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| | document type = SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES, TEXT-SAFETY REPORT | | | document type = SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES, TEXT-SAFETY REPORT |
| | page count = 2 | | | page count = 2 |
| | project = | | | project = TAC:61259 |
| | stage = Approval | | | stage = Approval |
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| 4;:? o g UNITED STATES e o NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 h | | 4;:? o g UNITED STATES e o NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 h |
| l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO APPENDIX R, 10 CFR PART 50, FIRE PROTECTION MODIFICATIONS OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. 1 DOCKET NO. 50-285 INTRODUCTION In a safety evaluation (SE) dated July 3, 1985, the staff granted a number of exemptions to the fire protection requirements of Appendix R to 10 CFR Part 50. | | l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO APPENDIX R, 10 CFR PART 50, FIRE PROTECTION MODIFICATIONS OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. 1 DOCKET NO. 50-285 INTRODUCTION In a safety evaluation (SE) dated July 3, 1985, the staff granted a number of exemptions to the fire protection requirements of Appendix R to 10 CFR Part 50. |
| By letter dated April 9,1986, the licensee provided clarifications to certain statements in the SE and requested approval of several changes in their approach toward satisfying previous commitments. | | By {{letter dated|date=April 9, 1986|text=letter dated April 9,1986}}, the licensee provided clarifications to certain statements in the SE and requested approval of several changes in their approach toward satisfying previous commitments. |
| EVALUATION In the SE, the staff stated that the licensee had committed to install a radiant energy shield between junction boxes JB-103C and JB-252C. Sub-sequently, JB-252C was relocated such that both junction boxes are separated by a radiant energy shield between two other components. The new configuration conforms with Section III.G. of Appendix R and is, therefore, acceptable. | | EVALUATION In the SE, the staff stated that the licensee had committed to install a radiant energy shield between junction boxes JB-103C and JB-252C. Sub-sequently, JB-252C was relocated such that both junction boxes are separated by a radiant energy shield between two other components. The new configuration conforms with Section III.G. of Appendix R and is, therefore, acceptable. |
| In the SE, the staff stated that the cables for valves HCV-240 and HCV-249 would be protected by either a " fire wrap or a thermal energy shield." The licensee subsequently completed modifications that resulted in these cables being protected by radiant energy shielding and 20 feet of special separation as described in the April 9, 1985 letter. The stcff's conclusion as to the acceptability of the protection for these cables remains valid. | | In the SE, the staff stated that the cables for valves HCV-240 and HCV-249 would be protected by either a " fire wrap or a thermal energy shield." The licensee subsequently completed modifications that resulted in these cables being protected by radiant energy shielding and 20 feet of special separation as described in the {{letter dated|date=April 9, 1985|text=April 9, 1985 letter}}. The stcff's conclusion as to the acceptability of the protection for these cables remains valid. |
| In the SE, the staff stated that shields will be erected in the air compressor room to protect safe shutdown equipment such as the motor driven auxiliary I feedwater pump. However, the installation of shielding above the equipment could adversely affect fire protection capability by dissipating the thermal column from a fire detector that is necessary for detection and could obstruct the water pattern from the ceiling-level sprinkler heads. For these reasons, the licensee has not installed the shields. Because the Preaction-type sprinkler system is not prone to inadvertent water discharge and because a horizontal barrier exists between the motor driven and steam powered auxiliary feedwater pumps, the staff considers the absence of umbrella-type shields above the electrical equipment to be acceptable. | | In the SE, the staff stated that shields will be erected in the air compressor room to protect safe shutdown equipment such as the motor driven auxiliary I feedwater pump. However, the installation of shielding above the equipment could adversely affect fire protection capability by dissipating the thermal column from a fire detector that is necessary for detection and could obstruct the water pattern from the ceiling-level sprinkler heads. For these reasons, the licensee has not installed the shields. Because the Preaction-type sprinkler system is not prone to inadvertent water discharge and because a horizontal barrier exists between the motor driven and steam powered auxiliary feedwater pumps, the staff considers the absence of umbrella-type shields above the electrical equipment to be acceptable. |
| l In the SE, the staff stated that an area-wide sprinkler system was to be installed in fire area 32. Fire area 32 consists of the air compressor room at elevation 989 feet and a small corridor at elevation 1011 feet. The l | | l In the SE, the staff stated that an area-wide sprinkler system was to be installed in fire area 32. Fire area 32 consists of the air compressor room at elevation 989 feet and a small corridor at elevation 1011 feet. The l |
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| In the SE, the staff stated that power feeder cables in the lower electrical penetration room for MCC's - 3A1, 381 and 3C1 would be rerouted inside the room in conduits and protected by a 1-hour fire-rated barrier. Instead of the above, the licensee indicated that these cables have been rerouted outside of the fire area. This change conforms with the requirements of Section III.G. | | In the SE, the staff stated that power feeder cables in the lower electrical penetration room for MCC's - 3A1, 381 and 3C1 would be rerouted inside the room in conduits and protected by a 1-hour fire-rated barrier. Instead of the above, the licensee indicated that these cables have been rerouted outside of the fire area. This change conforms with the requirements of Section III.G. |
| of Appendix R and is therefore, acceptable. | | of Appendix R and is therefore, acceptable. |
| CONCULSION Based on the evaluation of the information contained in the licensee's April 9, 1986 letter, the staff considers the above referenced changes and clarifi-cations to be in conformance with the requirements of Section III.G. of Appendix R to 10 CFR Part 50 and are acceptable. Thus, the staff's previous conclusion regarding Appendix R compliance for Ft. Calhoun is still valid. | | CONCULSION Based on the evaluation of the information contained in the licensee's {{letter dated|date=April 9, 1986|text=April 9, 1986 letter}}, the staff considers the above referenced changes and clarifi-cations to be in conformance with the requirements of Section III.G. of Appendix R to 10 CFR Part 50 and are acceptable. Thus, the staff's previous conclusion regarding Appendix R compliance for Ft. Calhoun is still valid. |
| Principal Contributor: D. Kubicki Date: | | Principal Contributor: D. Kubicki Date: |
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MONTHYEARML20202J5181986-04-0909 April 1986 Discusses Steps Taken to Comply W/Commitments to Perform Mods Underlying Requests for Exemptions from 10CFR50 App R. Installation of Radiant Energy Shields Completed During 1985 Refueling Outage Project stage: Other ML20199J0421986-07-0101 July 1986 Safety Evaluation Supporting Util 860409 Clarifications to NRC 850703 Safety Evaluation Granting Exemptions to Fire Protection Requirements of App R to 10CFR50 Project stage: Approval ML20199J0351986-07-0101 July 1986 Forwards Safety Evaluation Supporting Exemptions & Deviations Re Fire Protection Mods Per App R to 10CFR50 as Committed to in Util Project stage: Approval 1986-04-09
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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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4;:? o g UNITED STATES e o NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 h
l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO APPENDIX R, 10 CFR PART 50, FIRE PROTECTION MODIFICATIONS OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. 1 DOCKET NO. 50-285 INTRODUCTION In a safety evaluation (SE) dated July 3, 1985, the staff granted a number of exemptions to the fire protection requirements of Appendix R to 10 CFR Part 50.
By letter dated April 9,1986, the licensee provided clarifications to certain statements in the SE and requested approval of several changes in their approach toward satisfying previous commitments.
EVALUATION In the SE, the staff stated that the licensee had committed to install a radiant energy shield between junction boxes JB-103C and JB-252C. Sub-sequently, JB-252C was relocated such that both junction boxes are separated by a radiant energy shield between two other components. The new configuration conforms with Section III.G. of Appendix R and is, therefore, acceptable.
In the SE, the staff stated that the cables for valves HCV-240 and HCV-249 would be protected by either a " fire wrap or a thermal energy shield." The licensee subsequently completed modifications that resulted in these cables being protected by radiant energy shielding and 20 feet of special separation as described in the April 9, 1985 letter. The stcff's conclusion as to the acceptability of the protection for these cables remains valid.
In the SE, the staff stated that shields will be erected in the air compressor room to protect safe shutdown equipment such as the motor driven auxiliary I feedwater pump. However, the installation of shielding above the equipment could adversely affect fire protection capability by dissipating the thermal column from a fire detector that is necessary for detection and could obstruct the water pattern from the ceiling-level sprinkler heads. For these reasons, the licensee has not installed the shields. Because the Preaction-type sprinkler system is not prone to inadvertent water discharge and because a horizontal barrier exists between the motor driven and steam powered auxiliary feedwater pumps, the staff considers the absence of umbrella-type shields above the electrical equipment to be acceptable.
l In the SE, the staff stated that an area-wide sprinkler system was to be installed in fire area 32. Fire area 32 consists of the air compressor room at elevation 989 feet and a small corridor at elevation 1011 feet. The l
1 l e607080092 e60701 PDR ADOCK 05000285 F PDR
staff's concern for adequate fire protection features centered on the air compressor room only since no redundant cables or equipment required for safe shutdown are located in the corridor. The licensee has provided automatic sprinkler protection for the air compressor room, but not in the corridor.
Because there are no shutdown systems in the corridor and because it is not credible for a fire to start on elevation 1011 feet and spread downward, the absence of sprinklers in the corridor is considered acceptable.
In the SE, the staff stated that "... spray nozzles will be installed with cable trays to provide adequate coverage ...". This language is incorrect and should read "... spray nozzles will be installed along the cable trays to provide adequate coverage ..." (emphasis added).
In the SE, the staff stated that power feeder cables in the lower electrical penetration room for MCC's - 3A1, 381 and 3C1 would be rerouted inside the room in conduits and protected by a 1-hour fire-rated barrier. Instead of the above, the licensee indicated that these cables have been rerouted outside of the fire area. This change conforms with the requirements of Section III.G.
of Appendix R and is therefore, acceptable.
CONCULSION Based on the evaluation of the information contained in the licensee's April 9, 1986 letter, the staff considers the above referenced changes and clarifi-cations to be in conformance with the requirements of Section III.G. of Appendix R to 10 CFR Part 50 and are acceptable. Thus, the staff's previous conclusion regarding Appendix R compliance for Ft. Calhoun is still valid.
Principal Contributor: D. Kubicki Date:
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