ML20209H157
| ML20209H157 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/21/1987 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power & Light Co |
| Shared Package | |
| ML20209H162 | List: |
| References | |
| DPR-66-A-108 NUDOCS 8705010160 | |
| Download: ML20209H157 (5) | |
Text
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION y
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DUOVESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 REAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.108 License No. DPR-66
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1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated July 25, 1986 (Change Request No. 175) 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 confonnity 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 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 ifcense amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:
$0UkOON 50 4
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1 (2) Technical Specifications i.
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The Technical Specifications contained in Appendix A, as revised throuch Amendment No.108, are hereby 7
j incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amendment is effective on issuance, to be implemented no later than 30 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jeh
. Stolz, Dire Dr ject Directorate
-4 Hvision of Reactor Projects-I/II
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Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 21, 1987 4
4
ATTACHMENT TO LICENSE AMENDMENT AMENDF.ENT NO.108 TO FACILITY OPFPATING LICENSE NO. OPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:
Remove Pages Insert Pages 3/d 3-18 3/4 3-18 3/4 3-31 3/4 3-31
e, TABLE 3.3-3 (Continued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION N
N MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION E
4.
STEAM LINE ISOLATION M
I a.
Manual 2/ steam line 1/ steam line
~ 2/ operating 1, 2, 3 18 l
steam line c:ar i
rt b.
Automatic 2
1 2
1,2,3 13 i
v.
Actuation Logic c.
Containment Pressure 3
2 3
1,2,3 14 Intermediate-High-High w
d.
Low Steamline Pressure 32 (Loop Stop Valves open) wj, Three Loops Operating 3/ loop 2/ loop 2/ loop 1, 2, 3#
14 ao Any loop Any loop Two Loops Operating 3/ loop 2/ loop any 2/any 1, 2, 3#
15 operating operating loop loop l
e.
High Steam Pressure 3/ loop 2/ loop 2/ operating 3##
37 l
l j"
l g
Rate any loop loop I
EI e
=
c.
L 9*
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e, TABLE 4.3-2 (Centinued)
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION y
SURVEILLANCE REQUIREMENTS o
CHANNEL MODES IN WHICH 1
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE j
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED Dwy 4.
STEAM LINE ISOLATION i
a.
Manual N/A N/A
,M(1) 1, 2, 3 l
D b.
Automatic Actuation Logic N/A N/A M(2) 1, 2, 3 l
C r
rt c.
Containment Pressure--
S R
H 1,2,3 r
Intermediate-High-High d.
Steamline Pressure--Low S
R H
1, 2, 3 e.
Steamline Pressure Rate-High S
R H
1, 2, 3 l
w S.
)
ISOLATION j
\\
u 8
a.
Steam Generator Water S
R H
1, 2, 3 U
Level--Migh-High 6.
LOSS OF POWER j
a.
4.16kv Emergency Bus N/A R
H 1,2,3,4 Undervoltage (Loss of Voltage) Trip Feed &
T Start Diesel j
i b.
4.16kv and 480v Emergency N/A R
H 1,2,3,4 i
Bus Undervoltage (Degraded Voltage) 5 L
%d e
9"
.