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| | issue date = 05/31/1985 | | | issue date = 05/31/1985 |
| | title = Application for Amend to License DPR-20,revising Tech Specs to Change Requirement to Flow Test Auxiliary Feedwater Pump Discharge Valves from Monthly Test During Plant Operations to Refueling Outage Test | | | title = Application for Amend to License DPR-20,revising Tech Specs to Change Requirement to Flow Test Auxiliary Feedwater Pump Discharge Valves from Monthly Test During Plant Operations to Refueling Outage Test |
| | author name = DEWITT R B | | | author name = Dewitt R |
| | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), | | | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), |
| | addressee name = | | | addressee name = |
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| | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS | | | document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS |
| | page count = 4 | | | page count = 4 |
| | | project = |
| | | stage = Request |
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| {{#Wiki_filter:CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below: I. Changes Specification | | {{#Wiki_filter:CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below: |
| | I. Changes Specification 4.9 Auxiliary Feed-Water System Replace existing Section 4.9 "Specifications" "a and b" with the following: |
| | "Specifications Demonstrate the operability of each feedwater pump: |
| | : a. At least once per 31 days: |
| | : 1. The operabi.lity of each motor-driven pump shall be confirmed as required by Specification 4.3.c and Table 4.1.3. Ttem 16a. |
| | : 2. The operability of the steam driven pump shall be confirmed as required by Specification 4.3.c. and Table 4.1.3. Item 16a. |
| | The provisions of Specification 3.0.4 are not applicable for entry into Hot Standby. |
| | : 3. Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position. |
| | : b. At least once per 18 months by: |
| | : 1. Verifying that each Automatic Valve (CV-0736A, CV-0737A, CV-0727 and CV-0749) actuates to its correct position (or that specified flow is established) upon receipt of a simulated auxiliary feedwater pump start.signal. |
| | : 2. Verifying that each pump breaker (or steam valve control) receives an actuation signal upon receipt of an auxiliary feedwater actuation test signal." |
| | Specification 4.9 Basis Delete the existing Basis, Section 4.9 which specifies simultaneous testing of the auxiliary feedwater pumps with the discharge valves to confirm a flow path to the steam generator. The new Basis will read as follows: |
| | r-8506040180 850531 l PDR ADOCK 05000255 P |
| | * PDR |
| | * I NU0385-0162C-NL04 |
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| ===4.9 Auxiliary===
| | TSCR-Palisades Plant 2 "Basis The periodic testing of Section 4.9.a. will verify auxiliary feedwater pump operability by recirculating water to the condensate storage tank and monitoring pump performance as specified in Section 4.3.c. |
| | The operability testing of Section 4.9.b. will verify auto initiation of the auxiliary feedwater system by simulating a low steam generator level-and observation of an actuation signal for the electric-driven pump breakers and for the steam-driven pump valve control. Operability of the flow control valves (CV-0736A, CV-0737A, CV-0727 and CV-0749) will be verified through simulation of an auxiliary feedwater pump start signal and observing valve actuation to its correct position or by auxiliary feedwater system flow as monitored by installed instrumentation." |
| | Specification Table 4.1.3 Delete from Table 4.1.3, item 15.a, .the monthly AFW Pump check by comparison of channels of the flow indication. Change existing item "15b" to new item "15a". Change 16.a., Surveillance Method from "internal test signal" to "switch" as follows: |
| | Surveillance "Channel Description Function Frequency Surveillance Method |
| | : 15. Auxiliary Feed a. Calibrate R a *. Known Differential Pressure Pump Flow Applied to Sensors Indication |
| | : 16. Auxiliary Feed a. Test M (3) (5) a. Switch Pump Auto b. Calibrate R b. Known Differential Initiation Pressure Applied to Sensors II. Discussion The above proposed Technical Specifications changes are requested in order to reduce the occurrences of putting cold water into the steam generator during plant operation. Since the AFW system draws make-up water from the condensate storage tank during the monthly operability test cold water which may be as low as 45 degrees Fahrenheit, imposes. |
| | considerable thermal loads on the AFW *steam generator nozzle and nozzle liner. The concern was discussed in a meeting with NRC on May 23, 1984 following our reporting of an event which occurred involving failures to our previous AFW nozzle and sparger. (Reference Licensee Event Report No. 84-003 and IE Information Notice No. 84-32). Although the results of our analysis of the failed sparger thermal liner and external piping were incorporated into the design of our new nozzle to prohibit recurrence, good engineering practice necessitates that we reduce all unnecessary thermal loads to the AFW system. |
| | NU0385-0162C-NL04 |
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| Feed-Water System Replace existing Section 4.9 "Specifications" "a and b" with the following: "Specifications Demonstrate the operability of each feedwater pump: a. At least once per 31 days: 1. The operabi.lity of each motor-driven pump shall be confirmed as required by Specification 4.3.c and Table 4.1.3. Ttem 16a. b. 2. The operability of the steam driven pump shall be confirmed as required by Specification 4.3.c. and Table 4.1.3. Item 16a. The provisions of Specification 3.0.4 are not applicable for entry into Hot Standby. 3. Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
| | TSCR-Palisades Plant 3 A review of ASME B&PV Code Section XI and the Standard Technical Specifications did not produce any basis for the existing technical specification requirement to flow test the AFW pump discharge valves on a monthly interval. The valves are specified by the Code as Category B valves and are stroke tested once every three months in accordance with the Code. The monthly operability test of the pumps will be accomplished through the use of an existing bypass to the condensate storage tank. |
| At least once per 18 months by: 1. Verifying that each Automatic Valve (CV-0736A, CV-0737A, CV-0727 and CV-0749) actuates to its correct position (or that specified flow is established) upon receipt of a simulated auxiliary feedwater pump start.signal.
| | This proposed change incorporates the surveillance requirements of NUREG-0212, the Standard Technical Specification. |
| : 2. Verifying that each pump breaker (or steam valve control) receives an actuation signal upon receipt of an auxiliary feedwater actuation test signal." Specification
| | Basis for Determination of No Significant Hazards Consideration We have reviewed the proposed request to change the requirement to flow test the AFW pump discharge valves from a monthly t.est during plant operations to a refueling outage test in accordance with the requirements of. the ASME B&PV Code Section XI, NUREG-0737, and the guidance of Generic Letter 83-37 in order to determine whether or not this change involves a significant hazards consideration. In our review, we have u.sed the guidance of cerfain '*examples (48FR14870). One of the examples (vii) in th~ guidance is if a change makes a license conform to changes in the regulation, where the license change results in very minor changes to facility operations clearly in keeping with the regulations then that change can be considered not likely to involve significant hazards considerations. In another example (vi), the guidance identifies that a change may result in some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria with respect to the system or component specified in the Standard Review Plan then that change may also be considered not likely to involve significant hazards consideration. Since this change does not result in an increase in the probability or consequences of a previously analyzed accident nor reduce a safety margin specified in the Palisades Technical Specifications and the Standard Review Plan (SRP) specifies that the Combustion Engineering Standard Technical Specification (STS), NUREG-0212, is consistent with regulatory guidance contained in the SRP, and this change is consistent with the STS, we have determined that this change falls within the examples and therefore the change does not involve a significant hazards consideration. |
| | III. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined that this change does not involve an unreviewed safety question and therefore involves no significant hazards consideration. This change has also been reviewed under the cognizance of the Nuclear Safety Board. A copy of this NU0385-0162C-NL04 |
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| ===4.9 Basis===
| | TSCR-Palisades Plant 4 Technical Specification Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License. |
| Delete the existing Basis, Section 4.9 which specifies simultaneous testing of the auxiliary feedwater pumps with the discharge valves to confirm a flow path to the steam generator.
| | CONSUMERS POWER COMPANY Byjf6~~1i/- |
| The new Basis will read as follows: r-8506040180 850531
| | R B DeWiit, Vice President Nuclear Operations Sworn and subscribed to before me this 31st day of May 1985. |
| * I l PDR ADOCK 05000255 P
| | urfey, Nota County, Mic ig My commission expires November 5, 1986. |
| * PDR *' '. -. -NU0385-0162C-NL04 TSCR-Palisades Plant 2 "Basis The periodic testing of Section 4.9.a. will verify auxiliary feedwater pump operability by recirculating water to the condensate storage tank and monitoring pump performance as specified in Section 4.3.c. The operability testing of Section 4.9.b. will verify auto initiation of the auxiliary feedwater system by simulating a low steam generator and observation of an actuation signal for the electric-driven pump breakers and for the steam-driven pump valve control. Operability of the flow control valves (CV-0736A, CV-0737A, CV-0727 and CV-0749) will be verified through simulation of an auxiliary feedwater pump start signal and observing valve actuation to its correct position or by auxiliary feedwater system flow as monitored by installed instrumentation." Specification Table 4.1.3 Delete from Table 4.1.3, item 15.a, .the monthly AFW Pump check by comparison of channels of the flow indication.
| | SHERRY LYNN DURFEY Notary Public, Jackson County, Mich. |
| Change existing item "15b" to new item "15a". Change 16.a., Surveillance Method from "internal test signal" to "switch" as follows: Surveillance "Channel Description Function Frequency Surveillance Method 15. 16. II. Auxiliary Feed a. Calibrate R a *. Known Differential Pressure Pump Flow Applied to Sensors Indication Auxiliary Feed a. Test M (3) (5) a. Switch Pump Auto b. Calibrate R b. Known Differential Initiation Pressure Applied to Sensors Discussion The above proposed Technical Specifications changes are requested in order to reduce the occurrences of putting cold water into the steam generator during plant operation.
| | My Commission Expires Nov. 5, 1986. |
| Since the AFW system draws make-up water from the condensate storage tank during the monthly operability test cold water which may be as low as 45 degrees Fahrenheit, imposes. considerable thermal loads on the AFW *steam generator nozzle and nozzle liner. The concern was discussed in a meeting with NRC on May 23, 1984 following our reporting of an event which occurred involving failures to our previous AFW nozzle and sparger. (Reference Licensee Event Report No. 84-003 and IE Information Notice No. 84-32). Although the results of our analysis of the failed sparger thermal liner and external piping were incorporated into the design of our new nozzle to prohibit recurrence, good engineering practice necessitates that we reduce all unnecessary thermal loads to the AFW system. NU0385-0162C-NL04 TSCR-Palisades Plant A review of ASME B&PV Code Section XI and the Standard Technical Specifications did not produce any basis for the existing technical specification requirement to flow test the AFW pump discharge valves on a monthly interval.
| | NU0385-0162C-NL04}} |
| The valves are specified by the Code as Category B valves and are stroke tested once every three months in accordance with the Code. The monthly operability test of the pumps will be accomplished through the use of an existing bypass to the condensate storage tank. This proposed change incorporates the surveillance requirements of NUREG-0212, the Standard Technical Specification.
| |
| Basis for Determination of No Significant Hazards Consideration 3 We have reviewed the proposed request to change the requirement to flow test the AFW pump discharge valves from a monthly t.est during plant operations to a refueling outage test in accordance with the requirements of. the ASME B&PV Code Section XI, NUREG-0737, and the guidance of Generic Letter 83-37 in order to determine whether or not this change involves a significant hazards consideration.
| |
| In our review, we have u.sed the guidance of cerfain '*examples (48FR14870).
| |
| One of the examples (vii) in guidance is if a change makes a license conform to changes in the regulation, where the license change results in very minor changes to facility operations clearly in keeping with the regulations then that change can be considered not likely to involve significant hazards considerations.
| |
| In another example (vi), the guidance identifies that a change may result in some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria with respect to the system or component specified in the Standard Review Plan then that change may also be considered not likely to involve significant hazards consideration.
| |
| Since this change does not result in an increase in the probability or consequences of a previously analyzed accident nor reduce a safety margin specified in the Palisades Technical Specifications and the Standard Review Plan (SRP) specifies that the Combustion Engineering Standard Technical Specification (STS), NUREG-0212, is consistent with regulatory guidance contained in the SRP, and this change is consistent with the STS, we have determined that this change falls within the examples and therefore the change does not involve a significant hazards consideration.
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| III. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined that this change does not involve an unreviewed safety question and therefore involves no significant hazards consideration.
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| This change has also been reviewed under the cognizance of the Nuclear Safety Board. A copy of this NU0385-0162C-NL04 TSCR-Palisades Plant 4 Technical Specification Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License. CONSUMERS POWER COMPANY R B DeWiit, Vice President Nuclear Operations Sworn and subscribed to before me this 31st day of May 1985. urfey, Nota County, Mic ig My commission expires November 5, 1986. SHERRY LYNN DURFEY Notary Public, Jackson County, Mich. My Commission Expires Nov. 5, 1986. NU0385-0162C-NL04}}
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML18066A3251998-11-0909 November 1998 Application for Amend to License DPR-20,deleting CVCS Operability Requirements Currently in LCOs 3.2 & 3.17.6 & Associated Testing Requirements in SRs 4.2 & 4.17 ML18066A1981998-06-17017 June 1998 Application for Amend to License DPR-20,updating TS to Reflect Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18065B1831998-03-13013 March 1998 Revised Application for Amend to License DPR-20,requesting Relocation of TS Section 4.16 Snubber Testing Requirements to Plant Operating Requirements Manual (Orm).Affected Orm Pages Encl ML18065B1781998-03-13013 March 1998 Application for Amend to License DPR-20,changing Auxiliary Feedwater TS to Allow Installation of Plant Mod W/O Requiring Plant Shutdown ML18067A7051997-10-0101 October 1997 Application for Amend to License DPR-20,proposing That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note Re Insp at End of Cycle 12 ML18067A6751997-09-0303 September 1997 Application for Amend to License DPR-20,deleting Snubber Operability Requirements in LCO 3.20 & Snubber Testing Requirements in Surveillance Requirement 4.16 ML18067A6711997-09-0303 September 1997 Application for Amend to License DPR-20,reflecting Capabilities of Installed CR Ventilation Equipment & Emulate Std Tech Specs,C-E Plants,Per NUREG-1432 Requirements for Sys ML18067A4511997-03-26026 March 1997 Application for Amend to License DPR-20,allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18065A4891996-02-0606 February 1996 Application for Amend to License DPR-20,requesting to Remove cross-train Testing Requirements from LCO Action Statements ML18065A4381996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS to Allow Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas,To Suppl 951211 Administrative Controls Change Request ML18065A4341996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS Re Primary Coolant Pump Flywheel Insp.Rev 1 to Structural Integrity Assoc,Inc Rept SIR-94-080, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements Encl ML18065A4051996-01-10010 January 1996 Application for Amend to License DPR-20,requesting Exemption from 10CFR50 App J TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg ML18065A3821996-01-0505 January 1996 Application for Amend to License DPR-20,revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage ML18065A3751995-12-27027 December 1995 Application for Amend to License DPR-20,rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS ML18065A3461995-12-11011 December 1995 Application for Amend to License DPR-20,revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 from TS ML18065A3321995-12-0606 December 1995 Application for Amend to License DPR-20,relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage ML18065A1741995-10-17017 October 1995 Application for Amend to License DPR-20,changing Paragraph 2.B.(2) to Ref 10CFR40 & to Allow Use of Source Matls as Reactor Fuel,Rewording Paragraph 2.E & Deleting Paragraph 2.7 & Revising TS Pressurizer Cooldown Limit ML18064A8391995-07-0505 July 1995 Application for Amend to License DPR-20,deleting TS 6.4, Training & Revising TS 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff ML18064A7591995-05-0101 May 1995 Application for Amend to License DPR-20.Amend Would Place Requirements in TS Section 4.7 for Periodic DG Peak Load Tests ML18064A6121995-02-10010 February 1995 Application for Amend to License DPR-20,proposing One Time Deferral of 18-month Refueling Interval Surveillance Tests ML18064A5821995-01-13013 January 1995 Tech Specs Change Request to License DPR-20 Addressing Required Settings & Allowable as Found & as Left Tolerances for Primary & Secondary Safety Valves ML18064A5341994-12-29029 December 1994 Application for Amend to License DPR-20,revising TSs Re Iodine Removal Sys ML18064A5061994-12-13013 December 1994 Application for Amend to License DPR-20,adding Third High Thermal Performance DNB Correlation to Safety Limit 2.1 ML18064A4081994-10-0505 October 1994 Application for Amend to License DPR-20,revising TS Relating to Primary Coolant Sys pressure-temp Limits.Rev 0 to Engineering Analysis EA-A-PAL-92-095-01 & Excerpts from Rosemount Instruction Manual 4515,dtd Jan 1988 Encl ML18059B0961994-07-0707 July 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Intended to Resolve Concerns Arose During NRC Review of Change Request ML18059A9751994-05-0505 May 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Necessary Due to Intervening Amends Containing Listed Differences from Pages Submitted on 930519 ML18059A9321994-04-0707 April 1994 Application for Amend to License DPR-20,requesting TS Change Re Instrumentation & Control Section ML18059A9411994-04-0707 April 1994 Application for Amend to License DPR-20,relocating Cycle Specific Operating Limits to Colr,Per Guidance of GL 88-16, Removal of Cycle-Specific Parameter Limits from Ts. Proposed COLR Encl ML18059A8851994-03-11011 March 1994 Rev to 940222 I&C TS Change Request to License DPR-20,adding Surveillance Item 10 to Table 4.2.1 Which Require Verifying SIT Level & Pressure Each Shift & Adding Three Paragraphs to Basis for Proposed Section 3.17 ML18059A3721993-09-0303 September 1993 Changes to 930129 Application for Amend to License DPR-20, Modifying Radial Peaking Factor Limits in TS Table 3.23-2 to Incorporate Appropriate Limits for Modified L Fuel Assemblies Recently Installed in Reactor for Cycle 11 ML18058B8991993-06-25025 June 1993 Revises 921208 Application for Amend to License DPR-20 & Brings Proposed Specifications Closer to Model Tech Specs, While Retaining Necessary plant-specific Differences & Updating Proposed Pages to Reflect Amends 147 & 149 ML18058B7421993-03-29029 March 1993 Application for Amend to License DPR-20,changing TS to Required Frequency for Surveillance Test Which Requires Moving Each Control Rod to Once Each 92 Days Instead of Once Every 2 Wks ML18058B3881993-01-29029 January 1993 Application for Amend to License DPR-20,consisting of Proposed TS Changes to Table 3.23-2, Radiation Peaking Factor Limits for Cycle 11. Offsite Dose Calculations & EMF-92-178, Palisades Cycle 11:Disposition & ... Encl ML18058B3481993-01-19019 January 1993 Application for Amend to License DPR-20,changing Surveillance Interval for Testing Control Rod Drive mechanisms,CRD-20 & CRD-31 from Every Two Wks to Once in Mar 1993 ML18058A5631992-06-22022 June 1992 Suppl to 920317 Application for Amend to License DPR-20, Consisting of Revised Page 3-82 Re Shutdown Cooling ML18058A5561992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Better Coordinate Required Action Statement of Electrical Sys Spec W/Lco to Allow Testing & Loading of DG When Plant Above 325 F But Not Yet Critical ML18058A5491992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Delete Requirements Re Iodine Removal Sys Hydrazine Storage Tank Since Use of Hydrazine No Longer Considered in Current Rev of SRP ML18058A3631992-04-15015 April 1992 Application for Amend to License DPR-20,changing TSs to Incorporate Generic Ltr 90-06 PORV Requirements for Power Operation & Modifying Pcs Overpressure Protection Spec Venting Requirements ML18058A2921992-03-18018 March 1992 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling ML18058A1541992-02-0303 February 1992 Application for Amend to License DPR-20,deleting Three Primary Coolant Pump Testing Requirements & Revising Safety Limits & Limiting Safety Sys Settings Specs to Enhance Clarity of Subj Requirements ML18057B3711991-11-12012 November 1991 Application for Amend to License DPR-20,revising Tech Specs to Remove Schedule for Withdrawal of Reactor Vessel Matl Specimens,Per Generic Ltr 91-01 ML18057B3481991-11-0101 November 1991 Application for Amend to License DPR-20,changing TS for Operation During Cycle 10 as Results of Changes to Fuel Design (Reload N) & Fuel Mgt Scheme for Low Leakage Core. Siemens Repts EMF-91-176 & EMF-91-177 Encl ML18057B3061991-09-27027 September 1991 Application for Amend to License DPR-20,proposing Change to Tech Spec 5.2.3.a Re Containment Air Cooler Design,Per 861020 & 870430 Requests ML18057B3021991-09-26026 September 1991 Application for Amend to License DPR-20,consisting of Rev 2 to 890628 Request,In Response to Recommendations of Generic Ltr 88-17 to Add Shutdown Cooling Sys Operability Requirements to Tech Specs ML18057B1681991-07-15015 July 1991 Application for Amend to License DPR-20,requesting Tech Spec Changes in Administrative Controls W/Emphasis on Changes in Engineering ML18057A9821991-06-13013 June 1991 Application for Amend to License DPR-20,revising Tech Specs to Incorporate Change to Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A9631991-05-30030 May 1991 Application for Amend to License DPR-20,changing Tech Specs to Incorporate Change to Reactor Variable High Power Trip setpoint.ANF-90-181, Review & Analysis of SRP Chapter 15 Events for Palisades W/15% Variable High Power... Encl ML18057A9551991-05-28028 May 1991 Application for Amend to License DPR-20,changing Tech Specs Re Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A8881991-05-0101 May 1991 Rev 1 to Application for Amend to License DPR-20,changing TS Re Shutdown Cooling Sys Per Generic Ltr 88-17,by Adding Operability Requirements for Shutdown Cooling Sys & Steam Generators ML18057A8291991-03-25025 March 1991 Application for Amend to License DPR-20,changing Tech Specs Section 4.5.2a(2) & 4.5.2b(3) 1998-06-17
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML18066A3251998-11-0909 November 1998 Application for Amend to License DPR-20,deleting CVCS Operability Requirements Currently in LCOs 3.2 & 3.17.6 & Associated Testing Requirements in SRs 4.2 & 4.17 ML18066A1981998-06-17017 June 1998 Application for Amend to License DPR-20,updating TS to Reflect Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18065B1831998-03-13013 March 1998 Revised Application for Amend to License DPR-20,requesting Relocation of TS Section 4.16 Snubber Testing Requirements to Plant Operating Requirements Manual (Orm).Affected Orm Pages Encl ML18065B1781998-03-13013 March 1998 Application for Amend to License DPR-20,changing Auxiliary Feedwater TS to Allow Installation of Plant Mod W/O Requiring Plant Shutdown ML18067A7051997-10-0101 October 1997 Application for Amend to License DPR-20,proposing That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note Re Insp at End of Cycle 12 ML18067A6751997-09-0303 September 1997 Application for Amend to License DPR-20,deleting Snubber Operability Requirements in LCO 3.20 & Snubber Testing Requirements in Surveillance Requirement 4.16 ML18067A6711997-09-0303 September 1997 Application for Amend to License DPR-20,reflecting Capabilities of Installed CR Ventilation Equipment & Emulate Std Tech Specs,C-E Plants,Per NUREG-1432 Requirements for Sys ML18067A4511997-03-26026 March 1997 Application for Amend to License DPR-20,allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18065A4891996-02-0606 February 1996 Application for Amend to License DPR-20,requesting to Remove cross-train Testing Requirements from LCO Action Statements ML18065A4381996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS to Allow Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas,To Suppl 951211 Administrative Controls Change Request ML18065A4341996-01-18018 January 1996 Application for Amend to License DPR-20,revising TS Re Primary Coolant Pump Flywheel Insp.Rev 1 to Structural Integrity Assoc,Inc Rept SIR-94-080, Relaxation of Reactor Coolant Pump Flywheel Insp Requirements Encl ML18065A4051996-01-10010 January 1996 Application for Amend to License DPR-20,requesting Exemption from 10CFR50 App J TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg ML18065A3821996-01-0505 January 1996 Application for Amend to License DPR-20,revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage ML18065A3751995-12-27027 December 1995 Application for Amend to License DPR-20,rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS ML18065A3461995-12-11011 December 1995 Application for Amend to License DPR-20,revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 from TS ML18065A3321995-12-0606 December 1995 Application for Amend to License DPR-20,relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage ML18065A1741995-10-17017 October 1995 Application for Amend to License DPR-20,changing Paragraph 2.B.(2) to Ref 10CFR40 & to Allow Use of Source Matls as Reactor Fuel,Rewording Paragraph 2.E & Deleting Paragraph 2.7 & Revising TS Pressurizer Cooldown Limit ML18064A8391995-07-0505 July 1995 Application for Amend to License DPR-20,deleting TS 6.4, Training & Revising TS 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff ML18064A7591995-05-0101 May 1995 Application for Amend to License DPR-20.Amend Would Place Requirements in TS Section 4.7 for Periodic DG Peak Load Tests ML18064A6121995-02-10010 February 1995 Application for Amend to License DPR-20,proposing One Time Deferral of 18-month Refueling Interval Surveillance Tests ML18064A5821995-01-13013 January 1995 Tech Specs Change Request to License DPR-20 Addressing Required Settings & Allowable as Found & as Left Tolerances for Primary & Secondary Safety Valves ML18064A5341994-12-29029 December 1994 Application for Amend to License DPR-20,revising TSs Re Iodine Removal Sys ML18064A5061994-12-13013 December 1994 Application for Amend to License DPR-20,adding Third High Thermal Performance DNB Correlation to Safety Limit 2.1 ML18064A4081994-10-0505 October 1994 Application for Amend to License DPR-20,revising TS Relating to Primary Coolant Sys pressure-temp Limits.Rev 0 to Engineering Analysis EA-A-PAL-92-095-01 & Excerpts from Rosemount Instruction Manual 4515,dtd Jan 1988 Encl ML18059B0961994-07-0707 July 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Intended to Resolve Concerns Arose During NRC Review of Change Request ML18059A9751994-05-0505 May 1994 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling.Changes Necessary Due to Intervening Amends Containing Listed Differences from Pages Submitted on 930519 ML18059A9321994-04-0707 April 1994 Application for Amend to License DPR-20,requesting TS Change Re Instrumentation & Control Section ML18059A9411994-04-0707 April 1994 Application for Amend to License DPR-20,relocating Cycle Specific Operating Limits to Colr,Per Guidance of GL 88-16, Removal of Cycle-Specific Parameter Limits from Ts. Proposed COLR Encl ML18059A8851994-03-11011 March 1994 Rev to 940222 I&C TS Change Request to License DPR-20,adding Surveillance Item 10 to Table 4.2.1 Which Require Verifying SIT Level & Pressure Each Shift & Adding Three Paragraphs to Basis for Proposed Section 3.17 ML18059A3721993-09-0303 September 1993 Changes to 930129 Application for Amend to License DPR-20, Modifying Radial Peaking Factor Limits in TS Table 3.23-2 to Incorporate Appropriate Limits for Modified L Fuel Assemblies Recently Installed in Reactor for Cycle 11 ML18058B8991993-06-25025 June 1993 Revises 921208 Application for Amend to License DPR-20 & Brings Proposed Specifications Closer to Model Tech Specs, While Retaining Necessary plant-specific Differences & Updating Proposed Pages to Reflect Amends 147 & 149 ML18058B7421993-03-29029 March 1993 Application for Amend to License DPR-20,changing TS to Required Frequency for Surveillance Test Which Requires Moving Each Control Rod to Once Each 92 Days Instead of Once Every 2 Wks ML18058B3881993-01-29029 January 1993 Application for Amend to License DPR-20,consisting of Proposed TS Changes to Table 3.23-2, Radiation Peaking Factor Limits for Cycle 11. Offsite Dose Calculations & EMF-92-178, Palisades Cycle 11:Disposition & ... Encl ML18058B3481993-01-19019 January 1993 Application for Amend to License DPR-20,changing Surveillance Interval for Testing Control Rod Drive mechanisms,CRD-20 & CRD-31 from Every Two Wks to Once in Mar 1993 ML18058A5631992-06-22022 June 1992 Suppl to 920317 Application for Amend to License DPR-20, Consisting of Revised Page 3-82 Re Shutdown Cooling ML18058A5561992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Better Coordinate Required Action Statement of Electrical Sys Spec W/Lco to Allow Testing & Loading of DG When Plant Above 325 F But Not Yet Critical ML18058A5491992-06-12012 June 1992 Application for Amend to License DPR-20,changing TS to Delete Requirements Re Iodine Removal Sys Hydrazine Storage Tank Since Use of Hydrazine No Longer Considered in Current Rev of SRP ML18058A3631992-04-15015 April 1992 Application for Amend to License DPR-20,changing TSs to Incorporate Generic Ltr 90-06 PORV Requirements for Power Operation & Modifying Pcs Overpressure Protection Spec Venting Requirements ML18058A2921992-03-18018 March 1992 Application for Amend to License DPR-20,revising TS Re Shutdown Cooling ML18058A1541992-02-0303 February 1992 Application for Amend to License DPR-20,deleting Three Primary Coolant Pump Testing Requirements & Revising Safety Limits & Limiting Safety Sys Settings Specs to Enhance Clarity of Subj Requirements ML18057B3711991-11-12012 November 1991 Application for Amend to License DPR-20,revising Tech Specs to Remove Schedule for Withdrawal of Reactor Vessel Matl Specimens,Per Generic Ltr 91-01 ML18057B3481991-11-0101 November 1991 Application for Amend to License DPR-20,changing TS for Operation During Cycle 10 as Results of Changes to Fuel Design (Reload N) & Fuel Mgt Scheme for Low Leakage Core. Siemens Repts EMF-91-176 & EMF-91-177 Encl ML18057B3061991-09-27027 September 1991 Application for Amend to License DPR-20,proposing Change to Tech Spec 5.2.3.a Re Containment Air Cooler Design,Per 861020 & 870430 Requests ML18057B3021991-09-26026 September 1991 Application for Amend to License DPR-20,consisting of Rev 2 to 890628 Request,In Response to Recommendations of Generic Ltr 88-17 to Add Shutdown Cooling Sys Operability Requirements to Tech Specs ML18057B1681991-07-15015 July 1991 Application for Amend to License DPR-20,requesting Tech Spec Changes in Administrative Controls W/Emphasis on Changes in Engineering ML18057A9821991-06-13013 June 1991 Application for Amend to License DPR-20,revising Tech Specs to Incorporate Change to Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A9631991-05-30030 May 1991 Application for Amend to License DPR-20,changing Tech Specs to Incorporate Change to Reactor Variable High Power Trip setpoint.ANF-90-181, Review & Analysis of SRP Chapter 15 Events for Palisades W/15% Variable High Power... Encl ML18057A9551991-05-28028 May 1991 Application for Amend to License DPR-20,changing Tech Specs Re Inservice Insp Program for Shock Suppressors (Snubbers) ML18057A8881991-05-0101 May 1991 Rev 1 to Application for Amend to License DPR-20,changing TS Re Shutdown Cooling Sys Per Generic Ltr 88-17,by Adding Operability Requirements for Shutdown Cooling Sys & Steam Generators ML18057A8291991-03-25025 March 1991 Application for Amend to License DPR-20,changing Tech Specs Section 4.5.2a(2) & 4.5.2b(3) 1998-06-17
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CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant be changed as described in Section I below:
I. Changes Specification 4.9 Auxiliary Feed-Water System Replace existing Section 4.9 "Specifications" "a and b" with the following:
"Specifications Demonstrate the operability of each feedwater pump:
- a. At least once per 31 days:
- 1. The operabi.lity of each motor-driven pump shall be confirmed as required by Specification 4.3.c and Table 4.1.3. Ttem 16a.
- 2. The operability of the steam driven pump shall be confirmed as required by Specification 4.3.c. and Table 4.1.3. Item 16a.
The provisions of Specification 3.0.4 are not applicable for entry into Hot Standby.
- 3. Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
- b. At least once per 18 months by:
- 1. Verifying that each Automatic Valve (CV-0736A, CV-0737A, CV-0727 and CV-0749) actuates to its correct position (or that specified flow is established) upon receipt of a simulated auxiliary feedwater pump start.signal.
- 2. Verifying that each pump breaker (or steam valve control) receives an actuation signal upon receipt of an auxiliary feedwater actuation test signal."
Specification 4.9 Basis Delete the existing Basis, Section 4.9 which specifies simultaneous testing of the auxiliary feedwater pumps with the discharge valves to confirm a flow path to the steam generator. The new Basis will read as follows:
r-8506040180 850531 l PDR ADOCK 05000255 P
TSCR-Palisades Plant 2 "Basis The periodic testing of Section 4.9.a. will verify auxiliary feedwater pump operability by recirculating water to the condensate storage tank and monitoring pump performance as specified in Section 4.3.c.
The operability testing of Section 4.9.b. will verify auto initiation of the auxiliary feedwater system by simulating a low steam generator level-and observation of an actuation signal for the electric-driven pump breakers and for the steam-driven pump valve control. Operability of the flow control valves (CV-0736A, CV-0737A, CV-0727 and CV-0749) will be verified through simulation of an auxiliary feedwater pump start signal and observing valve actuation to its correct position or by auxiliary feedwater system flow as monitored by installed instrumentation."
Specification Table 4.1.3 Delete from Table 4.1.3, item 15.a, .the monthly AFW Pump check by comparison of channels of the flow indication. Change existing item "15b" to new item "15a". Change 16.a., Surveillance Method from "internal test signal" to "switch" as follows:
Surveillance "Channel Description Function Frequency Surveillance Method
- 15. Auxiliary Feed a. Calibrate R a *. Known Differential Pressure Pump Flow Applied to Sensors Indication
- 16. Auxiliary Feed a. Test M (3) (5) a. Switch Pump Auto b. Calibrate R b. Known Differential Initiation Pressure Applied to Sensors II. Discussion The above proposed Technical Specifications changes are requested in order to reduce the occurrences of putting cold water into the steam generator during plant operation. Since the AFW system draws make-up water from the condensate storage tank during the monthly operability test cold water which may be as low as 45 degrees Fahrenheit, imposes.
considerable thermal loads on the AFW *steam generator nozzle and nozzle liner. The concern was discussed in a meeting with NRC on May 23, 1984 following our reporting of an event which occurred involving failures to our previous AFW nozzle and sparger. (Reference Licensee Event Report No.84-003 and IE Information Notice No. 84-32). Although the results of our analysis of the failed sparger thermal liner and external piping were incorporated into the design of our new nozzle to prohibit recurrence, good engineering practice necessitates that we reduce all unnecessary thermal loads to the AFW system.
NU0385-0162C-NL04
TSCR-Palisades Plant 3 A review of ASME B&PV Code Section XI and the Standard Technical Specifications did not produce any basis for the existing technical specification requirement to flow test the AFW pump discharge valves on a monthly interval. The valves are specified by the Code as Category B valves and are stroke tested once every three months in accordance with the Code. The monthly operability test of the pumps will be accomplished through the use of an existing bypass to the condensate storage tank.
This proposed change incorporates the surveillance requirements of NUREG-0212, the Standard Technical Specification.
Basis for Determination of No Significant Hazards Consideration We have reviewed the proposed request to change the requirement to flow test the AFW pump discharge valves from a monthly t.est during plant operations to a refueling outage test in accordance with the requirements of. the ASME B&PV Code Section XI, NUREG-0737, and the guidance of Generic Letter 83-37 in order to determine whether or not this change involves a significant hazards consideration. In our review, we have u.sed the guidance of cerfain '*examples (48FR14870). One of the examples (vii) in th~ guidance is if a change makes a license conform to changes in the regulation, where the license change results in very minor changes to facility operations clearly in keeping with the regulations then that change can be considered not likely to involve significant hazards considerations. In another example (vi), the guidance identifies that a change may result in some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria with respect to the system or component specified in the Standard Review Plan then that change may also be considered not likely to involve significant hazards consideration. Since this change does not result in an increase in the probability or consequences of a previously analyzed accident nor reduce a safety margin specified in the Palisades Technical Specifications and the Standard Review Plan (SRP) specifies that the Combustion Engineering Standard Technical Specification (STS), NUREG-0212, is consistent with regulatory guidance contained in the SRP, and this change is consistent with the STS, we have determined that this change falls within the examples and therefore the change does not involve a significant hazards consideration.
III. Conclusion The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined that this change does not involve an unreviewed safety question and therefore involves no significant hazards consideration. This change has also been reviewed under the cognizance of the Nuclear Safety Board. A copy of this NU0385-0162C-NL04
TSCR-Palisades Plant 4 Technical Specification Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License.
CONSUMERS POWER COMPANY Byjf6~~1i/-
R B DeWiit, Vice President Nuclear Operations Sworn and subscribed to before me this 31st day of May 1985.
urfey, Nota County, Mic ig My commission expires November 5, 1986.
SHERRY LYNN DURFEY Notary Public, Jackson County, Mich.
My Commission Expires Nov. 5, 1986.
NU0385-0162C-NL04