proposed Tech Specs Control Rod Exercising & Standby Liquid Control Pump Operability Testing ML20070J7971994-07-31031 July 1994 Rev 8 to Oyster Creek Nuclear Generating Station Pump & Valve Inservice Testing Program ML20070E3411994-07-0808 July 1994 Proposed Tech Specs Re Improved Protection to Safety Related Electrical Equipment from Loss of Capability 1999-09-05
[Table view] |
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.0YSTER CREEK NUCLEAR GENERATING STATION (DOCKET NO. 50-219)
. -~ PROVISIONAL OPERATING LICENSE NO. DPR-16 Applicant hereby requests the Commission to amend Appendix A to the above captioned license.
l .- Section to be changed 3.3.E. Reactor Coolant Quality.(Page 3.3-2).
' 2 .- Change requested E. Reactor Coolant Quality
- 1. The reactor coolant quality during power operation with steaming rates to the-turbine-condenser of less than 100,000 pounds per hour shall be limited to:
conductivity 2 US/cm chloride ion 0.1 ppm
- 2. When the conductivity and chloride concentration limits given in 3.3.E.1 are exceeded, an orderly shutdown shall be initiated immediately, and the reactor coolant temperature shall be reduced to less than 212*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 3. The reactor coolant quality during power operation with steaming rates to the turbine-condenser of greater than or equal to 100,000 pounds per hour shall be limited to:
conductivity 10 uS/cm chloride ton 0.5 ppm
- 4. When the maximum conductivity or chloride concentration limits given in 3.3.E.3 are exceeded, an orderly shutdown shall be initiated immediately, and the reactor coolant temperature shall be reduced to less than 212*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 5. During power operation with steaming rates to the turbine-condenser of greater than or equal to 100,000 pounds per hour, the time limit above 1.0 uS/cm at 25*C (77'F) and 0.2 ppm chloride shall not exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for any single incident.
- 6. ..
'When the time limits for 3.3.E.5 are exceeded, an orderly shutdown shall be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- 3. Discussion:
During the integrated assessment of the SEP topics, the NRC staff indicated that Oyster Creek Technical Specifications have no provisions for the time-related conductivity limit and the current licensing criterion is a long-term limit of I uS/cm for power operation.
ONN9 PDR
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- ).
OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE N0. OPR-16 DOCKET NO. 50-219 Pursuant to 10CFR50.91, an analysis concerning significant hazards consideration is provided below:
- 1. Section to be changed:
3.3.E. - Reactor Coolant Quality (Page 3.3-2).
- 2. Extent of change:
- Revise Section 3.3.E. of the Oyster Creek Technical Specification to incorporate the conductivity and chloride limits given in Regulatory Guide 1.56.
- 3. Discussion:
Examples of amendments that are considered not likely to involve significant hazards considerations were provided in the Federal Register on April 6,1983(48FR14870). Revision of Section 3.3.E of
, the Oyster Creek Technical Specifications is within the provisions of example (ii) (as referenced above) in that the change constitutes an additional limitation, restriction, or control not presently included in the technical specifications.
- 4. Determination:
We have determined that the subject change request involves no significant hazards in that operation of the Oyster Creek Nuclear Generating Station in accordance with Technical Specification Change Request No. 124 would not:
- 1. Involve a significant increase in the probabil-ity or consequence of an accident previously evaluated; or 2r Create the possibility of a new or different kind of accident from any previously evaluated; or
- 3. Involve a significant reduction in a margin of safety.
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O ' J' 3.3-2 D. Reactor Coolant System Leakage Reactor coolant leakage.into the primary containment from unidentified sources shall not exceed 5 gpm. In addition, the total leakage in the ,
containment, identified and unidentified, shall not exceed 25 gpm. If these conditions cannot be met, the reactor will be placed in-the cold shutdown condition.
E. Reactor Coolant Quali ty
- 1. The reactor coolant quality during power operation with steaming rates to the turbine-condenser of less than 100,000 pounds per hour shall be limited to:
conductivity 2 US/cm chloride ton 0.1 ppm
- 2. When the conductivity and chloride concentration limits given in 3.3.E.1 are exceeded, an orderly shutdown shall be initiated immediately, and the reactor cociant temperature shall be reduced to less than 212"F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 3. The reactor coolant quality during power operation with steaming rates to the turbine-condenser of greater than or equal to 100,000 pounds per hour shall be limited to:
conductivity 10 uS/cm chloride ton 0.5 ppm
- 4. When the maximum conductivity or chloride concentration limits given in 3.3.E.3 are exceeded, an orderly shutdown shall be initiated immediately, and the reactor shall be reduced to less than 212*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 5. During power operation with steaming rates to the turbine-condenser of greater-than or equal to 100,000 pounds per hour, the time limit above 1.0 US/cm at 25*C (77'F) and 0.2 pom chloride shall not exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for any single incident.
- 6. When the time limits for 3.3.E.5 are exceeded, an orderly shutdown shall be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
F. Recirculation Loop Operability
- 1. The'7eactor shall not be operated with one or more recirculation loops out of service except as specified in Specification 3.3.F.2.
- 2. Reactor Operation with one idle recirculation loop is permitted provided that the idle loop is not isolated from the reactor vessel.
- 3. If Specifications 3.3.F.1 and 3.3.F.2 are not met, the reactor shall be placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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-t 3.3-6
._ Chlorides are known to (1) promote intergranular stress corrosion cracking of sensitized stainless steels, (2) induce
'transgranular promote pittingcracking)of non-sensitized and (4 promote stainless crevice attack in moststeels, RCS (3) materials (BWR Water Chemistry Guidelines, EPRI, April 1, 1984). The higher the concentration, the faster the attack.
Therefore, the level of chloride in the reactor water should be kept as low as is practically achievable. The limits-are therefore set to be consistent with Regulatory Guide 1.56 (Rev. 1.)
'In the case of BWR's where no additives are used in the primary coolant, and where neutral pH is maintained, conductivity provides a very good measure of the quality of
~the reactor water. When the conductivity is within its proper normal range, pH, chloride, and other impurities affecting conductivity and water quality must also be within their normal ranges. Significant changes in conductivity provide the operator with a warning mechanism so that he can-investigate and remedy the conditions causing the change.
Measurements of pH, chloride, and other chemical parameters are made to determine the cause of the unusual conductivity and instigate proper corrective action. These can be done before limiting conditions, with respect to variables affecting the boundaries of the reactor coolant, are exceeded.- Several techniques are available to correct off-standard reactor water quality conditions including removal of impurities from reactor water by the cleanup system, reducing input of impurities causing off-standard conditions by reducing power and reducing the reactor coolant.
temperature to less than 212*F. The major _ benefit of reducing the reactor coolant temperature to less than 212*F is to reduce the temperature dependent corrosion rates and thereby provide time for the' cleanup system to re-establish proper water quality.
References (1)FDSAR,VolumeI,SectionIV-2 (2)^(Deleted)
(3)(Deleted)
(4) Licensing Application Amendment 16 Design Requirements
.. Section (5)~(Deleted)
(6) FDSAR, Volume I, Section IV-2.3.3 and Volume II, Appendix H (7) FDSAR, Volume I, Table IV-2-1
. (8) Licensing Application Amendment 34, Question 14 (9) Licensing Application Amendment'28, Item III-B-2 (10) Licensing Application Amendment 32, Question 15 (11)(Deleted)
(12) Licensing Application Amendment 68, Supplement No. 6 Addendum 3 (13)LicensingApplicationAmendement16,Page1 g-