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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092K5471995-09-20020 September 1995 Revised Tech Spec Pages 4-31,4-32 & 4-33,incorporating Change in TS Section 4.4.1.5 ML20091L2911995-08-23023 August 1995 Proposed Tech Specs Page 6-11a,incorporating Ref to 10CFR20.1302 ML20087F4921995-08-11011 August 1995 Proposed TS Section 3.2 Re Makeup,Purification & Chemical Addition Sys Requirements ML20085N1601995-06-22022 June 1995 Proposed Tech Specs Revising Replacement Pages in Package & Remove Outdated Pages,In Response to NRC Request for Addl Info ML20084L4351995-06-0101 June 1995 Proposed TS 5.3.1.1,describing Use of Advanced Clad Assemblies ML20084N3501995-06-0101 June 1995 Proposed Tech Specs,Deleting RETS & Relocating TSs Per Guidance in GL 89-01 & NUREG-1430 ML20084B3361995-05-24024 May 1995 Proposed Tech Specs Re Change in Surveillance Test Requirements for source-range Nuclear Instrumentation ML20083N7841995-05-17017 May 1995 Proposed Tech Specs,Consisting of Change Requests 252, Removing Chemical Addition Sys Requirements from TS to COLR ML20079A7811994-12-23023 December 1994 Proposed Tech Specs Page 3-32a ML20069A6781994-05-20020 May 1994 Proposed Tech Specs,Supporting Cycle 10 Control Rod Trip Insertion Time Testing ML20065M6831994-04-19019 April 1994 Proposed Tech Specs,Reflecting Deletion of Audit Program Frequency Requirements ML20065K0451994-04-11011 April 1994 Proposed Tech Specs Reflecting Relocation of Detailed Insp Criteria,Methods & Frequencies of Containment Tendon Surveillance Program to FSAR & Providing Direct Ref to Existing Tendon Surveillance Program ML20073C7731994-03-22022 March 1994 Proposed Tech Specs Re Control Rod Trip Insertion Time Testing 1999-09-01
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20198T4721997-12-31031 December 1997 TMI-1 Cycle 12 Startup Rept ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20096F0521995-12-31031 December 1995 TMI-1 Cycle 11,Startup Rept ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program 1999-09-01
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METROPOLITAN EDISON CCMPANY JERSEY CENTRAL POWER & LIGHT CO?@ANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Suecification Change Request No. 80 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.
METROPOLITAN EDISON COMPANY By /s/ J. G. Herbein Vice President Sworn and subscribed to me this 16th day of May , 1978.
/s/ George J. Troffer Notary Public 7910810 62 5 1490 294
Three Mile Island Nuclear Station, Unit 1 Operating License No. DPR-50 Docket No. 50-289 Technical Scecification Change Recuest No. 80 The licensee requests that the attached changed figures replace figures 2.3-2, 3 5-2E and 3.5-2H of the existing Technical Specifications.
Reasons for Change Request The attached figures have been changed to accommodate the measured Cycle h power peaks, which did not meet the acceptance criteria of 7.5% on the total peak. A nuclear uncertainty of 13 5% requires new APSR Position Limits, Power Imbalance Limits and RPS Setpoints.
Safety Analysis Justifying Chance The Safety Analysis LOCA initial conditions are preserved by the alarm and trip setpoints which restrict operational flexibility. The setpoints are determined based en a calculational model. The Physics Testing Program shows real core operation and it verifies that the core is operating within the bounds of the analysis . When the physics testing indicates measured values greater than the acceptance criteria, the discrepancy is accounted for by increased uncertainties and the alarm and trip setpoints are adjusted to further restrict operational flexibility to preserve the Safety Analysis LOCA initial conditions.
The computer code used for the revised Tech. Spec. limits was the same as for the original analysis - the FLAME 3 computer code. That is, the calculated relative peaks used ver* the same. The differences in the revised imbalance trip setpoints (RPS) and the operational imbalance and APSR position limits (LOCA) compared to those currently approved resulted from the use of a larger calculational uncertainty factor when adjusting the calculated peaks and cccparing them to the allowable ther=al criteria (CFM, DNB, LOCA) .
The magnitude of the calculational uncertainty factor was determined by using the larger of the measured / calculational discrepancies observed for the radial and total peaks during startup testing fer Cycle k. At 75% FP these discrepancies were 9 6 and 11.29% for the radial and tot al peaks, respectively. For con-servatism, 6% vas added to the calculation 21 uncertainty values of 5% for the radial peak and 7.5% for the total peak, yielding 11% and 13 5%. The use of these values to adjust FLAME 3 peaks ic conservative, since the RPS is not DN3 limited (strong dependence on radial peak) even with the 11% uncertainty applied to the radial peaks. The CFM criteria (total peak dependent) are limiting, and the 13 5%
uncertainty applied is over 2% greater than the discrepancy between =easured and calculated values. The same is true of the LCCA criteria which are also total peaking criteria.
With limits for fall power operation derived as described above, the assurance is preserved that the FAC ECCS limits vill not be exceeded and the thermal design criteria vill not be violated.
Figure 2.3-2 was changed to reduce the negative reactor pcVer Lnbalance from -17%
to -12% at breakpoint 32 , without changing the slopes between breakpoints. This adjustment is conservative since the core was Central Fuel Melt (CFM) limited for the RPS, and the total peak which sets CFM limits , had a measured to calculated discrepancy less than h% above the acceptance criteriun.
1490 295
Figure 3.T -dE was changed to reduce the negative axial power imbalance from
-23.h0% to -17.Th% at the 102% FP breakpoint, and from -21.59% to 17.83% at the 92% FP breakpoint.
Figure 3 5-2H vas changed to include power restrictions for APSR position limits between 0% and 6.1% vithdrawn.
The adjustments to Figure 3.5-2E and Figure 3 5-2H are also conservative since these limits are based on LOCA KW/ft criteria and are not set from predicted total peaks.
These changes to alarm and trip setpoints assare operation with complete protection with regard to DNS, CFM and LOCA criteria.
Amendment Class (10 CFR 170)
The licensee has determined that, because this requested ame;dment involves a single safety issue, this is a Class III Amendment (per 10 CFR 170.22).
The appropriate remitt;_.e, therefore, is $h,000.00.
Additional Information Per NRC verbal request of May 15, 1978, attached in support of this Technical Specification Change Request, is (a) Radial Peaking Facters, power map at 75%
full power; (b) Total Peaking Factors , power map at 75% full power; and (c) su= mary of Zero Power Physics Testing for TMI-1, Cycle k.
1490 296
v v
THERNAL POWER LEVEL 5
- 120
(-12,1083 - 110 (108) (17,108)
/t I - 100 l g, = 1,3 ACCEPTABLE N2 = -1.0 4 PUMP
-- 90 (35,90)
(-35,85) / OPERATION i I
(80.7) 50 ACCEPTABLE - 70 3 & 4 PUNP (35,62.7)
~
(-35, 57.7) /0PERATION-- 60 l I
, (53.1) g -- 50 I l ACCEPTABLE - 40 2,3, & 4 PUNP (35,35.1)
(-35,30.1) / OPERATION g _ 30 1
Y M $ !
l u E E E I I I I t a I f f f g g [ g 60 -50 -40 20 -10 0 10 20 30 40 50 60 70 w
Reactor Power imoalance, 5 PROTECTION SYSTEN MAXINUM d LOTABLE s SETPOINTS FOR REACTOR POWER INd4 LANCE TNI-1, CYCLE 4 (FROM 0 TO 125 + _ EFPD)
Figure 2,3-2 1490 297
s Power, % of 2535 MWt RESTRICTED REGION --110
-17.Th, 102 -
- 00 **I
[
L
-17.83, 92 s.25.92 90
-21.59, 80 <
V -
- 80 0
PERNISSIBLE OPERATING REGION 60
- - 50
- . 40 m
30
- 20
- 10 I i i i t i i I i I 40 -30 -20 -10 0 10 20 30 40 50 b
Axial Power imbalance, %
L POWER IMBALANCE ENVELOPE FOR OPERATION FROM 0 TO 125 1 5 EFPD TMI-1, CYCLE 4 Figu re 3. 5-2E 1490 298
J 57.9,102
L RESTRICTED ,
'6.1, 92 90 - REGION V o, 80 57.9,80 80 70 -
$ 100,70 60
- PERMISSl8LE
f
=
REGION E 40 -
30 -
20 10 -
y I f f f f *l I f f 0 10 20 30 40 50 60 70 80 90 100 -
APSR 5 withdrawn y APSR POSITION LIMITS FOR OPERATION FROM 0 TO 125 ! 5 EFPD THI-1, CYCLE 4 Figure 3.5-2H
~
0 1490 299
RADIAL PEAKING FACTORE 1550-08 Revision 2 DATA SHEET E2D1 h/17/78 8 9 10 11 12 13 1 14 15 0 929 1.097 1.251 1.010 1.258 0.837 0.812 0.726 0.932 f.063 1.207 0 990 1.19h 0.93h 0.786 0.801 1.25h 1.12h 1.209 1.0h9 1.205 0.863 0.76h 1.22h 1.058 1.131 1.07 8 1.166 0.851 0.803
- 1.377 1.102 1.121 0.906 1.13h 0.660
. Maximum Peak -
' 1.2h5 1.0hh 1.096 0.935 1.210 0.696 0.925 1.2h3 0 967 0.906 M o.986 1.1h9 0 9h6 1.002 LEGEND X.XXX Measured Value 1.051 1.086 0.637 N 1.13h 0.715 X.XX Predicted Value 1.013 0.h97 0 0.5h1 1.377 - 1.2h5 x 100 = + 9 59%
1.377
% wd.
Gp. 1-4 100 Gp. 5 100 Gp. 6 100 Gp. 7 85 Gp. 8 29 Power Level Th.6 gyp Effective Full Power Days 2.37 EFPD TECH. SPEC. CHA: IGE REQUEST 80 2h.0 ADDITIONAI INFORMATION Page 1 of 3
. 1550-08 i #
TOTAL PEAKING FACTORa "G 8N8 DATA SIM E2D2 8 9 10 11 12 13 14 15 1.12h 1 307 1 516 1.216 1 536 1.065 0 993 0 915 H
1.12h l'.2h2 1.h13 1.132 1.h38 1.220 1.03h 1.0h1 1 503 1.h05 1.h6h 1.31h 1.h71 1.085 0 922 1.h39 1.2h1 1.313 1.295 1.h31 1.072 1.035 1.719 1.3h6 1.h51 1.078 1.h18 0.817 Maximum Peak i 1 525 1.2h8 1.h08 1.096 1 501 0.882-1.092 1 516 1.150 1.085 M 1.175 1.387 1.110 1.230 LEGEND X.XXX Measured Value 1.333 1.307 0.778 N
X.XX Predicted Value 1.232 1.380 0.881
- - - - - ~ ~ - -
0 595 0
0.657 1.719 - 1.525 x 100 = 11.29%
1.719
% vd.
Cp. 1-4 100 Gp. 5 100 Gp. 6 100 Gp. 7 85 Gp. 8 29 Power Level Th.6 %FP Effective Full Power Days 2.37 EFPD TECH. SPEC. CHANGE REQUEST 80 ADDITIONAL INFORMATION Page 2 of 3 25.0 1490 301
SUMMARY
OF ZERO POWER PHYSICS TESTING FOR TMI-1 CYCLE h Test Predicted Worth Measured Werth
- 1. All rods out boron 1226 1 100 ppm 1231 ppm concentration
- 2. First isothermal tempera- -1.1 X 10 % +2.6 X 10" % Ak/k/ F ture coefficient (1215 Ak/k/ F (123h ppts) ppms) i h X 10 % Ak/k/ F Moderator temperature coefficient shall be less than + 5 X 10 -3 % Ak/k/ F at zero power to assure a nonpositive temperature coefficient above 95% power.
3 Group 7 Integral Rod 1.37 1 0.21 % Ak/k 1.h8 % Ak/k Worth
- h. Group 6 Integral Rod 1.00 1 0.15% Ak/k 1.07 % Ak/k Worth 5 Group 5 Integral Rod 1.2h i 0.19% Ak/k 1.h2 % Ak/k Worth
- 6. Groups 5-7 Total Rod Worth 3.61 1 0 36 % Ak/k 3.97% Ak/k 7 Shutdown margin >1.0% Ak/k verification (vorst rod stuck out)
- 8. Ejected rod < 1.0% Ak/k Error adjusted maximum ejected rod - 0.98". Ak/k Control rod at D h using boron swap method w/ Group 5,0% vithdrawn Control rod at N-12 using boren swap method - 0.83% Ak/k Centrol rod at N h using rod swap method with Group 5 -
0.898% Ak/k Control rod at D-12 using rod swap with Group 5 - 0.85% Ak/k TECH. SPEC. CHANGE REQUEST 80 ADDITICNAL INFORMATION Page 3 of 3 1490 70?