Proposed Tech Specs Revising Tech Specs Section 3/4.9.7, Crane Travel - Spent Fuel Pit AreaML20235A261 |
Person / Time |
---|
Site: |
Sequoyah |
---|
Issue date: |
06/19/1987 |
---|
From: |
TENNESSEE VALLEY AUTHORITY |
---|
To: |
|
---|
Shared Package |
---|
ML20235A184 |
List: |
---|
References |
---|
TAC-R00211, TAC-R00212, TAC-R211, TAC-R212, NUDOCS 8709230253 |
Download: ML20235A261 (9) |
|
|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1201999-08-30030 August 1999 Proposed Tech Specs,Adding New Specification That Addresses Use of Interim Provisions Upon Discovery of Unintended TS Action ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207F7631999-03-0202 March 1999 Proposed Tech Specs Pages Re Application for Amends to Licenses DPR-77 & DPR-79,deleting Iseg from License Conditions ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units ML20129G7301996-09-26026 September 1996 Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations ML20113G2691996-09-20020 September 1996 Proposed Tech Specs Change 96-09, Clarification of Work Shift Durations for Overtime Limits ML20117J3391996-08-28028 August 1996 Proposed Tech Specs Revising Psv & MSSV Setpoint Tolerance from Plus or Minus 1% to Plus or Minus 3% ML20117D1651996-08-22022 August 1996 Proposed Tech Specs of SQN Units 1 & 2,deleting Table 4.8.1, DG Reliability, & Revising Section 3.8.1 to Allow Once Per 18 month,7 Day AOT for EDGs ML20117D3121996-08-22022 August 1996 Proposed Tech Specs,Lowering Minimum TS ice-basket Weight of 1,155 Lbs to 1,071 Lbs.Reduced Overall Ice Weight from 2,245,320 Lbs to 2,082,024 Lbs ML20117D3141996-08-21021 August 1996 Proposed TS 3.7.1.3 Re Condensate Storage Tank ML20117D3341996-08-21021 August 1996 Proposed Tech Specs Re Deletion of Surveillance Requirement 4.8.1.1.1.b ML20112H0431996-06-0707 June 1996 Proposed Tech Specs,Revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of STSs ML20101N7071996-04-0404 April 1996 Proposed Tech Specs,Allowing Conversion from Westinghouse Fuel to Fuel Provided by Framatome Cogema Fuels 1999-08-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F9701999-10-14014 October 1999 Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections ML20217E4301999-10-12012 October 1999 Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations ML20211K1201999-08-30030 August 1999 Proposed Tech Specs,Adding New Specification That Addresses Use of Interim Provisions Upon Discovery of Unintended TS Action ML20211M7341999-08-30030 August 1999 Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times ML20211K1721999-08-30030 August 1999 Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves ML20209B7731999-06-30030 June 1999 Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196F2211999-06-24024 June 1999 Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20196G4701999-06-24024 June 1999 Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196G7961999-06-22022 June 1999 Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators ML20196G8071999-06-22022 June 1999 Revs to Technical Requirements Manual ML20195E9841999-06-0707 June 1999 Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1611999-04-29029 April 1999 Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20206E1391999-04-29029 April 1999 Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations ML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20204H4081999-03-19019 March 1999 Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207F7631999-03-0202 March 1999 Proposed Tech Specs Pages Re Application for Amends to Licenses DPR-77 & DPR-79,deleting Iseg from License Conditions ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20199K6001999-01-15015 January 1999 Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection ML20206S0131999-01-15015 January 1999 Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual ML20195H6111998-11-16016 November 1998 Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting ML20154H7251998-10-0808 October 1998 Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS ML20238F3001998-08-27027 August 1998 Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs ML20238F1091998-08-27027 August 1998 Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20209J1631998-08-0707 August 1998 Rev 41 to Sequoyah Nuclear Plant Odcm ML20236G5961998-06-29029 June 1998 Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions ML20249C6371998-06-26026 June 1998 Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248F0051998-05-28028 May 1998 Proposed Tech Specs for Section 6, Administrative Controls Deletions ML20217N3511998-04-30030 April 1998 Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1681998-02-25025 February 1998 Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20202J6961998-02-13013 February 1998 Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7601998-02-13013 February 1998 Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements ML20198T4311998-01-21021 January 1998 Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 ML20199K4571997-11-21021 November 1997 Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3191997-09-17017 September 1997 Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20203B9731997-08-0505 August 1997 Rev 1 to RD-466, Test & Calculated Results Pressure Locking ML20217J5581997-07-31031 July 1997 Cycle Restart Physics Test Summary, for Jul 1997 ML20210J1671997-04-30030 April 1997 Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d) ML20137T0871997-04-0909 April 1997 Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria ML20137M8581997-04-0101 April 1997 Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits ML20137C8421997-03-19019 March 1997 Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel ML20136J0381997-03-13013 March 1997 Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks ML20134P8631997-02-14014 February 1997 Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b ML20134K9981997-02-0707 February 1997 Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs ML20138F2581997-01-17017 January 1997 Rev 39 to Sequoyah Nuclear Plant Odcm ML20134L9261996-11-0808 November 1996 Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable ML20129D2661996-10-18018 October 1996 Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units 1999-08-30
[Table view] |
Text
{{#Wiki_filter:.
I
.l I
i ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION CHANGE
~
SEQUOYAH NUCLEAR PLANT UNITS 1-AND 2 i~
DOCKET NOS. 50-327 AND 50-328 i
(TVA-SQN-TS-87-41)
LIST OF AFFECTED PAGES Unit 1 3/4 9-7 Unit 2 3/4 9-8 T
P
e l.
i l
REFUELING OPERATIONS 3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA LIMITING CONDITION FOR OPERATION 2.1CD Loads in excess of-2000 pounds shall be prohibited from travel over 3.9.7 fuel assemblies in the storage pool.
APPLICABILITY:. With fuel assemblies in the storage pool.
ACTION:
I With the requirements of the above specification not satisfied, place the crane load in.a saf e condition. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS Crane interlocks and physical stops which prevent crane travel with 4.9.7 z
)
loads in excess of-200t pisnds over fuel assemblies sh.all be demonstrated OPERABLE within 7 days prior to crane use and at least once per 7 days thereafter during crane operation.
and & s g h
- The. spent ftud pool h{ce cc.rwC g{A4C oc uc.l asscenblies 'm 4hc Fool dwider gcd, may -+rnv<,1 N b FTI-i 1
s t
SEQUOYAH - UNIT 1 3/4 9-7 l
'l
i j
l s
(-
4 l-REFUELING OPERATIONS l'
3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA l
I LIMITING CONDITION FOR OPERATION 2.100 3.9.7 Loads in excess of 4009 pounds #shall be prohibited from travel over I
fuel assemblies in the storage pool.
APPLICABILITY: With fuel assemblies in,the storage pool.
ACTION:
- With the requirements of the above specification rot satisfied, place the' crane load in a safe condition. The provisions of Specification 3.0.3 are not applicable.
g SURVEILLANCE REQUIREMENTS 4.9.7 Crane interlocks and physical stops which prevent crane travel with loads in excess of-400fF,pou,nds over fuel assemblies shall be demonstrated
{
OPERABLE within 7 days prior to crane use and at least. once per 7 days thereafter during crane operation.
d "E E
'l' Tne spenE % pool -h a.nsfcr Nd %
O pool dWider gde. may -fravel ovec -{ud 45mMic h W W Pat-
+
e -. m e k
F.
+
SEQUOYAH - UNIT 2 3/49-8
....__._________M
- >l.
'l ENCLOSURE 2
.i PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2
'A~"
DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-87-41)
DESCRIPTION AND JUSTIFICATION FOR CRANE TRAVEL OVER SPENT FUEL PIT AREA e
u___________________.
4 ENCLOSURE 2 DESCRIPTION OF CHANGE This change will revise Section 3/4.9.7
" Crane Travel - Spent Fuel pit Area,"
to (1) revise the maximum load transported over the fuel assemblies in the storage pool from 2,000 pounds to 2.100 pounds and-(2) allow for the fuel pool 4.-
divider gate and the fuel transfer canal gate to be transported over the storage pool when following safe load paths.
REASON FOR CHANGE Limiting Condition for Operation 3.9.7 prohibits loads in excess of 2,000 pounds from travel over fuel assemblies in the storage pool. The basis for weight limit is listed in the bases for the technical specification as the weight of a single spent fuel assembly, control rod assembly, and associated handling tool.
A review of the Westinghouse drawings of a Sequoyah Nuclear plant (SQN) fuel assembly, rod cluster control assembly (RCCA), and spent fuel handling tool identified the total nominal weight to be 2,024 pounds.
The proposed change will allow a 2,100-pound limit, which is rounded off to the next higher hundred to allow for thin extra weight and any minor equipment or fuel weight changes in future assemblies.
Approximately once a year, SQN performs a refueling operation.
During refueling, the fuel pool divider gate and the fuel transfer canal gate are lifted with the main Auxiliary Building crane within the storage pool and must travel over the spent fuel storage racks in order to be placed in the gate storage racks.
The proposed change will allow these gates to be transported within the spent fuel pool with the safe load path.
Together, the above changes to the control of loads across fuel assemblies in
{
the storage pool will resolve the weight limit discrepancy and the movement of the pool gates in excess of the present weight limit.
JUSTIFICATION FOR CHANGE The fuel handling accident analysis presented in section 15.4.5 of the Final Safety Analysis Report (FSAR) was examined to determine whether changing the load. limit from 2,000 pounds to 2,100 pounds would invalidate the analysis.
The accident is defined as dropping a spent fuel assembly onto the spent fuel pit floor and the environmental consequences of that accident.
Changing the maximum weight limit from 2,000 to 2,100 pounds transported over the assemblies will not affect or invalidate the FSAR fuel handling accident.
The analysis assumes that the dropping of the fuel assembly results in a rupture of the cladding of all the fuel rods and the resultant offsite dose effects and consequences. The accident analysis is based on radioactivity and dose limits and not the specific weight; simply correcting the nominal weight limit to 2,100 pounds in the technical specifications does not change the results of the FSAR fuel handling accident.
The 2,100-pound limit will not physically affect any normal plant operations but will allow the transport of a single fuel assembly, RCCA, and the handling tool over other fuel assemblies
9 l !
in the storage pool. Therefore, this review shows the proposed change is not detrimental to the health and safety of the public and is consistent with the basis for the technical specifications.
SQN compliance with the criteria of NUREG-0612 was evalu~ated and documented in the NRC Safety Evaluation Report (SER) and the Technical-Evaluation Report (TER-C5506-393/411) prepared by Franklin Research Center regarding compliance with the criteria of NUREG-0612. " Control of Heavy Loads at Nuclear power plants." NRC established seven general guidelines for handling heavy loads in NUREG-0612. Six of those guidelines pertain to criteria for lifting the spent fuel pool divider gate and the fuel transfer canal gate by the main Auxiliary Building crane.
As identified in the TER, SQN meets the criteria for the main Auxiliary Building crane, including operator training, crane testing, inspection, maintenance, and the crane design standards of the American National i
Standards Institute (ANSI).
I In accordance with the NUREG-0612 guidelines on lifting devices, SQN uses properly inspected and tested slings that meet the requirements of ANSI B30.9-1971.
Safe load paths are defined in Maintenance Instruction (MI)-6.22. " Control of Heavy Loads in Critical Lifting Zones - NUREG-0612." The safe load path defines the area where, if the gate should be dropped, the structure is more likely to withstand the impact.
MI-6.22 also requires a cognizant person to supervise the lift to ensure the safe load path is followed.
Finally, guideline requirements for load handling procedures are met.
MI-6.22 defines required equipment to be used, inspections required, and the safe load paths. Surveillance Instruction 104 ensures j
electrical / mechanical interlocks associated with the Auxiliary Building I
crane function properly in accordance with Surveillance Requirement 4.9.7.
I NRC also established interim measures to be implemented to provide assurance that heavy loads will be handled safely and reduce the potential for accidental load drops.
The Interim protection Measure 1 for technical specifications has been met since 3/4.9.7 exists to prohibit heavy loads over fuel in the storage pool without a single-failure-proof crane.
The technical specifications can be revised to permit lifts that have been j
properly evaluated, i.e., by the TER.
SQN can lift the spent fuel pool l
divider gate and the fuel transfer canal gate over the fuel in the storage l
pool provided the main Auxiliary Building crane is used, approved i
procedures are used, and the safe load path is followed.
j l
I l
l I
1 I
e
. Additionally, a new MI will be written to give detailed instructions for the removal and installation of the spent fuel pool divider gate and the fuel transfer canal gate. This procedure will list tools and rigging devices required for safe movement of the gates, including special requirements such as a load cell or scales to be used to detect binding
~
that might occur while removing or installing the gates.
The inst.uction will also include inflation, deflation, and inspection of the seals.
The proposed change will provide adequate protection of the health and safety of the public and is consistent with the NRC safety evaluation for NUREG-0612.
I
e e
ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATION CHANGES 4~-
SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 4
'~
DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-87-41)
DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATIONS FOR CRANE TRAVEL OVER SPENT FUEL PIT AREA l
l l
7 l 7
^ o ENCLOSURE 3 Significant Hazards Evaluation TVA has evaluated the proposed technical specification change and determined that it does not represent a significant hazards consideration based on
-3 ' ~
criteria established in 10 CFR 50.92(c). Operation of SQN in accordance with the proposed amendment will not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated.
The FSAR fuel handling accident analysis is not based on the weight of the fuel assembly and handling tool but on the radioactive release to the surroundings. Thus, the proposed change for the increased weight limit will not increase resultant offsite dose effects and consequences. The probability of an accident occurring that involves the spent fuel pool gates is very low. The gates are moved infrequently and many safety precautions are used, such as approved slings, procedures, and crane, to significantly lower the possibility of an accident.
Movement of the spent fuel pit gates in accordance with identified safety precautions provides reasonable assurance that the gates will not be dropped.
Therefore, the proposed change does not significantly increase the probability or consequences of an accident previously evaluated.
(2) create the possibility of a new or different kind of accident from any previously analyzed.
The proposed changes do not affect the methodology and analysis previously used in the FSAR.
Future refueling activities that involve moving fuel assemblies will be conducted as in the past. Movement of the spent fuel pool gates in accordance with the guidelines of NUREG-0612,
" Control of Heavy Loads at Nuclear power plants," provides reas'onable assurance that the gates will not be dropped, plant instructions will be revised to incorporate these guidelines, and a new plant procedure will specifically address detailed instructions for removal and installation of these gates. Thus, the proposed change does not create the possibility for a new or different accident.
(3) involve a significant reduction in a margin of safety.
The SER for NUREG-0612, concludes that the guidelines have been followed I
and remain within the safety limits.
The proposed change is in accordance with these guidelines, and thus the margin of safety is not reduced.
I 4
wa=
i______________..___}}