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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20211J9321999-09-0202 September 1999 Safety Evaluation Concluding That Licensee Proposed Alternatives Provide Acceptable Level of Quality & Safety. Proposed Alternatives Authorized for Remainder of Third ten- Yr ISI Interval for Fort Calhoun Station,Unit 1 ML20210G2181999-07-27027 July 1999 Safety Evaluation Supporting Amend 192 to License DPR-40 ML20210D9951999-07-22022 July 1999 Safety Evaluation Supporting Amend 191 to License DPR-40 ML20206L4241999-05-10010 May 1999 Safety Evaluation Supporting Corrective Actions to Ensure That Valves Are Capable of Performing Intended Safety Functions & OPPD Adequately Addressed Requested Actions Discussed in GL 95-07 ML20206M2601999-05-0606 May 1999 SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History ML20205Q5831999-04-15015 April 1999 Safety Evaluation Supporting Amend 190 to License DPR-40 ML20198S3771998-12-31031 December 1998 Safety Evaluation Supporting Amend 189 to License DPR-40 ML20198S4831998-12-31031 December 1998 Safety Evaluation Supporting Amend 188 to License DPR-40 ML20154M4881998-10-19019 October 1998 Safety Evaluation Supporting Amend 186 to License DPR-40 ML20154N2411998-10-19019 October 1998 Safety Evaluation Supporting Amend 187 to License DPR-40 ML20236V4891998-07-30030 July 1998 Safety Evaluation Relating to Response to GL 87-02,suppl 1 for Fort Calhoun Station,Unit 1 ML20248C0671998-05-21021 May 1998 Safety Evaluation Granting Licensee Request for Exemption from Technical Requirements of 10CFR50,App R, Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101 ML20217L7201998-03-23023 March 1998 Safety Evaluation Supporting Amend 185 to License DPR-40 ML20203M4161998-02-0303 February 1998 Safety Evaluation Supporting Amend 184 to License DPR-40 ML20203A4291998-01-26026 January 1998 Safety Evaluation Supporting Amend 183 to License DPR-40 ML20199L0711997-11-24024 November 1997 Safety Evaluation Supporting Amend 182 to License DPR-40 ML20198Q4031997-10-28028 October 1997 Safety Evaluation Re Control Room Habitability Requirements ML20137L6241997-03-27027 March 1997 Safety Evaluation Supporting Amend 181 to License DPR-40 ML20134N7751997-02-13013 February 1997 Safety Evaluation Supporting Amend 180 to License DPR-40 ML20134M6171997-02-13013 February 1997 Safety Evaluation Denying Licensee Request for Approval to Use ASME Section XI Code Case N-416-1 W/Proposed Exception & Code Case N-498-2 as Alternative to Required Hydrostatic Pressure Test ML20133P9161997-01-23023 January 1997 Safety Evaluation Accepting Revised Temperature Limits for DG-1 & DG-2 ML20133C2771996-12-30030 December 1996 Safety Evaluation Supporting Amend 179 to License DPR-40 ML20132F4911996-12-0909 December 1996 Safety Evaluation Related to Individual Plant Evaluation Omaha Power District,Fort Calhoun Station,Unit 1 ML20134M0871996-11-19019 November 1996 Safety Evaluation Supporting Request for Relief from Modifying Supports SIH-3,SIS-63,SIS-65 & RCH-13 at Fort Calhoun Station ML20129H3371996-10-25025 October 1996 Safety Evaluation Supporting Amend 178 to License DPR-40 ML20128F6441996-10-0202 October 1996 Safety Evaluation Supporting Amend 177 to License DPR-40 ML20129G3131996-09-27027 September 1996 Safety Evaluation Supporting Amend 176 to License DPR-40 ML20059J1831994-01-14014 January 1994 Safety Evaluation Supporting Amend 160 to License DPR-40 ML20059J2491994-01-14014 January 1994 Safety Evaluation Supporting Amend 159 to License DPR-40 ML20058G9371993-12-0303 December 1993 Safety Evaluation Supporting Amend 158 to License DPR-40 ML20058F5951993-11-22022 November 1993 Safety Evaluation Supporting Amend 157 to License DPR-40 ML20058C7491993-11-18018 November 1993 Safety Evaluation,Authorizing Alternative,On One Time Basis Only,W/Conditions That Licensee Perform Volumetric Exam of nozzle-to-vessel Welds During First Refueling Outage of Third 10-yr Insp Interval ML20059L7081993-11-10010 November 1993 Safety Evaluation Accepting Licensee Proposed Changes to Low Power Physics Testing Program ML20059G6601993-10-29029 October 1993 Safety Evaluation Supporting Amend 156 to License DPR-40 ML20057E3471993-10-0101 October 1993 Safety Evaluation Advising That Based on Determination That Alternative Testing Consistent w/OM-10,paragraph 4.3.2.2. Requirements,No Relief Required ML20056E5411993-08-12012 August 1993 Safety Evaluation Supporting Amend 155 to License DPR-40 ML20056E5371993-08-10010 August 1993 Safety Evaluation Supporting Amend 154 to License DPR-40 ML20056D6801993-07-26026 July 1993 Safety Evaluation Supporting Amend 153 to License DPR-40 ML20128B8241993-01-26026 January 1993 Safety Evaluation Supporting Amend 149 to License DPR-40 ML20128D4511992-11-30030 November 1992 Safety Evaluation Accepting Evaluation of 120-day Response to Suppl 1 to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors, Unresolved Safety Issue A-46 ML20062G6621990-11-19019 November 1990 Safety Evaluation Supporting Amend 134 to License DPR-40 ML20216K0661990-11-14014 November 1990 Safety Evaluation Denying Util 900221 & 0622 Requests for Exemption from App R of 10CFR50 for Fire Area 34B,upper Electrical Penetration Room.Current Level of Fire Protection Does Not Meet Section III.G.2 Requirements ML20062B6161990-10-12012 October 1990 Safety Evaluation Supporting Amend 133 to License DPR-40 ML20055G0221990-07-0606 July 1990 Safety Evaluation Supporting Amend 132 to License DPR-40 ML20246A0741989-08-17017 August 1989 Safety Evaluation Re Inservice Testing Program for Pumps & Valves ML20245H9031989-08-15015 August 1989 Safety Evaluation Re Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components). Licensee Program Meets Requirements of Item 2.1 (Part 1) of Generic Ltr 83-28 & Acceptable ML20245K3481989-08-11011 August 1989 Safety Evaluation Accepting Electrical Isolation Devices for Interfacing Safety & Nonsafety Sys Re Implementation of ATWS Rule ML20247H6421989-07-24024 July 1989 Safety Evaluation Granting 890118 Request for Relief from Hydrostatic Testing Requirements of Section XI of ASME Code ML20248C0851989-06-0202 June 1989 Safety Evaluation Supporting Amend 122 to License DPR-40 1999-09-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data LIC-99-0096, Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With ML20211J9321999-09-0202 September 1999 Safety Evaluation Concluding That Licensee Proposed Alternatives Provide Acceptable Level of Quality & Safety. Proposed Alternatives Authorized for Remainder of Third ten- Yr ISI Interval for Fort Calhoun Station,Unit 1 LIC-99-0084, Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With ML20216E6431999-08-26026 August 1999 Rev 19 to TDB-VI, COLR for FCS Unit 1 ML20210R1961999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fcs,Unit 1 ML20210G2181999-07-27027 July 1999 Safety Evaluation Supporting Amend 192 to License DPR-40 ML20210D9951999-07-22022 July 1999 Safety Evaluation Supporting Amend 191 to License DPR-40 ML20216E6361999-07-21021 July 1999 Rev 18 to TDB-VI, COLR for FCS Unit 1 ML20210R2081999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Fcs,Unit 1 LIC-99-0065, Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20210P5461999-06-0808 June 1999 Rev 0,Vols 1-5 of Fort Calhoun Station 1999 Emergency Preparedness Exercise Manual, to Be Conducted on 990810. Pages 2-20 & 2-40 in Vol 2 & Page 4-1 in Vol 4 of Incoming Submittal Not Included ML20195B4581999-05-31031 May 1999 Rev 3 to CE NPSD-683, Development of RCS Pressure & Temp Limits Rept for Removal of P-T Limits & LTOP Requirements from Ts ML20207H7401999-05-31031 May 1999 Performance Indicators Rept for May 1999 LIC-99-0053, Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 11999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 1 ML20195B4521999-05-17017 May 1999 Technical Data Book TDB-IX, RCS Pressure - Temp Limits Rept (Ptlr) ML20206L4241999-05-10010 May 1999 Safety Evaluation Supporting Corrective Actions to Ensure That Valves Are Capable of Performing Intended Safety Functions & OPPD Adequately Addressed Requested Actions Discussed in GL 95-07 ML20206M2601999-05-0606 May 1999 SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History LIC-99-0047, Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With ML20195E8621999-04-30030 April 1999 Performance Indicators, for Apr 1999 ML20205Q5831999-04-15015 April 1999 Safety Evaluation Supporting Amend 190 to License DPR-40 ML20210J4331999-03-31031 March 1999 Changes,Tests, & Experiments Carried Out Without Prior Commission Approval for Period 981101-990331.With USAR Changes Other than Those Resulting from 10CFR50.59 ML20206G2641999-03-31031 March 1999 Performance Indicators Rept for Mar 1999 LIC-99-0034, Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With ML20205J8181999-02-28028 February 1999 Performance Indicators, for Feb 1999 LIC-99-0025, Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With ML20207F3291999-01-31031 January 1999 FCS Performance Indicators for Jan 1999 ML20203B0991998-12-31031 December 1998 Performance Indicators for Dec 1998 LIC-99-0026, 1998 Omaha Public Power District Annual Rept. with1998-12-31031 December 1998 1998 Omaha Public Power District Annual Rept. with LIC-99-0003, Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With ML20198S3771998-12-31031 December 1998 Safety Evaluation Supporting Amend 189 to License DPR-40 ML20198S4831998-12-31031 December 1998 Safety Evaluation Supporting Amend 188 to License DPR-40 ML20196G2251998-12-18018 December 1998 Rev 2 to EA-FC-90-082, Potential Over-Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment ML20198M3141998-11-30030 November 1998 Performance Indicators Rept for Nov 1998 LIC-98-0172, Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With LIC-98-0160, Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated1998-11-25025 November 1998 Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated ML20203B0721998-11-16016 November 1998 Rev 6 to HI-92828, Licensing Rept for Spent Fuel Storage Capacity Expansion ML20196E4981998-10-31031 October 1998 Performance Indicators Rept for Oct 1998 ML20196G2441998-10-31031 October 1998 Changes,Tests & Experiments Carried Out Without Prior Commission Approval. with USAR Changes Other than Those Resulting from 10CFR50.59 LIC-98-0154, Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With ML20154M4881998-10-19019 October 1998 Safety Evaluation Supporting Amend 186 to License DPR-40 ML20154N2411998-10-19019 October 1998 Safety Evaluation Supporting Amend 187 to License DPR-40 LIC-98-0136, Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Fort Calhoun Station,Unit 1.With ML20155G4261998-09-30030 September 1998 Performance Indicators for Sept 1998 ML20154A1251998-08-31031 August 1998 Performance Indicators, Rept for Aug 1998 LIC-98-0122, Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Fort Calhoun Station Unit 1.With ML20238F7231998-08-17017 August 1998 Owner'S Rept for Isis ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency 1999-09-30
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NUCLEAR REGULATORY COMMISSION
.* 2 WASHINGTON, D.C. 30006 0001 i fD, .
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.180 TO FACILITY OPERATING LICENSE NO. DPR-40 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION. UNIT NO. 1 QQCKET NO. 50-285
1.0 INTRODUCTION
By application dated November 16, 1995, as supplemented by letter dated August 8,1996, Omaha Public Power District (OPPD) requested changes to the l Technical Specifications (Appendix A to Facility Operating License No. DPR-40) for the Fort Calhoun Station, Unit No. 1 (FCS). The requested changes would revise TS 2.7, " Electrical Systems," and TS 3.7, " Emergency Power System Periodic Tests." The changes include adding the safety-related inverters A, B, C, and D into the technical specifications (TSs) with a limiting condition for operation along with a surveillance test for the inverters, and deleting the nonsafety related instruments buses, which include inverters #1 and #2, from the TS.
The August 8,1996, supplemental letter provided additional clarifying information that did not change the initial no significant hazards consideration determination published in the Federal Register on March 13, 1996 (61 FR 10395).
2.0 BACKGROUND
The FCS a-c instrument system is comprised of six separate buses, four of which supply power to safety-related instrumentation. Each instrument bus is supplied by a separate solid-state inverter which receives input power from the d-c system. Safety-related inverters identified as A, B, C, and D are single phase 120-volts i 2 percent and are rated 7.5 KVA at a 0.8 power factor. The remaining two inverters identified as il and #2 are single-phase 120-volts i 2 percent and are rated 10 KVA at a 0.8 power factor.
Each of the instrument inverters that supply power to the instrument buses has a bypass source which supplies power to the bus when there is an inverter failure or when inverter maintenance is necessary. In the event of inverter failure, the load on the inverter is automatically transferred to the bypass source. The bypass source is supplied with power from the 480-volt distribution system. In addition to the bypass transformers, inverters #1 and
- 2 each have a dedicated test transformer that can supply convenience power to instrument buses 1 and 2 respectively when the normal inverter / bypass power supply is unavailable.
9702240438 970213 PDR P
ADOCK 05000205 PDR
.. Annunciation in the main control room is provided for all instrument buses upon detection of low bus voltage. Each inverter has its own annunciator point in the control room that is actuated when the inverter is in an off-normal condition.
3.0 EVALUATION The licensee has proposed the following specific changes to the FCS TSs:
Change 1: Under Specification 2.7, (1) Minimum Requirements, part (j.),
delete "120V a-c instrument panels AI-42A and AI-42B" and add
" Inverters A, B, C, and D."
Change 2: Under Specification 2.7, (1) Minimum Requirements, part (o.),
delete "Either one of the 120V a-c instrument panels AI-42A or AI-42B may be inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />" and add "One inverter (A, B, C, or D) may be inoperable for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided the reactor protective and engineered safeguards systems instrument channels supplied by the remaining three inverters are all operable and the 120V a-c instrument bus associated with the inoperable inverter is powered from its bypass source."
Change 3: Under Basis, add a final paragraph: "The time allowed to repair an inoperable inverter is based upon engineering judgement, taking into consideration the time required to repair an inverter and the additional risk to which the unit is exposed because of the inverter inoperability. In the event of inverter failure, the load on the inverter is automatically transferred to its safety related bypass source. The associated 120V a-c instrument bus is considered OPERABLE when it is being powered from its bypass source and during the short time it takes to manually or automatically transfer between sources."
Change 4: Under 3.7 Emergency Power System Periodic Tests, add "(5)
Inverters A, B, C and D. The correct inverter output (voltage, frequency, and alignment to required 120V a-c instrument buses) shall be verified weekly."
The staff expressed the concern that deleting the 120V a-c instrument panels AI-42A and AI-428 from the TSs may result in degrading the treatment of the inverters that normally supply power to these panels. If this were the case, the number of occurrences of loss of power output from these inverters would increase with an attendant increase in the number of occurrences involving loss of power from these panels. Thus, the potential for increasing the number of plant transients may result from this TS change due to the increased number of occurrences of loss of power from one or both of these panels. In response to this concern, the licensee stated that under the maintenance rule for the component reliability and demand failures, the nonsafety related inverters on the 120V a-c instrument panels AI-42A and AI-42B will be treated the same as the safety-related inverters. Preventative maintenance on the
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- inverters is performed consistent with the reliability-centered maintenance practices in accordance with the Fort Calhoun Station preventative maintenance I
program. Further, the licensee stated that OPPD had 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 i During its review, the staff also indicated that the Standard Technical
- Specifications (STS) explicitly notes that two hours are permitted for a
- normally inverter-supplied 120V a-c vital bus to be connected to an alternate j power source if the inverter is inoperable. However, the proposed TS change i does not explicitly address this. In response to this issue, the licensee j documents that TS 2.7(2) only allows either the inverter or the vital bus to i be inoperable. The STS have two separate limiting conditions for operation j (LC0), one for the inverter and one for the vital bus, that can be entered a simultaneously. The two hours is the time allowed by the LCO for an l inoperable vital bus in the STS. Since TS 2.7(2) only allows one of the i conditions listed, having both an inverter and vital bus inoperable at the i same time is a circumstance in excess of those addressed by TS 2.7, which
! requires entry into TS 2.0.1 and a plant shutdown. Thus, the proposed change j is more conservative thar, the STS because it would not allow any vital bus to be de-energized at the same time an inverter is inoperable.
I The change permitting an inverter to be inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> versus the current 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is consistent'with the STS requirement. The 24-hour limit is based upon engineering judgment taking into consideration the time required to repair an inverter and the additional risk to which the unit is exposed !
because of the inverter inoperability. This is balanced against the risk of j an immediate shutdown, along with the potential challenges to safety systems l such a shutdown might entail. The weekly TS surveillance requirement is also '
consistent with STS requirements.
On the basis of the above, the staff concludes that the proposed TS changes are technically adequate, consistent with STS requirements, and are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Nebraska State official was notified of the proposed issuance of the amendment. The State official i had no comments. 1 5.0 ENVIR0 MENTAL CONSIDERATION The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has detemined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (61 FR 10395). Accordingly, the amendment
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j I meets the eligibility criteria for categorical exclusion set forth in 10 CFR 1
51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or i
environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. i l
Principal Contributor: L. Cupidon
! Date: February 13, 1997 i
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