ML20065M750
| ML20065M750 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/04/1990 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065M753 | List: |
| References | |
| NUDOCS 9012110189 | |
| Download: ML20065M750 (9) | |
Text
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UNITED STATES -
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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO, 50-317 i
CALVERT CLIFFS NUCLEAR POWER PLANT UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.-149 License No. DPR-53 :
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (thelicensee)datedJanuary 20, 1989, as supplemented on June 30, 1989 and October 4, 1990, complies with the standards and re ments of the Atomic Energy Act of 1954, as amended (the Act) quire-and the Commission's rules and regulations set forth in 10 CFR Chapter I;.
B.
The facility will o)erate in conformity with the application, the provisions of t1e Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized-
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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 Commission'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:
9012110189 901204 PDR ADOCK 05000317 P
~2-(2) Technical Specifications The Technical Specifications contained in Appendices i
A and B, as revised through Amendment No.149, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendwent is effective as of the date of its-issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY. COMMISSION w t s cc. c w Robert A. Capra, Director Project Directorate I-1 Division'of Reactor Projects - I/II L
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 4, 1990 I
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UNITED STATES 0'
'. 1 NUCLEAR REGULATORY COMMISSION 3.-
e W ASmHO TON, D. C. 20555 BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO, 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.130 License No. DPR-69 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated-January 20, 1989, as supplemented on June 30, 1989, and October 4,1990, comnlies with the standards and re ments of the Atomic Energy Act of 1954, as amended (the Act) quire-and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applict. tion, the provisions of the Act, and the rules and regulations of the Comission; 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 (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
1ssuance' 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 naragraph 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.130, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical-Specifications.
3.
This license amendmerit is e' fective as of the date of its issuance and shall be implemented within-30 days.
FOM THE NUCLEAR REGULATORY COMMISSION T U L-W Robert A. Capra. Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
)
Changes to the Technical Specifications Date of Issuance:
December 4, 1990 i
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.149 FACILITY OPERATING LICENSE NO DPR-53 AMENDMENT NO. 130 FAC7LITY OPERATING LICENSE NO. DPR-69 i
DOCKET NOS. 50-317 AND 50-318 f
Revise Appendix A as follows:
l Remove Pants Insert Paaes 3/4 3-21 3/4 3-21 3/4 3-22*
3/4 3-22*
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- Pages that did not change, but are overlief i
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TABLE 3.3 5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 6.
Steam Generator Pressure Low a.
Main Steam Isolation s 6.9 b.
Feedwater Isolation s 80 7.
Refuelina Water Tank-low a.
Containment Sump Recirculation s 80 8.
Reactor Trio a.
Feedwater Flow Reduction to 5%
s 20 9.
Loss of Power a.
4.16 kv Emergency Bus Under-voltage (Loss of Voltage) s 2.2*
I b.
4.16 kv Emergency Bus Under-voltage (Degraded Voltage) s 8.4*
l 10.
Steam Generator Level-Low a.
Steam Driven AFW Pump 5 180 b.
Motor Driven AFW Punp 5 180 li.
Steam Generator aP Hich a.
Auxiliary Feedwater Isolation 1 20.0 TABLE NOTATION Response time measured from the incidence of the undervoltage condition to the diesel generator start signal.
(1) Header fill time not included.
~CALVERT CLIFFS UNIT 1 3/4 3 21 Amendment No. /S/JA/7J/72/
EEi 149 i
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i TABLE 4.3-2 Q
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUNENTATION SURVEILLANCE REQUIREMENTS
{
G l
g CHANNEL MODES IN HHICH
-1 CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE l2 FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED l
M Q
1.
SAFETY INJECTION (SIAS)'
i a.
Manual (Trip buttons)
N.A.
N.A.
R N.A.
b.
Containment Pressure - High 5
R M
1, 2, 3 c.
5 c.
Pressurizer Pressure - Low S
R M
1, 2, 3 H
d.
Automatic Actuation Logic N.A.
N.A.
M(t)(3) 1, 2, 3 l
l t
2.
CONTAIISIENT SPRAY (CSAS) a.
Manual (Trip buttons)
N.A.
N.A.
R N.A.
b.
Containment Pressure-High 5
R M
1, 2, 3 j
c.
Automatic Actuation Logic N.A.
M.A.
M(1)(6) 1, 2, 3 l
R 3.
CONTAlletENT ISOLATION (CIS)#
y a.
Manual CIS (Trip buttons)
N.A.
N.A R
N.A.
g b.
Containment Pressure-High S
R M
1, 2, 3 c.
Automatic Actuation Logic M.A.
N.A.
M(1)(4) 1, 2, 3 4.
MAIN STEAM LINE ISOLATION (SGIS)
- a. -Manual SGIS (ttSIV Hand Switches and Feed Head Isolation Hand Switches)
N.A.
N.A.
R N.A.
b.
Steam Generator Pressure-Low 5
R M
1,2,3 k
t c.
Automatic Actuation Logic N.A.
N.A.
M(1)(5) 1, 2, 3
- s
,3 I
g
- Containment isolation of non-essential penetrations is also initiated by SIAS (functional units 1.a and 1.c).
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TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 6.
Steam Generator Pressure-Low a.
Main Steam Isolation s 6.9 b.
Feedwater Isolation s 80 7.
Refuelina Water Tank-low a.
Containment Sump Recirculation s 80 8.
Reactor Trio a.
Feedwater Flow Reduction to 5%
$ 20 9.
Loss of Power a.
4.16 kv Emergency Bus Under-voltage (Loss of Voltage) s 2.2*
I b.
4.16 kv Emergency Bus Under-voltage (Degraded Voltage) s 8.4*
l 10.
Steam Generator level - (qs a.
Motor Driven AFW Pump 5 180 b.
Steam Driven AFW Pump 1 180 11, iteam Generator aP-Hiah' a.
Auxiliary Feedwater Isolation s 20.0 TABLE NOTATION Response time measured from the incidence of the undervoltage condition to the diesel generator start signal.
1 CALVERT CLIFFS - UNIT 2 3/4 3-21 Amendment No. 22/J//EJ, 130
TABLE 4.3-2 h
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTAION SURVEllLANCE REQUIRE M
y CHANNEL MODES IN WilCH n
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 4
1.
SAFETY INJECTION (SIAS)
~
a.
Manual (Trip Buttons)
N.A.
M.A.
R N.A.
E b.
Containment Pressure - High S
R M
1, 2, 3 q
c.
Pressurizer Pressure - Low S
R M
1, 2, 3 d.
Automatic Actuation Logic N.A.
N.A.
M(1)(3) 1, 2, 3 m
2.
CONTAINMENT SPRAY (CSAS) a.
Manuai (Trip Buttons)
N.A.
N.A.
R.
M.A.
~
b.
Containment Pressure --
High S
R M
1,2,3 c.
Automatic Actuation Logic N.A.
M.A.
'M(1)(6) 1, 2, 3 l
1 M
3.
CONTAINMENT ISOLATION (CIS) #
y a.
Manual CIS (Trip Buttons)
N.A.
N.A.
R N.A.
g b.
Containment-Pressure - High
-S R
M 1, 2, 3 c.
Automatic Actuation Logic
.N.A.-
N.A.
M(1)(4) 1, 2. 3 4.
MAIN STEAM LINE ISOLATION (SGIS) a.
Manual SGIS (MSIV. Hand Switches and Feed Head E
Isolation Hand Switches)
N.A.
N.A.
R N.A.
~
R-b.
Steam Generator Pressure - Low 5 R
M 1, 2, 3 c.
Automatic Actuation Logic N.A.
N.A.
M(1)(5) 1, 2, 3
- [
' # Containment isolation of non-essential penetrations is also initiated by SIAS (functional units s.
1.a and 1.c).
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