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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210R8051999-08-10010 August 1999 Startup Test Rept for Cycle 7 ML20210K3631999-07-30030 July 1999 Marked-up & Revised TS Bases Page B 3/4 5-2 Re ECCS ML20196G3671999-06-23023 June 1999 Proposed Tech Specs Increasing AOT for Crac from 30 Days to 60 Days on One Time Basis for Each Train to Facilitate on- Line Implementation of Design Enhancements During Current Operating Cycle ML20198E7411998-12-16016 December 1998 Proposed Tech Specs Pages Re LAR-98-15,involving Relocation of TS 3/4.7.10 & Associated TS Table 3.7-3 to Technical Requirements Manual ML20198E7831998-12-16016 December 1998 Proposed Tech Specs Pages to LAR 98-09,re Editorial & Administrative Changes to TS ML20155J1821998-11-0404 November 1998 Proposed Tech Specs 4.5.2b.1,removing Prescriptive Requirements of Using Venting Process as Sole Means to Verify That ECCS Piping Is Full of Water ML20249B4181998-06-17017 June 1998 Proposed Tech Specs 3.7.6 Re Control Room Emergency Makeup Air & Filtration Subsystem ML20247R7021998-05-20020 May 1998 Proposed Tech Specs Re Rev of Refueling Water Storage Tank low-low Level Setpoint ML20217E8871998-04-22022 April 1998 Proposed Tech Specs Re Surveillance Intervals to Accommodate 24-month Fuel Cycle,Per GL 91-04 ML20217F9651998-04-21021 April 1998 Proposed Tech Specs Page 3/4 5-5 Re Venting of Operating Chemical Vol & Control Sys Centrifugal Charging Pump ML20216C5921998-04-0808 April 1998 Proposed Tech Specs Changing Surveillance Intervals to Accommodate 24-month Fuel Cycle Per GL 91-04 ML20217Q2981998-04-0303 April 1998 Proposed Tech Specs Pages Re LAR 98-02,proposing Changes to TS to Accommodate Fuel Cycles of Up to 24 Months ML20217M3771998-03-27027 March 1998 Proposed Tech Specs 3.7.6 Re Control Room Emergency Makeup Air & Filtration Subsystem ML20217F0961998-03-23023 March 1998 Proposed Tech Specs Pages,Incorporating New Spec 3.0.5 Administrative Controls,Currently Approved for Use in NUREG-1431 ML20217Q1031998-03-0505 March 1998 Proposed Tech Specs Incorporating Programmatic Controls for Radioactive Effluents & for Environ Monitoring Conforming to Applicable Regulatory Requirements ML20217N8211998-03-0202 March 1998 Proposed Tech Specs 4.5.2B.1,excluding Prescriptive Requirement to Vent Operating CVCS CCP Casing ML20217N7321998-03-0202 March 1998 Proposed Tech Specs Pages,Revising Frequency for Performance of Specific Surveillances & Deleting Requirements for Accelerated Testing When Number of Valid Test Failures Associated W/Edgs Is Met or Exceeded ML20217Q1111998-02-25025 February 1998 Rev 18 to Odcm ML20211F4401997-09-26026 September 1997 Cycle 6 Startup Test Rept for Seabrook Station,Unit 1 ML20211E9981997-09-26026 September 1997 Proposed Tech Specs 3.7.6,separating Requirements for CR HVAC Sys Re Operation of CR Emergency Makeup Air & Filtration Sys Subsystem & CR Air Conditioning Subsystem ML20195J1451997-07-23023 July 1997 Rev 15 to Seabrook Station Operating Experience Manual (Ssoe) ML20148G0011997-05-29029 May 1997 Proposed Tech Specs Replacing Term Zircaloy W/Terminology That Identifies NRC Approved Westinghouse Fuel Assembly Design Consisting of Assemblies W/Either ZIRLO or Zircaloy- 4 Fuel Cladding Matl ML20148K1251997-05-0707 May 1997 Rev 6 to Part I, Seabrook Station Pump & Valve IST Program Plan ML20135C3541997-02-26026 February 1997 Proposed Tech Specs,Providing Retyped Page of Proposed Changes Re Design Features Fuel Assembly Reconstitution ML20134Q3451997-02-18018 February 1997 Proposed Tech Specs 5.3.1 Re Fuel Assemblies ML20134L8681997-02-12012 February 1997 Proposed Tech Specs 6.0 Re Administrative Controls ML20138J3351996-12-19019 December 1996 Rev 16 to Offsite Dose Calculation Manual ML20129B8361996-10-17017 October 1996 Proposed Tech Specs,Consisting of Change Request 96-02, Proposing Changes That Involve Relocation of Four TS Re Instrumentation Requirements Contained in TS Section 3/4.3 & Relocation of Selected Requirements ML20129B7761996-10-16016 October 1996 Proposed Tech Specs,Consisting of Change Request 96-06, Proposing Four Changes Re EDG Requirements Contained in TS 3/4.8.1, AC Sources ML20113B2031996-06-20020 June 1996 Proposed Tech Specs Re Svc Water Cooling Tower Loop Electrical Supply ML20117K3111996-06-0404 June 1996 Proposed Tech Specs Re Containment Leakage Testing Modifying Implementing Performance Based Program at Seabrook Station IAW 10CFR50,App J,Option B & Reg Guide 1.163 Requirements ML20115J7481996-03-26026 March 1996 Procedure for Ultrasonic Examination of Centrifugally Cast Stainless Steel Piping Using Low Frequency SAFT-UT System ML20138J3621996-03-21021 March 1996 Process Control Program ML20100G8351996-02-16016 February 1996 Startup Test Rept,Cycle 5. W/ ML20094D5341995-10-30030 October 1995 Proposed Tech Spec 3.4.6.2, RCS Operational Leakage Pressure Isolation Valve Table ML20092M1071995-09-22022 September 1995 Proposed TS 3.3.2,Table 3.3-3, ESFAS Instrumentation, Correcting Action Ref for Functional Unit 8.b Re Automatic Switchover to Containment Sump/Rwst Level low-low ML20092K2201995-09-20020 September 1995 Proposed Tech Specs,Changing Plant TS Bases Section 3/4.9.1 for Refueling B Concentration ML20098A4721995-09-20020 September 1995 Proposed Tech Specs,Relocating Functional Unit 6.b, FW Isolation-Low RCS Tavg Coincident W/Rt from TS Requirements Manual Licensee Controlled Document ML20092F9171995-09-12012 September 1995 Proposed Tech Specs Bases Section Clarifying What Specifically Constitutes Operable Pressurizer Safety Valve in Mode 5 ML20092A6331995-09-0505 September 1995 Proposed Tech Specs,Revising Main Steam Safety Valve Setpoints & Max Allowable Power Range Neutron Flux High Setpoints W/Inoperable Main Steam Safety Valves ML20091S1601995-08-28028 August 1995 Proposed Tech Specs Re Positive Moderator Temp Coefficient ML20086R2111995-07-24024 July 1995 Proposed Tech Specs,Relocating Table 3.4-1, RCS PIVs from TS 3.4.6.2, RCS Operational Leakage to Techical Requirements Manual ML20085L1161995-06-16016 June 1995 Proposed Tech Specs Re Increased Requirements for Core Reactivity Control Available from Borated Water Sources ML20084U5521995-06-0707 June 1995 Proposed Tech Specs,Consisting of Amend Request 95-02, Revising Footnote to SR 4.4.7 & Table 3.4-2 to Increase Temp Limit at Which Rc O Levels Determined by Sampling from 180 Degrees F to 250 Degrees F ML20084N9561995-05-31031 May 1995 Proposed Tech Specs Re Operation of Core W/Positive Moderator Temp Coefficient ML20083K7351995-04-19019 April 1995 Rev 74 to Emergency Response Manual (Sser) ML20082L5211995-04-16016 April 1995 Proposed Tech Specs,Revising TS 3.9.4 That Addresses Containment Bldg Penetrations to Allow Use of Alternate Containment Bldg Penetration Closure Methodologies for Postulated Accident Scenarios During Core Alterations ML20081J6021995-03-22022 March 1995 Revised Table A.3-1, Radioactive Liquid Waste Sampling & Analysis Program, to ODCM ML20078E0491995-01-25025 January 1995 Proposed Tech Specs Re Changing of Surveillance Requirement 4.6.1.2.a from Specific Schedule for Performance of Containment ILRTs ML20079B2491994-12-27027 December 1994 Proposed Changes to Part a of ODCM 1999-08-10
[Table view] Category:TEST REPORT
MONTHYEARML20210R8051999-08-10010 August 1999 Startup Test Rept for Cycle 7 ML20211F4401997-09-26026 September 1997 Cycle 6 Startup Test Rept for Seabrook Station,Unit 1 ML20100G8351996-02-16016 February 1996 Startup Test Rept,Cycle 5. W/ ML20073A7341994-09-12012 September 1994 Cycle 4 Startup Test Rept ML20128G1431993-02-0505 February 1993 Cycle 3 Startup Test Rept for Seabrook Station Unit 1 ML20128C7111993-01-21021 January 1993 Reactor Containment Bldg Integrated Leakage Rate Test,Types A,B & C Periodic Test ML20091P5791992-01-29029 January 1992 Cycle 2 Startup Test Rept for Seabrook Station,Unit 1. W/ ML20065F8421990-09-27027 September 1990 Suppl 3 to Initial Startup Rept for June-Aug 1990. W/ ML20065E0271990-09-13013 September 1990 Suppl 2 to Seabrook Station Initial Startup Rept for June- Aug 1990 ML20043G2411990-06-13013 June 1990 Suppl 1 to New Hampshire Yankee Seabrook Station Initial Startup Rept for Jul 1989 - May 1990. W/900613 Ltr ML20012D4741990-03-13013 March 1990 New Hampshire Yankee Seabrook Station Initial Startup Rept for Oct 1986 - June 1989. W/900313 Ltr ML20006E5731990-01-30030 January 1990 Reactor Containment Bldg Integrated Leakage Rate Test Types A,B & C,Periodic Test. W/900209 Ltr ML20207J0681988-08-0505 August 1988 Rept for Heat Number L4517 ML20141J5931986-04-30030 April 1986 ASTM E119-83 Std Methods of Fire Tests of Bldg Const & Matls of Metal Siding Partition Wall Assembly ML20211E6101986-04-25025 April 1986 Technical Rept TR-20422(842), Seabrook Nuclear Power Station Unit 1 Reactor Bldg Structural Integrity Test Results. App J & K to Containment Structural Integrity Test & Chronological Log Encl ML20141J5871986-03-31031 March 1986 ASTM E152-81 Std Methods of Fire Tests of Door Assemblies: 3-H Fire Resistance Test of Single Swinging Steel Door Assembly,EM414 Per United Engineers & Constructors Spec 9763.006-24-13 ML20199G1961986-03-31031 March 1986 Reactor Containment Bldg Integrated Leak Rate Test ML20198E7441985-01-10010 January 1985 Test Rept for Full Flow Testing of 16,18 & 20-Inch Main Steam Safety Valve Vent Stacks for Yankee Atomic Electric Co ML20069N2911982-08-31031 August 1982 Tests of Anchorages to Determine Effects of Prying, Final Rept ML20070H9171982-07-27027 July 1982 Test Repts on Emergency Spray Sys Testing Using Transco Therma-Wrap ML20052B6261982-01-22022 January 1982 Pipe Rupture Restraints - Final Stress Rept. 1999-08-10
[Table view] |
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SEABROOK STATION -
UNIT NO,1 STARTUP TEST REPORT CYCLE 6 ,
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- INDEX
'I.0 CIIRONOLOGICAL
SUMMARY
2.0 CORE DESIGN
SUMMARY
3.0 LOW POWER PHYSICS TESTING
SUMMARY
(LPPT)
~4.0. POWER ASCENSION TESTING
SUMMARY
(PAT) 5.0 TEST RESULTS TABLE 1 LPPT RESULTS
- TABLE 2 PAT FLUX MAP RESULTS TABLE 3 FULL POWER THERMAUHYDRAULIC DATA 1-
l'.0 ' CIIRONOLOGICAL
SUMMARY
4 Cycle 6 Fuel Load was completed June 12, 1997. Subsequent operation / testing milestones were completed as follows:
INITIAL CRITICALITY 06/26/97 LPPT COMPLETED 06/27/97 ON LINE 06/28/97 30% PAT COMPLETED 06/29/97 50% PAT COMPLETED 06/30/97 75% PAT COMPLETED 07/01/97 l 90% PAT COMPLETED 07/02/97 l
FULL IOWER 07/02/97 t-5
2'.0 CORE des 1GN
SUMMARY
The Cycle 6 core is designed to operate for 22,253 MWD /MTU (575 Effective Full Power Days). Eighty Four (84) fresh fuel assemblies wrn loaded into the Cycle 6 core. Eighty have an enrichment of 4.95 w/o. In addition, the top and bottom 6 inches have an j enrichment of 2.6 w/o creating an axial annular blanket. The remaining four fuel assemblies have an enrichment of 2.4 w/o. They are replacements for four once burned fuel assemblies i
that had degraded fuel rodsi By comparison, Cycle 5 utilized 80 fresh fuel assemblies with i
enrichments of 4.4 and 4.8 w/o with a similar 2.6 w/o axial annular blanket configuration.
1
- . Fresh assemblies for this cycle are Vantage 511 ZlRLO. This design utilizes ZIRLO for fuel clad, control rod guide tubes and instrument thimbles and Zircaloy-4 for the six low pressure drop mid grids. The mechanical design is identical to the Cycle 5 design which utilized the Inconel protective bottom grid.
i 4
F P
2-l l
J
3.0 -- LOW POWER PIIYSICS TESTING
SUMMARY
Testing was performed in accordance with the following general sequence:
1 Initial Criticality: Criticality was achieved using a controlled withdrawal of the Control banks once all the Shutdown banks had been withdrawn.
I
- 2. Zero Power Test Range Determination: This was determir.ed after the point of adding
- heat had been demonstrated. Additional emphasis was placed on this measurement to
- prevent testing too low in the test range, thus minimizing gamma contribution to the L excore signal.
i
- 3. On-line Verification of the Reactivity Computer: This was detennined using stable startup rates du.'ing flux doubling measurements.
^
- 4. Boron Endpoint Measurement: This was determined with all the Control and Shutdown banks withdrawn and again with only the Control banks inserted.
- 5. Isothcnnal Temperature Coefficient Measurement (lTC): This was determined from the reactivity change measured during a Reactor Coolant temperature change. The Moderator Temperature Coefficient (MTC) was calculated from the ITC Data.
- 6. Rod Worth Measurement: Individual Control Bank wcrths were measured during rod insertion.
l
i
. l 4.0 POWER ASCENSION TESTING
SUMMARY
c . Testing was perfonned_ at- specified power plateaus of 30%, 50%, 75%, 90%_ and 100%
l . Rated Thermal Power (RTP). Power changes were governed by operating procedures and-L fuel preconditioning guidelines specified by the fuel vendor, Westinghouse.
'In order to determine' the core power distribution, flux mapping was performed at 30%,
j- :50L 90% and 100% RTP using the Fixed Incore Detector System. The resultant' peaking
[
factors were compared to Technical Specification limits to verify that the core was operating '
within its design limits.
- - Thermal-hydraulic parameters, -nuclear parameters and related instrumentation were C
monitored throughout the Power Ascension, Data was compared to previous cycle power
-ascension data at each test plateau to identify calibration or system problems. - The major
- areas analyzed were
j:
- 1~. Nuclear Instrumentation Indication: Overlap data was obtained between the Intermediate Range and Power Range channels. Secondary plant: heat balance calculations were performed to verify the Nuclear Instrumentation indications.
g 2. RCS Delta-T Indication: The initial scaling of RCS AT was left the same as' Cycle 5. At 90% RTP, aemal full power AT was extrapolated out using data fro.n 30E 50%,75%
and 90% and AT was rescaled accordingly. Final adjustments were performed at 100%
RTP.
F
- 3. Upper Plenum Anomaly: In early 1992, Westinghouse notified North; Atlantic.that-Seabroek Station may be susceptible to a phenomenon known as- the Upper Plenum Anomaly _(UPA). The UPA is primarily characterid by a periodic step changes of 1*F to 2*F in hot leg temperature. A Design _ Document was prepared at that time to.
- implement a number.of operating contingencies should the UPA be present. Cycle 6 data -
collected at 100% RTP identified the presence of UPA for RCS loops 2 and 3. ~ Revised Tuor Average Scaling (RTAS) was not implemented.
- 4. RCS Temperatures: _ Data was obtained for the-Narrow Range Loop temperatures.
Evalua: ions for Delta-T ( F), Tavo Deviation Alarm Setpoint and T A va / Tars Indication ;
were performed.
4'.0 POWER ASCENSION TESTING
SUMMARY
(Continued)
- 5. Steam and Feedwater Flows: Data was obtained for the steam and feedwater flows.
Evaluations for deviations between redundant channels on individual steam generators were perforned.'
~
- 6. Steam Generator Pressures: Data- was obtained for the steam generator pressures.
Evaluations for deviations betwe(n redundant channels on individual steam generators were performed.
- 7. Turbine Impulse Pressure (Tarr): The initial scaling of impulse pressure was left the same as Cycle 5. Impulse pressure was evaluated at the 75% and 90 % RTP plateaus to determine if the existing scaling would support continued power increase. The Cycle 6 full power value was within 4 PSIG of the initial scaling value. The need for rescaling to the Cycle 6 full power value is being evaluated.
- 8. Incore/Excore Calibration: Scaling factors were calculated from flux map data using tim single point calibration methodology. The nuclear instrumentation power range _ channels were rescaled at 50% and 100% RTP.
- 9. RCS Flow: 'A primary heat balatee was performed at 90% RTP to determine total RCS flow. The measured flow was coirected for the effects of RCS " hot leg temperature streaming" using Westinghouse methodology [WCAP-145-11]. 1 The power ascension test program required no major changes from Cycle 5. 1
, . _ _ _ _ . _ _ . . _ _ . _ . .._ _ __. _ ._. _ _ ._.. _ ...__ .. _ _ _ . _ _ ._ _.. _.._.. ._.-__._m..__.
$.0 'RFSULTS
- 1. Low- Power Physics Testing: The acceptance and review criteria were revised per
- ' Westinghouse letter 94 NA#-G-0030, Recommended Westinghouse Physics Test Results.
- The acceptance criteria and review criteria were met. See Table 1 for results.
2.- Flux Mapping: No problems were identified during the flux maps a: 30%,50%,90%
and 100% RTP. See Table 2 for results.
- 3. Full Power Thermal /Ilydraulic Evaluation: No problems were encountered with the ;
instrumentat:an. An Upper Plenum-Anomaly was identified, however, RTAS was not-implemented. See Table 3 for results.
f
TABLE 1 LOW POWER PHYSICS RESULTS CYCLE 6 ITEM- MEASURED PREDICTED ERROR CRITERIA -
- CONTROL BANK D POSITION 174 steps 116 steps 166 pcm 1500 pcm AT CRITICALITY BORON END POINTS:
- - Al.L RODS OUT 2096 ppm 2138 ppm 257 pcm i 1000 pcm o CONTROL BANKS INSERTED 1622 ppm 1632 ppm 62 pcm 2 500 pcm *
- ALL RODS OUT ITC- (pcm/*F) -2.45 -1.80 0.65 i 2*
ALL RODS OUT MTC (pcm/*F) -0.81 -0.14 N/A < l.16**
CONTROL BANK ROD WORTilS: (pcm)
'e .C 918 942 24 2 141*
'o TOTAL 3109 3136 27 2 2822
- Review criteria, all others are acceptance criteria.
- COLR limit is 1.16 at BOC (1.35 is the max over the entire cycle).
TABLE 2 POWER ASCENSION FLUX MAP RESULTS CYCLE 6 1
ITEM MAP 1 MAP 2 MAP 3 MAP 4
. DATE OF MAP . 06/29/97 06/30/97 07/02/97 07/02/97 POWER LEVEL (%) 29.5 47.6 91.2 100.0 CONTROL BANK D POSITION (steps) 169 191 210 225 RCS BORON (ppm) 1888 1774 1544 1480 Fo- 2.3419 2.2346 1.9272 1.8952 Fm 1.6453 1.5999 1.5368 1.5200 INCORE TILT 1.0178 1.0185 1.0170 1.0169
~
TA BLE 3 FULL POWER THERMAL-IIYDRAULIC DATA: CYCLE 6 ITEM VALUE REACTOR COOLANT T4va 586.05 *F REACTOR COOLANT DELTA-T:
= LOOP 2 57.61 F
= LOOP 3 57.19 F e LOOP 4 57.96 *F REAGOR COOLANT FLOWS: (corrected for hot leg streaming affects)
. LOOP 1 100745 GPM
= LOOP 2 99559 GPM e LOOP 3 103971 GPM e LOOP 4 99695 GPM e TOTAL 403969 GPM AUCTIONEERED 111G11 TAvo 587.13 *F Tatr 587.I8'F TURBINE IMPULSE PRESSURE 669.7 PSIG STEAM GENERATOR PRESSURES:
= B 968.4 PSIG
= C 970.I PSIG
= D 967.9 PSIG 9