ML20127B568
| ML20127B568 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/05/1993 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127B569 | List: |
| References | |
| NUDOCS 9301120338 | |
| Download: ML20127B568 (7) | |
Text
..
t..
js/
'o.
UNITED STATES -
J d-NUCLEAR REGULATORY COMMISSION {
J-
,i
' WASHINGTON, D. C. 20555 L
lI a.***
BALTIMORE GAS AND ELECTRIC COMPANY-
-DOCKET NO.~ 50-317 CALVERT CLIFFS NUCLEAR' POWER PLANT-UNIT N0.=l~
. AMENDMENT TO FACILITY OPERATING LICENSE Amendment-No'.'178
~ License No. OPR-53'
.1.
The Nuclear Regulatory Comission (the Commission).has found that:
A.
The application for amendment by Baltimore Gas-and Electric Company (the licensee)-dated September 25, 1992,' complies with the standards-and requirements of the Atomic Energy ActLof-1954,- as amended (the-
'Act and the Comission's rules and regulations set forth in10 CFR'
-l
' Chap)ter I;'
~
B.
The' facility will operate in conformity. with the, application, the provisions Lof the Act, 'and the rules and regulations of the Commission; C.
There11s reasonable ' assurance (i)~that thecactivitiesLauthorizedi by this amendment can-be. conducted without-endangering-the health and safety"of the public, and (11) thatisuch activities will be conducted in. compliance with!the Comission's regulat'lons; D.
The issuance of thisL amendment will:not beiinimical to the-common-
-defense;andLsecurity or;to theihealth and safety of the#public;;and:
E.
The issuance of this amendment is in1accordance with 10 CFR Part-
- 51. of the Commission's regulations.and all applicable requirementsi have been satisfied.
L
- 12. - Accordingly,- the license 11s ' amended.by changes-to1the Technical, L
Specifications as indicated -in the' attachment to this license amendment,
.andparagraph2'C.(2)=ofFacilityOperatingLicense_No.DPR-53isherebyj s
amended to. read.as fo'llows:
gn-y u
9301120338.930105" 3 PDR ^z ~ADOCK'05000317 (PJ
. PDS. ~
b l (2) Technical Soccff_i. cations The Technical Specifications contained in Appendices A and B, as revised through Amendment No.178, are hereby incorporated in the license. The licensee shall operate the f acility 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 h 00 <l0 fapJ Robert A. Capra, Director Project Directorate 1-1 Division cf Reactor Projects - 1/11 Offlec of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: January 5,1993 l
((ps **%9'e, UNITED STATES g
g NUCLEAR REGULATORY COMMISSION I
wAsmuoiou, o c.20sss BALTIMORE GAS AND ELE [181L[DMEa!il QOCKET NO. 50-3lg GLyERT CLIFFS NUCLEAFLPOWER PLANT. UNIT NO. 2 A!iR@!fBT TO FACILITY OPERATING LLGI[GE Amsndment No.155 License No. DPR-69 1
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated September 25, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Connission's rules And regulations set forth in 10 CFR Chapter I; D.
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 (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Cocalssion's regulations; D.
The istuance of this amendment will not be inimical to the connon defense and security or to the health and. safety of the puolic; 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 Specificati3ns as indicated in the attachment to this license emendment, and paragraph 2.C.2 of Facility Operating License No, DPR-69 is hereby amended to read as follows:
i,
(2) Jaghnical SoecifiCAtions F
The Technical Specifications contained in Appendices A and B, 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 amendment 1 effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAP 1EGULATORY COMMISSION Y 0-Robert A. Capra, p l 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: January 5, 1993 I
9
)
n
. - ~...
W
.L
dilACHMENT T0 tiCENST AMENDMENTS M @DHENT NO. 178 FACILITY OPERATING LICENSE NO. OPR-53 M@DMLNT NO.155 FACILITY' OPERATING LICENSE NO.'0PR-69 DOCKET NO.S. 50-317 AND 50-316-Revise Appendix A as follows:
Remove Pace Insert Pace 3/4 7-7 3/4 7-7 1
' l I
)
- 4
-N^
6-
- "-w.-
u 3/4.7 PLANT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) 2.
Verify within one hour that No. 23 motor-driven twp 1::
OPERABLE and valve 2-CV-4550 has been exercised within the last 30 days, and 3.
Restore a second pump to automatic initiating status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
Whenever a subsystem (s) (a subsystem consisting of one pump, piping, velves and controls in the direct flow path) required for OPERASILITY is ino erable for the performance of periodic testing s
(e.g., manual disclar e valve closert for pump) Total Dynamic Head Test or Logic Testing adedicatedoperator(s will be stationed at the local station ( ) with direct comunication to the Control Room. Upon completion _of any testing, the subsystem (s) req 1tred for OPERABILITY will be returned to its proper status and verified in its proper status by an independent operator check.
d.
The requirements of Specification 3.0.4 are not applicable whenever one motor and one steam-driven pump (or two steam-driven pumps) are aligned for automatic flow initiation.
SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater flowpath dull be demonstrated OPERABLE:
a.
At least once per 31 days by 1.
Verifying that each stecadrivun pump develops a Total Dynamic Head of 2 2MO ft. on recirculation flow (if verification must S e demonstrated during STAP. TUP, e
surveillance testing shall be perfomed upon achieving an RCS temperature 1300 F and prior to entering MODE 1).
2.
Verifying that the motor-driven pump develops' a Total Dynamic Head of 13100 ft. on recirculation flow.
3.
Cycling each testable, remote-operated valve that is not in its operating position through at least one cciaplete cycle.
Verifying)that each valve (manual, power-operated nr 4.
automatic in the direct flow path that is not locked, sealed or otherwise secured in position is in its correct 1
position.
q-CALVERT CLIFFS - UNIT 1 3/4 7-7 Amendment No.178 i
3/4.7 PLMT SYSTEMS LIMITING C0h'01 TION FOR OPERATICW (Continued) 2.
Verify within one hour that No.13 motor-driven pum) is OPERALLE and valve 1-CV-4550 has been exercised wit 11n the last 30 days, and 3.
Restore a second pump to automatic initiating status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, c.
Whenever a subsystem (s) (a subsystem consisting of one pump, piping, valve, and controls in the direct flow path) required for operability is inoperable for tne perfootnance of periodic. testing (e.g., manual disc 1ar a valve closed for pum Total Dynamic Head Test or Logic Testing )a dedicated operator (p) will s
at the local station (
with direct conrnunication to the control Room.
Upon completion of any testing, the subsystem (s) required for operability will be returned to its proper status and verified in its proper status by an independent operator check, d.
The requiremants of Specification 3.0.4 are not applicable whenever one motor and one steam-driven pump (or two steam-driven pumps) are aligned for automatic flow initiation.
SURVEILLANCE REQUIREMENTS 4.7.1.2 Each r.axiliary feedwater flowpath shall. be demonstrated OPERA 1LE:
a.
At least once per 31 days by:
1.
Verifying that each steam-driven pump develops a Total Dynamic Head of 12800 ft. on recirculation ficw.
(If verification must ce demonstrated during STARTUP, surveillance testing shall be performed upon' achieving an RCS temperature 3 300'F and prior to entering N0DE 1).
2.
Verifyhg that the motor-<triven pump develops a Total Dynamic Head of 13100 ft. on recirculation flow.
3.
Cycling each testable, remote-operated valve that is not in its operating position through at Irast one complete cycle.
4.
Verifying that each valve (manual, power-operated or '.
automatic) in the direct fica path that is not locked, sealed or otherwise secured in position is in its correct position.
CALVERT CLIFFS - UNIT 2 3/4 7-7 Amendment No.155 v
s r
e