ML20073M930

Application for Amend to License NPF-7 Proposing Completion of License Condition 2.C(21)(i)(iv) Re Containment Radiation During Refueling Outage by 831130.Class III Fee Encl

ML20073M930
Person / Time
Site:	North Anna
Issue date:	04/18/1983
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Clark R, Harold Denton Office of Nuclear Reactor Regulation
References
145, NUDOCS 8304220331
Download: ML20073M930 (7)

Text

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e VINGINIA ELECTRIC AND PowEn COMPANY HIcnwoNu, VIRGINIA 20261 W. L. SrawAur Vace PassassamT Ntictuam oramarrone April 18, 1983 Mr. Harold R. Denton, Director Serial No. 145 Office of Nuclear Reactor Regulation N0/JHL: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 NORTH 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.

License Condition 2.C(21)(1)(iv) of the Nprth Anna Unit 2 Operating License states, " Containment radiation up to 10 R/hr. no later than the second refueling outage." The proposed change is to complete License Condition 2.C(21)(1)(iv) by November 30, 1983. The proposed amendment is provided in Attachment 1. A discussion of the proposed change is provided in Attachment 2.

This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been determined that this request does not involve an unreviewed safety question as defined in 10 CFR 50.59.

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 is enclosed in payment of the required fees.

Very truly yours,

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/ { n, y g' t,' Stewart 700 0.00 r304220331 830418 DR ADOCK 0500033 2

vimonwu EtscTaic amp Powra Couraxy T> Harold R. Denton Attachments:

1. Proposed Operating License Amendment

2. Discussion of Proposed Operating License Amendment

3. Voucher Check for $4000 cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. M. B. Shynlock NRC Resident Inspector - North Anna

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0 ATTACHMENT 1 PROPOSED OPERATING LICENSE AMENDMENT I

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(i) Containment 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 co'ncentration from 0 to 10 volume percent shall be installed. no later than January 1, 1983, and the hydrogen sampling system to be used in the interim shall remain in effect until January 1, 1983; (iv) Containment radiation up to 10 R/hr. no later than November 30, 1983.

(v) Noble gas effluent fgom each potential release point from normal concentrations to 10 mci /cc (Xe-133) no later than January 1, 1983.

VEPCO shall also provide capability for continuous sampling and for onsite analysis of the radioiodine and particulate effluent samples no later than January 1, 1983.

(j) Inadequate Core Cooling Instruments (Section 22.3 Item II.F.2)

VEPCO shall install and demonstrate the operability of additional instruments or controls needed to supplement installed equipment in order to provide unambiguous, easy-to-interpret indication of inadequate core cooling at the first outage of sufficient duration but no later than July 1, 1982.

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-Power Testing, dated April 11, 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 of the Commission.

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4 ATTACletENT 2 DISCUSSION OF PROPOSED OPERATING LICENSE AMENDMENT a

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-DISCUSSION OF PROPOSED OPERATING LICENSE AMENDMENT North Anpa 2 License Condition 2.C(21)(1)(iv) states, " Containment radiation up to 10 R/hr. no later than the second refueling outage".

The proposed amendment for North Anna 2 License Condiyion 2.C(21)(1)(iv) would enable completion of containment radiation up to 10 R/hr. (NUREG-0737 Item II.F.1.3; Containment High Range Radiation Monitors) no later than November

30. 1983.

The Containment High Range Radiation Monitoring System has been installed and

-tested. The system is not considered operable since final in-situ calibration can not be performed. The vendor of this system (Victoreen) has developed a prototype calibration source to perform the final in-situ calibration. This prototype calibration . source will be available by the end of March, 1983.

Vepco is in the process of procuring this prototype calibration source so the final in-situ calibration of the Containment High Range Radiation Monitors can be completed during the fall maintenance outage which is currently scheduled to be completed by November 30, 1983.

It should be noted that the Containment High Range Radiation Monitors have been source calibrated at the vendor's facility and electronically calibrated j in accordance with the vendor's procedures.

Until . the final in-situ calibration of the Containment High Range Radiation ,

Monitors can be performed, interim monitoring will be performed using the Containment Area Monitors, Manipulator Crane Area Monitor and the Incore Instrumentation Area Monitor.

4 The possibility of occurrence or the consequences of a malfunction of equipment important to safety and previously evaluated in the FSAR is not 4

increased because of a delay in the in-situ calibration of the Containment High Range Radiation Monitoring System.

The possibility of ' a different type of accident or malfunction than was previously evaluated in the FSAR has not been created by the delay in operability.

The margin of safety as described in the BASIS section of any part of the Technical; Specifications is not reduced because of the delay in the operability of the Containment High Range Radiation. Monitoring System. This delay will in no way affect the safe operation of the plant because this l- system is only used in accident conditions.

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COMMONWEALTH OF VIRGINIA )

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CITY OF RICHMOND )

The foregoing document was acknowledged before me, in and for the City and Connonwealth aforesaid, today by W. L. Stewart, 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 Company, and the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this / day of , 19 PA .

My Commission expires: 2 4 , 19 Pt ,

b Notary

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