ML20057D570
| ML20057D570 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/23/1993 |
| From: | Berkow M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057D571 | List: |
| References | |
| NUDOCS 9310040388 | |
| Download: ML20057D570 (11) | |
Text
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To UNITED STATES
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NUCLEAR REGULATORY COMMISSION
's WASHINGTON. D.C. 20555-0001
- %'..... at VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET N0. 50-338 NORTH ANNA POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.175 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 27, 1990, as supplemented by letters dated December 21, 1990 and March 29, 1993, 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.
1 9310040388 930923 PDR ADOCK 05000338 P
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 Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 175, are hereby incorporated in the 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.
FOR THE NUCLEAR REGULATORY COMMISSION
/
erbert N. Ber ow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 23, 1993 f
-J
ATTACHMENT TO LICENSE AMENDMENT NO.175 TO FACILITY OPERATING LICENSE NO. NPF-4 i
DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Paoes Insert Paoes 3/4 7-26 3/4 7-26 3/4 7-27 3/4 7-27 P
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i
Pl>NT SYST9AS 3/4.7.9 RESIDUAL HEAT REMOVAL SYSTEM - (RHR) l OPERATN3 l
UMmNG CONDmON FOR OPERATION 3.7.9.1 Two RHR subsystems shall be OPERABLE.
l APPUCABfUTY: MODES 1,2 and 3.
ACTION With one RHR subsystem inoperable, restore the Inoperable subsystem to OPERABLE l status within 7 days or be in HOT SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILIANCE REQUIREMENTS 4.7.9.1 Each RHR subsystem shall be demonstrated OPERABLE by:
- a. Verifying isolation of the RHR system prior to the Reactor Coolant System pressure exceeding 500 psig by closing and de-energizing both remote opetated RHR suction isolation valves and locking the associated breakers,
- b. At least once per 18 months, during shutdown,
- 1. Cyclino each, remote or automatically operated valve in the subsystem flowpath through one complete cycle of full travel.
NORTH ANNA-UNIT 1 3/4 7-26 Amendment No. 175
PUWT SYSTEMS RFRIDUAL HEAT RFMOVAL SYSTEM -(RHR) l S==
1 UMfTING CONDmON FOR OPERATON 3.7.9.2 As a minimum, one RHR subsystem shall be OPERABLE.
l APPLICABILITY MODES 4 and 5.
?
ACTON-With no RHR subsystem OPERABLE, immediately restore at least one RHR subsystem to OPERABLE status or maintain the Reactor Coolant System Tavg less than 350'F by use of alternate heat removal methods. The provisions of Specification 3.0.3,3.0.4 i
and 4.0.4 are not applicable.
j SURVEll1ANCf REOUIREMENTS
~
4.7.9.2 The required RHR subsystem shall be demonstrated OPERABLE by:
- a. Verifying isolation of the RHR system prior to the Reactor Coolant System pressure exceeding 500 psig by closing and de-energizing both remote operated RHR suction isolation valves and locking the associated breakers.
- b. At least once per 31 days:
- 1. Cycling each testable, remote or automatically operated valve in the subsystem flowpath through at least one mmplete cycle, and i
- 2. Verifying the correct position of each manual valve in the subsystem flowpath, not locked, sealed or otherwise secured in position, and
- 3. Verifying the correct position of each remote or automatically operated valve in the subsystem flowpath.
- c. At least once per 18 months:
- 1. Cycling eacn, remote or automatically operated valve in the subsystem flowpath through one complete cycle of full travel.
l NORTH ANNA-UNIT 1 3/4 7-27 Amendment No. 3, 175 1
PLANT SYSTEMS 3/4.7.10 SNUBBERS LIMITING CONDITIONS FOR OPERATION 3.7.10 All snubbers utilized on safety related systems shall be OPERABLE. For those snubbers utilized on non-safety related systems, each snubber shall beOPERABLE if a failure of that snubber or the failure of the non-safety related system would have an adverse effect on any safety related system.
APPLICABILITY:
MODES 1,2,3 and 4.
(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.10.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.10 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
NOTE: As used in this specification," type of snubber" shall mean snubbers of the same design and manufacturer, irrespective of capacity,
- a. Visual Insoection Snubbers are categorized as accessible or inaccessible during reactor operation. Each of the categories (accessible and inaccessible) may be inspected independently according to the schedule determined by the following table and the visual inspection interval for each type of snubber shall be determined based upon the criteria provided in that table.
NORTH ANNA-UNIT 1 3/4 7-28 Amendment No. 7;,77,144,
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y UNITED STATES i
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.j NUCLEAR REGULATORY COMMISSION i
's WASHINGTON. D.C. 20555-0001 s,..... si i
VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 i
NORTH ANNA POWER STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 156 License No. NPF-7 i
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 27, 1990, as supplemented by r
letters dated December 21, 1990 and March 29, 1993, _ 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 i
provisions of the Act, and the rules and regulations of the Commission-i 1
C.
There is reasonable assurance (i) that the activities authorized by l
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 i
defense and security or to the health and sai +.y 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.
s.
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I
. 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 amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.156, are hereby incorporated in the 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.
FOR TAIE NUCLEAR REGULATORY COMMISSION
~
' 'er ert N. Berk w, irector
. Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 23, 1993
i ATTACHMENT TO LICENSE AMENDMENT NO.156 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 indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Paaes Insert Paaes 3/4 7-23 3/4 7-23 3/4 7-24 3/4 7-24
Pt. ANT N i
I 3/4.7.9 RESIDUAL HEAT REMOVAL SYSTEM -(RHR) l OPER M l
j f'
UMmNG CONDmON FOR OPERATION 3.7.9.1 Two RHR subsystems shall be OPERABLE.
l APPLICABILITY: MODES 1,2 and 3.
ACTK)N With one RHR subsystem inoperable, restore the inoperable subsystem to OPERABLE l status within 7 days or be in HOT SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEfLLANCE REQUIREMENTS 4.7.9.1 Each RHR subsystem shall be demonstrated OPERABLE by:
- a. Verifying isolation of the RHR system prior to the Reactor Coolant System pressure exceeding 500 psig by closing and de-energizing both remote operated RHR suction isolation vakes and locking the associated breakers.
- b. At least once per 18 months, during shutdown,
- 1. Cycling each, remote or automatically operated vane in the subsystem flowpath through one complete cycle of full travel.
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- )
NORTH ANNA-UNIT 2 3/4 7-23 Amendment No. 156
etmrusrae RESIDUAL HEAT REMOVAL SYSTEM -(RHR) l SHUMM l
j UMmNG CONDmON FOR OPERATION 3.7.9.2 As a minimum, one RHR subsystem shall be OPERABLE.
l APPLICABILITY: MODES 4 and 5.
ACTON With no RHR subsystem OPERABLE,immediately restore at least one RHR subsystem to OPERABLE status or maintain the Reactor Coolant System Tavg less than 350'F by use of alternate heat removal methods. The provisions of Specification 3.0.3,3.0.4 I
and 4.0.4 are not applicable.
l SURVEILLANCE REOUIREMENTS 4.7.9.2 The required RHR subsystem shall be demonstrated OPERABLE by:
- a. Verifying isolation of the RHR system prior to the Reactor Coolant System pressure exceeding 500 psig by closing and de-energizing both remote operated RHR suction isolation valves and locking the associated breakers.
- b. At least once per 31 days:
- 1. Cycling each testable, remote or automatically operated valve in the subsystem flowpath through at least one complete cycle, and j
1
- 2. Verifying the correct position of each manual valve in the subsystem flowpath, i
not locked, sealed or otherwise secured in position, and i
- 3. Verifying the correct position of each remote or automatically operated vaive in the subsystem flowpath,
- c. At least once per 18 months:
- 1. Cycling each, remote or automatically operated vaive in the subsystem flowpath through one complete cycle of full travel.
i NORTH ANNA UNIT 2 3/4 7-24 Amendment No. 156
.