ML19345H632
| ML19345H632 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/14/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19345H633 | List: |
| References | |
| NUDOCS 8105210494 | |
| Download: ML19345H632 (13) | |
Text
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[1; UNITED STATES
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g NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20655 k..v /
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 28 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 (the licensee) dated July 30, 1980, 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 Commission's regulations; D.
The issuance of this anendment will not be inimical to the common defense and security or to the health and safety of the public; i
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.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. 28, are hereby incorporate t in the license. The licensee shall operate the faci'i.y in accordance with the Technical Specifications.
3.
This license amendment is effective within 3 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSI,0N Qf W
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Robert A. Clark, Chief Operating, Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 14, 1981 l
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 28 TO FACILITY OPERATING LICENSE NO. NPF-4 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.
Pages 3/4 3-33 3/4 6-37 i
I i
1 I
l TABl.E 4.3-2 (Continued) n 53 I
-g ENGINEERED SAFETY FEATlIRE ACTUATION SYSTEM INSTRUMENTATION SURVEll.l.ANCE REQUIREMENTS 3,
l E5is CllANNEL MODES IN WilICH CIIANNEL CHANNEL FUNCTIONAL SURVEILLANCE gj FUNCTIONAL UNIT CllECK CALIBRATION TEST REQUIRED Q
5.
TURBINE TRIP AND FEEDWATER g
ISOLATION a.
Steam Generator Water S
R H
j I,cvel--lii gh-liigh t
6.
AUXILIARY FEEDWATER PUMPS h$
a.
Steam Generat ur Water S
R H
1,2,3,4 l
i.evel--Low-Low o,
d2
')
h.
S.I.
See 1 above (all S.I. Surveillance Requirements) c.
Station Blackout N.A.
R N.A 1, 2, 3, 4 d.
Main Feedwater Pump Trip N. A..
N.A R
1, 2 7.
I.0SS OF POWER 4.16 KV Emergency Bus Eg a.
Loss of Voltage N.A.
R M(2) 1, 2, 3 l
$g h.
Degraded Voltage N.A.
R M(2) 1, 2, 3 l
4 0
M
CONTAINMENT SYSTEMS 5/4.6.5 SUBATMOSPHERIC PRESSURE CONTROL SYSTEM STEAM JET AIR EJECTOR LIMITING CONDITION FOR OPERATION 3.6.5.1 The inside and outside isolation valves in the steam jet air ejector suction line shall be closed.
J APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With the inside or outside isolation valve in the steam jet air ejector suction line not closed, restore the valve to the closed position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in 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 />.
SURVEILLANCE REQUIREMENTS 4.6.5.1.1 The steam jet air ejector suction line outside isolation valve shall be determined to be in the closed position by a visual inspection prior to increasing the Reactor Coolant System temperature above 200*F and at least once per 31 days thereafter if the valve is l
not locked, sealed or otherwise secured in the :losed position.
4.6.5.1.2 The steam jet air ejector suction line inside isolation valve shall be determined to be in the closed position prior to increas-ing the Reactor Coolant System temperature above 200*F.
NORTH ANNA-UNIT 1 3/4 6-37 Amendment No. 28 7- -,r+-+
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NUCLEAR '"GutATORY COMMISSION y pe(
3 waswincTom. o. c.20sss k' dN[j gg VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 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 (the licensee) dated July 30, 1980, complies with the standard; and requirements of the Atomic Energy Act of 1954, as amended (the Acc) 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.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications in paragraph 2.C.(2) of Facility Operating License No. NPF-7 and pagagraph 2.C.(2) is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 9
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(a) The written procedures required by Technical Specification 6.8.1 for the Technical Specifications listed below shall be implemented within 30 days after the date of this license:
4.3.2.1.3 Items 10 and 11 of Table 3.";-5 4.3.3.6 4.4.3.2.1 4.4.3.2.2 i
4.4.6.2.2 The required surveillance shall be completed before the end of the first surveillance interval.
(b) The end of the current surveillance period for the Surveillance t
Requirements listed below may be extended beyond the time limit specified by Technical Specification 4.0.2.a.
In each case, the required surveillance shall be completed by the revised due date.
After May 31, 1981 the plant shall not be operated in Modes 1,
- 2. 3, or 4 until the Surveillance Requirements listed below have been completed. Upon accomplishment of the surveillance, the provisions of Technical Specification 4.0.2.a shall apply.
Specification 4.8.2.3.2.d 4.8.2.4.2 3.
This license amendment is effective within 3 days from the date I
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of its issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION j
dk L
Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing Attachment.
J l
Changes to the Technical Specifications Date of Issuanca: Pay 14, 1981 l
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 9 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Appendix "A" Technical Specifications with the encloseo 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.
Pages 3/4 3-36 3/4 6-36 l
l
lAntE4.3-2(Continued}
ENGINEERED SAFETY FEATURE ACIUATION SYS1EM INSTRUMINTATION EU SURVEILLANCE REQUIREMGIS II CilANNEL MODES IN WillCil 5
CilANNEL CilANNEL TLMCTIONAL SURVEILLANCE I
FUNCTIONAL UNIT CilECK CAllBRATION 1EST REQUIRED i
4.
STEAM LIFE ISOLATION m
a.
Manual N.A.
N.A.
R 1,2,3 l
h.
Automatic Actuation Logic N.A.
N.A.
M(2) 1, 2, 3 c.
Containment Pressure--
S R
M(3) 1, 2, 3 l
Intermediate liigh-High R
M 1, 2, 3 d.
Steam flow in Two Steam 5
Lines--Iligh Coincident with T
-- Low-Low or Steam Line i
P9 Ensure--Low I
5.
TURBINE TRIP AND FEEDWATER ISOLATION Y
a.
Steam Generator Water S
R M
1, 2, 3 Level--liigh-liigh 6.
AUXILIARY FEEDWATER PUMPS 1
a.
Manual N.A.
N.A.
M(1) 1, 2, 3 h.
Automatic Actuation Logic N.A.
N.A.
M(2) 1, 2, 3 c.
Steam Generator Water S
R M
1,2,3 l
d.
S.I.
See 1 above (all S.I. Surveillance Requirements) e.
Station Blackout N.A.
R N.A.
1, 2, 3 I
f.
Main Feedwater Pump Trip N.A.
N.A.
R 1, 2 l
1 J
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_ _ =
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
I c.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laborato n analysis of represen-tative carbon sample obtained in accordance with Regulatory Posi_ tion C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Re' vision 2, March 1978.
d.
At least once per 18 months by:
1.
Verifying that the pressure drop across the HEPA filter and charcoal adsorber assembly is less than 8.5 inches Water Gauge while operating the filter train at a flow rate of 300 cfm i 10%.
e.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in place in accordance with ANSI N510-1975 while operating the system at.a flos.' rate of 300 cfm t 10%.
f.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 300 cfm 10%.
k 5
NOP.T-AN M - UN!T 2 3/4 6-35
CONTAINMENT SYSTEMS 3/4.6.5 SUBATMOSPHERIC PRESSURE CONTROL SYSTEM STEAM JET AIR EJECTOR LIMITING CONDITION FOR OPERATION 3.6.5.1 The inside and outside isolation valves in the steam jet air ejector suction line shall be closed.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With the inside or outside isolation valve in the steam jet air ejector suction line not closed, restore the valve to the closed position within I hour or be in 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 />.
SURVEILLANCE REQUIREMENTS l
4.6.5.1.1 The steam jet air ejector suction line outside isolation valve shall be determined to be in the closed position by a visual inspection prior to increasing the Reactor Coolant System temperature above 200*F and at least once per 31 days thereafter if the valve is not locked, sealed or otherwise secured in the closed position.
4.6.5.1.2 The steam jet air ejector suction line inside isolation valve shall be determined to be in the closed position prior to increasing the Reactor Coolant System temperature above 200*F.
l NORTH ANNA - UNIT 2 3/4 6-36 Amendment No. 9
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