ML20206D120
| ML20206D120 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/07/1988 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co |
| Shared Package | |
| ML20206D124 | List: |
| References | |
| DPR-66-A-132, NPF-73-A-008 NUDOCS 8811160546 | |
| Download: ML20206D120 (10) | |
Text
.
ouroc
'o UNITED STATES l ' g,q/[ gi NUCLEAR REGULATORY COMMISSION
~~
W-t WASHINGTON. D. C. 20555
'bo DUQUESNE LIGHT C0!!PANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 132 License No. OPR-66 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company, et al.
(tne licensee) dated June 22, 1988, 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 Cornmission's regulation: and all applicable requirements have been satisfied.
G911160546 G81107 POR ADOCK 05000334 P
[
L
- 2.
Accordingly, the license is amended by changes to the Techr.ical Specificatior s-as indicated in the attechment to this license amendment, and paragraph 2.C.(2) of Focility Operating License No. DPR-66 is hereby amended to read as follows:
(2) Technical Specifications l
The Technical Specifications contained in Appendix A, as revised i
through Arendment No.132, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the i
Technical Specifications.
3.
This license amendment is effective as of the date of issuance, to be implemented within 60 days of issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION Y
M 6n F. Stolz, Direct.
Project Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
Date of Issuance: November 7,1938 1
l l
ATTACHMENT TO LICENSE AMENDMENT NO. 132 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 c
Replace the following pages of Appendix A (Techn4. cal Specifications) with the enclosed page as indicated.
The revised page is identified by amendment number and contains a vertical line indicating the area of change.
Remove Insert 3/4 3-11 3/4 3-11 1
i h
1 i
1 l
TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUitENTATI0tl SURVEILLANCE REQUIREMENTS 5
Channel Modes in Which.
g Channel Channel Functional Surveillance
- p Functional Unit Check Ca1ibration Test Required 1.
Manual Reactor Trip N.A.
N.A.
S/U(1), R(10)
N.A.
N 2.
Power Range, Neutron Flux a.
High Setpoint S
D(2), M(3)
M 1, 2 c
and Q(6) ce c4 b.
Low Setpoint S
N.A.
S/U(1) 2 3.
Power Range, Neutron Flux, N.A.
R M
1, 2 High Positive Rate 4.
Power Range, Neutron Flux, N.A.
R M
1, 2 High Negative Rate S.
Intermediate Range, S
N.A.
S/U(1),
1, 2, 3*
o
}
Neutron Flux M(7) 4',
5*
6.
Source Range, Neutron Flux N.A.
N.A.
S/U(1),
2, 3
,4
[
(Below P-10)
M(8) and 5 7.
Overtemperature aT S
R M
1, 2 8.
Overpower AT S
R M
1, 2 5
9.
Pressurizer Pressure-Low S
R M
1, 2 10.
Pressurizer Pressure-High S
R M
1, 2 g
11.
Pressurizer Water Level-High S R
M 1, 2
[
12.
Loss of Flow-Single Loop S
R M
1 13.
Loss of Flow - Two Lrx)ps S
R N.A.
I
~
14.
Steam / Generator Water S
R M
1, 2
_g Level-Low-Low
/
'o UNivED STATE 3
[ '
",, [' gj NUCLEAR REGULATORY COMMISSION g
E WASHING TON, D. C. 20655 e
DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDI30N COMPAM DOCKET NO. 50-412 BEAVER VALLEY POWER STATION. UNIT NO. 2 AftENDMENT TO FACILITY OPEPATING LICENSE Amendment No. 8 License No. NPF-73 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company, et al.
(the licensee) dated June 22, 1988, complies with the standards and requiresnents 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 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.
The issuance of this amends,ent will not be inimical to the comon defense and security or to the health and safety of the public; and l
E.
The issuance of this amendment is in accordance with 10 CFR Port 51 of the Comission's regulations and all applicable requirements have been satisfied.
2-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license arrendtrent, and paragraph 2.C.(2) of Facility Operating License fio. NFF-73 is hereby amended to read as follows:
(2)
,T,e,c,h,n_i,c,a,1,,S.p_e ej f i c a t i o n s The Technical Specifications contained in Appendix A, as revised through Amendrent No. 8, and the Environmental Protection Flan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license.
DLCO shall operate the facility in at.cordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION D
j Q./
Jo 'z h lz, Directo
)./wr F. Sto Project Directorate I-Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 7,1938
/ '
ATTACHMENT TO LICENSE AftENDtiENT NO. 8 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 ReplacethefollowingpagesofAppendixA(TechnicalSpecifications) with the enclosed pages as indicated.
The revised pages are identified by anendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 1-22 3/4 1-22 3/4 3-6 3/4 3-6 3/4 3-10 3/4 3-10
~
REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM-SHUT 00WN LIMITING CONDITION FOR OPERATION 3.1.3.3 One digital rod position indicator (excluding demand position '.ndica-tion) shall be OPERABLE and capable of determining the control rod position within i 12 steps for eac5 shutdown or control rod not fully inserted.
APPLICAb nITY:
MODiS 3*#, 4*# and 5*#
ACTION:
With less than the above required digital rod position indicator (s) OPERABLE, l
open the reactor trip system breakers.
SURVEILLANCE REQUIREMENTS 4.1.3.3 Each of the above required digital rod position indicator (s) shall be determined to be OPERABLE by verifying that the digital rod position indicators agree with the demand position indicators within 12 steps when exercised ovar the full-range of rod travel at least once per 18 months.
'With the reactor trip system breakers in the closed position.
- See Special Test Exceptions Specification 3.10.5.
BEAVER VALLEY - UNIT 2 3/4 1-22 Amendment No. 8
TABLE 3.3-1 (Continued) b.
Above P-6 but below 5% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER, c.
Above 5% of RATED THERMAL POWER, POWER 0PERATION may continue.
ACTION 4 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
a.
Below P-6, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above P-6 setpoint and suspend positive reactivity operations.
b.
Above P-6, operation may continue.
ACTION 5 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or cpen the Reactor Trip System breakers, susper.d all operations involving positive reactivity changes and verify Valve 2CHS-91 is closed and secured in l
position within the next hour.
ACTION 6 -
This Action is not used.
ACTION 7 -
With the number of OPERABLE channels one less than the Total Number of Channels and with the THERMAL POWER level:
a.
Less than or equal to 5% of RATED THERMAL POWER, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; restore the inoperable channel to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after increasing THERMAL POWER above 5% of RATED THERMAL POWER; otherwise reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
l b.
Above 5% of RATED THERMAL POWER, place the inoperable I
channel in the tripped condition within I hour; operation may continue until performance of the next required CHANNEL FUNCTIONAL TEST.
ACTION 8 -
With the number of OPERABLE channels one less than the Total Number of Channels and with the THERMAL POWER level above P-9, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; operation may continue until performance of the next required CHANNEL FUNCTIONAL TEST ACTION 9 -
This ACTION is not used 1
BEAVER VALLEY - UNIT 2 3/4 3-6 Amendment No. 8
TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH N
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE h
Ft30TIONAL UNIT CHECK CALIBRATION TEST REQUIRED 1.
Manual Reactor Trip N.A.
N.A.
S/U(1),R(10) 1, 2, 3*, 4*, 5*
zU 2.
Power Range, Neutron Flux
~
a.
High Setpoint S
D(2),M(3)
M 1, 2 and Q(6) b.
Low Setpoint S
R S/U(1) 1(7),2 3.
Power Range, Neutron Flux, N.A.
R M
1, 2 g
High Positive Rate a
y 4.
Power Range, Neutron Flux, N.A.
R M
1, 2 g
High Negative Rate 5.
Intermediate Range, 5
R S/U(1),M(7) 1, 2, 3",
Neutron Flux 4*, 5*
G.
Source Range, Neutron Flux S
R S/U(1),M(8) 2,3,4 (Below P-10) and 5 7.
Overtemperature ai S
R M
1, 2 8.
Overpower AT S
R M
1, 2 5
9.
Pressurizer Pressure-Low S
R M
1, 2 y
(Above P-7)
A
- 10. Pressurizer Pressure-High S
R M
1, 2 5
i l
. - -