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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211B8931999-08-17017 August 1999 Safety Evaluation Supporting Amend 143 to License NPF-2 ML20210T2161999-08-0606 August 1999 Draft SE Supporting Proposed Conversion of Current TS to ITS for Plant ML20206L4551999-05-10010 May 1999 Safety Evaluation Supporting Amends 142 & 134 to Licenses NPF-2 & NPF-8,respectively ML20206G7471999-05-0404 May 1999 Safety Evaluation Accepting Corrective Actions Taken by SNC to Ensure That Valves Perform Intended Safety Functions & Concluding That SNC Adequately Addressed Requested Actions in GL 95-07 ML20203J0631999-02-19019 February 1999 Safety Evaluation Supporting Amends 107 & 85 to Licenses NPF-2 & NPF-8,respectively ML20199D8611999-01-12012 January 1999 SER Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2 ML20195E2281998-11-16016 November 1998 Safety Evaluation Authorizing Relief Request for Second 10-year ISI Program Relief Request 56 for Plant,Unit 1 ML20155E0271998-10-29029 October 1998 SER Approving & Denying in Part Inservice Testing Program Relief Requests for Plant.Relief Requests Q1P16-RR-V-3 & Q2P16-RR-V Denied Since Requests Do Not Meet Size Requirement of GL 89-04 NUREG-1407, Safety Evaluation Accepting IPEEE for Severe Accident Vulnerabilities,Per GL 88-20 & NUREG-14071998-10-0101 October 1998 Safety Evaluation Accepting IPEEE for Severe Accident Vulnerabilities,Per GL 88-20 & NUREG-1407 ML20154B6121998-10-0101 October 1998 Safety Evaluation Granting Second 10-year ISI Requests for Relief RR-13 & RR-49 Through RR-55 for Jm Farley NPP Unit 1 ML20237C5471998-08-20020 August 1998 Suppl to SE Re Amends 137 & 129 to Licenses NPF-2 & NPF-8, Respectively.Se Being Supplemented to Incorporate Clarifications/Changes & Revise Commitment for Insp of SG U-bends in Rows 1 & 2 for Unit 2 Only ML20236U6141998-07-23023 July 1998 Safety Evaluation Authorizing Use of Alternative Alloy 690 Welds (Inco 52 & 152) as Substitute for Other Weld Metal ML20236R8671998-07-0909 July 1998 Safety Evaluation Concluding That Southern Nuclear Operating Co USI A-46 Implementation Program Has Met Purpose & Intent of Criteria in GIP-2 & Staff SSER-2 on GIP-2 for Resolution of USI A-46 ML20236L2451998-07-0707 July 1998 Safety Evaluation Accepting Licensee Request for Exemption from Certain Requirements of 10CFR50.71(e)(4) Re Submittal of Revs to UFSAR for Facility Changes Made Under 10CFR50.59 for Plant,Units 1 & 2 ML20217P0571998-04-29029 April 1998 Safety Evaluation Supporting Amends 137 & 129 to Licenses NPF-02 & NPF-08,respectively ML20217D2591998-04-21021 April 1998 Safety Evaluation Accepting Licensee Proposed Alternative Re Augmented Exam of Reactor Vessel Shell Welds for Plant ML20217H3191998-03-31031 March 1998 Safety Evaluation Accepting Proposed Changes to Plant Matl Surveillance Programs ML20217D4081998-03-24024 March 1998 Safety Evaluation Accepting Proposed Changes to Maintain Calibration Info Required by ANSI N45.2.4-1972 ML20216H6731998-03-17017 March 1998 SER Accepting Quality Assurance Program Description Change for Joseph M Farley Nuclear Plant,Units 1 & 2 ML20203B4731998-02-0505 February 1998 Safety Evaluation Supporting Amends 135 & 127 to Licenses NPF-2 & NPF-8,respectively ML20203B7581998-02-0505 February 1998 Safety Evaluation Supporting Amends 134 & 126 to Licenses NPF-2 & NPF-8,respectively ML20199F8931998-01-23023 January 1998 Safety Evaluation Supporting Amends 133 & 125 to Licenses NPF-02 & NPF-08,respectively ML20199B0371998-01-22022 January 1998 SER Accepting Request for Relief (RR-27) for Plant,Units 1 & 2 from Certain Provisions of Section XI to ASME Boiler & Pressure Vessel Code.Relief Will Remove Insulation on ASME Code Class 1 Sys During Inservice Insp ML20198R5221997-10-29029 October 1997 Safety Evaluation Supporting Amends 132 & 124 to Licenses NPF-02 & NPF-08,respectively ML20212F4791997-10-23023 October 1997 Safety Evaluation Supporting Amend 131 to License NPF-2 ML20212A5711997-10-17017 October 1997 Safety Evaluation Supporting Amends 130 & 123 to Licenses NPF-2 & NPF-8,respectively ML20217E8501997-10-0101 October 1997 Safety Evaluation Supporting Amends 129 & 122 to Licenses NPF-2 & NPF-8,respectively ML20216G9521997-09-0404 September 1997 Safety Evaluation Authorizing Request for Relief for IEEE 279-1971,Section 4.7.3 Requirements Concerning Steam Generator Water Level Control ML20236N3331997-08-21021 August 1997 SER Re Request for Interpretation of EDG TS 4.8.1.1.2.e for Farley Nuclear Plant,Units 1 & 2 ML20140B8571997-06-0202 June 1997 Corrected Page 7 to Safety Evaluation Supporting Amend 124 to License NPF-2 ML20137E2951997-03-24024 March 1997 Safety Evaluation Supporting Amends 125 & 119 to Licenses NPF-2 & NPF-8,respectively ML20137B4371997-03-20020 March 1997 SER Accepting Request for Relief for 120-month Update of Facility Inservice Insp & Inservice Testing Programs & Code Addition & Addenda of Asme/Ansi Parts 6 & 10 ML20135E4811997-03-0404 March 1997 Safety Evaluation Accepting Implementation of 10CFR50.55a Requirements Related to Repair & Replacement Activities for Containment at Plant ML20056H1341993-08-23023 August 1993 Safety Evaluation Accepting Licensee 921217 Response to NRC 920917 SE Re Inservice Testing Program Relief Request ML20062D7001990-11-0909 November 1990 Safety Evaluation Supporting Util 881123 & 900917 Responses to Generic Ltr 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Matls & Its Effect on Plant Operations. Submittals Acceptable.Beltline Welds Discussed ML20245A8601989-06-13013 June 1989 Safety Evaluation Supporting Util 831104 & 850422 Responses to Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability for All Domestic Operating Reactors ML20247K6281989-05-19019 May 1989 Safety Evaluation Supporting Amends 81 & 73 to Licenses NPF-2 & NPF-8,respectively ML20247A8481989-05-0404 May 1989 Safety Evaluation Supporting Amends 80 & 72 to Licenses NPF-2 & NPF-8,respectively ML20195D5391988-10-31031 October 1988 Safety Evaluation Supporting ATWS Rule,10CFR50.62 ML20154C9651988-05-12012 May 1988 Safety Evaluation Re Flaw Indications in Reactor Pressure Vessel ML20147E2621987-11-16016 November 1987 Corrected Page 2 of Safety Evaluation Re Amends 74 & 66 to Licenses NPF-2 & NPF-8,respectively,deleting Ref to Quarterly Surveillance Testing on Staggered Test Basis ML20235D5061987-09-21021 September 1987 Safety Evaluation Supporting Amend 64 to License NPF-8 ML20235K4441987-07-0808 July 1987 Safety Evaluation Supporting Granting Licensee Relief from Volumetric Exam of Steam Generator Primary Side Noozles Inside Radiused Sections ML20216E7401987-06-23023 June 1987 Safety Evaluation Supporting Amend 71 to License NPF-2 ML20209E5981987-04-10010 April 1987 Safety Evaluation Supporting Amends 70 & 62 to Licenses NPF-2 & NPF-8,respectively ML20206G3561987-03-30030 March 1987 Safety Evaluation Supporting Amends 69 & 61 to Licenses NPF-2 & NPF-8,respectively ML20212E2241987-02-27027 February 1987 Safety Evaluation Accepting Util 831104 Response to Item 4.5.2 of Generic Ltr 83-28 Re on-line Functional Testing of Reactor Trip Sys,Including Independent Testing of Diverse Trip Features of Reactor Trip Breakers ML20211D5341987-01-0707 January 1987 Safety Evaluation Re Rev 1 to EGG-EA-6794, Conformance to Reg Guide 1.97,Joseph M Farley Nuclear Plant,Units 1 & 2 & Licensee Submittals.Response Acceptable ML20212F5101987-01-0707 January 1987 Safety Evaluation Accepting Licensee 831104 Response to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components) ML20207J8931986-12-29029 December 1986 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section Iii.G for 16 Fire Areas 1999-08-06
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P0761999-10-0606 October 1999 Non-proprietary, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217G0361999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20216E4941999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Jmfnp.With ML20212E7451999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Hcgs,Unit 1.With Summary of Changes,Tests & Experiments Implemented During Aug 1999.With ML20211B8931999-08-17017 August 1999 Safety Evaluation Supporting Amend 143 to License NPF-2 ML20210T2161999-08-0606 August 1999 Draft SE Supporting Proposed Conversion of Current TS to ITS for Plant ML20211B2011999-08-0404 August 1999 Informs Commission About Results of NRC Staff Review of Kaowool Fire Barriers at Farley Nuclear Plant,Units 1 & 2 & Staff Plans to Address Technical Issues with Kaowool & FP-60 Barriers ML20210R6031999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With 05000364/LER-1999-001-05, :on 990621,plant Was Manually Tripped Due to Decreasing Vacuum in Condenser.Caused by Broken Steam Dump Drain Line.Broken Section of Line Was Repaired & Licensee Will Implement Addl Design Change1999-07-0202 July 1999
- on 990621,plant Was Manually Tripped Due to Decreasing Vacuum in Condenser.Caused by Broken Steam Dump Drain Line.Broken Section of Line Was Repaired & Licensee Will Implement Addl Design Change
ML20196J3791999-06-30030 June 1999 Safety Evaluation of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs. Rept Acceptable L-99-267, Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20209G0661999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With 05000348/LER-1999-002-02, :on 990527,Unit 1 Reactor Trip Occurred Following Loss of 1A SG Feedwater Pump.Caused by Personnel Error.Unit Was Stabilized in Hot Standby.With1999-06-25025 June 1999
- on 990527,Unit 1 Reactor Trip Occurred Following Loss of 1A SG Feedwater Pump.Caused by Personnel Error.Unit Was Stabilized in Hot Standby.With
L-99-023, Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Jfnp Units 1 & 2. with ML20206L4551999-05-10010 May 1999 Safety Evaluation Supporting Amends 142 & 134 to Licenses NPF-2 & NPF-8,respectively ML20206G7471999-05-0404 May 1999 Safety Evaluation Accepting Corrective Actions Taken by SNC to Ensure That Valves Perform Intended Safety Functions & Concluding That SNC Adequately Addressed Requested Actions in GL 95-07 ML20206C9461999-04-30030 April 1999 1:Final Cycle 16 Freespan ODSCC Operational Assessment L-99-161, Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20204D4391999-03-31031 March 1999 Unit-1 1999 Voltage-Based Repair Criteria 90-Day Rept ML20204D7271999-03-15015 March 1999 ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jm Farley Nuclear Generating Plant,Unit 1 ML20207M6421999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20203J0631999-02-19019 February 1999 Safety Evaluation Supporting Amends 107 & 85 to Licenses NPF-2 & NPF-8,respectively ML20203A2651999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Jm Farley Nuclear Plant,Units 1 & 2.With 05000348/LER-1998-008-01, :on 981223,reactor Vessel Support Concrete Design Bases Temperature Exceeded Due to Closed Cooling Damper.Caused by Personnel Error.Damper Opened & Secured in Position.With1999-01-18018 January 1999
- on 981223,reactor Vessel Support Concrete Design Bases Temperature Exceeded Due to Closed Cooling Damper.Caused by Personnel Error.Damper Opened & Secured in Position.With
ML20199D8611999-01-12012 January 1999 SER Accepting Relief Request for Inservice Insp Program for Plant,Units 1 & 2 ML20206C8081998-12-31031 December 1998 Alabama Power 1998 Annual Rept ML20199E6591998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With 05000348/LER-1998-007-02, :on 981106,found Several TSP Circumferential Indications & Several TSP Axial Indications Extending Just Beyond Edge of Tsp.Caused by Tube Defects.Sg Tubes Have Been Plugged or Repaired as Required1998-12-22022 December 1998
- on 981106,found Several TSP Circumferential Indications & Several TSP Axial Indications Extending Just Beyond Edge of Tsp.Caused by Tube Defects.Sg Tubes Have Been Plugged or Repaired as Required
05000348/LER-1998-006-03, :on 981124,PRF Sys Suction Damper Was Outside Design & Licensing Basis.Caused by 1976 Personnel Failure to Identify Noted Inconsistency.Scheduled Design Change in 1999 to Modify Dampers to Ensure Licensing Basis Are Met1998-12-18018 December 1998
- on 981124,PRF Sys Suction Damper Was Outside Design & Licensing Basis.Caused by 1976 Personnel Failure to Identify Noted Inconsistency.Scheduled Design Change in 1999 to Modify Dampers to Ensure Licensing Basis Are Met
ML20198K4091998-12-18018 December 1998 COLR for Jm Farley,Unit 1 Cycle 16 05000364/LER-1998-007-01, :on 981116,ESF Actuation Occurred During DG 1000 Kw Load Rejection Test.Caused by Poor Jumper Electrical Connection.Improved Jumpers Will Be Used on Appropriate Terminals in Load Rejection Test Procedures.With1998-12-11011 December 1998
- on 981116,ESF Actuation Occurred During DG 1000 Kw Load Rejection Test.Caused by Poor Jumper Electrical Connection.Improved Jumpers Will Be Used on Appropriate Terminals in Load Rejection Test Procedures.With
ML20198B2561998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20195E2281998-11-16016 November 1998 Safety Evaluation Authorizing Relief Request for Second 10-year ISI Program Relief Request 56 for Plant,Unit 1 05000348/LER-1998-005-03, :on 981021,automatic Start of B Train Penetration Room Filtration Occurred Due to Filling Sf Tc. Caused by Inadequate Procedure.Changed Procedure to Provide Specific Guidance for Filling SFP Tc.With1998-11-12012 November 1998
- on 981021,automatic Start of B Train Penetration Room Filtration Occurred Due to Filling Sf Tc. Caused by Inadequate Procedure.Changed Procedure to Provide Specific Guidance for Filling SFP Tc.With
ML20195C9681998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20155E0271998-10-29029 October 1998 SER Approving & Denying in Part Inservice Testing Program Relief Requests for Plant.Relief Requests Q1P16-RR-V-3 & Q2P16-RR-V Denied Since Requests Do Not Meet Size Requirement of GL 89-04 NUREG-1407, Safety Evaluation Accepting IPEEE for Severe Accident Vulnerabilities,Per GL 88-20 & NUREG-14071998-10-0101 October 1998 Safety Evaluation Accepting IPEEE for Severe Accident Vulnerabilities,Per GL 88-20 & NUREG-1407 ML20154B6121998-10-0101 October 1998 Safety Evaluation Granting Second 10-year ISI Requests for Relief RR-13 & RR-49 Through RR-55 for Jm Farley NPP Unit 1 ML20154H0121998-09-30030 September 1998 Submittal-Only Screening Review of Farley Nuclear Plant IPEEE (Seismic Portion) ML20154H6001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20151V8341998-09-30030 September 1998 Non-proprietary Rev 2 to NSA-SSO-96-525, Jm Farley Nuclear Plant Safety Analysis IR Neutron Flux Reactor Trip Setpoint Change 05000348/LER-1998-004-03, :on 980909,turbine Trip & Consequent Reactor Trip Occurred.Caused by Reactor Protection Sys Card Failure. Failed Card Was Replaced & Unit 1 Returned to Power on 980910.With1998-09-28028 September 1998
- on 980909,turbine Trip & Consequent Reactor Trip Occurred.Caused by Reactor Protection Sys Card Failure. Failed Card Was Replaced & Unit 1 Returned to Power on 980910.With
05000348/LER-1998-003-04, :on 980816,determined That Wgdt Hydrogen & Oxygen Had Exceeded Concentration Limits,Per TS 3.11.2.5. Caused by Undetected Leak.Leak Was Identified & Isolated & Waste Gas Sys Was Returned to Svc on 980818.With1998-09-11011 September 1998
- on 980816,determined That Wgdt Hydrogen & Oxygen Had Exceeded Concentration Limits,Per TS 3.11.2.5. Caused by Undetected Leak.Leak Was Identified & Isolated & Waste Gas Sys Was Returned to Svc on 980818.With
05000348/LER-1997-003, :on 970315,determined That TS SR 4.5.3.2 Had Not Been Performed,Per Operating Procedure.Caused by Personnel Error.Verified That RHR Discharge to Charging Pump Suction MOVs 8706A & 8706B Were Closed.With1998-09-0808 September 1998
- on 970315,determined That TS SR 4.5.3.2 Had Not Been Performed,Per Operating Procedure.Caused by Personnel Error.Verified That RHR Discharge to Charging Pump Suction MOVs 8706A & 8706B Were Closed.With
05000348/LER-1998-005, :on 980315,failure to Perform Nuclear Instrumentation Surveillance Requirements Prior to Mode 2 & 3 Entry,Was Discovered.Caused by Personnel Error.Revised Applicable Procedures1998-09-0303 September 1998
- on 980315,failure to Perform Nuclear Instrumentation Surveillance Requirements Prior to Mode 2 & 3 Entry,Was Discovered.Caused by Personnel Error.Revised Applicable Procedures
05000348/LER-1998-002-05, :on 980816,SG Tube Leakage Investigation,Repair & Evaluation,Occurred.Caused by ODSCC in Two Locations on Same Tube.Operational Leak Rate Limit Requiring Plant Shutdown Has Been Administratively Reduced1998-09-0303 September 1998
- on 980816,SG Tube Leakage Investigation,Repair & Evaluation,Occurred.Caused by ODSCC in Two Locations on Same Tube.Operational Leak Rate Limit Requiring Plant Shutdown Has Been Administratively Reduced
ML20197C8991998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Jm Farley Nuclear Plant,Units 1 & 2.With ML20237C5471998-08-20020 August 1998 Suppl to SE Re Amends 137 & 129 to Licenses NPF-2 & NPF-8, Respectively.Se Being Supplemented to Incorporate Clarifications/Changes & Revise Commitment for Insp of SG U-bends in Rows 1 & 2 for Unit 2 Only ML20237B1891998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Jm Farley Nuclear Plant,Units 1 & 2 ML20236Y1121998-07-31031 July 1998 Voltage-Based Repair Criteria 90-Day Rept 1999-09-30
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pw UNITED STATES f
,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20665 0001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.135 TO FACILITY OPERATING LICENSE NO. NPF 2 AND AMENDMENT NO.127 TO FACILITY OPERATING LICENSE NO. NPF-8 SOUTHERN NUCLEAR OPERATING COMPANY. INC.. ET AL.
JOSEPH M FARLEY NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50 348 AND 50-364 I
1.0 INTRODUCTION
By letter dated October 16,1997, the Southem Nuclear Operating Company, Inc. (SNC or licensee) et al., submitted a request for changes to the Joseph M. Farley Nuclear Plant, Units 1 and 2, Technical Specifications (TS). The requested changes would increase the number of allowable operable charging pumps when the reactor coolant sy.c.em (RCS) is less than 180 *F.
It would ateo modify Maey TS 3.1.2.3 to allow a maximum of two charging pumps to be capable of injecting into the RCS during charging pump swap operations for a maximum of 15 minutes and add an action statement to address having more than one charging pump capable of injection into the RCS.
2.0 BACKGROUND
SNC proposed to change the TS for both Farley Units 1 and 2. The changes to the TS for both units are identical. The licensee proposed to change Section 3.1.2.3 that applies to charging pumps while in Modes 5 and 6. The current limiting condition for operation states:
- a. With no charging pump OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
The requested change retains this condition as paragraph "a." and adds:
- b. With more than one charging pump capable of injecting into the RCS, except as allowed during pump swap operations, immediately take action to render all but the above required OPERABLE pump inoperable as specified in 4.1.2.3.2.
A note that applies to the mode of applicability for the above limiting condition for operation is also supplemented. The current text states:
9802240293 900205 PDR ADOCK 0S000348 P
PDR
I 1
2-A maximum of one charging pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 180'F,
- The requested change adds the following phrase:
...; however, two charging pumps may be capable of injecting into the RCS during pump swap operations for a pt riod of no more than 15 minutes provided that the RCS is in a non water solid condition and both RHR [ residual heat i
removal) relief valves are OPERABLE or the RCS is vented via an opening of no -
less than 5.7 square inches in area.
l The TS Bases Section 3/4.1.2 for each Farley unit is also supplemented to address the requested changes to TS 3.1.2.3.
i 3.0 EVALUATlQN '
In order to maintain a steady supply of filtered seal water to the Reactor Coolant Pump (RCP) number we seal while_ swapping the charging pump, it is necessary to have two charging pumps running momentarily. The proposed changes to TS 3.1.2.3 will allow two charging pumps to be capable ofinjecting into t_he reactor coolant system for a period not to exceed 15 minutes while RCS cold leg temperature is at or below 180*F. This will allow the operator to start a second pump long enough to ensure that it operates properly and then to secure the L
pump that was running originally. This order of pump operation will allow seal injection flow to be maintained to the RCS pumps number one seal continuously, thus preventing loss of pressure to the seals and maintaining filtered water flow through the seals. In order to prevent l
an RCS mass addition transient during the pump swap operation, the RCS should be in a j
nonwater solid condition and the residual heat removal relief valves must be operable or the j
RCS must be vented. These proposed changes include sufficient controls to prevent an RCS l
overpressurization event.
L
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the State of Alabama official was notifed of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or uss of a facility t
component located within the restricted area as defined in 10 CFR Part 20.' The NRC staff has l'
determined that the amendments involve 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 i
no significant increase in individual or cumulative occupational radiation exposure. The l
Ccmmission has previously issued a proposed finding that the amendments involve no l
significant hazards consideration, and there has been no public comment on such 4
1
3-finding (62 FR 63983 dated December 3,1997). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmentalimpact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6? CONCLUSION The Commission has concluded that the proposed TS changes provide an operational flexibility during the pump swap operation while providing sufficient controls to prevent a RCS overpressurization event, and that (1) there is reasonable assurance that the health and safety of the public will not be enrkngered by operation in the proposed manner, (2) such activities will be conducted in compliai with the Commission's regulations, and (3) the issuance of the amendments will not be in,mical to the commori defense and security or to the health and safety of the public.
Princip
- ontributo K.Desai Date:
3ruary 5,1998 1
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