ML20076N579
| ML20076N579 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 04/30/1991 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076N581 | List: |
| References | |
| GL-89-19, NUDOCS 9105080140 | |
| Download: ML20076N579 (12) | |
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' UNITED STATES.
g NUCLEAR REGULATORY _ COMMISSION 5>
5 fj' WASHINGTON, D C,20655 1,..;./
o NORTHERN STATES' POWER COMPANY DOCKET'NO.-50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT N0. 1 i
' AMENDMENT TO FACILITY OPERATING LICENSE n
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Amendment No. 95 License No. DPR 11 The N'uclear Regulatory Commission (the Commission) has found that:
-j A.
The; application for amendment by Northern States Power Company
-(thelicensee)datedDecember 26, 1990, complies with the.
' standards and requirements of the Atomic Energy Act of 1954, as amended (the. Act).. and-the' Commission's rules-and regula-
' tions. set'=forth in 10 CFR Chapter I; s
B.
The facility-will operate in conformity with the application, the provisions 1of the Act, and-the rules and regulations of the Commission;
-C.
There is reasonable assurance'(1):that the activities authorized bytthis-amendment can be conducted without endangering the. health
- and safetyiof-the public, and (ii) that such activities will'be
~
2 Jconducted in: compliance with the Commission'.s regulations;--
I?
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 Commission's regulations and all applicable requirements have.
=been satisfied.
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-2.
Accordingly, the. license is amended-by changes to tne-Technical Specifications 1as' indicated in the attachment to this license amendment,.the paragraph '
l-
. 2.C.(2) of Facility Operating LMense No. DPR-42 :is-hereby amended to read
'as follows:
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9105080140 910430 ADOCK0500g2 DR
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i Technical Specifications-d
'The' Technical: Specifications l contained in Appendix A, as revised through Amendment'No. 95, are hereby incorporated in the= license. The licensee shallioperate the facility in accordance with the Technical Specifications.
3..tThis license'. amendment isteffective as of its-date of issuance.-
FOR THE NUCLEAR REGULATORY COMMISSION j
b$? w N
f L. B.-Marsh Director-W<
Project-Directorate 111-1 '
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. Division of Reactor. Projects III/IV/V-
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Office of Nuclear Reactor: Regulation-J
Attachment:
. Changes to the Technical; l
-Specifications-4
- Date of; Issuance'
- April 30, -i1991 f.
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. UNITED STATES -
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-NUCLEAR-REGULATORY COMMISSION
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. WASHINGTON, D. C. 20555 '
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NORTHERN STATES POWER COMPANY
'0OCKET NO. 50-306
- PRAIRIE' ISLAND NUCLEAR GENERATING PLANT, UNIT NO. 2 l
-AMENDMENT TO FACILITY OPERATING LICENSE l
y Amendment No. 88 License No. DPR-60 1a
- 1. :The Nuclear Regulatory Commission-(the Commission) has found that:
.A.
The application-for amendment by_ Northern States Power Company (the licensee) dated December;26, 1990 complies With the standards and requirements of'the Atomic Energy Act of 1954', as amended (the Act).,
m Land the Commission's rules and regulations set forth in 10 CFR-Chapter.I;.
j
'B.. cThe facility will operate in ionformity with the application, the provisions of the Act, ant the rules and regulations of cthe Commission; y
1
-C.
There is reasonable assurance _(1) that the activities authorized 4
by this amendment can be-conducted without endangaring the health and safety of the'.public, and:(ii) that such activities will be 3
Lconducted in' compliance with the_ Commission's regulations; D.c The issuance ofLthis amendment willEnot be inimical to the-common; defense and security or to the health and safety--of the public; and
. 'z'
-E.
The' issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and alll applicable requirements have.
been satisifed.
'l 2.- Accordingly, the license is amended by changes to the Technical Specifica-
- tior.s
- as indicated in the attachment to this license amendment, and paragraph' t
'2.C.(2) of Facility Operating. License No. DPR-60 is..hereby amended:to read' as follows:
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Technical Specifications
.l The Technical Specifications contained in: Appendix A, as revised
.l through Amendment No. 88, are hereby incorporaied in the license.
The licensee shall operate the facility in accordance with the Technical: Specifications.
.l
,3. -This license amendment is effective as of its date of issuance.
t-7 FOR THE NUCLEAR REGULATORY COMMISSION
'l M L. B. Marsh, Cirector Project Directorate ~III-1 1
Division of' Reactor Projects III/IV/V Office of Nuclear Reactor Regulation L
Attachment:
Changes:-to the Technical.
-Specifications 4
-Date.of. Issuance:! April 30, 1991 4
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l ATTACHMENT TO LICENSE AMENDMENT NO. 95-FACILITY OPERATING LICENSE NO. DPR-42
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DOCKET NO. 50-282 Revise' Appendix A. Technical = Specifications by removing the pages identified below-and inserting the-. attached pages. The revised pages are identified by amendment number and contain. marginal. lines indicating the area of change.
REMOVE INSERT i
Table!TS.3,5-4 Table 4 TS.3.5-4(Page1of2)
- Tablets.3.5-4(Page.2of.2)
Table TS.4'.1-1 (Page 2 of 5)
Table TS.4.1-1 (Page 2 of 5) s 1
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.x-TABLE TS.3.5-4 (Page 1 of. 2)
' INSTRUMENT OPERATINC ' CONDITIONS FOR ISOIATION FUNCTIONS l'
2-3 4
MINIMUM MINIMUM PERMISSIBLE OPERATOR ACTION IF OPERABLE DEGREE OF BYPASS-CONDITIONS OF COLUMN FUNCTIONAL UNIT CIIANNELS REDUNDANCY CONDITIONS
.1 OR 2 CANNOT BE MET' 1.
CONTAINMENT ISOIATION a.
Safety Injection (See Item No. 11of Table TS.3.5-3)
Hot Shutdown **
b Manual 2
1 Hot Shutdown
- 2,.
CONTAINMENT VENTIIATION ISOIATION a.
Safety Injection '
(See Item No. 1 of Table TS.3.5-3)
Maintain Purge _and Inservice Purge Valves closed if (1) conditions b.
High Radiation in Exhaust Air 2
1 of a, b, or' c cannot be met above COLD SHUTDOWN or (2)'if conditions-c.
Manual 2
1 of b or e cannot be met during fuel handling in. containment.-
3.
STEAM LINE IS01ATION a.
Hi-Hi Steam Flow with Safety 2/ loop 1
Hot Shutdown **
Inj ection t
b.
Hi " team Flow and 2 of 4 Low -T 2/ loop 1
Hot Shutdown **
y wit. Safety Injection aa55 c.
Hi Contairv.aent Pressure 2
1 Hot Shutdown **
S $-
.- a d.
Manual 1/ loop Hot Shutdown **
oI'
%y 4.
EMERCENCY COOLDOWN EQUIPMENT ROOM OY ISOIATION a.
liigh temperature in ventilation 2
1 Hot Shutdown **
system ducts i
- If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, steps shall be taken on the affected unit to place the-unit in cdIE SIIUTDOWN conditions.~
dPRAIRIE ISLAND UNIT 1 AMENDMENT NO. 46, 70, 9f, 95
e TABLE TS.3.5-4 (Page 2 of 2)
INSTRUMEttr OPERATING CONDITIONS FOR ISOIATION MJNCTIONS 1
2 3
4 MINIMUM MINIMUM PERMISSIBLE OPERATOR ACTION IF.
OPERABLE DEGREE OF BYPASS CONDITIONS OF COLUMN CilANNELS REDUNDANCY CONDITIONS 1 OR 2 CANNOT BE MET FUNCTIONAL UNIT 5.
FEEDWATER ISOIATION Hot Shutdown **
Hi I:1 Steam Generator Level 2
1 a.
b.
Safety Injection (See Item No. 1 of Table TS.3.5-3)
Hot Shutdown **
Hot Shutdown **
2 1
c.
Reactor Trip with 2 of 4 Low Tm (Main Valves only)
QY aF e en h) H o."
- If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, steps shall be taken on the affected unit to place the unit in COLD SIRITDOWN conditions.
OY i
n PRAIRIE ISLAND UNIT 1
~ AMENDMENT NO. 95
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TABLE TS.4.1-1 (Page 2 of 5) a MINIMUM FREOUENCIES FOR CHECKS. CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Functional
Response
Channel Description Check Calibrate Test Test Remarks 9.
Analog Rod Position S(1)
R T(2)
NA
- 1) With atep counters
- 2) Rod Position Deviation Monitor M(2)
Tested by updating computer bank count and comparing with analog rod position test signal 10.
Rod Position Bank S(1,2)
NA T(3)
NA
- 1) With analog rod position
- 2) Following rod motion in excess of M(3) six inches when the computer is l
Counters l
out of service
- 3) Control rod banks insertion limit monitor and control rod position deviation monitors lla. Steam Generator Low Level S
R H
NA 11b. Steam Generator High Level S
R H
NA 12.
Steam Flow S
R M
NA S
R NA NA 13.
Charging Flow 14 Residual Feat Removal S(1)
R NA NA
- 1) When in operation Pump Flow 15.
Boric Acid Tank Level D
R(1)
M(1)
NA
- 1) Transfer logic to Refueling Water Storage Tank 9Y 16.
Refueling Water Storage W
R M(1)
NA
- 1) Functional test can be performed by bleeding transmitter Tank Level "Y
.O eo 17.
Volume Control Tank S
R NA NA
<.n ' -
h 18a. Containment Pressure S
R M(1)
NA Vide Range Containment Pressure
- 1) Isolation Valve Signal SI Signal 18b. Containment Pressure S
R H
NA Narrow Range Containment Pressure Steam Line Isolation.
PRAIRIE ISLAND UNIT 1
'l AMENDMENT NO. 39, 6f, 75, 87, 95
t ATTACHMENT TO-LICENSE AMENDMENT NO. Aq l
FACILITY OPERATING LICENSE NO. DPR-60 DOCKET NO. 50-306 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
-REMOVE INSERT Table TS.3.5-4 Table TS.3.5-4 (Page 1 of 2 Table TS.3.5-4 (Page 2 of'2 Table TS.4.1-1 (Page 2 of 5)
Table TS.4.1-1 (Page 2 of 5
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TABLE TS.3.5-4:(Page11 of 2)
INSTRUMENT OPERATING CONDITIONS FOR ISOLATION FUNCTIONS 1
3' 4
MINIMUM MINIMUM PERMISSIBLE OPERATOR ACTION IF I
. OPERABLE.
DEGREE OF BYPASS CONDITIONS OF COLUMN FUNCTIONAL UNIT CILANNELS REDUNDANCY-CONDITIONS 1 OR 2 CANNOT BE ME' 1.
CONTAINMENT ISOIATION a.
Safety Injection (See Item No. 1lof Table TS.3.5-3)
Hot Shutdown **
I-b.
Manual 2
1 Hot Shutdown 2.
CONTAINMENT VENTIIATION ISOIATION a.
Safety Injection (See Item No. 1 of Table TS.3.5-3)
Maintain Purge and Inservice Purgei Valves closed if (1) conditions of a, b, or c cannot be set above -
b.
High Radiation in Exhaust Air
'2' 1
COID SHUTDOWN or (2) if conditions c.
Manual
'2 1
of b or e cannot be met during fuel handling in containment.
i 3.
STEAM LINE ISOIATION a.
Hi-Hi Steam Flow with. Safety.
2/ loop 1
Hot Shutdown **
Injection b.
Hl Steam Flow and 2 of 4 Low T, 2/ loop 1
Hot Shutdown **
with Safety Injection
-s ED c.
Hi Containment Pressure 2
1 Hot Shutdown **
5M
-.4 i
d.
Manual 1/ loop Hot Shutdown **
o 4
EMERGENCY COOLDOWN EQUIPMENT-ROOM
@[
IS01ATION
'High temperature.in ventilation-2 1-Hot Shutdown **
{
a.
system ducts-
- If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, steps shall be taken on the affected unit to place the unit in COLD SHUTDOWN conditions.
PRAIRIE ISLAND UNIT 2'
-AMENDMENT NO. 40, 64, 84, 88
~.-
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j TABLE TS.3.5-4 (Page 2 of 2)
INSTRUMENT. OPERATING CONDITIONS FOR ISOIATION FUNCTIONS 1
2 3
4 MINIMUM MINIMUM PERMISSIBLE OPERATOR ACTION IF OPEFABLE DEGREE OF BYPASS CONDITIONS OF COLUMN
-__ONDITIONS 1 OR 2 CANNOT BE MET C
FUNCTIONAL. UNIT CHANNELS RED 0NDANCY 5.
FEEDUATER ISOIATION Hi Hi Steam Generator 14 vel 2
1 Hot Shutdown **
a.
b.
Safety Injection (See Item No. 1 of Table TS.3.~.-3)
Hot Shutdown **
c.
1 Hot Shutdown **
with 2 of 4 low T m (Main Valves only) 1 5
4 5G we oF f*If minimum conditions;are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, steps shall be taken on the affected unit to place the
- P unit in COID SHUTDOWN conditions.
" Y.
PRAIRIE ISLAND UNIT 2 AMENDMENT NO. 88 l
l
s, a TABLE TS.4.1-1 (Pege 2 of 5)
MINIt'UM FREOUENCIES FOR' CHECKS. CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Functional.. Res'ponse '
Description Check Calibrate-Test
' Test Remarks 9.
Analog Rod Position S(1)
R T(2)
NA
- 1) With step counters M(2)
- 2) Rod Position Deviation Monitor Tested by updating computer bank count and. comparing with analog-rod position test signal 10.
Rod Position Bank S(1,2)
NA-T(3)
NA
- 1) With analog rod position Counters-M(3)
- 2) Following rod motion in excess of -
six inches when the computer is out of service
- 3) Control rod banks insertion limit monitor and control-rod position deviation monitors lla. Steam Generator low Imvel S
R M
NA lib. Steam Generator High Level S
R M
NA
.12. Steam Flow S
R M
NA 13.
Charging Flow S
R NA NA 14 Residual Heat Removal
'S(1)
R NA NA
- 1) When in operation Pump Flow 15.
Boric' Acid Tank Level' D
R(1) 11( 1 )
NA
- 1) Trans'er logic to Refueling Water Storage Tank Q l-
.i 16.
Refueling Water Storage W
R M(1)
NA
- 1) Ftmetional test can be performed 55 E Tank Level by bleeding transmitter wg.
17.
Volume Control Tank S
R NA NA P *-
18a. Containment Pressure' S
R M(1)
NA Vide Range Containment. Pressure SI Signal
- 1) Isolation Valve Signal 18b. Containment Pressure S
R-M-
NA Narrow Range Containment Pressure Steam Line Isciation PRAIRIE ISLAND UNIT 2.
l NIENDMENT NO. 33, 55, 68,80, 88
,.