Similar Documents at Surry |
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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML20195E2401999-05-31031 May 1999
Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag
ML18152B7081998-11-30030 November 1998
Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un.
ML20203H2301997-09-30030 September 1997
Rev 0 to COLR Surry 2 Cycle 15 Pattern Uz
ML18153A5261997-03-31031 March 1997
Rev 0 of COLR Surry 1,Cycle 15 Pattern Lt.
ML20113B5101996-04-30030 April 1996
Rev 0 to Surry Power Station Unit 2,Cycle 14 Colr
ML18152A0551995-11-22022 November 1995
Rev 0 to Surry Unit 1 Cycle 13 Core Performance Rept.
ML18153A6641995-08-31031 August 1995
Rev 0 to COLR Surry 1,Cycle 14,Pattern Oj.
ML20093C0001995-07-31031 July 1995
Rev 1 to COLR Surry 2 Cycle 13 Pattern Ug
ML20083C9881995-04-10010 April 1995
Cycle 12 Core Performance Rept, Dtd Mar 1995
ML20084Q9031995-02-28028 February 1995
Rev 0 to COLR Surry 2 Cycle 13 Pattern Ug
ML18151A7181994-04-15015 April 1994
Rev 0 to Technical Rept NE-978, Surry Unit 1 Cycle 12 Core Performance Rept.
ML18153B3851993-11-30030 November 1993
Reload Nuclear Design Methodology.
ML18151A9361993-05-31031 May 1993
Rev 0 to Technical Rept NE-930, Surry Unit 2,Cycle 11 Core Performance Rept.
ML18153D3831993-05-25025 May 1993
Cycle 12 Core Operating Limits Rept.
ML18153D3841993-05-25025 May 1993
COLR for Surry 2 Cycle 12.
ML18153D0461992-05-31031 May 1992
Rev 0 to Technical Rept NE-893, Surry,Unit 1,Cycle 11 Core Performance Rept.
ML18151A9691991-07-23023 July 1991
Rev 0 to Technical Rept NE-850, Surry Unit 2,Cycle 10 Core Performance Rept.
ML18151A5571991-06-30030 June 1991
Rev 0 to NE-823, Surry Unit 1 Cycle 10 Core Performance Rept. W/910719 Ltr
ML18151A8911988-10-31031 October 1988
Rev 0 to Surry Unit 2,Cycle 9 Core Performance Rept.
ML18153B4771988-06-30030 June 1988
Cycle 9 Core Performance Rept.
ML18149A4361986-10-31031 October 1986
Cycle 8 Core Performance Rept.
ML18149A4301986-09-30030 September 1986
Rev 1-A to Reload Nuclear Design Methodology.
ML18149A2151986-05-31031 May 1986
Cycle 8 Core Performance Rept.
ML20135H9491985-08-31031 August 1985
Rev 1 to Reload Nuclear Design Methodology
ML18139C3341983-03-31031 March 1983
Rev 1 to Reload Safety Evaluation for Surry 2 Cycle 7 (Pattern JB2).
1999-05-31
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 October 1999
Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619.
ML18152B3531999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr
ML18152B6651999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr
ML18152B4421999-08-27027 August 1999
LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr
ML18152B4411999-08-27027 August 1999
LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed
ML18151A3981999-08-13013 August 1999
SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage.
ML18152B3771999-08-13013 August 1999
LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms
ML18152B3791999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr
ML18152B3911999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr
ML18152B4341999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr
ML20195E2401999-05-31031 May 1999
Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag
ML18152B4181999-05-18018 May 1999
LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr
ML18152B4161999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr
ML18152B4111999-04-28028 April 1999
LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr
ML18152B6511999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2
ML18153A2741999-03-29029 March 1999
LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
ML18153A2681999-03-19019 March 1999
LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
ML18152B7331999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr
ML18152B5421999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With 990210 Ltr
ML18151A3031999-01-29029 January 1999
ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements.
ML18152B7261999-01-21021 January 1999
LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
ML18152B6011998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With 990115 Ltr
ML18152B5781998-12-16016 December 1998
LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B5811998-12-16016 December 1998
LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B7121998-12-0404 December 1998
LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened
ML18152B7041998-12-0101 December 1998
LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr
ML18152B7081998-11-30030 November 1998
Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un.
ML18152B5721998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With 981214 Ltr
ML18152B6161998-11-0606 November 1998
LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable
ML18152B6241998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With 981111 Ltr
ML18152B6081998-10-23023 October 1998
LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely
ML18152B6881998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With 981012 Ltr
ML18153A3271998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2
ML18152B7811998-07-31031 July 1998
LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
ML18153A3161998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2.W/980807 Ltr
ML18152B7621998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Surry Power Station,Units 1 & 2.W/980707 Ltr
ML18153A2581998-06-0303 June 1998
LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed
ML20248F7441998-05-31031 May 1998
Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity
ML18153A3141998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Surry Power Station,Units 1 & 2.W/980610
ML18152B8241998-05-22022 May 1998
LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed
ML18152B8161998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2.W/980508 Ltr
ML18152B7951998-04-29029 April 1998
LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6
ML18153A2511998-04-22022 April 1998
LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced
ML18153A2521998-04-22022 April 1998
LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame
ML20217P9941998-04-0707 April 1998
Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024
ML18153A2951998-03-31031 March 1998
Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ 980408 Ltr
ML18153A2391998-03-13013 March 1998
LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued
ML18153A2341998-03-0909 March 1998
LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition
ML18153A2301998-03-0606 March 1998
LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs
ML18153A2251998-03-0404 March 1998
LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket
1999-09-30
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Text
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E 1
CORE OPERATING LIMITS REPORT SURRY 2 CYCLE 13 PATTERN UG
' Revision.1 July,*1995 l
i 4
S2C13/UG COLR, Rev. 1 (July 95) Page 1 of 6 9510120190 951006 PDR ADOCK 05000281
- -.P_._,.,~~. ,
.PDR.
. . . - . - - - - _ . . _ . - - . . - - . . . . . . . = -- . - _ . - . . - . . - . ..-
l -
i l
1.0 CORE OPERATING LIMITS REPORT The Surry 2 Cycle 13 Core Operating Limits Report (COLR) has been
. revised to reflect changes in COLR parameters impacted by the '
implementation of the core uprate (increase in thermal power from 2441 ,
MW to 2546 MW) for Surry Power Station Unit 2.
Accident- reanalyses for core uprate utilized a maximum positive moderator temperature coefficient of +6 pcm/*F versus the previous analysis value of +3 pcm/*F. Technical Specifications 3.1.E and 5.3. A.6.b place an upper limit of +6 pcm/*F on the MTC. Section 2.1 of this COLR has been revised to' incorporate the +6 pcm/*F value.
The increase in power requires that a reduction in the FAH limit be made to ensure that the LOPAR fuel still meets thermal-hydraulic requirements. To accommodate this without unnecessarily penalizing the SIF fuel, separate FAH limits for LOPAR and SIF fuel have been established which ensure DNB limits are met for the applicable fuel type. This change is reflected in COLR section 2.4 Nuclear Enthalpy
' Rise Hot Channel Factor - FAH(N) .
This Core Operating Limits Report for Surry Unit 2 Cycle 13 operation at ,
uprate conditions has been prepared in accordance with the requirements l of Technical Specification (TS) 6.2.C.
The Technical Specifications affected by this report are: l TS 3.1.E and TS 5.3.A.6.b - Moderator Temperature Coefficient TS 3.12.A.2 and TS 3.12.A.3 - Control Bank Insertion Limits TS 3 .12 . B .1 and TS 3 .12 . B . 2 - Power Distribution Limits i
l i
S2C13/UG COLR, Rev. 1 (July 95) Page 2 of 6 !
2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.2.C.
2.1 Moderator Temperature Coefficient (TS 3.1.E and TS 5.3.A.6.b) 2.1.1 The Moderator Temperature Coefficient (MTC) limits are:
+6.0 pcm/*F at less than 50 percent of RATED POWER, or
+6.0 pcm/ F at 50% of Rated Power and linearly decreasing to O pcm/*F at Rated Power 2.2 control Bank Insertion Limits (TS 3.12.A.2) 2.2.1 The control rod banks shall be limited in physical insertion as shown in Figure 1.
2.3 Heat Flux Hot Channel Factor-FO(Z) (TS 3.12.B.1)
CFQ FQ(Z) s ----
P 1
CFQ FQ (Z) s ---
0.5 THERMAL POWER where: P= --------------
RATED POWER 2.3.1 CFQ = 2.32 l Y
2.3.2 K(Z) is provided in Figure 2.
S2C13/UG COLR, Rev. 1 (July 95) Page 3 of 6
i 2,4' Nuclear Enthalov Rise. Hot Channel Factor - FAH(N) (TS 3.12.B.1).
4 FAH(N). s CFDH * (1 +:PFDH * (1 -.P))
THERMAL POWER where: P = -------------
RATED POWER
-2.4.1.a CFDH - 1.56 for Surry Improved fuel (SIF)
~
2.4.1;b CFDH = 1.346 for LOPAR fuel ji 2.4.2 PFDHL= 0.3 i '
i i.
~S2C13/UG COLR, Rev. 1 (July.95) Page 4 of 6 i.
FIGURE 1 CONTROL BANK INSERTION LIMITS l
FULLY WITHDRAWN - 227 Steps j 230 220 p ,,73, ,, 7) 210 200 i
190
/ C Bank p , i,o, 3,3) 180 170 , , )
160 2
O 150
/ /
E u) 140 5 '5'1 f
/
k 130 #
- o. s 10 3 120
/
, 3 a.%m 110
/
SI100 '
b 90 f I
~
O 80 70 60
1 50 /
40 30
20 10 0
0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 FRACTION OF RATED THERMAL POWER 4
4 S2C13/UG COLR, Rev. 1 (July 95) Page 5 of 6
FIGURE 2 K(Z) - NORMAllZED FO AS A FUNCTION OF CORE HEIGHT 1.2 1.1
- 6.1.0; 1
% g0.925) 0.9 0.8 0
'OO.7 N
a g 0.6 cc o
y 0.5 l E
w 0.4 0.3 .
0.2 0.1 0
0 1 2 3 4 5 6 7 8 9 10 11 12 CORE HEIGHT (FT) )
l l
S2C13/UG COLR, Rev. 1 (July 95) Page 6 of 6
