ML20012B306
| ML20012B306 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/06/1990 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20012B307 | List: |
| References | |
| NUDOCS 9003140168 | |
| Download: ML20012B306 (6) | |
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1 BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT 1 1
J AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.140 License No. DPR-53 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated December 20, 1989, and supplemented on January 23, l
1990 and February 2 and 14,1990, 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; O.
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.
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license i
amendment, and paragraph 2.C.2 of facility Operating License No.
DPR-53 is hereby amended to read as follows:
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l (2) Technical Specifications The Technical Specifications contained in Appendices l
A and B as revised through Amendment No.140, are herebyIncorporatedinthelicense.
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 s
i shall be implemented within 30 days.
F FOR THE NUCLEAR REGULATORY COMMISSION Y O N-V Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulatfon
Attachment:
Changes to the Technical Specifications Date of Issuance: March 6, 1990 L
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l ATTACHMENT TO LICENSE AMENDMENTS i
ov, AMENDMENT NO.
FACILITY OPERATING LICENSE NO. DPR-53 l
L DOCKET NO. 50-317 i
Revise Appendix A as follows:
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Remove Pages Insert Pages j
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3/4 3-11 3/4 3-11
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3/4'5-6 3/4 5 !
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l TABLE 3.3-3
'ENGIIKERED SAFETY FEATU'tE ACTUATION SYST[M INSTRtNENTATION n?
m MINIfMI TOTAL NO.
CHAMELS CHAMELS APPLICABLE n
FUNCTIONAL INIIT OF CHAfMIELS TO TRIP OPERABLE MODES ACTION l.
SAFETY INJECTION (SIAS)@
I y
a.
Manual (Trip Buttons) 2 1
2 1, 2, 3, 4 6
4 E
b.
Containment Pressure-Z High 4
2 3
1, 2, 3 7*-
c.
Pressurizer Pressure -
Low 4
2 3
1, 2, 3(a) 7*
2.
CONTAllWIENT SPRAY (CSAS) a.
Manual (Trip Buttons) 2 1
2 1, 2, 3, 4 6
b.
Containscrt Pressure --
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High 4
2 3
1, 2, 3 11 3.
CONTAllOENT ISOLATION (CIS)I a.
Manual CIS (Trip Buttons) 2 1
2 1, 2, 3,- 4 6
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b.
Containment Pressure -
i High 4
2 3
1, 2, 3 7*
l E
E Containment isola.-*an of non-essential penetrations is also initiated by SIAS (functional units 1.a and -
i l.c).
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When Tavg i 350 F, the OPERABLE high pressure safety injection pump will be placed in " pull-to-lock" 0
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and will not start automatically.
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T, 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) i F,
SAFETY INJECTION TANKS l
LIMITING CONDITION FOR OPERATION 3.5.1 Each reactor coolant system safety injection tank shall be OPERABLE with:
a.
The isolation valve open.
b.
A contained borated water volume of between 1113 and 1179 cubic feet of borated water (equivalent to tank levels of between 187 and 199 inches, respectively),
i A boron concentration of between 2300 and 2700 ppm, and c.
d.
A nitrogen cover-pressure of between 200 and 250 psig.
eLfLICABillTY: MODES 1, 2 and 3.
f ACTION:
With one safety injection tank inoperable, except as a result a.
of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour 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 />, b.
.With one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in HOT STAN08Y within one hour and be in Hoi SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVElllANCE RE0VIREMENTS 1
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4.5.1 Each safety injection tank shall be demonstrated OPER/.BLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
a.
1.
Verifying the contained horated water volume and nitrogen l
cover-pressure in the v snks, and L
2.
Verifying that each safety injection tank isolation valve is open.
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CALVERT CLIFFS - UNIT 1 3/4 5-1 Amendment No. /E, 55,140 m
b-1 c.
EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - Tayg < 300 F 0
LIMITING CONDIT!0N FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:
One' OPERABLE high pressure safety injection pump, and l
a.
b.
An OPERABLE flow path capable of taking suction f:nt the refueling water tank on a Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal, 3
APPLICABILITY: MODES 3* and 4.
ACTION:
1 With no ECCS subsystem OPERABLE, restore at least one ECCS a.
subsystem to OPERABLE status within I hour or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
b.
In the event the ECCS is actuated and injects. water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
SURVEILLANCE REOUIREMENTS 4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.E.
a.5.3.2 All high pressure safety injection pumps, except the above required OPERABLE pump, shall be demonstrated inoperable at least once per12hgFbyverifyingthat-themotorcircuitbreakershavebeenremo urs whenever the temperature of one or more of the RCS cold legs is 1275 from their electrical power supply circuits.
- With pressurizer pressure < 1750 psia.
- A maximum of one high pressure safety injection pump shall be OPERAB E whenever ti.e temperature of one or more of the RCS cold legs is s 275gF.
0 When Tavg i 350 F, the OPERABLE high pressure safety injection pump will be placed in Pull-to lock and will not start automatically. Manual use of the high pressure safety injection pump will be conducted in accordance with approved procedures.
CALVERT CLIFFS UNIT 1 3/4 5-6 Amendment No. #, 140
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