ML20071N602
| ML20071N602 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/28/1994 |
| From: | Mccree V Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071N603 | List: |
| References | |
| NUDOCS 9408080068 | |
| Download: ML20071N602 (10) | |
Text
-
@QC8009 y.
1 UNITED STATES j,
,j NUCLEAR REGULATORY COMMISSION
~t WASHINGTON, D.C. 2055M001 49 * * * * *,o VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.185 License No. NPF-4 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 April 19, 1994, 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 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.
9400000068 940728 PDR ADOCK 05000338 p
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 Nc. NPF-4 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 185, are hereby incorporated in the license. The licensee shall operate the facility in accordanc.e 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 f LEAR REGULATORY COMMISSION Victor M. Mc ree Actir Project Directorhte IIJ g Director 2
DivisionofReacbrPrQects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 28, 1994
1 ATTACHMENT TO LICENSE AMENDMENT NO.185 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO 50-338 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated.
The revised page is identified by amendment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
Remove Page Insert Pace 3/4 1-19 3/4 1-19 i
l
REACTIVITY CONTROL SYSTEMS LB11TfNG CONDITION FOR OPERATION (Continued) b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and c) A power distribution map is obtained fmm the movable incom detectors and N
are verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or Fn(Z) andF3H d) Either the THERMAL POWER level is reduced to s 75% of RATED THERMAL POWER within one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip serpoint is reduced to 5 85% of RATED THERMAL POWER, or e) The remainder of the rods in the group with the inoperable rod are aligned to within t 12 steps of the inoperable rod within the hour while maintaining the thermal power, rod sequence, and insertion limits of Specification 3.1.3.6 during subsequent operation.
SURVEILLANCE REQUIREMENTS i
4.1.3.1.1 The position of each rod shall be determined to be within the group demand limit by l
verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Moniter is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4.1.3.1.2 Each rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 92 days.
l i
NORTH ANNA UNIT 1 3/4 1-19 Amendment No. 16.138,185, 1
f I
1 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL LENGTH R0D Rod Cluster Control Assembly Insertion l
Characteristics Rod Cluster Control Assembly Misalignment Loss of Reactor Coolant From Small Ruptured Pipes Or From Cracks In large Pipes Which Actuates The Emergency Core Cooling System Single Rod Cluster Control Assembly Withdrawal At Full Power Major Reactor Coolant System Pipe Rupture (Loss Of Coolant Accident)
Major Secondary System Pipe Rupture Rupture of a Control Rod Drive M2chanism Housing (Rod Cluster Control Assembly Ejection)
NORTH ANNA-UNIT 1 3/4 1-20 Amendment No.16
I p*"%g s
1 h
ft UNITED STATES
! I Dif j
NUCLEAR REGULATORY COMMISSION F
j WASHINGTON, D.C. 2055Mr;01 g
%) y 4
VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE 0CKET NO. 50-339 NORTH ANNA POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 166 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 April 19, 1994, 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 pplication, the provisions of the Act, and the rules and regulacions of the Commission; C.
There is reascnable 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; 0.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of :.he 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.
. 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 amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.166
, are hereby incorporated in the license.
The licensee shall operate the facility ia accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR TH LEAR REGULATORY COMMISSION Victor M. McCrt>, Ac ing Director Project Directorato 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 28, 1994 m
ATTACHMENT TO LICENSE AMENDMENT N0. 166 TO FACILITY OPERATING LICENSE N0. NPF-7 D0.CKET NO. 50-339 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page as indicated. The revised page is identified by amendment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
P Pemove Paag Insert Pagg 3/4 1-17 3/4 1-17
V 1
r.
b
/
REACITVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) i b) The SHUTDOWN MARGIN requimment of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and c) A powerdistgbution map is obtained from the movable incore detectors and Fn(Z) and Fg are verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or d) Either:
- 1) The THERMAL POWER levelis reduced to less than or equal to 75%
of RATED THERMAL POWER within one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip serpoint is reduced to less than or equal l
co 85% of RATED HIERMAL POWER, or
- 2) The remainder of the rods in the group with the inoperable rod are aligned to within 12 steps of the inoperable rod within the hour while maintaining the thermal power, rod sequence, and insertion limits of Specification 3.1.3.6 during subsequent operation.
l SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4.1.3.1.2 Each rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 92 days.
l i
i i
i l
NORTH ANNA - UNIT 2 3 f41-17 Amer.dment No. 4M.166, l
s 4
-r=
/
TABLE 3.1-1 i
ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE ROD i
Rod Cluster Control Assembly Insertion Characteristics Rod Cluster Centrol Assembly Misalignment Loss of Reactor Coolant From Small Ruptured Pipes Or From Cracks In Large Pipes Which Actuates The Emergency Core Cooling System Single Rod Cluster Control Assembly Withdrawal At Full Power j
Major Reactor Coolant System Pipe Rupture (Loss of Coolant Accident)
Major Secondary Pipe Rupture
)
Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection)
NORTH ANNA - UNIT 2 3/4 1-18
- - - -.