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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211B0271999-08-13013 August 1999 SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1 ML20212H9961999-06-22022 June 1999 Safety Evaluation Supporting Amend 233 to License NPF-3 ML20195K2871999-06-16016 June 1999 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20207G6661999-06-0808 June 1999 Safety Evaluation Supporting Amend 232 to License NPF-3 ML20206U7371999-05-19019 May 1999 Safety Evaluation Supporting Amend 231 to License NPF-3 ML20206U2441999-02-0909 February 1999 Safety Evaluation Supporting Amend 229 to License NPF-3 ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant ML20155B6781998-10-28028 October 1998 Safety Evaluation Accepting Proposed Reduction in Commitment Changes in QA Program Matl Receipt Insp Process ML20236R1441998-07-15015 July 1998 SER Related to Quality Assurance Program Description Changes for Davis-Besse Nuclear Power Station,Unit 1 ML20236M9411998-07-0707 July 1998 Safety Evaluation Supporting Amend 225 to License NPF-3 ML20236K3981998-06-30030 June 1998 SER Accepting in Part & Denying in Part Relief Requests from Some of ASME Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Davis-Besse Nuclear Power Station,Unit 1 ML20236K4321998-06-30030 June 1998 Safety Evaluation Supporting Amend 224 to License NPF-03 ML20236K5131998-06-29029 June 1998 Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1 ML20249A7661998-06-11011 June 1998 Safety Evaluation Supporting Amend 222 to License NPF-3 ML20249A7551998-06-11011 June 1998 Safety Evaluation Supporting Amend 223 to License NPF-3 ML20216B9401998-04-15015 April 1998 Safety Evaluation Supporting Amend 221 to License NPF-3 ML20216B8381998-04-14014 April 1998 Safety Evaluation Supporting Amend 220 to License NPF-3 ML20202C6131998-02-0303 February 1998 Safety Evaluation Supporting Amend 219 to License NPF-3 ML20199J9511998-01-30030 January 1998 SER Related to Exemption from Section Iii.O of App R,To 10CFR50,for Davis-Besse Nuclear Power Station,Unit 1 ML20198R4771998-01-13013 January 1998 SER Approving Second 10-year Interval Inservice Inspection Program Plan Requests for Relief for Davis-Besse Nuclear Power Station,Unit 1 ML20203C1401997-12-0202 December 1997 Safety Evaluation Supporting Amend 217 to License NPF-3 ML20203B2141997-12-0202 December 1997 Safety Evaluation Supporting Amend 218 to License NPF-3 ML20203C2701997-12-0202 December 1997 Safety Evaluation Supporting Amend 216 to License NPF-3 ML20138L0491997-02-11011 February 1997 Safety Evaluation Supporting Amend 214 to License NPF-3 ML20128L3001996-10-0202 October 1996 SER Supporting Dbnp IPE Process of Identifying Most Likely Severe Accidents & Severe Accident Vulnerabilities ML20058M9591993-09-28028 September 1993 SE Accepting Licensee Response to GL 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.' ML20057A3791993-08-20020 August 1993 SE Concluding That Second 10-yr Interval Inservice Insp Program Plan for Plant Has Unacceptable Exam Sample as Discussed in Encl Inel TER ML20056G4301993-08-18018 August 1993 Safety Evaluation Re Inservice Testing Program Requests for Relief.Licensee Made Changes to Subj Program to Include Exercising & fail-safe Testing of Auxiliary Feedwater Valves AF-6451 & AF-6452,in Response to TER Anomaly 8 ML20126A3051992-12-0808 December 1992 Safety Evaluation Supporting Amend 176 to License NPF-3 ML20056B2721990-08-20020 August 1990 Safety Evaluation Granting Relief from ASME Code Repair Requirements for ASME Code 3 Piping ML20248H6371989-10-0303 October 1989 Safety Evaluation Supporting Amend 139 to License NPF-3 ML20248D8271989-09-29029 September 1989 Safety Evaluation Accepting Util 890228 & 0630 Submittals Presenting Proposed Designs to Comply w/10CFR50.62 ATWS Rule Requirements ML20248E2771989-09-20020 September 1989 Safety Evaluation Supporting Amend 138 to License NPF-3 ML20248B3801989-09-20020 September 1989 Safety Evaluation Supporting Amend 137 to License NPF-3 ML20247E6901989-09-0505 September 1989 Safety Evaluation of Audit of Facility Design for Resolution of IE Bulletin 79-27 Re Loss of non-Class IE Instrumentation & Control Power Sys Bus During Operation.Preventive Maint & Testing Program Should Be Developed for Bus Power Sources ML20245K1871989-08-15015 August 1989 Safety Evaluation Supporting Amend 136 to License NPF-3 ML20245F5791989-08-0404 August 1989 Safety Evaluation Supporting Amend 134 to License NPF-3 ML20245H9531989-08-0404 August 1989 Safety Evaluation Supporting Amend 135 to License NPF-3 ML20247J8731989-05-18018 May 1989 Safety Evaluation Supporting Amend 133 to License NPF-3 ML20245G0371989-04-25025 April 1989 Safety Evaluation Supporting Amend 131 to License NPF-3 ML20245F0631989-04-25025 April 1989 Safety Evaluation Supporting Amend 132 to License NPF-3 ML20244D4031989-04-13013 April 1989 Safety Evaluation Supporting Amend 130 to License NPF-3 ML20196D9601988-12-0808 December 1988 Safety Evaluation Re Util Response Concerning Auxiliary Feedwater Sys Reliability Study.Util Should Ensure That Sys Mods Do Not Result in Net Reduction in Sys Reliability ML20207K7911988-10-0404 October 1988 Safety Evaluation Supporting Operation in Cycle 6 W/O Removing Flaws in Cracked HPI Nozzle ML20207K1071988-09-19019 September 1988 Safety Evaluation Supporting Amend 120 to License NPF-3 ML20207H9271988-08-24024 August 1988 Safety Evaluation Supporting Amend 117 to License NPF-3 ML20207H3891988-08-19019 August 1988 Safety Evaluation Supporting Amend 116 to License NPF-3 ML20207E3931988-08-0202 August 1988 Safety Evaluation Supporting Amend 114 to License NPF-3 ML20207D5171988-08-0202 August 1988 Safety Evaluation Supporting Amend 115 to License NPF-3 ML20150C4621988-03-0909 March 1988 Safety Evaluation Supporting Amend 109 to License NPF-3 1999-08-13
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & PNPP QA Program ML20217D5441999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Davis-Besse Nuclear Power Station.With 05000346/LER-1998-011, :on 981014,manual Reactor Trip Occurred.Caused by Component Cooling Water Sys Leak.Breaker Being Installed Into D1 Bus cubicle.AACD1 Was Removed from Cubicle1999-09-0303 September 1999
- on 981014,manual Reactor Trip Occurred.Caused by Component Cooling Water Sys Leak.Breaker Being Installed Into D1 Bus cubicle.AACD1 Was Removed from Cubicle
ML20211R0811999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1999-003, :on 990727,failure to Perform Engineering Evaluation for Pressurizer Cooldown Rate Exceeding TS Limit Was Noted.Caused by Inadequate Procedural Guidance.Provided Required Reading for Operators.With1999-08-26026 August 1999
- on 990727,failure to Perform Engineering Evaluation for Pressurizer Cooldown Rate Exceeding TS Limit Was Noted.Caused by Inadequate Procedural Guidance.Provided Required Reading for Operators.With
ML20211B0271999-08-13013 August 1999 SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1 ML20210Q8541999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20209E6231999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-013, :on 981105,safety Valve Rupture Disks May Induce Excessive Eccentric Loading of Pressurizer Vessel Nozzles.Caused by Failure of RCS Pressure Boundary.Plant Mod Was Implemented in May of 1999.With1999-06-24024 June 1999
- on 981105,safety Valve Rupture Disks May Induce Excessive Eccentric Loading of Pressurizer Vessel Nozzles.Caused by Failure of RCS Pressure Boundary.Plant Mod Was Implemented in May of 1999.With
ML20212H9961999-06-22022 June 1999 Safety Evaluation Supporting Amend 233 to License NPF-3 ML20195K2871999-06-16016 June 1999 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20207G6661999-06-0808 June 1999 Safety Evaluation Supporting Amend 232 to License NPF-3 ML20195F4871999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20206U7371999-05-19019 May 1999 Safety Evaluation Supporting Amend 231 to License NPF-3 ML20207E8011999-05-19019 May 1999 Non-proprietary Rev 2 to HI-981933, Design & Licensing Rept DBNPS Unit 1 Cask Pit Rack Installation Project ML20207F4351999-05-0404 May 1999 Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504 ML20206M6341999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Davis-Besse Nuclear Station,Unit 1.With ML20205M2931999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Davis-Besse Nuclear Power Station.With 05000346/LER-1999-002, :on 990208,both Trains of Emergency Ventilation Sys Were Rendered Inoperable.Caused by Unattended Open Door. Door Was Immediately Closed Upon Discovery.With1999-03-0505 March 1999
- on 990208,both Trains of Emergency Ventilation Sys Were Rendered Inoperable.Caused by Unattended Open Door. Door Was Immediately Closed Upon Discovery.With
ML20207J1461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20206U2441999-02-0909 February 1999 Safety Evaluation Supporting Amend 229 to License NPF-3 ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199E2501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20205K5781998-12-31031 December 1998 Waterhammer Phenomena in Containment Air Cooler Swss ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl ML20197J3441998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-012, :on 981018,reactor Trip Occurred from Approx 4% Power Due to ARTS Signal.Caused by Inadequate Design Drawing Resulting in Inadequate Procedure.Procedure Revised to Correct Deficiency.With1998-11-17017 November 1998
- on 981018,reactor Trip Occurred from Approx 4% Power Due to ARTS Signal.Caused by Inadequate Design Drawing Resulting in Inadequate Procedure.Procedure Revised to Correct Deficiency.With
05000346/LER-1998-009, :on 980909,RCS Pressurizer Spray Valve Was Not Functional with Two of Eight Body to Bonnet Nuts Missing. Caused by Less than Adequate Matl Separation Work Practices. Bonnet Nuts Replaced.With1998-11-13013 November 1998
- on 980909,RCS Pressurizer Spray Valve Was Not Functional with Two of Eight Body to Bonnet Nuts Missing. Caused by Less than Adequate Matl Separation Work Practices. Bonnet Nuts Replaced.With
05000346/LER-1998-011, :on 981014,manual RT Due to Ccws Leak Was Noted.Caused by Failure of One Letdown Cooler Rupture Disk. All Letdown Cooler Rupture Disks Were Replaced Prior to Plant Restart.With1998-11-13013 November 1998
- on 981014,manual RT Due to Ccws Leak Was Noted.Caused by Failure of One Letdown Cooler Rupture Disk. All Letdown Cooler Rupture Disks Were Replaced Prior to Plant Restart.With
ML20195D0001998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20155B6781998-10-28028 October 1998 Safety Evaluation Accepting Proposed Reduction in Commitment Changes in QA Program Matl Receipt Insp Process 05000346/LER-1998-010, :on 980924,manual Reactor Trip Was Noted.Caused by Misdiagnosed Failure of Main FW Control Valve Solenoid Valve.Faulty Solenoid valve,SVSP6B1,was Replaced & Tested. with1998-10-26026 October 1998
- on 980924,manual Reactor Trip Was Noted.Caused by Misdiagnosed Failure of Main FW Control Valve Solenoid Valve.Faulty Solenoid valve,SVSP6B1,was Replaced & Tested. with
05000346/LER-1998-008, :on 981001,documented Proceduralized Guidance for Initiation of Post LOCA B Dilution Flow Path.Caused by Design Analysis Oversight.Revised Procedures to Provide Active B Dilution Flow Path Guidance.With1998-10-0101 October 1998
- on 981001,documented Proceduralized Guidance for Initiation of Post LOCA B Dilution Flow Path.Caused by Design Analysis Oversight.Revised Procedures to Provide Active B Dilution Flow Path Guidance.With
ML20154H5801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-007, :on 980824,CR Humidifier Ductwork Failure Caused Excessive Opening in Positive Pressure Boundary. Caused by Less than Adequate Fabrication.Evaluation of CR Humidifiers Conducted.With1998-09-22022 September 1998
- on 980824,CR Humidifier Ductwork Failure Caused Excessive Opening in Positive Pressure Boundary. Caused by Less than Adequate Fabrication.Evaluation of CR Humidifiers Conducted.With
ML20151W1611998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Dbnps.With 05000346/LER-1998-006, :on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources1998-08-21021 August 1998
- on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources
ML20237E3171998-08-21021 August 1998 ISI Summary Rept of Eleventh Refueling Outage Activities for Davis-Besse Nuclear Power Station ML20237B1681998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236U5011998-07-23023 July 1998 Special Rept:On 980624,Unit 1 Site Damaged by Tornado & High Winds.Alert Declared by DBNPS Staff,Dbnps Emergency Response Facilities Activiated & Special Insp Team Deployed to Site by Nrc,As Result of Event ML20236R1441998-07-15015 July 1998 SER Related to Quality Assurance Program Description Changes for Davis-Besse Nuclear Power Station,Unit 1 05000346/LER-1998-004, :on 980601,ductwork for Number 2 Control Room Humidifier Found Disconnected from Humidifier.Caused by Less than Adequate Connection at Humidifier Blower Housing. Ductwork Repaired1998-07-13013 July 1998
- on 980601,ductwork for Number 2 Control Room Humidifier Found Disconnected from Humidifier.Caused by Less than Adequate Connection at Humidifier Blower Housing. Ductwork Repaired
05000346/LER-1998-005, :on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations1998-07-11011 July 1998
- on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations
ML20236M9411998-07-0707 July 1998 Safety Evaluation Supporting Amend 225 to License NPF-3 ML20236K3981998-06-30030 June 1998 SER Accepting in Part & Denying in Part Relief Requests from Some of ASME Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Davis-Besse Nuclear Power Station,Unit 1 ML20236N7451998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236K4321998-06-30030 June 1998 Safety Evaluation Supporting Amend 224 to License NPF-03 ML20236K5131998-06-29029 June 1998 Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1 05000346/LER-1998-003, :on 980519,Mode 3 Entry Without Completion of Surveillance Requirement Occurred.Caused by Failure of I&C Technicians to Perform Each Sp as Written or Adherence. Revised Procedure1998-06-18018 June 1998
- on 980519,Mode 3 Entry Without Completion of Surveillance Requirement Occurred.Caused by Failure of I&C Technicians to Perform Each Sp as Written or Adherence. Revised Procedure
1999-09-30
[Table view] |
Text
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- s h
UNITED STATES 4-j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 300ss com l
I~
. SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
O FACILITY OPERATING LICENSE NO. NPF-3 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO.1 DOCKET NO. 50-346
1.0 INTRODUCTION
By letter dated October 27,1998, Toledo Edison Company, Centerior Service Company, and
= The Cleveland Electric illuminating Company (the licensees at the time of the submittal),
submitted a request for changes to the Davis-Besse Nuclear Power Station, Unit No.1, Technical Specifications (TSs). FirstEnergy Nuclear Operating Company (FENOC) became the sole licensed operator on January 1,1999.
The proposed amendment would relocate a TS surveillance requirement (SR) from TS Section 3/4.6.5.1, " Shield Building - Emergency Ventilation System" to TS Section 3/4.6.5.2, " Shield Building Integrity." Administrative and bases changes would also be made.
By letter dated March 19,1999, the licensee revised the application, making a minor change that did not affect the staff's proposed determination of no significant hazards considerations.
This revision to the application deleted a clarification statement that had been proposed in the initial application, but had been found to be unnecessary.
]
1
2.0 BACKGROUND
The shield building is discussed in the Davis-Besse Updated Safety Analysis Report (USAR),
Section 3.8.2.2, " Design of Seismic Class I and ll Structures - Shield Building," Section 6.2.1.
" Containment Systems - Containment Vessel Functional Design," Section 12.2.2.1, " Ventilation -
i Shield Building and Penetration Rooms," and Section 15.4.6, " Class 3 - Design Basis Accidents
- Major Rupture of Pipes Containing Reactor Coolant Up To and including Double-Ended Rupture of the Largest Pipe in the Reactor Coolant System (Loss-of-Coolant Accident)." The emergency ventilation system (EVS) is discussed in USAR Section 6.2.3, " Containment l
Systems - Containment Vessel Air Purification and Cleanup System,"in addition to Sections 12.2.2.1 and 15.4.6.
As stated in the USAR, the shield building encloses the containment vessel, the personnel access openings, the equipment hatch, and the portion of all penetrations that are associated 9906280266 990622 PDR ADOCK 05000346 P
PDR
d.
with primary containment. This building provides for biological shielding, controlled release of the annulus atmosphere under accident conditions, and environmental protection of the
- containment vessel.
' The EVS is intended for use in an accident situation to provide a negative pressure in the
. annulus between the shield building and the containment vessel, the penetration rooms, and the emergency core cooling system equipment rooms, and to reduce airborne fission product leakage to the environment by filtration prior to release of air through the station vent.
The EVS has two redundant, independent subsystems, each capable of meeting the functional requirement. A single failure of an active component in either subsystem does not affect the functional capability of the other subsystem. Each subsystem includes prefiiters, higharfficiency particulate air (HEPA) filters and charcoal adsorbers to remove airborne particles and methyliodide as well as elemental iodine contaminants resulting from a loss-of-coolant accident.
During normal operation, the EVS is in standby mode. An SFAS (safety features actuation system) signal actuates the fans, and control room instrumentation monitors the operation. The fans can be operated on emergency diesel generator power.
3.0 EVALUATION Currently, if shield building integrity is not adequate, both trains of EVS must be declared inoperable, so that TS 3.0.3 must be entered, which requires the initiation of a plant shutdown within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. _ The licensee is proposing to relocate the portion of the EVS TS addressing L negative pressure capability to the shield building integrity TS. The principal effect of this relocation would be the extension of the time to initiate a plant shutdown (due to a loss of negative pressure capability) from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Each proposed change is discussed below.
3.1 IS_Indag
. The licensee proposes to delete the definitions index item " Shield Building Integrity." This is an administrative change consistent with the change discussed in Section 3.2. Therefore, it is
- acceptable.
3.2 TJ Definitions The licensee proposes to delete the " Shield Building Integ'ity" definition, which reads:
.1.24 SHIELD BUILDING INTEGRITY shall exist when; a.
The airtight doors and blowout panels listed in Table 4.6-1 are closed except the alitight doors may be used for normal transit entry and exit.
b.
The emergency ventilation system is OPERABLE.
L c.
The sealing mechanism associated with each penetration (e.g.,
welds, bellows or O-rings) is OPERABLE.
The text of TS 1.24.a is also included in Shield Building Integrity TS SR 4.6.5.2. Therefore, the deletion of TS 1.24.a is acceptable.
. TS 1.24.b states that Shield Building Integrity requires the EVS to be operable. The licensee proposes to remove this dependency. As currently written, to satisfy Definition 1.24.b, only one l
train of EVS needs to be operable (TS 3.6.5.1 allows 7 days to restore one inoperable EVS train or initiate a shutdown). If both trains of EVS are inoperable, then TS 3.0.3 must be entered, which requires the initiation of a plant shutdown within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to initiate shutdown is L
more restrictive than the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowed in TS 3.6.5.2 for loss of shield building integrity (due to both trains of EVS being inoperable as stated in TS Definition 1.24.b). Hence, TS Definition 1.24.b is not needed and its removal is acceptable.
The text of TS 1.24.c is also included in Containment Integrity TS 1.8.e, which refers to the same penetrations as Shield Building Integrity TS 1.24.c. If a sealing mechanism is not operable, then Containment Integrity TS 3.6.1.1 requires a plant shutdown to be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Since this is more restrictive than Shield Building integrity TS 3.6.5.2 (which requires the initiation of a plant shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), and since both are applicable in Modes 1,2,3 and 4 only, TS 1.24.c is not necessary. Therefore, its deletion is acceptable.
Since the term " SHIELD BUILDING INTEGRITY" is only referred to in the shield building integrity TS and since the removal of each subpart of the definition is acceptable, the deletion of i
this definition is acceptable.
3.3 TS 4.6.5.1. " Containment Systems - Shield Buildina - Surveillance Reauirements" TS 4.6.5.1.d.4 currently reads:
4.
Verifying that each system products a negative pressure of greater than or equal to 0.25 inches Water Gauge in the annulus within 4 seconds after the fan attains a flow rate of 8000 cfm *10%. This test is to be performed with the flow path l
established prior to starting the EVS fan,' and the other dampers associated with the negative pressure boundary closed.
l The licensee proposes to move this TS from the EVS surveillance requirements to TS 4.6.5.2 as l
part of the shield building integrity surveillance requirements. EVS TS 3.6.5.1 requires that two independent EVSs be operable. Currently, without shield building integrity, both trains of EVS would have to be declared inoperable due to the loss of the capability to produce an acceptable negative pressure. TS 3.0.3 would then be entered, requiring a plant shutdown to be initiated l
within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
l l
I-
~... -
f With a loss of shield building integrity, TS 3.6.5.2 allows 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore integrity or immediately initiate a shutdown. Therefore, the proposed move of TS 4.6.5.1.d.4 has the effect of increasing the allowed restoration time from i hour to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, during which time the plant would be without shield building integrity though the EVS would still be considered operable since the negative pressure criteria would no longer be applicable.
l l
Maintaining shield building integrity ensures that the release of radioactive material from the primary containment atmosphere is restricted to those leakage paths and associsted leakage rates assumed in the accident analysis. The staff has determined that increasing the restoration time from i hour to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> still provides a reasonable completion time considering the limited leakage design of the containment and the low probability of a design basis accident during this time period. Therefore, moving TS 4.6.5.1.d.4 from the EVS surveillance requiremc"s to the shield building integrity surveillance requirements is acceptable.
The licensee also proposes to delete the word "and" from TS 4.6.5.1.d.3 and insert "and" into TS 4.6.5.1.d.2. This is an administrative change only and is therefore acceptable.
3.4 TS 3.6.5.2. " Containment Systems - Shield Buildina Intearity - Limitina Condition for Ooeration" TS 3.6.5.2 currently reads:
.3.6.5.2 SHIELD BUILDING INTEGRITY shall be maintained.
APPLICABILITY: MODES 1,2,3 and 4 ACTION:
Without SHIELD BUILDING INTEGRITY, restore SHIELD BUILDING INTEGRITY within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The licensee proposes to change " SHIELD BUILDING INTEGRITY" to " shield building integrity."
Since this is consistent with the removal of the shield building integrity definition discussed in Section 3.2, this is an administrative change only and is acceptable.
3.5' TS 4.6.5.2. " Containment Systems - Shield Buildina Intearity - Surveillance Recuirements The licensee proposes to change " SHIELD BUILDING INTEGRITY" to " Shield building integrity" in TS 4.6.5.2, and renumber the current requirement TS 4.6.5.2.1. These are administrative changes consistent with other approved changes and are therefore acceptable.
The licensee proposes to add TS 4.6.5.2.2, which will read:
4.6.5.2.2 Shield building integrity shall be demonstrated at least once per REFUELING
)
INTERVAL by verifying that each Emergency Ventilation System train produces a i
l negative pressure of greater than or equal to 0.25 inches Water Gauge in the annulus within 4 seconds after the fan attains a flow rate of 8000 cfm i 10%. This test is to be performed with the flow path established prior to starting the EVS fan, and the other dampers associated with the negative pressure boundary closed.
This addition was addressed in Section 3.3 where the staff accepted the move of this TS from the EVS surveillance requirements to TS 4.6.5.2.2 as part of the shield building integrity surveillance requirements. Hence, this new TS is acceptable.
The licensee also proposes changes to some of the language at the beginning of this TS (to be consistent with the remainder of the shield building integrity specifications) without altering the content. Therefore, these language changes are administrative only and are acceptable.
3.6 TS Table 4 6-1. " Access Ooeninas Reauired to be Closed to Ensure Shield Buildina Intearity" The description of air tight door no. 307 currently reads:
Access Door from Corridor 304 to the No. 3 Mechanical Penetration Room (Room 308)
The licensee proposes to change the description to reference Room 303 (from Room 308),
consistent with plant construction. This is an administrative change only and is acceptable.
3.7 TS Bases 3/4.6.5.1. "Emeroency Ventilation System" The licensee proposes to add the following text to this bases:
The proper functioning of the EVS fans, dampers, filters, adsorbers, etc., as a system is verified by the ability of each train to produce the required system flow rate.
j This provides clarification that EVS operability does not depend on the ability to provide an acceptable negative pressure, consistent with the other changes already reviewed. Therefore, this addition is acceptable.
3.8 TS Bases 3/4.6.5.2. " Shield Buildina Intearity" The licensee proposes to change " SHIELD BUILDING INTEGRITY" to " shield building integrity."
Thb is an administrative change only and is acceptable.
The licensee also proposes to insert the following text:
in the event shield building integrity, including the capability of the EVS to provide a negative pressure of greater than or equal to 0.25 inches Water Gauge, is not maintained, shield building integrity must be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Twenty-four hours l
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is a reasonable completion time considering the limited leakage design of the containment and the low probability of a Design Basis Accident occurring during this time period.
This addition provides clarifying information consistent with the proposed TS changes and is therefore acceptable.
4.0 STATE CONSULTATION
~ In accordance with the Commission's regulations, the Ohio State official was notified 'of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
This 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 or changes a 1
surveillance requirement. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent 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 (63 FR 64125). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
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6.0 CONCLUSION
The staff 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 this amendment will not be inimical to the common defense and security or to the health and safet of the public.
Principal Contributor: A. Hansen Date: June 22, 1999 j
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