Similar Documents at Fermi |
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217N4381999-10-25025 October 1999 Safety Evaluation Supporting Amend 17 to License DPR-9 ML20206J9301999-05-10010 May 1999 SER Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Powered-Operated Gate Valves ML20206G5081999-05-0505 May 1999 Safety Evaluation Approving Request for Relief PR-8,Rev 2 on Basis That Licensee Committed to Meet All Related Requirements of ASME OM-6 Std & PR-12 on Basis That Proposed Alternative Will Provide Acceptable Level of Safety ML20205Q7141999-04-15015 April 1999 Safety Evaluation Supporting Amend 16 to License DPR-9 ML20204E0371999-03-17017 March 1999 Safety Evaluation Accepting Licensee Request for NRC Approval of Alternative Rv Weld Exam,Per Provisions of 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(ii)(A)(5) for Plant,Unit 2 for 40-month Period ML20198S3341999-01-0606 January 1999 Safety Evaluation Supporting Amend 15 to License DPR-9 ML20154R2331998-10-21021 October 1998 Safety Evaluation Supporting Amend 13 to License DPR-9 ML20154L1031998-10-14014 October 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode ML20153B8811998-09-18018 September 1998 Safety Evaluation Accepting Request for Relief from Certain Requirements of ASME Boiler & Pressure Vessel Code,Section Xi,For Plant,Unit 2 ML20151X0651998-09-11011 September 1998 Safety Evaluation Re Inservice Testing Program Relief Request VR-63 for Plant ML20237E1171998-08-25025 August 1998 Safety Evaluation Accepting Licensee Relief Requests for First 10-yr Interval Inservice Insp Nondestructive Exam Program ML20236X8611998-08-0505 August 1998 SER Related to Revised Feedwater Nozzle Analysis to Facility Operating License NPF-43,Enrico Fermi Nuclear Power Plant, Unit 2 ML20236K3261998-07-0101 July 1998 SER Accepting Licensee Response Related to Revised Feedwater Nozzle Analysis to License NPF-43 for Enrico Fermi Nuclear Power Plant,Unit 2 ML20198L4241998-01-0808 January 1998 Safety Evaluation Accepting Proposed Rev 2 to Relief Request VR-51 Under Fermi 2 Pump & Valve Inservice Testing Program Per 10CFR50.55a(f)(6)(i) for First 10-yr Interval ML20217E9071997-10-0202 October 1997 Safety Evaluation Accepting Licensee Request for Relief from Certain ISI Requirements of ASME Boiler & Pressure Vessel Code,Section XI for Plant,Unit 2 ML20210R0501997-08-22022 August 1997 Safety Evaluation Accepting Revised Fermi-2 Control Ctr HVAC Sys Design Criteria in Design Criteria Document Submitted by Detroit Edison ML20138L7961997-02-19019 February 1997 SER Related to Inservice Testing Program Relief Request Detroit Edison Co,Fermi Unit 2 ML20133L7371997-01-0202 January 1997 Safety Evaluation Supporting Amend 11 to License DPR-9 ML20059J4591994-01-25025 January 1994 Safety Evaluation Supporting Request for Relief from ASME Code Re Inservice Testing Requirements to Measure Vibration Amplitude Displacement ML20125C8041992-12-0808 December 1992 Safety Evaluation Accepting Util 920729 Revised Feedwater Nozzle Analysis for Plant,Per Generic Ltr 81-11 ML20246B2891989-04-28028 April 1989 Safety Evaluation Supporting Amend 9 to License DPR-9 ML20244B7141989-04-0404 April 1989 SER Accepting Util Responses to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability ML20237A7051987-12-10010 December 1987 Safety Evaluation Re Util Response to Generic Ltr 83-28, Item 2.1,Part 2 Requiring Confirmation That Interface Established W/Nsss or W/Vendors of Each Reactor Trip Sys Components.Response Acceptable ML20237A6971987-12-10010 December 1987 Safety Evaluation Re Util Response to Generic Ltr 83-28, Item 2.1,Part 1 Requiring Confirmation That All Reactor Trip Sys Components Identified as safety-related.Response Acceptable ML20237B4091987-12-0808 December 1987 SER Accepting Util Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing (Reactor Trip Sys Components, All Other safety-related Components) ML20236L6551987-11-0404 November 1987 SER Re Generic Ltr 83-28,Item 2.2.1, Equipment Classification Programs for All Safety-Related Components. Util 831103 Response Acceptable ML20236A3981987-10-15015 October 1987 Safety Evaluation Re Potential Hazards Associated W/ Operation of & Potential Explosion Accidents at Rockwood Stone,Inc Quarry.Hazards Considered Insignificant,Based on Util Confirmatory Analysis & Independent NRC Evaluation ML20235S8731987-10-0606 October 1987 Safety Evaluation Re First 10-yr Interval Inservice Insp Program.Relief Granted from Exam & Testing Requirements of ASME Code & Alternate Methods Imposed Through Document ML20236D7421987-07-28028 July 1987 Safety Evaluation Re Main Steam Instrument Line Leaks. Licensee Satisfactorily Resolved Problems Re Main Steam Instrument Line Leaks Which Occurred in Jan 1987 & Recurred in Apr 1987 ML20206B5371987-04-0707 April 1987 Safety Evaluation Supporting Util Request to Amend License Condition 2.C(10), Emergency Diesel Generator Lube Oil Surveillance Program. NRC Does Not Agree Condition Should Be Revised by Substituting for Mar 1985 Ltr ML20207R8541987-03-12012 March 1987 Safety Evaluation Re Facility Mark I Containment Vacuum Breaker Structural Integrity.Licensee Restored Safety Margins of Breakers by Replacing Critical Parts W/Adequate Matl.Corrective Action Acceptable ML20212E3161987-02-27027 February 1987 Safety Evaluation Re Operation of Rockwood Stone,Inc Quarry Near Plant ML20212J8421987-02-26026 February 1987 Safety Evaluation Approving Individual to Serve as Shift Operations Advisor,Per Generic Ltr 84-16 IR 05000341/19850501987-01-16016 January 1987 Safety Evaluation Re Proposed Fire Protection Mod to Independent Alternative Safe Shutdown Capability to Satisfy Open Items in Insp 50-341/85-50 ML20215E0061986-12-12012 December 1986 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification of Reactor Trip Sys Components ML20203L5701986-08-19019 August 1986 Safety Evaluation Supporting Proposed Tech Specs Re Alternative Shutdown Sys.Acceptability Based,In Part,On Performance of Tests in Accordance W/Reg Guide 1.68, Initial Test Programs for Water-Cooled Nuclear Plants ML20207H5551986-07-16016 July 1986 SER Re Corrective Actions for Emergency Diesel Generators. Concurs W/Licensee Proposed Special Bearing Insp,Provided Envelope Provided by Demonstration Test Program Not Exceeded ML20154L4261985-04-18018 April 1985 Safety Evaluation Supporting 1983 ASME Code,Section XI, Paragraph IWV-3520 Requirement for Periodic Closure Verification Testing of Normally Closed Check Valves w/safety-related Functions 1999-05-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N4381999-10-25025 October 1999 Safety Evaluation Supporting Amend 17 to License DPR-9 ML20217P3551999-10-22022 October 1999 LER 99-S01-00:on 990922,loaded 9mm Handgun Was Discovered on Truck Cargo Area of Vehicle Inside Protected Area.Caused by Inadequate Vehicle Search.Guidance in Procedures & Security Training to Address Multiple Vehicle Searches Was Provided NRC-99-0095, Monthly Operating Rept for Sept 1999 for Fermi 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fermi 2.With NRC-99-0067, Monthly Operating Rept for Aug 1999 for Fermi 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fermi 2.With NRC-99-0065, Monthly Operating Rept for July 1999 for Fermi 2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fermi 2.With NRC-99-0088, Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with1999-06-30030 June 1999 Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with NRC-99-0064, Monthly Operating Rept for June 1999 for Fermi 2.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fermi 2.With NRC-99-0062, Monthly Operating Rept for May 1999 for Fermi 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fermi 2.With ML20206J9301999-05-10010 May 1999 SER Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Powered-Operated Gate Valves ML20206G5081999-05-0505 May 1999 Safety Evaluation Approving Request for Relief PR-8,Rev 2 on Basis That Licensee Committed to Meet All Related Requirements of ASME OM-6 Std & PR-12 on Basis That Proposed Alternative Will Provide Acceptable Level of Safety NRC-99-0022, Monthly Operating Rept for Apr 1999 for Fermi 2.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fermi 2.With ML20205Q7141999-04-15015 April 1999 Safety Evaluation Supporting Amend 16 to License DPR-9 ML20205P9721999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fermi 2 ML20204E0371999-03-17017 March 1999 Safety Evaluation Accepting Licensee Request for NRC Approval of Alternative Rv Weld Exam,Per Provisions of 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(ii)(A)(5) for Plant,Unit 2 for 40-month Period ML20204D0361999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fermi 2 ML20198S3341999-01-0606 January 1999 Safety Evaluation Supporting Amend 15 to License DPR-9 NRC-99-0005, Monthly Operating Rept for Dec 1998 for Fermi 2.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fermi 2.With ML20207B7491998-12-31031 December 1998 1998 Annual Operating Rept for Fermi 2 ML20205Q9621998-12-31031 December 1998 Revised Monthly Operating Rept for Dec 1998 for Fermi 2 NRC-99-0021, 1998 Annual Financial Rept for Detroit Edison Co. with1998-12-31031 December 1998 1998 Annual Financial Rept for Detroit Edison Co. with NRC-98-0153, Monthly Operating Rept for Nov 1998 for Fermi 2.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fermi 2.With NRC-98-0160, Monthly Operating Rept for Oct 1998 for Fermi 2.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fermi 2.With ML20154R2331998-10-21021 October 1998 Safety Evaluation Supporting Amend 13 to License DPR-9 ML20154L1031998-10-14014 October 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode NRC-98-0139, Monthly Operating Rept for Sept 1998 for Fermi,Unit 2.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Fermi,Unit 2.With ML20154H8161998-09-30030 September 1998 Rev 0 to COLR Cycle 7 for Fermi 2 ML20153B8811998-09-18018 September 1998 Safety Evaluation Accepting Request for Relief from Certain Requirements of ASME Boiler & Pressure Vessel Code,Section Xi,For Plant,Unit 2 ML20151X0651998-09-11011 September 1998 Safety Evaluation Re Inservice Testing Program Relief Request VR-63 for Plant NRC-98-0111, Monthly Operating Rept for Aug 1998 for Fermi 2.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Fermi 2.With ML20153B7921998-08-31031 August 1998 Rev 0 to Fermi 1 Sar ML20237E1171998-08-25025 August 1998 Safety Evaluation Accepting Licensee Relief Requests for First 10-yr Interval Inservice Insp Nondestructive Exam Program ML20236X8611998-08-0505 August 1998 SER Related to Revised Feedwater Nozzle Analysis to Facility Operating License NPF-43,Enrico Fermi Nuclear Power Plant, Unit 2 NRC-98-0109, Monthly Operating Rept for July 1998 for Fermi 21998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Fermi 2 ML20236K3261998-07-0101 July 1998 SER Accepting Licensee Response Related to Revised Feedwater Nozzle Analysis to License NPF-43 for Enrico Fermi Nuclear Power Plant,Unit 2 NRC-98-0097, Monthly Operating Rept for June 1998 for Fermi,Unit 21998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Fermi,Unit 2 NRC-98-0127, Annual Rept for Period 970701-9806301998-06-30030 June 1998 Annual Rept for Period 970701-980630 NRC-98-0079, Monthly Operating Rept for May 1998 for Fermi 21998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Fermi 2 NRC-98-0076, Monthly Operating Rept for Apr 1998 for Fermi 21998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Fermi 2 NRC-98-0072, Monthly Operating Rept for Mar 1998 for Fermi 21998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Fermi 2 NRC-98-0050, Monthly Operating Rept for Feb 1998 for Fermi 21998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Fermi 2 NRC-98-0019, Monthly Operating Rept for Jan 1998 for Fermi 21998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Fermi 2 ML20198L4241998-01-0808 January 1998 Safety Evaluation Accepting Proposed Rev 2 to Relief Request VR-51 Under Fermi 2 Pump & Valve Inservice Testing Program Per 10CFR50.55a(f)(6)(i) for First 10-yr Interval NRC-98-0015, Monthly Operating Rept for Dec 1997 for Fermi 21997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Fermi 2 ML20217N3821997-12-31031 December 1997 Annual Operating Rept for 970101-1231 NRC-98-0053, 1997 Annual Financial Rept for Detroit Edison Company1997-12-31031 December 1997 1997 Annual Financial Rept for Detroit Edison Company ML20205Q9601997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Fermi 2 NRC-97-0141, Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility1997-12-23023 December 1997 Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility ML20197A9921997-12-15015 December 1997 Rev 0 to Efp,Unit 1 Fermi 1 Sar NRC-97-0131, Monthly Operating Rept for Nov 1997 for Fermi 21997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Fermi 2 ML20248H1151997-10-31031 October 1997 Rev 1 to Colr,Cycle 6 for Fermi 2 1999-09-30
[Table view] |
Inspection Report - Fermi - 1985050 |
---|
|
|
Text
- .
Enclosura
[er aeg)og UNITED STATES g g NUCLEAR REGULATORY COMMISSION 3 :p WASHINGTON, D. C. 20555
\~.../ SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION RilATIVE TO PROPOSFO FIRE PPOTECTION MODIFICATION TO INDEPENDENT ALTERNATIVE SAFE SHUTDOWN CAPAPILITY TO SATISFY OPEN ITFMS IN REGION III RFPORT OF SPECIAL INSPECTTON (REPORT NO. 50-341/R5050 (DRS)) LICENSE NO. NPF-43 DFTROIT EDIS0N COMPANY FERMI-2 DOCKET NO. 50-341 1.0 INTRODUCTION By letter dated October 22. 1984, the licensee made certain commitments to the NRC regardino installation of an independent alternative safe shutdown syste Later, the licensee identified three electrical cable feeds used in the independent alternative shutdown system that are routed through the fire areas of concern for which the shutdown system is prnvided. A fire in these areas could disable both the normal shutdown systems and the independent alternative shutdown system. By letter dated January 3, 1986, the licensee proposed a different solution for each of the three electrical cable feeds. In one case they proposed installing a one-hour fire barrier around the entire length of the alternative shutdown system cables where they pass through the fire area of concer In another case the licensee chose to protect the cabling for one of the redundant safe shutdown trains and not rely on the independent alternative safe shutdown syste In the third instance, the electrical cable feeds are in cable trays in a congested area which makes it unfeasible to provide a one-hour fire barrier wrap around the trays. The licensee now contends it is not necessary to provide the fire barrier wraps proposed in their January 3, 1986 letter for these trays. Although these trays contain several indication and control circuits needed for safe shutdown, the licensee now states that the indication functions are independently available elsewhere and one of the control functions can be accomplished manuall .0 EVAtVATION Electrical feed cable No. R.I. 005 ?P supplies power to DC distribution cabinet No. 2PB-7. This cabinet then supplies power to the safety relief valve (SRV) No F013G solenoid enabling contro1 of the SRV from the shutdown panel. This cable No. R.I. 005 2P originates at the Division II battery and is then routed down into Fire Zone 8, (the fire zone of concern for which this part of the alternative safe shutdown system was installed at the 631 ft, elevation in the Auxiliary Building. After passing through Fire 7one 8, the cable passes upward to the 2PD-2 distribution cabinet. The licensee has installed a 3M-brand one-hour fire barrier wrap on this cable throughout Fire Zone 8. In addition, Fire Zone 8 is protected by automatic fire detectors and 07013001DO DR 070116 ADOCK 05000341 PDR
-
- .
- .
-2-an automatic carbon dioxide fire suppression system. This combination of automatic fire detection and automatic fire suppression in con,iunction with one-hour fire barrier wrap conforms to the guidelines of the Standard Review Plan, Branch Technical Position 9.5-1 and is an acceptable method of fire protection for this electrical feed cable No. R.I. 005 2P. Therefore, Region III open item 341/85050-03 (6.g.(1) in Inspection Peport dated January 3, 1986)
is satisfie The other two electrical cable feeds in question are routed through Fire Zone AB-2. One of these, known as the Calvert Bus, is a 4160 volt power feed for the independent auxiliary safe shutdown system. The other involves three cable trays (2K-017, 2K-029 and 2K-030) which contain cables for indication and control circuits needed for safe shutdown. The licensee originally proposed (letter No. EF2-72717, dated August 3, 19841 to meet the guidelines of the Standard Review Plan, Franch Technical Position 9.5-1 by wrapping all of the divisional cables in Fire Zone AB- Because of difficulties encountered in wrapping all of the cables, the licensee later proposed to meet the fire protection guidelines by satisfying the technical requirements of Section III.L. of Appendix R to 10 CFR 50 and provide an alternative shutdown capability that was independent of Fire Zone AB-2. The licensee encountered difficulties attempting to instell alternative safe shutdown capability that was independent of Fire Zone AB-2. They have since reevaluated the function of the Calvert Pus and cable trays 2K-017, 2K-024 and 2K-030 and available alternative means of providing those functions. The licensee has concluded that these cable feeds are not essential for safe shutdown, given a fire in Fire Zone AB- Each is considered separately, as follow The Calvert Bus originates at the Division I Switchgear Room Buses and is routed through the cable area at the 603.5 ft. level of the auxiliary building (FireZoneAB-2,oneofthefirezonesofconcern)andontotheRadwaste Switchgear Room Puses. This Calvert Bus supplies power to the Standby Feedwater System which is part of the independent alternative safe shutdown syste ByletterdatedJanuary3,1986(letterNo.VP-85-0221), the licensee again changed their approach to fire protection in Fire Zone AB-2. They returned to their original approach of August 3,1984, and comitted to satisfy the technical requirements of Section ITT.G.2 of Appendix R to 10 CFR 50 in Fire Zone AB-2 by protecting one division of safe shutdown cables and eliminating dependence on the Calvert Bus in this area. The zone was already protected by automatic fire detection and automatic fire suppression. Additional protection that is provided for one divi: ion of safe shutdown cabling in the zone consists of a coabination of one-hour rated wraps, spatial separation and fire stoss installed in horizontal cable trays constituting intervening combustibles located within the 20-foot space between unprotected cable trays of redundant divisions of safe shutdown cables. This combination of (1)
automatic fire detection and automatic fire suppression, (2) one-hour fire rated wraps around trays of one division of safe shutdown cables, (3) 20-feet of spatial separation that is free of intervening combustibles between unpiotected trays of redundant divisions of safe shutdown cables, and (4) fire
.:.
-3-stops installed on horizontal cable trays that are located in the 20-foot clear space between redundant divisions of safe shutdown cables, constitutes an acceptable method of fire protection for the function of the Calvert Bu Therefore, Region III open item 341/85050-04(6.g.(2)inInspectionReport dated January 3, 1986) is satisfie Cable trays 2K-017, 2K-029 a'nd 2K-030 contain indication and control circuits for reactor pressure, reactor water level, torus water level, torus temperature, and temperature control of the EECW Heat Exchanger inlet valv Since all of the above indication functions (reactor pressure and water level and torus temperature and water level) are available independent of Fire 7one AB-2 in the control room or at the dedicated (3L) panel, these cables are not required for safe shutdown and are not required to be protected. With respect to the EECW Heat Exchanger inlet valve, the licensee has revised their procedures to require an operator to manually disable the control to the Division II Heat Exchanger Temperature Control Valve so that the valve fails open (safe) in the event of fire in Fire Zone AR-2. This change in procedure and the independent availability of indication functicos at the dedicated (3Li panel and in the control room, along with the existing automatic fire detection and automatic fire suppression in Fire Zone AR-2 constitutes an acceptable method of fire protection for the cables contained in cable trays 2K-017, 2K-029 and 2K-030. Therefore, Region III open item 341/P5050-05 (6.g.(3) in Inspection Report dated .1anuary 3, 1986) is satisfie .0 CONCLUSIONS Based upon the above evaluation, we ccnclude that Pegion III open item 341/85050-03 (6.g.(1) in Inspection Report dated .1anuary 3.1 986), pertaining to protection of electrical feed cable No. R.I. 005 2P where it passes through Fire Zone 8, is satisfactorily resolved, since the combination of automatic fire detection and automatic fire suppression in con.iunction with the one-hour fire barrier wrap conforms to guidelines of the Standard Review Plan, Pranch Technical Position 9.5.-1 and the Section III.G.2.c of Appendix R to 10 CFR 5 We have also concluded that the other two Region III open items concerning electrical feeds passing through Fire Zone AB-2 have been satisfactorily resolved. Resolution of open item 341/85050-04 (6.g.(2) in the January 3, 2986 Inspection Report) is acceptable because of the combination of (1)
automatic fire detection and suppression, (2) one-hour fire rated wraps provided for one division of safe shutdown cables, (3) 20-feet of spatial separation that is free of intervening combustibles between unprotected trays of redundant divisions of safe shutdown cables, and (4) fire stops installed on horizontal cable trays that are located in the 20-foot clear space between redundant divisions of safe shutdown cables. Resolution of open item 3A1/85050-05 (6.g.(3) in Inspection Report dated January 3, 1986) is acceptable because of (1) indication functions available, independent of Fire Zone AP-2, at the dedicated (3L) shutdown panel and in the control room, and (2) changes 'in the procedures to require an operator to ranua11y open the Division II Heat Exchanger Temperature Control Valve in the event of fire in Fire Zone AR-2 to assure it is a safe configuration,
p, ,
. . .
.
-4-In addition to these conclusions based upon the above evaluation Region III conducted a follow-up inspection on June 30 - July 1, 1986. In their letter to the licensee dated July 21, 1986, covering the results of that inspectio Pegion III found the actions of the licensee acceptable with respect to these three open items and closed each of them (341/85050-03, -04 and -05).
.