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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20196G3531999-06-23023 June 1999 LAR 99-19 for License NPF-86,increasing AOT for Cracs from 30 Days to 60 Days on One Time Basis for Each Train to Facilitate on-line Implementation of Design Enhancements During Current Operating Cycle ML20207J6201999-03-15015 March 1999 Application for Amends to Licenses NPF-49 & NPF-86, Transferring Control of Licenses to Reflect Change in Upstream Economic Ownership of Parent Company of Nep,Vols I & Ii.Pages 48,49 & Annual Rept 1996 Pages 2 & 3 Omitted ML20207G9261999-03-0505 March 1999 Suppl Application for Transfer of License NPF-86,requesting Consent for Transfer of Montaup Electric Co Interest in OL for Seabrook Station to Little Bay Power Corp ML20198E7291998-12-16016 December 1998 Application for Amend to License NPF-86.Amend Involves Relocation of TS 3/4.7.10 & Associated TS Table 3.7-3 to Technical Requirements Manual ML20198E7781998-12-16016 December 1998 License Amend Request 98-09 to License NPF-86,either Revising Refs & Statements That Are Inaccurate or Providing Relief from Administrative Controls Which Provide Insignificant Safety Benefit ML20155J1671998-11-0404 November 1998 LAR 98-17 to License NPF-86,revising TS SR 4.5.2b.1 to Remove Prescriptive Requirements of Using Venting Process as Sole Means to Verify That ECCS Piping Is Full of Water ML20154F9971998-09-29029 September 1998 Application 98-16 for Amend to License NPF-86,reflecting Removal of Montaup Electric Co & Addition of Little Bay Power Corp ML20249B4161998-06-17017 June 1998 Revised LAR 98-07,reflecting Proposed Changes in LAR 98-07 W/Recently Issued License Amend 56 Which Split TS 3/4.7.6 Into Separate TSs,3/4.7.6.1 & 3/4.7.6.2 ML20247R6821998-05-20020 May 1998 LAR 97-07 to License NPF-86,revising Refueling Water Storage Tank low-low Level Setpoint ML20217E8611998-04-22022 April 1998 LAR 98-04 to License NPF-86,changing TS Surveillance Intervals to Accommodate 24 Month Fuel Cycle,Per GL 91-04 ML20216C5751998-04-0808 April 1998 Application 98-03 for Amend to License NPF-86,changing TS Surveillance Intervals to Accommodate 24-month Fuel Cycle, Per GL 91-04 ML20217Q2761998-04-0303 April 1998 Application for Amend to License NPF-86,LAR 98-02,proposing Changes to TS to Accomodate Fuel Cycles of Up to 24 Months, Per GL 91-04, Changes in TS Surveillance Intervals to Accommodate 24-Month Fuel Cycle ML20217M3671998-03-27027 March 1998 LAR 98-07 to License NPF-86,modifying Tech Specs 3.7.6, Control Room Emergency Makeup Air & Filtration Subsystem ML20217F0931998-03-23023 March 1998 Application for Amend to License NPF-86,proposing Administrative Change to TS to Incorporate Administrative Controls of New Specification 3.0.5,currently Approved for Use in NUREG-1431 ML20217Q0971998-03-0505 March 1998 Application for Amend to License NPF-86,incorporating Programmatic Controls in TS for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20217N7231998-03-0202 March 1998 Application for Amend to License NPF-86,changing TS to Revise Frequency for Performance of Specific Surveillances & Delete Requirements for Accelerated Testing When Number of Valid Test Failures Associated W/Edgs Is Met or Exceeded ML20217N8151998-03-0202 March 1998 Application for Amend to License NPF-86,changing TS to Exclude Prescriptive Requirement to Vent Operating CVCS CCP Casing ML20211E9761997-09-26026 September 1997 Application for Amend (LAR 97-05),changing TS 3.7.6 by Separating Requirements for Control Room HVAC Sys Re Operation of Control Room Emergency Makeup Air & Filtration Sys Subsystem & Control Room Air Conditioning Subsys ML20141B3521997-06-19019 June 1997 License Amend Request 97-03 to License,Revising TS Administrative Control 6.8.1.6.b to Include Ref to NRC Approved W Topical Rept WCAP-12610-P-A, Vantage + Fuel Assembly Ref Core Rept ML20148F9971997-05-29029 May 1997 License Amend Request 97-02,to License NPF-86,replacing Term Zircaloy W/Terminology That Identifies NRC Approved Westinghouse Fuel Assembly Design Consisting of Assemblies W/Either ZIRLO or Zircaloy-4 Fuel Cladding Matl ML20134Q3291997-02-18018 February 1997 Application for Amend to License NPF-86,changing Reactor Core Fuel Assembly Design Features Requirements Contained in Tech Specs 5.3.1, Fuel Assemblies ML20134L8591997-02-12012 February 1997 Application for Amend to License NPF-86,requesting Rev to TS Section 6.0 Re Administrative Controls ML20129B8211996-10-17017 October 1996 Application for Amend to License NPF-86,consisting of Change Request 96-02,proposing Changes That Involve Relocation of Four TS Re Instrumentation Requirements Contained in TS Section 3/4.3 ML20129B7631996-10-16016 October 1996 Application for Amend to License NPF-86,consisting of Change Request 96-06,proposing Four Changes Re EDG Requirements Contained in TS 3/4.8.1, AC Sources ML20113B1911996-06-20020 June 1996 License Amend Request 96-17 to License NPF-86,increasing Allowed Outage Time for Inoperable Svc Water Cooling Tower Loop Electrical Supply to Be Equivalent to Allowed Outage Time for Inoperable Svc Water Cooling Tower Loop ML20117K3051996-06-0404 June 1996 Application for Amend to License NPF-86,implementing Performance Based Containment Leak Rate Testing Program at Seabrook Station by Changing Tss.Request Submitted IAW 10CFR50,App J,Option B & Reg Guide 1.163 Requirements ML20092M1011995-09-22022 September 1995 Application for Amend to License NPF-86,consisting of LAR 95-07 Re Automatic Switchover to Containment Sump/Rwst Level low-low ML20098A4711995-09-20020 September 1995 Application for Amend to License NPF-86,relocating Functional Unit 6.b, FW Isolation- Low RCS T Avg Coincident W/Rt from TS 3.3.2 to Plant TS Requirements Manual Licensee Controlled Document ML20092K2091995-09-20020 September 1995 Application for Amend to License NPF-86,changing TS 3/4.9.1 Re Refueling Boron Concentration (Ref NUREG-1431) ML20092F9141995-09-12012 September 1995 Application for Amend to License NPF-86,TS Bases for RCS Safety Valves Bases Section 3/4.4.2 Were Made to Clarify What Specifically Constitutes Operable Pressurizer Safety Valve in Mode 5 ML20092A6251995-09-0505 September 1995 Application for Amend to License NPF-86,revising Main Steam Safety Valve Setpoints & Max Allowable Power Range Neutron Flux High Setpoints W/Inoperable Main Steam Safety Valves ML20086R2091995-07-24024 July 1995 LAR 95-03 to License NPF-86,relocating Table 3.4-1, RCS PIVs from TS 3.4.6.2, RCS Operational Leakage to Technical Requirements Manual ML20085L1101995-06-16016 June 1995 Application for Amend to License NPF-86.Amend Would Increase Requirements for Core Reactivity Control Available from Borated Water Sources ML20084U5391995-06-0707 June 1995 Application for Amend to License NPF-86,consisting of Amend Request 95-02,revising Footnote to SR 4.4.7 & Table 3.4-2 to Increase Temp Limit at Which Rc O Levels Determined by Sampling from 180 Degrees F to 250 Degrees F ML20084N9501995-05-30030 May 1995 Application for Amend to License NPF-86.Amend Will Allow Operation of Core W/Positive Moderator Temp Coefficient ML20082L5001995-04-17017 April 1995 Application for Amend to License NPF-86,revising TS 3.9.4 That Addresses Containment Bldg Penetrations to Allow Use of Alternate Containment Bldg Penetration Closure Methodologies for Postulated Accident Scenarios During Core Alterations ML20078E0351995-01-25025 January 1995 Application for Amend to License NPF-86,to Revise Surveillance Requirement 4.6.1.2.a from Specific Schedule for Performance of Containment ILRTs ML20076G2691994-10-0707 October 1994 License Amend Request 94-03 to License NPF-86,modifying TS Administrative Control Requirements for Emergency & Security Plans,Per GL 93-07 ML20059H6321994-01-14014 January 1994 LAR 93-20 to License NPF-86,changing Administrative Controls in TS Section 6.0 to Redefine Composition of Sorc,Create Station Qualified Reviewer Program,Delete Requirement to Perform Periodic Procedure Reviews & Revise TS 6.4.2.9 ML20058C2991993-11-23023 November 1993 LAR 93-18 to License NPF-86,allowing Operation of Core within Axial Flux Difference Band Expanded from Current Band in TSs & Improved Fuel Cycle Mgt Through Implementation of Core Design Enhancements ML20059C5191993-10-28028 October 1993 LAR 93-14 to License NPF-86,changing TS to Implement 13 Line Item Improvements Recommended by GL 93-05, Line-Item TS Improvements to Reduce SRs for Testing During Power Operation ML20057F2981993-10-0404 October 1993 Application for Amend to License NPF-86,proposing Changes to TS Correcting Inconsistency within TS by Deleting Requirement to Verify EDG Speed ML20056F7641993-08-26026 August 1993 LAR Requesting Exercise of Enforcement Discretion from Requirement to Perform Channel Check on Narrow Range RWST low-low Level Transmitters ML20045C5541993-06-18018 June 1993 LAR 93-08 to License NPF-86,changing Title of TS 6.2.3 to Independent Technical Reviews & Deleting Requirement to Maintain Five Person Organization,Iseg ML20045D5831993-06-18018 June 1993 LAR Proposing Changes to Seabrook Station Tech Specs to Reduce Frequency of Surveillances Which Are Required to Verify Integrity of CST Enclosure ML20036A4491993-05-0707 May 1993 License Amend Request 93-05 to License NPF-86,changing TS to Permit Mod of Containment Structure Air Purge & Heating Subsystem to Provide More Reliable Means of Containment Isolation for Two Containment Penetrations ML20035H2191993-04-23023 April 1993 License Amend Request 93-04 to License NPF-86,changing TS to Increase Surveillance Test Interval,Allowed Outage Time & Channel Bypass Time for Reactor Trip Sys & ESFAS ML20034F5261993-02-26026 February 1993 License Amend Request 93-01 to License NPF-86,changing TS 3/4.7.3 to Redefine Requirements for Operable Primary Component Cooling Water Sys to Enhance Plant Operations & Outage Flexibility ML20127F8071993-01-13013 January 1993 License Amend Request 92-015 to License NPF-86,changing TS 6.8.1.4, Semiannual Radioactive Effluent Release Rept, to Change Submittal Frequency from Semiannually to Annually ML20117A7941992-11-25025 November 1992 License Amend Request 92-14 to License NPF-86,revising TS to Allow Fixed Incore Detectors to Be Used as Independent Sys to Perform TS Surveillances 1999-06-23
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217C8411999-10-0505 October 1999 Amend 64 to License NPF-86,revising TSs 3.7.6.1 & 3.7.6.2 to Delete Restriction to Suspend All Operations Involving Positive Reactivity Changes During Plant Conditions Specified ML20212L1071999-10-0101 October 1999 Amend 63 to License NPF-86,relocating TS 3/4.7.10, Area Temperature Monitoring, & Associsted TS Table 3.7-3.to Technical Requirements Manual ML20212D0761999-09-17017 September 1999 Amend 62 to License NPF-86,revising TS 3.7.6.2 to Increase AOT for Control Room Air Conditioning Subsystem from 30 to 60 Days to Allow Adequate Time to Replace Portions of Existing System During Current Operating Cycle ML20210Q1631999-08-12012 August 1999 Amend 61 to License NPF-86,revising TS SR 4.5.2b.1 to Delete Prescribed Method of Venting ECCS Which Would Allow Alternate Method to Verify That ECCS Piping Will Be Full of Water ML20196G3531999-06-23023 June 1999 LAR 99-19 for License NPF-86,increasing AOT for Cracs from 30 Days to 60 Days on One Time Basis for Each Train to Facilitate on-line Implementation of Design Enhancements During Current Operating Cycle ML20207J6201999-03-15015 March 1999 Application for Amends to Licenses NPF-49 & NPF-86, Transferring Control of Licenses to Reflect Change in Upstream Economic Ownership of Parent Company of Nep,Vols I & Ii.Pages 48,49 & Annual Rept 1996 Pages 2 & 3 Omitted ML20204E3391999-03-12012 March 1999 Amend 60 to License NPF-86,revising TS Table 3.3-4 to Depict Change to Refueling Water Storage Tank low-low Level Setpoint ML20207G9261999-03-0505 March 1999 Suppl Application for Transfer of License NPF-86,requesting Consent for Transfer of Montaup Electric Co Interest in OL for Seabrook Station to Little Bay Power Corp ML20198E7781998-12-16016 December 1998 License Amend Request 98-09 to License NPF-86,either Revising Refs & Statements That Are Inaccurate or Providing Relief from Administrative Controls Which Provide Insignificant Safety Benefit ML20198E7291998-12-16016 December 1998 Application for Amend to License NPF-86.Amend Involves Relocation of TS 3/4.7.10 & Associated TS Table 3.7-3 to Technical Requirements Manual ML20155J1671998-11-0404 November 1998 LAR 98-17 to License NPF-86,revising TS SR 4.5.2b.1 to Remove Prescriptive Requirements of Using Venting Process as Sole Means to Verify That ECCS Piping Is Full of Water ML20154F9971998-09-29029 September 1998 Application 98-16 for Amend to License NPF-86,reflecting Removal of Montaup Electric Co & Addition of Little Bay Power Corp ML20249C6401998-06-24024 June 1998 Amend 58 to License NPF-86,revises TS 4.5.2.b.1 for ECCS Subsystems to Delete Requirements to Vent Operating Chemical Volume & Control Sys Centrifugal Charging Pump Casing ML20249B4161998-06-17017 June 1998 Revised LAR 98-07,reflecting Proposed Changes in LAR 98-07 W/Recently Issued License Amend 56 Which Split TS 3/4.7.6 Into Separate TSs,3/4.7.6.1 & 3/4.7.6.2 ML20247R6821998-05-20020 May 1998 LAR 97-07 to License NPF-86,revising Refueling Water Storage Tank low-low Level Setpoint ML20217E8611998-04-22022 April 1998 LAR 98-04 to License NPF-86,changing TS Surveillance Intervals to Accommodate 24 Month Fuel Cycle,Per GL 91-04 ML20216C7861998-04-0909 April 1998 Amend 56 to License NPF-86,revising App a TSs Re Requirements for Control Room Subsystems ML20216C5751998-04-0808 April 1998 Application 98-03 for Amend to License NPF-86,changing TS Surveillance Intervals to Accommodate 24-month Fuel Cycle, Per GL 91-04 ML20217Q2761998-04-0303 April 1998 Application for Amend to License NPF-86,LAR 98-02,proposing Changes to TS to Accomodate Fuel Cycles of Up to 24 Months, Per GL 91-04, Changes in TS Surveillance Intervals to Accommodate 24-Month Fuel Cycle ML20217M3671998-03-27027 March 1998 LAR 98-07 to License NPF-86,modifying Tech Specs 3.7.6, Control Room Emergency Makeup Air & Filtration Subsystem ML20236R9301998-03-26026 March 1998 Amend 55 to License NPF-86,modifing TS Sections 6.0, Administrative Control, to Reflect Recent Organizational Changes & Changes to Approval Title for Section Qualified Reviewer Program & Correcting Incorrect Ref in TS 6.4.3.9.b ML20217F0931998-03-23023 March 1998 Application for Amend to License NPF-86,proposing Administrative Change to TS to Incorporate Administrative Controls of New Specification 3.0.5,currently Approved for Use in NUREG-1431 ML20216H8341998-03-17017 March 1998 Amend 54 to License NPF-86,revising App a TSs Relating to Requirements for AC Power Sources,Changing Certain Requirements Related to EDG Stated in TS 3/4.8.1, AC Sources ML20217Q0971998-03-0505 March 1998 Application for Amend to License NPF-86,incorporating Programmatic Controls in TS for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20217N8151998-03-0202 March 1998 Application for Amend to License NPF-86,changing TS to Exclude Prescriptive Requirement to Vent Operating CVCS CCP Casing ML20217N7231998-03-0202 March 1998 Application for Amend to License NPF-86,changing TS to Revise Frequency for Performance of Specific Surveillances & Delete Requirements for Accelerated Testing When Number of Valid Test Failures Associated W/Edgs Is Met or Exceeded ML20211E9761997-09-26026 September 1997 Application for Amend (LAR 97-05),changing TS 3.7.6 by Separating Requirements for Control Room HVAC Sys Re Operation of Control Room Emergency Makeup Air & Filtration Sys Subsystem & Control Room Air Conditioning Subsys ML20141D5901997-06-24024 June 1997 Amend 53 to License NPF-86,modifying TS to Identify Fuel Assemblies Design Features ML20141D1391997-06-24024 June 1997 Amend 52 to License NPF-86,modifying TS 6.8.1.6.b to Include Reference to NRC W Topical Rept WCAP-12610-P-A, Vantage+Fuel Assembly Reference Core Rept, Dtd April 1995 ML20141B3521997-06-19019 June 1997 License Amend Request 97-03 to License,Revising TS Administrative Control 6.8.1.6.b to Include Ref to NRC Approved W Topical Rept WCAP-12610-P-A, Vantage + Fuel Assembly Ref Core Rept ML20148F9971997-05-29029 May 1997 License Amend Request 97-02,to License NPF-86,replacing Term Zircaloy W/Terminology That Identifies NRC Approved Westinghouse Fuel Assembly Design Consisting of Assemblies W/Either ZIRLO or Zircaloy-4 Fuel Cladding Matl ML20135C1561997-02-24024 February 1997 Amend 49 to License NPF-86,revising Plant App a TSs 1.7, Containment Integrity, 3/4.6.1, Primary Containment, & 3/4.6.5, Containment Enclosure Bldg, to Incorporate Provisions of Option B to 10CFR50,App J ML20134Q3291997-02-18018 February 1997 Application for Amend to License NPF-86,changing Reactor Core Fuel Assembly Design Features Requirements Contained in Tech Specs 5.3.1, Fuel Assemblies ML20134L8591997-02-12012 February 1997 Application for Amend to License NPF-86,requesting Rev to TS Section 6.0 Re Administrative Controls ML20129B8211996-10-17017 October 1996 Application for Amend to License NPF-86,consisting of Change Request 96-02,proposing Changes That Involve Relocation of Four TS Re Instrumentation Requirements Contained in TS Section 3/4.3 ML20129B7631996-10-16016 October 1996 Application for Amend to License NPF-86,consisting of Change Request 96-06,proposing Four Changes Re EDG Requirements Contained in TS 3/4.8.1, AC Sources ML20113B1911996-06-20020 June 1996 License Amend Request 96-17 to License NPF-86,increasing Allowed Outage Time for Inoperable Svc Water Cooling Tower Loop Electrical Supply to Be Equivalent to Allowed Outage Time for Inoperable Svc Water Cooling Tower Loop ML20117K3051996-06-0404 June 1996 Application for Amend to License NPF-86,implementing Performance Based Containment Leak Rate Testing Program at Seabrook Station by Changing Tss.Request Submitted IAW 10CFR50,App J,Option B & Reg Guide 1.163 Requirements ML20108D9981996-05-0707 May 1996 Amend 47 to License NPF-86,revising App a TS 3.3.2, Engineered Safety Features Actuation Sys Instrumentation ML20095L0681995-12-21021 December 1995 Corrected Page 3/4 4-25 & 26 W/Overleaf for Completeness of Amend 46 to License NPF-86.Error Involved TS Page W/O Page & Amend Number ML20095L0641995-12-21021 December 1995 Corrected Pages 3/4 3-33,3/4 3-26 & 3/4 3-19 & 20 W/Overleafs for Completeness of Amends 45 & 46 to License NPF-86 ML20094P9741995-11-28028 November 1995 Amend 44 to License 44,revise App a TS Re RCS Leakage & Deletes Table 3.4-1 from TS Section 3.4.6.2 & Ref Table 3.4-1 from Limiting Condition for Operation 3.4.6.2 F ML20094F4371995-11-0202 November 1995 Amend 43 to License NPF-86,modifying App a TSs for Turbine Cycle Safety Valves ML20092M1011995-09-22022 September 1995 Application for Amend to License NPF-86,consisting of LAR 95-07 Re Automatic Switchover to Containment Sump/Rwst Level low-low ML20098A4711995-09-20020 September 1995 Application for Amend to License NPF-86,relocating Functional Unit 6.b, FW Isolation- Low RCS T Avg Coincident W/Rt from TS 3.3.2 to Plant TS Requirements Manual Licensee Controlled Document ML20092K2091995-09-20020 September 1995 Application for Amend to License NPF-86,changing TS 3/4.9.1 Re Refueling Boron Concentration (Ref NUREG-1431) ML20092F9141995-09-12012 September 1995 Application for Amend to License NPF-86,TS Bases for RCS Safety Valves Bases Section 3/4.4.2 Were Made to Clarify What Specifically Constitutes Operable Pressurizer Safety Valve in Mode 5 ML20092A6251995-09-0505 September 1995 Application for Amend to License NPF-86,revising Main Steam Safety Valve Setpoints & Max Allowable Power Range Neutron Flux High Setpoints W/Inoperable Main Steam Safety Valves ML20091Q7321995-08-31031 August 1995 Amend 40 to License NPF-86,revising App a Re Containment Bldg Penetrations ML20086R2091995-07-24024 July 1995 LAR 95-03 to License NPF-86,relocating Table 3.4-1, RCS PIVs from TS 3.4.6.2, RCS Operational Leakage to Technical Requirements Manual 1999-09-17
[Table view] |
Text
- - - _ _ _ _ _ _ _ _ _ _ _ _ _ -
i, New Hampshire Ted C. Feigenbaum Yh hh President and Chief Executive Officer NYN-91067 April 24,1991 United States Nuclear Regulatory Cc,mmission Washington, D.C.
20555 Attention:
Docurrent Control Desk
References:
(a)
Facility Operating License No. NPF 86, Docket No. 50-443 (b)
USNRC Generic Letter 8817 dated October 17,1988, " Loss of Decay Heat Removal" (c)
NHY Letter NYN 90211 dated December 14, 1990, " Safety injection Pump Operability in a Reduced Inventory Condition", T. C. Feigenbaum to USNRC
Subject:
Request for License Amendment: Safety injection Pump Operability in MODES 5 and 6 Gentlemen:
Pursuant to 10 CFR 50.90, New Hampshire Yankee (NHY) proposes to amend the Seabrook Station Operating License (Facility Operating License NPF-86) by incorporating the proposed changes, provided herein as Enclosure 1, into the Seabrook Station Technical Specifications. These proposed changes will allow a Safety injection (SI) pump to be made OPERABLE in MODES 5 and 6 when the Reactor Coolant System has a vent area equal to or greater than 18 square inches.
This request for a license amendment addresses the recommendations, and in particular programmed enhancement (3b), of NRC Generic Letter 8817 [ Reference (b)].
Revised BASES are provided as Enclosure 2 to this letter.
In accordance with the provisions of 10 CFR 50.36, these BASES are not considered to be part of the Technical Specifications.
j This request for a license amendment supersedes our previous request of December 14,1990 (Reference (c)]. New Hampshire Yankee is providing this submittal to address concerns raised by NRC reviewers regarding the use of asterisks in the Technical Specifications. NHY believes that the revised page 3/4 5-10 utilizes the asterisk in a more effective manner with regard to human factors considerations in the technical specifications.
The BASES have been revised to be consistent with the wording of the Technical Specification.
9104260177 910424 I
PDR ADOCK 05000443 P
PDR
^'#'""'
New Hampshire Yankee Division of Public Service Company of New Hampshire P.O. Box 300
e United States Nuclear Regulatory Commission April 24,1991 Attention:
Document Control Desk Page two The proposed changes affect the following Technical Specification and Bases:
e Technical Specification 3.5.3.2. 'ECCS Subsystem - Tave Eaual To Or Less Than 200'F'. Pace 3/4 510 The currunt Technical Specification does not allow a Safety Injection (SI) pump to be OPERABLE and to discharge to the Rt. actor Coolant System (RCS) in MODE 5 and MODE 6 with the reactor vessel head on.
The change to this Technical Specification allows one SI pump to be OPERABLE and to discharge to the RCS when the RCS has a vent area equal to or greater than 18 square inches. This change addresses programmed enhancement (3b) of NRC Oeneric Letter 8817 and provides an additional means of adding inventory to the RCS. The use of the Si pump provides a diverse and redundant means to makeup RCS inventory in the event that the Residual Heat Removal System and the Centrifugal Charging Pump become unavailable while the plant is operating in a reduced inventory condition.
The operation of an SI pump under these conditions also allows testing of flow paths and filling of the accumulator to be performed. The 18 square inch vent is specified to ensure that the reactor vessel pressure limits of 10CFR50, Appendix 0 are not exceeded during a mass addition transient.
This Specification was reformatted to minimize the use of asterisks and to more clearly state under what conditions an Si pump may be made OPERABLE in MODE 5 and MODE 6. Additionally, the page sub title was revised to eliminate the heading
'ECCS Subsystems T,y Equal To or Less Than 350*F'. This specification is applicable in MODE 5 and MODE 6 and therefore only applies when T., is equal to or less than 200'F.
e Technical Specification 3.4.9.3. 'Overoressure Protection Systems' Paces 3/4 4-34 and 3/4 4-35 This specification was revised to establish, within a single specification, the requirements for overpressure protection in MODES 4, 5 and 6.
The specification establishes the overpressure protection requirements in plant configuration 1) In MODE 4 when the temperature of any RCS cold leg is less than or equal to 329'F; and in MODE 5 and MODE 6 with all Safety Injection pumps inoperable; and 2) in MODE 5 and MODE 6 with all Safety injection pumps except one inoperable. The Action statements have been revised to be consistent with the Limiting Conditino for Operation.
Additionally, Surveillance Requirement 4.4.9.3.3 was revised to allow a valve or device to be locked, scaled or secured in the open position to provide the required vent pathway.
l
\\
United States Nuclear Regulatory Commission April 24,1991 Attention:
Document Control Desk Page three e
Technical Specification Bases 3/4.4.9. ' Pressure / Temperature Limits
.L.
The change to this Bases section is a clarification of the wording dealing with the reasoning behind the assumption that there will be no single failure of a PORV in conjunction with an inadvertent actuation of a single ESP train. The existing sentence is not clear. The proposed change rewrites the sentence and inserts the approprir.te words to make the sentence complete. This change is just a wording clarification of an existing aspect of the BASES.
e Technical Specification Bases 3/4.4.9. " Pressure / Temperature 1.imits' Pace B 3/4 416 The change to this Bases section is consistent with the Technical Specification changes proposed herein and specifies that one Safety injection pump is allowed to be operable in MODE 5 and MODE 6.
The Bases also states that the overpressure protection is provided by the mechanical opening in the RCS that provides a vent area equal to or greater than 18 square inches, e
Technical Snecification Bases 3/4.5.3. 'ECCS Subsystems' Pace B 3/4 51 The change to this Bases section is consistent with the Technical Specification changes proposed herein. These changes clarify that when a Safety injection pump is made OPERABLE in MODE 5 or MODE 6 the cold overpressure protection and the ability to relieve a mass addition transient is provided by the RCS vent area equal t' greater than 18 square inches.
Additionally, the bases includes the surveillance requirement to verify the presence of the RCS vent area when a Safety injection pump is OPERABLE in' MODE 5 or MODE 6.
'New Hampshire Yankee has reviewed the proposed changes in accordance with the criteria specified in 10 CFR 50.92 and has determined that the proposed changes would not involve a Significant Hazards Consideration pursuant to 10 CFR 50.92. The basis for this determination is provided in Enclosure 3, which includes n description and evaluation of the proposed changes.
New Hampshire Yankee requests approval of these proposed changes by May 30, 1991. If you have any questions, please contact Mr. Terry L. Harpster, NHY Director of Licensing Services, at (603) 474-9521, extension 2765.
Very truly yours, (4 kl6mb-Ted C. Feigtnbaum TCF:JMP/act/ssi Enclosures
United States Nuclear Regulatory Commission April 24,1991 Attention:
Document Control Desk Page four cc:
Mr. Thomas T. Martin Regional Administrator United States Nuclear Regulatory Comenission Region 1 475 Allendale Road King of Prussia, PA 19406 Mr. Gordon E. Edison, Sr. Project Manager Project Directorate 13 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Otorge L. lverson, Director Office of Emergency Management State Office Park Sot'.h
- 107 Pleasant Street Concord. NH 03301 Mr. Noel Dudley NRC Senior Resident Inspector P.O. Box 1149 St.abrook, NH 03874