ML20141E022
| ML20141E022 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 03/27/1986 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20141E019 | List: |
| References | |
| NUDOCS 8604080413 | |
| Download: ML20141E022 (10) | |
Text
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UNITED STATES f.
t NUCLEAR REGULATORY CC,h..a20N j
(
WASHINGTON, D. C. 20555 v
e COMMONWEALTH EDISON COMPANY DOCKET NO. 50-295 ZION NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 97 License No. DPR-39 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 8, 1985, 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 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 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 2.C.(?) of Facility Operating License No. DPR-39 is hereby amended to read as follows:
9604080413 860327 PDR ADOCK 05000295 p
-., (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 97. 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.
FOR THE NU" R REGULATORY COMMISSION r
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'#' Steven A. Var,, DIlec<.ul, r tor PW3 Project Directorate #3 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 27, 1986
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UNITED STATES c-
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NUC, LEAR REGULATOR / COMMISSION
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g wAsmNG TON,0. C. 20555 o
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPEPATING LICENSE Amend.ent No.87 License No. DPR-48 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 8, 1985, complies with the standards and requirements of the Atomic Energy Act of 1054, 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 applicatinn, 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 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 2.C.(?) of Facility Operating License No. DPP-48 is hereby amended to read as follows:
1
4
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 87 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.
FOR THE NUCLEAR. REGULATORY COMMISSION 1
)
' \\\\ s N6u-6 j
i l
l #" Steven A. Varg'a, Director PWR Project Directorate #3
{ Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications I
- Date of Issuance:
March 27, 1986 e
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 97 FACILITY OPERATING LICENSE NO. DPP-39 AMENDMENT NO. 87 FACILITY OPERATIt!G LICENSE NO. DPR-48 DOCKET NOS. 50-295 AND 50-304 I
I Revise Appendix A as follows:
Remove Pages Insert Pacer 130a j
131 131 l
133a 133a 135 135 258 258 4
d W
e b
i 1.
2.
3.
4.
5.
6.
Actuation Channel No. of Minimum Minimum Operator Action Description (Per Unit)
No. of Channels Operable Degree of if column 3 or 4 Channels to trip _
Channels +++
Redundancy _
cannot be met +
Setpoints+
V.
Manual 1/ pump 1/punp 1/ pump 0
Maintain Ifot Shutdown *'
N.A.
2.
Automatic 2
1 2
1 Maintain Hot Shutdown ***
N.A.
t 3.
Steam Generator (S/G)
Water Level low-low I. Start Motor 2 per S/G Griven Pumps 3 f.er S/G any 1/4 S/G 2 per S/G 1 per $/G Maintain llot Shutdown * ** 10%
Narrow Range II. Start Turbine 2 per S/G Driven Pumps 3 per S/G any 2/4 S/G 2 per S/G 1 per S/G Maintain Hot Shutdown *** 10%
l Narrow Range 4.
Undervoltage-RCP burses Start Turbine Driven Pump 4-1/ bus 2
3 1
Maintain flot Shutdown *** RCP Bus 75%
Voltage 5.
S.I. Start Motor and Turbine Driven Pumps 2
1 2
1 Natntain Hot Shutdown ***
N.A.
6.
Station Blackool 3-1/hus 2
2 1
Maintain Hot shutdown *** Time Start Motor and Turbine Driven Pump Dependent on Voltage 7.
Secondary Undervoltage 2/hus 2
2 0
N.A.
3846 17% volts for 5 15% min.
with inherent
^
time delay of U 12 sec.
SEE F001 NOTES ON PAGE 131b.
ENGINEERED SAFEGUARDS ACTUATION SYSTEM - LIMITING CONDITl0NS FOR OPERATION 07143 130a Amendment Nos. 97 and 87 0350A
PERNISSIVES Sehntl P-11 Pressurtrer' pressure (2/3) below 1915 psig allows w nual i
b1nck of safety injection attuation during a plant cooldown.
I'-12 Tavs (2/4) below 540*F allows manual bicck of !!)gh Steam Flow safety injecticn actuation if borated -to greater than cold shutdown conditions.
J S
4 1
5EE F00TNOTLS ON PAGE 131b.
ENGtMEERED SAFEGUARDS ACTUA110N SYSTEM - LIMillNG CONDITIONS FOR DPERATION AND SETPO!!
TASlE 3.4-1 (CONTINUED) 07020 Amendment Nos. 97 and 87 13T
.~
Thannel Description Devico Description V.
AU4tLIARY FEEDWATER s
1.
Manual i
NA 2.
Automal1C NA 3.
Steam Generator LC-5170, LC-5270, 1.0-5373, LC-547n Water level Low-low 10-5188, LC-$2HB, LC-5388, LC-54f*D LC-5198, LC-529R.1 C-5398,1 C-549H i
4.
Undervoltage - RCP Busses Unit i 44 7(KP)-142, 44 7(KP).-143, 447(KP)-14 4, 44 7(KF)-145 Start Turbine Driven Pump Unit il 447(KP)-242, 447(KP)-243, 447(KF)-244, 447(KP) 245 5.
SI Start Motor and See Section I of this Table.
]
Turbine Driven Pumps 6.
Station Blackout j
i a.
Start Motor Driven Pumps Unit I 427(CV-7)-142, 427(CV-7)-143, 427(CV-7)-144 Unit 11 427(CV-7)-242, 427(CV-7)-243, 427(CV-7)-244 b.
Start Turbine Driven Pumps Unit I 447(KP)-142, 447(KP)-143, 447(KP)-144, 447(KP)-145 i
Unit 11 44 7(KP)-242, 44 7(KP)-243, 447(KP)-244, 44 7(KP)-245 7.
Secondary Undervoltage Unit i 427-1(270)-147, 427-1(270)-148, 427-1(210)-149 Protection System 427-2(270)-147, 427-2(270)-148, 427-2(270)-149 Unit 11 427-1(270)-247, 427-1(270)-248, 427-1(270)-245 PERMISSIVES 427-2(270)-247, 427-2(27D)-240, 427-2(270)-249 j
P-11 Pressurizer pressure - PT-455, PT-456. PT-457 I
i P-12 Temperature - TE-411A, TE-4118, TE-421A, TE-4218 TE-431A, TE-4318. TE-441A, TE-4418 l
1 ENGINEERED SAFEGUARDS SYSTEM INSTRUMENT NUMBERS TABLE 3.4-2 (Continued) 0533t/0534t 133a Amendment Nos, 97 and 87 0098A m
ACTUATION CHANNEL CHANNEL-CHANNEL.
EHANNEL DESCRIPi10N
_ CHECK CALIBRATION FUNCTION TEST I V.-
STEAMLINE ISOLATION 1.
Manual Actuation N.A.
N.A.
R 2.
Automatic Actuation N.A, M.A.
M 3.
High-H1gh Containment Pressure See item 11 Above 4.
High Steam Line Flew in Coincidence with low-tow Tavg See Item i Above or low Steam Pressure V.
AUKILIARY FEIDWAT_LR, 1.
Manual N.A.
N.A.
R J
2.
Automatic N.A.
N.A.
M 3.
R Q
Water level Low-tow 4.
Undervoltage - RCP Busses M.A.
R R
S.
Safety injection See item I on Page 134 6.
Station Blackout N.A.
R R
l 7.
Secondary Undervoltage M
R R
PERMISSIVES 1.
P-11 N.A.
N.A.
Q 2.
P-12 N.A.
N.A.
Q
$ - Once per shift M - Once per month N.A. - Not applicable R - Once per refueling shutdown - tallbration of these instruments may be dnne as much as s1F months prior 10 the start of refueling outage and still satisfy this requirement.
ENGINEERED SAFEGUARDS SYSTEM TESilNG AND CAllBRATION REQUIREMENIS TABLE 4.4 (Continued) 0T140 135 Amendment Nos. 97 and 87
4 LIMITING CONDITION FOR OPERAT10M SURVEILLANCE REQUIREMENT 3.15.1.8 (continued) 4.15.1.8 3.
Refueling outage testing During each refueling outage a.
the diesel generators shall lie started and loaded under simulated LDCA and loss-of-Offsite power conditions, and run for a minimum of 5 minutes in each case, with ewergency loads.
J The proper diesel-generator starting and loading time, required bus load shedding, and sequential starting and operation of emergency equipment shaII be verified.
b.
During each refueling outage, the diesel generator shall be loaded to 4000 KW and held at this load for one hour after the diesel generator operating temperatures have stabilized.
c.
During each refueling outage, the tapabt11ty of the diesel generator to reject a load of 4000 KW shall be demonstrated.
This test need not be performed on the common diesel (0) if it was performed in conjunction with the previous refueling outage of the other unit.
07020 75R Amendment Nos. 97 and 87
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