ML20050C955
| ML20050C955 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/15/1982 |
| From: | Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.F.2, TASK-TM 183, NUDOCS 8204090447 | |
| Download: ML20050C955 (5) | |
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VIHOINIA NIECTHIC AND POWISH COMPANY CIjpg H ICIIMOND, VIHOINIA 20 2G1
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N Mr. Harold R. Denton, Director Serial No. 183 Office of Nuclear Reactor Regulation N0/ Jill:acm Attn:
Mr. Robert A. Clark, Chief Docket No.~50-339 Operating Reactors Branch No. 3 License No. NPF-7 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Centlemen:
AMENDMENT TO OPERATING LICENSE NPF-7 NORTil ANNA POWER STATION UNIT NO. 2 PROPOSED OPERATING LICENSE AMENDMENT Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests an amendment to Operating License NPF-7 for North Anna Power Station Unit No. 2.
The proposed change to the Operating License is enclosed.
Paragraph 2.C(21)(j) of the North Anna Unit 2 Operating License requires that Vepco shall install and demonstrate the operability of additional instruments or controla needed to supplement installed equipment in order to provide unambiguous indication of inadequate core cooling no later than July 1, 1982.
The proposed change to the Operating License is to change the operability requirement for additional instrumentation for the Reactor Vessel Level Systen.
The proposed amendment is enclosed in Attachment 1.
A discussion of the proposed change is provided in Attachment 2.
The proposed change will require the Reactor Vessel Level System to be operational following startup from the first refueling after January 1, 1983.
The basis for the proposed change is that the system should not be made operable until the NRC has completed the revicw which will demonstrate that the system will not erroneously indicate inadequate core cooling and meet the criteria established by NUREG 0737.
Any required procedure or equipment modifications as a result of the NRC review should be clearly defined by January 1, 1983.
This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control staff.
It has hecu determined that this request does not involve an unreviewed safety quc9 tion as defined in 10 CFR 50.59.
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!!arold R. Denton v NONA ELecraic asu Powrk Coxmv to We have evaluated this request in accordance with the criteria in 10 CFR 170.22.
Since this-request involves a safety issue which the Staff should be able to determine does not pose a significant hazard consideration for Unit 2, a Class III license amendment fee is required for Unit 2.
Accordingly, a voucher check in the amount of $4000.00 is enclosed in payment of the required fees.
Very trily ours, R. H. Leasburg Attachments:
1.
Proposed Operating License Amendment 2.
Discussion of Propor.cd Operating License Amendment 3.
Voucher Check No. 14987 for $4000.00 cc:
Mr.. Tames P. O'Reilly, Regional Administrator Office of Inspection and Enforcement r,egion 11
L C0!910NWEALTH OF VIRGINIA )
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CITY OF RICHMOND
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The foregoing document was acknowledged before me, ir.. and for the City and.___
Commonwealth aforesaid, today by R. H. Leasburg, who is Vice President-Nuclear Operations, of the Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Ccapany, and the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this 8 day of M
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My Commission expires:
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. (i) Containnent pressure from 0 psia to three times the design pressure of the containment no later than the implementation schedule of NUREG-0737; (ii) Containment water level from (1) the bottom to the top of the containment sump, and (2) the bottom of the containment to a level equivalent to 600,000 gallons of water no later than the implementation schedule of NUREG-0737.
(iii) Containment atmosphere hydrogen concentration from i
I 0 to 10 volume percent shall be installed at the first outage of sufficient duration but no later than July 1 1982, and the hydrogen sampling system to be used in the interim shall remain in effect until July 1, 1982.
(iv) Containment radiation up to 10 R/hr. at the first outage of sufficient duration but no later than July 1, 1982, and (v) Noble gas effluent from each potgntial release point from normal concentrations to 10 uCi/cc (Xe-133) shall be implemented at the first outage of sufficient duration but no later than July 1, 1982.
VEPCO shall also provide capability for continuous sampling and for onsite analysis of the radiciodine and particulate effluent samples at the first outage of sufficient duration but no later than July 1, 1982.
(j) Inadequate Core Cooling Instruments (Section 22.3 Item II.F.2)
VEPCO shall have an operationt.1 system which will provide unambiguous, easy to interpret indication of inadequate core cooling-following startup from the first refueling after January 1, 1983.
D.
An exemption from certain requirements of Appendix J to 10 CFR Part 50 is described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report Supplement No. 10.
This exemption is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest. The exemption is, therefore, hereby granted. The granting of the exemption was authorized with the issuance of the License for Fuel-Loading and Low-Pcyer Testing, dated April ll, 1980. The facility will operate, to the extent authorized herein, in conformity with the application, as amended, to provisions of the Act, and the regulations on the Commission.
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DISCUSSION OF PROPOSED OPERATING LICENSE AMENDMENT The proposed change to paragraph 2.C. (21) (j )
extends the operability requirement of the reactor vessel level system until the first refueling following January 1, 1983.
The purpose of this extension is to allow review of the system by the NRC to determine if the requirements of system are met.
These requirements are as follows:
(1) Give advanced warning of the approach of ICC.
(2)
Includes reactor vessel water level indication.
(3) Must provide this indication over the full range from normal operation to uncovering the core.
(4) Must indicate ICC caused by various phenomenon.
(5) Must not erroneously indicate ICC due to unrelated phenomenon.
The proposed change does not increase the possibility of an accident or present an unreviewed safety question since the requested change delays the time at which the system will be made functional until all questions regarding the capability of the system have been answered.
This proposed system is not ESF or Reactor Protection related.
It serves as a monitoring instrument only.
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