Similar Documents at Salem |
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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML18107A2881999-04-0707 April 1999
Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11.
ML18106A6721998-06-12012 June 1998
Startup & Power Ascension Units 1 & 2.
ML18106A3861998-03-16016 March 1998
Final Version of COLR for Salem Unit Cycle 13
ML18106A2671997-12-17017 December 1997
Rev 0 to NFS-0163, Colr.
ML18101A4221994-12-15015 December 1994
Radial Peaking Factor Limit Rept,Salem Unit 2,Cycle 9.
ML18100A6841993-09-16016 September 1993
Cycle 12 Peaking Factor Limit Rept.
ML18096A6641992-03-18018 March 1992
Cycle 11 Peaking Factor Limit Rept.
ML18096A6231992-01-10010 January 1992
Nonproprietary Version of CDC-92-014, Peaking Factor Limit Rept Evaluation for Salem Unit 2 Cycle 7 Redesign.
ML18092B0701986-03-14014 March 1986
Rev 1 to Salem Reactor Physics Methods.
ML20202A8331986-03-14014 March 1986
Rev 0 to Accident Analysis Methods for Application to Salem Nuclear Units
ML18092B0011986-01-10010 January 1986
Rev 0 to Vol I of Salem Reactor Physics Methods Model Qualification.
ML18092A5081984-11-27027 November 1984
Reload Safety Evaluation,Salem Nuclear Plant Unit 2, Cycle 3.
1999-04-07
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML18107A5581999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr
ML18107A5571999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr
ML18107A5301999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr
ML18107A5311999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913
ML18107A5031999-08-26026 August 1999
LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr
ML18107A5201999-08-12012 August 1999
Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF).
ML18107A4811999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr
ML18107A4821999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr
ML18107A4691999-07-28028 July 1999
LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr
ML18107A4441999-07-0606 July 1999
LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr
ML18107A4211999-07-0202 July 1999
LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr
ML18107A4331999-07-0101 July 1999
LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr
ML18107A4321999-07-0101 July 1999
LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr
ML18107A5211999-07-0101 July 1999
Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF).
ML18107A4351999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr
ML18107A4341999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML18107A3951999-06-17017 June 1999
LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr
ML18107A3661999-06-0909 June 1999
LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr
ML18107A3551999-06-0202 June 1999
LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr
ML18107A3441999-06-0101 June 1999
Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716
ML18107A3541999-06-0101 June 1999
LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr
ML18107A3681999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr
ML18107A3721999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr
ML18107A2931999-05-12012 May 1999
LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr
ML18107A2781999-05-10010 May 1999
LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr
ML18107A2791999-05-0404 May 1999
LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr
ML18107A2741999-05-0303 May 1999
LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr
ML18107A3711999-04-30030 April 1999
Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1
ML18107A3151999-04-30030 April 1999
Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1
ML18107A2991999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr
ML18107A2971999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr
ML18107A2351999-04-23023 April 1999
LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr
ML18107A2881999-04-0707 April 1999
Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11.
ML18107A1821999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr
ML18107A1831999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr
ML18106B1471999-03-29029 March 1999
LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr
ML18106B1021999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr
ML18106B1011999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr
ML18106B0931999-02-25025 February 1999
Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified
ML18106B0701999-02-16016 February 1999
LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr
ML18106B0551999-02-0101 February 1999
Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl
ML18106B0561999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr
ML18106B0571999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr
ML20205P1671999-01-31031 January 1999
a POST-PLUME Phase, Federal Participation Exercise
ML18106B0441999-01-29029 January 1999
Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables
ML18106B0491999-01-28028 January 1999
LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr
ML18106B0401999-01-18018 January 1999
LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr
ML18106B0251998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr
1999-09-30
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Text
_LR-N98 QO Oi
- NFS-0163 Revision 0 December 17, 1997 l .O ' CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Salem Unit l Cycle 13 has been prepared in accordance with the requirements of Technical Specification 6.9.1.9.
The Technical Specifications affected by this report are listed below:
3/4.1.1.4 Moderator Temperature Coefficient 3/4.1.3.5 Control Rod Insertion Limits 3/4.2. l Axial Flux Difference 3/4.2.2 Heat Flux Hot Channel Factor - F0(Z) 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor - fN Mi qso1230395 980115 Page 1 of 7 PDR ADOCK 05000272 P PDR I_
LI~ - N9 8 0.0 0 7
- OPERA TING LIMITS The cycle-specific parameter limits for the specifications listed in Section l.O are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.9. l. 9.
2.1 Moderator Temperature Coefficient (Specification 3/4.1. l .4) 2.1. l The Moderator Temperature Coefficient (MTC) limits are:
The BOUAROrrIZP-MTC shall be less positive than 0 Afclk/°F.
The EOUARO/RTP-MTC shall be less negative than 4.4x 10-4 ~°F.
2.1.2 The MfC Surveillance limit is:
The 300 ppm/ARO/RTP-MfC should be less negative than or equal to-3.7xiQ-4 ~°F.
where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER EOL stands for End of Cycle Life RTP stands for Rated THERMAL POWER Page 2 of 7
LR-N980007
- ATTACHMENT 1 2.2 . Control Rod Insertion Limits (Specification 3/4.1.3.5)
- NFS-0163 Revision 0 December 17, 1997 2.2.1 The control rod banks shall be limited in physical insertion as shown in Figure 1.
2.3 Axial Flux Difference (Specification 3/4.2. l)
[Constant Axial Offset Control (CAOC) Methodology]
2.3.1 The Axial Flux Difference (AFD) target band is +6%, -9%.
2.3.2 The AFD Acceptable Operation Limits are provided in Figure 2.
2.4 Heat Flux Hot Channel Factor* F0(Z) (Specification 3/4.2.2)
[Fxy Methodology] *
THERMAL POWER where: P=
RATED THERMAL POWER 2.4. l F J1P = 2.40 2.4.2 K(Z) is provided in Figure 3.
Page 3 of 7
LR-N980007
- NFS-0163 Revision 0 December 17, 1997
2.4.3 where
F~_R,TP
.. -- 1. 77 fior the unro dded core p lanes 2.13 for the core plane containing Bank D control rods PF,.v =0.3 2.5 Nuclear Enthalpy Rise Hot Channel Factor - fN t.H (Specification 3/4.2.3)
F~ = F,:;P [l.O + PFMl (1.0 - P)]
Operation with pNm values equal to or less than those given by the above equation are acceptable.
p = THERMAL POWER
~~~~~~~~~~~
where:
RATED THERMAL POWER 2.5.1 F:ff = 1.65 2.5.2. PFMl = 0.3 Page 4 of 7
LR.:;..N9 8 0 00 7
- NFS-0163 Revision 0 December 17, 1997 FIGURE l ROD BANK INSERTION LIMITS vs. THERMAL POWER 240
/
220 17,2281 ' 172,2281
/
200 I !BANK Bl /
180 I
10,1861
, I I
1100,1701 160 I
' I
/
!BANK Cl J
I 140 z
0 1-i e--
~ 120
c.
~
I I v
)
100
~
~ 80 I IBANK DI CJ 60
- / 0 58 I I
/
40
' I J
I 20 0*
0 10 2Q
~
I 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER (\)
Page 5 of 7
LR ::_.N 9 8 0 0 0 7
- NFS-0163 Revision 0 December 17, 1997 FIGURE 2 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER 100 I I I I ( -11, 90) I 1(+11, 90)1 80 I \
!UNACCEPTABLE' OPERATION I \ IUNACCEPTABLEI OPERATION I \
'ACCEPTABLE OPERATION v \
I r( - n, 50) I (+31, 50) I o~
~
20
~
0
-50 -40 -30 -20 -10 0 10 20 30 40 50 FLUX DIFFERENCE (\ Delta I)
Page 6 of 7
- NFS-0163 Revision 0 December 17, 1997 FIGURE3 K(Z) - NORMALIZED F0 (Z) AS A FUNCTION OF CORE HEIGHT
- 1. 2
- 1. 0 ~
-N
-~
~ 0 .8 0
E-<
~
i:... FQ K (z) HEIGHT (ft)
C!) ------ -------- ----------
z H
2.40 1.0 o.o
- ..:: 2.40 1. 0 6.0
~
2.22 0.925 12.0
~ 0. 6 Cl i::a N
H
..J
~
0 "
z
- 0. 4
- 0. 2
~
- 0. 0 0 2 4 6 8 10 12 CORE HEIGHT (Feet)
Page 7 of 7
