LIC-96-0106, Responds to RAI on TS Change Re SR Inverters
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Letter Sequence Other | |
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TAC:M94814, (Approved, Closed) | |
MONTHYEARLIC-96-0106, Responds to RAI on TS Change Re SR Inverters1996-08-0606 August 1996
[Table View]Responds to RAI on TS Change Re SR Inverters Project stage: Other LIC-96-0130, Forwards Response to Request for Addl Info Re Plant Application for Amend Submitted in Ltr to Allow Use of Either Zircaloy or ZIRLO Cladding1996-09-0303 September 1996 Forwards Response to Request for Addl Info Re Plant Application for Amend Submitted in Ltr to Allow Use of Either Zircaloy or ZIRLO Cladding Project stage: Request ML20129H3151996-10-25025 October 1996 Forwards Amend 178 to License DPR-40 & Safety Evaluation. Amend Changes Section 4.3.2 of TS to Allow Use of Zircaloy or ZIRLO Fuel Cladding & Use Depleted U as Reactor Fuel Matl Project stage: Approval ML20133C2581996-12-30030 December 1996 Forwards Amend 179 to License DPR-40 & Safety Evaluation. Amend Revises TSs to Increase Amount of TSP Dodecahydrate Located in Containment Sump Storage Baskets Which Will Be Verified by TS SRs Project stage: Approval ML20133K9111997-01-15015 January 1997 Forwards Revised Page 2-22 of Amend 179 to License DPR-40. Subj Page Incorrectly Stated Amount of Active TSP That Shall Be Contained in TSP Baskets Project stage: Other ML20134N7571997-02-13013 February 1997 Forwards Amend 180 to License DPR-40 & Safety Evaluation. Amend Revises TS to Add Limiting Condition for Operation & Surveillance Test for Safety Related Inverters & Deletes Nonsafety Related Instrument Buses Project stage: Approval ML20141C8831997-05-15015 May 1997 Provides List of TAC Issues Considered Ready to Close Project stage: Other 1996-09-03 |
| ML20116H939 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/06/1996 |
| From: | Tira Patterson OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-96-0106, LIC-96-106, TAC-M94814, NUDOCS 9608120341 | |
| Download: ML20116H939 (3) | |
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Category:CORRESPONDENCE-LETTERS
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& EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld LIC-99-0066, Forwards Fort Calhoun Performance Indicators Rept for May 19991999-07-0707 July 1999 Forwards Fort Calhoun Performance Indicators Rept for May 1999 LIC-99-0060, Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld1999-07-0101 July 1999 Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld LIC-99-0063, Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 9906241999-07-0101 July 1999 Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 990624 LIC-99-0061, Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl1999-06-30030 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl LIC-99-0056, Forwards Rev 2 to EA-FC-90-082, Potential Over- Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment, to Facilitate Review of Response to GL 96-061999-06-22022 June 1999 Forwards Rev 2 to EA-FC-90-082, Potential Over- Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment, to Facilitate Review of Response to GL 96-06 LIC-99-0059, Provides Formal Notification to NRC of Plans Re Renewal of Operating License DPR-40 for Unit 1.Util Will Continue to Inform NRC of Decisions Relative to License Renewal in Order to Facilitate NRC Resource Planning1999-06-22022 June 1999 Provides Formal Notification to NRC of Plans Re Renewal of Operating License DPR-40 for Unit 1.Util Will Continue to Inform NRC of Decisions Relative to License Renewal in Order to Facilitate NRC Resource Planning LIC-99-0054, Forwards Manual Containing Description of Fort Calhoun Station 1999 Emergency Preparedness Exercise, to Be Conducted on 9908101999-06-0808 June 1999 Forwards Manual Containing Description of Fort Calhoun Station 1999 Emergency Preparedness Exercise, to Be Conducted on 990810 LIC-99-0052, Forwards Fort Calhoun Station Performance Indicators, for Apr 19991999-06-0202 June 1999 Forwards Fort Calhoun Station Performance Indicators, for Apr 1999 LIC-99-0045, Forwards Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated NDTT Shift Curve & LTOP Limits & Values from FCS TS to OPPD Controlled Document.Rev 3 to TR CE NPSD-683 & Supporting TSs Encl1999-05-26026 May 1999 Forwards Application for Amend to License DPR-40,proposing to Relocate pressure-temp Curves,Predicated NDTT Shift Curve & LTOP Limits & Values from FCS TS to OPPD Controlled Document.Rev 3 to TR CE NPSD-683 & Supporting TSs Encl LIC-99-0046, Forwards Scope & Objectives for Plant 1999 EP Exercise to Be Conducted 990810.Info Provided Ninety Days Prior to Exercise IAW Established Stds.Complete Scenario Package Will Be Submitted to NRC & FEMA Sixty Days Prior to Exercise1999-05-12012 May 1999 Forwards Scope & Objectives for Plant 1999 EP Exercise to Be Conducted 990810.Info Provided Ninety Days Prior to Exercise IAW Established Stds.Complete Scenario Package Will Be Submitted to NRC & FEMA Sixty Days Prior to Exercise LIC-99-0028, Provides NRC with Status of Corrective Actions Re Plant Fire Protection Program,As Result of NRC Insp Rept 50-285/97-06. Mod to MOV Is in Design Phase & Currently Scheduled for Installation During 1999 Refueling Outage1999-04-30030 April 1999 Provides NRC with Status of Corrective Actions Re Plant Fire Protection Program,As Result of NRC Insp Rept 50-285/97-06. Mod to MOV Is in Design Phase & Currently Scheduled for Installation During 1999 Refueling Outage LIC-99-0036, Submits Annual Rept of 1998 Loca/Eccs Models Per 10CFR50.46. Small & Large Break LOCA PCT Values Continue to Remain Less than 10CFR50.46(b)(1) Acceptance Criterion of 2200 F1999-04-28028 April 1999 Submits Annual Rept of 1998 Loca/Eccs Models Per 10CFR50.46. Small & Large Break LOCA PCT Values Continue to Remain Less than 10CFR50.46(b)(1) Acceptance Criterion of 2200 F LIC-99-0043, Forwards Fort Calhoun Performance Indicators Rept for Mar 19991999-04-28028 April 1999 Forwards Fort Calhoun Performance Indicators Rept for Mar 1999 LIC-99-0041, Informs That Util Has Implemented Necessary Actions Associated with Open TACs M92926,M99885,M98619 & M98933 Issues.Items Considered Ready to Close,Subject to Agreement by Nrc/Nrr Project Manager1999-04-27027 April 1999 Informs That Util Has Implemented Necessary Actions Associated with Open TACs M92926,M99885,M98619 & M98933 Issues.Items Considered Ready to Close,Subject to Agreement by Nrc/Nrr Project Manager LIC-99-0037, Responds to NRC 990126 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Response Confirms with NRC & NEI Recommendations to Utilize Generic Industry Response to Issue1999-04-26026 April 1999 Responds to NRC 990126 RAI Re GL 97-01, Degradation of CRDM Nozzle & Other Vessel Closure Head Penetrations. Response Confirms with NRC & NEI Recommendations to Utilize Generic Industry Response to Issue LIC-99-0039, Forwards Diskette Containing 1998 Annual Rept of Individual Monitoring for Fcs,Per 10CFR20.2206.Diskette Follows File Structure of Reg Guide 8.7,App a1999-04-20020 April 1999 Forwards Diskette Containing 1998 Annual Rept of Individual Monitoring for Fcs,Per 10CFR20.2206.Diskette Follows File Structure of Reg Guide 8.7,App a LIC-99-0038, Forwards 1998 Radiological Environ Operating Rept & Annual Rept for TS Section 5.9.4.A for 980101-981231, for Fcs,Unit 1.Rept Is Presented in Format Outlined in Reg Guide 1.21,rev 1.Results of Quarterly Dose Calculations,Encl1999-04-20020 April 1999 Forwards 1998 Radiological Environ Operating Rept & Annual Rept for TS Section 5.9.4.A for 980101-981231, for Fcs,Unit 1.Rept Is Presented in Format Outlined in Reg Guide 1.21,rev 1.Results of Quarterly Dose Calculations,Encl LIC-99-0033, Forwards Addl Info to Support NRC Review of Response to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps1999-04-15015 April 1999 Forwards Addl Info to Support NRC Review of Response to GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps LIC-99-0035, Forwards Proprietary Rev 2b to FCS Emergency Plan Form FC-EPF-17 & non-proprietary Revised FC-EPF Forms Index,Rev 5a to FC-EPF-1 & Rev 4 to FC-EPF-15.Proprietary Info Withheld from Public Disclosure1999-04-0808 April 1999 Forwards Proprietary Rev 2b to FCS Emergency Plan Form FC-EPF-17 & non-proprietary Revised FC-EPF Forms Index,Rev 5a to FC-EPF-1 & Rev 4 to FC-EPF-15.Proprietary Info Withheld from Public Disclosure LIC-99-0031, Forwards Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate1999-03-31031 March 1999 Forwards Application for Amend to License DPR-40,increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0032, Forwards Fort Calhoun Station Performance Indicators, for Feb 19991999-03-31031 March 1999 Forwards Fort Calhoun Station Performance Indicators, for Feb 1999 LIC-99-0029, Forwards Response to 990226 RAI for GL 97-05, SG Tube Insp Techniques1999-03-30030 March 1999 Forwards Response to 990226 RAI for GL 97-05, SG Tube Insp Techniques LIC-99-0027, Forwards Rev 16B to FCS Site Security Plan,Rev 2 to FCS Safeguards Contingency Plan & Rev 6 to FCS Training & Qualification Plan.Encls Withheld1999-03-16016 March 1999 Forwards Rev 16B to FCS Site Security Plan,Rev 2 to FCS Safeguards Contingency Plan & Rev 6 to FCS Training & Qualification Plan.Encls Withheld LIC-99-0022, Agrees with NRC Request That Proposed Wording of USAR Section 9.2.5 Included in Be Revised to Indicate That Use of Letdown Sys Following Transient.Revs of Appropriate Pages to ,Encl1999-03-12012 March 1999 Agrees with NRC Request That Proposed Wording of USAR Section 9.2.5 Included in Be Revised to Indicate That Use of Letdown Sys Following Transient.Revs of Appropriate Pages to ,Encl LIC-99-0024, Informs That OPPD Withdraws Applications Submitted by 950626 &1999-03-12012 March 1999 Informs That OPPD Withdraws Applications Submitted by 950626 & LIC-99-0016, Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives1999-03-0101 March 1999 Requests Relief from Certain Requirements of Paragraphs IWA- 5242(a) & IWA-5250(a)(2) of ASME Section Xi,For Remainder of Third 10-year Insp Interval on Basis of Attached Proposed Alternatives LIC-99-0023, Forwards FCS Performance Indicators for Jan 19991999-03-0101 March 1999 Forwards FCS Performance Indicators for Jan 1999 LIC-99-0020, Forwards non-proprietary EPIP Index,Page 1 of 2,rev 31 to EPIP-OSC-1, Emergency Classification, FC-EPF Forms Index, Page 1 of 2, Rev 8 to FC-EPF-14 & Rev 15 to RERP-Appendix a, Rerp. Proprietary Version of Rev 15 to RERP, Included1999-02-24024 February 1999 Forwards non-proprietary EPIP Index,Page 1 of 2,rev 31 to EPIP-OSC-1, Emergency Classification, FC-EPF Forms Index, Page 1 of 2, Rev 8 to FC-EPF-14 & Rev 15 to RERP-Appendix a, Rerp. Proprietary Version of Rev 15 to RERP, Included LIC-99-0011, Forwards 1999 Biennial Decommissioning Funding Status Rept for Fort Calhoun Station,Unit 11999-02-0505 February 1999 Forwards 1999 Biennial Decommissioning Funding Status Rept for Fort Calhoun Station,Unit 1 1999-09-08 |
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"" , -. M Omaha P7blicP7werD 444 South 16th Street Mall Omaha NE 68102-2247 August 6, 1996 LIC-96-0106 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, D.C. 20555
References:
- 1. Docket No. 50-285
- 2. Letter from 0 PPD (W. G. Gates) to NRC (Document Control Desk) dated November 16, 1995 (LIC-95-0218)
- 3. Letter from NRC (L. R. Wharton) to OPPD (T. L. Patterson) dated July 5, 1996
Subject:
Response to Request for Additional Information (RAI) on Technical Specification Change Related to Safety-Related Inverters (TAC No.
M94814)
On July 8,1996, the Omaha Public Power District (0 PPD) received the NRC's RAI relative to OPPD's Technical Specification change provided in Reference 2.
Attached please find OPPD's response to.this RAI.
If you should have any questions, please contact me.
Sincerely,
.b T. L. Patterson Division Manager Nuclear Operations Attachment TLP/dll c: Winston & Strawn (w/o Attachment) l !
L. J. Callan, NRC Regional Administrator, Region IV i L. R. Wharton, NRC Project Manager W. C. Walker, NRC Senior Resident Inspector ;
9608120341 960806 I PDR ADOCK 05000285 p PDR 45.512A Employrrent with EqualOpportunny I
LIC-96-0106 Attachment Page 1 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION UNIT NO. 1 RESPONSE TO REQUEST FOR INFORMATION (RAI)
TECHNICAL SPECIFICATION CHANGE RELATED TO SAFETY-RELATED INVERTERS NRC Reauest No. 1:
Please provide a brief electrical design description addressing the Fort Calhoun technical specification change for safety-relsted and non-safety inverters, attendant 120 Vac buses, and alternate power ::srce or sources for these buses.
OPPD Response:
Please refer to the Fort Calhoun Station (FCS) Updated Safety Analysis Report (USAR) Section 8.3.5 and Figure 8.1-1, which provide the appropriate information.
NRC Reauest No. 2:
Explain why removing 120 Vac instrument panels AI-42A and AI-42B from the Fort Calhoun technical specifications will not result in degrading the treatment of the inverters that normally supply power to these panels.
OPPD Response:
Under the Maintenance Rule for component reliability and demand failures, the non-safety-related inverters on the 120 VAC instrument panels AI-42A and AI-428 will be treated the same as the safety-related inverters.
Preventative maintenance on the inverters is perfonned consistent with the reliability centered maintenance practices in accordance with the FCS Preventive Maintenance (PM) program. The ability to perform maintenance on the inverters is enhanced by allowing more time for troubleshooting and corrective maintenance.
As noted in a telephone conference on June 27, 1996 between OPPD and the NRC/NRR, OPPD has performed a study which concluded that in a normal plant alignment, loss of AI-42A and AI-42B will not result in a plant trip.
i TIC-9ff-0106 Attachment Page 2 i
! NRC Reauest No. 3:
1 The Standard Technical Specifications explicitly notes that two hours are permitted for a normally inverter-supplied 120 VAC vital bus to be connected to an alternate power source if the inverter. is inoperable.
Explain why the proposed Fort Calhoun Technical Specification change does not explicitly address this.
OPPD Response:
i As stated on page 2 of the application for amendment, the note in the l Standard Technical Specifications is not applicable because Technical Specification (TS) 2.7(2) only allows one of the conditions listed in TS , 2.7(2). The Standard TS have two separate Limiting Conditions for l Operation (LCO), one for the inverter and one for the vital bus, that can l be entered simultaneously. The two hours is the time allowed by the LC0 l for an inoperable vital bus in Standard TS. The current revision of the Standard TS (NUREG-1432 Rev.1) no longer states the two hour requirement, l it only directs that the LC0 for distribution systems be entered with any vital bus de-energized.
l Since TS 2.7(2) only allows one of the conditions listed, having both an inverter and vital bus inoperable at the same time is a circumstance in l excess of those addressed by TS 2.7, which requires entry into TS 2.0.1 and a plant shutdown. The proposed change is more conservative than the Standard TS because it would not allow any vital bus to be de-energized at
- the same time an inverter is inoperable.
! NRC Reauest No. 4:
Verify that for the proposed technical specification change regarding safety-related and non-safety inverters that the battery equalizing charges are applied with these inverters in operation.
OPPD Response:
Both safety-related and non-safety-related inverters are used continuously while their station battery feed is under equalize charge. The equalizing charge voltage of the station batteries is 136 1 0.5 VDC. Inverter input is rated up to 140 VDC.
l