ML20235K281
| ML20235K281 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/07/1987 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235K285 | List: |
| References | |
| NUDOCS 8707160246 | |
| Download: ML20235K281 (27) | |
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UNITED STATES y,
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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NOS. 50-317
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plVERTCLIFFSNUCLEARPOWERPLANT, UNIT 1 AVENDMENT TO FACILITY CPERATING LICENSE Amendment No. 127 License No. DPP-53 1.
The Nuclear Pegulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated October 1,1986, as supplemented March 13, March 19, April 17 and May 4,1987, 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 Comnission'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.
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-53 is hereby amended to read as follows:
8707160246 070707 PDR ADOCK 0500 17 P
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.127, are hereby incorporated in the license.
The licensee shall j
operate the facility in accordance with the Technical l
Specifications.
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3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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' bert A. Capra, Act Director j
roject Directorate I-1 j
Division of Reactor Projects, I/II
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Attachment:
l Changes to the Technical Specifications i
Date of Issuance: July 7, 1987 l
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WASHINGTON, D. C. 20555 8
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,e BALTIMORE GAS AND ELECTPIC COMPANY DOCKET NOS. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 2
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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 109 License No. DPR-69 1.
The Nuclear Regulatory Comission (the Commission) has found that:
i A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated October 1, 1986, as supplemented March 13, March 19, April 17 and May 4, 1987, 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 Comission's regulatioiis 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-69 is hereby amended to read as follows:
1
-2 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 109, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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1 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGU'.ATORY COMMISSION
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ober A. Capra, ing Director roject Directorate I-1 4
Division of Reactor Projects, I/II
Attachment:
Changes to the Technical i
Specifications Date of Issuance: July 7, 1987 1.
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NUCLEAR REGULATORY COMMISSION E,k WASHINGTON, D. C. 20555
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ss ATTACH. VENT TO LICENSE AMENDMENTS AMENDMENT NO. 127 FACILITY OPERATING LICENSE NO. DPR-53 AMENPPENT NO. 109 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET N05. 50-317 AND 50-318 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 1-17 3/4 1-17 3/4 1-18 3/4 1-18 3/4 1-19 3/4 1-19 3/4 1-19A 3/4 1-198 3/4 1-20*
3/4 1-20*
3/4 3-19 3/4 3-19*
3/4 3-20 3/4 3-20 03/4 1-3 83/4 1-3**
B3/4 1-4 B3/4 1-4 B3/4 1-5 B3/4 1-5
- Overleaf pages provided to maintain document completeness
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RE ACTIVITY CONTROL SYSTEMS 3 /4.1. 3 MOVABLE CONTROL ASSEMBLIES LIMITING CONDITION FOR OPER ATION 3.1.3.1 The CEA Motion Inhibit and all shutdown and regulating CEAs shall be OPERABLE with each CEA of a given group positioned within 7.5 inches (indicated position; of all other CEAs in its group.
APPLICABILITY: MODES l' and 2*
ACTION:
With one or more CEAs inoperable due to being immovable as a result a.
of excessive friction or mechanical interference or known to be untrippable, be in at least IIOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the CEA Motion Inhibit inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either:
1.
Restore the CEA Motion Inhibit to OPERABLE status, or 2.
Place and maintain the CEA drive system mode switch in either the "Off" or any " Manual Mode" position and fully withdraw all CEAs in groups 3 and 4 and withdraw the CEAs in group 5 to less than 5% insertion, or 3.
Be in at least IIOT STANDBY.
c.
With one CEA inoperable due to causes other than addressed by ACTION a, above, and inserted beyond the Long Term Steady State Insertion Limits but within its above specified alignment requirements, operation in MODES 1 and 2 may continue for up to 7 days per occurrence with a total accumulated time of s 14 days per calendar year.
d, With one CEA inoperable due to causes other than addressed by ACTION a,
- above, but within its above specified alignment requirements and either fully withdrawn or within the Long Term Steady State Insertion Limits if in CEA group 5, operation in MODES I and 2 may continue.
See Special Test Exceptions 3.10.2 and 3.10.4.
CALVERT CLIFFS - UNIT 2 3/4 1 17 Amendment No.109
REACTIVITY CONTROL SYSTEh1S LIhllTING CONDITION FOR OPER ATION e.
With one or more CEAs misaligned from any other CEAs in its group by more than 7.5 inches but less than 15 inches, operation in h10 DES I and 2 may continue, provided that within one hour the misaligned CEA(s) is either:
1.
Restored to OPERABLE status within its above specified alignment requirements, or 2.
Declared inoperable.
After declaring the CEA inoperable, operation in 510 DES I and 3 may continue for up to 7 days per occurrence with a total accumulated time of s 14 days per calendar year provided all of the following conditions are met:
a.
The THERh1AL POWER level shall be reducing to s 70% of the maximum allowable TIIER$1AL POWER level for the existing Reactor Coolant Pump combination within one hour; if negative reactivity insertion is required to reducing THERh1AL POWER, i
boration shall be used.
~
b.
Within one hour after reducing the THERh1AL POWER as required by a) above, the remainder of the CEAs in the group with the inoperable CEA shall be aligned to within 7.5 inches of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits shown on Figure 3.1 -2; the THERh1AL POWER level shall be restricted pursuant to l
Specification 3.1.3.6 during subsequent operation.
f.
With one CEA miu.ligned from any other CEA in its group by 15 inches or more, operation in h10 DES 1 and 2 may continue, provided that the misaligned CEA is positioned within 7.5 inches of the other CEAs in its group in accordance with the time allowance shown in Figure 3.1-3.
The pre-misaligned F[ value used to determine the allowable time to realign the CEA from Figure 3.1-3 shall be the latest measurement taken within 5
days prior to the CEA misalignment.
If no measurements were taken within 5 days prior to the misalignment, a pre-misaligned F[ of 1.65 shall be assumed.
g.
With one CEA misaligned from any other CEA in its group by 15 inches or more at the conclusion of the time allowance permitted in Figure 3.1-3, immediately start to implement the following actions:
1.
If the THERh1AL POWER level prior to the misalignment was greater than 50% of RATED THERh1AL POWER, THERh1AL POWER shall be reduced to less than the greater of:
CALVERT CLIFFS - UNIT 2 3/4 1-18 Amendment No.109
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1 ENGINEERED S AFETY FE ATURES RESPONSE TIMES INITI ATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 1.
Manual a.
Not Appli:able b.
CSAS Containment Spray Not Applicable c.
CIS Containment Isolation Not Applicable d.
RAS Containment Sump Recirculation Not Applicable l
e.
AFAS Auxiliary Feedwater Initiation Not Applicable 2.
Pressurizer Pressure-Low a.
Safety Injection (ECCS) s 30*/30**
3.
Containment Pressure-Hieh a.
Safety Injection (FCCS) s 30*/30**
b.
Containment Isolation s 30 l
c.
Containment Fan Coolers s 35*/10**
4.
Containment Pressure-Hieh a.
Containment Spray s 60*/60 " (1) 5.
Containment Radiation-Hich a.
Containment Purge Valves Isolation s7 CALVERT CLIFFS - UNIT 2 3/4 3-20 Amendment No. /I, //, //,109
REACTIVITY CONTROL SYSTEMS BASES The boron capability required below 200 F is based upon providing a 3% ok/k SHUTDOWN MARGIN after xenon decay and cooldown from 200*F to 140*F. This condition requires either 737 callons of 7.25% boric acid solution frorr the boric acid tanks or 9,844' gallons of 2300 ppm borated water from the refueling water tank.
The OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.
3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) the potential effects of a CEA ejection accident are limited to acceptable levels.
The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original criteria are met.
i The ACTION statements applicable to a stuck or untrippable CEA and
,1 to a large misalignment (1 15 inches) of two or more CEAs, require a l
prompt shutdown of the reactor since either of these conditions may be indicative of a possible loss of mechanical functional capability of the CEAs and in the event of a stuck or untrippable CEA, the loss of SHUT-DOWN MARGIN.
n U
For small misalignments (1 15 inches) of the CEAs, there is 1) a small degradation in the peaking factors relative to those assumed in generating LCOs and LSSS setpoints for DNBR and linear heat rate, 2) a small effect on the-time dependent long term power distributions rela-tive to those used in generating LCOs and LSSS setpoints for DNBR and linear heat rate, 3) a small effect on the available SHUTDOWN MARGIN, and 4) a small effect on the ejected CEA worth used in the safety analysis.
Therefore, the ACTION statement associated with the small misalignment of a CEA permits a one hour time interval during which attempts may be made to restore the CEA to within its alignment require-ments prior to initiating a reduction in THERMAL POWER.
The one hour time limit is sufficient to (1) identify causes of a misaligned CEA, (2) take appropriate corrective action to realign the CEAs and (3) minimize the effects of xenon redistribution.
CALVERT CLIFFS - UNIT 2 B 3/4 1-3 Amendment No. f;, Jy,109
l l
RE ACTIVITY CONTROL SYSTEMS HASES Overpower margin is provided to protect the core in the event of a targe misalignment ( > 15 inches) of a CEA. However, this misalignment would clause distortion of the core power distribution. The reactor protective system would not detect the degradation in radial peaking factors and since variations in other system parameters (e.g., pressure and coolant temperature) may not be sufficient to cause trips, it is possible that the reactor could be operating with l
process variables less conservative than those assumed ir generating LCO and LSSS setpoints.
The ACTION statement associated with a
large CEA misalignment requires prompt a: tion to realign the CEA to avoid excessive margin degradation.
If the CEA is not realigned within the given time constraints, action is specified which will preserve margin, including reductions in THERMAL POWER.
For a single CEA misalignment, the time allowance to realign the CEA (Figure 3.1-3) is permitted for the following reasons:
1.
The margin calculations which support the power distribution LCOs for DNBR are based on a steady-state Fl as specified in Technical i
Specification 3.2.3.
2.
When the actual F[is less than the Technical Specification value, additional margin exists.
3.
This additional margin can be credited to offset the increase in F[
with time that will occur following a CEA misalignment due to xenon 4
redistribution.
The requirement to reduce power lesel after the time limit of Figure 3.1-3 is reached offsets the continuing increase in F[ that can occur due to xenen redistribution. A power reduction is not required below 50% power. Below 50%
power there is sufficient conservatism in the DNB power distribution LCOs to completely offset any, or any additional, xenon redistribution effects.
The ACTION statements applicable to misaligned or inoperable CEAs include requirements to align the OPERABLE CEAs in a given group with the inoperable CEA. Conformance with these alignment requirements bring the core, within a short period of time, to a configuration consistent with that assumed in generating LCO and LSSS setpoints.
However, extended operation with CEAs significantly inserted in the core may lead to perturbations in 1) local burnup,
)
- 2) peaking factors, and 3) available shutdown margin which are more adverse than the conditions assumed to exist in the safety analyses and LCO and LSS3 setpoints determination. Therefore, time limits have been imposed on operation with inoperable CEAs to preclude such adverse conditions from developing.
CALVERT CLIFFS - UNIT 2 B 3/4 1-4 Amendment No. pf, 7/1/, 109
RE ACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVAULE CONTROL ASSEMBLIES 1,lMITING CONDITION FOR OPER ATION 3.1.3.1 The CEA Motion Inhibit and all shutdown and regulating CEAs shall be OPERABLE with each CEA of a given group positioned within 7.5 inches l
(indicated position) of all other CEAs in its group.
APPLICA BILITY: MODES l' and 2*
ACTION:
With one or more CEAs inoperable due to being immovable as a result a.
l of excessive friction or mechanical interference or known to be untrippable, be in at least IIOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the CEA Motion inhibit inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either:
1.
Restore the CEA Motion Inhibit to OPERABLE status, or 2.
Place and maintain the CEA drive system mode switch in either the "Off" or any " Manual Mode" position and fully withdraw all CEAs in groups 3 and 4 and withdraw the CEAs in group 5 to less than 5% insertion, or f
3.
De in at least IIOT STANDBY.
c.
With one CEA inoperable due to causes other than addressed by l
ACTION a, above, and inserted beyond the Long Term Steady State It:sertion Limits but within its above specified alignment requirements, operation in MODES I and 2 may continue for up to 7 days per occurrence with a total accumulated time of s 14 days per calendar year.
d.
With one CEA inoperable due to causes other than addressed by l
ACTION a,
- above, but within its above specified alignment requirements and either fully withdrawn or within the Long Term Steady State Insertion Limits if in CEA group 5, operation in MODES I and 2 may continue.
See Special Test Exceptions 3.10.2 and 3.10.4.
CALVERT CLIFFS - UNIT 1 3/4 1-17 Amendment No.127
RE ACTIVITY CONTROL SYSTEh1S LIN11 TING CONDITION FOR OPER ATION e.
With one or more CFAs misaligned from any other CEAs in its ' group l
by more than 7.5 inches but less than 15 inches, operation in h10 DES 1 and 2 may continue, provided that within one hour the misaligned j
CEA(s) is either:
1.
Restored to OPERABLE status within its above specified alignment requirements, or 2.
Declared inoperable.
After declaring the CEA inoperable, operation in h! ODES I and 2 may continue for up to 7 days per occurrence with a total accumulated time of s 14 days per calendar year provided all of the following conditions are met:
a.
The THERh1AL POWER level shall be reduced to s 70% of the maximum allowable TIIERh1AL POWER level for the existing Reactor Coolant Pump combination within one hour; if negative reactivity insertion is required to reduce TIIERh1AL POWER, boration shall be used, b.
Within one hour after reducing the THERh1AL POWER as required by a) above, the remainder of the CEAs in the group with the inoperable CEA shall be aligned to within 7.5 inches of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits shown on Figure 3.1 -2; the THERh1AL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.
f.
With one CEA misaligned from any other CEA in its group by 15 inches or more, operation in h10 DES I and 2 may continue, provided that the misaligned CEA is positioned within 7.5 inches of the other CEAs in its group in accordance with the time allowance shown in Figure 3.1-3.
The pre-misaligned F[ value used to determine the allowable time to realign the CEA from Figure 3.1-3 shall be the latest measurement taken within 5
days prior to the CEA misalignment.
If no measurements were taken within 5 days prior to the misalignment, a pre-misaligned F[ of 1.65 shall be assumed.
g.
With one CEA misaligned from any other CEA in its group by 15 inches or more at the conclusion of the time allowance permitted in Figure 3.1-3, immediately start to implement the following actions:
1.
If the TIIERh1AL POWER level p.-ior to the misalignment was greater than 50% of RATED THERh1AL POWER, THERh1AL POWER shall be reduced to less than the greater of:
I CALVERT CLIFFS - UNIT 1 3/4 1-18 Amendment No.127
RE ACTIVITY CONTROL SYSTEh1S Llh11 TING CONDITION FOR OPER ATION I
j l
a) 50% of RATED TIIERh1AL POWER b) 75% of the TIIERS1AL POWER level prior to the misalignment within one hour after exceeding the time allowance permitted by Figure 3.1-3.
2.
If the TilERh1AL POWER level prior to the misalignment was s 50%
of RATED TilERh1AL POWER, maintain TIIERh1AL POWER no higher than the value prior to the misalignment.
If negative reactivity insertion is required to reduce TIIERh1AL POWER, boration shall be used. Within one hour after establishing the appropriate THERh1AL POWER as required above, either:
1.
Restore the CEA to within the above specified alignment requirements, or i
2.
Declare the CEA inoperable. After declaring the CEA inoperable, l
POWER OPERATION may continue for up to 7 days per occurrence I
with a total accumulated time of s 14 days per calendar year i
provided the remainder of the CEAs in the group with the inoperable CEA are aligned to within 7.5 inches of the inoperable
=
CEA while maintaining the allowable CEA sequence and insertion limits shown on Figure 3.1-2; the THERA 1AL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.
l h.
With more than one CEA inoperable or misaligned from any other CEA l
l in its group by 15 inches (indicated position) or more, be in at least IlOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
i.
For the purposes of performing the CEA operability test of TS 4.1.3.1.2, if the CEA has an inoperable position indication channel, the alternate indication system (pulse counter or voltage dividing network) will be used to monitor position.
If a direct position indication (full out reed switch or voltage dividing network) cannot be restored within ten minutes from the commencement of CEA motion, or CEA withdrawal exceeds the surveillance testing insertion by > 7.5 inches, the position of the CEA shall be assumed ~ to have been > 15 l
inches from its group at the commencement of CEA motion.
CALVERT CLIFFS - UNIT 1 3/4 1-19 Amendment No. 2jEy, y, 127
l REACTIVITY CONTROL SYSTEMS SURVEILL ANCE REQUIREMENTS 4.1.3.1.1 The position of each CEA shall be determined to be within 7.5 inqhes l
(indicated position) of all other CEAs in its group at least once per 12 haurs except during time intervals when the Deviation Circuit and/or CEA Motion l
Inhibit are inoperable, then verify the individual CEA positions at least once i
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 CEA not fully inserted shall be determined to be OPERABLE by l
inserting it at least 7.5 inches at least once per 31 days.
1 4.1.3.1.3 The CEA Motion Inhibit shall be demonstrated OPERABLE at least once per 31 days by a functional test which verifies that the circuit maintains the CEA group overlap and sequencing requirements of Specification 3.1.3.6 and that the circuit also prevents any CEA from being misaligned from all other CEAs in its group by more than 7.5 inches (indicated position).
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CALVERT CLIFFS - UNIT 1 3/4 1-19A Amendment No. 127
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CALVERT CLIFFS - UNIT 2 3/4 1-19B Amendment No.109
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l CALVERT CLIFFS-UNIT 2 3/4 1-20 Amendment No. 6. 13, AM, 109 l
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l REACTIVITY CONTROL SYSTEMS BASES The boron capability required below 200*F is based upon providing a 3% tk/k SHUTDOWN MARGIN after xenon decay and cooldown from 200*F to This condition requires either 737 gallons of 7.25% boric acid 140*F.
solution from the boric acid tanks or 9,844 gallons of 2300 ppm borated water from the refueling water tank.
The OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.
3/ 4.1. 3 MOVABLE CONTROL ASSEMBLIES j
The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) the potential effects of a CEA ejection accident are limited to acceptable levels.
The ACTION statements which pennit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original criteria are met.
The ACTION statements applicable to a stuck or untrippable CEA and i
?
to a large misalignment (> 15 inches) of two or more CEAs, require a prompt shutdown of the reactor since either of these conditions may be indicative of a possible loss of mechanical functional capability of the CEAs and in the event of a stuck or untrippable CEA, the loss of SHUT-i DOWN MARGIN.
For small misalignments (< 15 inches) of the CEAs, there is 1) a small degradation in the peakiiig factors relative to those assumed in generating LCOs and LSSS setpoints for DNBR and linear heat rate, 2) a small effect on the time dependent long term power distributions rela-tive to those used in generating LCOs and LSSS setpoints for DNBR and linear heat rate, 3) a small effect on the available SHUTDOWN MARGIN, and 4) a small effect on the ejected CEA worth used in the safety Therefore, the ACTION statement associated with the small analysis.
misalignment of a CEA permits a one hour time interval during which attempts may be made to restore the CEA to within its alignment require-The one hour ments prior to initiating a reduction in THERMAL POWER.
I time limit is sufficient to (1) identify causes of a misaligned CEA, (2) take appropriate corrective action to realign the CEAs and (3) minimize the effects of xenon redistribution.
Amendment No. LA, 48' g,
CALVERT CLIFFS - UNIT 1 B 3/4 1-3 127
REACTIVITY CONTROL, SYSTEMS BASES Overpower margin is provided to protect the core in the event of a Iptge misalignment ( t 15 inches) of a CEA. However, this misalignment would cause distortion of the core power distribution. The reactor protective system would not detect the degradation in radial peaking factors and since variations in other system parameters (e.g., pressure and coolant temperature) may not be i
l sufficient to cause trips, it is possible that the reactor could be operating with l
process variables less conservative than those assumed in generating LCO and LSSS setpoints.
The ACTION statement associated with a
large CEA misalignment requires prompt action to realign the CEA to avoid excessive margin degradation, if the CEA is not realigned within the given time constraints, action is specified which will preserve margin, including reductions in THERMAL POWER.
For a single CEA misalignment, the time allowance to realign the CEA (Figure 3.1-3) is permitted for the following reasons:
1.
The margin calculations which support the ower distribution LCOs for DF'B R are based on a steady-state F as specified in Technical j
Specification 3.2.3.
2.
When the actual F[ is less than the Technical Specification value, i
additional margin exists.
1 3.
This additional margin can be credited to offset the increase in F[
with time that will occur following a CEA misalignment due to xenon redistribution.
The requirement to reduce power level after the time limit of Figure 3.1-3 is reached offsets the continuing increase in F[ that can occur due to xenon redistribution. A power reduction is not required below 50% power. Below 50%
power there is sufficient conservatism in the DNB power distribution LCOs to completely offset any, or any additional, xenon redistribution effects.
The ACTION statements applicable to misaligned or inoperable CEAs include requirements to align the OPERABLE CEAs in a given group with the inoperable CEA. Conformance with these alignment requirements bring the core, within a short period of time, to a configuration consistent with that assumed in generating LCO and LSSS setpoints.
However, extended operation with CEAs significantly inserted in the core may lead to perturbations in 1) local burnup,
- 2) peaking factors, and 3) available shutdown margin which are more adverse than the conditions assumed to exist in the safety analyses and LCO and LSSS setpoints determination. Therefore, time limits have been imposed on operation with inoperable CEAs to preclude such adverse conditions from developing.
CALVERT CLIFFS - UNIT 1 B 3/4 1 4 Amendment No. lff, W,127
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CALVERT CLIFFS-UNIT 1 3/4 1-20 AmendmentNo.27,28,//,FN, 127
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- -- ~ _ _, _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
REACTIVITY CONTROL SYSTEh1S I.IN11 TING CONDITION FOR _OPER ATION a) 50% of RATED TilERh1AL POWER b) 75% of the TIIERh1AL POWER level prior to the misalignment i
within one hour after exceeding the time allowance permitted by i
Figure 3.1-3.
2.
If the TIIERh1AL POWER level prict to the misalignment was s 50%
of RATED TIIERh1AL POWER, maintain TIIERh1AL POWER no higher than the value prior to misalignment.
If negative reactivity insertion is required to reduce TIIERh1AL POWER, boration shall be used. Within one hour after establishing the appropriate THERh1AL POWER as required above, either:
1.
Restore the CEA to within the above specified alignment requirements, or 2.
Declare the CEA inoperable. After declaring the CEA inoperable, I
POWER OPERATION may continue for up to 7 days per occurrence with a total accumulated time of s 14 days per calendar year provided the remainder of the CEAs in the group with the inoperable CEA are aligned to within 7.5 inches of the inoperable i
CEA while maintaining the allowable CEA sequence and insertion I
limits shown on Figure 3.1-2; the TIIERh1AL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent l
operation.
h.
With more than one CEA inoperable or misaligned from any other CEA I
in its group by 15 inches (indicated position) or more, be in at least ilOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
i.
For the purposes of performing the CEA operability test of TS I
4.1.3.1.2, if the CE A has an inoperable position indication channel, the alternate indication system (pulse counter or voltage dividing network) will be used to monitor position, if a direct position indication (full out reed switch or voltage dividing network) cannot be restored within ten minutes from the commencement of CEA motion, or CEA withdrawal exceeds the surveillance testing insertion by > 7.5 inches, the position of the CEA shall be assumed to have been > 15 inches from its group at the commencement of CEA motion.
CALVERT CLIFFS - UNIT 2 3/4 1-19 Amendment No. yy, ff, 109 l
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REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 1
i l
l 4.1.3.1.1 The position of each CEA shall be determined to be within 7.5 inches l
l (indicated position) of all other CEAs in its group at least once per 12 ho'urs except during time intervals when the Deviation Circuit and/or CEA Motion l
Inhibit are inoperable, then verify the individual CEA positions at least once l.
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 CEA not fully inserted shall be determined to be OPERABLE by l
inserting it at least 7.5 inches at least once per 31 days.
]
1 4.1.3.1.3 The CEA Motion inhibit shall be demonstrated OPERABLE at least
{
once per 31 days by a functional test which verifies that the circuit maintains
]
the CEA group overlap and sequencing requirements of Specification 3.1.3.6 j
and that the circuit also prevents any CEA from being misaligned from all other CEAs in its group by more than 7.5 inches (indicated position).
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l CALVERT CLIFFS - UNIT 2 3/4 1-19A Amendment No.109 i
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l ENGINEERED S AFETY FE ATURES RESPONSE TINfES l
RESPONSE TIMF TN SECONDS INITI ATING SIGNAL AND FUNCTION 1.
Manual i
a.
SIAS Not Applicable Safety Injection (ECCS) b.
CSAS Not Applicable Containment Spray c.
CIS Not Applicable Containment Isolatioti f
d.
L1 Not Applicable l
Containment Sump Recirculation e.
AFAS Not Applicable l
Auxiliary Feedwater Initiation 2.
Pressurizer Pressure-Low s 30*/30 "
a.
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Containment Pressure-Hich s 30*/30**
Safety Injection (ECCS) a.
s 30 b.
Catainment Isolation l
l s 35*/10 "
c.
Containment Fan Coolers l
4 Containment Pressure-Hinh 60*/60"(1) 5 a.
Containment Radiation-Hieh I
Containment Purge Valves Isolation s7 I
a.
CALVERT CLIFFS - UNIT 1 3/4 3-20 Amendment No. //, f/, //,127
REACTIVITY CONTROL SYSTEMS BASES Operability of the CEA position indicators is required to determine CEA positions and thereby ensure compliance with the CEA alignment and insertion limits and ensures proper operation of the rod block circuit.
The CEA " Full In" and " Full Out" limits provide an additional independent means-for determining the CEA positions when the CEAs are at either their fully inserted or fully withdrawn positions.
Therefore, the OPERABILITY and the ACTION statements applicable to inoperable CEA position indicators permit continued operations when positions of CEAs with inoperable indicators can be verified by the " Full In" or " Full Out" limits.
CEA positions and OPERABILITY of the CEA position indicators are
)
required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable.
)
These verification frequencies are adequate for assuring that the applicable LCOs are satisfied.
The surveillance requirements affecting CEAs with inoperable position indication channels allow 10 minutes for testing each affected CEA. This time limit was selected so that 1) the time would be long enough for the reqtared testing, and 2) if all position indication were lost during testing, the time would be short enough to allow a power reduction to 70% of maximum allowable thermal power within one hour from when the testing was initiated. The time linGt ensures CEA misalignments occurring during CEA testing are corrected within the time requirements required by existing specifications.
The maximum CEA drop time restriction is consistent with the assumed CEA drop time used in the safety analyses. Measurement with T
> 515 F and with all reactor coolant pumps operating ensures that the Esiired drop times will be representative of insertion times experienced during a reactor trip at operating conditions.
The LSSS setpoints and the power distribution LCOs were generateo based upon a core burnup which would be achieved with the core operating in an essentially unrodded configuration. Therefore, the CEA insertion limit specifications require that during MODES 1 and 2, the full length CEAs be nearly fully withdrawn.
The amount of CEA insertion permitted i
by the Steady State Insertion Limits of Specification 3.1.3.6 will not have a significant effect upon the unrodded burnup assumption but will still provide sufficient reactivity control. The Transient Insertion Limits of Specification 3.1.3.6 are provided to ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) the potential effects of a CEA ejection accident are limited to acceptable levels; however, long term operation 4
at these insertion limits could have adverse effects on core power distribution during subsequent operation in an unrodded configuration.
i I
CALVERT CLIFFS - UNIT 1 B 3/4 1-5 Amendment No. 32,127 1
I l
I 1
REACTIVITY CONTROL SYSTEMS IiASES Operability of the CEA position indicators is required to determine CEA positicas and thereby ensure compliance with the CEA alignment and insertion limits and ensures proper operation of the rod block circuit.
3 The CEA. " Full In" and
- Full Out" limits provide an additional independent means for determining the CEA positions when the CEAs are at either their fully in'serted or fully withdrawn positions.
Therefore, the OPERABILITY and the ACTION I
statements applicable to inoperable CEA position indicators permit continued operations when positions of CEAs with inoperable indicators can be verified by the
- Full In" or " Full Out" limits.
CEA positions and OPERABILITY of the CEA position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable.
These verification frequencies are adequate for assuring that the applicable LCOs are satisfied.
[
The surveillance requirements affecting CEAs with inoperable position indication channels allow 10 minutes for testing each affected CEA. This time limit was selected so that 1) the time would be long enough for the required testing, and 2) if all position indication were lost during testing, the time wetld be short enough to allow a power reduction to 70% of maximum allowable thermal power within one hour from when the testing was initiated.
The time limit ensures CEA misalignments occurring during CEA testing are corrected within the time requirements required by existing specifications.
The maximum CEA drop time restriction is consistent with the assumed CEA drop time used in the accident analyses. Measurements with Tavg a 5150 with all reactor coolant purnps operating ensures that the measured drop times will and be representative of insertien tinies experienced during a reactor trip at operating conditions.
The LSSS setpoints and the power distribution LCOs were generated based upon a core burnup which would be achieved with the core operating in an essentially unrodded configuration.
Therefore, the CEA insertion limit specifications require that during MODES 1 and 2, the full length CEAs be nearly fully withdrawn.
The amount of CEA insertion permitted by the Steady State Insertion Limits of. Specification 3.1.3.6 will not have a significant effect upon the unrodded burnup assumption but will still provide sufficient reactivity control.
The Transient Insertion Limits of Specification 3.1.3.6 are provided to ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) the potential effects of a CEA ejection accident are limited to acceptable levels; however, long tenn operation at these insertion limits could have adverse effects on core power distribution during subsequent operation in an unrodded configuration.
CALVERT CLIFFS - UNIT 2 B 3/4 1-5 Amendment No. l'a',109 i
b
_ _ _ _ _ _ _ _ _ _ _.