ML20076A740
| ML20076A740 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/27/1991 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076A743 | List: |
| References | |
| NUDOCS 9107080271 | |
| Download: ML20076A740 (31) | |
Text
Y
%g
.s o,
! T,
,1
't UNITED STATES i
NUCLEAR REGULATORY COMMISSION i ;A WASWNGToN, O C. 20%5
~
t
%....'. /
RALTIMORE GAS AND ELECTRIC COMPANY 00CKET NO. 50-317 CALVERT. CLIFFS NUCLEAR POWER PLANT UNIT NO 1 AMENDMENT TO FACILITY OPERATING-LICENSE Amendment No.155 License No. DPR-53 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated November 7,1990, as supplemented on May 20, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 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:
9107000271 910627 ADOCKOS00g7 DR
l i
2 (2)
Technical.Speci fica t ions The Technical Specifications contained in Appendices A and 8. as revised through Amendment No. 155. are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license anendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION S h (d CW Robert A. Capra, Director Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 27,1991 l
l
p""%
,j UNITED STATES
{hg.J'%,]//,1 NUCLEAR REGULATORY COMMISSION s,
.[f tu g
WASHINGTON, D C. 20%5
....+
j BALTIMORE GAS AND ELECTRIC COYpANY DOCKET NO. 50-31ft I
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. -?
AMENDMENT TO. FACILITY OPERATING.LICENSC Amendment No. 135 License No. DPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated November 7, 1990, as supplemented on May 20, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; 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 Comission'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 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 P.C.2 of Facility Operating License No.
OPR-69 is hereby amended to read as follows:
l l
4 2
(2) _ Technical Specifications The Technical Specifications contained in Appendices A and B as revised through Amendment No.135, 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 and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION SU &
- W Robert A. Capra, Director Project Directorate 1-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 27,1991 i
- -. - =.
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.,1,qq,fACILIT,Y,0PERATjNG_ LICENSE NO. DPR-53 AMENDMENTNO,._tg,f,ACILITYOPERATitlGLICENSE110.DPR-69 E9C,K,E,T, p,0,S,,50-317 AND Sb-318 eevise Appendix A as follows:
Remove Pag,e,s Insert Pag,es 3/4 8-5 3/4 8-5 3/4 8-6*
3/4 8-6*
3/4 8-7 3/4 8-7 3/4 8-8 3/4 8-8 3/4 8-9 3/4 8-9 3/4 8-10 3/4 8-10 3/4 8-11 3/4 8-11 3/4 9-3*
3/4 9-3*
3/4 9-4 3/4 9-4 3/4 9-4a B 3/4 6-1 0 3/4 6-1 B 3/4 9-1 B 3/4 9-1 B 3/4 9-2*
B 3/4 9-2*
- Pages which did not change, but are overleaf.
P
ELECTRICAL POWER SYSTEMS SHUTDOWN LIMITING CONDITION FOR 0PERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE
- I a.
One circuit between the offsite transmission network and the onsite Class IE distribution system, and b.
One diesel generator with:
1.
A day fuel tank containing a minimum vclume of 375 gallons of fuel, 2.
A fuel storage system containing a aiinimum volume of 18,250 gallons of fuel, and 3.
A fuel transfer pump.
APPLICABILITY: MODES 5 and 6.
ACTION:
With less than the above minimum required A.C. electrical power sources OPERABLE:
a.
Immediately* suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel and movement of heavy loads over irradiated fuel, and b.
Immediately initiate corrective actions to restore the minimum A.C. electrical power sources to OPERABLE status, and c.
Establish containment penetration closure as identified in Specification 3.9.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
SURVEILLANCE RE0VIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for requirement 4.8.1.1.2a.5.
Performance of Action a. shall not preclude completion of actions to establish a safe conservative position.
CALVERT CLIFFS - UNIT 1 3/4 8-5 Amendment No. 155
[LECTRICAL POWER SYSTEMS SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources si m be OPERABLE:
a.
One circuit between the offsite transmission network and the onsite Class lE distribution system, and b.
One diesel generator with:
1.
A day fuel tank containing a minimum volume of 375 gallons of fuel, 2.
A fuel storage system containing a minimum volume of 18,250 gallons of fuel, and 3.
A fuel transfer pump.
APPLICABILITJ: MODES 5 and 6.
ACTION:
With less than the above minimum required A.C. electrical power sources OPERABLE:
Immediately* suspend all operations involving CORE ALTERATIONS, a.
positive reactivity changes, movement of irradiated fuel and movement of heavy loads over irradtated fuel, and b.
Immediately initiate corrective actions to restore the minimum A.C. electrical power sources to OPERABLE status, and c.
Establish containment penetration closure as identified in Specification 3.9.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for requirement 4.8.1.1.2a.5.
l 1
Performance of Action a. shall not preclude completion of actions to l
establish a safe conservative position.
1 CALVERT CLIFFS - UNIT 2 3/4 8-5 Amendment No. 135
~
i ELECTRICAL POWER SYSTEMS 3/4.B.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. DISTRIBV110N - OPERATIM LIMITING CONDITION FOR OPERATION 3.8.2.1 The following A.C. electrical busses shall be OPERABLE and energized from sources of power other than the diesel generators with tie breakers open between redundant busses:
4160 volt Emergency Bus #11 4160 volt Emergency Bus #14 480 volt Emergency Bus #11A or 14B 480 volt Emergency Bus #14A of 118 120 volt A.C. Vital Bus #11 120 volt A.C. Vital Bus #12 120 volt A.C. Vital Bus #13 120 volt A.C. Vital Bus #14 APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With less than the above complement of A.C. busses OPERABLE, restore the inoperable bus to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SilU1DOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
EURVEILLANCE RE0VIREMENTS 4.8.2.1 The specified A.C. busses shall be determined OPERABLE and energized from A.C. sources other than the diesel generators with tie breakers open between redundant busses at least once per 7 days by t
verifying correct breaker alignment and indicated power availability.
l CALVERT CLIFFS - UNIT 1 3/4 8-6 Amendment No. 155 U----..--.-
_ _ _ __ _ ~
r ELECTRICAL POWER SYSTEMS 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. DISTRIBUTION - OPERATING LIMITING CONDITION 10R OPERATION 3.8.2.1 The following A.C. electrical busses shall be OPERABLE and energized from sources of power other than the diesel generators with tie breakers open between redundant busses:
4160 volt Emergency Bus #21 4160 volt Emergency Bus #24 480 volt Emergency Bus #21A or 248 480 volt Emergency Bus #24A of 21B 120 volt A.C. Vital Bus #21 120 volt A.C. Vital Bus #22 120 volt A.C. Vital Bus #23 120 vcit A.C. Vital Bus #24 APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With less than the above complement of A.C. busses OPERABLE, restore the inoperable. bus to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least il0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVElltANCE RE0VIREMENTS 4.8.2.1 The specified A.C. busses shall be determined OPERABLE and energized from A.C. sources other than the diesel generators with tie breakers open between redundant busses at least once per 7 days by verifying correct breaker alignment and indicated power availability, p
L CALVERT CLIFFS - UNIT 2 3/4 8-6 Amendment No. ES 135
ELECTRICAL POWER SYSTEMS A.C. DISTRIBUTION - SHVTDOWH LIMITING CONDITION FOR OPERATION 3.8.2.2 As a minimum, the following A.C. electrical busses shall be OPERABLE and energized from sources of power other than a diesel generator but aligned to an OPERABLE diesel generator:
1 - 4160 volt Emergency Bus.
1-480 volt Emergency Bus 2-120 volt A.C. Vital Busses APPLICABILITY: MODES 5 and 6 ACTION:
With less than the above complement of A.C. h.sses OPERABLE and energized:
Immediately* suspend all operations involving CORE ALTERATIONS, a.
positive reactivity changes, movement of irradiated fuel and movement of heavy loads over irradiated fuel, until the minimum required A.C. busses are restored to OPERABLE and energized status, and b.
Immediately initiate corrective actions to restore the minimum A.C. electrical busses to OPERABLE and energized status, and c.
Establish containment penetration closure as identified in Specification 3.9.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
ERVEllLXCE RE0VIREMENTS 4.8.2.2 The specified A.C. busses shall be determined OPERABLE and energized from A.C. sources other than the diesel generators at least once per 7 days by verifying correct breaker alignment and indicated power availability.
Performance of Action a, shall not preclude completion of actions to establish a safe conservative position.
CALVERT CLIFFS - UNIT 1 3/4 8-7 Amendment No. 155 1
l ELECTRICAL POWER SYSTEMS A.C. DISTRIBUTION - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.2 As a minimum, the following A.C. electrical bustes shall be OPERABLE and energized from sources of power other that c diesel generator but aligned to an OPERABLE diesel generator:
1 - 4160 volt Emergency Bus 1-480 volt Emergency Bus 2-120 volt A.C. Vital Busses APPLICABillTY:
MODES 5 and 6 A I103:
l With less that the above complement of A.C. busses OPERABLE and energized:
a.
Immediately* suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel and movement of heavy loads over irradiated fuel, until the minimum required A.C. busses are restored to OPERABLE and ene.gized status, and b.
Immediately initiate corrective actions to restore the minimum A.C. electrical busses to OPERABLE and energized status, and c.
Establish containment penetration closure as identified in Specification 3.9.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
SVRVEILLANCE RE0VIREMENTS 4.8.2.2 The specified A.C. busses shall be determined OPERABLE and energized from A.C. sources other than the diesel generators at least once per 7 days by verifying correct breaker alignment and indicated power availability.
Performance of Action a. shall not preclude completion of actions to establish a safe conservative position.
CALVERT CLIFFS - UNIT 2 3/4 8-7 Amendment No.
135
ELECTRICAL POWER SYSTEMS (LC. DISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.3 The following D.C. bus trains shall be energized and OPERABLE:
125-volt D.C. bus No. 11, the associated 125-volt D.C. battery a.
bank or as necessary the Reserve Battery, and one associated full capacity charger.
b.
125 volt D.C. bus No.12, the associated 125-volt D.C. battery bank or as as necessary the Reserve Battery, and one associated full capacity charger.
125-volt D.C. bus No. 21, the associated 125 volt D.C. battery c.
bank or as necessary the Reserve Battery, and one associated full capacity charger, d.
125-volt D.C. bus No. 22, the associated 125-volt D.C. battery bank or as necessary the Reserve Battery, and one associated full capacity charger.
APPLICABILJJ1: MODES 1, 2, 3 and 4.
ACTION:
With one 125-volt bus inoperable, restore the inoperable bus to a.
OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.
With one 125 volt D.C. battery inoperable and the associated 125-volt D.C. bus not being supplied by the Reserve Battery except during surveillance testing per Specification 4.8.2.3.2.d.1:
1.
Restore the inoperable battery to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or replace the inoperable battery with the OPERABLE Reserve Battery within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or 2.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, c.
With both 125-volt battery chargers from the same D.C. bus inoperable:
1.
Except when ne'cessary during surveillance testing per L
Specification 4.8.2.3.2.d.1, restore at least one 125-volt L
D.C. battery charger to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or l
be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in l
COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l I
CALVERT CLIFFS - UNIT 1 3/4 8-8 Amendment No. 7p//9/ M / # ////,155 l'
b.
- - - ~ - - -
- - - - - - ' ~ ~ ~ ~ ~
ELECTRICAL POWER SYSTEMS D.C. DISTRIBUTION - OPERATING LUiLTElG CONDITION FOR OPERATION 3.8.2.3 The following D.C. bus trains shall be energized and OPERABLE:
a.-
125-volt D.C. bus No. II, the associated 125-volt D.C. battery bank or as necessary the Reserve Battery, and one associated full capacity charger, b.
125-volt D.C. bus No. 12, the associated 125-volt D.C. battery bank or as as necessary the Reserve Battery, and one associated full capacity charger.
d c.
125-volt D.C. bus No. 21, the associated 125-volt D.C. battery bank or as necessary the Reserve Battery, and one associated full capacity charger d.
125-volt D.C. bus No
'.2, the assoc!ated 125-volt D.C. battery bank or as necessary the Reserve Battery, and one associated full capacity charger.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
a.
With one 125-volt bus ino)erable, restore the inoperable bus to OPERABLE status within 2 Tours or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUIDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With one 125-volt D.C. battery inoperable and the associated 125-volt D.C. bus not being supplied by the Reserve Battery except during surveillance testing per Specification 4.8.2.3.2.d.1:
1.
Restore the inoperable battery to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or replace the inoperable battery with the OPERABLE Reserve Battery within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or l
2.
Be in at least HOI STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
With both 125-volt battery chargers from the same D.C. bus inoperable:
1.
Except when necessary during surveillance testing per Specification 4.8.2.3.2.d.1, restore at least one 125-volt l
D.C. battery charger to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
CALVERT CLIFFS - UNIT 2 3/4 8-8 Amendment No. /E/////S////S/,.135
ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION 1 Continued) 2.
During-surveillance testing per Specification 4.8.2.3.2.d.1, restere at least one 125-volt D.C. battery charger 'o OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or 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 /> and in COLD 59?r,00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
d.
With single cells having a voltage decrease of more than 0.10 volts from the previous performance discharge test (4.8.2.3.2.f.) value, but still 2 2.10 volts per surveillance requirement 4.8.2.3.2.b.l., either restore / replace cells or replace the affected battery with the Reserve Battery within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUIDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
M YEILLSjCE RE0VIREMENTS 4.8.2.3.1 fech D.C. bus train shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated p uer availability.
4.8.2.3.2: Each 125 volt battery bank and charger and the Reserve Battery shall be demonstrated OPERABLE:
a.
At least once per 7 days by verifying that:
1.
The electrolyte level of each pilot cell is between the minimum and maximum level indication marks.
2.
The pilot cell specific gravity, corrected to 77 F and 0
full electrolyte level is 2 1.200.
3.
The pilot cell voltage is 2 2.10 volts.
4.
The overall battery voltage is 2 125 volts.
-b.
At least once per 92 days by verifying that:
1.
The voltage of each connected cell is 2 2.10 volts under float charge and has not decreased more than 0.10 volts
-from the value observed during the latest performance discharge test (4.8.2.3.2.f).
0 2.
The specific gravity, corrected to 77 F and full electrolyte level, of each connected cell is 11.200 and has not decreased more than 0.02 from t.he val:1 observed during the previous test.
3.
The electrolyte level of each connected cell ts between the mir.imum and maximum level indication marks.
CALVERT CLIFFS - UNIT 1 3/4 8-9 Amendment No. f9/A8/9//JJA,155
.o ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) 2.
During surve1 lance testing per Specification 4.8.2.3.2.d.1, restore at least one 125-volt D.C. battery charger to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or 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 /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, d.
With single cells having a voltage decrease of more than 0.10 volts from the previous performance discharge test (4.8.2.3.2.f.) value, but still 2 2.10 volts per surveillance requirement 4.8.2.3.2.b.l., either restore / replace cells or replace the affected battery with the Reserve Battery within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE RE0VIREMENTS 4.8.2.3.1 Each D.C. bus train shall be determined OPERABLE and energized at lea once per 7 days be verifying correct breaker alignment and indicatcd power availability.
4.8.2.1.2 Each 125-volt battery bank and charger and the Reserve Battery shall be demonstrated OPERABLE:
a.
At least once per 7 days by verifying that:
1.
The electrolyte level of each pilot cell is between the minimum and maximum level indication marks.
2.
The pilot cell specific gravity, corrected to 77 F and 0
full electrolyte level is 2 1.205.
3.
The pilot cell voltage is 2 2.10 volts.
4.
The overall battery voltage is 2 125 volts, b.
At least once per 92 days be verifying that:
1.
The voltage of each connected cell is 2 2.10 volts under float charge and has not decreased more than 0.10 volts from the value observed during the latest performance discharge test (4.8.2.3.2.f).
0 2.
The specific gravity, corrected to 77 F and full electrolyte level, of each connected cell is 2 1.200 and has not decreased more than 0.02 from the value observed during the previous-test.
'3.
The electrolyte level of each connected cell is between the minimum and maximum level indication marks.
CALVERT CLIFFS - UNIT 2 3/4 8-9 Amendment No. /2//p//J#/,135
ELECTRfCAL POWER SYSTEMS SURyUllANCE REQUIREMENTS ((gntinued) c.
At least once per 18 months by verifying that:
1.
The cells, cell plates and battery racks show no visual indication of physical damage or deterioration.
2.
The cell-to-cell and terminal connections are clean, tight, and coated with anti-corrosion material, d.
At least once per 18 months by verifying that the battery capacity, with the charger disconnected, is adequate to either:
1.
Supply and maintain in OPERABLE status all of the actual emergency loads for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when the battery is subjected to a battery service test.
At tne completion of this test, surveillance 4.8.2.3.2.e shall be performed for the affected battery.
The battery shall be charged to at least 95% capacity in 1 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or 2.
Supply a dummy load simulating the emergency loads of the design duty cycle for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> while maintaining the battery terminal voltage ;t 105 volts. At the completion of this test, the battery shall be charged to at least 95% capacity in 1 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, excluding the stabilization time.
The emergency loads of the design duty cycle shall be documented and updated, as appropriate, in the system description contained in FSAR Chapter 8, and updated in accordance with 10 CFR 50.71(e),
e.
At least once per 18 months, the battery charger
- shall be demonstrated capable of recharging the battery at a rate of 5 400 amperes while supplying normal D.C. loads or equivalent or greater dummy load, f.
At least once per 60 months by verifying that the battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test.
This performance discharge test shall be performed subsequent to the satisfactory completion of the required battery service test.
Not applicable to the charger associated with the Reserve Battery.
CALVERT CLIFFS - UNIT 1 3/4 8-10 Amendment No. fp/EE/$f/SJ/JJ//JR I
155
ELECTRICAL-POWER SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) c.
At least once per 18 months by verifying that:
1.
The cells, cell plates and battery racks show no visual indication of physical damage or deterioration.
2.
The cell-to-cell and terminal connections are clean, tight, and coated with anti-corrosion material.
d.
At least once per 18 months by verifying that the battery capacity, with the charger disconnected, is adequate to either:
1.
Supply and maintain in OPERABLE status all of the actual emergency loads for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when the battery is subjected to a battery service test. At the completion of this test, surveillance 4.8.2,3.2.e shall be performed for the affected battery.
The battery shall be charged to at least 95% capacity in 5 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or 2.
Supply a dummy load simulating the emergency loads of the design duty cycle for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> while maintaining the battery terminal voltage > 105 volts.
At the completion of this test, the battery shall be charged to at least 95% capacity in s 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, excluding the stabilization time.
The emergency loads of the design duty cycle shall be documented and updated, as I
I appropriate, in the system description contained in FSAR Chapter 8, and updated in accordance with 10 CFR 50.71(e).
1 At least once per 18 months, the battery charger
- shall be e.
demonstrated capable of recharging the battery at a rate of 1 400 amperes while supplying normal D.C. loads or equivalent or greater dummy load.
l f.
At least once per 60 months by verifying that the battery capacity is at least 80%-of the manufacturer's rating when -
subjected to a performance discharge test.
This performance discharge test shall be performed subsequent to the satisfactory completion of the required battery cervice test.
Not applicable to the charger associated with the Reserva Battery.
I:
CALVERT CLIFFS - UNIT 2 3/4 8-10 Amendment No. 22//p//E//J/97/
J79,135
4; Ei.ECTRICAL POWER SYSTEMS D.C. DISTRIBUTION -' SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.4 As a minimum, the following D.C. electrical equipment and busses shall be energized and OPERABLE:
2-125-volt D.C. busses, and 4
2-125 volt battery banks, one of which may be the Reserve Battery, and one associated charger per bank supplying the above D.C. busses.
APPLICABILITY: MODES 5 and 6.
ACTION:
With less than the above complement of D.C. equipment and busses OPERABLE:
Immediately* suspend all operations involving CORE ALTERATIONS, a.
positive reactivity changes, movement of irradiated fuel, and movement of heavy loads over irradiated fuel until the minimum required D.C. equipment and busses are restored to OPERABLE status,.and b.-
.Immediately initiate corrective actions.to restore the minimum D.C. equipment and busses to OPERABLE status, and c.
Establish containment penetration closure as identified in Specification 3.9.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
SVRVEILLANCE RE0VIREMENTS 4.8.2.4.1- -The above required 125-volt D.C. busses shall be determined OPERABLE and energized at least once per 7 days by verifying correct
-breaker alignment and indicated power--availability.
- 4.8.2.4.2 The above required 125-volt battery banks and chargers shall
- be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.
l l
l-Performance of Action a. shall not preclude completion of actions to establish a safe conservative position.
CALVERT CLIFFS - UNIT 1 3/4 8-11 Amendment No. JJf, 155
f1ECTRICAL POWER SYSTEMS D.C. DISTRIBUTION - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.4 As a minimum, the following D.C. electrical equipment and busses shall be energized and OPERABLE:
2-125-volt D.C. busses, and 2-125-volt battery banks, one of which may be the Reserve Battery, and one associated charger per bank supplying the above D.C. busses.
APPLICABILITY: MODES 5 and 6.
ACTION:
With less than the above complement of D.C. equipment and busses OPERABLE:
Immediately* suspend all operations involving CORE ALTERATIONS, a.
positive reactivity changes, movement of irradiated fuel and movement of heavy loads over irradiated fuel until the minimum required D.C. equipment and busses are restored to OPERABLE status, and b.
Immediately initiate corrective actions to restore the minimum D.C. equipment and busses to OPERABLE status, and c.
Establish containment penetration closure as identified in Specification 3.9.4 within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
SURVEILLANCE RE0VIREMENTS 4.8.2.4.1 The above required 125-volt D.C. busses shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.
4.8.2.4.2 The above required 125-volt battery banks and chargers shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.
- Performance of Action a. shall not preclude completion of actions to establish a safe conservative position.
CALVERT CLIFFS - UNIT 2 3/4 8-11 Amendment No. 97,135
1 l
REFUELING OPERATIONS DECAY TIME LIMITING CONDITION FOR OPERA ~10N 3.9.3 The reactor shall be subcritical for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.
ACTION:
With the reactor subcritical for less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, suspend all operations involving movement of irradiated fuel in the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.9.3 The reactor shall be determined to have been subcritical for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> by verification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor pressure vessel.
CALVERT CLIFFS - UNIT 1 3/4 9-3 Amendment No. 155
~
REFUELING OPERATIONS DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3 The reactor shall be subcritical for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
APPLICABILITY:
During movement of irradiated fuel in the reactor pressure vessel.
ACTION:
With the reactor subcritical for less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, suspend all operations involving movement of irradiated fuel in the reactor pressure vessel.
The provisions of Specification 3.0.3 are not applicable.
SURVElllANCE RE0VIREMENTS 4.9.3 The reactor shall be determined tc have been subtritical for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> by verification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor pressure vessel.
1 CALVERT CLIFFS - UNIT 2 3/4 9-3 Amendment Nr.135
~_
m REFUELING OPERATIONS CONTAINMENT PENETRATIONS LIMITING CQEDITION FOR OPERATION 3.9.4 The containment penetrations shall be in the following status a.
The equipment door closed and held in place by a minimum of four bolts, b.
A minimum of one door in each airlock is closed,* and c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
1.
Closed by an isolation valve, blind flange, or manual valve, or 2.
Be capable of being closed by an OPERACLE automatic containment purge valve.
APPLICABILITY:
During CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel within the containment, movement of heavy loads over irradiated fuel within the containment building, and electrical power distribution system degradation as required by Specifications 3.8.1.2, 3.8.2.2 and 3.8.2.4.
ACTION:
With the requirements of the above specification not satisfied, a.
immediately** suspend all operat ans involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel within the containment and movement of heavy loads over irradiated fuel within the containment building, b.
The provisions of Specification 3.0.3' are not applicable.
The emergency escape hatch temporary closure device is an acceptable replacement for that airlock door.
Performance of Action a. shall not preclude completion of actions to establish a safe conservative position.
CALVERT CLIFFS - UNIT 1 3/4 9-4 Amendment No. JEE,155
1 REFUELING OPERATIONS l
CONTAINMENT PENETRATIONS SVRVEILLANCE REQ _VIREMENTS 4.9.4 Each of the above required containment penetrations shall be determined to be either in its closed / isolated condition or capable of being closed by an OPERABLE automatic containment purge valve within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel in the containment, movement of heavy loads over irradiated fuel within the containment building, or electrical power distribution system degradation by:
a.
Verifying the penetrations are in their closed / isolated condition, or b.
Testing the containment purge valves per the applicable portions of Specification 4.6.4.1.2.
CALVERT CLIFFS - UNIT 1 3/4 9-4a Amendment No. 155
REFUEllNG OPERATIONS-CONTAINMENT PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment penetrations shall be in the following status:
a.
The equipment door closed and held in place by a minimum of four bolts, b.
A minimum of one door in each airlock is closed *, and c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
1.
Closed-by an isolation valve, blind flange, or manual valve, or 2.
Be capable of being closed by an OPERABLE automatic containment purge valve.
APPLICABILITY: During CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel within the containment, movement of heavy loads over irradiated fuel within the containment building, and electrical power distribution system degradation as required by Specifications 3.8.1.2, 3.8.2.2 and 3.8.2.4.
AC1103:
a.
With the requirements of the above specification not satisfied, immediately** suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel within the containment and movement of heavy loads over-irradiated fuel within the containment building.
b.
The provisions of Specification 3.0.3 are not applicable.
The emergency escape hatch temporary closure device is an acceptable replacement for that airlock door.
Performance of Action a. shall not preclude completion of actions to establish a safe conservative position.
l CALVERT CLIFFS - UNIT 2 3/4 9-4 Amendment No. N,135 i
t -.
.. =.
BEfVELING OPERATIONS CONTAINMENT PENETRATIONS SURVEILLANCE RE0VIREMENTS 4.9.4 Each of the above required containment penetrations shall be determined to be either in its closed / isolated condition or capable of being closed by an OPERABLE automatic containment purge valve within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel in the containment, movement of heavy loads over irradiated fuel within the containment building, or electrical power distribution system degradation by:
a.
Verifying the penetrations are in their closed / isolated condition, or b.
Testing the containment purge valves per the applicable portions of Specification 4.6.4.1.2.
i i
L L
i CALVERT CLIFFS - UNIT 2 3/4 9-4a Amendment No.135
l 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 _10NTAINMENT INTEGRITY In MODES 1, 2, 3, and 4, primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment acmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses.
This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.
In H0 DES 5 and 6, the probability and consequences of these events are reduced because of the Reactor Coolant System (RCS) pressure and temperature limitations of these modes, by preventing operations which could lead to a need for containment isolation, and by providing containment isolation through penetration closure.
3/4.6.1.2 CCNTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, P.
As an added a
conservatism, the measured overall integrated leakage rate is further limited to 1 0.75 L or 0.75 Lt (as applicable) during performance of a
the periodic tests to account for possible degradation of the containment leakage barriers between leak tests.
The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50.
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.
Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
CALVERT CLIFFS - UNIT 1 B 3/4 6-1 Amendment No. 155
3/4.6 CONTAINMENT SYSTElil BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMFST INTEGRIll in MODES 1, 2, 3, and 4, primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses.
This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.
In MODES 5 and 6, the probability and consequences of these events are reduced because of the Reactor Coolant System (RCS) pressure and temperature limitations of these modes, by preventing operations which could lead to a need for containment isolation, and by providing containment isolation through penetration closure.
3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, P. As an added a
conservatism, the measured overall integrated leakage rate is further limited to 5 0.75 L or 1 0.75 Lt (as applicable) during performance of a
the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50.
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.
Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
CALVERT CLIFFS - UNIT 2 8 3/4 6-1 Amendment No.135
3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on minimum boron concentration (2300 ppm) ensure that:
- 1) the reactor will remain subcritical during CORE ALTERATIONS, and 2) a uniform boron concentration is maintained for reactivity control in the water volumes having direct access to the reactor vessel. The li91tation on Keff of no greater than 0.95 which includes a conservative allowance for uncertainties, is sufficient to prevent reactor criticality during refueling operations.
3/4.9.2 INSTRUMENTATIQN The OPERABILITY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products.
This decay time is consistent with the assumptions used in the accident analyses.
3/4.9.4 CONTAINMENT PENETRATIONS During CORE ALTERATIONS or movement of irradiated fuel within containment, a release of fission product radioactivity to the environment must be prevented.
During MODES 1, 2, 3, and 4, this is accomplished by maintaining CONTAINMENT INTEGRITY as described in LC0 3.6.1.
In other situations, the potential for containment pressurization as a result of an accident is not present, therefore, less stringent requirements are needed to isolate the containment from the outside atmosphere.
The containment structure serves to contain fission product radioactivity which may be released from the reactor core following a Design Basis Accident (DBA), such that offsite radiation exposures are maintained within the requirements of 10 CFR 100.
Additionally, this structure provides radiation shielding from the fission products which may be present in the containment atmosphere following accident conditions.
3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during CORE ALTERATIONS.
CALVERT CLIFFS - UNIT 1 B 3/4 9-1 Amendment No. /E,155
~..
i 3/4.9 REFUFt1NG OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on minimum boron concentration (2300 ppm) ensure that:
- 1) the reactor will remain subcritical during CORE ALTERATIONS, and 2) a uniform boron concentration is maintained for reactivity control in the water volumes having direct access to the reactor vessel.
The limitation on Kerg of no greater than 0.95 which includes a conservative allowance for uncertainties, is sufficient to prevent reactor criticality during refueling operations.
3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.
3/4.9.3 DECAY TIdf The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor pressure vessel. ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This decay time is consistent with the assumptions used in the accident analyses.
3/4.9.4 CONTAINMENT PENETRATIONS During CORE ALTERATIONS or movement of irradiated fuel within containment, a release of fission product radioactivity to the environment must be prevented.
During MODES 1, 2, 3, and 4, this is accomplished by maintaining CONTAINMENT INTEGRITY as described in LCO 3.6.1.
In other situations, the potential for containment pressurization as a result of an accident is not present, therefore, less stringent requirements are needed to isolate the containment from the outside atmosphere.
- The containment structure serves to contain fission product
-radioactivity which may be released from the reactor core following a Design Basis Accident (DBA), such that offsite radiation exposures are maintained within the requirements of 10 CFR 100. Additionally, this structure provides radiation shielding from the fission products which-may be present in the containment atmosphere-following accident conditions.
3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during CORE ALTERATIONS.
CAVLERT CLIFFS - UNIT 2' 8 3/4 9-1 Amendment No. U,135
REFUELING OPERATIONS BASES 3/4.9.6 REFUEllNG MACHINE OPERABILITY The OPERABILITY requirements for the refueling machine ensure that:
(1) the refueling machine will be used for movement of CEAs and fuel assemblies, (2) the refueling machine has sufficient load capacity to lift-a CEA or fuel assembly, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
3/4.9.7 CRANE TRAVEL SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly and CEA over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.
3/4.9.8 COOLANT CIRCULATION The requirement that at least one shutdown cooling loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor. pressure vessel 0
below 140 F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.
t The requirement to have two shutdown cooling loops OPERABLE when there-is less than 23 feet of water above the core ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability. With the reactor vessel head removed and 23 feet of water above the core, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling loop, adequate time is provided to initiate l
emergency procedures to cool the core.
3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM L
The OPERABILITY of this system ensures that the containment purge valves will be automatically isolated upon detection of high radiation L
levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.
i CALVERT CLIFFS - UNIT I B 3/4 9-2 Amendment No. 55,155 l
CAVLERT CLIFFS - UNIT 2 Amendment No. 38,135
1
~
-REFUELING OPERATIONS-BASES-3/4.9.6 REFUELING MACHINE OPERABILITY The OPERABILITY requirements for the refueling machine ensure that:
(1) the refueling machine will be used for movement of CEAs and fuel assemblies, (2) the refueling machine has sufficient load capacity to lift a CEA or fuel assembly, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly and CEA over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array.
This assumption is consistent with the activity release assumed in the accident analyses.
3/4.9.8 COOLANT CIRCULATION-The requirement that at least one shutdown cooling loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay. heat and maintain the water in the reactor pressure vessel 0
y below 140 F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.
The requirement to have-two shutdown cooling loops OPERABLE when there is less than 23 feet of water above the core ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability.
With the reactor vessel head removed and 23 feet of water-above the core, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling loop, adequate time is provided to initiate emergency procedures to cool the core.
3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment.
The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.
l CALVERT CLIFFS - UNIT 1 B 3/4 9-2 Amendment No. SF, 155 CAVLERT CLIFFS - UNIT 2 Amendment No. N, 135 i