ML20216F115
| ML20216F115 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/14/1998 |
| From: | Kuo P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216F123 | List: |
| References | |
| NUDOCS 9804160422 | |
| Download: ML20216F115 (12) | |
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i UNITED STATES g
j NUCLEAR REGULATORY COMMISSION
%..... /g WASHINGTON. D.C. 3000H001 o
VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338
' NORTH ANNA' POWER STATION. UNIT NO. 1
~
AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 209 License No. NPF-4 l
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company l
et al.. (the licensee) dated February 3. 1998, 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 i
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:
l C.
There is reasonable assurance (1) that the activities authorized by this amendment can be c~onducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations:
I 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.
9804160422 980414 PDR ADOCK 05000338 P
i L L 2.
Accordingly, the license is amended.by changes to the; Technical Speci-fications-as indicated in the attachment to this license amendment. and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:
(2) Technical Snecifications The Technicalj Specifications contained in Appendices A and B. as revised through Amendment No. 209, are hereby incorporated in the license. 'The' licensee ^shall. operate the facility in 'accordarice ~
L
~
l with the Technical Specifications.
3.
This. license amendment is effective as of its date of issuance and shall
- be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 0-/
- [
\\
L T.' Kuo, Director Project Directorate 11-1 l
Division of Reactor. Projects - I/II-Office of Nuclear Reactor Regulation
Attachment:
-Changes to the. Technical Specifications l:
Date of-Issuance:
April 14,1998 L
4 I
l AHACHMENT TO LICENSE AMENDMENT NO. 209 TO FACILITY OPERATING LICENSE NO. NPF-4~
l DOCKET NO. 50-338 l-Replace the following pages of the Appendix "A" Technical Specifications with L
the enclosed pages'as' indicated ~. Tne revised ~pages are' identified by i
amendment number and contain vertical' lines indicating the areas of change.
l Overleaf page 3/4 3-3 is included for document completeness.
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TABLE 4 3-1 (Continued)
NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.
Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
(1)-
If not performed in previous 7 days.
(2)-
Heat balance oMy, akve 15% of RATED THERMAL POWER.
(3)-
Compare incore to excore axial offset above 15% of RATED THERMAL POWER.
Adjust channel if absolute difference 2: 3 percent.
(4)-
Manual ESF functional input check every 18 months.
(5) -
Each train or logic channel shall be tested at least every 62 dcys on a STAGGERED TEST BASIS.
(6)-
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7) -
The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the manual reactor trip function. The test shall also verify the operability of the Bypass Breaker Trip circuit (s).
(8)-
Local manual shunt trip the reactor trip bypass breaker immediately after placing the bypass breaker into service, but prior to commencing reactor trip system testing or reactor trip breaker maintenance.
(9) -
Automatic undervoltage trip.
(10)-
The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.
(11)-
Monthly Surveillance in Modes 3*,4* and 5* shall also include verification that Permissives P-6 and P-10 are in their required state for existing plant conditions by i
observation of the permissive annunciator window.
(12)-
Detector plateau curves shall be obtained and evaluated. The provisions of Specification 4.0.4 are not applicable for entry into Mode 2 or 1.
l 1
NORTH ANNA - UNIT 1 3/4 3-14 Amendment No. 81,306, 209
f* '*4 y
i UNITED STATES g
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30566-0001
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 190 License No. NPF-7 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al,, (the licensee) dated February 3, 1998, 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 l
of the Comission's regulations and all applicable requirements have been satisfied.
l
l,
l 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby i
amended to read as follows:
L (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 190. are hereby incorporated in the l
- license.' The licensee shall operate the facility'in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
l FOR THE NUCLEAR REGULATORY COMMISSION P.
T.
Kuo, Director-Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l
Attachment:
i Changes to the Tecnnical l
Specifications l
l Date of Issuance:
April 14,1998 l
L
L l
ATTACHMENT TO LICENSE AMENDMENT NO. 190
.TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339
~ Replace the following pages of the Appendix."A" Technical Specifications with the enclosed 'pages ~as~ indicited. 'The rsvised pages 'are~ identified by'
~
amendment number and contain vertical lines indicating the areas of change.
Overleaf page 3/4 3-3 is included for document completeness.
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TABLE 4.3-1(CONTINUED)
NOTATION With the reactor trip system breakers closed and the control rod drive system capcble of rod withdrawal.
Surveillance requirements for the manual ESF functional test of the safety injection input to the reactor trip breakers is suspended for the duration of Cycle 9 operation.
Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
(1)-
If not performed in previous 7. days.
' ~
(2) --
Heat balance only, abo' e 15% of; RATED THERMAL POWER. Adjust channel if v
absolute difference >2 percent.
(3)-
Compare incore to excore axial offset above 15 % of RATED THERMAL POWER.
Recalibrate if absolute difference it 3 percent.
(4) -
Manual ESF functionalinput check every 18 months.
(5)-
- Each train or logic channel shall be tested at least every 62 days on a STAGGER".:.D TEST BASIS.
(6)-
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7)-
Below the P-6, (Block of Source Range Reactor Trip) Setpoint.
(8)-
The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).
(9)-
Local manual shunt trip the reactor trip bypass breaker immediately after placing the bypass breaker into service, but prior to commencing reactor trip system testing or reactor trip breaker maintenance.
i (10)-
Automatic undervoltage trip.
. (11)-
The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.
(12)-
Monthly Surveillance in Modes 3*,4* and 5* shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.
(13)-
Detector plateau curves shall be obtained and evaluated. The provisions of Specification 4.0.4 are not applicable for entry into. Mode 2 or 1.
1 NORTH ANNA - UNIT 2 3/4 3-14 Amendment No. 450,4&t.190