ML20023C939
| ML20023C939 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/05/1983 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20023C940 | List: |
| References | |
| NUDOCS 8305180579 | |
| Download: ML20023C939 (17) | |
Text
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UNITED STATES y'$'.q j', g NUCLEAR REGULATORY COMMISSION
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WASHINGTON. D. C. 20535 g ".'.. j
BALTIM0RE GAS AND ELECTRIC COMPANY 00CKZT NO. 50-317 CALVERT CLIFFS NbC! EAD POWER PLANT UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. OPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated March 15, 1983, 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 confonnity with the application, the proirisions 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 l
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 l
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
B305180579 830505 PDR ADOCK 05000317 P
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. 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 84, 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 its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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-y Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 5, 1983 1
e
ATTACHMENT TO LICENSE AMENDMENT N0. 84 FACILITY OPERATING LICENSE NO. DPR-53 DOCKET N0. 50-317 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain. vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Pages 3/4 1-19
__ c 3/4 1-22 B 3/4 1-4 h
e 4
4 e
I REACTIVITY CONTROL SYSTEMS LI!ilTING CONDITIOh FOR OPERATION 2.
Declare the CEA inoperable. After declaring the CEA inoper-able, POWER OPERATION may continue for up to 7 days per occurrence with a total accumulated time of < 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 CEA while maintaining the allow-
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able CEA sequence and insertion limits shown on Figure 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.
g.
With more than one full length CEA inoperable or misaligned from any other CEA in its group by 15 inches (indicated position) or more, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
h.
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 positi6n indication (full out reed switch or voltage dividing net-work) cannot be restored within ten minutes from the commencement of CEA motion, or CEA withdrawal exceeds the surveillance testing inser' tion by > 7.5 inches, the position of the CEA shall be assumed to have been > 15 inches from its group at the commence-ment of CEA motion.
SURVEILLANCE REQUIREliENTS 4.1. 3.1.1 The position of each full length CEA shall be determined to be within 7.5 inches (indicated position) of all other CEAs in its group 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 Deviation Circuit and/
or CEA liotion Inhibit are inoperable, then verify the individual CEA 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 CEA not fully inserted shall be determined to be OPERABLE by inserting it at least 7.5 inches at least once per 31 days.
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 main-tains 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).
CALVERT CLIFFS - UNIT 1 3/4 1-19 Amendment No. 28, 84 4
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CALVERT CLIFFS-UNIT 1 3/4 1-20 Amendment No. 27,28,//,84 l
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jjREACTIVITYCONTROLSYSTEMS POSITION INDICAT'OR CHANNELS LIMITING CONDITION FOR OPERATION 3.1.3.3 All shutdown and regulating CEA reed switch position indicator channels and CEA pulse counting position indicator channels shall be OPERABLE and capable of determining the absolute CEA positions within t 2.25 inches.
APPLICABILITY: MODES 1 and 2.
ACTION:
I a.
Deleted
'I b.
With a maximum of one reed switch position indicator channel per group or one pulse counting position indicator channel per group inoperable and the CEA(s) with the inoperable position indicator channel partially inserted, either:
l 1.
14ithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> l
a)
Restore the inoperable position inoicator channel to OPERABLE status, or b)
Be in at least HOT STANDBY, or l
l c)
Reduce THERMAL POWER to < 70% of the maximum allowable I
i THERMAL POWER level for the existing Reactor Coolant Pump j
combination; if negative reactivity insertion is required to reduce THERMAL POWER, boration shall be used.
Opera-tion at or below this reduced THERMAL POWER level may l
' l continue provided that within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
1)
The CEA group (s) with the inoperable position indi-l cator is fully withdrawn while maintaining the with-drawal sequence required by Specification 3.1.3.6 and when this CEA group reaches its fully withdrawn position, the " Full Out"' limit of the CEA with the l
inoperable position indicator is actuated and verifies l
this CEA to be fully withdrawn.
Subsequent to fully withdrawing this CEA group (s), the THERMAL POWER level may be returned to a level consistent with all other applicable specific.ations; or 2)
The CEA group (s) with the inoperable position indi-l cator is fully inserted, and subsequently maintained fully inserted, while maintaining the withdrawal sequence and THERMAL POWER level required by Specifica-tion 3.1.3.6 and when this CEA group reaches its fully l
'CALVERT CLIFFS - UNIT 1 3/4 1-21 Amendment No. 32, 73, 84 l
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REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS LIMITING CONDITION FOR OPERATION inserted position, the " full In" limit.of the CEA with the inoperable indicator is actuated and verifies this CEA to be fully inserted.
Subsequent operation shall be within the limits of Specification 3.1.3.6.
2.
or, if the failure existed before entry into MODE 2 or occurs prior to an "all CEAs out" configuration, the CEA group (s) with inoperable position indicator channel must be moved to the
" Full Out" position and verified to be fully withdrawn via a
" Full Out" indicator.
These actions must be completed within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of entry into MODE 2 and prior to exceeding 70% of the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combination.
The provisions of Specification 3.0.4 are not applicable.
c.
With a maximum of one reed switch position indicator channel per group or one pulse counting position indicator channel per group inoperable and the CEA(s) with the inoperable position indicator channel at either its fully inserted position or fully withdrawn position, opera-tion may continue provided:
1.
The position of this CEA is verified immediately and at least once per 12 nours thereafter by its " Full In" or " Full Out" I
l limit (as applicable),
l 2.
The affected CEA(s) is subsequently maintained fully inserted or fully withdrawn (as applicable).
This requirement is exempted during CEA motion required for surveillance testing pursuant to Technical Specification 3.1. 3.1.
3.
Subsequent operation is within the limits of Specification
' l.3.6 and 3.1.3.1.
l l
l d.
With more than one pulse counting position indicator channels inoper-able, operation in MODES 1 and 2 may continue for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided all of the reed switch position indicator channels are OPERABLE.
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SURVEILLANCE REQUIREMENTS 4.1. 3. 3 Each position indicator channel shall be determined to be OPERABLE by verifying the pulse counting position indicator channels and the reed switch position indicator channels agree within 4.5 inches 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 Deviation circuit is inoperable, then compare the pulse counting position indicator and reed switch 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 />.
CALVERT CLIFFS - UNIT 1 3/4 1-22 Amendment No. 66, 73,84 L
REACTIVITY CONTROL SYSTEMS BASES The boron capability required below 200'F is based upon providing a 3% Ak/k SHUTDOWN MARGIN after xenon decay and cooldown from 200'F to 140*F. This condition requires either 737 gallons of 7.25% boric acid 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
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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.
The ACTION statements applicable to a stuck or untrippable CEA and 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-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 h. eat 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 sxfficient 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 1 B 3/4 1-3 Amendment No. fA, 48
' REACTIVITY CONTROL SYSTEMS BASES Overpower margin is provided to protect the core in the event of a large misalignment (> 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 varia-tions in other system parameters (e.g., pressure and coolant temperature) may not be sufficient to cause trips, it is probable that the reactor could be operating with process variables less conservative than those assumed in generating LCO and LSSS setpoints. Therefore, the ACTION statement associated with the large misalignment of a CEA requires a prompt and significant reduc-tion in THERf1AL POWER prior to attempting realignment of the misaligned CEA.
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 LC0 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 LC0 and LSSS setpoints determination. Therefore, time limits have been imposed on operation with inoperable CEAs to preclude such adverse conditions from developing.
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 deter-mining the CEA positions when the CEAs are at either their fully inserted or fully withdrawn positions.
Therefore, the ACTION statements applicable to inoperable CEA position indicators permit continued operations when the positions of CEAs with inoperable position 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 nore 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 affectea CEA. This time
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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 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 limit ensures CEA misalignments occurring during CEA testing are corrected within the time requirements required by existing specifications.
CALVERT' CLIFFS - UNIT 1 B 3/4 1-4 Amendment No. 84
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UNITED STATES
!'3c.c,.g NUCLEAR REGULATORY COMMISSION 3g C
WASHINGTON, D. C. 20S55 1 ?-
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BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET N0. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 License No. DPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated March 15, 1983, 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 regulctions and all applicable requirements have been. satisfied.
L
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. 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:
2. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 67, 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 its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION lk:b. I.'tY.. "1 L f>
-Te Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the 1
Technical Specifications Date of Issuance: May 5,1983 i
t
ATTACHMENT TO LICENSE AMENDMFNT N0. 67 FACILITY OPEP.ATING LICENSE NO. OPR-69 DOCKET NO. 50-318 Replace the fallowing pages of the Appendix A Technical Specifications with the enclosed pages as indicated.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to-maintain document completeness.
Pages 3/4 1-19 3/4 1-22 B 3/4 1-4 e
e
REA~TIVITY CONTROL SYSTEMS LIfCTING CONDITION FOR OPERATION 2.
Declare the CEA inoperable. After declaring the CEA inoperable, POWER OPERATION may continue for up to,7 days per occurrence with a total accumulated time of 1 14 days per calendar year provided the remainder of the CEAs in the group with the inoper-able CEA are aligned to within 7.5 inces of the inoperable CEA while maintaining the allowable CEA sequen:e and insertion limits shown on Figure 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.
g.
With more than one full length CEA inoperable or misaligned from any other CEA in its group by 15 inches (indicated position) or more, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
h.
For the purposes of performing the CEA operability test of T.S.
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 inches from its group at the commencenent of CEA motion.
SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each full lengtn CEA shall be determined to be witnin 7.5 inches (indicated position) of all other CEAs in its group at least once per 12-hou's except during time intervals when the Deviation r
Circuit and/or CEA Motion Inhibit are inoperable, then verify the individual CEA 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 CEA not fully inserted shall be determined to be OPERABLE by inserting it at least 7.5 inches at least once per 31 days.
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 main-tains 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).
CALVERT CLIFFS - UNIT 2 3/4 1-19 Amendment No. 73, 67
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i CALVERT CLIFFS-UNIT 2 3/4 1-20 Amendment No. 6. 73, 18 7
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REACTIVITY CONTROL SYSTEMS POSITIONINDICATbRCHANNELS LIMITING CONDITION FOR OPERATION 3.1.3.3 All shutdown and regulating CEA reed switch position indicator channels and CEA pulse counting position indicator channels shall be OPERABLE and capable of determining the absolute CEA positions within + 2.25 inches.
APPLICABILITY: MODES 1 and 2.
ACTION:
a.
Del eted b.
With a maximum of one reed switch position indicator channel per group or one pulse counting position indicator channel per group inoperable and the CEA(s) with the inoperable position indicator-channel partially inserted, either:
l 1.
Within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> l
a)
Restore the inoperable position indicator channel to l
OPERABLE status, or I
b)
Be in at least HOT STANDBY, or c)
Reduce THERMAL POWER to < 70% o# the maximum allowable I
THERMAL POWER level for the existing Reactor Coolant Pump combination; if negative reactivity insertion is required to reduce THERMAL POWER, boration shall be used. Opera-tion at or below this reduced THERMAL POWER level may continue provided that within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
1)
The CEA group (s) with the inoperable position indi-l cator is fully withdrawn while maintaining the with-drawal sequence required by Specification 3.1.3.6 and when this CEA group reaches its fully withdrawn position, the " Full Out" limit of the CEA with the inoperable position indicator is actuated and verifies this CEA to be fully withdrawn.
Subsequent to fully withdrawing this CEA group (s), the THERMAL POWER level may be returned to a level consistent with all other applicable specifications; or 2)
The CEA group (s) with the inoperable position indi-I cator is fully inserted, and subsequently maintained fully inserted, while maintaining the withdrawal sequence and THERMAL POWER level required by Specifica-tion 3.1.3.6 and when this CEA group reaches its fully CALVERT CLIFFS - UNIT 2 3/4 1-21 Amendment No. JB, 54 o
s
REACTIVITY CONTROL SYSTEMS POSITION INDI'ATO'R CHANNELS C
LIMITING CONDITION FOR OPERATION inserted position, the " Full In" limit of the CEA with the inoperable indicator is actuated and verifies this CEA to be fully inserted. Subsequent operation shall be within the limits of Specification 3.1.3.6.
2.
or, if the failure existed before entry into MODE 2 or occurs prior to an "all CEAs out" configuration, the CEA group (s) with inoperable position indicator channel must be moved to the
" Full Out" position and verified to be fully withdrawn via a
" Full Out" indicator.
These actions must be completed within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of entry into MODE 2 and prior to exceeding 70% of the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combination. The provisions of Specification 3.0.4 are not applicable.
c.
With a maximum of one reed switch position indicator channel per group or one' pulse counting position indicator channel per group inoperable and the CEA(s) with the inoperable position indicator channel at either its fully inserted position or fully withdrawn position, opera-tion 'may continue provided:
1.
The position of this CEA is verified immediately and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter by its " Full In" or " Full Out" limit (as applicable),
2.
The affected CEA(s) is subsequently maintained fully: inserted or fully withdrawn (as applicable).
This requirement is exempted during CEA motion required for surveillance testing pursuant to Technical Specification 3.1.3.1.
3.
Subsequent operation is within the limits of Specifications 3.1.3.1 and 3.1.3.~6.
d.
With more than one pulse counting position indicator channels inoper-able, operation in MODES 1 and 2 may continue for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided all of the reed switch position indicator channels are OPERABLE.
SURVEILLANCE REQUIREMENTS 4.1. 3. 3 Each position indicator channel shall be determined to be OPERABLE by verifying the pulse counting position indicator channels and the reed swit'ch position indicator channels agree within 4.5 inches 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 Deviation circuit is inoperable, then compare the pulse counting position indicator and reed switch 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 />.
CALVERT CLIFFS - UNIT 2 3/4 1-22 Amendthent No. fB, S4, 67 s
,Q.
REC TIVITY CONTROL SYSTEv.S SASES The boron capability required below 200 F is based upon providing a 3% ok/k SHUTDOWN MAR 3IN af ter xenon decay and cooldown from 200*F' to 140*F.
This condition requires either 737 gallons of 7.25% boric acid solution from the boric acid tanks or 9,844 gallons of 2300 ppm borated water from the refueling water tank.
The OPERABILITY of one beren injection. system during REFUELING ensures that this system is available for reactivity control while in MODE 6.
3/a.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 ejcction accident are limited to acceptable levels.
The ACTION statements which permit limited variations from the basic recuirements are accompanied by additional restrictions which ensure that
. tne original criteria are met.
~
The ACTION statements applicable to a stuck or untrippable CEA and te 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-DOWN MARGIN.
For small misalignments (< 15 incnes) of the CEAs, there is 1) a l small cegradation 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 o.ne 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.
Overpower margin is provided to protect the core in the event of a large misalignment (> 15 inches) of a CEA.
However, this misalignment would cause distortion of the core power distribution.
The reactor CALVERT CLIFFS - UNIT 2' B 3/4 1-3 Amendment No. 6, 31
REACTIVITY CONTROL SYSTEMS BASES protective system would not detect the degradation in radial peeking factors and since variations in other system parameters (e.g., pressure and coolant tempera-ture) may not be sufficient to cause trips, it is probable that the reactor could be operating with process variables less conservative than those assumed in generating LC0 and LSSS setpoints. Therefore, the ACTION statement associ-ated with the large misalignment of a CEA requires a prompt and significant reduction in THERMAL POWER prior to attempting realignment of the misaligned CEA.
The ACTION statements appli' able to misaligned ar inoperable CEAs include c
requirements to align the OPERABLE CEAs in a given group with the inoperable CEA.
Conformance with these alignment requirements brings 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 condi-tions assumed to exist in the safety analyses and LC0 and LSSS setpoints deter-mination. Therefore, time limits have been imposed on operation with inoperable CEAs to preclude such adverse conditions from developing.
Operability 'f the CEA position indicators is required to determine CEA o
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 deter-mining the CEA positions when the CEAs are at either their fully inserted or fully withdrawn positions.
Therefore, the ACTION statements applicable to inoperable CEA position indicators permit continued operations when the posi-tions of CEAs with inoperable position 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 manitoring 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 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 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 T avg -
51 5 and with all reactor coolant pumps operating ensures that the CALVERT CLIFFS - UNIT 2 B 3/4 1-4 Amendment No. 67
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