ML20041C219
| ML20041C219 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/08/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17342A100 | List: |
| References | |
| TAC-7318, NUDOCS 8202260360 | |
| Download: ML20041C219 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION U
k WASHINGTON, C. C. 20555 o..
o BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 License No. DPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated July 27, 1977, 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 confomity 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 anendment 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 j
Part 51 of the Commissicn's regulations and all applicable j
requirements have been satisfied.
I l
1 8202260360 820208 PDR ADOCK 05000317 P
2-i 2.
Accordingly, Facility License No. DPR-53 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2), is hereby amended to read as follows:
(2) Technical Specifications i
The Technical Specifications contained in Appendices A and B, as. revised through Amendment No. 66, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l 3.
This license amendment is effective as of the date of its issuance.
(
FOR THE NUCLEAR REGULATORY COMMISSION I
I.-
b~
Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing Attahcment:
Changes to the Technical Specifications Date of Issuance: February 8, 1982 v
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.i ATTACHMENT TO LICENSE AMENDMENT NO. 66 I
FACILITY OPERATING LICENSE NO. DPR-53 DOCKET N0. 50-317
--Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
l The corresponding overleaf page is also provided to maintain document i
completeness.
r Page 3/4 1-22 4
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REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS LIMITING CONDITION FOR OPERATION 3.1.3.3 All shutdown and regulating CEA reed switch position indicator l
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.
Deleted 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, 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 inoperable position indicator channel to OPERABLE status, or 2.
Be in at least HOT STANDBY, or 3.
Rcduca THERMAL POWER to < 70% of the miximum allowable THERMA'. POWER level ~for the existing Reactor Coolant Pump combir.ation; 'f 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:
a)
The CEA group (s) with the inoperable position indi-cator is fully withdrawn while maintaining the withdrawal sequence required by Specification 3.1.3.6 4
l 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 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 j
other applicable specifications; or L
CALVERT CLIFFS - UNIT 1 3/4 1 -21 Amendment No. 32
REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION b)
The CEA group (s) with the inoperable position indicator is fully inserted, and subsequently maintained fully inserted, while maintaining the withdrawal sequence and THERMAL POWER level require 1 by Specification 3.1.3.6 and when this CEA group reaches its fully inserted position, the " Full In" lim t of the CEA with the inoperable position inficator is actuated and verifies this CEA to be fully inserted. Subsequent operation shall be within the limits of Specification 3.1.3.6.
4.
If the failure of the position indicator. channel (s) is during i
STARTUI, the CEA group (s) with the inoperable position indi-cator c iannel must be moved to the " Full' Out" position and verifie to be fully withdrawn via a " Full Out" indicator within a hours.
The provisions of Specification 3.0.4 are no:
applicalle.
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 inopecable position indicator channel at either its fully inserted position or fully withdrawn position, operation may continue provided:
1.
The position of this CEA is verified immediately and at least once pe-12 hours thereaf ter by its " Full In" or " Full Out" limit (i s applicable),
2.
The fully inserted or fully withdrawn (as applicable) CEA group (s) containing the inoperable position indicator channel is subsequently maintained fully inserted (r fully withdrawn (as applicable), and 3.
Subsequent operation is within the limits of Specification 3.1.3.6.
d.
With more than one pulse counting position inficator channels in-operable, 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 positinn 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 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 />.
C;LVERT CLIFFS - UNIT 1 3/4 1-22 Amendment No.66 s
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UNITED STATES.
[o NUCLEAR REGULATORY COMMISSION 8
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BALTIMORE GAS AND ELECTRIC COMPANY
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DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE' Amendment No. 4B 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 July 27, 1977, complies with the i
standar.ds and requirements of the Atomic. Energy' Act of 1954, as amended (the Act) and the Commission't 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 Conmission's regulations; D.
The issuance of this amendment will not be inimical to the ccamon 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.
l l
r
i s-t 2.
Accordingly, Facility License No. DPR-69 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2, is hereby amended to read as follows:
2 Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 48, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
'^
h ('c R er$N.' Clark, Chief
~
Operating Reactors Branch #3 Division of Licensing Attachnent:
Changes to the Technical Specifications Date of Issuance: Februar) 8,1982 l
a:.
ATTACHMENT TO LICENSE AMENDMENT NO. 48 6
FACILITY OPERATING LICENSE N0. DPR-69 DOCKET NO. 50-318 Replace the following page of the Appendix A Technical Specificatiois with the enclosed page as indicated. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
Page I
3/4 1-22 4
4 a
S
s REACTIVITY CONTROL SYSTEMS l
POSITION INDICATOR CHANNELS LIMITING CONDITION FOR OPERATION 3.1.3.3 All shutdown and regulating CEA reed switch position indicator l
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.
Deleted.
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, 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 inoperable position indicator channel to OPERABLE status, or 2.
Be in at least HOT STANDBY, or 3.
Reduce THERMAL POWER to < 70% of the maximum allowable 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:
a)
The CEA group (s) with tr a inoperable position indi-cator is fully withdrawr, while maintair.ing the withdrawal 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 withdr1 wing this CEA group (s), the THERMAL POWER level may be returned to a level consistent with all other applicable specifications; or CALVERT CLIFFS-UNIT 2 3/4 1 -21 Amendment No. 18
REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION b) Tt e CEA group (s) with the inoperable position indicator is folly inserted, and subsequently maintained fully inserted, while maintaining the withdrawal sequence and THERMAL POWD level required by Specification 3.1.3.6 and when this LEA group reaches its fully inserted position, the " Full In" limit of the CEA with the inoperable position indicator is actuated and verifies this CEA to be fully inserted.
Subse-quent oper tion shall be within the limits of Specificatir 3.1.3.6.
4.
If the failure of the position indicator channel (s) is durin; I
STARTUP, the CEA group (s) with the inoperable position indicator channel must be moved to the " Fill Out" position and verified to be fully withdrawn via a " Full Out" indicator within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
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 tne inoperi ble position indicator channel at eithe:
its fully inserted position or fully withdrawn position, operation may continue provided:
1.
The position of this CEA is verified immeaiately 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 /> thereaf ter by its " Full In" or " Full Out" limit (as applicable),
2.
The fully inserted or fully withdrawn (as applicable) CEA group (s) containing the inoperable position indicator channel is subsequently maintained fully inser+.ed or fully withdrawn (as applicable), and 3.
Subsequent operation is within the limits of Specification 3.1.3.6.
d.
With more than one pulse counting position indicator channels in-operable, operation in t10 DES 1 a i 2 nay 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 posit on 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 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 col nting position indicator and reed switch position indicator
) channels at least on' e per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
CALVEF T CLIFFS - UNIT 2 3/4 1-22 Amendment No. 48