ML20108C142
| ML20108C142 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley, Catawba |
| Issue date: | 05/01/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co |
| Shared Package | |
| ML20108C146 | List: |
| References | |
| DPR-66-A-199, NPF-73-A-081 NUDOCS 9605060194 | |
| Download: ML20108C142 (11) | |
Text
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's UNITED STATES t
S NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D.C. 20066-0001
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DUQUESNE LIGHT COMPANY l
.T OHIO EDISON COMPANY j
PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.199 4
License No. DPR-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated December 27, 1995, 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 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 chis 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 Commission'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 Commission's regulations and all applicable requirements have been satisfied.
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PDR ADOCK 05000334
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, 7~
and paragraph 2.C.(2) of Facility Operating License No. OPR-66 is hereby amended to read as follows:
(2) Technical Snecifications
)
TheTechnicalSpecifigAgionscontainedinAppendixA,asrevised l
through Amendment No.19, are hereby incorporated in the license.
1 The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days.
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FOR THE NUCLEAR REGULATORY COMMISSION i
h-John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical j
Specifications i
i Date of Issuance: May 1, 1996 i
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ATTACHMENT TO LICENSE AMENDMENT NO.I99 FACILITY OPERATING LICENSE NO. OPR-66 DOCKET NO. 50-334 Replace the following pages of Appendix A Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 3-50 3/4 3-50 3/4 3-51 3/4 3-51 3/4 3-52 3/4 3-52 m
4 DPR-66 INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION I
3.3.3.8 The accident monitoring instrumentation channels shown in Table 3.3-11 shall be OPERABLE.
l APPLICABILITY:
MODES 1, 2 and 3.
ACTIOH:
a.
With the number of OPERABLE accident monitoring i
instrumentation channels less than the Total Number of Channels shown in Table 3.3-11, either restore the l
inoperable channel (s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (follow Specification 3.4.11 when determining ACTIONS for Items 5 and 6).
I b.
With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERABLE requirements of Table 3.3-11, either restore the inoperable channel (s) 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 i
be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.8 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.
.1 BEAVER VALLEY - UNIT 1 3/4 3-50 Amendment No.199
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TABLE 3.3-11 DPR-66 ACCIDENT MONITORING INSTRUMENTATION 4
TOTAL NO.
MINIMUM CHANNELS QF_CMANNELS OPenmars 1.
Pressurizer Water Level 3
2 l
2.
Auxiliary Feedwater Flow Rate 1 per steam 1 per steam f
generator generator 3.
Reactor Coolant System Subcooling Margin Monitor 1
1 4.
Deleted l
f i
5.
PORV Limit Switch Position Indicator 1/ valve 0/ valve 6.
PORV Block Valve Limit Switch Position Indicator 1/ valve 0/ valve f
7.
Safety Valve Acoustical Detector Position Indicator 2/ valve
- 1/ valve 8.
Deleted l
i 9.
Containment Sump Wide Range Water Level 2
1 f
10.
Containment Wide-Range Pressure 2
0 11.
In-Core Thermocouples (Core-Exit Thermocouples) 4/ core 2/ core quadrant quadrant j
12.
Reactor Vessel Level Indicating System 1
1 One Detector Active, Second Detector Passive t
BEAVER VALLEY - UNIT 1 3/4 3-51 Amendment No.199 i
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TABLE 4.3-7 DPR-66 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS l
CHANNEL CHANNEL l
CHECK CALIBRATION i
i 1.
Pressurizer Water Level M
R N
2.
Auxiliary Feedwater Flow Rate S/U R
3.
Reactor Coolant System Subcooling Margin M
R 4.
Deleted l
5.
PORV Limit Switch Position Indicator M
R
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6.
PORV Block Valve Limit Switch Position Indicator M
R 7.
Safety Valve Acoustical' Detector Position Indicator M
R i
8.
Deleted l
9.
Deleted i
10.
Containment Sump Wide-Range Water Level M
R l
11.
Containment Wide-Range Pressure N/A R
12.
In-Core Thermocouples (Core-Exit Thermocouples)
M R
13.
Reactor Vessel Level Indicating System M
R i
(1)
Channel check to be performed in conjunction with Surveillance Requirement 4.7.1.2.c following an extended plant outage.
e BEAVER VALLEY - UNIT 1 3/4 3-52 Amendment No.199 y
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UNITED STATES s
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON. D.C. - aaat
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DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412, BEAVER VALLEY POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 License No. NPF-73 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated December 27, 1995, 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 conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 Commission'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 Commission's regulations and all applicable requirements have been satisfied.
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' 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. NPF-73 is hereby amended to read as follows:
(2) Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 81, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLC0 shall operate the facility in accordance with the Technical Specifications and the i
Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COP 941SSION, h & Y). $ & ~
[JohnF.Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of Issuance:
May 1, 1996
ca ATTACHMENT TO LICENSE AMENDMENT NO. 81 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 3-58 3/4 3-58 l
3/4 3-59 3/4 3-59 i
B 4
e NPF-73 TABLE 3.'3-11 ACCIDENT MONITORING INSTRUMENTATION MINIMUM TOTAL NO.
CHANNELS 1
INSTRUMENT OF CHANNELS OPERABLE ACTION 1.
Pressurizer Water Level 3
2 a, b 2.
Auxiliary Feedwater Flow Rate 2 per steam 1 per steam a, b generator generator 3.
1 c
Subcooling Margin Monitor 4.
PORV Limit Switch Position 1/ valva 0/ valve a, b Indicator 5.
PORV Block Valve Limit Switch 1/ valva 0/ valve a, b Position Indicator 6.
Safety Valve Position Indicator 1/ valve 0/ valve a, b 7.
Deleted l
8.
Containment Sump Wide Range 2
1 a, b Water Level 9.
Containment Wide-Range Pressure 2
1 a',
b 10.
Reactor Vessel Level Indication 2
1 a, b System 11.
Core Exit Thermocouples 4/ core 2/ cote a, b quadrant quadrant BEAVER VALLEY - UNIT 2 3/4 3-58 Amendment No. 81
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NPF-73 TABLE 4'3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEIr.rANCE REOUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.
Pressurizer Water Level M
R 2.
Auxiliary Feedwater Flow Rate S/U*
R 3.
Reactor Coolant Sydtem Subcooling M
R Margin Monitor 4.
PORV Limit Switch Position M
R Indicator 5.
PORV Block Valve Limit Switch M
R Position Indicator 6.
Safety Valve Position Indicator M
R 7.
Deleted l
8.
Containment Sump Wide-Range Water M
R Levei 9.
Containment Wide-Range Pressure N/A R
10.
Reactor Vessel Level Indication M
R System 11.
R Channel check to be performed in conjunction with Surveillance Requirement 4.7.1.2.b following an extended plant outage.
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'EAVER VALLEY - UNIT 2 3/4 3-59 Amendment No.8' i
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