|
---|
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 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 ML20207D6331999-02-26026 February 1999 Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets ML20207D6011999-02-26026 February 1999 Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM 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 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 ML20202J7651998-02-13013 February 1998 Technical Requirements Manual ML20202J7141998-02-13013 February 1998 Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves 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 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 ML20134J9991996-09-23023 September 1996 Fuel Assembly Insp Program 1999-08-30
[Table view] Category:TEST REPORT
MONTHYEARML20204E8501999-03-21021 March 1999 Plant,Four Yr Simulator Test Rept for Period Ending 990321 ML20199F8231997-11-30030 November 1997 Cycle 9 Restart Physics Test Summary, for 971011-971130 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) ML20064M0881994-03-0707 March 1994 Reactor Containment Bldg Integrated Leak Rate Test Sequoyah Nuclear Plant Unit 1 Conducted 931217-20 ML20099B8841992-07-0909 July 1992 Reactor Containment Bldg Intergrated Leak Rate Test Sequoyah Nuclear Plant Unit 2, Conducted on 920427-29 ML20029A3091991-01-31031 January 1991 Nonproprietary Sequoyah Nuclear Plant Unit 2 Cycle 5 Restart Physics Test Summary. ML20059H1881990-08-31031 August 1990 Nonproprietary Sequoyah Nuclear Plant Unit 1,Cycle 5 Restart Physics Test Summary ML20056A5321990-08-0606 August 1990 Reactor Bldg Containment Integrated Leak Rate Test, Sequoyah Nuclear Plant Unit 1 Conducted on 900504-06 ML20044B2191990-07-13013 July 1990 Eagle 21 Start-Up Rept for 900522- 0616. W/900713 Ltr ML20245B3631989-03-18018 March 1989 Reactor Bldg Containment Integrated Leak Rate Test ML20195J8251987-11-23023 November 1987 Insulation Wall Thickness Measurement of Silicone-Rubber Cables at Identified Failure Points ML20236V5171987-11-19019 November 1987 Qualification Test Program for Silicone Rubber Cables W/ Reduced Insulation Thicknesses for Use in TVA Sequoyah Nuclear Plant,Unit 2 ML20236T5381987-11-13013 November 1987 Rev 1 to DC High Voltage Cable Test Rept ML20236Q1871987-10-13013 October 1987 Elevated Temp Test Rept & Mechanical Pull Test Rept for Littelfuse Flas 5,5 AMP Fuses Lot 2,3,4 & 6 ML20236T9461987-09-0303 September 1987 Rev 0 to Special Test Instruction STI-23, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1730B, Incorporating Instruction Change Icf 87-1616 ML20236T6421987-09-0101 September 1987 Rev 0 to Special Test Instruction STI-34, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit Mc 1497B, Incorporating Temporary Change 87-1520 ML20195J8031987-08-31031 August 1987 Impact Testing of Rockbestos & Anaconda Cables ML20236T9891987-08-31031 August 1987 Rev 0 to Special Test Instruction STI-29, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit MC1606A, Incorporating Temporary Change TCF 87-1623 ML20236T8481987-08-25025 August 1987 Rev 2 to Special Test Instruction STI-17, DC High Voltage Test for Selected Unit 2 1E Cables in Vertical Drop Configuration ML20236T6141987-08-17017 August 1987 Rev 0 to Special Test Instruction STI-33, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage ML20236T9781987-08-0303 August 1987 Rev 1 to Special Test Instruction STI-28, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit MC1605A ML20236T8641987-07-29029 July 1987 Rev 1 to Special Test Instruction STI-19, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Jamming, Incorporating Change 87-1251 ML20236T9101987-07-29029 July 1987 Rev 0 to Special Test Instruction STI-23, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage - Conduit MC1748A, Incorporating Change 87-1176 ML20195J7721987-07-22022 July 1987 Impact Testing of Aiw Cable ML20236S0511987-07-22022 July 1987 Rev 0 to Special Test Instruction STI-31, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1732B ML20236T8971987-07-21021 July 1987 Rev 0 to Special Test Instrustion STI-22, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1728B, Incorporating Instruction Change Icf 87-1619 ML20236T9641987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-27, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage, Incorporating Change ICF-87-1283 ML20236T9261987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-25, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage Conduit MC1754A, Incorporating Change 87-1252 ML20236T9181987-07-21021 July 1987 Rev 1 to Special Test Instruction STI-24, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage, Incorporating Instruction Change ICF-87-1253 ML20236T8801987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-21, Cables ML20236T6521987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-35, DC High Voltage Test for Selected 1E Cables W/Potential for Cable Pullby Damage ML20236T5931987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-32, Cables ML20236T5691987-07-21021 July 1987 Rev 0 to Special Test Instruction STI-30, Functional ML20195J7581987-07-20020 July 1987 Tests on Silicone Rubber Insulated Control Cables ML20236A2541987-06-10010 June 1987 Rev 1 to Lab Tests of Air Entrapment in Slightly Sloped Sensing Lines & Consequent Pressure Transmission Error ML20215C5691986-05-30030 May 1986 Cable Sidewall Bearing Pressure Tests ML20154K7711986-02-14014 February 1986 Reactor Bldg Containment Integrated Leak Rate Test,Sequoyah Nuclear Plant Unit 1,Conducted 851203-05 ML20107F6541985-02-19019 February 1985 Reactor Bldg Containment Integrated Leak Rate Test, Conducted on 841120-21 ML20071B3981983-02-17017 February 1983 Reactor Bldg Containment Integrated Leak Rate Test, Conducted on 821208-09 ML18025B8521982-03-18018 March 1982 Revision a to Qualification Test Rept for Model 1801104-05 PSA 1/4 Shock. ML20039A7801981-12-10010 December 1981 Summary Auxiliary Feedwater Pump Endurance Test,Sequoyah Nuclear Plant Unit 2. ML20010H7341981-08-31031 August 1981 Catalytic Combustion Hydrogen in Presence of Methyl Iodide, Final Rept ML20004A9741981-05-19019 May 1981 Reactor Bldg Containment Integrated Leak Rate Test, Conducted 810214-15 ML20050D0091981-04-16016 April 1981 Main Steam Line Break Qualification Test on Okozel Insulation, Final Rept ML20008F8721981-04-13013 April 1981 Table 14.1-2a to Revised Startup Test Program ML20003F0931981-04-13013 April 1981 Startup Test Revisions. ML20050D0111981-04-0808 April 1981 Qualification Tests of Electric Cables Under Simulated Steam Line Break (Slb) by Sequential Environ Exposure to Environs of Thermal Aging,Radiation,Steam & Chemical Spray. ML20008E5551981-02-27027 February 1981 Insp Device in Lieu of Insp Ports. Photographs Encl 1999-03-21
[Table view] |
Text
-'
ENCLOSURE SEQUOYAH NUCLEAR PLANT NATURAL CIRCULATION TEST Demonstrate the Ability to Cooldown, Depressurize, and Boron Mix Special Test 9B, Boron Mixing and Cooldown, was performed on unit 1 of Sequoyah Nuclear plant after zero power physics testing.
1.0 objective A. To borate and verify uniform boron mixing while in natural circulation.
B. To demanstrate the capability to cool down and depressurize while in untural circulation.
C. To provide operator training in the natural circulation mode during a primary system boron addition and cooldown.
2.0 Results With the reactor at approximately 2.5-percent power an6 natural circulation established, a slow boration of the reactor coolan' system was started (2.7 gal / min) and allowed to run for a 2-h or period. Core exit thermocouple maps were run periodically to deter-mine if a nonuniform boron distribution would develop in the core.
Along with the T/C maps, the incore movable detectors (6) worm positioned in the core at varying radial and axial positions.
The time delay from the initiation of the boron addition until the negative reactivity effects were observed in the core was approxi-mately the same as in forc;4 circul;; ion (4-5 minutes). The traces from the incore detectors shewed occasional indications of a slightly nonuniform distribution, but f'r the most part the flux levels recorded by the detectors trended consistently. The core exit thermocouple maps showed no indica' ion of nonuniform distribution as again the exit temperature distribution was slightly better than in the full flow case.
After sampling the system to ensure adequate mixing, a slow cool-down was started and again thermocouple maps were taken periodically to detect, in this case, nonuniform temperature distributions during l the cooldown. The overall temperature distribution remained very l uniforn throughout the cooldown with some indications of a slightly increased radial tilt as measured by the thermocouples. The thermo-couple calculated tilt is not considered extremely accurate, but the trend of the tilt from 550"F to 450"F should be a relatively reliable indication of the direction of changes.
t 4
=
8 012094m
i l
.. In the first performance of the test, the cooldown was accomplished using steam dump to the condenser. In the second performance, the .
main steam isolation valves were closed and the cooldown was accomplished using atmospheric relief valves. In this case, main-taining constant natural circulation in each loop proved to be difficult due to steaming off of individual steam. generators el different times. When one steam generator was steamed off, the natural circulation flow would quickly increase in that loop and reduce in other loops. The best way to cool down proved to be positioning the relief and feedwater valves to give a continuous steam and feed flow and establishing consistent natural circulation flow in each loop rather than letting the automatic system control feedwater and steam flow.
During the cooldown, the indicated temperatures in the upper head, as indicated by the upper head thermocouples, were monitored closely to determine if the upper head temperatures would drop with system temperature under natural circulation. As seen in Figure 1, the upper head temperatures lagged the core exit and hot leg temperatures but followed the cooldown very well indicating that some natural circulation flow was reaching the upper head region.
3.0 Conclusions i
Special Test 9B, Boron Mixing and Cooldown, demonstrated the ability to cool down and depressurize the plant and to demonstrate that boron mixing is sufficient under natural circulation circumstances. Approxi-mately 300 gallons of boric acid were added during the first portion of the test. The results of the test showed that the boron mixing was as expected and better than adequ..te. The results also show that boron addition can be made satis.factorily to bring the unit to the cold shutdown xenon-free condition.
The second portion of the test demonstrated the ability to cool 'down and depressurize under such circumstances. Approximately 100 F of cooldown and 400 psig of depressurization were performed during the test. The results of this portion of the test demonstrated satisfactorily that the unit could be cooled down and depressurized from hot standby to hot shutdown under such circumstances. The results also showed that the upper head temperature followed the cooldown very well indicating that some natural circulation flow was reaching the upper head region.
CLT:CLT 10/29/80 a
ah - 4 W%WM .W M' g .
' ~
n O' FIGURE 1
+
ST -
9B NATURAL CIRCULATION COOLDOW' o- .
a C ,.
4 . . . - . . . i ' '
L
.-- 4,_^ '
I
...-.L.
f '
.. .*%
- Core!E M _Ther=ccouples _..
' ~ ~~
o _
M' c.' . , - '
!!n n n - he d Th o me t mnl on-to _~""" '- _' **
_g 6
. . - . _ =
Y
. = . .' =
g c, i s g es9eb - -UTtO.9 ,
, g%gg U - - L I a.
.-I m __
- 4
. Ns "g
L3 61_ . _ _ . . . _--
~
_\ \".s\
Y\
g - - , . - - . j
.Q c .. .
-._ -... . __,, l _\L(
g ~ ~ ~ ~
, V, ga ,
. p f'(_
es '
M . _\
tn . _ .
C p \a\ \
w 2- , \..
g - - - - - , _
w e.=*e-emme s\
g
~-'-
Fa . i \
._ g _ .
tn . <
- _' . \ . .
\_-
A F
- _g..f 1
O ! i i (yj i #
y
.. A v%g ;i, y
N e ,
t
, t e
. I h i a i
{ t f i e , i O ! !
6 7 -4 L 6..
0' 1 . 2 3
.,dl7 =.
4- TIME (HOURS) e *cW L % '
L r .
. . . . .