ML20090D603
| ML20090D603 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/03/1992 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20090D606 | List: |
| References | |
| NUDOCS 9203060336 | |
| Download: ML20090D603 (6) | |
Text
,.
/pR Pf Cg]o, E'
h UNITED STATES 3#7
{c-
- c NUCLEAR REGULATORY COMMISSION o,
J WASHINoTON. D C 20S55 g[
ylRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ElFCTRIC COOPERATIVE DOCKET NO. 50-338 NOR~iH ANNA POWER STATION. UNIT NO. 1 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No.153 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 January 28, 1992, as supplemented February 27, 1992, complies with the standards cr.d 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.
I i
920306033S 920303 PDR ADOCK 05000338 PDR p
4-u
.c e-i l 2.
Accordingly, license condition 2.0.(1) to Facility Operating License NPF-4 is modified to read as follows:**
i (1) Maximum Power Level VEPC0 is authorized to operate the North Anna Power Station, Unit No.1, at reactor core power levels not in excess of 2893 megawatts (thermal).*
- The maximum reactor power level shall be limited to 2748 megawatts (thermal) which is 95% of RATED THERMAL POWER in accordance with the licensee's submittal dated January 28, 1992 (Serial No.92-042) for the period of operation until the steam generator replacement.
3.
In addition, 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 Specificat ions The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 153, are hereby incorporated in the license.
VEPC0 shall operate the facility in accordance with the Technical Specifications.
4.
This license amendment is effective as of its date of issuance.
FOR TlE NUCLEAR REGULATORY COMMISSION
[
rit.r ert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/II Of fice of Nuclear Reactor Regulation l
Attachments:
- 1. Page 4 of License
- 2. Changes to the Technical Specifications Date of Issuance:
1
- Page 4 is attached, for convenience, for the composite license to reflect this change.
l l
1
C,~,
?.- I (1) Maximum Power Level VEPC0 is authorized to operate the North Anna Power Station, Unit No.1, at reactor core power levels not in excess of 2893 megawatts (thermal)
- q (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 153, are hereby incorporated in the license.
VEPC0 shall operate the facility in accordance with the Technical Specifications.
(3) Additional Conditions The matte.'s specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the isseance of this amendment or within the operational restrictions indicated.
The removal of these conditions -shall be made by an amendment to the -
license supported by a favorable evaluation by the i
Commission:
4..
c.
Virginia Electric and Power Company shall not operate the reactor in operational modes 1 and 2 with less than three reactor coolant pumps in operation.
d.
VEPC0 may use two (2) fuel assemblies containing fuel rods clad with an advanced zirconium base alloy cladding material as described in the
-licensee's submittals dated February 20,-1987 and September 30, 1988.
F e.
If Virginia Electric and Power Company plans to remove or to make significant changes in the normal operation of equipment that controls the amount of radioactivity in effluents from the e
North t'na Station, the Commission shall be.
rot'f' O in writing regardless of whether the chany a'fects the amount of radioactivity in the t'f ants.
- The maximum reactor power level shall be limited to 2748 megawatts (thermal) which is 95% of RATED-THERMAL POWER in accordance with the licensee's submittal dated' January 28, 2992 (Serial iM.92-042) for the peried of operation until the steam generator replacement.
l Amendment No. 31, 49, 64, +44, 153
4 ATTACHMEN' To llCENSE AMENDMENT NO. 153 TO FAfillTY 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 complettness.
[
Bemove Pgag Jnsert Pang 3/4 5-3 3/4 5-3 T
+
+
l e,v v~,- e r r w, 0,- w rv.-.niv., a n,r --,,,,- re.,, - w,v,.w,,,,,,, -,,m-w-- -,v en -n,n.n w.
,e.
_ en,,,
,,,,.-v r,m r,,w-r wnn, rw w,, r.,- w,-
t 4
DAERGEtCYCORE COOLtJG SYSTEMS ECCS LdBSYSTEMS. Tava 2 350:F U'alTING CONDITION FOR OPERATION r
3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of:
a.
One OPERABLE centrifugal charging pump, b.
One OPERABLE low t.ead safety injection pump, c.
An OPERABLE flow path capab'e of transferring fluid to the Reactor Coolant System when taking suction from the refueling v.ater storage tank on a safety injection signal or from the containment sump witen suction is transferred during the recirculation phase of ope-ration or frcm the discharge of the outside recircuir on spray pump.
APPLICABILITY:
MODES 1,2 and 3.
ACTION:
a.
With one ECCS subsystein inoperable, reestore the inoperable subsystem to OPERABLE status with;n 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 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 />.
l b.
b the event the ECCS is a:tuated and injects water into the Reactor Coolant System, a Special Report sha!! be prepared and submitted to the Commission pursuant to Specification 6 9 2 within 90 days describing the circumstances of the actuation and the totat 3::umulated actuation cycles to date.
l c.
The provi3:ons of Specifications 3.0.4 are not applicable to 3.5.2.a and 3.5.2.b for one hour following heatup above 324'F or prior to cooldown below 324*F.
Adherence to ACTION "a* shall require the following equipment OPER ABILITY for the period of operation until steam generator replacement:
With one low head safety injection pump inoperable, two centrifugal charging pumps (one in ea:h subsystem) and their associated flow paths shall be OPEr.ABLE or be in HOT ST ANDSY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and be in HOT SHL PDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> NORTH ANNA UNIT 1 34 53 Amendment No. 3,7f, 177,153 4
O EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall te demonstrated OPERABLE:
a.
't least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the followirg valves are in the indicated po31tions with power to the valvt operators removed:
Valve Number Valve Function Valve position
- a. MOV-1890A
- a. LHS1 to hot leg
- a. closed
- b. MOV-1890B
- b. LHS! to not leg
- b. closed
- c. MOV-1836
- c. Ch pump to cold leg
- c. Closed
- d. MOV-1869A
- d. Ch pump to hot leg
- d. closed
- e. MOV-1869B
- e. Cb pump to hot leg
- e. closed b.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, ir. in its correct position.
c.
By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 1
2.
Of the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
1.
A visual inspection of the containment sump ard verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structurTl distress or corrosion.
e.
At least once per 18 months, during shutdown, by:
1.
Verifying that each automatic valve in the flow cath actuates to its correct position on a safety injection test signal.
NORTH ant:A-UNIT 1 3/4 5-4
..