ML17332A681
| ML17332A681 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/15/1995 |
| From: | Hannon J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17332A682 | List: |
| References | |
| NUDOCS 9503200314 | |
| Download: ML17332A681 (24) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 193 License No. DPR-58 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Nichigan Power Company (the licensee) dated January 17, 1994 and supplemented February 10,
- 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
iy50$200~~+ 05oooai5 4 9503<5 PDR PDR L
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-58 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. f 93
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 15, i995 Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO.
DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE 3/4 1-18 3/4 1-19 3/4 1-20 B 3/4 2-4 INSERT 3/4 1-18 3/4 1-19 3/4 1-19b 3/4 1-20 B 3/4 2-4
f'
CTIV TY CO TROL YS EMS 3 4.1 3
OVABLE CO OL SSEMB IES GROUP HEIGHT IMITI G CONDITION FOR OPERATION 3.1.3.1 All full length (shutdown and control) rods shall be OPERABLE with all individual indi.cated rod positions within the allowed rod misalignment of their group step counter demand position as follows:
for THERMAL POWER less than or equal to 85X of RATED THERMAL POWER, the allowed rod misalignment is i18 steps, and for THERMAL POWER greater than 85X of RATED THERMAL POWER, the allowed rod misalignment is ~12 steps or as determined from Figure 3.1-4.
Figure 3.1-4 permits an allowed rod misalignment from z13 steps (for APL equal to 101X) to z18 steps (for APL greater or equal to 106X) provided the value of R (defined in Figure 3.1-4) is greater than or equal to 1.04.
ACTION'.
With one or more full length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specification 3,1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With more than one full length rod inoperable or misaligned from the group step counter demand position by more than the allowed rod misalignment, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With one full length rod inoperable due to causes other than addressed by ACTION a,
- above, or misaligned from its group step counter demand position by more than the allowed rod misalignment, POWER OPERATION may continue provided that within one hour either:
1.
The affected rod is restored to OPERABLE status within the above alignment requirements, or THERMAL POWER level is reduced to less than or equal to 85X of RATED THERMAL POWER for rod misalignments less than or equal to z18 steps, or 2.
The affected rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.
POWER OPERATION may then continue provided that:
a)
A reevaluation of each accident analysis of Table 3.1-1 i,s performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions, and
- See Special Test Exceptions 3.10.2 and 3.10.4 COOK NUCLEAR PLANT - UNIT 1 3/4 1-18 AMENDMENT NO. 4$,
Q4, ~,
193
EACTIVITY CONTROL SYSTEMS IMITING CONDITION FOR OPERATION Continued b)
The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and c)
A power distribution map is obtained from the movable incore detectors and F~(Z) and FN~ are verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and d)
Either the THERMAL POWER level is reduced to less than or equal to 75X of RATED THERMAL POWER within one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to less than or equal to 85X of RATED THERMAL POWER, or e)
The remainder of the rods in the group with the inoperable rod are aligned to within the allowed rod misalignment of the inoperable rod within one hour while maintaining the rod sequence and insertion limits as specified in the COLR; the THERMAL POWER level shall be restricted pursuant to Specification 3. 1. 3. 5 during subsequent operation.
SURVEILLANCE RE UIREMENTS 4.1.3.1.1 The position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 8 steps in any one direction at least once per92 days.
4.1.3.1.3 The allowed rod misalignment for THERMAL POWER greater than 85X of RATED THERMAL POWER shall be determined in conjunction with the measurement of APL as defined in Specification 4.2.6,2.
COOK NUCLEAR PLANT - UNIT 1 3/4 1-19 AMENDMENT NO. ~s ~ LN, 193
ALLOWED ROD MISALIGNMENTABOVE 85'lo RTP FIGURE 3.1-4 20 STEPS 19 17 16 15 Applicable when R
> 1.04 LITAfT i fd0%"'RT
'F ~
Vdhere R -
100 101 102 103 104 105 106 107 108 APL GOOK NUCLEAR PLANT - UNIT 1 3/4 1-19b Amendment No. ~93
REACTIVITY CONTROL SYSTEMS OSITION INDICATOR CKQiNELS LIMITING CONDITION FOR OPERATION 3.1.3.2 All shutdown and control rod position indicator channels and the demand position indication system shall be OPERABLE and capable of determining the control rod positions within the allowed rod misalignment specified in Specification 3.1.3.1.
~CTION:
a.
With a maximum of one rod position indicator channel per group inoperable either:
1.
Determine the position of the non-indicating rod(s) indirectly by the movable incore detectors at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and immediately after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or 2.
Reduce THERMAL POWER to less than 50X of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
With a maximum of one demand position indicator per bank inoperable either:
1.
Verify that all rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of the allowed rod misalignment of each other, at least once per 8
- hours, or 2.
Reduce THERMAL POWER to less than 50X of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.1.3.2 Each rod position indicator channel shall be determined to be OPERABLE by verifying the demand position indication system and the rod position indicator channels agree within the allowed rod misalignment at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then compare the demand position indication system and the rod position indicator channels at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
COOK NUCLEAR PLANT - UNIT 1 3/4 1-20 AMENDMENT NO. ~,
193
POW R DISTRIBUTION LIMITS ASES 3
4 2
2 and 3/4 2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CANNEL FACTOR The limits on heat flux hot channel factor, and nuclear enthalpy rise hot channel factors ensure that 1) the design limits on peak local power density and m'nimum DNBR are not exceeded and 2) in the event of a LOCA the peak fuel clad temperature will not exceed the 2200'F ECCS acceptance criteria limit.
Each of these is measurable, but will normally only be determined periodically, as specified in Specifications 4.2.2.1, 4.2.2.2, 4.2.3, 4.2.6.1 and 4.2.6.2.
This periodic surveillance is sufficient to ensure that the hot channel factor limits are maintained provided:
a.
Control rods in a single group move together with no individual rod insertion differing by more than
~ 18 steps from the group demand position (allowed rod misalignment) for power levels less than or equal to 85X of RATED THERMAL POWER.
For power levels greater than 85X of RATED THERMAL POWER, the allowed rod misalignment is from ~12 to ~18 steps, which is dependent on the Allowable Power Level and the ratio of F~ limit at 100X of RATED THERMAL POWER to maximum measured F~ as indicated in Figure 3.1-4.
b.
Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.5.
c ~
The control rod insertion limits of Specifications 3.1.3.4 and 3.1.3.5 are maintained.
d.
The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.
The relaxation in F~ as a function of THERMAL POWER allows changes in the radial power shape for all permissible rod insertion limits.
F~ will be maintained within its limits as specified in the COLR, provided conditions (a) through (d) above are maintained.
When an F~ measurement is taken, both experimental error and manufacturing tolerance must be allowed for.
5X is the appropriate allowance for a full core map taken with the incore detector flux mapping system, and 3X is the appropriate allowance for manufacturing tolerance.
When F~~ is measured, experimental error must be allowed for, and 4X is the appropriate allowance for a full core map taken with 'the incore detection system.
This 4X measurement uncertainty has been included in the design DNBR limit value.
The specified limit for F~ also contains an additional 4X allowance for uncertainties.
The total allowance is based on the following considerations:
COOK NUCLEAP. PLANT - UNIT 1 B 3/4 2-4 AMENDMENT NO. M, 440, 446,
)9$
gp,R REGII c,~
Cg
~o I
o qo UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON< D.C. 2055&4001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
179 License No.
DPR-74 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
E.
The application for amendment by Indiana Michigan Power Company (the licensee) dated January 17, 1994 and supplemented February 10,
- 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2, Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-74 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 179
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~Qc'ttachment:
Changes to the Technical Specifications Date of Issuance:
March 15, 1995 Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO.
179 FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE 3/4 1-18 3/4 1-19 3/4 1-21 B 3/4 2-4 INSERT 3/4 1-18 3/4 1-19 3/4 1-20a 3/4 1-21 B 3/4 2-4
EACTIVITY CONTROL S
STEMS 3 4.
3 OVABLE CO OL ASSEMBLIES LIMIT G CONDITION FOR OPERA ION 3.1.3.1 All full length (shutdown and control) rods shall be OPERABLE with all individual indicated rod positions within the allowed rod misalignment of their group step counter demand position as follows:
for THERMAL POWER less than or equal to 85X of RATED THERMAL POWER, the allowed rod misalignment is tl8 steps, and for THERMAL POWER greater than 85X of RATED THERMAL POWER, the allowed rod misalignment is g12 steps or as determined from Figure 3.1-4.
Figure 3.1-4 permits an allowed rod misalignment from g13 steps (for APL equal to 101X) to ~18 steps (for APL greater or equal to 106X) provided the value of R (defined in Figure 3.1-4) is greater than or equal to 1.04
'PPLICABILITY:
MODES 1* and 2*
ACTION a.
With one or more full length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With more than one full length rod inoperable or misaligned from the group step counter demand position by more than the allowed rod misalignment, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With one full length rod inoperable due to causes other than addressed by ACTION a, above, or misaligned from its group step counter demand position by more than the allowed rod misalignment, j
POWER OPERATION may continue provided that within one hour either:
1.
The affected rod is restored to OPERABLE status within the above alignment requirements, or THERMAL POWER level is reduced to less than or equal to 85X of RATED THERMAL POWER for rod misalignments less than or equal to z18 steps, or 2.
The affected rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3 '.1.1 is satisfied.
POWER OPERATION may then continue provided that:
a)
A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions, and
- See Special Test Exceptions 3 10.2 and. 3.10,3 COOK NUCLEAR PLY - UNIT 2 3/4 1-18 AMENDMENT NO. 40, ~,
179
EACTIVITY CON ROL SYSTEYiS IMITING COÃDI ON FOR OPERATION Continued b)
The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and c)
A power distribution map is obtained from the movable incore detectors and F<(Z) and F~ are verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and d)
Either the THERMAL POWER level is reduced to less than or equal to 75X of RATED THERMAL POWER within one hour and
~ithin t'e next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to less than or equal to 85X of RATED THERMAL POWER, or e)
The remainder of the rods in the group with the inoperable rod are aligned to within the allowed rod misalignment of the inoperable rod within one hour while maintaining the rod sequence and insertion limits as specified in the COLR; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.
SURVEILLANCE REQUIREMENTS 4.1.3 '.1 The position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 8 steps in any one direction at least once per ~2 days.
4.1.3.1.3 The allowed rod misalignment for THERMAL POWER greater than 85X of RATED THERMAL POWER shall be determined in conjunction with the measurement of APL as defined in Specification 4.2.6.2.
COOK NUCLEAR PLANT - UNIT 2 3/4 1-19 AMENDMENT NO 40 407 ~
Ns 179
ALLOWED ROD MISALlGNMENTABOVE 85% RTP FIGURE 3.1-4 20 STEPS 19 18 17 15 14 13 Applicable when R
> 1.04 LIMIT 4 i00%" RTP F ~
Where R
=
F" I
12 100 101 102 103 104 105 106 107 108 API COOK NUCLEAR PLANT - UNIT 2 3/4 1-20a Amendment No. 179
EACTTVITY CONTROL SYSTEMS POSITION INDICATO. CHANNEL -OPERATING IMITING CONDTT ON FOR OPERA~I N
3.1.3.2 All shutdown and control rod position indicator channels and the demand position indication system shall be OPERABLE and capable of determining the control rod positions within the allowed rod misalignment specified in Specification 3.1.3.1.
ACTION:
a.
With a maximum of one rod position indicator channel per group inoperable either:
1.
Determine the position of the non-indicating rod(s) indirectly by the movable incore detectors at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and immediately after any motion of the non-indicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or 2.
Reduce THERMAL POWER to less than 50X of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
With a maximum of one demand position indicator per bank inoperable either:
1.
Verify that all rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of the allowed rod misalignment of each other, at least once per 8
- hours, or 2.
Reduce THERMAL POWER to less than 50X of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.1.3.2 Each rod position indicator channel shall be dete'rmined to be OPERABLE by verifying the demand position indication system and the rod position indicator channels agree within the allowed rod misalignment at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then compare the demand position indication system and the rod position indicator channels at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
COOK NUCLEAR PLP'lT - UNIT 2 3/4 1-21 AMENDMENT NO. 40, )79
~OVER DISTRIBUTION LIMITS BASES 3/4.2 2 and 3 4.2.3 HEAT FLUX HOT CHAWEL FACTOR AND
'UCLEAR ENTHALPY RISE HOT CHANNEL FACTOR The limits on heat flux hot channel factor, and nuclear enthalpy rise hot channel factor ensure that 1) the design limits on peak 'cal power density and minimum DNBR are not exceeded and 2) in the event of a LOCA the peak fuel clad temperature will not exceed the 2200 F ECCS acceptance criteria limit.
Each of these is measurable but will normally only be determined periodically as specified in Specifications 4.2.2.1, 4 '.2.2, 4.2.3, 4,2.6.1 and 4.2.6.2.
This periodic surveillance is sufficient to ensure that the limits are maintained provided:
a.
Control rods in a single group move together with no individual rod insertion differing by more than J18 steps from the group demand position (allowed rod misalignment) for power levels less than or equal to 85X of RATED THERMAL POWER. For power levels greater than 85X of RATED THERMAL POWER, the allowed rod misalignment is from ~12 to ~18 steps, which is dependent on the Allowable Power Level and the ratio of F~~ limit at 100X of RATED THERMAL POWER to maximum measuered F~ as indicated in Figure 3.1-4.
b.
Control rod groups are sequenced with overlapping groups as described in Specificat'on 3.1.3.6.
c The control rod insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are maintained.
d.
The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.
F~ will be maintained within its limits as specified in the COLR provided conditions a.
through d.
above are maintained.
The relaxation of F~~
as a
function of THERMAL POWER allows changes in the radial power shape for all permissible rod insertion limits. The form of this relaxation for DNBR limits is discussed in Section 2.1.1 of this basis.
I%en an F< measurement is taken, both experimental error and manufacturing tolerance must be allowed for.
5X is the appropriate allowance on F< for a full core map taken with the incore detector flux mapping system and 3X is the appropriate allowance for manufacturing tolerance.
COOK NUCLEAR PLANT - UNIT 2 B 3/4 2-4 AMENDMENT NO. 8R, 4QQ, 434.,
179